Analysis of human factors in incidents reported by Swiss nuclear power plants to the inspectorate

International Nuclear Information System (INIS)

Alder, H.P.; Hausmann, W.

1997-01-01

197 reported incidents in Swiss Nuclear Power Plants were analyzed by a team of the Swiss Federal Nuclear Safety Inspectorate (HSK) using the OECD/NEA Incident Reporting System. The following conclusions could be drawn from this exercise. While the observed cause reported by the plant was ''technical failure'' in about 90% of the incidents, the HSK-Team identified for more than 60% of the incidents ''human factors'' as the root cause. When analyzing this root cause further it was shown that only a smaller contribution came from the side of the operators and the more important shares were caused by plant maintenance, vendors/constructors and plant management with procedural and organizational deficiencies. These findings demonstrate that root cause analysis of incidents by the IRS-Code is a most useful tool to analyze incidents and to find weak points in plant performance. (author). 5 tabs

Study on optimization of normal plant outage work plan for nuclear power plants

International Nuclear Information System (INIS)

Aoki, Takayuki; Kodama, Noriko; Takase, Kentaro; Miya, Kenzo

2011-01-01

This paper discusses maintenance optimization in maintenance implementation stage following maintenance planning stage in nuclear power plants and proposes a methodology to get an optimum maintenance work plan. As a result of consideration, the followings were obtained. (1) The quantitative evaluation methodology for optimizing maintenance work plan in nuclear power plants was developed. (2) Utilizing the above methodology, a simulation analysis of maintenance work planning for BWR's PLR and RHR systems in a normal plant outage was performed. Maintenance cost calculation in several cases was carried out on the condition of smoothening man loading over the plant outage schedule as much as possible. (3) As a result of the simulation, the economical work plans having a flat man loading over the plant outage schedule were obtained. (author)

Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Perkins, W.C.; Durant, W.S.; Dexter, A.H.

1980-12-01

The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents

Planning product quality: An example - ornamental plants

Directory of Open Access Journals (Sweden)

Kovačević Miodrag

2003-01-01

Full Text Available The industry of ornamental plants is a subject of quality planning. The quality plan is a document setting out the specific quality practices in ornamental plants production. That plan introduce organizational structure procedures, processes and resources needed to implement quality in life cycle of product chain. For engineers it represents a new tool.

Evacuation planning for Lilco's Shoreham plant

International Nuclear Information System (INIS)

Zorpette, G.

1987-01-01

This article reports that the Shoreham Nuclear Power Station, an 820-megawatt boiling-water reactor built by the Long Island Lighting Co., has taken 19 years to build and has so far cost nearly $5 billion. Because no emergency plan for coping with a major accident has been approved by the U.S. Nuclear Regulatory Commission, the plant has not been issued a Federal license to operate at full power. The cause of this impasse is the refusal of New York State and Suffolk County to participate in any emergency plan, on the ground that the geography of Long Island would make such a plan impossible to execute. The regulatory commission's rules require the operator of a nuclear plant to enlist cooperation from state and local authorities in an emergency plan. Shoreham's supporters charge that state and county are exploiting that requirement to block operation of the politically unpopular plant

Study on actions for social acceptance of a nuclear power plant incident/accident

International Nuclear Information System (INIS)

Kotani, Fumio; Tsukada, Tetsuya; Hiramoto, Mitsuru; Nishimura, Naoyuki

1998-01-01

When an incident/accident has occurred, dealing technically with it in an appropriate way is essential for social acceptance. One of the most important actions that are expected from the plant representative is to provide, without delay, each of the concerned authorities and organizations with full information concerning the incident/accident, while necessary technical measures are being implemented. While the importance of socially dealing with the incident/accident is widely recognized, up to now there have been no attempts to study previous incidents/accidents cases from the social sciences viewpoint. Therefore, in the present study is a case study of the incident/accident that occurred in 1991 at the No.2 Unit of the Mihama Nuclear Plant of Kansai Power Co., Ltd.. The data used in the present study is based on intensive interview of the staff involved in this incident/accident. The purpose of the study was to shed light on the conditions necessary for maintaining and improving the skill of the plant representative when dealing with social response in case of an incident/accident. The results of the present study has led to a fuller recognition of the importance of the following factors: On the personal level: 1) recognition of personal accountability, 2) complete disclosure of information concerning the incident/accident. On the organizational level: 1) acceptance of different approaches and viewpoints, 2) promoting risk-taking behavior, 3) top management's vision and commitment to providing a social response. (author)

Use of plant specific PSA to evaluate incidents at nuclear power plants

International Nuclear Information System (INIS)

1991-06-01

One of the possible applications of the plant specific probabilistic safety assessment (PSA) is its use in the analysis of operational events at the plant. The methodological development in that area was initiated recently in the framework of the IAEA's Incident Reporting System where determination of the safety significance of the event is essential for optimizing feedback of operating experience. This report provides details of the methodology and procedures to be used in event analysis. The report also contains three case studies which have been performed and summarizes lessons learned from those case studies. The results (event probabilities) obtained using plant specific PSA and the results of the analysis of the same events in the framework of the Accident Sequence Precursor (ASP) programmes (generic models) were compared and commented on. 6 refs, figs and tabs

Application of Real-Time Automated Traffic Incident Response Plan Management System: A Web Structure for the Regional Highway Network in China

Directory of Open Access Journals (Sweden)

Yongfeng Ma

2014-01-01

Full Text Available Traffic incidents, caused by various factors, may lead to heavy traffic delay and be harmful to traffic capacity of downstream sections. Traffic incident management (TIM systems have been developed widely to respond to traffic incidents intelligently and reduce the losses. Traffic incident response plans, as an important component of TIM, can effectively guide responders as to what and how to do in traffic incidents. In the paper, a real-time automated traffic incident response plan management system was developed, which could generate and manage traffic incident response plans timely and automatically. A web application structure and a physical structure were designed to implement and show these functions. A standard framework of data storage was also developed to save information about traffic incidents and generated response plans. Furthermore, a conformation survey and case-based reasoning (CBR were introduced to identify traffic incident and generate traffic incident response plans automatically, respectively. Twenty-three traffic crash-related incidents were selected and three indicators were used to measure the system performance. Results showed that 20 of 23 cases could be retrieved effectively and accurately. The system is practicable to generate traffic incident response plans and has been implemented in China.

Hanford Waste Vitrification Plant applied technology plan

International Nuclear Information System (INIS)

Kruger, O.L.

1990-09-01

This Applied Technology Plan describes the process development, verification testing, equipment adaptation, and waste form qualification technical issues and plans for resolution to support the design, permitting, and operation of the Hanford Waste Vitrification Plant. The scope of this Plan includes work to be performed by the research and development contractor, Pacific Northwest Laboratory, other organizations within Westinghouse Hanford Company, universities and companies with glass technology expertise, and other US Department of Energy sites. All work described in this Plan is funded by the Hanford Waste Vitrification Plant Project and the relationship of this Plan to other waste management documents and issues is provided for background information. Work to performed under this Plan is divided into major areas that establish a reference process, develop an acceptable glass composition envelope, and demonstrate feed processing and glass production for the range of Hanford Waste Vitrification Plant feeds. Included in this work is the evaluation and verification testing of equipment and technology obtained from the Defense Waste Processing Facility, the West Valley Demonstration Project, foreign countries, and the Hanford Site. Development and verification of product and process models and other data needed for waste form qualification documentation are also included in this Plan. 21 refs., 4 figs., 33 tabs

Danish emergency plan for Barsebaeck Power Plant

International Nuclear Information System (INIS)

1981-01-01

A revised edition of the Danish emergency plan for the Swedish Power Plant Barsebaeck (about 20 km from the Danish Territory) is prepared at the request of Environmental Council in cooperation with police management and civil defense organisations. The plan is valid from October 1981. The emergency plan defines the emergency organization and the provisions to be taken quickly to protect the population if it is exposed to ionizing radiation from release of radioactive effluents as a result of an accident in the Barsebaeck power plant. The emergency plan is based upon Regulation no. 278, June 27, 1963 and Regulation no. 502, October 1, 1974. (EG)

Computer simulation of nuclear pollutant diffusion from Shimane nuclear power plants and development of an evacuation strategy in the event of a nuclear incident

International Nuclear Information System (INIS)

Yakura, Haruna; Kurimasa, Akihiro

2012-01-01

Beginning from Tohoku (northeastern) Earthquake on March 11, an accident at the Fukushima Dai-ichi Nuclear Power Plant resulted in a substantial release of radioactivity to the environment. The accident forced a large number of residents to evacuate from surrounding areas. Moreover, the nuclear incident was life-threatening for the elderly and for people with serious illnesses who were confined in hospital or nursing homes. Strikingly, the causes of death were not directly attributed to radiation exposure but to problems encountered during evacuation. Using nuclear diffusion data from the Fukushima incident, we simulated nuclear pollutant dispersion using computer software A2C in an area of Tottori and Shimane Prefectures surrounding the Shimane Nuclear Power Plant. We generated a model for the spread of nuclear pollutants around the Emergency Planning Zone, id est (i.e.) EPZ. From these findings, we proposed evacuation strategies for residents near the power plant to ensure a safe and reliable escape from nuclear pollutants. Our recommendations include: immediate evacuation from PAZ area (within 5 km), securing indoor shelter in the area of the UPZ (from 5 km to 30 km) and preparations to evacuate further outwards from the nuclear plant site, daytime evacuation within a 30 km area after considering wind direction and velocity, and preparation of a planned evacuation strategy that identifies secure facilities for weaker people in the event of a disaster. (author)

Particular intervention plan of the Civaux Nuclear Power Plant. Public version. Special provision of the organisation plan for civil protection response

International Nuclear Information System (INIS)

2016-04-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Civaux nuclear power plant (Vienne, France)

AVLIS production plant waste management plan

International Nuclear Information System (INIS)

1984-01-01

Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables

Pinellas Plant FY1990 site specific implementation plan

International Nuclear Information System (INIS)

Klein, R.D.

1990-02-01

This Site Specific Implementation Plan describes the Corrective Action, Environmental Restoration, and Waste Management activities to be performed at the Pinellas Plant in FY1990 (October 1, 1989 to September 30, 1989). These FY1990 activities are described in the Pinellas Plant FY1991--95 Five-Year Plan. The information used to prepare this plan reflects the best estimate of the project scope, schedules, regulatory, and funding requirements at the time of plan preparation. The Environmental Restoration/Waste Management Five-Year Plan is a dynamic document and will be modified each year; the Site Specific Implementation Plan will, in turn, be modified each year to reflect new findings, information, and knowledge of the various projects. 4 figs., 11 tabs

Legal consequences of the special development plan 'power plant sites' on regional planning and on guidelines for building plans

International Nuclear Information System (INIS)

1978-01-01

The Special Development Plan 'Power plant sites' was made compulsory by the regulation given by the Land government in Juli 1976. For extending the energy supply system this Special Development Plan intends to provide a sufficient amount of power plant sites suitably located with regard to present and future consumption centres and permitting a cooling by means of river water while safeguarding the interests of water resources policy. The Special Development Plan established in accordance with the articles 25 and 27 of the planning law of the Land lays down that 14 specified areas are to be kept free from utilization purposes which could be opposed to the realization of power plant projects. Thus the securing of these (potential) sites has become an objective of area planning and planning of the Land in the sense of article 5 paragraph 4 of the Federal law on area planning. (orig./HP) [de

A management plan for hospitals and medical centers facing radiation incidents.

Science.gov (United States)

Davari, Fereshteh; Zahed, Arash

2015-09-01

Nowadays, application of nuclear technology in different industries has largely expanded worldwide. Proportionately, the risk of nuclear incidents and the resulting injuries have, therefore, increased in recent years. Preparedness is an important part of the crisis management cycle; therefore efficient preplanning seems crucial to any crisis management plan. Equipped with facilities and experienced personnel, hospitals naturally engage with the response to disasters. The main purpose of our study was to present a practical management pattern for hospitals and medical centers in case they encounter a nuclear emergency. In this descriptive qualitative study, data were collected through experimental observations, sources like Safety manuals released by the International Atomic Energy Agency and interviews with experts to gather their ideas along with Delphi method for polling, and brainstorming. In addition, the 45 experts were interviewed on three targeted using brainstorming and Delphi method. We finally proposed a management plan along with a set of practicality standards for hospitals and medical centers to optimally respond to nuclear medical emergencies when a radiation incident happens nearby. With respect to the great importance of preparedness against nuclear incidents adoption and regular practice of nuclear crisis management codes for hospitals and medical centers seems quite necessary.

Waste Isolation Pilot Plant, Land Management Plan

International Nuclear Information System (INIS)

1993-01-01

To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives

Waste Isolation Pilot Plant, Land Management Plan

Energy Technology Data Exchange (ETDEWEB)

1993-12-01

To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives.

Production Planning and Planting Pattern Scheduling Information System for Horticulture

Science.gov (United States)

Vitadiar, Tanhella Zein; Farikhin; Surarso, Bayu

2018-02-01

This paper present the production of planning and planting pattern scheduling faced by horticulture farmer using two methods. Fuzzy time series method use to predict demand on based on sales amount, while linear programming is used to assist horticulture farmers in making production planning decisions and determining the schedule of cropping patterns in accordance with demand predictions of the fuzzy time series method, variable use in this paper is size of areas, production advantage, amount of seeds and age of the plants. This research result production planning and planting patterns scheduling information system with the output is recommendations planting schedule, harvest schedule and the number of seeds will be plant.

Development of a decommissioning plan for nuclear power plant 'Krsko'

International Nuclear Information System (INIS)

Tankosic, Djurica; Fink, Kresimir

1991-01-01

Nuclear Power Plant 'Krsko' (NEK), is the only nuclear power plant in Yugoslavia, is a two-loop, Westinghouse-design, pressurized water reactor rated at 632 MWe. When NEK applied for an operating license in 1981, it did not have to explain how the plant would be decommissioned and decommissioning provisions were not part of the licensing process. Faced with mounting opposition to nuclear power and a real threat that the plant would be shut down, the plant management developed a Mission Plan for resolving the decommissioning problem. The Mission Plan calls for a preliminary decommissioning plan to be prepared and submitted to the local regulatory body before the end of 1992

Making the connection: advancing traffic incident management in transportation planning : a primer.

Science.gov (United States)

2013-07-01

"The intent of this primer is to inform and guide traffic incident management (TIM) professionals and transportation planners to initiate and develop collaborative relationships and advance TIM programs through the metropolitan planning process. The ...

Field assessment of a model tuberculosis outbreak response plan for low-incidence areas

Directory of Open Access Journals (Sweden)

Pascopella Lisa

2007-10-01

Full Text Available Abstract Background For a regional project in four low-incidence states, we designed a customizable tuberculosis outbreak response plan. Prior to dissemination of the plan, a tuberculosis outbreak occurred, presenting an opportunity to perform a field assessment of the plan. The purpose of the assessment was to ensure that the plan included essential elements to help public health professionals recognize and respond to outbreaks. Methods We designed a semi-structured questionnaire and interviewed all key stakeholders involved in the response. We used common themes to assess validity of and identify gaps in the plan. A subset of participants provided structured feedback on the plan. Results We interviewed 11 public health and six community stakeholders. The assessment demonstrated that (1 almost all of the main response activities were reflected in the plan; (2 the plan added value by providing a definition of a tuberculosis outbreak and guidelines for communication and evaluation. These were areas that lacked written protocols during the actual outbreak response; and (3 basic education about tuberculosis and the interpretation and use of genotyping data were important needs. Stakeholders also suggested adding to the plan questions for evaluation and a section for specific steps to take when an outbreak is suspected. Conclusion An interactive field assessment of a programmatic tool revealed the value of a systematic outbreak response plan with a standard definition of a tuberculosis outbreak, guidelines for communication and evaluation, and response steps. The assessment highlighted the importance of education and training for tuberculosis in low-incidence areas.

A management plan for hospitals and medical centers facing radiation incidents

Directory of Open Access Journals (Sweden)

Fereshteh Davari

2015-01-01

Full Text Available Background: Nowadays, application of nuclear technology in different industries has largely expanded worldwide. Proportionately, the risk of nuclear incidents and the resulting injuries have, therefore, increased in recent years. Preparedness is an important part of the crisis management cycle; therefore efficient preplanning seems crucial to any crisis management plan. Equipped with facilities and experienced personnel, hospitals naturally engage with the response to disasters. The main purpose of our study was to present a practical management pattern for hospitals and medical centers in case they encounter a nuclear emergency. Materials and Methods: In this descriptive qualitative study, data were collected through experimental observations, sources like Safety manuals released by the International Atomic Energy Agency and interviews with experts to gather their ideas along with Delphi method for polling, and brainstorming. In addition, the 45 experts were interviewed on three targeted using brainstorming and Delphi method. Results: We finally proposed a management plan along with a set of practicality standards for hospitals and medical centers to optimally respond to nuclear medical emergencies when a radiation incident happens nearby. Conclusion: With respect to the great importance of preparedness against nuclear incidents adoption and regular practice of nuclear crisis management codes for hospitals and medical centers seems quite necessary.

Support system development for evacuation plan decision in nuclear plant disaster

International Nuclear Information System (INIS)

Fujita, Masahiko; Takayama, Jun-ichi; Nakayama, Sho-ichiro; Ushiba, Takashi

2011-01-01

These days, our interest in nuclear plant accidents has increased, and civic actions for them have also been activated. Therefore, improvement of the disaster prevention planning to nuclear plant accidents is requested. In this study, we developed a microscopic traffic simulation system for evacuation plan near the nuclear plant as a system which supports to examine the disaster prevention planning, and applied the system to Kashiwazaki-Kariwa nuclear plant area. Furthermore, the risk of each region near the nuclear plant disaster from the viewpoint of wind direction and the population was considered, the importance of each evacuation simulation was examined. As a result, we found that the present plan Kashiwazaki-Kariwa made has the problem on evacuation routes and others. (author)

Maintenance Implementation Plan for B Plant

International Nuclear Information System (INIS)

Tritt, S.E.

1993-04-01

The objective of the Maintenance Implementation Plan (MIP) is to describe how the B Plant will implement the requirements established by US Department of Energy (DOE) Order 4330.4A, Maintenance Management Program, Chapter II, ''Nuclear Facilities'' (DOE 1990). The plan provides a blueprint for a disciplined approach to implementation and compliance. Each element of the order is prioritized, categorized, and then placed into one of three phases for implementation

Survey of reportable incidents in nuclear power plants of the Federal Republic of Germany in the year 1991

International Nuclear Information System (INIS)

1992-01-01

In 1991, there were 249 reportable nuclear power plant incidents in Germany (old and new federal Laender). The report comprehensively lists all these incidents. There was no release of radioactivity exceeding the maximum permissible limits, and there were no effects on man or the environment. There were no incidents of reporting category S (Urgent notification), and ten belonging to category E (immediate notification). The six incidents reported in the first half of 1991 from nuclear power plants in the new federal Laender all belonged to category AE 3, which is the lowest. (orig./DG) [de

Trend evaluation of incident and failure data from japanese nuclear power plants

International Nuclear Information System (INIS)

Kondo, S.; Hada, M.; Mikami, Y.

1990-01-01

Major incident and failure at nuclear power plants in Japan have to be reported to the regulatory agency i.e. Ministry of International Trade and Industry (MITI). Nuclear Power Safety Information Research Center (NUSIRC) has established a system for the collection, classification and analysis of this report under the contract to MITI. In this paper, the authors give several results of trend analyses of the incidents related to electric and instrumentation and control (I and C) systems reported, especially, the trend of the contribution of troubles in I and C system to the operation states, analysis of dominant contributors to the failure of I and C systems. Also, the relations of failure frequency of these systems with the plant age and effect of periodic inspections of it are discussed in some detail

Maintenance planning for nuclear power plants

International Nuclear Information System (INIS)

Mattu, R.K.; Cooper, S.E.; Lauderdale, J.R.

2004-01-01

Maintenance planning for nuclear power plants is similar to that in other industrial plants but it is heavily influenced by regulatory rules, with consequent costs of compliance. Steps by the nuclear industry and the Nuclear Regulatory Commission to address that problem include development of guidelines for maintenance of risk-critical equipment, using PRA-based techniques to select a set of equipment that requires maintenance and reliability-centered maintenance (RCM) approaches for determining what maintenance is required. The result of the process is a program designed to ensure effective maintenance of the equipment most critical to plant safety. (author)

Web tools concerning performance analysis and planning support for solar energy plants starting from remotely sensed optical images

International Nuclear Information System (INIS)

Morelli, Marco; Masini, Andrea; Ruffini, Fabrizio; Potenza, Marco Alberto Carlo

2015-01-01

We present innovative web tools, developed also in the frame of the FP7 ENDORSE (ENergy DOwnstReam SErvices) project, for the performance analysis and the support in planning of solar energy plants (PV, CSP, CPV). These services are based on the combination between the detailed physical model of each part of the plants and the near real-time satellite remote sensing of incident solar irradiance. Starting from the solar Global Horizontal Irradiance (GHI) data provided by the Monitoring Atmospheric Composition and Climate (GMES-MACC) Core Service and based on the elaboration of Meteosat Second Generation (MSG) satellite optical imagery, the Global Tilted Irradiance (GTI) or the Beam Normal Irradiance (BNI) incident on plant's solar PV panels (or solar receivers for CSP or CPV) is calculated. Combining these parameters with the model of the solar power plant, using also air temperature values, we can assess in near-real-time the daily evolution of the alternate current (AC) power produced by the plant. We are therefore able to compare this satellite-based AC power yield with the actually measured one and, consequently, to readily detect any possible malfunctions and to evaluate the performances of the plant (so-called “Controller” service). Besides, the same method can be applied to satellite-based averaged environmental data (solar irradiance and air temperature) in order to provide a Return on Investment analysis in support to the planning of new solar energy plants (so-called “Planner” service). This method has been successfully applied to three test solar plants (in North, Centre and South Italy respectively) and it has been validated by comparing satellite-based and in-situ measured hourly AC power data for several months in 2013 and 2014. The results show a good accuracy: the overall Normalized Bias (NB) is − 0.41%, the overall Normalized Mean Absolute Error (NMAE) is 4.90%, the Normalized Root Mean Square Error (NRMSE) is 7.66% and the overall

Web tools concerning performance analysis and planning support for solar energy plants starting from remotely sensed optical images

Energy Technology Data Exchange (ETDEWEB)

Morelli, Marco, E-mail: marco.morelli1@unimi.it [Department of Physics, University of Milano, Via Celoria 16, 20133 Milano (Italy); Masini, Andrea, E-mail: andrea.masini@flyby.it [Flyby S.r.l., Via Puini 97, 57128 Livorno (Italy); Ruffini, Fabrizio, E-mail: fabrizio.ruffini@i-em.eu [i-EM S.r.l., Via Lampredi 45, 57121 Livorno (Italy); Potenza, Marco Alberto Carlo, E-mail: marco.potenza@unimi.it [Department of Physics, University of Milano, Via Celoria 16, 20133 Milano (Italy)

2015-04-15

We present innovative web tools, developed also in the frame of the FP7 ENDORSE (ENergy DOwnstReam SErvices) project, for the performance analysis and the support in planning of solar energy plants (PV, CSP, CPV). These services are based on the combination between the detailed physical model of each part of the plants and the near real-time satellite remote sensing of incident solar irradiance. Starting from the solar Global Horizontal Irradiance (GHI) data provided by the Monitoring Atmospheric Composition and Climate (GMES-MACC) Core Service and based on the elaboration of Meteosat Second Generation (MSG) satellite optical imagery, the Global Tilted Irradiance (GTI) or the Beam Normal Irradiance (BNI) incident on plant's solar PV panels (or solar receivers for CSP or CPV) is calculated. Combining these parameters with the model of the solar power plant, using also air temperature values, we can assess in near-real-time the daily evolution of the alternate current (AC) power produced by the plant. We are therefore able to compare this satellite-based AC power yield with the actually measured one and, consequently, to readily detect any possible malfunctions and to evaluate the performances of the plant (so-called “Controller” service). Besides, the same method can be applied to satellite-based averaged environmental data (solar irradiance and air temperature) in order to provide a Return on Investment analysis in support to the planning of new solar energy plants (so-called “Planner” service). This method has been successfully applied to three test solar plants (in North, Centre and South Italy respectively) and it has been validated by comparing satellite-based and in-situ measured hourly AC power data for several months in 2013 and 2014. The results show a good accuracy: the overall Normalized Bias (NB) is − 0.41%, the overall Normalized Mean Absolute Error (NMAE) is 4.90%, the Normalized Root Mean Square Error (NRMSE) is 7.66% and the overall

Maintenance implementation plan for the B Plant/WESF. Revision 4

International Nuclear Information System (INIS)

Tritt, S.E.; Lueck, B.H.

1996-01-01

This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the B Plant/WESF (Waste Encapsulation Storage Facility) complex. The objective of this plan is to provide baseline information for establishing and identifying WHC conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at B Plant/WESF. The B Plant WESF facility complex consists of three main facilities and several support structures located in the 200 East Area of the Hanford site. B Plant is a transition facility that is required to ensure safe storage and management of WESF (operating facility) cesium and strontium capsules. B Plant/WESF also contains substantial radiological inventory from previous campaigns. There are no production activities at B Plant, but several of its operating systems are required to accomplish the current B Plant/WESF mission. B Plant/WESF are each considered a nuclear facility due to the storage of cesium and strontium capsules at WESF and the large radiological inventory from past processing

Incident Wave Climate at the OWC Pico Plant

DEFF Research Database (Denmark)

Le Crom, I.; Cabrera Bermejo, H.; Pecher, Arthur

2011-01-01

The aim of the study is to retrieve the incident wave information that coincides with former Pico plant operation periods. The recent implementation of a directional pressure sensor for wave measurement as well as the recovery of the data gathered by a directional wave rider buoy allowed embarkin...... on the validation of two different models by using both wave measurements: a model for wave propagation (SWAN) and an Artificial Neural Network (ANN). This paper, as a first step of a comprehensive study, leads to several recommendations to improve both methodologies in future works....

Maintenance implementation plan for T Plant. Revision 2

International Nuclear Information System (INIS)

Ayers, W.S.

1995-05-01

This document is a Maintenance Implementation Plan (MIP) for the T Plant Facility complex located in the 200 West Area of the Hanford Reservation in Washington state. This plan has been developed to provide a disciplined approach to maintenance functions and to describe how the T Plant facility will implement and comply with the regulations according to US DOE order 4330.4B, entitled Maintenance Management Program, Chapter 2.0 open-quotes Nuclear Facilitiesclose quotes. Physical structures, systems, processes, as well as all associated equipment specifically assigned to these groups are included in the MIP

Risk perception, trust, and factors related to a planned new nuclear power plant in Taiwan after the 2011 Fukushima disaster

International Nuclear Information System (INIS)

Ho, Jung-Chun; Su, Chien-Tien; Chen, Ruey-yu; Chang, Hung-Lun; Ieong, Marco C F; Chang, Peter Wushou; Kao, Shu-Fen; Wang, Jung-Der; Lee, Chiao-Tzu Patricia

2013-01-01

After the Fukushima nuclear disaster in March 2011, an international review of nuclear safety indicated that two of the three nuclear power plants (NPPs) operating in Taiwan were listed as the most dangerous in the world. To understand the perception of NPP risks by the public in Taiwan and their attitudes regarding a planned fourth NPP after the Fukushima nuclear incident in 2011, a study was conducted in August 2011. A sample of 2819 individuals responded to the survey, with 66% perceiving that Taiwan’s safety management of NPPs was inferior to Japan’s, while 40% perceived a higher possibility of nuclear accidents like that in Japan. On average, a ‘safe’ distance of 94 km from an NPP was expected. 56% opposed the planned fourth NPP, with females (adjusted odd ratios (aOR) 2.03; 95% confidence interval (CI) 1.71–2.41), residence near the planned fourth NPP (aOR/CI 13.90/7.79–24.80), distrust of safety management (aOR/CI 1.98/1.45–2.69) and emergency planning (aOR/CI 1.89/1.49–2.40) as the main determinants. Others included those who expected larger safe distances from an NPP (trend test, p < 0.001), perceived excess cancer risks of living within 30 km of an NPP (aOR/CI 2.74/2.02–3.71), and projection of no electric shortage without NPPs (aOR/CI 1.93/1.50–2.49). Given that Taiwan’s large population lives close to the existing NPPs and long-term concerns about the safety of these nuclear plants, the Fukushima incident in Japan likely augmented public risk perceptions on nuclear power in general and on the planned fourth NPP. (paper)

Quality planning for major plant design modifications

International Nuclear Information System (INIS)

Dulee, R.J.

1988-01-01

This paper reviews the approach and activities undertaken by Public Service Electric and Gas Company's (PSE and G's) nuclear quality assurance (QA) department to support major plant design modifications conducted during refueling outages at Salem Generating Station. It includes the planning and implementation of quality plans developed to provide both QA and quality control (QC) coverage of modification performed by contracted service organizations

Nuclear power plant Severe Accident Research Plan

International Nuclear Information System (INIS)

Larkins, J.T.; Cunningham, M.A.

1983-01-01

The Severe Accident Research Plan (SARP) will provide technical information necessary to support regulatory decisions in the severe accident area for existing or planned nuclear power plants, and covers research for the time period of January 1982 through January 1986. SARP will develop generic bases to determine how safe the plants are and where and how their level of safety ought to be improved. The analysis to address these issues will be performed using improved probabilistic risk assessment methodology, as benchmarked to more exact data and analysis. There are thirteen program elements in the plan and the work is phased in two parts, with the first phase being completed in early 1984, at which time an assessment will be made whether or not any major changes will be recommended to the Commission for operating plants to handle severe accidents. Additionally at this time, all of the thirteen program elements in Chapter 5 will be reviewed and assessed in terms of how much additional work is necessary and where major impacts in probabilistic risk assessment might be achieved. Confirmatory research will be carried out in phase II to provide additional assurance on the appropriateness of phase I decisions. Most of this work will be concluded by early 1986

Discussion of in-service inspection planning for nuclear power plants

International Nuclear Information System (INIS)

Aoki, Takayuki; Takagi, Toshiyuki

2012-01-01

For creating an inspection plan for industrial plants like nuclear power plants, it is necessary to have a well-grounded basis. Therefore, this paper proposes a method for determining the following three elements of such a plan: the equipment to be inspected, the inspection method to be adopted, and the timing of its implementation using a scientific approach. The key idea is to analyze the components of the plan by employing the understanding of cancer detection and diagnosis in medical science and also to take an approach of creating a plan based on the characteristic features of the component and its aging degradation mode, the performance of the inspection method, and the relationship between the two. Taking all the above into account, the factors to be considered and the best way for inspecting the plants are presented in this paper. (author)

A preliminary analysis of incident investigation reports of an integrated steel plant: some reflection.

Science.gov (United States)

Verma, A; Maiti, J; Gaikwad, V N

2018-06-01

Large integrated steel plants employ an effective safety management system and gather a significant amount of safety-related data. This research intends to explore and visualize the rich database to find out the key factors responsible for the occurrences of incidents. The study was carried out on the data in the form of investigation reports collected from a steel plant in India. The data were processed and analysed using some of the quality management tools like Pareto chart, control chart, Ishikawa diagram, etc. Analyses showed that causes of incidents differ depending on the activities performed in a department. For example, fire/explosion and process-related incidents are more common in the departments associated with coke-making and blast furnace. Similar kind of factors were obtained, and recommendations were provided for their mitigation. Finally, the limitations of the study were discussed, and the scope of the research works was identified.

Childhood leukaemia incidence below the age of 5 years near French nuclear power plants

International Nuclear Information System (INIS)

Laurier, D; Hemon, D; Clavel, J

2008-01-01

A recent study indicated an excess risk of leukaemia among children under the age of 5 years living in the vicinity of nuclear power plants in Germany. We present results relating to the incidence of childhood leukaemia in the vicinity of nuclear power plants in France for the same age range. These results do not indicate an excess risk of leukaemia in young children living near French nuclear power plants. (note)

Effect of γ-radiation on the incidence of plant tumors (to the problem of carcinogenesis)

International Nuclear Information System (INIS)

Kuzin, A.M.; Yurov, S.S.; Vagabova, M.Eh.; Shchelkaeva, N.V.

1986-01-01

In experiments on two plant species: of Kalanchoe diagremontiana and potato (Solanum tuberosum) it was shown that γ-irradiation of the plant tissues, before infecting with Ti-plasmide Agrobacterium tumefaciens C-58, with doses stimulating the development of the plants markedly increases the incidence of tumors, promotes their growth, and increases the probability of inverse differentiation of tumor cells

Incidents at nuclear power plants caused by the human factor

International Nuclear Information System (INIS)

Mashin, V. A.

2012-01-01

Psychological analysis of the causes of incorrect actions by personnel is discussed as presented in the report “Methodological guidelines for analyzing the causes of incidents in the operation of nuclear power plants.” The types of incorrect actions and classification of the root causes of errors by personnel are analyzed. Recommendations are made for improvements in the psychological analysis of causes of incorrect actions by personnel.

Cancer incidence in northern Sweden before and after the Chernobyl nuclear power plant accident.

Science.gov (United States)

Alinaghizadeh, Hassan; Tondel, Martin; Walinder, Robert

2014-08-01

Sweden received about 5 % of the total release of (137)Cs from the Chernobyl nuclear power plant accident in 1986. The distribution of the fallout mainly affected northern Sweden, where some parts of the population could have received an estimated annual effective dose of 1-2 mSv per year. It is disputed whether an increased incidence of cancer can be detected in epidemiological studies after the Chernobyl nuclear power plant accident outside the former Union of Soviet Socialist Republics. In the present paper, a possible exposure-response pattern between deposition of (137)Cs and cancer incidence after the Chernobyl nuclear power plant accident was investigated in the nine northernmost counties of Sweden (2.2 million inhabitants in 1986). The activity of (137)Cs from the fallout maps at 1986 was used as a proxy for the received dose of ionizing radiation. Diagnoses of cancer (ICD-7 code 140-209) from 1980 to 2009 were received from the Swedish Cancer Registry (273,222 cases). Age-adjusted incidence rate ratios, stratified by gender, were calculated with Poisson regression in two closed cohorts of the population in the nine counties 1980 and 1986, respectively. The follow-up periods were 1980-1985 and 1986-2009, respectively. The average surface-weighted deposition of (137)Cs at three geographical levels; county (n = 9), municipality (n = 95) and parish level (n = 612) was applied for the two cohorts to study the pre- and the post-Chernobyl periods separately. To analyze time trends, the age-standardized total cancer incidence was calculated for the general Swedish population and the population in the nine counties. Joinpoint regression was used to compare the average annual percent change in the general population and the study population within each gender. No obvious exposure-response pattern was seen in the age-adjusted total cancer incidence rate ratios. A spurious association between fallout and cancer incidence was present, where areas with the

Cancer incidence in northern Sweden before and after the Chernobyl nuclear power plant accident

International Nuclear Information System (INIS)

Alinaghizadeh, Hassan; Tondel, Martin; Walinder, Robert

2014-01-01

Sweden received about 5 % of the total release of "1"3"7Cs from the Chernobyl nuclear power plant accident in 1986. The distribution of the fallout mainly affected northern Sweden, where some parts of the population could have received an estimated annual effective dose of 1-2 mSv per year. It is disputed whether an increased incidence of cancer can be detected in epidemiological studies after the Chernobyl nuclear power plant accident outside the former Union of Soviet Socialist Republics. In the present paper, a possible exposure-response pattern between deposition of "1"3"7Cs and cancer incidence after the Chernobyl nuclear power plant accident was investigated in the nine northernmost counties of Sweden (2.2 million inhabitants in 1986). The activity of "1"3"7Cs from the fallout maps at 1986 was used as a proxy for the received dose of ionizing radiation. Diagnoses of cancer (ICD-7 code 140-209) from 1980 to 2009 were received from the Swedish Cancer Registry (273,222 cases). Age-adjusted incidence rate ratios, stratified by gender, were calculated with Poisson regression in two closed cohorts of the population in the nine counties 1980 and 1986, respectively. The follow-up periods were 1980-1985 and 1986-2009, respectively. The average surface-weighted deposition of "1"3"7Cs at three geographical levels; county (n = 9), municipality (n = 95) and parish level (n = 612) was applied for the two cohorts to study the pre- and the post-Chernobyl periods separately. To analyze time trends, the age-standardized total cancer incidence was calculated for the general Swedish population and the population in the nine counties. Joinpoint regression was used to compare the average annual percent change in the general population and the study population within each gender. No obvious exposure-response pattern was seen in the age-adjusted total cancer incidence rate ratios. A spurious association between fallout and cancer incidence was present, where areas with the lowest

Cancer incidence in northern Sweden before and after the Chernobyl nuclear power plant accident

Energy Technology Data Exchange (ETDEWEB)

Alinaghizadeh, Hassan; Tondel, Martin; Walinder, Robert [Uppsala University, Occupational and Environmental Medicine, Department of Medical Sciences, Uppsala (Sweden)

2014-08-15

Sweden received about 5 % of the total release of {sup 137}Cs from the Chernobyl nuclear power plant accident in 1986. The distribution of the fallout mainly affected northern Sweden, where some parts of the population could have received an estimated annual effective dose of 1-2 mSv per year. It is disputed whether an increased incidence of cancer can be detected in epidemiological studies after the Chernobyl nuclear power plant accident outside the former Union of Soviet Socialist Republics. In the present paper, a possible exposure-response pattern between deposition of {sup 137}Cs and cancer incidence after the Chernobyl nuclear power plant accident was investigated in the nine northernmost counties of Sweden (2.2 million inhabitants in 1986). The activity of {sup 137}Cs from the fallout maps at 1986 was used as a proxy for the received dose of ionizing radiation. Diagnoses of cancer (ICD-7 code 140-209) from 1980 to 2009 were received from the Swedish Cancer Registry (273,222 cases). Age-adjusted incidence rate ratios, stratified by gender, were calculated with Poisson regression in two closed cohorts of the population in the nine counties 1980 and 1986, respectively. The follow-up periods were 1980-1985 and 1986-2009, respectively. The average surface-weighted deposition of {sup 137}Cs at three geographical levels; county (n = 9), municipality (n = 95) and parish level (n = 612) was applied for the two cohorts to study the pre- and the post-Chernobyl periods separately. To analyze time trends, the age-standardized total cancer incidence was calculated for the general Swedish population and the population in the nine counties. Joinpoint regression was used to compare the average annual percent change in the general population and the study population within each gender. No obvious exposure-response pattern was seen in the age-adjusted total cancer incidence rate ratios. A spurious association between fallout and cancer incidence was present, where areas with

Planning and evaluation of plant under safety aspects

International Nuclear Information System (INIS)

Strnad, H.

1985-01-01

Plant denotes a technical product characterized as being structured, complex, comprising the use of energy, and that of measuring, automatic control and monitoring systems to keep track of present, control and monitor processes. Particular attention is paid to methods of developing plant concepts, measures to exclude or detect risks, integration of safety engineering into the course of planning, safety concept and ergonomics in plant design. (DG) [de

Hanford Waste Vitrification Plant Technology Plan

International Nuclear Information System (INIS)

Sexton, R.A.

1988-06-01

The reference Hanford plan for disposal of defense high-level waste is based on waste immobilization in glass by the vitrification process and temporary vitrified waste storage at the Hanford Site until final disposal in a geologic repository. A companion document to the Hanford Waste Management Plan (HWMP) is the Draft, Interim Hanford Waste Management Technology Plan (HWMTP), which provides a description of the technology that must be developed to meet the reference waste management plan. One of the issues in the HWMTP is DST-6, Immobilization (Glass). The HWMTP includes all expense funding needed to complete the Hanford Waste Vitrification Plant (HWVP) project. A preliminary HWVP Technology Plan was prepared in 1985 as a supporting document to the HWMTP to provide a more detailed description of the technology needed to construct and operate a vitrification facility. The plan was updated and issued in 1986, and revised in 1987. This document is an annual update of the plan. The HWVP Technology Plan is limited in scope to technology that requires development or confirmation testing. Other expense-funded activities are not included. The relationship between the HWVP Technology Plan and other waste management issues addressed in the HWMTP is described in section 1.6 of this plan. 6 refs., 4 figs., 34 tabs

Master plan: Guntersville Reservoir Aquatic Plant Management. Executive summary

Energy Technology Data Exchange (ETDEWEB)

1992-12-31

In 1989, Congress provided funding to start a five-year comprehensive project to manage aquatic plants in Guntersville Reservoir, to be jointly implemented by the US Army Corps of Engineers (Corps) and Tennessee Valley Authority (TVA). TVA serves as the overall project coordinator and is the lead agency for this project. Known as the Joint Agency Guntersville Project (JAGP), the project will test and demonstrate innovative management technologies, and incorporate the most effective technologies into a comprehensive aquatic plant management plan for Guntersville Reservoir. The JAGP is intended to serve as a National Demonstration Project for aquatic plant management. As part of this JAGP, the Master Plan for Aquatic Plant Management for the Guntersville Reservoir Project, Alabama-Tennessee is authorized by Corps Contract Number DACW62-90-C-0067.

Contents of management plans for incidents and accidents involving the transport of radioactive substances. Guide no. 17, Version of 22/12/2014

International Nuclear Information System (INIS)

2014-01-01

This guide presents the essential topics to be developed in a management plan for incidents and accidents involving the transport of radioactive substances for civil use. It does not aim to be exhaustive and could be added to by each party involved in the transport, who can make the necessary adaptations and additions, taking account of the particularities of its shipments and its organisation, as well as those of the company or group to which it belongs. The radioactive substances transport incident and accident management plan is a document comprising a descriptive part and an operational part. It presents the overall response of the party involved in the transport operation to an incident or accident situation concerning one of its shipments and the steps it intends to make in order to support the authorities in charge of this situation, in the best possible conditions. This response is designed to cover the cases of incidents or accidents whether or not they lead to a radiological emergency situation. The guide exclusively concerns: - road transport; - rail transport; - the 'road' and 'rail' parts of multimodal transport operations. The case of an incident or an accident occurring during a particular stop such as a transit site, in a transhipment area (port, airport, railway station, etc.), or in a transport infrastructure, is also covered by the radioactive substances transport incident and accident management plan, which then supports the entities in charge of managing this situation (operator of the transhipment area or the transport infrastructure and - as applicable - their supervisory authorities). The level of risk associated with transport incidents and accidents varies widely, according to the nature and quantities of the materials being carried, the number of shipments made and the package model used. The incident and accident management plan must therefore be tailored to the specific nature of the shipments by the party concerned. The radioactive

B Plant Complex generator dangerous waste storage areas inspection plan: Revision 1

International Nuclear Information System (INIS)

Beam, T.G.

1994-01-01

This document contains the inspection plan for the <90 day dangerous/mixed waste storage areas and satellite accumulation areas at B Plant Complex. This inspection plan is designed to comply with all applicable federal, state and US Department of Energy-Richland Operations Office training requirements. In particular, the requirements of WAC 173-303 ''Dangerous Waste Regulations'' are met by this inspection plan. This inspection plan is designed to provide B Plant Complex with the records and documentation showing that the waste storage and handling program is in compliance with applicable regulations. The plan also includes the requirements for becoming a qualified inspector of waste storage areas and the responsibilities of various individuals and groups at B Plant Complex

Effect of the planting material on the incidence of dry rot in Colocasia esculenta (L. Schott and Xanthosoma spp.

Directory of Open Access Journals (Sweden)

Ernesto Espinosa

2012-10-01

Full Text Available The cocoyam (Xanthosoma spp. and Colocasia esculenta is a monocot plant with vegetative propagation. This work was developed with the aim of determining the effect of the planting material type on the incidence of dry rot in two cultivars of Colocasia and Xanthosoma genera. Primary and secondary rhizomes, crowns of primary rhizomes and in vitro plants were used. The plantation was maintained for twelve months and the plants were characterized morphologically in the growing stage. Besides, it was determined the incidence of dry rot per treatment at growing and harvest stage. Finally, the yield was determined. When in vitro plants were used the percentage of incidence and intensity of the damage of dry rot was less in both cultivars. The yield in primary rhizomes and overall was significantly higher. The results indicated the superiority of in vitro plants as initial plantation material over the traditional seed used in taro culture. Furthermore, it allows the designing a seed production program by biotechnological methods. Key words: clone, cocoyam, dry rot, in vitro plants.

Optimized production planning model for a multi-plant cultivation system under uncertainty

Science.gov (United States)

Ke, Shunkui; Guo, Doudou; Niu, Qingliang; Huang, Danfeng

2015-02-01

An inexact multi-constraint programming model under uncertainty was developed by incorporating a production plan algorithm into the crop production optimization framework under the multi-plant collaborative cultivation system. In the production plan, orders from the customers are assigned to a suitable plant under the constraints of plant capabilities and uncertainty parameters to maximize profit and achieve customer satisfaction. The developed model and solution method were applied to a case study of a multi-plant collaborative cultivation system to verify its applicability. As determined in the case analysis involving different orders from customers, the period of plant production planning and the interval between orders can significantly affect system benefits. Through the analysis of uncertain parameters, reliable and practical decisions can be generated using the suggested model of a multi-plant collaborative cultivation system.

Survey of reportable incidents in nuclear power plants in Germany in the year 1992

International Nuclear Information System (INIS)

1993-01-01

In 1992, 223 reportable incidents in German nuclear power plant have been reported. There was no radioactivity release exceeding the maximum permissible limits, and there were no hazardous effects on the population or the environment. There was no incident belonging to category S of the official event scale, requiring urgent notification, while there were two incidents requiring immediate notification. All other incidents reported belonged to category N, the lowest on the scale, requiring normal notification. 216 incidents belonged to category 0 of the INES scale, and 7 to INES category 1 (disturbance). The tabulated survey of the report lists the various events and their position on the INES scale. The reportable events have been analysed thoroughly from various viewpoints, but no systematic pattern of weak points could be detected. (orig./HP) [de

Relation between source term and emergency planning for nuclear power plants

International Nuclear Information System (INIS)

Shi Zhongqi; Yang Ling

1992-01-01

Some background information of the severe accidents and source terms related to the nuclear power plant emergency planning are presented. The new source term information in NUREG-0956 and NUREG-1150, and possible changes in emergency planning requirements in U.S.A. are briefly provided. It is suggested that a principle is used in selecting source terms for establishing the emergency planning policy and a method is used in determining the Emergency Planning Zone (EPZ) size in China. Based on the research results of (1) EPZ size of PWR nuclear power plants being built in China, and (2) impact of reactor size and selected source terms on the EPZ size, it is concluded that the suggested principle and the method are suitable and feasible for PWR nuclear power plants in China

A SAS/AF application to administrate and query a file of incidents occurring in foreign nuclear power plants

International Nuclear Information System (INIS)

Durbec, V.

1994-07-01

The Research and Development Division of Electricite de France has a file of incidents occurring in foreign pressurized water nuclear power stations. These incidents have an impact either on safety or reliability. The file is stored on an IBM 3090. For each incident, a docket is assigned, containing the identity of the nuclear plant and information in the form of code or text on the incident. An application has been built with the SAS System under IBM (MVS) in order to: - allow the input of new nuclear plant identities, monthly operating coefficients and new incidents; - subset data from each SAS data set, according to selection criteria (country, manufacturers, period, materials, etc...) in the form of coded fields and characters strings; -calculate simple statistical analyses on subset data (histograms of break duration, distribution of operating coefficients, cross-tabulation tables of sets and materials which bring about the incident) with a restitution on screen and/or printer; - edit an annual booklet containing general results of functioning of plants. After validation, data retrieved from the database are used in probabilistic safety analysis of nuclear power plants and materials designing studies (comparison with French materials, identification of factors having an impact on performance). The application is an interactive menu-driven tool and contains data entry screens (for new data or selection criteria). These screens have been built with SAS/AF software and Screen Control Language. Data selection and processing have been developed with Base SAS and SAS/GRAPH software. (author). 1 ref., 6 figs., 2 tabs

Planning for Biogas Plant in Denmark

DEFF Research Database (Denmark)

Landt, Cristina C.; Gaarsmand, Regin; Palsberg, Aske

2016-01-01

This article is about establishing biogas in Denmark in the region of Zealand, the challenges that are related to this establishment and how to overcome this challenges. The article highlights three reasons for these challenges: 1) Regulation, 2) The municipal planning and 3) Involved various...... stakeholders. It investigates how these challenges affected the process and were overcome in the establishment of Solrod Biogas. In terms of ownership and biomass input, this biogas plant is unique compared to other Danish biogas plants. The biogas plant is based on organic by-products from local industries...... and seaweed. The plant solves an essential environmental issue for the municipality and citizens who were affected by the smell of rotten seaweed washed up in Koge Bay. The seaweed is used as input; this solves several problems at the same time. The method used to establish Solrod Biogas was an integrated...

76 FR 75771 - Emergency Planning Guidance for Nuclear Power Plants

Science.gov (United States)

2011-12-05

... Guidance for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of NUREG... Support of Nuclear Power Plants;'' NSIR/DPR-ISG-01, ``Interim Staff Guidance Emergency Planning for Nuclear Power Plants;'' and NUREG/CR-7002, ``Criteria for Development of Evacuation Time Estimate Studies...

Plutonium finishing plant dangerous waste training plan

International Nuclear Information System (INIS)

ENTROP, G.E.

1999-01-01

This training plan describes general requirements, worker categories, and provides course descriptions for operation of the Plutonium Finish Plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas

Planning and management of outages in nuclear power plants

International Nuclear Information System (INIS)

Sica, G.F.; Fusari, W.; Reginelli, A.

1984-01-01

At present the Ente Nazionale per l'Energia Elettrica (ENEL) operates three nuclear power plants, only one of which belongs to the new generation, i.e. the Caorso Nuclear Power Plant which has been in commercial operation since December 1981. Outage planning, implementation and analysis are very important in order to minimize the shutdown time and thus improve plant availability, which is of particular importance for a large nuclear power plant. Such activities are very complicated because of the large number of jobs that have to be performed in accordance with detailed written procedures and which have to be properly documented and controlled. Large off-site resources are required which have to be accurately interfaced with on-site staff. The ENEL is making a great effort to define both the administrative and technical aspects of refuelling outages. As outage planning requires the availability and handling of a large amount of data and information, a maintenance information system that has been widely used in conventional plants was applied, with some modifications made especially for the Caorso Nuclear Power Plant. After two years the following results have been achieved: a large number of raw and processed data are now available, the first refuelling outage was carried out with few problems and according to schedule, and the second refuelling outage, based on the experience of the first, required somewhat less preparation and is developing well even though many special activities have had to be scheduled. The ENEL believes that the efforts made in the planning and management areas will pay off in terms of the short duration, smoothness and economy of further outages, both for Caorso and for future plants. (author)

Regional coordination in medical emergencies and major incidents; plan, execute and teach

Directory of Open Access Journals (Sweden)

Hedelin Annika

2009-07-01

Full Text Available Abstract Background Although disasters and major incidents are difficult to predict, the results can be mitigated through planning, training and coordinated management of available resources. Following a fire in a disco in Gothenburg, causing 63 deaths and over 200 casualties, a medical disaster response centre was created. The center was given the task to coordinate risk assessments, disaster planning and training of staff within the region and on an executive level, to be the point of contact (POC with authority to act as "gold control," i.e. to take immediate strategic command over all medical resources within the region if needed. The aim of this study was to find out if the centre had achieved its tasks by analyzing its activities. Methods All details concerning alerts of the regional POC was entered a web-based log by the duty officer. The data registered in this database was analyzed during a 3-year period. Results There was an increase in number of alerts between 2006 and 2008, which resulted in 6293 activities including risk assessments and 4473 contacts with major institutions or key persons to coordinate or initiate actions. Eighty five percent of the missions were completed within 24 h. Twenty eight exercises were performed of which 4 lasted more than 24 h. The centre also offered 145 courses in disaster and emergency medicine and crisis communication. Conclusion The data presented in this study indicates that the center had achieved its primary tasks. Such regional organization with executive, planning, teaching and training responsibilities offers possibilities for planning, teaching and training disaster medicine by giving immediate feed-back based on real incidents.

B Plant complex hazardous, mixed and low level waste certification plan

International Nuclear Information System (INIS)

Beam, T.G.

1994-11-01

This plan describes the administrative steps and handling methodology for certification of hazardous waste, mixed waste, and low level waste generated at B Plant Complex. The plan also provides the applicable elements of waste reduction and pollution prevention, including up front minimization and end product reduction of volume and/or toxicity. The plan is written to satisfy requirements for Hanford Site waste generators to have a waste certification program in place at their facility. This plan, as described, applies only to waste which is generated at, or is the responsibility of, B Plant Complex. The scope of this plan is derived from the requirements found in WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria

B Plant complex hazardous, mixed and low level waste certification plan

Energy Technology Data Exchange (ETDEWEB)

Beam, T.G.

1994-11-01

This plan describes the administrative steps and handling methodology for certification of hazardous waste, mixed waste, and low level waste generated at B Plant Complex. The plan also provides the applicable elements of waste reduction and pollution prevention, including up front minimization and end product reduction of volume and/or toxicity. The plan is written to satisfy requirements for Hanford Site waste generators to have a waste certification program in place at their facility. This plan, as described, applies only to waste which is generated at, or is the responsibility of, B Plant Complex. The scope of this plan is derived from the requirements found in WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria.

Space-time variability of citrus leprosis as strategic planning for crop management.

Science.gov (United States)

Andrade, Daniel J; Lorençon, José R; Siqueira, Diego S; Novelli, Valdenice M; Bassanezi, Renato B

2018-01-31

Citrus leprosis is the most important viral disease of citrus. Knowledge of its spatiotemporal structure is fundamental to a representative sampling plan focused on the disease control approach. Such a well-crafted sampling design helps to reduce pesticide use in agriculture to control pests and diseases. Despite the use of acaricides to control citrus leprosis vector (Brevipalpus spp.) populations, the disease has spread rapidly through experimental areas. Citrus leprosis has an aggregate spatial distribution, with high dependence among symptomatic plants. Temporal variation in disease incidence increased among symptomatic plants by 4% per month. Use of acaricides alone to control the vector of leprosis is insufficient to avoid its incidence in healthy plants. Preliminary investigation into the time and space variation in the incidence of the disease is fundamental to select a sampling plan and determine effective strategies for disease management. © 2018 Society of Chemical Industry. © 2018 Society of Chemical Industry.

Indicators for management of planned outages in nuclear power plants

International Nuclear Information System (INIS)

2006-04-01

The outages considered within the scope of this publication are planned refuelling outages (PWR and BWR nuclear power plants) and planned outages associated with major maintenance, tests and inspections (PHWR and LWGR nuclear power plants). The IAEA has published some valuable reports providing guidance and assistance to operating organizations on outage management. This TECDOC outlines main issues to be considered in outage performance monitoring and provides guidance to operating organizations for the development and implementation of outage programmes which could enhance plant safety, reliability and economics. It also complements the series of reports published by the IAEA on outage management and on previous work related to performance indicators developed for monitoring different areas of plant operation, such as safety, production, reliability and economics. This publication is based upon the information presented at a technical meeting to develop a standardized set of outage indicators for outage optimization, which was organised in Vienna, 6-9 October 2003. At this meeting, case studies and good practices relating to performance indicator utilization in the process of planned outage management were presented and discussed

Characterization plan for the Hanford Generating Plant (HGP)

International Nuclear Information System (INIS)

Marske, S.G.

1996-09-01

This characterization plan describes the sample collection and sample analysis activities to characterize the Hanford Generating Plant and associated solid waste management units (SWMUs). The analytical data will be used to identify the radiological contamination in the Hanford Generating Plant as well as the presence of radiological and hazardous materials in the SWMUs to support further estimates of decontamination interpretation for demolition

Invasive Plant Management Plan for the Oak Ridge Reservation

Energy Technology Data Exchange (ETDEWEB)

Giffen, Neil R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); McCracken, Kitty [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-01

Invasive non-native plant species have become one of the greatest ecological threats across the country and around the world. Actively managing incursions of invasive plants is crucial to maintaining ecosystems, protecting natural resources, and ensuring proper function of facilities and their support infrastructures, power lines and other utility rights-of-way (ROWs), communications structures, roadways, and waterways. Invasive plants can threaten cultural resources, public and private properties, forests, wetlands, and other natural areas through increased risks of fire and storm damage, as well as decrease native plant diversity, particularly disrupting vital habitats of threatened and endangered species, both plant and animal. In 2000, the Federal Plant Protection Act came into effect. Under this Act, federal agencies are required to develop and coordinate an undesirable plants management program for control of invasive plants on federal lands under each agency’s respective jurisdiction. The agency must adequately fund the undesirable plants management program using an Integrated Pest Management Plan. Additionally, each agency is required to implement cooperative agreements with local and state agencies, as well as other federal agencies, to manage undesirable plants on federal lands under the agency’s jurisdiction. The US Department of Energy (DOE) takes its responsibility for addressing invasive and undesirable plant issues very seriously. Many DOE sites have programs to control invasive pest plant species. DOE has taken a proactive stance toward invasive plant control, and the Invasive Plant Management Plan— created to meet regulatory requirements of federal laws, executive orders, presidential memos, contracts, and agreements on DOE’s Oak Ridge Reservation (ORR)—has been in effect since 2004. This document represents the second revision of this plan.

Project plan remove special nuclear material from PFP project plutonium finishing plant

International Nuclear Information System (INIS)

BARTLETT, W.D.

1999-01-01

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

AVLIS Production Plant Preliminary Quality Assurance Plan and Assessment

International Nuclear Information System (INIS)

1984-01-01

This preliminary Quality Assurance Plan and Assessment establishes the Quality Assurance requirements for the AVLIS Production Plant Project. The Quality Assurance Plan defines the management approach, organization, interfaces, and controls that will be used in order to provide adequate confidence that the AVLIS Production Plant design, procurement, construction, fabrication, installation, start-up, and operation are accomplished within established goals and objectives. The Quality Assurance Program defined in this document includes a system for assessing those elements of the project whose failure would have a significant impact on safety, environment, schedule, cost, or overall plant objectives. As elements of the project are assessed, classifications are provided to establish and assure that special actions are defined which will eliminate or reduce the probability of occurrence or control the consequences of failure. 8 figures, 18 tables

Radiological monitoring plan for the Oak Ridge Y-12 Plant: Surface Water

International Nuclear Information System (INIS)

1997-10-01

The Y-12 Plant conducts a surface water monitoring program in response to DOE Orders and state of Tennessee requirements under the National Pollutant Discharge Elimination System (NPDES). The anticipated codification of DOE Order 5400.5 for radiation protection of the public and the environment (10 CFR Part 834) will require an environmental radiation protection plan (ERPP). The NPDES permit issued by the state of Tennessee requires a radiological monitoring plan (RMP) for Y-12 Plant surface waters. In a May 4, 1995 memo, the state of Tennessee, Division of Water Pollution Control, stated their desired needs and goals regarding the content of RMPs, associated documentation, and data resulting from the RMPs required under the NPDES permitting system (L. Bunting, General Discussion, Radiological Monitoring Plans, Tennessee Division of Water Pollution Control, May 4,1995). Appendix A provides an overview of how the Y-12 Plant will begin to address these needs and goals. It provides a more complete, documented basis for the current Y-12 Plant surface water monitoring program and is intended to supplement documentation provided in the Annual Site Environmental Reports (ASERs), NPDES reports, Groundwater Quality Assessment Reports, and studies conducted under the Y-12 Plant Environmental Restoration (ER) Program. The purpose of this update to the Y-12 Plant RMP is to satisfy the requirements of the current NPDES permit, DOE Order 5400.5, and 10 CFR Part 834, as current proposed, by defining the radiological monitoring plan for surface water for the Y-12 Plant. This plan includes initial storm water monitoring and data analysis. Related activities such as sanitary sewer and sediment monitoring are also summarized. The plan discusses monitoring goals necessary to determine background concentrations of radionuclides, to quantify releases, determine trends, satisfy regulatory requirements, support consequence assessments, and meet requirements that releases be ''as low as

Environmental impacts of power plants and transmission lines in power system planning

International Nuclear Information System (INIS)

Miracapillo, C.; Moreschini, G.; Rome Univ. 'La Sapienza'

1992-01-01

This paper deals with a criterion to assess the environmental impacts of power plants and transmission lines in power system planning. First, the effects of hydro-plants, thermal plants and transmission lines are reviewed. Then, a number of methods for the evaluation of the environmental impacts of civil and industrial plants are described. A new criterion is proposed to introduce the evaluation of the environmental impact and related costs into methods for power system planning. Finally, the criterion is applied to a simple case

Developing a highway emergency response plan for incidents involving hazardous materials, second edition, March 1992

International Nuclear Information System (INIS)

Anon.

1992-01-01

This provides minimum guidelines for developing an emergency response plan for incidents involving hazardous liquid hydrocarbons, such as gasoline and crude oil, transported in MC 306/DOT 406 and MC 307/DOT 407 aluminum cargo tanks and for coordinating and cooperating with local, state, and federal officials. This publication covers response plan priorities, personnel training, special equipment, media relations, environmental relations, and post-response activities. The apprendixes to this recommended practice outline a highway emergency response plan and suggest a procedure for removing liquid hydrocarbons from overturned cargo tanks and righting the tank vehicles

Adaptive Management Plan for Sensitive Plant Species on the Nevada Test Site

International Nuclear Information System (INIS)

Wills, C. A.

2001-01-01

The Nevada Test Site supports numerous plant species considered sensitive because of their past or present status under the Endangered Species Act and with federal and state agencies. In 1998, the U.S. Department of Energy, Nevada Operation Office (DOE/NV) prepared a Resource Management Plan which commits to protects and conserve these sensitive plant species and to minimize accumulative impacts to them. This document presents the procedures of a long-term adaptive management plan which is meant to ensure that these goals are met. It identifies the parameters that are measured for all sensitive plant populations during long-term monitoring and the adaptive management actions which may be taken if significant threats to these populations are detected. This plan does not, however, identify the current list of sensitive plant species know to occur on the Nevada Test Site. The current species list and progress on their monitoring is reported annually by DOE/NV in the Resource Management Plan

SMALL HYDRO PLANTS IN LAND USE SYSTEM PLANNING IN POLAND

Directory of Open Access Journals (Sweden)

Anita Bernatek

2014-10-01

Full Text Available Small hydropower plants are present in the land use system planning in Poland. At the national level the important role of spatial planning in the development of renewable energy was highlighted, included small hydroplants. However, it seems that at the regional level this demand has not been realized. The necessity of developing small hydroplants as a renewable energy was highlighted, but negative environmental impact was not indicated. At local level legal instrument of small hydropower plants is specified.

Training and plant performance: a strategic planning partnership

International Nuclear Information System (INIS)

Coe, R.P.

1987-01-01

The nuclear industry as a whole, and specifically GPU Nuclear, is refocusing its attention on performance indicators. This standardized assessment of plant operational performance surfaces numerous examples of how performance-based training positively impacts plant performance. Numerous examples of high dollar savings range from scram reduction programs to reducing personnel rem exposures. The deeper the authors look the more they find that training is making a difference. The question now is, how long can they continue to afford the ever increasing demands of the pursuit of excellence. Early in 1985, the Training and Education Department at GPU Nuclear proactively began its strategic planning effort in order to address the increasing industry initiatives while facing flat or reduced commitments of resources. The Training Strategic Plan addresses detailed plans for each of the following areas: curriculum planning; program development; training and education organizational structure; training and education administrative procedures; training advisory structure and priority process; financial strategies. All of the above strategies are designed to assure training effectiveness. With the nuclear option under such strong public scrutiny, it is in the best interest of all of the nuclear utilities to assure the most cost effective approach to successful operation while achieving their standards of excellence

Post-event reviews: Using a quantitative approach for analysing incident response to demonstrate the value of business continuity programmes and increase planning efficiency.

Science.gov (United States)

Vaidyanathan, Karthik

2017-01-01

Business continuity management is often thought of as a proactive planning process for minimising impact from large-scale incidents and disasters. While this is true, and it is critical to plan for the worst, consistently validating plan effectiveness against smaller disruptions can enable an organisation to gain key insights about its business continuity readiness, drive programme improvements, reduce costs and provide an opportunity to quantitatively demonstrate the value of the programme to management. This paper describes a post mortem framework which is used as a continuous improvement mechanism for tracking, reviewing and learning from real-world events at Microsoft Customer Service & Support. This approach was developed and adopted because conducting regular business continuity exercises proved difficult and expensive in a complex and distributed operations environment with high availability requirements. Using a quantitative approach to measure response to incidents, and categorising outcomes based on such responses, enables business continuity teams to provide data-driven insights to leadership, change perceptions of incident root cause, and instil a higher level of confidence towards disaster response readiness and incident management. The scope of the framework discussed here is specific to reviewing and driving improvements from operational incidents. However, the concept can be extended to learning and evolving readiness plans for other types of incidents.

Developing a hazmat incident evaluation program

International Nuclear Information System (INIS)

Williams, D.L.; Kaikumba, F.

1991-01-01

This paper reports that all communities are at risk of experiencing a hazardous materials incident, whether in transportation or at a fixed facility (such as petroleum refineries, oil fields, processing plants, etc.). However, many communities are unprepared to cope with this emergency. Administrators of state agencies and local response organizations often face fierce competition for tax dollars in support of their hazardous materials emergency response programs. Historically, little statistical information has been available to support their call for additional budget dollars in the areas of personnel, training, and equipment. It is difficult to plan for an emergency when you have little understanding of the risks, the frequency of incidents, the type of chemicals generally involved, and other vital information. The Illinois Hazardous Materials Incident Evaluation Program was designed to address the state and local needs, and position government and industry in a more responsive and proactive mode. The result is a program that works

B Plant treatment, storage, and disposal (TSD) units inspection plan

International Nuclear Information System (INIS)

Beam, T.G.

1996-01-01

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ''Dangerous Waste Regulations'' (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements

Waste Isolation Pilot Plant Strategic Plan

International Nuclear Information System (INIS)

1993-03-01

The purpose of the Waste Isolation Pilot Plant (WIPP) Strategic Plan is to provide decision makers, project participants, and the public with a high-level overview of the objectives, issues, and strategiesthat impact a decision on the suitability of WIPP as a permanent, safe disposal facility for transuranic (TRU) waste that has resulted from defense activities. This document is a component of an integrated planning process and is a key management tool that is coordinated and consistent with the Secretary's Disposal Decision Plan and the Environmental Restoration and Waste Management (EM) Five-Year Plan. This documentsupports other US Department of Energy (DOE) planning efforts, including the TRU Waste Program. The WIPP Strategic Plan addresses the WIPP Program Test Phase, Disposal Decision, Disposal Phase, and Decommissioning Phase (decontamination and decommissioning). It describes the actions and activities that the DOE will conduct to ensure that WIPP will comply with applicable, relevant, and appropriate requirements of the US Environmental Protection Agency (EPA), State of New Mexico, and other applicable federal and state regulations. It also includes the key assumptions under which the strategy was developed. A comprehensive discussion of the multitude of activities involved in the WIPP Program cannot be adequately presented in this document. The specific details of these activities are presented in other, more detailed WIPP planningdocuments

Plant Identification Characteristics for Deciduous Trees & Shrubs. Lesson Plans.

Science.gov (United States)

Burkholder, Kathy

This manual contains a group of lesson plans designed for use with a slide series (not included here). Its purpose is to introduce students to the basic concepts and terminology used in the identification of deciduous trees and shrubs. The manual is composed of 12 lesson plans. The first lesson is an introduction to plant identification. The…

Project plan remove special nuclear material from PFP project plutonium finishing plant; TOPICAL

International Nuclear Information System (INIS)

BARTLETT, W.D.

1999-01-01

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617,Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

Main pumps lost incident in the nuclear power plant Atucha I. Modelling with RELAP5/MOD3.2

International Nuclear Information System (INIS)

Ventura, M.A.; Rosso, R.D.

1998-01-01

Time evolution of natural circulation in the nuclear power plant Atucha I (CNA-I), in a main pumps lost incident because of the lost of external power feed, is analyzed. It leads to a strong stop transient, without an important blow down, from a forced nominal flow to a natural circulation one. The results are obtained from RELAP5/MOD3.2 code's modeling. The study is based on the refrigeration conditions analysis, during the first minutes of the reactor out of service. Previously to the transient, work had been done to obtain the plant steady state, with design parameters in operation conditions at 100 % of power. The object is that the actual plant state would be represented. In this way, each plant part (steam generators, reactor, pressurizer, pumps) had been modeled in separated form with the appropriate boundary conditions, to be used in the whole circuit simulation. The developed model, had been validated making use of the comparison between the values obtained to the principal thermodynamic parameters with the plant recorded values, in the same incident. The results are satisfactory in a way. On the other hand, it has suggested some modeling changes. The RELAP5/MOD3.2 capability to model the thermodynamic phenomena in a PHWR plant has been verified when, according to the mentioned incident, the flow pass from a nominal forced flow, to one which is governed by natural circulation, still with the CNA-I untypical design conditions. (author) [es

Nuclear power plant thermal-hydraulic performance research program plan

International Nuclear Information System (INIS)

1988-07-01

The purpose of this program plan is to present a more detailed description of the thermal-hydraulic research program than that provided in the NRC Five-Year Plan so that the research plan and objectives can be better understood and evaluated by the offices concerned. The plan is prepared by the Office of Nuclear Regulatory Research (RES) with input from the Office of Nuclear Reactor Regulation (NRR) and updated periodically. The plan covers the research sponsored by the Reactor and Plant Systems Branch and defines the major issues (related to thermal-hydraulic behavior in nuclear power plants) the NRC is seeking to resolve and provides plans for their resolution; relates the proposed research to these issues; defines the products needed to resolve these issues; provides a context that shows both the historical perspective and the relationship of individual projects to the overall objectives; and defines major interfaces with other disciplines (e.g., structural, risk, human factors, accident management, severe accident) needed for total resolution of some issues. This plan addresses the types of thermal-hydraulic transients that are normally considered in the regulatory process of licensing the current generation of light water reactors. This process is influenced by the regulatory requirements imposed by NRC and the consequent need for technical information that is supplied by RES through its contractors. Thus, most contractor programmatic work is administered by RES. Regulatory requirements involve the normal review of industry analyses of design basis accidents, as well as the understanding of abnormal occurrences in operating reactors. Since such transients often involve complex thermal-hydraulic interactions, a well-planned thermal-hydraulic research plan is needed

Particular intervention plan of The Bugey Nuclear Power Plant

International Nuclear Information System (INIS)

2014-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Bugey NPP (Ain, France)

Particular intervention plan of the Flamanville Nuclear Power Plant

International Nuclear Information System (INIS)

2008-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Flamanville NPP (Manche, France)

B Plant Complex pollution prevention plan. Revision 1

International Nuclear Information System (INIS)

Beam, T.G.

1994-01-01

The US Department of Energy (DOE) has directed Westinghouse Hanford Company (WHC) to develop an effective strategy to minimize the generation of hazardous, radioactive, and mixed wastes at Hanford in compliance with state and federal regulations. WHC has formalized a pollution prevention program composed of management policies, management requirements and procedures. This plan addresses pollution prevention for B Plant Complex. A pollution prevention team is in place and has been assigned responsibility for implementing the plan. This plan includes actions and goals for reducing volume and toxicity of waste generated, as well as a basis for evaluation of progress. Descriptions of waste streams, current specific goals, general pollution prevention methods, and specific accomplishments are in the appendices of this plan

Modeling time to recovery and initiating event frequency for loss of off-site power incidents at nuclear power plants

International Nuclear Information System (INIS)

Iman, R.L.; Hora, S.C.

1988-01-01

Industry data representing the time to recovery of loss of off-site power at nuclear power plants for 63 incidents caused by plant-centered losses, grid losses, or severe weather losses are fit with exponential, lognormal, gamma and Weibull probability models. A Bayesian analysis is used to compare the adequacy of each of these models and to provide uncertainty bounds on each of the fitted models. A composite model that combines the probability models fitted to each of the three sources of data is presented as a method for predicting the time to recovery of loss of off-site power. The composite model is very general and can be made site specific by making adjustments on the models used, such as might occur due to the type of switchyard configuration or type of grid, and by adjusting the weights on the individual models, such as might occur with weather conditions existing at a particular plant. Adjustments in the composite model are shown for different models used for switchyard configuration and for different weights due to weather. Bayesian approaches are also presented for modeling the frequency of initiating events leading to loss of off-site power. One Bayesian model assumes that all plants share a common incidence rate for loss of off-site power, while the other Bayesian approach models the incidence rate for each plant relative to the incidence rates of all other plants. Combining the Bayesian models for the frequency of the initiating events with the composite Bayesian model for recovery provides the necessary vehicle for a complete model that incorporates uncertainty into a probabilistic risk assessment

Guidance for emergency planning in nuclear power plants

International Nuclear Information System (INIS)

Magnusson, Tommy; Ekdahl, Maria

2008-06-01

Ringhals has been a model for this study, but the purpose has been to make the report applicable at all nuclear power plants in Sweden. The work has been done in close co-operation with the Swedish nuclear power plants and Rescue Services in the nuclear power municipalities Oesthammar, Oskarshamn, and Varberg. The internal fire brigade at the nuclear power plants has also been involved. A document will also be published as a further guidance at efforts of the type fires, which are mentioned in the enclosed document. After a fire in a switchgear room in 2005 the need of making the existing effort planning more effective at nuclear power plants was observed. The idea with the planning is to plan the effort in order to give the operational and emergency staff a good and actual support to come to a decision and to start the mission without delay. The risk information is showed by planning layouts, symbols and drawings as basis, give risk information and effort information. The effort information shows outer arrangements, manual action points, fire installations, passive fire safety etc. The risk information is shown by risk symbols. Their purpose is to give a fast overview of the existing risks. Reactor safety effects is the ruling influence if an effort has to be done in order to secure safety for a third person. In order to make an effort in an area personal risks for rescue staff, such as electricity risks, radiological risks, chemicals and gas bottles with compressed gases, has to be eliminated. For complicated missions detailed instructions are needed in order to handle specific risks. In a group discussion different people with pertinent knowledge has to value which problematic efforts need detailed instruction. Missions that have to be analyzed in a work group as above are: fire may affect the reactor safety, fire that may threaten the structural integrity, chemical discharge with big consequence on environment/third person and handling of gas system (compressed

Mortality and cancer incidence experience of employees in a nuclear fuels fabrication plant

International Nuclear Information System (INIS)

Hadjimichael, O.C.; Ostfeld, A.M.; D'Atri, D.A.; Brubaker, R.E.

1983-01-01

The mortality and cancer incidence experience of 4,106 employees in a nuclear fuels fabrication plant was evaluated in this retrospective cohort study. Standardized mortality (SMR) and incidence ratios were calculated for groups of employees holding different jobs in the company associated with various types of industrial exposures and with low levels of radiation. Connecticut population mortality rates and Connecticut Tumor Registry incidence rates, specific for age-sex, calendar year and cause of death or cancer site, were used for the calculation of expected rates. Results showed the SMR for all male employees to be significantly lower than expected for all causes and what would be expected for all cancer deaths. More deaths were observed than expected from diseases of the central and peripheral nervous system and from obstructive pulmonary disease. The overall cancer incidence experience of the male employees was significantly lower than expected among the industrial employees. There was no risk associated with any particular job exposure group. Log linear models analysis showed no significant effect from industrial and radiation exposures or from their combined influence

The incidence of Pyrenochaeta terrestris in root of different plant species in Serbia

Directory of Open Access Journals (Sweden)

Lević Jelena T.

2013-01-01

Full Text Available Root samples of cereals (oats, wheat, barley, maize and sorghum, vegetables (garlic, onion, pepper, cucumber, pumpkin, carrot and tomato, industrial plant (soya bean and weeds (Johnson grass, barnyard grass and green bristle-grass collected in different agroecological conditions in Serbia were analysed for the presence of Pyrenochaeta terrestris. The fungus was found in 42 out of 51 samples (82.4%, while the incidence varied from 2.5 to 72.5%. The highest incidence was detected in cereals (average 30.3%, and then in weeds of the Poaceae family (average 14.2%. Considering single species, maize (up to 72.5% in root and Johnson grass (up to 37.5% were mostly attacked by this fungus. The lowest incidence of the fungus was determined in vegetable crops (average 6.7%. Red to reddish discoloration of root was correlated with the incidence of the fungus. Obtained data indicate that P. terrestris is widespread in Serbia and conditions for its development are favourable. [Projekat Ministarstva nauke Republike Srbije, br. TR-31023

Plan for addressing issues relating to oil shale plant siting

Energy Technology Data Exchange (ETDEWEB)

Noridin, J. S.; Donovan, R.; Trudell, L.; Dean, J.; Blevins, A.; Harrington, L. W.; James, R.; Berdan, G.

1987-09-01

The Western Research Institute plan for addressing oil shale plant siting methodology calls for identifying the available resources such as oil shale, water, topography and transportation, and human resources. Restrictions on development are addressed: land ownership, land use, water rights, environment, socioeconomics, culture, health and safety, and other institutional restrictions. Descriptions of the technologies for development of oil shale resources are included. The impacts of oil shale development on the environment, socioeconomic structure, water availability, and other conditions are discussed. Finally, the Western Research Institute plan proposes to integrate these topics to develop a flow chart for oil shale plant siting. Western Research Institute has (1) identified relative topics for shale oil plant siting, (2) surveyed both published and unpublished information, and (3) identified data gaps and research needs. 910 refs., 3 figs., 30 tabs.

Effects of plant conduction systems and organic fertilizer management on disease incidence and severity in ‘Osiana’ and ‘Carola’ roses

Directory of Open Access Journals (Sweden)

Márcia de Nazaré Oliveira Ribeiro

2015-04-01

Full Text Available Conventional pruning is a very common practice for pruning rose cultivars in Brazil. However, few Brazilian producers known any other efficient plant training method for roses, namely “lateral stem bending” or “arching technique”, which involves bending the branches of the rosebush in order to increase the photosynthetic rate of the plant. As well as plant training, the use of fertilizers must also be done carefully in order to obtain high quality roses. Biofertilizers are recommended because of their multiple effects: fertilizer, protein synthesis stimulant, insect repellent, and disease controller. The aim of this study was to assess the plant training system and management of organic fertilizer on the incidence and severity of disease in the ‘Osiana’ and ‘Carola’ roses. The ‘Osiana’ rosebushes received three concentrations (0%, 5%, and 15% of foliar biofertilizer applied monthly to the leaves together with two plant conduction methods (conventional pruning and lateral stem bending. ‘Carola’ roses were treated with three types of fertilizer (chemical fertilizer on the soil + bokashi on the soil, chemical fertilizer on the soil + foliar FishfertilÒand chemical fertilization on the soil without applying organic fertilizers every two weeks, together with 2 plant conduction systems (conventional pruning and lateral stem bending. The additional treatments in ‘Carola’ roses were composed of two organic fertilizers (Bokashi and foliar Fishfertil® and chemical fertilization with lateral pruning. The incidence and severity of disease in these plants during the experiment were assessed over 5 months. For the ‘Osiana’ rose, the incidence and severity of disease were not influenced by fertilizer management or plant training methods. For the ‘Carola’ roses, the different types of fertilizer caused different responses according to the plant training system used, with the biofertilizer Fishfertil® reducing the incidence

The Need for Strategic Planning for Nuclear Power Plant I and C Upgrades

International Nuclear Information System (INIS)

Hill, J. Douglas; Moore, Paul

2002-01-01

Nuclear power plants rely on Instrumentation and Control (I and C) systems for control, monitoring and protection of the plant. The original, analog designs used in most nuclear plants have become or soon will be obsolete, forcing plants to turn to digital technology. Many factors affect the design of replacement equipment, including long-term and short-term economics, regulatory issues, and the way the plant operates on a day-to-day basis. The first step to all modernization projects should involve strategic planning, to ensure that the overall long and short-term goals of the plant are met. Strategic planning starts with a thorough evaluation of the existing plant control systems, the available options, and the benefits and consequences of these options. (authors)

Stochastic Programming for Fuel Supply Planning of Combined Heat and Power Plants

DEFF Research Database (Denmark)

Guericke, Daniela; Blanco, Ignacio; Morales González, Juan Miguel

The consumption of biomass to produce power and heat has increased due to the carbon neutral policies. Combined heat and power (CHP) plants often combine biomass with other fuels, e.g., natural gas. The negotiation process for supply contracts involves many uncertainties due to the long planning...... horizon. The demand for biomass is uncertain, and heat demand and electricity prices vary during the planning period. We propose a method using stochastic optimization to support the biomass and natural gas supply planning for CHP plants including short-term decisions for optimal market participation....

Project Management Plan to Maintain Safe and Compliant Conditions at the Plutonium Finishing Plant

International Nuclear Information System (INIS)

COX, G.J.

1999-01-01

This Project Management Plan presents the overall plan, description, mission, and workscope for the Plutonium Finishing Plant (PFP) maintain safe and compliant conditions project at PFP. This plan presents the overall description, mission, work scope, and planning for the Plutonium Finishing Plant (PFP) Maintain Safe and Compliant Conditions Project at PFP. This project includes all tasks required to maintain the safety boundary for the PFP Complex, except for the 2736-2 Vault Complex and the 234-52 vaults and vault-type rooms. The intent of this plan is to describe how this project will be managed and integrated with the stabilization, and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This is the top-level definitive project management document that specifies the technical (work scope), schedule, and cost baselines that will manage the execution of this project. It describes the organizational approach and roles/responsibilities implemented to execute the project. This plan is under configuration management and any deviations must be authorized by appropriate change control action

Study of cancer incidence among 6363 male workers in four Norwegian ferromanganese and silicomanganese producing plants.

Science.gov (United States)

Hobbesland, A; Kjuus, H; Thelle, D S

1999-09-01

Little has been known about the risk of cancer associated with occupational exposure to manganese. The objective of this study was therefore to examine the associations between duration of specific work and cancer incidence among employees in four Norwegian ferromanganese and silicomanganese producing plants. Among men first employed in 1933-91 and with at least 6 months in these plants, the incident cases of cancer during 1953-91 were obtained from The Cancer Registry of Norway. The numbers of various cancers were compared with expected figures calculated from age and calendar time specific rates for Norwegian men during the same period. Internal comparisons of rates were performed with Poisson regression analysis. The final cohort comprised 6363 men. A total of 607 cases of cancer were observed against 596 cases expected (standardised incidence ratio (SIR) 1.02). Internal comparisons of rates showed a positive trend between the rate of all cancers and duration of furnace work. A slightly weaker trend was also found for duration of blue collar non-furnace work when lags of 25 or 30 years were applied in the analyses. However, several results indicated that the incidence of all cancers among the non-furnace workers decreased during the period of active employment. Furnace and non-furnace workers may have exposures that increase the incidence of several cancers. The low incidence of cancer among non-furnace workers during the period of ongoing exposure cannot be explained. As this study cannot identify any causal factors, the role of exposure to manganese remains unclear.

Simulations of the recent LaSalle-2 incident with the BNL plant analyzer

International Nuclear Information System (INIS)

Cheng, H.S.; Mallen, A.N.; Wulff, W.

1989-01-01

This paper presents the results of simulations of the recent power oscillation incident at the LaSalle-2 nuclear power plant using the BNL plant analyzer. The causes of the oscillation were investigated and the sensitivity of the oscillation to key parameters was studied. It is concluded that the observed power oscillation was caused by boiling instability (i.e., density wave oscillation) reinforced by the reactivity feedback in neutron kinetics, and that the density wave oscillation resulted from flow reduction due to recirculation pump trip and feedwater temperature reduction due to partial loss of feedwater heating capability as well as power peaking

Interesting tools for the cybersecurity plan of a nuclear power plant

International Nuclear Information System (INIS)

Pareja, I.; Carrasco, J. A.; Cerro, F. J. del

2012-01-01

The use of digital technologies in monitoring and control systems of nuclear power plants and their connectivity requirements, originate cybersecurity difficulties that should be addressed in a cybersecurity plan. This plan should guide the policies and procedures followed during the design maintenance and operation of the systems inside a nuclear power plant. It also should refer to adequate tools able to reach the established cybersecurity requirements. The combination of Datadiodes and tools for publishing video(like tVGA2web), permit an isolation and remote maintenance in a 100% safety way and their use should be disseminated. In the paper other type of tools useful for nuclear power plants are also mentioned.

Planning of dairy farm and dairy plant based ecotourism

Science.gov (United States)

Sarnyoto, A. S.; Tama, I. P.; Tantrika, C. F. M.

2017-06-01

One of a dairy production company producing pasteurized milk and yoghurt drink, whose brand has widely known in East Java, has a factory plant in Batu City, one of tourism destinations in Indonesia. Behind the factory plant, there is a vacant land with an estimated total area of 2.3 ha and a vacant cowshed which had not been used for cattle ranching. Because of that, the company planned to develop the vacant land as a dairy farm and plant based ecotourism. In addition, dairy farm and dairy plant based tourism attractions are still rarely found in Batu. Thus, the first aim of this study was to analyse the potencies of the company that related to future plans of ecotourism built. The second aim was to set up the strategies that can be done in order to actualize the ecotourism project. The next aim was to plan the ecotourism, especially the facilities planning and the facilities arrangement on the vacant land. Strategic management approach was used to analyse the potencies and to determine the strategies. To select the proper facilities, tourists were asked to give appraisal by using questionnaire. Appraisal result was mapped onto four quadrants spatial map to see advantages and shortcomings of each facility along with choosing the right facilities to be built. Those facilities and tourist activities were compared with ecotourism criteria to make sure that the facilities were appropriate to provide not only entertainment but also ecotourism function. To arrange the chosen facilities, the step in Systematic Layout Planning were conducted to generate a propose layout of facilities arrangement. Based on potencies analysis, in Internal-External matrix, the company current position was on quadrant 2 (grow and build), with the most appropriate strategy was intensive or integrative. The proposed strategies were to build the new infrastructure, to renovate cowshed, and to add new tourism facilities on the land. There were 11 selected facilities based on MDS. Moreover, based

Incidence of 'Candidatus Liberibacter asiaticus'-Infected Plants Among Citrandarins as Rootstock and Scion Under Field Conditions.

Science.gov (United States)

Boava, Leonardo Pires; Sagawa, Cíntia Helena Duarte; Cristofani-Yaly, Mariângela; Machado, Marcos Antonio

2015-04-01

Huanglongbing (HLB), caused by the bacterium 'Candidatus Liberibacter' spp., is currently one of the most serious diseases of citrus plants and has caused substantial economic losses. Thus far, there is no source of genetic resistance to HLB in the genus Citrus or its relatives. However, several studies have reported Poncirus trifoliata and some of its hybrids to be more tolerant to the disease. The main objective of this study was to report differences in the incidence of 'Ca. L. asiaticus' infection in citrandarin plants, hybrids from Sunki mandarin (Citrus sunki (Hayata) hort. ex Tanaka), and trifoliate orange Rubidoux (P. trifoliata (L.) Raf.)), after conducting an extensive survey under field conditions. These hybrid plants were established for approximately 7 years in an area with a high incidence of 'Ca. L. asiaticus'-infected plants. We selected two experimental areas (area A and area B), located approximately 10 m apart. Area A consists of Pera sweet orange (C. sinensis (L.) Osb.) grafted onto 56 different citrandarin rootstocks. Area B consists of citrandarin scions grafted onto Rangpur lime (C. limonia Osb.) rootstock. Bacteria in the leaves and roots were detected using real-time quantitative polymerase chain reaction. The incidence of 'Ca. L. asiaticus'-infected plants was 92% in area A and 14% in area B. Because infected plants occurred in both areas, we examined whether the P. trifoliata hybrid rootstock influenced HLB development and also determined the distribution of 'Ca. L. asiaticus' in Citrus tree tissues. Although this survey does not present evidence regarding the resistance of P. trifoliata and its hybrids in relation to bacteria or psyllids, future investigation, mainly using the most promising hybrids for response to 'Ca. L. asiaticus', will help us to understand the probable mechanism of defense or identifying compounds in P. trifoliata and its hybrids that are very important as strategy to combat HLB. Details of these results are

Industrial Fuel Gas Demonstration Plant Program: environmental permit compliance plan

Energy Technology Data Exchange (ETDEWEB)

Bodamer, Jr., James W.; Bocchino, Robert M.

1979-11-01

This Environmental Permit Compliance Plan is intended to assist the Memphis Light, Gas and Water Division in acquiring the necessary environmental permits for their proposed Industrial Fuel Gas Demonstration Plant in a time frame consistent with the construction schedule. Permits included are those required for installation and/or operation of gaseous, liquid and solid waste sources and disposal areas. Only those permits presently established by final regulations are described. The compliance plan describes procedures for obtaining each permit from identified federal, state and local agencies. The information needed for the permit application is presented, and the stepwise procedure to follow when filing the permit application is described. Information given in this plan was obtained by reviewing applicable laws and regulations and from telephone conversations with agency personnel on the federal, state and local levels. This Plan also presents a recommended schedule for beginning the work necessary to obtain the required environmental permits in order to begin dredging operations in October, 1980 and construction of the plant in September, 1981. Activity for several key permits should begin as soon as possible.

Planning of emergency medical treatment in nuclear power plant

International Nuclear Information System (INIS)

Kusama, Tomoko

1989-01-01

Medical staffs and health physicists have shown deep concerning at the emergency plans of nuclear power plants after the TMI nuclear accident. The most important and basic countermeasure for accidents was preparing appropriate and concrete organization and plans for treatment. We have planed emergency medical treatment for radiation workers in a nuclear power plant institute. The emergency medical treatment at institute consisted of two stages, that is on-site emergency treatment at facility medical service. In first step of planning in each stage, we selected and treatment at facility medical service. In first step of planning in each stage, we selected and analyzed all possible accidents in the institute and discussed on practical treatments for some possible accidents. The manuals of concrete procedure of emergency treatment for some accidents were prepared following discussion and facilities and equipment for medical treatment and decontamination were provided. All workers in the institute had periodical training and drilling of on-site emergency treatment and mastered technique of first aid. Decontamination and operation rooms were provided in the facillity medical service. The main functions at the facility medical service have been carried out by industrial nurses. Industrial nurses have been in close co-operation with radiation safety officers and medical doctors in regional hospital. (author)

Planning for protecting power plants must not be just an afterthought

International Nuclear Information System (INIS)

Hogg, Bruce

1991-01-01

In this paper the Principal Fire and Major Incident Engineer at Nuclear Electric plc looks at fire safety in nuclear power plants, from the application of sophisticated 'state of the art' detection and extinguishment systems to the provision of well-trained firefighting teams. (author)

New fire and security rules change USA nuclear power plant emergency plans

International Nuclear Information System (INIS)

Garrou, A.L.

1978-01-01

New safety and security rules for nuclear power plants have resulted from the Energy Reorganisation Act and also from a review following the Browns Ferry fire. The content of the emergency plan which covers personnel, plant, site, as well as a general emergency, is outlined. New fire protection rules, the plan for security, local and state government assistance are also discussed, with a brief reference to the impact of the new rules on continuity of operations. (author)

Particular intervention plan of the Cruas-Meysse Nuclear Power Plant

International Nuclear Information System (INIS)

2013-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Cruas-Meysse NPP (Ardeche, France)

Outage planning in nuclear power plants. A paradigm shift from an external towards an integrated project planning tool

Energy Technology Data Exchange (ETDEWEB)

Rosemann, Andreas [Gesellschaft fuer integrierte Systemplanung (GIS) mbH, Weinheim (Germany)

2014-07-01

Latest demands on nuclear plant inspections are the ongoing actualisation of the outage plan on the basis of the current work progress and current events as well as the permanent access to the current planning status and work process of all people involved in the outage. Modern EAM systems (EAM: Enterprise Application Management) made up ground on established project planning tools with regard to functionalities for scheduling work orders. A shift towards an integrated planning in the EAM system increases the efficiency in the outage planning and improves the communication of current states of planning. (orig.)

Outage planning in nuclear power plants. A paradigm shift from an external towards an integrated project planning tool

International Nuclear Information System (INIS)

Rosemann, Andreas

2014-01-01

Latest demands on nuclear plant inspections are the ongoing actualisation of the outage plan on the basis of the current work progress and current events as well as the permanent access to the current planning status and work process of all people involved in the outage. Modern EAM systems (EAM: Enterprise Application Management) made up ground on established project planning tools with regard to functionalities for scheduling work orders. A shift towards an integrated planning in the EAM system increases the efficiency in the outage planning and improves the communication of current states of planning. (orig.)

Lessons learned from recent safety related incidents at A Canadian uranium conversion facility

International Nuclear Information System (INIS)

Jaferi, Jafir

2013-01-01

This paper presents the Canadian Nuclear Safety Commission's (CNSC) regulatory requirements for nuclear fuel facility licensees to report any situation or incident that results or is likely to result in a hazard to the health or safety of any person or the environment and to submit its incident investigation report with cause(s) of the incident and corrective actions taken or planned. In addition, the paper presents two recent safety-related incidents that occurred at a uranium conversion facility in Canada along with their consequences, causes, corrective actions and any lessons learned. The first incident resulted in a release of uranium hexafluoride (UF6) inside the UF6 cylinder filling station and the second one resulted in a spill of uranium tetrafluoride (UF 4 ) slurry inside the UF6 plant. Both incidents had no impact on the workers or the environment. (authors)

Tactical supply chain planning for a forest biomass power plant under supply uncertainty

International Nuclear Information System (INIS)

Shabani, Nazanin; Sowlati, Taraneh; Ouhimmou, Mustapha; Rönnqvist, Mikael

2014-01-01

Uncertainty in biomass supply is a critical issue that needs to be considered in the production planning of bioenergy plants. Incorporating uncertainty in supply chain planning models provides improved and stable solutions. In this paper, we first reformulate a previously developed non-linear programming model for optimization of a forest biomass power plant supply chain into a linear programming model. The developed model is a multi-period tactical-level production planning problem and considers the supply and storage of forest biomass as well as the production of electricity. It has a one-year planning horizon with monthly time steps. Next, in order to incorporate uncertainty in monthly available biomass into the planning, we develop a two-stage stochastic programming model. Finally, to balance the risk and profit, we propose a bi-objective model. The results show that uncertainty in availability of biomass has an additional cost of $0.4 million for the power plant. Using the proposed stochastic optimization model could reduce this cost by half. - Highlights: • Developed a two-stage stochastic optimization model to consider supply uncertainty. • Maximized the profit of a forest biomass power plant value chain. • Minimized two risk measures, variability index and downside risk, to manage risks. • Stochastic optimization model provided feasible solution for all scenarios. • Results showed a trade-off between profit and risk management

Monitoring well installation plan for the Department of Energy Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1997-09-01

The installation and development of groundwater monitoring wells is a primary element of the Y-12 Plant Groundwater Protection Program (GWPP), which monitors groundwater quality and hydrologic conditions at the Oak Ridge Y-12 Plant. This document is a groundwater monitoring well installation and development plan for the US Department of Energy (DOE) Y-12 Plant located in Oak Ridge, Tennessee. This plan formalizes well installation and construction methods, well development methods, and core drilling methods that are currently implemented at the Y-12 Plant under the auspices of the GWPP. Every three years, this plan will undergo a review, during which revisions necessitated by changes in regulatory requirements or GWPP objectives may be made

Nuclear Plant Aging Research (NPAR) program plan

International Nuclear Information System (INIS)

1985-07-01

The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechansims of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring and maintenance as means of mitigating such effects. Specifically the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of structures, components, and systems and thereby impair plant safety; (2) to identify methods of inspection, surveillance and monitoring, or of evaluating residual life of structures, components, and systems, which will assure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

Mesothelioma incidence in the neighbourhood of an asbestos-cement plant located in a national priority contaminated site

Directory of Open Access Journals (Sweden)

Lucia Fazzo

2014-12-01

Full Text Available BACKGROUND: An epidemic of asbestos-related disease is ongoing in most industrialized countries, mainly attributable to past occupational exposure but partly due to environmental exposure. In this perspective, the incidence of pleural mesothelioma close to a former asbestos-cement plant in a national contaminated site was estimated. METHODS: The census-tracts interested by atmospheric dispersion of facilities in the contaminated site were identified. Two subareas with different estimated environmental asbestos impact were distinguished. An ecological study at micro-geographic level was performed. The standardized incidence ratios (SIR for study area and the two subareas, in comparison with region and municipality were computed. The standardized incidence rate ratio (IRR between the two subareas was computed. RESULTS: Mesothelioma incidence in the study area was increased: 46 cases were observed with respect to 22.23 expected (SIR: 2.02. The increase was confirmed in analysis considering only the subjects without an occupationally exposure to asbestos: 19 cases among men (SIR = 2.48; 95% CI: 1.49-3.88; 11 case among women (SIR = 1.34; 95% CI: 0.67-2.40. The IRR between the two subareas is less than one in overall population considering all age-classes and of 3 fold (IRR = 3.14, 95% CI: 0.65-9.17 in the age-classes below 55 years. CONCLUSIONS: The findings indicate an increased incidence of pleural mesothelioma in the neighbourhood of asbestos-cement plant, and a possible etiological contribution of asbestos environmental exposure in detected risks.

Hazardous materials incidents on major highways -- A case study

International Nuclear Information System (INIS)

McElhaney, M.S.

1995-01-01

Personnel from both the public and private sectors have been involved for many years in pre-planning for hazardous materials releases at fixed installations all over the world. As a result of several major petroleum releases during marine transportation, oil companies, private contractors and government agencies have been preparing contingency plans for oil spills and other petroleum product releases in marine settings. Various industry groups have also developed plans for railway and pipeline disasters. These response plans are of varying quality, complexity and usefulness. Organizations such as plant emergency response teams, government agencies, contract response and clean-up crews and fire departments use these plans as a basis for training and resource allocation, hopefully becoming familiar enough with them that the plans are truly useful when product releases occur. Planners and emergency responders to hazardous materials releases must overcome some of the deficiencies which have long stood in the way of efficient and effective response and mitigation efforts. Specifically they must recognize and involve all resources with which they may respond or interact during an incident. This involvement should begin with the planning stages and carry through to training and emergency response and recovery efforts. They must ensure that they adopt and utilize a common command and control system and that all potential resources know this system thoroughly and train together before the incident occurs. It is only through incorporating these two factors that may successfully combat the ever growing number of unwanted product releases occurring in the more difficult realm of transportation

Radiological monitoring plan for the Oak Ridge Y-12 Plant: Surface water

International Nuclear Information System (INIS)

1995-01-01

National Pollutant Discharge Elimination System (NPDES) Permit TN0002968, issued April 28, 1995, requires that the Y-12 Plant Radiological Monitoring Plan for surface water be modified (Part 111-H). These modifications shall consist of expanding the plan to include storm water monitoring and an assessment of alpha, beta, and gamma emitters. In addition, a meeting was held with personnel from the Tennessee Department of Environment and Conservation (TDEC) on May 4, 1995. In this meeting, TDEC personnel provided guidance to Y-12 Plant personnel in regard to the contents of the modified plan. This report contains a revised plan incorporating the permit requirements and guidance provided by TDEC personnel. In addition, modifications were made to address future requirements of the new regulation for radiation protection of the public and the environment in regards to surface water monitoring

Developing and assessing accident management plans for nuclear power plants

International Nuclear Information System (INIS)

Hanson, D.J.; Johnson, S.P.; Blackman, H.S.; Stewart, M.A.

1992-07-01

This document is the second of a two-volume NUREG/CR that discusses development of accident management plans for nuclear power plants. The first volume (a) describes a four-phase approach for developing criteria that could be used for assessing the adequacy of accident management plans, (b) identifies the general attributes of accident management plans (Phase 1), (c) presents a prototype process for developing and implementing severe accident management plans (Phase 2), and (d) presents criteria that can be used to assess the adequacy of accident management plans. This volume (a) describes results from an evaluation of the capabilities of the prototype process to produce an accident management plan (Phase 3) and (b), based on these results and preliminary criteria included in NUREG/CR-5543, presents modifications to the criteria where appropriate

Spatial Distribution and Sampling Plans for Grapevine Plant Canopy-Inhabiting Scaphoideus titanus (Hemiptera: Cicadellidae) Nymphs.

Science.gov (United States)

Rigamonti, Ivo E; Brambilla, Carla; Colleoni, Emanuele; Jermini, Mauro; Trivellone, Valeria; Baumgärtner, Johann

2016-04-01

The paper deals with the study of the spatial distribution and the design of sampling plans for estimating nymph densities of the grape leafhopper Scaphoideus titanus Ball in vine plant canopies. In a reference vineyard sampled for model parameterization, leaf samples were repeatedly taken according to a multistage, stratified, random sampling procedure, and data were subjected to an ANOVA. There were no significant differences in density neither among the strata within the vineyard nor between the two strata with basal and apical leaves. The significant differences between densities on trunk and productive shoots led to the adoption of two-stage (leaves and plants) and three-stage (leaves, shoots, and plants) sampling plans for trunk shoots- and productive shoots-inhabiting individuals, respectively. The mean crowding to mean relationship used to analyze the nymphs spatial distribution revealed aggregated distributions. In both the enumerative and the sequential enumerative sampling plans, the number of leaves of trunk shoots, and of leaves and shoots of productive shoots, was kept constant while the number of plants varied. In additional vineyards data were collected and used to test the applicability of the distribution model and the sampling plans. The tests confirmed the applicability 1) of the mean crowding to mean regression model on the plant and leaf stages for representing trunk shoot-inhabiting distributions, and on the plant, shoot, and leaf stages for productive shoot-inhabiting nymphs, 2) of the enumerative sampling plan, and 3) of the sequential enumerative sampling plan. In general, sequential enumerative sampling was more cost efficient than enumerative sampling.

Monitoring well inspection and maintenance plan Y-12 Plant, Oak Ridge, Tennessee (revised)

International Nuclear Information System (INIS)

1996-09-01

Inspection and maintenance of groundwater monitoring wells is a primary element of the Oak Ridge Y-12 Plant Groundwater Protection Program (GWPP). This document is the revised groundwater monitoring well inspection and maintenance plan for the U.S. Department of Energy (DOE) Y-12 Plant in Oak Ridge, Tennessee. The plan provides a systematic program for: (1) inspecting the physical condition of monitoring wells at the Y-12 Plant and (2) identifying maintenance needs that will extend the life of each well and ensure that representative groundwater quality samples and hydrologic data are collected from the wells. Original documentation for the Y-12 Plant GWPP monitoring well inspection and maintenance program was provided in HSW, Inc. 1991a. The original revision of the plan specified that only a Monitoring Well Inspection/Maintenance Summary need be updated and reissued each year. Rapid growth of the monitoring well network and changing regulatory requirements have resulted in constant changes to the status of wells (active or inactive) listed on the Monitoring Well Inspection/Maintenance Summary. As a result, a new mechanism to track the status of monitoring wells has been developed and the plan revised to formalize the new business practices. These changes are detailed in Sections 2.4 and 2.5

Nuclear power plant operating experiences from the IAEA / Nea incident reporting system 2002-2005

International Nuclear Information System (INIS)

2006-01-01

The Incident Reporting System (IRS) is an essential element of the international operating experience feedback system for nuclear power plants. The IRS is jointly operated and managed by the Nuclear Energy Agency (NEA), a semi-autonomous body within the Organisation for Economic Co-operation and Development (OECD), and the International Atomic Energy Agency (IAEA), a specialized agency within the United Nations System. (author)

State and local planning procedures dealing with social and economic impacts from nuclear power plants

International Nuclear Information System (INIS)

Curry, M.; Goodrieght, J.; Green, M.; Merwin, D.; Smith, R.

1977-01-01

The roles of state and local agencies in planning for and managing social and economic impacts of nuclear power plants are studied. In order to be effective in these roles state and local agencies must work with each other as well as the NRC. A comparative case study approach is used which analyzes six sites in three West Coast states. The case studies included plants in operation, plants under construction, and plants still in the planning stages. In contrast to some states, all three of these states have moderately centralized procedures for siting power plants, and all have strong environmental laws

Monitoring well plugging and abandonment plan, Y-12 Plant, Oak Ridge, Tennessee (revised)

International Nuclear Information System (INIS)

1997-05-01

Plugging and abandonment (P ampersand A) of defunct groundwater monitoring wells is a primary element of the Oak Ridge Y-12 Plant Groundwater Protection Program (GWPP) (AJA Technical Services, Inc. 1996). This document is the revised groundwater monitoring well P ampersand A plan for the U.S. Department of Energy (DOE) Y-12 Plant located in Oak Ridge, Tennessee. This plan describes the systematic approach employed by Y-12 Plant GWPP to identify wells that require P ampersand A, the technical methods employed to perform P ampersand A activities, and administrative requirements. Original documentation for Y-12 Plant GWPP groundwater monitoring well P ampersand A was provided in HSW, Inc. (1991). The original revision of the plan specified that a comprehensive monitoring well P ampersand A was provided in HSW, Inc. (1991). The original revision of the plan specified that a comprehensive monitoring well P ampersand A schedule be maintained. Wells are added to this list by issuance of both a P ampersand A request and a P ampersand A addendum to the schedule. The current Updated Subsurface Data Base includes a single mechanism to track the status of monitoring wells. In addition, rapid growth of the groundwater monitoring network and new regulatory requirements have resulted in constant changes to the status of wells. As a result, a streamlined mechanism to identify and track monitoring wells scheduled for P ampersand A has been developed and the plan revised to formalize the new business practices

Development of a Traffic Management Decision Support Tool for Freeway Incident Traffic Management (FITM) Plan Deployment : Research Summary

Science.gov (United States)

2017-12-01

In designing an effective traffic management plan for non-recurrent congestion, it is critical for responsible highway agencies to have some vital information, such as estimated incident duration, resulting traffic queues, and the expected delays. Ov...

Near-term benefits of life extension planning for nuclear power plants

International Nuclear Information System (INIS)

Pickens, T.; Gregor, F.E.

1988-01-01

Life Extension of Nuclear Power Plants is now viewed as a realistic alternative to construction of new generating facilities. The subject has been under intensive study since 1984 and two comprehensive pilot plant programs have been completed under EPRI, U.S. Department of Energy and utility sponsorship. A major lesson learned from these studies is that planning for life extension must start early and that many activities must be implemented as early in life as possible to enhance the option for life extension through mitigate and preventive actions. It was also determined that achievement of a 40-year licensed life is by no means guaranteed without substantial effort during the remaining plant life. In examining these recommended actions, it becomes obvious that conscientious implementation also leads to realization of significant short-term benefits in the form of availability improvement, outage reduction, maintenance optimization and longer term planning decisions. In addition to the economic benefits, plant safety is also enhanced by reducing challenges to the safety systems and slowly switching from a corrective maintenance to a preventive maintenance program

Experimental program plan for the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included.

Experimental program plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1994-01-01

The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included

Phenomenological modelling of second cancer incidence for radiation treatment planning

International Nuclear Information System (INIS)

Pfaffenberger, Asja; Oelfke, Uwe; Schneider, Uwe; Poppe, Bjoern

2009-01-01

It is still an unanswered question whether a relatively low dose of radiation to a large volume or a higher dose to a small volume produces the higher cancer incidence. This is of interest in view of modalities like IMRT or rotation therapy where high conformity to the target volume is achieved at the cost of a large volume of normal tissue exposed to radiation. Knowledge of the shape of the dose response for radiation-induced cancer is essential to answer the question of what risk of second cancer incidence is implied by which treatment modality. This study therefore models the dose response for radiation-induced second cancer after radiation therapy of which the exact mechanisms are still unknown. A second cancer risk estimation tool for treatment planning is presented which has the potential to be used for comparison of different treatment modalities, and risk is estimated on a voxel basis for different organs in two case studies. The presented phenomenological model summarises the impact of microscopic biological processes into effective parameters of mutation and cell sterilisation. In contrast to other models, the effective radiosensitivities of mutated and non-mutated cells are allowed to differ. Based on the number of mutated cells present after irradiation, the model is then linked to macroscopic incidence by summarising model parameters and modifying factors into natural cancer incidence and the dose response in the lower-dose region. It was found that all principal dose-response functions discussed in the literature can be derived from the model. However, from the investigation and due to scarcity of adequate data, rather vague statements about likelihood of dose-response functions can be made than a definite decision for one response. Based on the predicted model parameters, the linear response can probably be rejected using the dynamics described, but both a flattening response and a decrease appear likely, depending strongly on the effective cell

An Assessment for Emergency Preparedness Plan in Hanul Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Park, Sunghyun; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

2016-10-15

The purpose of emergency preparedness aims to protect the accident and mitigate the radiation damage of public by setting emergency preparedness plan. In order to perform successfully the emergency preparedness plan, it should be optimized through a quantitative analysis. There are so many variables to analyze it quantitatively. It is mission to classify a realistic and suitable variables among these variables. The realistic variables is converted to the decision node in decision tree which is helpful to decide what evacuation or sheltering is effective to mitigate public damage. Base on it, it's idealistic method to analyze offsite consequences for each end points in the decision tree. In this study, we selected the reference plant which already has the emergency preparedness plan. Among the plan, we implemented offsite consequence analysis for a specific plan by using MACCS 2 code. In this study, target group is people who gathered in place 1 have sheltered and evacuated along the pathway. the offsite consequences analysis result of the group are 1.17·10-9 (early fatality), 1.77·10-7 (late fatality). Various cases need to be quantified for make an optimized decision. In the future, we will perform the verification and modification of decision node. After The assessment of emergency preparedness plan for Hanul nuclear power plant unit 5, 6 might be contribute to establish the optimized decision making of emergency prepared plan.

Operations Program Plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1990-09-01

This document, Revision 4 of the Operations Program Plan, has been developed as the seven-year master plan for operating of the Waste Isolation Pilot Plant (WIPP). Subjects covered include public and technical communications; regulatory and environmental programs; startup engineering; radiation handling, surface operations, and underground operations; waste certification and waste handling; transportation development; geotechnical engineering; experimental operations; engineering program; general maintenance; security program; safety, radiation, and regulatory assurance; quality assurance program; training program; administration activities; management systems program; and decommissioning. 243 refs., 19 figs., 25 tabs. (SM)

Industrial Fuel Gas Demonstration Plant Program. Demonstration plant operation plan (Deliverable No. 38)

Energy Technology Data Exchange (ETDEWEB)

None

1979-01-01

The Demo Plant Operating Plan is composed of the following sequence of events starting with the training or personnel, familiarizing of the personnel with the plant and completing the long-term run in the following sequences: inspection during construction, plant completion, shakedown of equipment, process unit startup, shakedown of process units, variable run operation and a turnaround. During the construction period, technical personnel from DRC, MLGW and IGT will be at the plant site becoming familiar with the equipment, its installation and all of the auxiliaries so that on completion of construction they will be well grounded on the plant detail and its configuration. At the same time the supervisory operating personnel will have hands on training the gasifier operation at the IGT pilot plant to develop a field for gasifier operation. As a plant sections are completed, they will be checked out in accordance with the contractor and operator (client) procedure as outlined. Subsequent to this, various vendor designs and furnished equipment will be checked out operating-wise and a performance test run if feasible. The actual startup of the plant will be subsequential with the support areas as utilities, coal handling and waste treatment being placed in operation first. Subsequent to this the process units will be placed in operation starting from the rear of the process train and working forward. Thus the downstream units will be operating before the reactor is run on coal. The reactor will be checked out on coke operation.

76 FR 30957 - Endangered and Threatened Wildlife and Plants; Notice of Availability of a Draft Recovery Plan...

Science.gov (United States)

2011-05-27

... and Threatened Wildlife and Plants (List). Recovery plans help guide our recovery efforts by...] Endangered and Threatened Wildlife and Plants; Notice of Availability of a Draft Recovery Plan, First... plan, you may submit your comments in writing by any one of the following methods: U.S. mail: Field...

Soil Management Plan for the Y-12 Plant

International Nuclear Information System (INIS)

1993-01-01

Construction activities at the US Department of Energy (DOE) Y-12 Plant have often required the excavation or other management of soil within the facility. Because some of this soil may be contaminated, Martin Marietta Energy Systems, Inc. (Energy Systems) adopted specific policies to ensure the proper management of contaminated or potentially contaminated soil at the plant. Five types of contaminated or potentially contaminated soil are likely to be present at the Y-12 Plant: Soil that is within the boundaries of a Comprehensive Response, Compensation, and Liability Act (CERCLA) Area of Contamination (AOC) or Operable Unit (OU); Soil that contains listed hazardous wastes; Soil that is within the boundaries of a RCRA Solid Waste Management Unit (SWMU); Soil that contains polychlorinated biphenyls (PCBS); Soil that contains low-level radioactive materials. The regulatory requirements associated with the five types of contaminated soil listed above are complex and will vary according to site conditions. This Soil Management Plan provides a standardized method for managers to determine the options available for selecting soil management scenarios associated with construction activities at the Y-12 Plant

Project Plan For Remove Special Nuclear Material (SNM) from Plutonium Finishing Plant (PFP) Project

International Nuclear Information System (INIS)

BARTLETT, W.D.

1999-01-01

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove SNM Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617. This project plan is the top-level definitive project management document for the PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baseline to manage the execution of the Remove SNM Materials project. Any deviation to the document must be authorized through the appropriate change control process. The Remove SNM Materials project provides the necessary support and controls required for DOE-HQ, DOE-RL, BWHC, and other DOE Complex Contractors the path forward to negotiate shipped/receiver agreements, schedule shipments, and transfer material out of PFP to enable final deactivation

Facility effluent monitoring plan for the B plant

International Nuclear Information System (INIS)

Lesser, J.E.

1994-09-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plant assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated every three years

Computerized planning system for nuclear power plant evaluation

International Nuclear Information System (INIS)

Bonczek, R.H.; Holsapple, C.W.; Whinston, A.B.

1976-01-01

A computerized system is described for information storage and query processing adapted to complex socio-technological issues. The system is referred to as GPLAN (Generalized Planning System) and can accommodate both qualitative (verbal) and quantitative data. The issue illustrated is the construction of a nuclear power plant, and involves interdisciplinary research and planning. The system's outstanding features are the use of the network variety of data base, the selective retrieval of any configuration of data from a particular network structure, automatic execution of any desired application program from a standard or special library of applications, user interface with a data base and applications by submitting English-like, non-procedural queries, and generality which allows tailoring to specific applications and provides a basis for integration of planning and research activities. The system is general and can be used for a wide variety of socio-technological issues which involve complex data relationships

Effect of medicinal plants extracts on the incidence of mosaic disease caused by cucumber mosaic virus and growth of chili

Science.gov (United States)

Hamidson, H.; Damiri, N.; Angraini, E.

2018-01-01

This research was conducted to study the effect of the application of several extracts of medicinal plants on the incidence of mosaic disease caused by Cucumber Mosaic Virus infection on the chili (Capsicum annuum L.) plantation. A Randomized Block Design with eight treatments including control was used throughout the experiment. Treatments consisted of Azadiracta indica (A), Piper bitle (B), Cymbopogon citrates (C), Curcuma domestica (D), Averroa bilimbi (E), Datura stramonium (F), Annona Muricata (G) and control (H). Each treatment consist of three replications. The parameters observed were the incidence of mosaic attack due to CMV, disease severity, plant height, wet and dry weight and production (number of fruits and the weight of total fruits) each plant. Results showed that the application of medicinal plant extracts reduced the disease severity due to CMV. Extracts of Annona muricata and Datura stramonium were most effective in suppressing disease severity caused by the virus as they significantly different from control and from a number of treatment. The plants medicinal extracts were found to have increased the plant height and total weight of the plant, fruit amount and fruit weight. Extracts of Curcuma domestica, Piper bitle and Cymbopogon citrates were the third highest in fruit amount and weight and significantly different from the control.

Groundwater Interim Measures Work Plan for the Former Chemical Plant

Science.gov (United States)

May 2012 Groundwater IMWP, revised per EPA's approval, focuses on the installation of a groundwater containment system to mitigate groundwater migration from the former plant. A prior 2002 work plan is included in its entirety in Appendix B.

Presentation plan of the reconstruction and upgrade hydroelectric power plant 'Zvornik'

Directory of Open Access Journals (Sweden)

Krstić Dušan B.

2016-01-01

Full Text Available By the basic project of the energy utilization of the middle part of the river Drina (from Višegrad to Zvornik building of five large hydroelectric power plants was planned. Hydroelectric power plant near Zvornik had the greatest advantage, and it is the first built. Hydroelectric power plant 'Zvornik' separates the river Drina, about 1 km upstream from Mali Zvornik in Serbia and Zvornik in Bosnia and Herzegovina. In order to extend the work life, by the urban development project was planned modernization of production aggregates and associated equipment, the upgrade of annexes above the aggregate siphons A1 and A2, as well as the upgrade of the annexes of the powerhouse on the right bank of the river in the function of accommodation of electrical equipment. By replacing of the vital parts of turbines with increasing diameter with an increase of efficiency, Bow and power, as well as replacing generators with new generator of higher power with excitation and all the necessary auxiliary equipment, will ensure reliable operation of the hydroelectric power plant and will extend the working life of the next 40 years, creating opportunities for retrofitting additional fifth unit.

Targeting safety improvements through identification of incident origination and detection in a near-miss incident learning system

International Nuclear Information System (INIS)

Novak, Avrey; Nyflot, Matthew J.; Ermoian, Ralph P.; Jordan, Loucille E.; Sponseller, Patricia A.; Kane, Gabrielle M.; Ford, Eric C.; Zeng, Jing

2016-01-01

Purpose: Radiation treatment planning involves a complex workflow that has multiple potential points of vulnerability. This study utilizes an incident reporting system to identify the origination and detection points of near-miss errors, in order to guide their departmental safety improvement efforts. Previous studies have examined where errors arise, but not where they are detected or applied a near-miss risk index (NMRI) to gauge severity. Methods: From 3/2012 to 3/2014, 1897 incidents were analyzed from a departmental incident learning system. All incidents were prospectively reviewed weekly by a multidisciplinary team and assigned a NMRI score ranging from 0 to 4 reflecting potential harm to the patient (no potential harm to potential critical harm). Incidents were classified by point of incident origination and detection based on a 103-step workflow. The individual steps were divided among nine broad workflow categories (patient assessment, imaging for radiation therapy (RT) planning, treatment planning, pretreatment plan review, treatment delivery, on-treatment quality management, post-treatment completion, equipment/software quality management, and other). The average NMRI scores of incidents originating or detected within each broad workflow area were calculated. Additionally, out of 103 individual process steps, 35 were classified as safety barriers, the process steps whose primary function is to catch errors. The safety barriers which most frequently detected incidents were identified and analyzed. Finally, the distance between event origination and detection was explored by grouping events by the number of broad workflow area events passed through before detection, and average NMRI scores were compared. Results: Near-miss incidents most commonly originated within treatment planning (33%). However, the incidents with the highest average NMRI scores originated during imaging for RT planning (NMRI = 2.0, average NMRI of all events = 1.5), specifically

Targeting safety improvements through identification of incident origination and detection in a near-miss incident learning system

Energy Technology Data Exchange (ETDEWEB)

Novak, Avrey; Nyflot, Matthew J.; Ermoian, Ralph P.; Jordan, Loucille E.; Sponseller, Patricia A.; Kane, Gabrielle M.; Ford, Eric C.; Zeng, Jing, E-mail: jzeng13@uw.edu [Department of Radiation Oncology, University of Washington Medical Center, 1959 NE Pacific Street, Campus Box 356043, Seattle, Washington 98195 (United States)

2016-05-15

Purpose: Radiation treatment planning involves a complex workflow that has multiple potential points of vulnerability. This study utilizes an incident reporting system to identify the origination and detection points of near-miss errors, in order to guide their departmental safety improvement efforts. Previous studies have examined where errors arise, but not where they are detected or applied a near-miss risk index (NMRI) to gauge severity. Methods: From 3/2012 to 3/2014, 1897 incidents were analyzed from a departmental incident learning system. All incidents were prospectively reviewed weekly by a multidisciplinary team and assigned a NMRI score ranging from 0 to 4 reflecting potential harm to the patient (no potential harm to potential critical harm). Incidents were classified by point of incident origination and detection based on a 103-step workflow. The individual steps were divided among nine broad workflow categories (patient assessment, imaging for radiation therapy (RT) planning, treatment planning, pretreatment plan review, treatment delivery, on-treatment quality management, post-treatment completion, equipment/software quality management, and other). The average NMRI scores of incidents originating or detected within each broad workflow area were calculated. Additionally, out of 103 individual process steps, 35 were classified as safety barriers, the process steps whose primary function is to catch errors. The safety barriers which most frequently detected incidents were identified and analyzed. Finally, the distance between event origination and detection was explored by grouping events by the number of broad workflow area events passed through before detection, and average NMRI scores were compared. Results: Near-miss incidents most commonly originated within treatment planning (33%). However, the incidents with the highest average NMRI scores originated during imaging for RT planning (NMRI = 2.0, average NMRI of all events = 1.5), specifically

Criteria for classification and reporting of fire incidences in nuclear power plants of India

International Nuclear Information System (INIS)

Kapoor, R.K.

1998-01-01

Is is important that all fires in and around fire effective neighbourhood of Nuclear Power Plant (NPP) should be promptly reported (Reportable fires) and investigated. However, the depth of investigation and the range of authorities to whom the individual fire incidence need to be reported depends upon the severity of fire. In case of conventional non-chemical industries, the severity of fire depends mainly on the extent of loss caused by fire on property and the burn injury to persons. In case of NPP, two additional losses viz, release of radioactivity to working/public environment and the risk to safety related systems of NPP due to fire assume greater importance. This paper describes the criteria used in NPPs of India for classification of reportable fire incidences into four categories, viz. Insignificant, small, medium and large fires. It also gives the level of investigation depending upon the severity of fire. The fire classification scheme is explained in this paper with the help of worked out examples and two incidences of fire in Indian NPPs. (author)

Nuclear power plant operating experiences from the IAEA/NEA Incident Reporting System 1999-2002

International Nuclear Information System (INIS)

2003-01-01

Incident reporting has become an increasingly important aspect of the operation and regulation of all public health and safety-related industries. Diverse industries such as aeronautics, chemicals, pharmaceuticals and explosives all depend on operating experience feedback to provide lessons learned about safety. The Incident Reporting System (IRS) is an essential element of the system for feeding back international operating experience for nuclear power plants. IRS reports contain information on events of Safety significance with important lessons learned. These experiences assist in reducing or eliminating recurrence of events at other plants. The IRS is jointly operated and managed by the Nuclear Energy Agency (NEA), a semi-autonomous body within the Organisation for Economic Co-operation and Development (OECD), and the International Atomic Energy Agency (IAEA). It is important that sufficient national resources be allocated to enable timely and high quality reporting of events important to safety, and to share these events in the IRS database. The first report, which covered the period July 1996 - June 1999, was widely acclaimed and encouraged both agencies to prepare this second report in order to highlight important lessons learned from around 300 events reported to the IRS for the period July 1999 - December 2002. Several areas were selected in this report to show the range of important topics available in the IRS. These include different types of failure in a variety of plant systems, as well as human performance considerations. This report is primarily aimed at senior officials in industry and government who have decision-making roles in the nuclear power industry

Organisational learning - literature review and plans for 2004

International Nuclear Information System (INIS)

Ludvigsen, Jan Tore

2004-01-01

Efficient organisational learning is considered to be a precondition for high reliability organisations. Organisational learning allows an organisation to learn from its own and/or others' failures, which contributes to ensure that incidents are avoided in the future. The first part of the paper provides an overview of the field of organisational learning, and describes the past and current trends in this extensive field. The second part presents the plans for a case study that will be completed this year. The objective of the case study is to describe the learning practices at a small nuclear research plant, with the purpose of assessing the current approach to learning from failures and incidents at the plant. The case study serves as a pilot study, and the outcome of the study will make up the basis for conducting similar research on larger nuclear power plants. A long-term goal is to develop a framework for assessing and implementing learning practices that facilitate the learning competence of nuclear power plants. (Author)

One year of operation of the Belgonucleaire (Dessel) plutonium fuel fabrication plant

International Nuclear Information System (INIS)

Leblanc, J.M.

1975-01-01

Based on experience with plutonium since 1958, Belgonucleaire has successively launched a pilot plant and then a fuel fabrication plant for mixed uranium and plutonium oxides in 1968 and 1973 respectively. After describing briefly the plants and the most important stages in the planning, construction and operation of the Dessel plant, the present document describes the principal problems which were met during the course of operation of the plant and their direct incidence on the capacity and quality of the production of fuel elements

Biomass Supply Planning for Combined Heat and Power Plants using Stochastic Programming

DEFF Research Database (Denmark)

Guericke, Daniela; Blanco, Ignacio; Morales González, Juan Miguel

method using stochastic optimization to support the biomass supply planning for combined heat and power plants. Our two-phase approach combines mid-term decisions about biomass supply contracts with the short-term decisions regarding the optimal market participation of the producer to ensure......During the last years, the consumption of biomass to produce power and heat has increased due to the new carbon neutral policies. Nowadays, many district heating systems operate their combined heat and power (CHP) plants using different types of biomass instead of fossil fuel, especially to produce......, and heat demand and electricity prices vary drastically during the planning period. Furthermore, the optimal operation of combined heat and power plants has to consider the existing synergies between the power and heating systems while always fulfilling the heat demand of the system. We propose a solution...

Inspection maintenance and planning of shutdown in thermal electric generating plants

International Nuclear Information System (INIS)

Dezordi, W.L.; Correa, D.A.; Kina, M.

1984-01-01

The schedule shutdown of an industrial plant and, more specifically, of an electrical generating station, is becoming increasingly important. The major parameters to be taken into account for the planning of such a shutdown are basically of economic-financial nature such as costs of the related services (materials, equipment, manpower, etc), loss of revenue caused by the station's shutdown as well as by the station availability, and other requirements expected from it by the Load Dispatch and consumers. Improving the equipment's performances and the station's availability are the fundamental objectives to be strived for. The authors present in this paper, in an abridged form, the planning tools used for thermal electric generating plants shutdowns for inspections, maintenance and design changes implementation. (Author) [pt

Trend analysis of the adverse event cause in nuclear power plants

International Nuclear Information System (INIS)

Takagawa, Kenichi

2010-01-01

The adverse incidents which occurred in domestic and U. S. nuclear power plants during the period from 2003 to 2008 were classified by the cause classification method developed by INSS. From the results, it is clarified that the most frequent cause both in Japan and the U.S. is 'maintenance errors' accounting for approximately 40% of the total causes. Among 'maintenance errors', 'imperfect planning' is the most frequent one in the U. S. and increased from fiscal year 2007 in Japan. 'Workers error' has reduced its frequency by half in the U. S. and is staying at more frequent level in Japan. From the result of tendency analysis, corrective action against 'imperfect planning' and/or the effective use of incident information is thought to become effective to reduce the frequency of adverse incidents. Therefore, future subjects should include a study of alternative methods to analyze 'imperfect planning' which enable supplemented current RCA. At the same time, it should also be a theme to consider the proper ways of making incident reports to have the worker or planner easily extract lessons learned from them, as well as understanding the importance of utilizing incident information such as NUCIA. (author)

An Archeological Overview and Management Plan for the Tarheel Army Missile Plant Alamance County, North Carolina.

Science.gov (United States)

1984-05-21

factory planning engineer, noted that bedrock lies about 22 feet be- low the surface in the eastern portion of the main plant area, but had not...Carolina Press. Lee, James B. 1983. Personal communication. Factory Planning Engineer, Western Electric Company, Tarheel Army Missile Plant. Lefl1cr, Hugh

Waste Isolation Pilot Plant (WIPP) startup plan

International Nuclear Information System (INIS)

1988-03-01

To allow the Waste Isolation Pilot Plant (WIPP) to transition from a Major System Acquisition to an operating demonstration facility, the Acquisition Executive and the Energy System Acquisition Advisory Board (ESAAB) must concur in the facility's readiness to receive waste. This action, designated in DOE Order 4700.1 as Key Decision Four, concludes with the Chairman of the ESAAB issuing a Record of Decision. Since the meeting leading to the Record of Decision is scheduled for August 1988, plans must be made to ensure all activities contributing to that decision are completed in a clear and well-coordinated process. To support that effort, this Start-Up Plan was prepared to identify and track key events necessary to verify WIPP's readiness to receive waste; this provides a management/scheduling/tracking tool for the DOE WIPP Project Office (WPO) and a tracking mechanism for the DOE Albuquerque Operations Office (DOE-AL) and for DOE Headquarters (DOE-HQ); and describe the process to ensure readiness is documented by providing relevant data and reports to the cognizant decision makers. The methods by which these two purposes are achieved are discussed in further detail in the remainder of this plan

The outline of clearance plan for Rokkasho uranium enrichment plant

International Nuclear Information System (INIS)

Kojima, Takuo; Sasaki, Hitoshi; Shouno, Shuuzou; Nozawa, Kenji

2011-01-01

Japan Nuclear Fuel Limited (JNFL) started operation of uranium enrichment by metal cylinder centrifuge at Rokkasho Uranium Enrichment Plant in 1992. Since operation start, JNFL has extended the plant capacity sequentially, but metal cylinder centrifuges ceased operation gradually with time. Replacement to advanced centrifuge is under construction now. Generally, Uranium Enrichment Plant continues operation by replacing centrifuges after a certain period of operation. So, many used centrifuges (metal waste) are generated through the operation period. JNFL is now considering the disposal plan. We can reduce the radioactivity level that is not necessary to treat as the radioactive waste by decontaminating the radioactive material sticking to the surface of metal materials of used centrifuge. And JNFL plants to recycle (reuse) metal material by making much of the clearance system. (author)

Analysis of human factor aspects in connection with available incident reports obligatorily reported by German nuclear power plants

International Nuclear Information System (INIS)

Wilpert, B.; Freitag, M.; Miller, R.

1993-01-01

Goal of the present study is the analysis of human factor aspects in connection with available incident reports obligatorily reported by German nuclear power plants. Based on psychological theories and empirical studies this study develops a classification scheme which permits the identification of foci of erroneous human actions. This classification scheme is applied to a selection of human factor relevant incidents by calculating frequencies of the occurrence of human error categories. The results allow insights into human factor related problem areas. (orig.) [de

Emergency-control planning in the vicinity of large-scale technical plants

International Nuclear Information System (INIS)

Lindackers, K.H.

1982-01-01

In 7 theses, the author shows the most important aspects of disaster control planning: 1) The planning of disaster control measures should not be the object of a licencing procedure. 2) On site allocation or planned determination of sites for potentially hazardous plants it shall be examined whether disaster control measures can be performed sufficiently. 3) Planning of disaster control measures must not be based on detailed accident scenarios. 4) It should be limited to a few day's duration after the accident has occurred. 5) Special attention should be dedicated to the problems of - information and communications, - decision-taking procedures and translation of decicions into action, - practical realization of measures. 6) The bodies charged with planning and implementation must have appropriate personnel and material. 7) Only adequate exercises can guarantee planned disaster control measures to engage under conditions of severity. (HSCH) [de

A nuclear power plant certification test plan and checklist

International Nuclear Information System (INIS)

Halverson, S.M.

1989-01-01

Regulations within the nuclear industry are requiring that all reference plant simulators be certified prior to or during 1991. A certification test plan is essential to ensure that this goal is met. A description of each step in the certification process is provided in this paper, along with a checklist to help ensure completion of each item

The spill prevention, control, and countermeasures (SPCC) plan for the Y-12 Plant

International Nuclear Information System (INIS)

1992-08-01

This spill prevention, control and countermeasures (SPCC) Plan is divided into two volumes. Volume I addresses Y-12's compliance with regulations pertinent to the content of SPCC Plans. Volume II is the SPCC Hazardous Material Storage Data Base, a detailed tabulation of facility-specific information and data on potential spill sources at the Y-12 Plant. Volume I follows the basic format and subject sequence specified in 40 CFR 112.7. This sequence is prefaced by three additional chapters, including this introduction and brief discussions of the Y-12 Plant's background/environmental setting and potential spill source categories. Two additional chapters on containers and container storage areas and PCB and PCB storage for disposal facilities are inserted into the required sequence. The following required subjects are covered in this volume: Spill history, site drainage; secondary containment/diversion structures and equipment; contingency plans; notification and spill response procedures; facility drainage; bulk storage tanks; facility transfer operations, pumping, and in-plant processes; transfer stations (facility tank cars/tank tracks); inspections and records; security, and personnel, training, and spill prevention procedures

Amendment to the Decree of the Slovak Nuclear Regulatory Authority on details concerning emergency planning in case of nuclear incident or accident

International Nuclear Information System (INIS)

Biharyová, Michaela

2018-01-01

Following up amendment to the Slovak Atomic Act, the Decree No. 55/2006 on details concerning emergency planning in case of nuclear incident or accident has also been amended now. Following a short introductory text by the author, the entire text of the ‘Decree of the Nuclear Regulatory Authority of the Slovak Republic No 9/2018 Coll. of 2 January 2018 amending Decree of the Nuclear Regulatory Authority of the Slovak Republic No 55/2006 Coll. on details in emergency planning in case of nuclear incident or accident as amended by Decree No. 35/2012 Coll.’ is reproduced. The Amendment entered into force 1 February 2018. (orig.)

Identification of potential safety-related incidents applicable to a breeder fuel reprocessing plant

International Nuclear Information System (INIS)

Perkins, W.C.

1980-01-01

The current emphasis on safety in all phases of the nuclear fuel cycle requires that safety features be identified and included in designs of nuclear facilities at the earliest possible stage. A popular method for the early identification of these safety features is the Preliminary Hazards Analysis. An extension of this analysis is to illustrate the nature of a hazard by its effects in accident situations, that is, to identify what are called safety-related incidents. Some useful tools are described which have been used at the Savannah River Laboratory, SRL, to make Preliminary Hazards Analyses as well as safety analyses of facilities for processing spent nuclear fuels from both power and production reactors. These tools have also been used in safety studies of waste handling operations at the Savannah River Plant. The tools are the SRL Incidents Data Bank and the What If meeting. The application of this methodology to a proposed facility which has breeder fuel reprocessing capability, the Hot Experimental Facility (HEF) is illustrated

Incidence and physical properties of PSE chicken meat in a commercial processing plant

Directory of Open Access Journals (Sweden)

RG Garcia

2010-12-01

Full Text Available It is known that PSE meat present important functional defects, such as low water holding capacity and ultimate pH, which may compromise the quality of further-processed meat products. In this study, L* (lightness, a* (redness, and b* (yellowness values of 500 chicken breast fillets were determined using a portable colorimeter (Minolta, model CR-400 in a commercial processing plant. Fillets were considered pale when their L* was >49. Out of those samples, 30 fillets with normal color and 30 pale fillets were evaluated as to pH, drip loss, cooking loss, water holding capacity, shear force, and submitted to sensorial analysis. An incidence of 10.20% PSE meat was determined. Pale and normal fillets presented significantly different (p0.05 between pale and normal fillets. Despite the significant differences in meat physical properties, these were not perceived by consumers in terms of tenderness, aspect, and flavor. The observed incidence of PSE may cause losses due to its low water retention capacity.

Incident Management: Process into Practice

Science.gov (United States)

Isaac, Gayle; Moore, Brian

2011-01-01

Tornados, shootings, fires--these are emergencies that require fast action by school district personnel, but they are not the only incidents that require risk management. The authors have introduced the National Incident Management System (NIMS) and the Incident Command System (ICS) and assured that these systems can help educators plan for and…

RETRAN code analysis of Tsuruga-2 plant chemical volume control system (CVCS) reactor coolant leakage incident

International Nuclear Information System (INIS)

Kawai, Hiroshi

2002-01-01

In the Chemical Volume Control System (CVCS) reactor primary coolant leakage incident, which occurred in Tsuruga-2 (4-loop PWR, 3,423 MWt, 1,160 MWe) on July 12, 1999, it took about 14 hours before the leakage isolation. The delayed leakage isolation and a large amount of leakage have become a social concern. Effective procedure modification was studied. Three betterments were proposed based on a qualitative analysis to reduce the pressure and temperature of the primary loop as fast as possible by the current plant facilities while maintaining enough subcooling of the primary loop. I analyzed the incident with RETRAN code in order to quantitatively evaluate the leakage reduction when these betterments are adopted. This paper is very new because it created a typical analysis method for PWR plant behavior during plant shutdown procedure which conventional RETRAN transient analyses rarely dealt with. Also the event time is very long. To carry out this analysis successfully, I devised new models such as an Residual Heat Removal System (RHR) model etc. and simplified parts of the conventional model. Based on the analysis results, I confirmed that leakage can be reduced by about 30% by adopting these betterments. Then the Japan Atomic Power Company (JAPC) modified the operational procedure for reactor primary coolant leakage events adopting these betterments. (author)

Long-term capital planning considering nuclear plant life-cycle management

International Nuclear Information System (INIS)

Negin, C.A.; Simpson, J.M.; Hostetler, D.R.

1992-09-01

The creation of a Life Cycle Management (LCM) group at utilities to evaluate the long term capital refurbishment needs is gaining favor. Among the functions of such groups can be the responsibility for recommending long term capital planning projects based on results of evaluations of systems, structures, and components that are not only essential to achieving the full current license term of operation, but also to extend the service life of the plant. Making such recommendations, in content and timing, requires the ability to view all recommendations in the context of an overall capital budget and long range outage impacts. This report illustrates an approach for creating a Long-Term Capital Plan with methods for deciding on, compiling, integrating, and presenting projects from the perspective of an LCM program for a nuclear power plant. It also addresses a rationale for capitalization of LCM program activities that would not be allowed under current accounting treatment

An integrated reliability management system for nuclear power plants

International Nuclear Information System (INIS)

Kimura, T.; Shimokawa, H.; Matsushima, H.

1998-01-01

The responsibility in the nuclear field of the Government, utilities and manufactures has increased in the past years due to the need of stable operation and great reliability of nuclear power plants. The need to improve the reliability is not only for the new plants but also for those now running. So, several measures have been taken to improve reliability. In particular, the plant manufactures have developed a reliability management system for each phase (planning, construction, maintenance and operation) and these have been integrated as a unified system. This integrated reliability management system for nuclear power plants contains information about plant performance, failures and incidents which have occurred in the plants. (author)

Systematic safety evaluation of old nuclear power plants

International Nuclear Information System (INIS)

Dredemis, G.; Fourest, B.

1984-01-01

The French safety authorities have undertaken a systematic evaluation of the safety of old nuclear power plants. Apart from a complete revision of safety documents (safety analysis report, general operating rules, incident and accident procedures, internal emergency plan, quality organisation manual), this examination consisted of analysing the operating experience of systems frequently challenged and a systematic examination of the safety-related systems. This paper is based on an exercise at the Ardennes Nuclear Power Plant which has been in operation for 15 years. This paper also summarizes the main surveys and modifications relating to this power plant. (orig.)

The link between off-site-emergency planning and plant-internal accident management

Energy Technology Data Exchange (ETDEWEB)

Braun, H.; Goertz, R.

1995-02-01

A variety of accident management measures has been developed and implemented in the German nuclear power plants. They constitute a fourth level of safety in the defence-in-depth concept. The containment venting system is an important example. A functioning link with well defined lines of communication between plant-internal accident management and off-site disaster emergency planning has been established.

IAEA expert review mission completes assessment of fuel cleaning incident at Paks Nuclear Power Plant

International Nuclear Information System (INIS)

2003-01-01

Full text: The IAEA today completed its expert review mission to investigate the 10 April fuel cleaning incident at the Paks nuclear power plant in Hungary. The mission was requested by the Hungarian Government to provide an independent assessment of the causes and actions taken by the plant and Hungarian authorities. The team was composed of nuclear and radiation experts from the IAEA, Austria, Canada, Finland, Slovakia, the United Kingdom and the United States. In a press conference, team leader Miroslav Lipar highlighted the team's findings in five areas: On management, the team concluded that the Hungarian Atomic Energy Authority and Paks are committed to improving the safety of the plant. They noted that as a result of steam generator decontamination in previous years, deposits became attached to the fuel assemblies. A decision was made to clean the fuel and contract an outside company to develop and operate a fuel cleaning process. The team found that the design and operation of the fuel cleaning tank and system was not accomplished in the manner prescribed by the IAEA Safety Standards. Neither the Hungarian Atomic Energy Authority nor Paks used conservative decision-making in their safety assessments for this unproven fuel cleaning system. The team determined that there was an over-reliance on the contractor that had been selected for the design, management and operation of the fuel cleaning system. Time pressure related to a prescribed fuel outage schedule, combined with confidence generated by previous successful fuel cleaning operations, contributed to a weak assessment of a new design and operation, which involved fuel directly removed from the reactor following a planned shutdown. On regulatory oversight, the IAEA team concluded that the Hungarian Atomic Energy Authority underestimated the safety significance of the proposed designs for the fuel cleaning system, which resulted in a less than rigorous review and assessment than should have been necessary

Incidents with hazardous radiation sources

International Nuclear Information System (INIS)

Schoenhacker, Stefan

2016-01-01

Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

The spill prevention, control, and countermeasures (SPCC) plan for the Y-12 Plant. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1992-08-01

This spill prevention, control and countermeasures (SPCC) Plan is divided into two volumes. Volume I addresses Y-12`s compliance with regulations pertinent to the content of SPCC Plans. Volume II is the SPCC Hazardous Material Storage Data Base, a detailed tabulation of facility-specific information and data on potential spill sources at the Y-12 Plant. Volume I follows the basic format and subject sequence specified in 40 CFR 112.7. This sequence is prefaced by three additional chapters, including this introduction and brief discussions of the Y-12 Plant`s background/environmental setting and potential spill source categories. Two additional chapters on containers and container storage areas and PCB and PCB storage for disposal facilities are inserted into the required sequence. The following required subjects are covered in this volume: Spill history, site drainage; secondary containment/diversion structures and equipment; contingency plans; notification and spill response procedures; facility drainage; bulk storage tanks; facility transfer operations, pumping, and in-plant processes; transfer stations (facility tank cars/tank tracks); inspections and records; security, and personnel, training, and spill prevention procedures.

Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

Energy Technology Data Exchange (ETDEWEB)

Washington TRU Solutions

2002-09-24

U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP.

Controversy still simmers over plan to build plasma-fractionation plant in Nova Scotia.

OpenAIRE

Robb, N

1995-01-01

Controversy still simmers over a plan by the Canadian Red Cross Society and a US biopharmaceutical manufacturer to build a plasma-fractionation plant near Halifax. The unilateral decision to go ahead with the plant was taken as the Krever inquiry into Canada's blood-supply system was holding public hearings across the country. A panel created to evaluate the proposal has supported the fractionation plant, but made additional recommendations concerning product pricing, research and development...

Comparison of Planning, Management and Organizational Aspects of Nuclear Power Plants A1 and V1 Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Stubna, M.; Michal, V., E-mail: Marian.Stubna@vuje.sk, E-mail: V.Michal@iaea.org [VUJE, Inc. Trnava (Slovakia); Daniska, V., E-mail: Daniska@decom.sk [DECOM, Inc. Trnava (Slovakia); Sirota, J., E-mail: Sirota.Jan@javys.sk [JAVYS, Inc. Bratislava, (Slovakia)

2013-08-15

This contribution deals with planning, management and organizational aspects of decommissioning of NPP shut down due to the accident (prototype NPP A1) and NPP shut down after normal operation (NPP V1). The A1 and V1 NPPs are located very close in Bohunice nuclear site however both plants have very different technology and operational history. The preparation of A1 NPP decommissioning strategy and relevant decommissioning plans was long term process, because the plant was shut down after the accident in 1977 and decommissioning was implemented first time in Slovakia with many specific difficulties. The decommissioning planning of V1 NPP was shorter and easier, because the plant was shut down after normal operation, there were lessons learned from the A1 NPP decommissioning planning, available legislation, available financing etc. Development of decommissioning strategies, preparation and planning for decommissioning, development of legislation for decommissioning, management of decommissioning projects and other aspects are described and compared. Lessons learned are formulated on the basis of analysis of past, ongoing and planned decommissioning activities in Slovakia. (author)

National nuclear power plant safety research 2011-2014. SAFIR2014 framework plan

International Nuclear Information System (INIS)

2010-01-01

A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating organisations of the plants and a regulatory body. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. Ministry of employment and the economy appointed a group to write the Framework Plan of the new programme. This report contains a proposal for the general outline of the programme, entitled as SAFIR2014 (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2011-2014, but it is based on safety challenges identified for a longer time span as well. Olkiluoto 3, the new nuclear power plant unit under construction and new decisions-in-principle have also been taken into account in the plan. The safety challenges set by the existing plants and the new projects, as well as the ensuing research needs do, however, converge to a great extent. The research programme is strongly based on the Chapter 7a of the Finnish Nuclear Energy Act. The construction of new power plant units will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The Framework Plan aims to define the important research needs related to the safety

Interesting tools for the cybersecurity plan of a nuclear power plant; Herramientas de utilidad para el plan de Ciberseguridad de una Planta Nuclear

Energy Technology Data Exchange (ETDEWEB)

Pareja, I.; Carrasco, J. A.; Cerro, F. J. del

2012-07-01

The use of digital technologies in monitoring and control systems of nuclear power plants and their connectivity requirements, originate cybersecurity difficulties that should be addressed in a cybersecurity plan. This plan should guide the policies and procedures followed during the design maintenance and operation of the systems inside a nuclear power plant. It also should refer to adequate tools able to reach the established cybersecurity requirements. The combination of Datadiodes and tools for publishing video (like tVGA2web), permit an isolation and remote maintenance in a 100% safety way and their use should be disseminated. In the paper other type of tools useful for nuclear power plants are also mentioned.

Nuclear Plant Aging Research (NPAR) program plan

International Nuclear Information System (INIS)

1991-06-01

A comprehensive Nuclear Plant Aging Research (NPAR) Program was implemented by the US NRC office of Nuclear Regulatory Research in 1985 to identify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants. This is Revision 2 to the Nuclear Plant Aging Research Program Plant. This planes defines the goals of the program the current status of research, and summarizes utilization of the research results in the regulatory process. The plan also describes major milestones and schedules for coordinating research within the agency and with organizations and institutions outside the agency, both domestic and foreign. Currently the NPAR Program comprises seven major areas: (1) hardware-oriented engineering research involving components and structures; (2) system-oriented aging interaction studies; (3) development of technical bases for license renewal rulemaking; (4) determining risk significance of aging phenomena; (5) development of technical bases for resolving generic safety issues; (6) recommendations for field inspection and maintenance addressing aging concerns; (7) and residual lifetime evaluations of major LWR components and structures. The NPAR technical database comprises approximately 100 NUREG/CR reports by June 1991, plus numerous published papers and proceedings that offer regulators and industry important insights to aging characteristics and aging management of safety-related equipment. Regulatory applications include revisions to and development of regulatory guides and technical specifications; support to resolve generic safety issues; development of codes and standards; evaluation of diagnostic techniques; (e.g., for cables and valves); and technical support for development of the license renewal rule. 80 refs., 25 figs., 10 tabs

Combined heat and power production planning in a waste-to-energy plant on a short-term basis

International Nuclear Information System (INIS)

Touš, Michal; Pavlas, Martin; Putna, Ondřej; Stehlík, Petr; Crha, Lukáš

2015-01-01

In many cases, WtE (waste-to-energy) plants are CHP (combined heat and power) producers. They are often integrated into a central heating system and they also export electricity to the grid. Therefore, they have to plan their operation on a long-term basis (months, years) as well as on a short-term basis (hours, days). Simulation models can effectively support decision making in CHP production planning. In general, CHP production planning on a short-term basis is a challenging task for WtE plants. This article presents a simulation based support. It is demonstrated on an example involving a real WtE plant. Most of the models of relevant WtE sub-systems (boilers, steam turbine) are developed using operational data and applying linear regression and artificial neural network technique. The process randomness given mainly by fluctuating heating value of waste leads to uncertainty in a calculation of CHP production and a stochastic approach is appropriate. The models of the sub-systems are, therefore, extended of a stochastic part and Monte-Carlo simulation is applied. Compared to the current planning strategy in the involved WtE plant, the stochastic simulation based planning provides increased CHP production resulting in better net thermal efficiency and increased revenue. This is demonstrated through a comparison using real operational data. - Highlights: • Introduction of a stochastic model of a CHP production in a waste-to-energy plant. • An application of the model for the next day CHP production planning. • Better net thermal efficiency and therefore increased revenue achieved.

HIV incidence in sub-Saharan Africa: a review of available data with implications for surveillance and prevention planning.

Science.gov (United States)

Braunstein, Sarah L; van de Wijgert, Janneke H H M; Nash, Denis

2009-01-01

HIV incidence estimation is increasingly being incorporated into HIV/AIDS surveillance activities in both resource-rich and developing countries. We conducted a systematic review to assess the availability of HIV incidence data from sub-Saharan Africa. We examined peer-reviewed articles, conference proceedings and technical reports published from 1987-2008. Incidence estimates were classified by country, year, population group, and estimation method (prospective study or the serologic testing algorithm for recent HIV seroconversion; STARHS). Our search yielded HIV incidence estimates for 15 of 44 sub-Saharan African countries, with 57 studies generating 264 unique estimates. Of these, 239 (91%) were obtained via prospective studies, and 25 (9%) via the STARHS method (24 using the BED-CEIA assay). Only five countries reported population-based estimates, and less than two-thirds of studies reported risk factor information. STARHS use increased over time, comprising 20% of estimates since 2006. However, studies that compared STARHS estimates with prospectively observed or modeled estimates often found substantial levels of disagreement, with STARHS often overestimating HIV incidence. Population-based HIV incidence estimates and risk factor information in sub-Saharan Africa remain scant but increasingly available. Regional STARHS data suggest a need for further validation prior to widespread use and incorporation into routine surveillance activities. In the meantime, prevalence and behavioral risk factor data remain important for HIV prevention planning.

Plant life extension program for Indian PHWR power plants - Actual experience and future plans

International Nuclear Information System (INIS)

Sharma, M.B.; Ghoshal, B.; Shirolkar, K.M.; Ahmad, S.N.

2002-01-01

Full text: The Nuclear Power Corporation of India Limited (NPCIL) is responsible for design, construction and operation for all nuclear power plants in India. Currently, it has fourteen (14) reactor units under operation and another eight units are under various stages of planning and construction. India has adopted Pressurised Heavy Water Reactors (PHWRs) for the initial phase of its nuclear power program. In the earlier PHWRs zircaloy-2 has been used as coolant tube material. Subsequent studies and experience have shown their life to be considerably lower (about 10 full power years) than originally estimated. This meant that reactors at Rajasthan - 1 and 2 Madras - 1 and 2 Narora - 1 and 2 and Kakrapara-1 would require en-masse coolant channel replacement at least once in their lifetime. Subsequent reactors from Kakrapara-2 onwards would not need this en-masse coolant channel replacement as the coolant tube material has been upgraded to Zr 2.5% Nb. En-masse coolant channel replacement and other life extension work have been carried out successfully in Rajasthan Unit-2 (RAPS-2). Madras unit-2 (MAPS-2) has been shutdown since January 2002 and preparatory work for en-masse coolant channel replacement and plant life extension is in progress. This paper discusses in brief the experience of RAPS-2 in carrying out the above jobs as well as the strategies being adopted for MAPS-2. Since the coolant channel replacement work requires a plant outage of about 18 months, this opportunity is used to extend life of existing systems as well as upgradation work. This life extension and upgradation program is based on the results of detailed in service inspection, evaluation of performance of critical equipment, obsolescence and other strategic reasons. This paper discusses in detail some of the major areas of work done, for example introduction of supplementary control room, process control, computer based plant information and event analysis systems, provision of enhanced

Influência de sistemas de plantio e armadilha adesiva na incidência de Frankliniella williamsi Hood na cultura do milho = Influence of planting systems and adhesive trap on the incidence of Frankliniella williamsi Hood in crop maize

Directory of Open Access Journals (Sweden)

Fernando Alves de Albuquerque

2006-07-01

Full Text Available Esta pesquisa objetivou avaliar a influência de diferentes sistemas de plantio de milho e o efeito de armadilha adesiva na incidência de Frankliniella williamsi Hood. Os tratamentos consistiram no plantio direto do milho sobre aveia dessecada com glyphosate, aveia tombada, aveia roçada e plantas daninhas, aveia incorporada e plantio convencional. Alguns tratamentos foram associados a armadilha adesiva de coloração azul, colocada horizontalmente no centro da parcela. Verificou-se que tanto a presença de armadilha quanto os diferentes sistemas de plantio influíram significativamente na infestação das plantas de milho pelo tripes, sendo que os tratamentos “aveia dessecada” e “aveia roçada e plantas daninhas” apresentaram menor incidência do inseto, com esse efeito diminuindo com o desenvolvimento das plantas.This research aimed to evaluate the influence of different systems of corn planting and the effect of adhesive trap on the incidence ofFrankliniella williamsi. The treatments consisted of sowing the corn seed directly on oats dried by glyphosate, tilt oats, cut oats and weeds, incorporated oats, and also conventional planting. Some treatments were associated with adhesive trap of blue coloration, puthorizontally in the center of the plot. Results showed that the presence of traps, as well as the different planting systems influenced significantly on the thrips infestation, and the treatmentswith "dry oats" and "cut oats and weeds" presented smaller incidence of the insect with a decreasing effect along the plants growth.

Environmental Restoration Site-Specific Plan for the Paducah Gaseous Diffusion Plant, FY 93

International Nuclear Information System (INIS)

1993-01-01

This report provides an overview of the major Environmental Restoration (ER) concerns at Paducah Gaseous Diffusion Plant (PGDP). The identified solid waste management units at PGDP are listed. In the Department of Energy (DOE) Five Year Plan development process, one or more waste management units are addressed in a series of activity data sheets (ADSs) which identify planned scope, schedule, and cost objectives that are representative of the current state of planned technical development for individual or multiple sites

The human factor in high-tech plant operation

Energy Technology Data Exchange (ETDEWEB)

Grassani, E

1988-02-01

The article develops a series of considerations on reliability standards applied to operators of technologically complex industrial installations. From research conducted within the field of cognitive psychology, significant indications are emerging relative to professional training within industry, as well as to the functional and human interface characteristics of automated control systems. Recent tragic incidents (Three Mile Island nuclear power plant, Bopal methyl isocynate storage, Mexico City petroleum tank farm and Chernobylsk-4 reactor) have evidenced the greater weight that should be given to human factors in plant safety and reliability assessments and planning.

Facility Effluent Monitoring Plan for the 284-E and 284-W power plants

International Nuclear Information System (INIS)

Herman, D.R.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The 284-E and 284-W Power Plants are coal-fired plants used to generate steam. Electricity is not generated at these facilities. The maximum production of steam is approximately 159 t (175 tons)/h at 101 kg (225 lb)/in 2 . Steam generated at these facilities is used in other process facilities (i. e., the B Plant, Plutonium-Uranium Extraction Plant, 242-A Evaporator) for heating and process operations. The functions or processes associated with these facilities do not have the potential to generate radioactive airborne effluents or radioactive liquid effluents, therefore, radiation monitoring equipment is not used on the discharge of these streams. The functions or processes associated with the production of steam result in the use, storage, management and disposal of hazardous materials

The incident guidelines for nuclear power stations of the FRG - an example illustrating the degradation of safety standards for nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

The 'Guidelines for the Assessment of the Design of Nuclear Power Plants Against Incidents', i.e. the Federal German Incident Guidelines, have been the subject of an official hearing of experts before the Committee of Internal Affairs of the German Bundestag on February 22, 1984. The report in hand presents the official invitation to the meeting, the list of questions posed, written statements given by critics, and an appendix with the full text of the Incident Guidelines, as of August 12, 1983. (orig./HP) [de

An Economic Evaluation on Replacement Plan for Aged Thermal Power Plants through a Real Option Approach

Science.gov (United States)

Kato, Moritoshi; Zhou, Yicheng

This paper presents a novel method to evaluate replacement plan for aged thermal power plants under uncertain circumstances through a real option approach. The most economical plan is selected among the three options: an option to operate an existing oil-fired thermal plant, an option to mothball it, and an option to abandon it and to construct an advanced gas combined cycle power plant (ACC) at the same time. Basic ideas of our model are: we use quadranomial approach in order to evaluate an option value consisted by two different uncertain assets; we consider cash flow with a dividend in order to reflect conditions of an aged oil-fired thermal plant and use the sequential compound option approach; we evaluate replacement time using quadranomial decision tree taking into account the options. We also analyze value and time of replacement using numerical examples. Our proposed method will be practically used for generation planning. For example it is possible to make priority quantitatively in replacements of aged thermal power plants by real option values. The target year of replacement may be set as a year when cumulative probability of replacement becomes over certain level.

The nuclear industry's plan to achieve new nuclear power plant orders in the 1990's

International Nuclear Information System (INIS)

Bayne, P.

1993-01-01

Since the Arab Oil Embargo of 1973, there has been a direct relationship between the growth in the Gross Domestic Product and the growth in the use of electricity in the United States. That close relationship between economic growth and electricity will continue. If that is true, the United States Department of Energy says this country will need between 190,000 to 275,000 megawatts of new generating capacity in the next 20 years. Electricity is one of the cleanest and most efficient uses of energy. Of all the ways to generate electricity, nuclear power plants are the cleanest, producing no air pollution and no greenhouse gases. To help supply the needed increase in electricity generating capacity, the US nuclear power industry has developed a Strategic Plan for Building New Nuclear Power Plants. The plan identified fourteen issues which must be dealt with to create the conditions under which utilities could place orders for new nuclear plants by the mid-1990's. The plan was published in November of 1990 and significant progress has been made on most of the fourteen issues. The plan and progress made are reviewed in depth

Planning of a Quadgeneration power plant for Jammerbugt energy system

DEFF Research Database (Denmark)

Rudra, Souman; Hoffmann, Jessica; Rosendahl, Lasse

2011-01-01

Quadgeneration is the simultaneous production of power, heat and cooling and different fuels from flexible feedstocks such as biomass, waste, refinery residue etc. In order to accommodate more renewable energy into the energy system, it is extremely necessary to develop new flexible power plants...... of some equipments in the Quadgeneration power plant. This paper presents two models for the investment planning of a Quadgeneration energy system in Jammerbugt municipality, and uses these models for different case studies addressing the system for production of heat, cooling, liquid fuels...... that can quickly increase or decrease the production of electricity. Such plants should be ultra flexible in terms of production and able to run on many different types of fuels, with one of its major outputs being liquid fuels for the transport sector. The aim of this paper is to integrate district...

77 FR 76065 - Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for Kendall Warm...

Science.gov (United States)

2012-12-26

...] Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for Kendall Warm Springs Dace... revised recovery plan for the Kendall Warm Springs dace (Rhinichthys osculus thermalis). This species is... recovery plan. The Kendall Warm Springs dace (Rhinichthys osculus thermalis), found only in one location in...

Development and planning of plant for the high-pressure extraction of natural products

Energy Technology Data Exchange (ETDEWEB)

Eggers, R; Tschiersch, R [Thyssen Industrie A.G., Witten (Germany, F.R.)

1978-11-01

Important criteria in the designing of plant for the recovery of carrier or extract are reviewed, especially for the extraction of natural products with supercritical CO/sub 2/. The quantities to be determined in the planning of a large-scale plant are outlined and a typical process, the extraction of spices, is discussed in detail. The plant components and assemblies are presented together with their particular process engineering and construction characteristics. Finally, the thermodynamic aspects are dealt with in more detail and ways of optimizing a large-scale plant and reducing the power consumption are outlined. Particular attention is paid to the question of optimization regarding the most economic method of operation of such a plant in the future.

Combined photogrammetry and 3-D CAD for plant documentation and planning of refits

International Nuclear Information System (INIS)

Fraas, K.C.; Giese, U.; Kamsties, K.D.

1991-01-01

Meticulous advance planning and erection studies using a three-dimensional computer-aided design model of the plant area concerned can reduce the problem that unexpected events during a plant refit will prolong the required inspection period. This presupposes that a 3-D CAD scale model of the running plant has been generated. A method is described with which the as-built condition of the plant area is converted into a 3-D CAD model by combining photogrammetry with 3-D CAD. The minimum amount of time required for in-plant surveying and the completeness and clarity of results are the special advantages of this method in comparison with other measurement techniques. Selected applications are presented. (orig.) [de

Test phase plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-03-01

The US Department of Energy (DOE) has prepared this Test Phase Plan for the Waste Isolation Pilot Plant to satisfy the requirements of Public Law 102-579, the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act (LWA). The Act provides seven months after its enactment for the DOE to submit this Plan to the Environmental Protection Agency (EPA) for review. A potential geologic repository for transuranic wastes, including transuranic mixed wastes, generated in national-defense activities, the WIPP is being constructed in southeastern New Mexico. Because these wastes remain radioactive and chemically hazardous for a very long time, the WIPP must provide safe disposal for thousands of years. The DOE is developing the facility in phases. Surface facilities for receiving waste have been built and considerable underground excavations (2150 feet below the surface) that are appropriate for in-situ testing, have been completed. Additional excavations will be completed when they are required for waste disposal. The next step is to conduct a test phase. The purpose of the test phase is to develop pertinent information and assess whether the disposal of transuranic waste and transuranic mixed waste in the planned WIPP repository can be conducted in compliance with the environmental standards for disposal and with the Solid Waste Disposal Act (SWDA) (as amended by RCRA, 42 USC. 6901 et. seq.). The test phase includes laboratory experiments and underground tests using contact-handled transuranic waste. Waste-related tests at WIPP will be limited to contact-handled transuranic and simulated wastes since the LWA prohibits the transport to or emplacement of remote-handled transuranic waste at WIPP during the test phase

Storm water pollution prevention plan for the Oak Ridge Y-12 Plant

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Environmental Protection Agency (EPA) published the final storm water regulation on November 16, 1990. The storm water regulation is included in the National Pollutant Discharge Elimination System (NPDES) regulations. An NPDES permit was issued for the Y-12 Plant on April 28, 1995, and was effective on July 1, 1995. The permit requires that a Storm Water Pollution Prevention Plan (SWP3) be developed by December 28, 1995, and be fully implemented by July 1, 1996; this plan has been developed to fulfill that requirement. The outfalls and monitoring points described in this plan contain storm water discharges associated with industrial activities as defined in the NPDES regulations. For storm water discharges associated with industrial activity, including storm water discharges associated with construction activity, that are not specifically monitored or limited in this permit, Y-12 Plant personnel will meet conditions of the General Storm Water Rule 1200-4-10. This document presents the programs and physical controls that are in place to achieve the following objectives: ensure compliance with Section 1200-4-10-.04(5) of the TDEC Water Quality Control Regulations and Part 4 of the Y-12 Plant NPDES Permit (TN0002968); provide operating personnel with guidance relevant to storm water pollution prevention and control requirements for their facility and/or project; and prevent or reduce pollutant discharge to the environment, in accordance with the Clean Water Act (CWA) and the Tennessee Water Quality Control Act.

Storm water pollution prevention plan for the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

1995-09-01

The Environmental Protection Agency (EPA) published the final storm water regulation on November 16, 1990. The storm water regulation is included in the National Pollutant Discharge Elimination System (NPDES) regulations. An NPDES permit was issued for the Y-12 Plant on April 28, 1995, and was effective on July 1, 1995. The permit requires that a Storm Water Pollution Prevention Plan (SWP3) be developed by December 28, 1995, and be fully implemented by July 1, 1996; this plan has been developed to fulfill that requirement. The outfalls and monitoring points described in this plan contain storm water discharges associated with industrial activities as defined in the NPDES regulations. For storm water discharges associated with industrial activity, including storm water discharges associated with construction activity, that are not specifically monitored or limited in this permit, Y-12 Plant personnel will meet conditions of the General Storm Water Rule 1200-4-10. This document presents the programs and physical controls that are in place to achieve the following objectives: ensure compliance with Section 1200-4-10-.04(5) of the TDEC Water Quality Control Regulations and Part 4 of the Y-12 Plant NPDES Permit (TN0002968); provide operating personnel with guidance relevant to storm water pollution prevention and control requirements for their facility and/or project; and prevent or reduce pollutant discharge to the environment, in accordance with the Clean Water Act (CWA) and the Tennessee Water Quality Control Act

Addressing the gap between public health emergency planning and incident response

Science.gov (United States)

Freedman, Ariela M; Mindlin, Michele; Morley, Christopher; Griffin, Meghan; Wooten, Wilma; Miner, Kathleen

2013-01-01

Objectives: Since 9/11, Incident Command System (ICS) and Emergency Operations Center (EOC) are relatively new concepts to public health, which typically operates using less hierarchical and more collaborative approaches to organizing staff. This paper describes the 2009 H1N1 influenza outbreak in San Diego County to explore the use of ICS and EOC in public health emergency response. Methods: This study was conducted using critical case study methodology consisting of document review and 18 key-informant interviews with individuals who played key roles in planning and response. Thematic analysis was used to analyze data. Results: Several broad elements emerged as key to ensuring effective and efficient public health response: 1) developing a plan for emergency response; 2) establishing the framework for an ICS; 3) creating the infrastructure to support response; 4) supporting a workforce trained on emergency response roles, responsibilities, and equipment; and 5) conducting regular preparedness exercises. Conclusions: This research demonstrates the value of investments made and that effective emergency preparedness requires sustained efforts to maintain personnel and material resources. By having the infrastructure and experience based on ICS and EOC, the public health system had the capability to surge-up: to expand its day-to-day operation in a systematic and prolonged manner. None of these critical actions are possible without sustained funding for the public health infrastructure. Ultimately, this case study illustrates the importance of public health as a key leader in emergency response. PMID:28228983

Use of Plan-Do-Study-Act cycles to decrease incidence of neonatal hypothermia in the labor room.

Science.gov (United States)

Shaw, Subhash Chandra; Devgan, Amit; Anila, Sushila; Anushree, Neha; Debnath, Himadri

2018-04-01

Body temperature of a neonate continues to be under-documented, under-recognized, and under-managed, even though studies have shown that neonatal hypothermia increases mortality and morbidity. We aimed to reduce neonatal hypothermia (body temperature improvement (QI) initiative using the rapid-cycle Plan-Do-Study-Act approach (PDSA) improvement model and the project was conducted from 15 Jan 2017 to 25 Feb 2017. All singleton neonates with gestational ages above 34 completed weeks born by vaginal delivery were targeted. Exclusion criteria included neonates needing any form of resuscitation, those developing respiratory distress after birth needing any form of respiratory support or observation in NICU. We ran PDSA cycles (including pre-warmed cloths, skin to skin care with mother, early breast feeding, delaying weight check by 1 h and checklist of planned steps), every week, after taking the baseline data in the first week. A total of 46 neonates were studied. After 4 PDSA cycles, incidence of neonatal hypothermia at 1 h of birth dropped to zero from 50% at baseline and we were able to sustain 100% normal temperature (36.5-37.5 °C) since then. This QI project has significantly reduced the incidence of hypothermia in term and late preterm neonates born by vaginal delivery in our institute.

Outage planning in nuclear power plants. A paradigm shift from an external towards an integrated project planning tool

Energy Technology Data Exchange (ETDEWEB)

Rosemann, Andreas [Gesellschaft fuer integrierte Systemplanung (GiS) mbH, Weinheim (Germany)

2014-05-15

In nuclear power plants it is common to carry out the technical planning of the annual outage work orders in an Enterprise Application Management (EAM) system and to schedule the outage tasks in a project planning tool. The reason for this is historical: Former EAM systems did not (or just to some extend) offer the necessary functionalities to realise the scheduling of the outage; graphical support for the planning was not provided at all. Consequently, scheduling the annual outage was performed in a separate planning tool. Modern Enterprise Application Management (EAM) software builds on established project planning tools with respect to the functionalities and timing of work orders. As a standard they provide editable charts as well as a lot of functionalities which are required for scheduling the annual outage. The functional gap between the demanded planning functionalities and the functionalities provided by the EAM system has been significantly reduced. Depending on the deployed software itself it is possible to extend the EAM system with little effort (in comparison to the promising advantages) so that external project timing planning tools are not required any more. By shifting towards an integrated planning tool, efficiency in planning an outage as well as the quality of communication of the current planning status increases. Furthermore, the basis of information for work orders by the control room staff and therefore safety can be enhanced. (orig.)

Outage planning in nuclear power plants. A paradigm shift from an external towards an integrated project planning tool

International Nuclear Information System (INIS)

Rosemann, Andreas

2014-01-01

In nuclear power plants it is common to carry out the technical planning of the annual outage work orders in an Enterprise Application Management (EAM) system and to schedule the outage tasks in a project planning tool. The reason for this is historical: Former EAM systems did not (or just to some extend) offer the necessary functionalities to realise the scheduling of the outage; graphical support for the planning was not provided at all. Consequently, scheduling the annual outage was performed in a separate planning tool. Modern Enterprise Application Management (EAM) software builds on established project planning tools with respect to the functionalities and timing of work orders. As a standard they provide editable charts as well as a lot of functionalities which are required for scheduling the annual outage. The functional gap between the demanded planning functionalities and the functionalities provided by the EAM system has been significantly reduced. Depending on the deployed software itself it is possible to extend the EAM system with little effort (in comparison to the promising advantages) so that external project timing planning tools are not required any more. By shifting towards an integrated planning tool, efficiency in planning an outage as well as the quality of communication of the current planning status increases. Furthermore, the basis of information for work orders by the control room staff and therefore safety can be enhanced. (orig.)

A quantification of the effectiveness of EPID dosimetry and software-based plan verification systems in detecting incidents in radiotherapy

Energy Technology Data Exchange (ETDEWEB)

Bojechko, Casey; Phillps, Mark; Kalet, Alan; Ford, Eric C., E-mail: eford@uw.edu [Department of Radiation Oncology, University of Washington, 1959 N. E. Pacific Street, Seattle, Washington 98195 (United States)

2015-09-15

Purpose: Complex treatments in radiation therapy require robust verification in order to prevent errors that can adversely affect the patient. For this purpose, the authors estimate the effectiveness of detecting errors with a “defense in depth” system composed of electronic portal imaging device (EPID) based dosimetry and a software-based system composed of rules-based and Bayesian network verifications. Methods: The authors analyzed incidents with a high potential severity score, scored as a 3 or 4 on a 4 point scale, recorded in an in-house voluntary incident reporting system, collected from February 2012 to August 2014. The incidents were categorized into different failure modes. The detectability, defined as the number of incidents that are detectable divided total number of incidents, was calculated for each failure mode. Results: In total, 343 incidents were used in this study. Of the incidents 67% were related to photon external beam therapy (EBRT). The majority of the EBRT incidents were related to patient positioning and only a small number of these could be detected by EPID dosimetry when performed prior to treatment (6%). A large fraction could be detected by in vivo dosimetry performed during the first fraction (74%). Rules-based and Bayesian network verifications were found to be complimentary to EPID dosimetry, able to detect errors related to patient prescriptions and documentation, and errors unrelated to photon EBRT. Combining all of the verification steps together, 91% of all EBRT incidents could be detected. Conclusions: This study shows that the defense in depth system is potentially able to detect a large majority of incidents. The most effective EPID-based dosimetry verification is in vivo measurements during the first fraction and is complemented by rules-based and Bayesian network plan checking.

Sensationalization of reports of the Kashiwazaki-Kariwa nuclear power plant incident. A search for top stories in Japanese newspapers

International Nuclear Information System (INIS)

Nakajima, Tatsuo

2009-01-01

The purpose of this study is to clarify whether reports of nuclear accidents, particularly the damage done by the 2007 Niigata-ken Chuetsu-Oki earthquake to the Kashiwazaki-Kariwa nuclear power plant in Niigata, Japan, tend to be exaggerated by national media. News related to the Kashiwazaki incident was compared with that for nine other high-profile accidents in Japan, including the 1999 JCO critical accident and the 2005 JR-West Fukuchiyama Line derailment. Articles were extracted from four national newspapers in Japan, focusing on the 30 issues immediately following each accident. The numbers of articles and top stories related to the relevant accidents appearing on the front pages of the newspapers were counted. Based on these numbers, the Kashiwazaki incident was reported at a level similar to the JCO accident and Fukuchiyama line derailment in some newspapers, although these two accidents were more serious than the Kashiwazaki incident. This suggests that at least some newspapers in Japan sensationalized reports of the Kashiwazaki incident. (author)

Planning and architectural safety considerations in designing nuclear power plants

International Nuclear Information System (INIS)

Konsowa, Ahmed A.

2009-01-01

To achieve optimum safety and to avoid possible hazards in nuclear power plants, considering architectural design fundamentals and all operating precautions is mandatory. There are some planning and architectural precautions should be considered to achieve a high quality design and construction of nuclear power plant with optimum safety. This paper highlights predicted hazards like fire, terrorism, aircraft crash attacks, adversaries, intruders, and earthquakes, proposing protective actions against these hazards that vary from preventing danger to evacuating and sheltering people in-place. For instance; using safeguards program to protect against sabotage, theft, and diversion. Also, site and building well design focusing on escape pathways, emergency exits, and evacuation zones, and the safety procedures such as; evacuation exercises and sheltering processes according to different emergency classifications. In addition, this paper mentions some important codes and regulations that control nuclear power plants design, and assessment methods that evaluate probable risks. (author)

Waste Isolation Pilot Plant Environmental Monitoring Plan

International Nuclear Information System (INIS)

2004-01-01

U.S. Department of Energy (DOE) Order 450.1, Environmental Protection Program, requires each DOE site to conduct environmental monitoring. Environmental monitoring at the Waste Isolation Pilot Plant (WIPP) is conducted in order to: (a) Verify and support compliance with applicable federal, state, and local environmental laws, regulations, permits, and orders; (b) Establish baselines and characterize trends in the physical, chemical, and biological condition of effluent and environmental media; (c) Identify potential environmental problems and evaluate the need for remedial actions or measures to mitigate the problem; (d) Detect, characterize, and report unplanned releases; (e) Evaluate the effectiveness of effluent treatment and control, and pollution abatement programs; and (f) Determine compliance with commitments made in environmental impact statements, environmental assessments, safety analysis reports, or other official DOE documents. This Environmental Monitoring Plan (EMP) has been written to contain the rationale and design criteria for the monitoring program, extent and frequency of monitoring and measurements, procedures for laboratory analyses, quality assurance (QA) requirements, program implementation procedures, and direction for the preparation and disposition of reports. Changes to the environmental monitoring program may be necessary to allow the use of advanced technology and new data collection techniques. This EMP will document any proposed changes in the environmental monitoring program. Guidance for preparation of Environmental Monitoring Plans is contained in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance. The plan will be effective when it is approved by the appropriate Head of Field Organization or their designee. The plan discusses major environmental monitoring and hydrology activities at the WIPP and describes the programs established to ensure that WIPP operations do not

Program for accident and incident management support, AIMS

International Nuclear Information System (INIS)

Putra, M.A.

1993-12-01

A prototype of an advisory computer program is presented which could be used in monitoring and analyzing an ongoing incident in a nuclear power plant. The advisory computer program, called the Accident and Incident Management Support (AIMS), focuses on processing a set of data that is to be transmitted from a nuclear power plant to a national or regional emergency center during an incident. The AIMS program will assess the reactor conditions by processing the measured plant parameters. The applied model of the power plant contains a level of complexity that is comparable with the simplified plant model that the power plant operator uses. A standardized decay heat function and a steam water property library is used in the integral balance equations for mass and energy. A simulation of the station blackout accident of the Borssele plant is used to test the program. The program predicts successively: (1) the time of dryout of the steam generators, (2) the time of saturation of the primary system, and (3) the onset of core uncovery. The coolant system with the actual water levels will be displayed on the screen. (orig./HP)

Criteria and Planning Guidance for Ex-Plant Harvesting to Support Subsequent License Renewal

Energy Technology Data Exchange (ETDEWEB)

Ramuhalli, Pradeep [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Devanathan, Ram [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Meyer, Ryan M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Glass, Samuel W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Knobbs, Katherine J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-12-07

As U.S. nuclear power plants look to subsequent license renewal (SLR) to operate for a 20-year period beyond 60 years, the U.S. Nuclear Regulatory Commission and the industry will be addressing technical issues around the capability of long-lived passive components to meet their functionality objectives. A key challenge will be to better understand likely materials degradation mechanisms in these components and their impacts on component functionality and margins to safety. Research addressing many of the remaining technical gaps in these areas for SLR may greatly benefit from materials sampled from plants (decommissioned or operating). Because of the cost and inefficiency of piecemeal sampling, there is a need for a strategic and systematic approach to sampling materials from structures, systems, and components (SSC) in both operating and decommissioned plants. This document describes a potential approach for sampling (harvesting) materials that focuses on prioritizing materials for sampling using a number of criteria. These criteria are based on an evaluation of technical gaps identified in the literature, research needs to address these technical gaps, and lessons learned from previous harvesting campaigns. The document also describes a process for planning future harvesting campaigns; such a plan would include an understanding of the harvesting priorities, available materials, and the planned use of the materials to address the technical gaps.

Augmented reality for improved communication of construction and maintenance plans in nuclear power plants

International Nuclear Information System (INIS)

Sorensen, Soren S.

2010-01-01

The purpose of implementing Augmented Reality, AR, in the planning, construction and maintenance of Nuclear Power Plants is to secure strict control, precise and correct constructions, exact execution of assignments and heightened safety at all levels. Communication of construction plans to ensure precise and correct assembly of structural elements is essential in all building projects. This is especially crucial in the construction of nuclear plants and installation of new components. The current ways in which construction plans are communicated, blueprints, 3D digital models and written descriptions all embody the need for significant levels of abstraction and interpretation, and are thus both difficult to understand and can lead to misinterpretations. A simulation system with full scale three dimensional models experienced in the physical setting where operations are to take place would bring operators closer to the real life assignments. Augmented Reality is a visualization technology that provides this motivation. (author)

Planning study and economic feasibility for extended life operation of light water reactor plants

International Nuclear Information System (INIS)

Negin, C.A.; Goudarzi, L.A.; Kenworthy, L.U.; Lapides, M.E.

1980-01-01

The purpose of this planning study was to perform an assessment of the engineering and economic feasibility of extended life operation of present nuclear power plant units and to recommend future programs that may be warranted by the feasibility assessments. This effort concludes, essentially, that there is sufficient economic motivation for refurbishment to warrant more extensive examination for present plants and to identify possible design modifications that would facilitate extended service life in future plants. The costs of replacing the deterioration-prone equipment in a nuclear power plant appear to represent a small portion of the total plant costs, provided downtime is not excessive. A refurbishment and economic analysis is presented

Development and application of the methodology to establish life extension and modernization plan of aged hydropower plants

International Nuclear Information System (INIS)

Kim, Jong Sung; Kwon, Hyuck Cheon; Song, Byung Hun; Kwon, Chang Seop

2009-01-01

This paper provides how to establish an integrated plan for LE (Life Extension) and MD (MoDernization) of aged hydropower plants. The methodology is developed through review of overseas/domestic LE/MD histories, investigation of the previous overseas methodologies and consideration of domestic practices. The methodology includes reviews of the various factors such as condition, operation and maintenance history, up-to-date technology, and economic benefit. In order to establish the life extension/modernization plan, the methodology is applied to the domestic aged hydropower plants. Finally, priority rankings and draft practice plans for LE/MD are derived.

Industrial Fuel Gas Demonstration Plant Program. Task III, Demonstration plant safety, industrial hygiene, and major disaster plan (Deliverable No. 35)

Energy Technology Data Exchange (ETDEWEB)

None

1980-03-01

This Health and Safety Plan has been adopted by the IFG Demonstration Plant managed by Memphis Light, Gas and Water at Memphis, Tennessee. The plan encompasses the following areas of concern: Safety Plan Administration, Industrial Health, Industrial Safety, First Aid, Fire Protection (including fire prevention and control), and Control of Safety Related Losses. The primary objective of this plan is to achieve adequate control of all potentially hazardous activities to assure the health and safety of all employees and eliminate lost work time to both the employees and the company. The second objective is to achieve compliance with all Federal, state and local laws, regulations and codes. Some thirty specific safe practice instruction items are included.

Improved Management of Part Safety Classification System for Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Park, Jin Young; Park, Youn Won; Park, Heung Gyu; Park, Hyo Chan [BEES Inc., Daejeon (Korea, Republic of)

2016-10-15

As, in recent years, many quality assurance (QA) related incidents, such as falsely-certified parts and forged documentation, etc., were reported in association with the supply of structures, systems, components and parts to nuclear power plants, a need for a better management of safety classification system was addressed so that it would be based more on the level of parts . Presently, the Korean nuclear power plants do not develop and apply relevant procedures for safety classifications, but rather the safety classes of parts are determined solely based on the experience of equipment designers. So proposed in this paper is a better management plan for safety equipment classification system with an aim to strengthen the quality management for parts. The plan was developed through the analysis of newly introduced technical criteria to be applied to parts of nuclear power plant.

Safety and regulatory requirements of nuclear power plants

International Nuclear Information System (INIS)

Kumar, S.V.; Bhardwaj, S.A.

2000-01-01

A pre-requisite for a nuclear power program in any country is well established national safety and regulatory requirements. These have evolved for nuclear power plants in India with participation of the regulatory body, utility, research and development (R and D) organizations and educational institutions. Prevailing international practices provided a useful base to develop those applicable to specific system designs for nuclear power plants in India. Their effectiveness has been demonstrated in planned activities of building up the nuclear power program as well as with unplanned activities, like those due to safety related incidents etc. (author)

Reduction of mercury in plant effluents data management implementation plan FY 1998 Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Fischer, K.N.; Forsberg, V.M.

1998-01-01

The purpose of the Data Management Implementation Plan (DMIP) is to document the requirements and responsibilities for managing, using, and archiving data used for the Reduction of Mercury in Plant Effluents (RMPE) project. The DMIP was created for the RMPE project in accordance with the guidance given in Environmental Data Management Implementation Handbook for the Environmental Restoration Program (ES/ER/TM- 88/R 1) and in ''Developing, implementing, and Maintaining Data Management Implementation Plans'' (EMEF/ER-P2216, Rev. 0). This document reflects the state of the RMPE project and the types of environmental monitoring planned as they existed through March 16, 1998. The scope of this document is the management of the RMPE project's environmental information, which includes electronic or hard copy records describing environmental processes or conditions. The RMPE program was established as a best management practice to address sources in the Y-12 Plant that contribute mercury to plant effluents being discharged to Upper East Fork Poplar Creek. The strategy is multifaceted: reroute clean water through clean conduits; clean, reline, and/or replace mercury-contaminated water conduits; eliminate or reduce accumulations of mercury in tanks and sumps; isolate inaccessible mercury from contact with water; and install treatment capability for streams where the source(s) cannot be eliminated or mitigated to acceptable levels. The RMPE project database consists of data from surface water monitoring and sediment sampling at locations of interest within the Y-12 Plant. This DMIP describes the types and sources of RMPE data, other data systems relevant to the RMPE project, the different data management interactions and flow of information involved in processing RMPE data, and the systems used in data management

Radioactive waste management plan for the PBMR (Pty) Ltd fuel plant

International Nuclear Information System (INIS)

Makgae, Mosidi E.

2009-01-01

The Pebble Bed Modular Reactor (Pty) Ltd Fuel Plant (PFP) radioactive waste management plan caters for waste from generation, processing through storage and possible disposal. Generally, the amount of waste that will be generated from the PFP is Low and Intermediate Level Waste. The waste management plan outlines all waste streams and the management options for each stream. It also discusses how the Plant has been designed to ensure radioactive waste minimisation through recycling, recovery, reuse, treatment before considering disposal. Compliance to the proposed plan will ensure compliance with national legislative requirements and international good practice. The national and the overall waste management objective is to ensure that all PFP wastes are managed appropriately by utilising processes that minimize, reduce, recover and recycle without exposing employees, the public and the environment to unacceptable impacts. Both International Atomic Energy Agency (IAEA) and Department of Minerals and Energy (DME) principles act as a guide in the development of the strategy in order to ensure international best practice, legal compliance and ensuring that the impact of waste on employees, environment and the public is as low as reasonably achievable. The radioactive waste classification system stipulated in the Radioactive Waste Management Policy and Strategy 2005 will play an important role in classifying radioactive waste and ensuring that effective management is implemented for all waste streams, for example gaseous, liquid or solid wastes.

Project of Particular intervention plan of the Belleville-sur-Loire NPP. Special provisions of the ORSEC plan

International Nuclear Information System (INIS)

2015-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the project of Particular intervention plan for the Belleville-sur-Loire Nuclear Power Plant (Cher, France)

Particular intervention plan of the Saint Alban-Saint Maurice l'Exil Nuclear Power Plant

International Nuclear Information System (INIS)

2010-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Saint Alban-Saint Maurice NPP (Isere, France)

Comparison of the incidence of Listeria on equipment versus environmental sites within dairy processing plants.

Science.gov (United States)

Pritchard, T J; Flanders, K J; Donnelly, C W

1995-08-01

This study was undertaken to compare the incidence of Listeria contamination of processing equipment with that of the general dairy processing environment. A total of 378 sponge samples obtained from 21 dairy plants were analyzed for Listeria using three different enrichment media. Use of extended microbiological analysis allowed us to identify 26 Listeria positive sites which would have not been identified had a single test format been employed. Eighty (80) of 378 sites (21.2%) were identified as Listeria positive. Listeria innocua was isolated from 59 of the 80 (73.8%) positive samples, L. monocytogenes was identified in 35 (43.8%) of the positive samples, and L. seeligeri was isolated from 5 (6.3%) of the Listeria positive samples. Positive equipment samples were obtained from 6 of the 21 (28.6%) plants and 19 of the 21 (90.5%) plants had positive environmental sites. Seventeen of the 215 (7.9%) samples from equipment were positive for Listeria species. Eleven of these sites, including 3 holding tanks, 2 table tops, 3 conveyor/chain systems, a pasta filata wheel, a pint milk filler and a brine pre-filter machine, were positive for L. monocytogenes. Nineteen of the 21 (90.5%) plants had positive environmental sites. Sixty-three of the 163 (41.1%) samples from environmental sites were Listeria positive and 24 were positive for L. monocytogenes. Two-tailed student t-test analysis of the mean frequencies indicated that the level of contamination was significantly higher (p plant, and that greater emphasis needs to be placed on the cleaning and sanitizing of the plant environment.

75 FR 57055 - Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for Utah Prairie Dog

Science.gov (United States)

2010-09-17

...] Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for Utah Prairie Dog AGENCY: Fish... recovery plan for the Utah prairie dog (Cynomys parvidens). This species is federally listed as threatened... and peer reviewers in an appendix to the approved recovery plan. The Utah prairie dog (Cynomys...

The Three-Mile Island incident

International Nuclear Information System (INIS)

Davies, L.M.

1979-10-01

A description is given of the engineering design principles of the PWR (Pressurized Water Reactor) of the Three Mile Island-2 power plant. The successive stages of the incident are recounted, with diagrammatic illustrations, and graphs showing the reactor coolant system parameters at various times after the incident. The consequential events and core damage are discussed. (U.K.)

Oak Ridge Y-12 Plant biological monitoring and abatement program (BMAP) plan

Energy Technology Data Exchange (ETDEWEB)

Adams, S.M.; Brandt, C.C.; Cicerone, D.S. [and others

1998-02-01

The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y-12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided, but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas or a reduction in sampling intensity in others. By using the results of previous monitoring efforts to define the current program and to guide them in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions.

Oak Ridge Y-12 Plant biological monitoring and abatement program (BMAP) plan

International Nuclear Information System (INIS)

Adams, S.M.; Brandt, C.C.; Cicerone, D.S.

1998-02-01

The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y-12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided, but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas or a reduction in sampling intensity in others. By using the results of previous monitoring efforts to define the current program and to guide them in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions

A Planning Tool for Estimating Waste Generated by a Radiological Incident and Subsequent Decontamination Efforts - 13569

International Nuclear Information System (INIS)

Boe, Timothy; Lemieux, Paul; Schultheisz, Daniel; Peake, Tom; Hayes, Colin

2013-01-01

Management of debris and waste from a wide-area radiological incident would probably constitute a significant percentage of the total remediation cost and effort. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a unique planning tool for estimating the potential volume and radioactivity levels of waste generated by a radiological incident and subsequent decontamination efforts. The WEST was developed to support planners and decision makers by generating a first-order estimate of the quantity and characteristics of waste resulting from a radiological incident. The tool then allows the user to evaluate the impact of various decontamination/demolition strategies on the waste types and volumes generated. WEST consists of a suite of standalone applications and Esri R ArcGIS R scripts for rapidly estimating waste inventories and levels of radioactivity generated from a radiological contamination incident as a function of user-defined decontamination and demolition approaches. WEST accepts Geographic Information System (GIS) shape-files defining contaminated areas and extent of contamination. Building stock information, including square footage, building counts, and building composition estimates are then generated using the Federal Emergency Management Agency's (FEMA's) Hazus R -MH software. WEST then identifies outdoor surfaces based on the application of pattern recognition to overhead aerial imagery. The results from the GIS calculations are then fed into a Microsoft Excel R 2007 spreadsheet with a custom graphical user interface where the user can examine the impact of various decontamination/demolition scenarios on the quantity, characteristics, and residual radioactivity of the resulting waste streams. (authors)

Waste Isolation Pilot Plant disposal phase supplemental environmental impact statement. Implementation plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

The Implementation Plan for the Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (SEIS-II) has two primary purposes: (1) To report on the results of the scoping process (2) To provide guidance for preparing SEIS-II SEIS-II will be the National Environmental Policy Act (NEPA) review for WIPP`s disposal phase. Chapter 1 of this plan provides background on WIPP and this NEPA review. Chapter 2 describes the purpose and need for action by the Department of Energy (hereafter DOE or the Department), as well as a description of the Proposed Action and alternatives being considered. Chapter 3 describes the work plan, including the schedule, responsibilities, and planned consultations with other agencies and organizations. Chapter 4 describes the scoping process, presents major issues identified during the scoping process, and briefly indicates how issues will be addressed in SEIS-II.

Waste Isolation Pilot Plant disposal phase supplemental environmental impact statement. Implementation plan

International Nuclear Information System (INIS)

1996-05-01

The Implementation Plan for the Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (SEIS-II) has two primary purposes: (1) To report on the results of the scoping process (2) To provide guidance for preparing SEIS-II SEIS-II will be the National Environmental Policy Act (NEPA) review for WIPP's disposal phase. Chapter 1 of this plan provides background on WIPP and this NEPA review. Chapter 2 describes the purpose and need for action by the Department of Energy (hereafter DOE or the Department), as well as a description of the Proposed Action and alternatives being considered. Chapter 3 describes the work plan, including the schedule, responsibilities, and planned consultations with other agencies and organizations. Chapter 4 describes the scoping process, presents major issues identified during the scoping process, and briefly indicates how issues will be addressed in SEIS-II

Oak Ridge Y-12 Plant Biological Monitoring and Abatement Program Plan

Energy Technology Data Exchange (ETDEWEB)

Adams, S.M.; Brandt, C.C.; Christensen, S.W.; Greeley, M.S.JR.; Hill, W.R.; Peterson, M.J.; Ryon, M.G.; Smith, J.G.; Southworth, G.R.; Stewart, A.J.

2000-09-01

The revised Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted as required by the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995 and became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Science Division (ESD) at the Oak Ridge National Laboratory (ORNL) at the request of the Y-12 Plant. The revision to the BMAP plan is based on results of biological monitoring conducted during the period of 1985 to present. Details of the specific procedures used in the current routine monitoring program are provided; experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas (e.g., additional bioaccumulation monitoring if results indicate unexpectedly high PCBs or Hg) or a reduction in sampling intensity in others (e.g., reduction in the number of sampling sites when no impact is still observed). The program scope will be re-evaluated annually. By using the results of previous monitoring efforts to define the current program and to guide us in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of Y-12 Plant operations (past and present) on the biota of EFPC and to document the ecological effects of remedial actions.

The permissibility of power plants and other large-scale projects outside densely populated areas from the point of view of planning legislation

International Nuclear Information System (INIS)

Hoppe, W.

1978-01-01

For the licensing of power plants, nuclear power plants and other industrial large projects, the question of the building law admissibility gains more and more importance in the licensing procedure. According to paragraph 6 of the Fed. Immission Protection, it is not only necessary that immission protection duties of the operator of plants which are subject to licensing are fulfilled, but other public law regulations must be in correspondance with the construction and operation of the plant. In this connection, the planning law admissibility of the project must also be examined. This is also valid for nuclear power plants. In the practical application of licensing such plants are treated in different ways, as far as terms of building planning are concerned. Some licensing authorities regard them as priviledged outskirts projects, others demand a zoning plan of the community. The author pleads for such large projects to be licensed only on the basis of a zoning plan set up by the community. (orig.) [de

Sampling and analysis plan for groundwater and surface water monitoring at the Y-12 Plant during calendar year 1995

International Nuclear Information System (INIS)

1994-10-01

This plan provides a description of the groundwater and surface-water quality monitoring activities planned for calendar year (CY) 1995 at the Department of Energy Y-12 Plant. Included in this plan are the monitoring activities managed by the Y-12 Plant Health, Safety, Environment, and Accountability (HSEA) Organization through the Y-12 Plant Groundwater Protection Program (GWPP). Other groundwater and surface water monitoring activities (e.g. selected Environmental Restoration Program activities, National Pollution Discharge Elimination System (NPDES) monitoring) not managed through the Y-12 Plant GWPP are not addressed in this report. Several monitoring programs will be implemented in three hydrogeologic regimes: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime), and the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Bear Creek and East Fork regimes are located within Bear Creek Valley, and the Chestnut Ridge Regime is located south of the Y-12 Plant. For various reasons, modifications to the 1995 monitoring programs may be necessary during implementation. For example, changes in regulatory requirements may alter the parameters specified for selected wells, or wells could be added to or deleted from the monitoring network. All modifications to the monitoring programs will be approved by the Y-12 Plant GWPP manager and documented as addenda to this sampling and analysis plan

Next Generation Nuclear Plant Methods Technical Program Plan

Energy Technology Data Exchange (ETDEWEB)

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-12-01

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Natural biostimulants reduce the incidence of BER in sweet yellow pepper plants (Capsicum annuum L.

Directory of Open Access Journals (Sweden)

Nada Parađiković

2013-06-01

Full Text Available Modern greenhouse pepper production should evolve towards more sustainable systems. The growing technique which combines soilless culture and biostimulants may reduce nutrient and water use with beneficial impact on the environment. Therefore, this work aimed to investigate effects of biostimulants application on hydroponically produced pepper plants (Capsicum annuum L. in conditions of reduced fertilization. Positive influence of biostimulant treatment on yield parameters was observed along with significant decrease in incidence of blossom-end rot (BER in two pepper cultivars. Biostimulants application resulted in overall increase in macro- and microelement content in fruits of treated pepper cultivars. Generally, biostimulants improved the yield of pepper plants grown hydroponically by increasing the nutrient uptake and decreasing the occurrence of BER. Thus, the application of biostimulants could be considered as a good production strategy for obtaining high yields of nutritionally valuable vegetables with lower impact on the environment.

Using PROGUMBEL to predict extreme external hazards during nuclear power plant construction

International Nuclear Information System (INIS)

Diburg, S.; Hoelscher, N.; Niemann, H.J.; Meiswinkel, R.

2010-01-01

Safety considerations concerning the construction of power plants, supporting structure planning, safety concept and structural design require reliable data on external events, their incidence probability and characteristic parameters. The basis for supporting structure calculations based on probabilistic reliability considerations is the knowledge on the statistical distribution or the incidence frequency of specific phenomena and their characteristic basic variables. The extreme value statistics software PRO GUMBEL is the extended version of the original GUMBEL software used for seismic assessments. The authors describe the features of the software, that covers seismic events, flooding and extreme storms.

Development of incident progress prediction technologies for nuclear emergency preparedness. Current status and future subjects

International Nuclear Information System (INIS)

Yoshida, Yoshitaka; Yamamoto, Yasunori; Kusunoki, Takayoshi; Kawasaki, Ikuo; Yanagi, Chihiro; Kinoshita, Ikuo; Iwasaki, Yoshito

2014-01-01

Nuclear licensees are required to maintain a prediction system during normal condition for using a nuclear emergency by the Basic Plan for Disaster Prevention of government. With prediction of the incident progress, if the present condition of nuclear power plant is understood appropriately and it grows more serious with keeping the present situation, it is in predicting what kind of situation will be occurred in the near future, choosing the effective countermeasures against the coming threat, and understanding the time available of intervention time. Following the accident on September 30 1999 in the nuclear fuel fabrication facility in Tokai Village of Ibaraki Prefecture, the Institute of Nuclear Safety System started development of incident progress prediction technologies for nuclear emergency preparedness. We have performed technical applications and made improvements in nuclear emergency exercises and verified the developed systems using the observed values of the Fukushima Daiichi Nuclear Power Plant accident. As a result, our developed Incident Progress Prediction System was applied to nuclear emergency exercises and we accumulated knowledge and experience by which we improved the system to make predictions more rapidly and more precisely, including for example, the development of a prediction method for leak size of reactor coolant. On the other hand, if a rapidly progressing incident occurs, since end users need simple and quick predictions about the public's protection and evacuation areas, we developed the Radioactive Materials Release, Radiation Dose and Radiological Protection Area Prediction System which changed solving an inverse problem into a forward problem solution. In view of the water-level-decline incident of the spent fuel storage facility at the Fukushima Daiichi Nuclear Power Plant, the spent fuel storage facility water level and the water temperature evaluation tool were improved. Such incident progress prediction technologies were

Comparative risk analysis for the Rocky Flats Plant integrated project planning

International Nuclear Information System (INIS)

Jones, M.E.; Shain, D.I.

1994-01-01

The Rocky Flats Plant is developing, with active stakeholder participation, a comprehensive planning strategy that will support transition of the Rocky Flats Plant from a nuclear weapons production facility to site cleanup and final disposition. Consideration of the interrelated nature of sitewide problems, such as material movement and disposition, facility and land use endstates, costs, relative risks to workers and the public, and waste disposition are all needed. Comparative Risk Analysis employs both incremental risk and cumulative risk evaluations to compare risks from postulated options or endstates and is an analytical tool for the Rocky Flats Plant Integrated Project Planning which can assist a decision-maker in evaluating relative risks among proposed remediation activity. However, risks from all of the remediation activities, decontamination and decommissioning activities, and normal ongoing operations are imposed upon the Rocky Flats workers, the surrounding public, and the environment. Comparative Risk Analysis will provide risk information, both human health and ecological, to aid in reducing unnecessary resource and monetary expenditures by focusing these resources on the largest risks first. Comparative Risk Analysis has been developed to aggregate various incremental risk estimates to develop a site cumulative risk estimate. The Comparative Risk Analysis methodology Group, consisting of community stakeholders, was established. Early stakeholder involvement in the risk analysis methodology development provides an opportunity for stakeholders to influence the risk information delivered to a decision-maker. This paper discusses development of the Comparative Risk Analysis methodology, stakeholder participation and lessons learned from these challenges

Next Generation Nuclear Plant Project Preliminary Project Management Plan

International Nuclear Information System (INIS)

Dennis J. Harrell

2006-01-01

This draft preliminary project management plan presents the conceptual framework for the Next Generation Nuclear Plant (NGNP) Project, consistent with the authorization in the Energy Policy Act of 2005. In developing this plan, the Idaho National Laboratory has considered three fundamental project planning options that are summarized in the following section. Each of these planning options is literally compliant with the Energy Policy Act of 2005, but each emphasizes different approaches to technology development risks, design, licensing and construction risks, and to the extent of commercialization support provided to the industry. The primary focus of this draft preliminary project management plan is to identify those activities important to Critical Decision-1, at which point a decision on proceeding with the NGNP Project can be made. The conceptual project framework described herein is necessary to establish the scope and priorities for the technology development activities. The framework includes: A reference NGNP prototype concept based on what is judged to be the lowest risk technology development that would achieve the needed commercial functional requirements to provide an economically competitive nuclear heat source and hydrogen production capability. A high-level schedule logic for design, construction, licensing, and acceptance testing. This schedule logic also includes an operational shakedown period that provides proof-of-principle to establish the basis for commercialization decisions by end-users. An assessment of current technology development plans to support Critical Decision-1 and overall project progress. The most important technical and programmatic uncertainties (risks) are evaluated, and potential mitigation strategies are identified so that the technology development plans may be modified as required to support ongoing project development. A rough-order-of-magnitude cost evaluation that provides an initial basis for budget planning. This

Incident Management Organization succession planning stakeholder feedback

Science.gov (United States)

Anne E. Black

2013-01-01

This report presents complete results of a 2011 stakeholder feedback effort conducted for the National Wildfire Coordination Group (NWCG) Executive Board concerning how best to organize and manage national wildland fire Incident Management Teams in the future to meet the needs of the public, agencies, fire service and Team members. Feedback was collected from 858...

Participation of the ININ in the external radiological emergency plan of the Laguna Verde power plant

International Nuclear Information System (INIS)

Martinez S, R.; Cervini L, A.

1991-01-01

The planning of performances in radiological emergencies, with the object of reducing the consequences as much as possible on the population to accidental liberations of radioactive material coming from Nuclear power plant, it has been of main interest in the nuclear community in the world. In Mexico it has not been the exception, since with the setting in march of the Laguna Verde nuclear power plant exists an executive program of planning for emergencies that it outlines the activities to follow trending to mitigate the consequences that are derived of this emergency. As integral part of this program this the External Plan of Radiological Emergency (PERE) that covers the emergencies that could leave the frontiers of the Laguna Verde power plant. In the PERE it settles down the planning, address and control of the preparation activities, response and recovery in emergencies, as well as the organization and coordination of the institutions that participate. The National Institute of Nuclear Research (ININ), like integral part of these institutions in the PERE, has an infrastructure that it allows to participate in the plan in a direct way in the activities of 'Control of the radiological exhibition the response personnel and control of water and foods' and of support way and consultant ship in the activities of 'Monitoring, Classification and decontamination of having evaluated' and 'Specialized medical radiological attention'. At the moment the ININ has a radiological mobile unit and this conditioning a second mobile unit to carry out part of the activities before mentioned; also accounts with 48 properly qualified people that directly intervene in the plan. In order to guarantee an adequate response in the PERE an organization it has been structured like that of the annex as for the personnel, transport, team, procedures and communication system, with the objective always of guaranteeing the security and the population's health in emergency situations in the

Sequential Sampling Plan of Anthonomus grandis (Coleoptera: Curculionidae) in Cotton Plants.

Science.gov (United States)

Grigolli, J F J; Souza, L A; Mota, T A; Fernandes, M G; Busoli, A C

2017-04-01

The boll weevil, Anthonomus grandis grandis Boheman (Coleoptera: Curculionidae), is one of the most important pests of cotton production worldwide. The objective of this work was to develop a sequential sampling plan for the boll weevil. The studies were conducted in Maracaju, MS, Brazil, in two seasons with cotton cultivar FM 993. A 10,000-m2 area of cotton was subdivided into 100 of 10- by 10-m plots, and five plants per plot were evaluated weekly, recording the number of squares with feeding + oviposition punctures of A. grandis in each plant. A sequential sampling plan by the maximum likelihood ratio test was developed, using a 10% threshold level of squares attacked. A 5% security level was adopted for the elaboration of the sequential sampling plan. The type I and type II error used was 0.05, recommended for studies with insects. The adjustment of the frequency distributions used were divided into two phases, so that the model that best fit to the data was the negative binomial distribution up to 85 DAE (Phase I), and from there the best fit was Poisson distribution (Phase II). The equations that define the decision-making for Phase I are S0 = -5.1743 + 0.5730N and S1 = 5.1743 + 0.5730N, and for the Phase II are S0 = -4.2479 + 0.5771N and S1 = 4.2479 + 0.5771N. The sequential sampling plan developed indicated the maximum number of sample units expected for decision-making is ∼39 and 31 samples for Phases I and II, respectively. © The Authors 2017. Published by Oxford University Press on behalf of Entomological Society of America. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

A basic study for development of environmental standard review plan of Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Chung, Chang Hyun; Cho, Jae Seon; You, Young Woo [Seoul Nationl Univ., Seoul (Korea, Republic of)] (and others)

1999-12-15

In this study is performed a basic study to be ready for the development and detail analysis of NUREG-1555 ESRP. As a fundamental research for literature survey and development of draft review plan, review and translation of NUREG-1555 published by NRC, and which is applied to licensing procedure of Nuclear Power Plants are included. These provided the basic information for the developments of the environmental standard review plan.

OAK RIDGE Y-12 PLANT BIOLOGICAL MONITORING AND ABATEMENT PROGRAM (BMAP) PLAN

Energy Technology Data Exchange (ETDEWEB)

ADAMS, S.M.; BRANDT, C.C.; CHRISTENSEN, S.W.; CICERONE, D.S.; GREELEY, M.S.JR; HILL, W.R.; HUSTON, M.S.; KSZOS, L.A.; MCCARTHY, J.F.; PETERSON, M.J.; RYON, M.G.; SMITH, J.G.; SOUTHWORTH, G.R.; STEWART, A.J.

1998-10-01

The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y- 12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas (e.g., additional toxicity testing if initial results indicate low survival or reproduction) or a reduction in sampling intensity in others (e.g., reduction in the number of sampling sites when no impact is observed). By using the results of previous monitoring efforts to define the current program and to guide us in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions.

Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants: Criteria for utility offsite planning and preparedness: Final report

International Nuclear Information System (INIS)

Podolak, E.M. Jr.; Sanders, M.E.; Wingert, V.L.; Donovan, R.W.

1988-09-01

The Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) have added a supplement to NUREG-0654/FEMA-REP-1, Rev. 1 that provides guidance for the development, review, and evaluation of utility offsite radiological emergency response planning and preparedness for those situations in which state and/or local governments decline to participate in emergency planning. While this guidance primarily applies to plants that do not have full-power operating licenses, it does have relevance to operating nuclear power plants

Planning for decommissioning of Ignalina Nuclear Power Plant Unit-1

International Nuclear Information System (INIS)

Poskas, P.; Poskas, R.; Zujus, R.

2002-01-01

In accordance to Ignalina NPP Unit 1 Closure Law, the Government of Lithuania approved the Ignalina NPP Unit 1 Decommissioning Program until 2005. For enforcement of this program, the plan of measures for implementation of the program was prepared and approved by the Minister of Economy. The plan consists of two parts, namely technical- environmental and social-economic. Technical-environmental measures are mostly oriented to the safe management of spent nuclear fuel and operational radioactive waste stored at the plant and preparation of licensing documents for Unit 1 decommissioning. Social-economic measures are oriented to mitigate the negative social and economic impact on Lithuania, inhabitants of the region, and, particularly, on the staff of Ignalina NPP by means of creating favorable conditions for a balanced social and economic development of the region. In this paper analysis of planned radioactive waste management technologies, licensing documents for decommissioning, other technical-environmental and also social-economic measures is presented. Specific conditions in Lithuania important for defining the decommissioning strategy are highlighted. (author)

A Planning Tool for Estimating Waste Generated by a Radiological Incident and Subsequent Decontamination Efforts - 13569

Energy Technology Data Exchange (ETDEWEB)

Boe, Timothy [Oak Ridge Institute for Science and Education, Research Triangle Park, NC 27711 (United States); Lemieux, Paul [U.S. Environmental Protection Agency, Research Triangle Park, NC 27711 (United States); Schultheisz, Daniel; Peake, Tom [U.S. Environmental Protection Agency, Washington, DC 20460 (United States); Hayes, Colin [Eastern Research Group, Inc, Morrisville, NC 26560 (United States)

2013-07-01

Management of debris and waste from a wide-area radiological incident would probably constitute a significant percentage of the total remediation cost and effort. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a unique planning tool for estimating the potential volume and radioactivity levels of waste generated by a radiological incident and subsequent decontamination efforts. The WEST was developed to support planners and decision makers by generating a first-order estimate of the quantity and characteristics of waste resulting from a radiological incident. The tool then allows the user to evaluate the impact of various decontamination/demolition strategies on the waste types and volumes generated. WEST consists of a suite of standalone applications and Esri{sup R} ArcGIS{sup R} scripts for rapidly estimating waste inventories and levels of radioactivity generated from a radiological contamination incident as a function of user-defined decontamination and demolition approaches. WEST accepts Geographic Information System (GIS) shape-files defining contaminated areas and extent of contamination. Building stock information, including square footage, building counts, and building composition estimates are then generated using the Federal Emergency Management Agency's (FEMA's) Hazus{sup R}-MH software. WEST then identifies outdoor surfaces based on the application of pattern recognition to overhead aerial imagery. The results from the GIS calculations are then fed into a Microsoft Excel{sup R} 2007 spreadsheet with a custom graphical user interface where the user can examine the impact of various decontamination/demolition scenarios on the quantity, characteristics, and residual radioactivity of the resulting waste streams. (authors)

Emergency imaging after a mass casualty incident: role of the radiology department during training for and activation of a disaster management plan

NARCIS (Netherlands)

Berger, Ferco H.; Körner, Markus; Bernstein, Mark P.; Sodickson, Aaron D.; Beenen, Ludo F.; McLaughlin, Patrick D.; Kool, Digna R.; Bilow, Ronald M.

2016-01-01

In the setting of mass casualty incidents (MCIs), hospitals need to divert from normal routine to delivering the best possible care to the largest number of victims. This should be accomplished by activating an established hospital disaster management plan (DMP) known to all staff through prior

Planning for rate base treatment of large power plants

International Nuclear Information System (INIS)

Faruki, C.J.

1986-01-01

This paper addresses two related areas of planning for inclusion in rate base of large generating stations. First, the paper discusses the range of options available as to how the plant is to go into rate base, e.g., phase-in plans. In this connection the process of generating the entire range of options that may be available is described and examined. Second, the paper examines innovative ways of using procedures (e.g., accounting proceedings, settlement procedures, cost caps, and other ideas short of a full-blown rate case) and the resources available in the ratemaking arena, to obtain, in the least painful way possible, the necessary ratemaking orders. The thesis is that there must be better alternatives to the many proceedings that have either begun as, or seem to be leading to, endless retrospective examinations of multiple questions (from load forecasting to construction management to continuation-of-construction decisions) under the label of prudence inquiries

Interação enxerto e porta-enxerto na incidência da resinose do cajueiro Effect of cashew clone used as rootstocks and scions on gummosis incidence in cashew plants

Directory of Open Access Journals (Sweden)

José Emilson Cardoso

2010-09-01

genotypes used to both as scion and root-stock. This may contribute to enhance crop vulnerability to some biological harm such as the infection by the gummosis fungus agent, Lasiodiplodia theobromae, the most important disease of this plant in semi-arid north-eastern Brazil. It has been estimated that half a million graft plants of EDC are yearly produced in Brazil, most of them obtained by grafting over seedling from CCP 06 clone as root-stock. The only means of managing gummosis is by the use of genetically resistant clones. However, the lack of studies on the scion and stock genotypic interactions has contributed to outbreak of successive gummosis epidemics. This study was developed in order to evaluate the effect of different combinations of EDC clones used as scion and stock on gummosis incidence. Root-stocks, prepared from seeds of six open pollinated plants, were grafted with two commercial clones: CCP 75 (susceptible and BRS 226 (resistant. The field trial was laid out under high disease pressure, in a 2 by 6 factorial scheme in a completely randomized block design with four replications and nine plants per plot. Disease incidence (I and severity (S (scale 0 to 4 was monitored for three years. On the third year, gummosis incidence and severity were higher in CCP 76 (I =97% and I = 2.10 than in BRS 226 (I =33% and I = 0.36, independently of root-stock. CCP 06 clone was the only one root-stock which reduced both incidence and severity of gummosis independently of scion. This clone was able to reduce susceptibility of CCP 76 as canopy.

Stormwater Pollution Prevention Plan - TA-60 Asphalt Batch Plant

Energy Technology Data Exchange (ETDEWEB)

Sandoval, Leonard Frank [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2018-01-31

This Storm Water Pollution Prevention Plan (SWPPP) was developed in accordance with the provisions of the Clean Water Act (33 U.S.C. §§1251 et seq., as amended), and the Multi-Sector General Permit for Storm Water Discharges Associated with Industrial Activity (U.S. EPA, June 2015) issued by the U.S. Environmental Protection Agency (EPA) for the National Pollutant Discharge Elimination System (NPDES) and using the industry specific permit requirements for Sector P-Land Transportation and Warehousing as a guide. This SWPPP applies to discharges of stormwater from the operational areas of the TA-60-01 Asphalt Batch Plant at Los Alamos National Laboratory. Los Alamos National Laboratory (also referred to as LANL or the “Laboratory”) is owned by the Department of Energy (DOE), and is operated by Los Alamos National Security, LLC (LANS). Throughout this document, the term “facility” refers to the TA-60 Asphalt Batch Plant and associated areas. The current permit expires at midnight on June 4, 2020.

When it is unfamiliar to me: Local acceptance of planned nuclear power plants in China in the post-fukushima era

International Nuclear Information System (INIS)

Guo, Yue; Ren, Tao

2017-01-01

Many contributions have been made in the studies of the factors that influence public acceptance of nuclear power. However, previous studies seldom focused on nuclear power plants in the planning stage. Actually public perception is usually more sensitive at the preliminary planning stage of a nuclear power station. Mainly utilizing questionnaire survey and focus group methods, we have identified the factors that are correlated with local acceptance of planned nuclear power plants in China. We conducted our survey in two cities, Huludao, Liaoning province in northern China, and Shanwei, Guangdong province in southern China, where the local government was planning to build its first nuclear power plant. We find that people who live closer to the plant sites are less willing to accept nuclear power than those who live farther away. As for “surface psychology” factors, perceived benefits and risks significantly influence local acceptance. As for “deep psychology” factors, emotional identification and social trust can significantly influence local acceptance, while perceived knowledge cannot. When citizens are unfamiliar with nuclear power plants, they are more inclined to evaluate the benefits and risks through emotional identification and social trust, rather than through pure rational deduction based on concrete facts. - Highlights: • We focus on the local acceptance of nuclear power in the planning stages. • People who live closer to plant sites are less willing to accept nuclear power. • Perceived benefits and risks significantly influence local acceptance. • Emotional identification and trust can significantly influence local acceptance. • While perceived knowledge cannot significantly influence local acceptance.

Next Generation Nuclear Plant Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

P. E. MacDonald

2005-01-01

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

Next Generation Nuclear Plant Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

None

2005-01-01

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

Planning and building a complex mine water treatment plant for Vietnam; Planung und Bau einer komplexen Grubenwasserreinigungsanlage fuer Vietnam

Energy Technology Data Exchange (ETDEWEB)

Schlenstedt, Joerg [LMBV international, Senftenberg (Germany); Bilek, Felix [GFI Grundwasserforschungsinstitut GmbH, Dresden (Germany); Kochan, Hans-Juergen

2010-05-15

In an anthracite coal mine in the northeast of Vietnam a mine water treatment plant shall be built. This plant is meant to be a pilot plant for further plants in this region. Apart from the climatic situation and the initially barely existing hydrological and hydrochemical data material, the high solids and manganese content in the mine water are a major challenge. Only by monitoring and capacity building which ran parallel to the planning process as well as the data collection and process optimisation in laboratory and bench scale, the planning process could be realised successfully. For the mine water remediation such a process was developed and well planned. This process is based on neutralisation, oxidation and hydroxide sedimentation as well as on oxidation and sorption processes which are catalysed on solid material surfaces. The project is financed by the BMBF sponsored RAME group and the individual contribution of the German project partners on the on hand. In this framework all scientific and engineering performances are generated. On the other hand the Vietnamese partner VINACOMIN invests by financing the construction of the plant, partly building it and participating on the planning with own engineering performances. Beside the authors, Peter Denke from LMBV international, Stefan Kurtz from GFI Dresden and Marlies Jaschke from eta-AG are involved in the project. (orig.)

Portsmouth Gaseous Diffusion Plant Decontamination and Decommissioning Program surveillance and maintenance plan, FY 1993--2002

International Nuclear Information System (INIS)

Schloesslin, W.

1992-11-01

The Decontamination and Decommissioning (D ampersand D) Program at the Portsmouth Gaseous Diffusion Plant (PORTS) is part of the Environmental Restoration (ER) and Waste Management (WM) Programs (ERWM). The objective of the ER Program is to provide PORTS the capability to meet applicable environmental regulations through facility development activities and site remedial actions. The WM Program supports the ER Program. The D ampersand D Program provides collective management of the sites within the plant which require decontamination and decommissioning, prioritizes those areas in terms of health, safety and environmental concerns, and implements the appropriate level of remedial action. The D ampersand D Program provides support to facilities which formerly served one or more of the many Plant functions. Program activities include (1) surveillance and maintenance of facilities awaiting decommissioning; (2) planning safe and orderly facility decommissioning; and (3) implementing a program to accomplish facility disposition in a safe, cost effective, and timely manner. In order to achieve the first objective, a formal plan which documents the surveillance and maintenance needs for each inactive facility has been prepared. This report provides this documentation for the PORTS facilities currently included in the D ampersand D Program and includes projected resource requirements for the planning period of FY 1993 through FY 2002

78 FR 14503 - Amendment 4 to the Corals and Reef Associated Plants and Invertebrates Fishery Management Plan of...

Science.gov (United States)

2013-03-06

.... 120718255-3038-01] RIN 0648-BC38 Amendment 4 to the Corals and Reef Associated Plants and Invertebrates... Fishery Management Plan (FMP) for Corals and Reef Associated Plants and Invertebrates of Puerto Rico and... the coral reef resources FMU to include a vast array of plants and invertebrates that provide habitats...

Medical emergency planning in case of severe nuclear power plant accidents

International Nuclear Information System (INIS)

Ohlenschlaeger, L.

1980-01-01

This paper is an attempt to discuss a three-step-plan on medical emergency planning in case of severe accidents at nuclear power plants on the basis of own experiences in the regional area as well as on the basis of recommendations of the Federal Minister of the Interior. The medical considerations take account of the severity and extension of an accident whereby the current definitions used in nuclear engineering for accident situations are taken as basis. A comparison between obligatory and actual state is made on the possibilities of medical emergency planning, taking all capacities of staff, facilities, and equipment available in the Federal Republic of Germany into account. To assure a useful and quick utilization of the existing infra-structure as well as nation-wide uniform training of physicians and medical assistants in the field of medical emergency in case of a nuclear catastrophe, a federal law for health protection is regarded urgently necessary. (orig.) [de

Improvement in operating incident experience at the Savannah River Burial Ground

International Nuclear Information System (INIS)

Cornman, W.R.

1979-01-01

Low-level radioactive wastes generated at the Savannah River Plant and Laboratory are stored at the Savannah River burial ground. These wastes have accumulated from >20 years of reprocessing nuclear fuels and materials for defense programs at the Savannah River Plant. Burial in earthen trenches and aboveground storage for transuranic materials are the principal modes of storage. The infrequent operating incidents that have occurred during the 20-year period have been analyzed. The incidents can be categorized as those causing airborne contamination, waterborne contamination, or vegetation contamination through penetration of plant roots into contaminated soil. Contamination was generally confined to the immediate area of the burial ground. Several incidents occurred because of unintentional burial or exhumation of material. The frequency of operating incidents decreased with operating experience of the burial ground, averaging only about two incidents per year during the last six years of operation

75 FR 56131 - Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for the Northern...

Science.gov (United States)

2010-09-15

... on the MOCA network recommended in the 2008 Recovery Plan and will instead use the model results to... DEPARTMENT OF THE INTERIOR Fish and Wildlife Service [FWS-R1-ES-2010-N184; 10120-1113-0000-C2] Endangered and Threatened Wildlife and Plants; Draft Revised Recovery Plan for the Northern Spotted Owl...

Comparative risk analysis for the Rocky Flats Plant integrated project planning

International Nuclear Information System (INIS)

Jones, M.E.; Shain, D.I.

1994-01-01

The Rocky Flats Plant is developing, with active stakeholder a comprehensive planning strategy that will support transition of the Rocky Flats Plant from a nuclear weapons production facility to site cleanup and final disposition. Final disposition of the Rocky Flats Plant materials and contaminants requires consideration of the interrelated nature of sitewide problems, such as material movement and disposition, facility and land use endstates, costs relative risks to workers and the public, and waste disposition. Comparative Risk Analysis employs both incremental risk and cumulative risk evaluations to compare risks from postulated options or endstates. These postulated options or endstates can be various remedial alternatives, or future endstate uses of federal agency land. Currently, there does not exist any approved methodology that aggregates various incremental risk estimates. Comparative Risk Analysis has been developed to aggregate various incremental risk estimates to develop a site cumulative risk estimate. This paper discusses development of the Comparative Risk Analysis methodology, stakeholder participation and lessons learned from these challenges

Environmental Restoration Site-Specific Plan for the Portsmouth Gaseous Diffusion Plant, FY 93

International Nuclear Information System (INIS)

1993-01-01

The purpose of this Site-Specific Plan (SSP) is to describe past, present, and future activities undertaken to implement Environmental Restoration and Waste Management goals at the Portsmouth Gaseous Diffusion Plant (PORTS). The SSP is presented in sections emphasizing Environmental Restoration description of activities, resources, and milestones

Opportunity study and a business plan for a wind power plant

International Nuclear Information System (INIS)

Nikolov, Marjan; Naumov, Risto

2006-01-01

This paper provides illustration of opportunity study and a business plan for utilizing the wind renewable resource for electricity production in Macedonia. The study is prepared under UNIDO recommendations for feasibility studies (see [1]) and following the IAS, by Marjan Nikolov and Risto Naumov. This is a project simulation for a small wind farm comprising 3 power plant units. We use price list from 'Proven Engineering Products Ltd' UK.

Proposed plan for remedial action at the chemical plant area of the Weldon Spring site

International Nuclear Information System (INIS)

1992-11-01

This proposed plan addresses the management of contaminated material at the chemical plant area of the Weldon Spring site and nearby properties in St. Charles County, Missouri. The site consists of a chemical plant area and a noncontiguous limestone quarry, both of which are radioactively and chemically contaminated as a result of past processing and disposal activities. Explosives were produced at the chemical plant in the 1940s, and uranium and thorium materials were processed in the 1950s and 1960s. Various liquid, sludge, and solid wastes were disposed of at the Chemical plant area and in the quarry during that time. The Weldon Spring site is listed on the National Priorities List (NPL) of the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) is conducting cleanup activities at the site under its Environmental Restoration and Waste Management Program. The proposed plan is organized as follows: Chapter 2 presents the history and setting of the Weldon Spring site and briefly describes the contaminated material at the chemical plant area. Chapter 3 defines the scope of the remedial action and its role in the Weldon Spring Site Remedial Action Project. Chapter 4 summarizes the risks associated with possible exposures to site contaminants in the absence of remedial action and identifies proposed cleanup levels for soil. Chapter 5 briefly describes the final alternatives considered for the remedial action. Chapter 6 summarizes the evaluation of final alternatives for managing the contaminated material, identifies the currently preferred alternative, and discusses a possible contingency remedy to provide treatment flexibility. Chapter 7 presents the community's role in this action. Chapter 8 is a list of the references cited in this proposed plan

Managing Materials and Wastes for Homeland Security Incidents

Science.gov (United States)

To provide information on waste management planning and preparedness before a homeland security incident, including preparing for the large amounts of waste that would need to be managed when an incident occurs, such as a large-scale natural disaster.

Guidance for emergency planning in nuclear power plants; Vaegledning foer insatsplanering i kaerntekniska anlaeggningar

Energy Technology Data Exchange (ETDEWEB)

Magnusson, Tommy; Ekdahl, Maria (Ringhals AB, Vaeroebacka (Sweden))

2008-06-15

Ringhals has been a model for this study, but the purpose has been to make the report applicable at all nuclear power plants in Sweden. The work has been done in close co-operation with the Swedish nuclear power plants and Rescue Services in the nuclear power municipalities Oesthammar, Oskarshamn, and Varberg. The internal fire brigade at the nuclear power plants has also been involved. A document will also be published as a further guidance at efforts of the type fires, which are mentioned in the enclosed document. After a fire in a switchgear room in 2005 the need of making the existing effort planning more effective at nuclear power plants was observed. The idea with the planning is to plan the effort in order to give the operational and emergency staff a good and actual support to come to a decision and to start the mission without delay. The risk information is showed by planning layouts, symbols and drawings as basis, give risk information and effort information. The effort information shows outer arrangements, manual action points, fire installations, passive fire safety etc. The risk information is shown by risk symbols. Their purpose is to give a fast overview of the existing risks. Reactor safety effects is the ruling influence if an effort has to be done in order to secure safety for a third person. In order to make an effort in an area personal risks for rescue staff, such as electricity risks, radiological risks, chemicals and gas bottles with compressed gases, has to be eliminated. For complicated missions detailed instructions are needed in order to handle specific risks. In a group discussion different people with pertinent knowledge has to value which problematic efforts need detailed instruction. Missions that have to be analyzed in a work group as above are: fire may affect the reactor safety, fire that may threaten the structural integrity, chemical discharge with big consequence on environment/third person and handling of gas system (compressed

Y-12 Plant Groundwater Protection Program: Groundwater and surface water sampling and analysis plan for Calendar Year 1998

International Nuclear Information System (INIS)

1997-09-01

This plan provides a description of the groundwater and surface water quality monitoring activities planned for calendar year (CY) 1998 at the Department of Energy (DOE) Y-12 Plant. These monitoring activities are managed by the Y-12 Plant Environmental Compliance Organization through the Y-12 Plant Groundwater Protection Program (GWPP). Groundwater and surface water monitoring during CY 1998 will be performed in three hydrogeologic regimes at the Y-12 Plant: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime), and the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Bear Creek and East Fork regimes are located within Bear Creek Valley, and the Chestnut Ridge Regime is located south of the Y-12 Plant. Groundwater and surface water monitoring will be performed during CY 1998 to comply with: (1) requirements specified in Resource Conservation and Recover Act (RCRA) post-closure permits regarding RCRA corrective action monitoring and RCRA detection monitoring; (2) Tennessee Department of Environment and Conservation regulations governing detection monitoring at nonhazardous solid waste management facilities; and (3) DOE Order 5400.1 surveillance monitoring and exit pathway monitoring. Data from some of the sampling locations in each regime will be used to meet the requirements of more than one of the monitoring drivers listed above. Modifications to the CY 1998 monitoring program may be necessary during implementation. For example, changes in regulatory requirements may alter the parameters specified for selected monitoring wells, or wells could be removed from the planned monitoring network. All modifications to the monitoring program will be approved by the Y-12 Plant GWPP manager and documented as addenda to this sampling and analysis plan

Y-12 Plant Groundwater Protection Program Groundwater and Surface Water sampling and Analysis Plan for Calendar Year 2000

International Nuclear Information System (INIS)

1999-01-01

This plan provides a description of the groundwater and surface water quality monitoring activities planned for calendar year (CY) 2000 at the U.S. Department of Energy (DOE) Y-12 Plant that will be managed by tie Y-12 Plant Groundwater Protection Program (GWPP). Groundwater and surface water monitoring during CY 2000 will be performed in three hydrogeologic regimes at the Y-12 Plant: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime), and the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Bear Creek and East Fork regimes are located in Bear Creek Valley, and the Chestnut Ridge Regime is located south of the Y-12 Plant (Figure 1). Groundwater and surface water monitoring performed under the auspices of the Y-12 Plant GWPP during CY 2000 will comply with: Tennessee Department of Environment and Conservation regulations governing detection monitoring at nonhazardous Solid Waste Disposal Facilities (SWDF); and DOE Order 5400.1 surveillance monitoring and exit pathway/perimeter monitoring. Some of the data collected for these monitoring drivers also will be used to meet monitoring requirements of the Integrated Water Quality Program, which is managed by Bechtel Jacobs Company LLC. Data from five wells that are monitored for SWDF purposes in the Chestnut Ridge Regime will be used to comply with requirements specified in the Resource Conservation and Recovery Act post closure permit regarding corrective action monitoring. Modifications to the CY 2000 monitoring program may be necessary during implementation. Changes in regulatory or programmatic requirements may alter the analytes specified for selected monitoring wells, or wells could be added or removed from the planned monitoring network. All modifications to the monitoring program will be approved by the Y-12 Plant GWPP manager and documented as addenda to this sampling and analysis plan

Removal action work plan for the YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-03-01

The US Department of Energy is conducting environmental restoration activities at the Y-12 Plant in Oak Ridge, Tennessee. As part of these efforts, a removal action is planned for the former YS-860 Firing Ranges as described in the Action Memorandum for the project. This removal action work plan (RmAWP) is focused on the former YS-860 Firing Ranges, located outside the primary fenceline at the eastern end of the plant. This RmAWP defines the technical approach, procedures, and requirements for the removal of lead-contaminated soil and site restoration of the former YS-860 Firing Ranges at the Y-12 Plant. This RmAWP describes excavation, verification/confirmatory sampling, and reporting requirements for the project. Lower tier plans associated with the RmAWP, which are submitted as separate stand-alone documents, include a field sampling and analysis plan, a health and safety plan, a quality assurance project plan, a waste management plan, a data management implementation plan, and a best management practices plan. A site evaluation of the YS-86O Firing Ranges conducted in 1996 by Lockheed Martin Energy Systems, Inc., determined that elevated lead levels were present in the Firing Ranges target berm soils. The results of this sampling event form the basis for the removal action recommendation as described in the Action Memorandum for this project. This RmAWP contains a brief history and description of the Former YS-860 Firing Ranges Project, along with the current project schedule and milestones. This RmAWP also provides an overview of the technical requirements of the project, including a summary of the approach for the removal activities. Finally, the RmAWP identifies the regulatory requirements and the appropriate removal action responses to address applicable or relevant and appropriate requirements to achieve the project goals of substantially reducing the risk to human health and the environment

76 FR 53482 - Endangered and Threatened Wildlife and Plants; Notice of Availability of a Revised Recovery Plan...

Science.gov (United States)

2011-08-26

... and revised the recovery plan accordingly. The desert tortoise is a large, herbivorous reptile that... tortoise populations. Disease and increased incidence of fire in the Mojave Desert have also been... tortoises, there are few data available to evaluate or quantify the effects of threats on desert tortoise...

Mobile central heating plant ensures the supply during the power-plant modernization. Planning-safe reconstruction; Mobile Heizzentrale sichert Versorgung waehrend Kraftwerksmodernisierung. Planungssicherer Umbau

Energy Technology Data Exchange (ETDEWEB)

Bernhard, Petra [Mobiheat GmbH, Friedberg (Germany). Presse- und Oeffentlichkeitsarbeit

2012-09-15

During the comprehensive energetic retrofitting of district heating plants in the spa resort of Badenweiler (Federal Republic of Germany) a mobile 2-MW heating plant from Mobilheat (Ebersberg, Federal Republic of Germany) was used for the heat supply. Thus, the installation of environmental friendly energy supply based on cogeneration plants could be implemented with planning security. This particularly was important because, among other things, the traditional spa resort, the Kurhaus as well as hotels and private customers depend on the heat supply system. These buildings have be supplied with thermal water also in the summer.

76 FR 31973 - Endangered and Threatened Wildlife and Plants; Notice of Availability of Draft Recovery Plan for...

Science.gov (United States)

2011-06-02

... for invasive introduced plant removal, as appropriate, and adaptive management plans to address... consider the species for reclassification or removal from the Federal List of Endangered and Threatened... hispida under the Endangered Species Act of 1973, as amended (Act). This draft plan is an addendum to the...

Fiscal year 1990 Rocky Flats Plant environmental restoration program current-year work plan

International Nuclear Information System (INIS)

Nielsen, T.; Waage, E.; Miller, D.

1990-01-01

This paper reports on the FY90 Current Year Work Plan (CYWP), intended to serve as a guiding document with which the Environmental Restoration and RCRA Compliance programs will be implemented at the Rocky Flats Plant, The Current Year Work Plan document serves to provide in one single document any cross-references necessary to understand how the DOE Five Year Plan, Site Specific Plan, or any other related documents fit into the Current Year Work Plan for the Rocky Flats Environmental Restoration. The scope of this paper will compare the planned Fiscal Year 1990 environmental restoration activities to those actually achieved at the end of the fiscal year. The DOE Headquarters (HQ) issued the Environmental Restoration and Waste Management (ER/WM) Five-Year Plan (FYP). The purpose of the FYP is to establish an agenda for compliance and cleanup against which progress will be measured. The Five Year Plan has been updated to include the Colorado Department of Health (CDH), Evironmental Protection Agency (EPA), and Department of Energy (DOE) Inter Agency Agreement Environmental Restoration activities. It addresses hazardous wastes, radioactive wastes, mixed wastes (radioactive and hazardous), and sanitary wastes. It also addresses facilities and sites contaminated with or used in the management of those wastes

BEAP profiles as rapid test system for status analysis and early detection of process incidents in biogas plants.

Science.gov (United States)

Refai, Sarah; Berger, Stefanie; Wassmann, Kati; Hecht, Melanie; Dickhaus, Thomas; Deppenmeier, Uwe

2017-03-01

A method was developed to quantify the performance of microorganisms involved in different digestion levels in biogas plants. The test system was based on the addition of butyrate (BCON), ethanol (ECON), acetate (ACON) or propionate (PCON) to biogas sludge samples and the subsequent analysis of CH 4 formation in comparison to control samples. The combination of the four values was referred to as BEAP profile. Determination of BEAP profiles enabled rapid testing of a biogas plant's metabolic state within 24 h and an accurate mapping of all degradation levels in a lab-scale experimental setup. Furthermore, it was possible to distinguish between specific BEAP profiles for standard biogas plants and for biogas reactors with process incidents (beginning of NH 4 + -N inhibition, start of acidification, insufficient hydrolysis and potential mycotoxin effects). Finally, BEAP profiles also functioned as a warning system for the early prediction of critical NH 4 + -N concentrations leading to a drop of CH 4 formation.

IAEA/NEA incident reporting system (IRS). Reporting guidelines. Feedback from safety related operating experience for nuclear power plants

International Nuclear Information System (INIS)

1998-01-01

The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants. These guidelines have been jointly developed and approved by the NEA/IAEA

Economic Evaluation of Decommissioning Cost of Nuclear Power Plant in the National Electricity Plan in Korea

International Nuclear Information System (INIS)

Lee, Man Ki; Nam, Ji Hee

2008-01-01

Decommissioning cost of a nuclear power plant includes the costs related with dismantling a nuclear power plant, disposal of a spent fuel and of a low/medium radioactive waste. The decommissioning cost is different from the other expenditures in that it is occurred after the reactor finishes its commercial operation. In this respect, the electricity act was enforced to secure provisions for decommissioning a nuclear power plant during its commercial operation. The purpose of this study is to provide economic evaluation and economic cost for a decommissioning when the cost of a decommissioning is provided as one of input to the national electricity plan. Therefore, this study does not deal with whether the estimated amount of a decommissioning cost is just or not. This study focuses how to transfer the estimated decommissioning cost given in the electricity act to the economic cost, which can be used in the national electricity plan

Precursor incident program at EDF

International Nuclear Information System (INIS)

Fourest, B.; Maliverney, B.; Rozenholc, M.; Piovesan, C.

1998-01-01

The precursor program was started by EDF in 1994, after an investigation of the US NRC's Accident Sequence Precursor Program. Since then, reported operational events identified as Safety Outstanding Events have been analyzed whenever possible using probabilistic methods based on PSAs. Analysis provides an estimate of the remaining protection against core damage at the time the incident occurred. Measuring the incidents' severity enables to detect incidents important regarding safety. Moreover, the most efficient feedback actions can be derived from the main accident sequences identified through the analysis. Therefore, incident probabilistic analysis provides a way to assess priorities in terms of treatment and resource allocation, and so, to implement countermeasures preventing further occurrence and development of the most significant incidents. As some incidents cannot be analyzed using this method, probabilistic analysis can only be one among the methods used to assess the nuclear power plants' safety level. Nevertheless, it provides an interesting complement to classical methods of deterministic studies. (author)

A plan for safety evaluation of tsunamis at the Uljin nuclear power plant site

International Nuclear Information System (INIS)

Lee, H. K.; Lee, D. S.

1999-01-01

The sites of many nuclear and thermal power plants are located along the coast line to obtain necessary cooling water. Therefore, they are vulnerable to coastal disasters like tsunamis. The safety evaluation on tsunamis of the site of Uljin nuclear power plants was performed with the maximum potential earthquake magnitude and related fault parameters in 1986. But according to the results of recent research, the possibility was suggested that the earthquake which has bigger magnitude than was expected is likely to happen in the seismic gaps near Akita, Japan. Therefore, a plan for safety evaluation of tsunamis at the Uljin nuclear power plants was laid out

Planning of maintenance of electrical equipment in nuclear plants/laboratories [Paper No.: VB-3

International Nuclear Information System (INIS)

Narasinga Rao, S.N.; Bhattacharyya, A.K.

1981-01-01

Satisfactory operating performance of electrical systems ensures continuous availability of power to the various plants and machinery in nuclear plant and laboratories. For effective optimal functioning of the electrical equipment and to reduce their down time, scheduled planning of maintenance to the equipment is essential. Maintenance of power plant, nuclear or fossil, and industrial plant and research laboratories demands essential ingredients such as right type of trained and motivated technical personnel, adoption of standard procedures for maintenance, adequate safety and protection for equipment, safety procedures adopted in the installation to prevent hazards to the workers, provision of adequate stores and inventories, facilities for quick repairs and testing of equipment and effective planning of procedures for their maintenance. While breakdown maintenance allows equipment to operate before it is repaired or replaced, preventive maintenance makes use of scheduled inspection and periodical equipment overhaul and has little value for predicting future continuous performances of equipment. The engineered maintenance is most advantageous and offers maximum operating time to reduce down time of the equipment while adding predictive testing technique to aid in determining the frequency of overhaul of equipment. The important checks to be conducted and preventive maintenance programme to be scheduled are discussed in this paper. The safety and reliable functioning of the electrical equipment depend on proper optimal design, selection of equipment, their installation, subsequent maintenance and strict compliance with safety regulations. (author)

77 FR 24975 - Endangered and Threatened Wildlife and Plants; Revised Recovery Plan for the Utah Prairie Dog

Science.gov (United States)

2012-04-26

...-FF06E00000] Endangered and Threatened Wildlife and Plants; Revised Recovery Plan for the Utah Prairie Dog... Utah prairie dog (Cynomys parvidens). This species is federally listed as threatened under the... recovery plan for the Utah prairie dog. The Service and other Federal agencies also will take these...

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

International Nuclear Information System (INIS)

Randklev, E.H.

1993-06-01

The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented

Criticality incident detection assessment methodology

International Nuclear Information System (INIS)

Haley, Richard M.; Warburton, Simon J.; Bowden, Russell L.

2003-01-01

In the United Kingdom, all nuclear facilities that handle, treat or store fissile material require a Criticality Incident Detection and Alarm System (CIDAS) to be installed, unless a case is made for the omission of such a system. Where it is concluded that a CIDAS is required, the primary objective is the reliable detection of criticality and the initiation of prompt evacuation of plant workers from the vicinity of the incident. This paper will examine and compare various methods that can be used to demonstrate that a CIDAS will satisfy the detection criterion. The paper will focus on fit-for-purpose and cost-effective methods for the assessment of gamma-based systems. In the experience of the authors this is particularly useful in demonstrating the efficacy of existing systems in operational plant. (author)

Report to Congress on status of emergency response planning for nuclear power plants

International Nuclear Information System (INIS)

1981-03-01

This report responds to a request (Public Law 96-295, Section 109) for the Nuclear Regulatory Commission (NRC) to report to Congress on the status of emergency response planning in support of nuclear power reactors. The report includes information on the status of this planning as well as on the Commission actions relating to emergency preparedness. These actions include a summary of the new regulatory requirements and the preliminary results of two comprehensive Evacuation Time Estimate studies; one requested by the NRC including 50 nuclear power plant sites and one conducted by the Federal Emergency Management Agency (FEMA) for 12 high population density sites. FEMA provided the information in this report on the status of State and local planning, including projected schedules for joint State/county/licensee emergency preparedness exercises. Included as Appendicies are the NRC Emergency Planning Final Regulations, 10 CFR Part 50 (45 FR 55402), the FEMA Proposed Rule, 'Review and Approval of State and Local Radiological Emergency Plans and Preparedness', 44 CFR Part 350 (45 FR 42341) and the NRC/FEMA Memorandums of Understanding

Contribution of Topography and Incident Solar Radiation to Variation of Soil and Plant Litter at an Area with Heterogeneous Terrain

Directory of Open Access Journals (Sweden)

Felipe Cito Nettesheim

2015-06-01

Full Text Available Natural processes that determine soil and plant litter properties are controlled by multiple factors. However, little attention has been given to distinguishing the effects of environmental factors from the effects of spatial structure of the area on the distribution of soil and litter properties in tropical ecosystems covering heterogeneous topographies. The aim of this study was to assess patterns of soil and litter variation in a tropical area that intercepts different levels of solar radiation throughout the year since its topography has slopes predominantly facing opposing geographic directions. Soil data (pH, C, N, P, H+Al, Ca, Mg, K, Al, Na, sand, and silt and plant litter data (N, K, Ca, P, and Mg were gathered together with the geographic coordinates (to model the spatial structure of 40 sampling units established at two sites composed of slopes predominantly facing northwest and southeast (20 units each. Soil and litter chemical properties varied more among slopes within similar geographic orientations than between the slopes facing opposing directions. Both the incident solar radiation and the spatial structure of the area were relevant in explaining the patterns detected in variation of soil and plant litter. Individual contributions of incident solar radiation to explain the variation in the properties evaluated suggested that this and other environmental factors may play a particularly relevant role in determining soil and plant litter distribution in tropical areas with heterogeneous topography. Furthermore, this study corroborates that the spatial structure of the area also plays an important role in the distribution of soil and litter within this type of landscape, which appears to be consistent with the action of water movement mechanisms in such areas.

Incidents with hazardous radiation sources; Zwischenfaelle mit gefaehrlichen Strahlenquellen

Energy Technology Data Exchange (ETDEWEB)

Schoenhacker, Stefan [Bundesministerium fuer Inneres, Traiskirchen (Austria). Abt. 1/9 - Zivilschutzschule

2016-07-01

Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

Desfolha, população de plantas e precocidade do milho afetam a incidência e a severidade de podridões de colmo Defoliation, plant population, and earliness of maize affect the incidence and severity of stalk rots

Directory of Open Access Journals (Sweden)

Luiz Eduardo Bassay Blum

2003-10-01

Full Text Available As relações entre fonte e dreno interferem sobre a ocorrência de podridões de colmo na cultura do milho (Zea mays. O estudo foi conduzido em Lages, SC, para avaliar o efeito da desfolha, população de plantas e híbridos sobre as podridões do colmo do milho. O delineamento experimental foi de blocos ao acaso com parcelas sub-subdivididas e três repetições. Os híbridos P32R21 (superprecoce, Premium (precoce e C333B (tardio foram testados sem desfolha e com 50% de desfolha no estágio de espigamento nas populações de 25.000, 50.000, 75.000 e 100.000 plantas ha-1. Avaliaram-se a incidência e a severidade das podridões do colmo causadas por Colletotrichum graminicola, Diplodia maydis e Fusarium moniliforme. O híbrido P32R21 foi o mais afetado pelos fungos causadores de podridões. Nos híbridos P32R21 e Premium, as plantas desfolhadas foram mais severamente infectadas pelos patógenos do que as intactas. O aumento da população de plantas aumentou a intensidade (incidência ou severidade de podridões de colmo nas plantas intactas e diminuiu a ocorrência nas desfolhadas.The relationship between source and sink interferes on maize (Zea mays stalk rot occurrence. This study was conducted in Lages, SC, Brazil, to evaluate the effect of defoliation, plant population, and hybrids on the intensity (incidence or severity of maize stalk rots. The experiment was set in a randomized complete block design (three replications with a split-split-plot arrangement. The hybrids P32R21 (very early, Premium (early and C333B (late were tested without defoliation and with 50% defoliation on ear formation stage at plant populations of 25,000, 50,000, 75,000, and 100,000 plants ha-1. The incidence and severity of Colletotrichum graminicola, Diplodia maydis and Fusarium moniliforme stalk rots were evaluated. The hybrid P32R21 was the most affected by stalk rots. Defoliation enhanced rots on P32R21 and Premium. Enhancements in plant population increased

Nuclear Plant Aging Research (NPAR) program plan: Components, systems, and structures

International Nuclear Information System (INIS)

1987-09-01

The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems and major components at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechanisms of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring, and maintenance as means of mitigating such effects. Specifically, the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of equipment, a systems, and major components and thereby impair plant safety; (2) to identify methods of inspection, surveillance, and monitoring, or of evaluating residual life of equipment, systems, and major components, which will ensure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair, and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

Risk Insights Gained from Fire Incidents

International Nuclear Information System (INIS)

Kazarians, Mardy; Nowlen, Steven P.

1999-01-01

There now exist close to 20 years of history in the application of Probabilistic Risk Assessment (PRA) for the analysis of fire risk at nuclear power plants. The current methods are based on various assumptions regarding fire phenomena, the impact of fire on equipment and operator response, and the overall progression of a fire event from initiation through final resolution. Over this same time period, a number of significant fire incidents have occurred at nuclear power plants around the world. Insights gained from US experience have been used in US studies as the statistical basis for establishing fire initiation frequencies both as a function of the plant area and the initiating fire source.To a lesser extent, the fire experience has also been used to assess the general severity and duration of fires. However, aside from these statistical analyses, the incidents have rarely been scrutinized in detail to verify the underlying assumptions of fire PRAs. This paper discusses an effort, under which a set of fire incidents are being reviewed in order to gain insights directly relevant to the methods, data, and assumptions that form the basis for current fire PRAs. The paper focuses on the objectives of the effort, the specific fire events being reviews methodology, and anticipated follow-on activities

Resource conversation and recovery act (RCRA) Contingency Plan for interim status or permitted units at the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

1992-08-01

The official mission of the Y-12 Plant is to serve as a manufacturing technology center for key processes such that capabilities are maintained for safe, secure, reliable, and survivable nuclear weapons systems and other applications of national importance. The Y-12 RCRA Contingency Plan will be reviewed and revised if necessary if the facility RCRA operating permits are revised, the plan is inadequate in an emergency, the procedures herein can be improved, the facility's operations change in a manner that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Preparedness Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste interim status or permitted treatment, storage, or disposal facilities. The 90-day storage areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

Plant-Based Dietary Patterns and Incidence of Type 2 Diabetes in US Men and Women: Results from Three Prospective Cohort Studies.

Directory of Open Access Journals (Sweden)

Ambika Satija

2016-06-01

Full Text Available Plant-based diets have been recommended to reduce the risk of type 2 diabetes (T2D. However, not all plant foods are necessarily beneficial. We examined the association of an overall plant-based diet and hypothesized healthful and unhealthful versions of a plant-based diet with T2D incidence in three prospective cohort studies in the US.We included 69,949 women from the Nurses' Health Study (1984-2012, 90,239 women from the Nurses' Health Study 2 (1991-2011, and 40,539 men from the Health Professionals Follow-Up Study (1986-2010, free of chronic diseases at baseline. Dietary data were collected every 2-4 y using a semi-quantitative food frequency questionnaire. Using these data, we created an overall plant-based diet index (PDI, where plant foods received positive scores, while animal foods (animal fats, dairy, eggs, fish/seafood, poultry/red meat, miscellaneous animal-based foods received reverse scores. We also created a healthful plant-based diet index (hPDI, where healthy plant foods (whole grains, fruits, vegetables, nuts, legumes, vegetable oils, tea/coffee received positive scores, while less healthy plant foods (fruit juices, sweetened beverages, refined grains, potatoes, sweets/desserts and animal foods received reverse scores. Lastly, we created an unhealthful plant-based diet index (uPDI by assigning positive scores to less healthy plant foods and reverse scores to healthy plant foods and animal foods. We documented 16,162 incident T2D cases during 4,102,369 person-years of follow-up. In pooled multivariable-adjusted analysis, both PDI and hPDI were inversely associated with T2D (PDI: hazard ratio [HR] for extreme deciles 0.51, 95% CI 0.47-0.55, p trend < 0.001; hPDI: HR for extreme deciles 0.55, 95% CI 0.51-0.59, p trend < 0.001. The association of T2D with PDI was considerably attenuated when we additionally adjusted for body mass index (BMI categories (HR 0.80, 95% CI 0.74-0.87, p trend < 0.001, while that with hPDI remained

Savannah River experience using a Cause Coding Tree to identify the root cause of an incident

International Nuclear Information System (INIS)

Paradies, M.W.; Busch, D.A.

1986-01-01

Incidents (or near misses) provide important information about plant performance and ways to improve that performance. Any particular incident may have several ''root causes'' that need to be addressed to prevent recurrence of the incident and thereby improve the safety of the plant. Also, by reviewing a large number of these incidents, one can identify trends in the root causes and generic concerns. A method has been developed at Savannah River Plant to systematically evaluate incidents, identify their root causes, record these root causes, and analyze the trends of these causes. By providing a systematic method to identify correctable root causes, the system helps the incident investigator to ask the right questions during the investigation. It also provides the independent safety analysis group and management with statistics that indicate existing and developing trouble sports. This paper describes the Savannah River Plant (SRP) Cause Coding Tree, and the differences between the SRP Tree and other systems used to analyze incidents. 2 refs., 14 figs

A basic plan for the environment-friendly aspects of improved Korean standard nuclear power plant

International Nuclear Information System (INIS)

Jung, Hoon-Seok; Lee, Yong-Koo; Kim, Kwang-Ho

2006-01-01

The Improved Korean Standard Nuclear Power Plant (KSNP+) design has been made possible on the basis of engineering experiences and referring to an in-depth analysis of the design and construction of all the domestic nuclear power plants in operation. The KSNP+ is designed for improved safety, better economics, operability and maintainability by means of advanced technology expecting to demonstrate enhanced performance. The plant also has incorporated several environmentally friendly features through the restoration of excavated areas using an ecological approach, external coloring, figure of turbine generator building and landscaping around nuclear power plant. This is the first time that KOPEC has embarked on inducing environmentally friendly features into the basic plan. This is expected to mitigate the negative perceptions held by the residents in the vicinity of nuclear power plants and will contribute to a new and improved image of nuclear power plants. (authors)

Sectorial Group for Incident Analyses (GSAI)

International Nuclear Information System (INIS)

Galles, Q.; Gamo, J. M.; Jorda, M.; Sanchez-Garrido, P.; Lopez, F.; Asensio, L.; Reig, J.

2013-01-01

In 2008, the UNESA Nuclear Energy Committee (CEN) proposed the creation of a working group formed by experts from all Spanish NPPs with the purpose of jointly analyze relevant incidents occurred in each one of the plants. This initiative was a response to a historical situation in which the exchange of information on incidents between the Spanish NPP's was below the desired level. In june 2009, UNESA's Guide CEN-29 established the performance criteria for the so called Sectorial Group for Incident Analyses (GSAI), whose activity would be coordinated by the UNESA's Group for Incident Analyses (GSAI), whose activity would be coordinated by the UNESA's Group of Operating Experience, under the Operations Commission (COP). (Author)

Decommissioning planning of Swedish nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hedin, Gunnar; Bergh, Niklas [Westinghouse Electric Sweden AB, Vaesteraes (Sweden)

2013-07-01

The technologies required for the decommissioning work are for the most part readily proven. Taken into account that there will be many more years before the studied reactor units will undergo decommissioning, the techniques could even be called conventional at that time. This will help bring the decommissioning projects to a successful closure. A national waste fund is already established in Sweden to finance amongst others all dismantling and decommissioning work. This will assure that funding for the decommissioning projects is at hand when needed. All necessary plant data are readily available and this will, combined with a reliable management system, expedite the decommissioning projects considerably. Final repositories for both long- and short-lived LILW respectively is planned and will be constructed and dimensioned to receive the decommissioning waste from the Swedish NPP:s. Since the strategy is set and well thought-through, this will help facilitate a smooth disposal of the radioactive decommissioning waste. (orig.)

Distribution, incidence and severity of yam (Dioscorea spp

African Journals Online (AJOL)

toualy

2014-01-15

Jan 15, 2014 ... incidence, severity of viral diseases, and viruses associated with the infected plants. Incidence and severity of the viral diseases were estimated based on symptoms. Enzyme-linked immunosorbent assay. (ELISA) and polymerase chain reaction (PCR)-based techniques were used for the detection of Yam.

Psychological Trauma in the Workplace: Variation of Incident Severity among Industry Settings and between Recurring vs Isolated Incidents.

Science.gov (United States)

DeFraia, G S

2015-07-01

Psychologically traumatic workplace events (known as critical incidents) occur within various work environments, with workgroups in certain industries vulnerable to multiple incidents. With the increasing prevalence of incidents in the USA, incident response is a growing practice area within occupational medicine, industrial psychology, occupational social work and other occupational health professions. To analyze a measure of incident severity based on level of disruption to the workplace and explore whether incident severity varied among different industry settings or between workgroups experiencing multiple vs single traumatic incidents. Administrative data mining was employed to examine practice data from a workplace trauma response unit in the USA. Bivariate analyses were conducted to test whether scores from an instrument measuring incident severity level varied among industry settings or between workgroups impacted by multiple vs isolated events. Incident severity level differed among various industry settings. Banks, retail stores and fast food restaurants accounted for the most severe incidents, while industrial and manufacturing sites reported less severe incidents. Workgroups experiencing multiple incidents reported more severe incidents than workgroups experiencing a single incident. Occupational health practitioners should be alert to industry differences in several areas: pre-incident resiliency training, the content of business recovery plans, assessing worker characteristics, strategies to assist continuous operations and assisting workgroups impacted by multiple or severe incidents.

Functional analysis of controbloc incidents

International Nuclear Information System (INIS)

Gouffon, A.; Jorel, M.

1992-11-01

The subject of the present paper is the survey jointly carried out in 1989 by the IPSN Safety Analysis Department and the Firm BERTIN and Co. on significant incidents related to the Controbloc system equipping the EDF 1300 MWe PWR power plants in France. This survey consisted in a general review of Controbloc operating problems, together with analysis of the safety consequences of the incidents discussed. The survey enabled improvements to be recommended in this respect and provided a basis for safety analysis

Construction engineering and planning of buildings related to the EPR

International Nuclear Information System (INIS)

Kaercher, H.

1995-01-01

Among the site-independent unit buildings are the reactor building with annulus; building for safety systems with main control room; new fuel storage pit, emergency power unit, reactor auxiliaries, access building; conventional switchgear building, and the turbine building. All buildings housing safety-related systems are protected against external and internal influences. Among the design-determining external influences are earthquakes, explosion high-pressure wave and aircraft crash. Internal incidents are caused by failure of components and pipes. The most discussed incident in the connection is the failure of the reactor pressure vessel involving core melt release which is safely retained by special devices. Earlier 3D plant models made of plastic have been replaced by 3D CAE computer models. Thus the graphic data of CAD systems have been added to the immense amount of logistic programmes/process data chains. This leads to new planning tools which are able to safely process such amounts of data and at the same time notably reduce planning time and expense. The whole data processing concept is characterized by simple, consistent data structures according to a uniform data model. It enables continual treatment throughout all planning stages and data exchange through simple, uniformly structured interfaces. (orig./HP) [de

Hypothetical accidents of light-water moderated nuclear power plants in the framework of emergency planning

International Nuclear Information System (INIS)

1979-07-01

Hypothetical accidents in nuclear power plants are events which by definition can have a devastating impact on the surroundings of the plant. Apart from an adequate plant design, the protection of the population in case of an accident is covered by the emergency planning. Of major importance are the measures for the short-term emergency protection. The decision on whether these measures are applied has to be based on appropriate measurements within the plant. The aim and achieved result of this investigation is to specify accident types. They serve as operational decision making criteria to determine the necessary measurements for analysing the accident in the accident situation, and to provide indications for choosing the suitable strategy for the protection measures. (orig.) [de

Non-linear multi-objective model for planning water-energy modes of Novosibirsk Hydro Power Plant

Science.gov (United States)

Alsova, O. K.; Artamonova, A. V.

2018-05-01

This paper presents a non-linear multi-objective model for planning and optimizing of water-energy modes for the Novosibirsk Hydro Power Plant (HPP) operation. There is a very important problem of developing a strategy to improve the scheme of water-power modes and ensure the effective operation of hydropower plants. It is necessary to determine the methods and criteria for the optimal distribution of water resources, to develop a set of models and to apply them to the software implementation of a DSS (decision-support system) for managing Novosibirsk HPP modes. One of the possible versions of the model is presented and investigated in this paper. Experimental study of the model has been carried out with 2017 data and the task of ten-day period planning from April to July (only 12 ten-day periods) was solved.

Energy and environmental studies associated to the emergency plan of natural gas thermal power plants

International Nuclear Information System (INIS)

Ferreira, Vinicius V.M.; Grynberg, Sueli E.; Aronne, Ivan D.; Jacomino, Vanusa M.F.; Branco, Otavio E.A.; Martinez, Carlos B.; Versiani, Bruno R.

2002-01-01

This work presents a first exertion to evaluate the environmental impacts due to the operation of planned gas power plants. This study was carried out with the model EcoSense, that is a computer program developed for the quantification of environmental impacts and their external costs resulting from the operation of thermal power plants or other industrial activities. EcoSense is still in development and the achieved results should still be considered with caution although it becomes clear the potentiality of the use of this tool in the support of the decision making process in energy planning. Based on the method of approach of the damage function established in the ExternE project this program provides models for an integrated evaluation of the impact rate from the air pollutants resulting from burning fossil fuel, which are transported by the air. (author)

Dryout delay in loss-of-coolant incidents in nuclear power plants

International Nuclear Information System (INIS)

Belda, W.

1975-01-01

The maximum credible accident (MCA) as a result of a fault in the system is assumed to be the rupture of a pipe in the primary circuit. During the outflow process following the rupture - called blowdown - it is possible that the internals of a reactor pressure vessel are exposed to extreme mechanical and thermal stresses. The fuel rods in the core, the Zircaloy cladding tubes of which can be heated up by lack of coolant to inadmissibly high temperatures, are particularly at risk. In case of the cladding tubes being damaged, radioactive substances are released. If they escape from the outer containment, this would lead to pressures on the immediate and more distant vicinity of the nuclear pover plant. In order to eliminate the factors of uncertainty when calculating the overall blowdown process in advance, it is necessary to have a relationship valid for the instationary circumstances to work out the burnout delay which is of decisive importance for the post-incident cooling phase of the reactor. The aim of this investigation, therefore, is to develop, with the aid of a suitable model, a method of calculating the burnout delay. (orig./TK) [de

Mound Plant Environmental Monitoring Plan

International Nuclear Information System (INIS)

Bauer, L.R.; Tullis, M.S.; Paulick, R.P.; Roush, L.L.

1994-07-01

The purpose of this Environmental Monitoring Plan (EMP) is to describe the environmental monitoring and surveillance programs in place at Mound. The Plan is required by DOE Order 5400.1 (DOE, 1990). The programs described in the EMP are required by the DOE 5400 Order series and by the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environment Surveillance (DOE 1991a), referred to as the Regulatory Guide throughout this Plan

78 FR 33255 - Amendment 4 to the Corals and Reef Associated Plants and Invertebrates Fishery Management Plan of...

Science.gov (United States)

2013-06-04

... DEPARTMENT OF COMMERCE National Oceanic and Atmospheric Administration 50 CFR Part 622 [Docket No. 120718255-3500-02] RIN 0648-BC38 Amendment 4 to the Corals and Reef Associated Plants and Invertebrates... Associated Plants and Invertebrates Fishery Management Plan (FMP) of Puerto Rico and the U.S. Virgin Islands...

Yampa River Valley sub-area contingency plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-08-01

The Yampa River Valley sub-area contingency plan (Contingency Plan) has been prepared for two counties in northwestern Colorado: Moffat County and Routt County. The Contingency Plan is provided in two parts, the Contingency Plan and the Emergency Response Action Plan (ERAP). The Contingency Plan provides information that should be helpful in planning to minimize the impact of an oil spill or hazardous material incident. It contains discussions of planning and response role, hazards identification, vulnerability analysis, risk analysis, cleanup, cost recovery, training, and health and safety. It includes information on the incident command system, notifications, response capabilities, emergency response organizations, evacuation and shelter-in-place, and immediate actions.

Development, Implementation, and Evaluation of a Strategic Plan for Improving Physical Plant Management at Southwest Texas Junior College.

Science.gov (United States)

Box, Wilford Winston

A study was conducted at Southwest Texas Junior College (STJC) to assess current management practices used by the physical plant maintenance department (PPMD) and to develop a strategic plan for physical plant management. Procedures included an analysis of current management practices and systems that affect physical resources, and periodic and…

Simulating traffic for incident management and ITS investment decisions

Science.gov (United States)

1998-08-01

UTPS-type models were designed to adequately support planning activities typical of the 1960s and 1970s. However, these packages were not designed to model intelligent transportation systems (ITS) and support incident management planning. To ov...

Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Hickey, Eva E.; Strom, Daniel J.

2005-08-01

Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

Waste Isolation Pilot Plant Dry Bin-Scale Integrated Systems Checkout Plan

International Nuclear Information System (INIS)

1991-04-01

In order to determine the long-term performance of the Waste Isolation Pilot Plant (WIPP) disposal system, in accordance with the requirements of the US Environmental Protection Agency (EPA) Standard 40 CFR 191, Subpart B, Sections 13 and 15, two performance assessment tests will be conducted. The tests are titled WIPP Bin-Scale Contact Handled (CH) Transuranic (TRU) Waste Tests and WIPP In Situ Alcove CH TRU Waste Tests. These tests are designed to measure the gas generation characteristics of CH TRU waste. Much of the waste will be specially prepared to provide data for a better understanding of the interactions due to differing degradation modes, waste forms, and repository environmental affects. The bin-scale test is designed to emplace nominally 146 bins. The majority of the bins will contain various forms of waste. Eight bins will be used as reference bins and will contain no waste. This checkout plan exercises the systems, operating procedures, and training readiness of personnel to safely carry out those specifically dedicated activities associated with conducting the bin-scale test plan for dry bins only. The plan does not address the entire WIPP facility readiness state. 18 refs., 6 figs., 3 tabs

Planning of biogas plants. A question of co-operation and negotiation; Planering av biogasanlaeggningar. En fraaga om samverkan och foerhandling

Energy Technology Data Exchange (ETDEWEB)

Khan, Jamil

2003-04-01

During the last years there has been an increased interest in Sweden to build biogas reactors. The planning of a biogas plant brings about the need for co-operation between a variety of actors. Furthermore, there are a number of different issues that need to be dealt with. To build a biogas plant is thus a rather complicated thing to do. The aim of this report is to increase the knowledge about the processes that precede a decision to build a biogas plant, in order to try to facilitate the planning of future projects. The report is based on case studies of the planning of two biogas plants in Sweden and the empirical material consists of interviews with key persons as well as written documents. In the study, three parallel processes are identified and analysed, which are all crucial to carry through a project. These are the project planning process, the political process and the application process. The most important result of the study is that there is not only one way to carry through a project and that the choice of strategy depends on the character of the project and the different questions that need to be handled. Examples of other results are: the importance of an early and continuous dialogue with the political leadership, the necessity to build an organisation for the co-operation between key actors and that the project leaders should be flexible and open to changes in the project throughout the planning process.

Psychological Trauma in the Workplace: Variation of Incident Severity among Industry Settings and between Recurring vs Isolated Incidents

Directory of Open Access Journals (Sweden)

GS DeFraia

2015-07-01

Full Text Available Background: Psychologically traumatic workplace events (known as critical incidents occur within various work environments, with workgroups in certain industries vulnerable to multiple incidents. With the increasing prevalence of incidents in the USA, incident response is a growing practice area within occupational medicine, industrial psychology, occupational social work and other occupational health professions. Objective: To analyze a measure of incident severity based on level of disruption to the workplace and explore whether incident severity varied among different industry settings or between workgroups experiencing multiple vs single traumatic incidents. Methods: Administrative data mining was employed to examine practice data from a workplace trauma response unit in the USA. Bivariate analyses were conducted to test whether scores from an instrument measuring incident severity level varied among industry settings or between workgroups impacted by multiple vs isolated events. Results: Incident severity level differed among various industry settings. Banks, retail stores and fast food restaurants accounted for the most severe incidents, while industrial and manufacturing sites reported less severe incidents. Workgroups experiencing multiple incidents reported more severe incidents than workgroups experiencing a single incident. Conclusion: Occupational health practitioners should be alert to industry differences in several areas: pre-incident resiliency training, the content of business recovery plans, assessing worker characteristics, strategies to assist continuous operations and assisting workgroups impacted by multiple or severe incidents.

[Design of a HACCP Plan for the Gouda-type cheesemaking process in a milk processing plant].

Science.gov (United States)

Dávila, Jacqueline; Reyes, Genara; Corzo, Otoniel

2006-03-01

The Hazard Analysis and Critical Control Point (HACCP) is a preventive and systematic method used to identify, assess and control of the hazards related with raw material, ingredients, processing, marketing and intended consumer in order to assure the safety of the food. The aim of this study was to design a HACCP plan for implementing in a Gouda-type cheese-making process in a dairy processing plant. The used methodology was based in the application of the seven principles of the HACCP, the information from the plant about the compliment of the pre-requisite programs (70-80%), the experience of the HACCP team and the sequence of stages settles down by the COVENIN standard 3802 for implementing the HACCP system. A HACCP plan was proposed with the scope, the selection of HACCP team, the description of the product and the intended use, the flow diagram of the process, the hazard analysis and the control table of the plan with the critical control points (CCP). The following CCP were identified in the process: pasteurization, coagulation and ripening.

Computer aided process planning at the Oak Ridge Y-12 plant: a pilot project

International Nuclear Information System (INIS)

Hewgley, R.E. Jr.; Prewett, H.P. Jr.

1979-01-01

In 1976, a formal needs analysis was conducted in one of the Fabrication Division Shops of all activities from the receipt of an order through final machining. The results indicated deficiencies in process planning activities involving special production work. A pilot program was organized to investigate the benefits of emerging CAM technology and application of GT concepts for machining operations at the Y-12 Plant. The objective of the CAPP Project was to provide computer-assisted process planning for special production machining in th shop. The CAPP team was charged with the specific goal of demonstrating computer-aided process planning within a four-year term. The CAPP charter included a plan with intermediate measurable milestones for achieving its mission. In three years, the CAPP project demonstrated benefits to process planning. A capability to retrieve historical records for similar parts, to review accurately the status of all staff assignments, and to generate detailed machining procedures definitely can impact the way in which a machine shop prepared for new orders. The real payoff is in the hardcopy output (N/C programs, studies, sequence plans, and procedures). 4 figures,

Factor analysis for imperfect maintenance planning at nuclear power plants by cognitive task analysis

International Nuclear Information System (INIS)

Takagawa, Kenichi; Iida, Hiroyasu

2011-01-01

Imperfect maintenance planning was frequently identified in domestic nuclear power plants. To prevent such an event, we analyzed causal factors in maintenance planning stages and showed the directionality of countermeasures in this study. There is a pragmatic limit in finding the causal factors from the items based on report descriptions. Therefore, the idea of the systemic accident model, which is used to monitor the performance variability in normal circumstances, is taken as a new concept instead of investigating negative factors. As an actual method for analyzing usual activities, cognitive task analysis (CTA) was applied. Persons who experienced various maintenance activities at one electric power company were interviewed about sources related to decision making during maintenance planning, and then usual factors affecting planning were extracted as performance variability factors. The tendency of domestic events was analyzed using the classification item of those factors, and the directionality of countermeasures was shown. The following are critical for preventing imperfect maintenance planning: the persons in charge should fully understand the situation of the equipment for which they are responsible in the work planning and maintenance evaluation stages, and they should definitely understand, for example, the maintenance bases of that equipment. (author)

Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

Energy Technology Data Exchange (ETDEWEB)

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-09-01

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

The management plan preparation activities nuclear power plant in Indonesia

International Nuclear Information System (INIS)

Utomo

2011-01-01

A feasibility Study that has been updated show that two nuclear power units with each unit of power up to 1000 MWe can represent decently an economical alternative energy supply. It added that the available time schedule was quite tight so that the preparation for the development must be starting first. This paper will discuss the preparation of plans of the first nuclear power plant which includes program activities, the structure of contracts, schedules of activities and funding. From the information obtained to date that in addition to a candidate site that is ready to be built in Muria peninsula is still required another potential alternative site besides to search other complete data information. This site investigation activities completed within the time schedule was passed ''critical path'', so that these activities should be carried out intensively and obey the time. This paper describes the steps that need to be prepared to welcome the first nuclear power plant, after reviewing the various input above and apply the reality in Indonesia as the initial conditions. (author)

Preliminary Hanford Waste Vitrification Plan Waste Form Qualification Plan

International Nuclear Information System (INIS)

Nelson, J.L.

1987-09-01

This Waste Form Qualification Plan describes the waste form qualification activities that will be followed during the design and operation of the Hanford Waste Vitrification Plant to ensure that the vitrified Hanford defense high-level wastes will meet the acceptance requirements of the candidate geologic repositories for nuclear waste. This plan is based on the defense waste processing facility requirements. The content of this plan is based on the assumption that the Hanford Waste Vitrification Plant high-level waste form will be disposed of in one of the geologic repository projects. Proposed legislation currently under consideration by Congress may change or delay the repository site selection process. The impacts of this change will be assessed as details of the new legislation become available. The Plan describes activities, schedules, and programmatic interfaces. The Waste Form Qualification Plan is updated regularly to incorporate Hanford Waste Vitrification Plant-specific waste acceptance requirements and to serve as a controlled baseline plan from which changes in related programs can be incorporated. 10 refs., 5 figs., 5 tabs

History of Plant Phenological Observation in Hungary and Plans for Renewal of System to detect Evidence of the Climate Change

Science.gov (United States)

Hunkar, M.; Dunkel, Z.

2009-04-01

The first plant protection warning was issued 1760 by the Senate of the Town of Debrecen concerning the destruction of caterpillar's nest. In the middle of the 19th century the first responsible Hungarian Government issued a note in which the minister takes measurements for the phytosanitary safety of agricultural products. Though Hungary had not got independent institutional system for plant protection at the end of the 19th c., still in the middle of the 1870s, the territory of the country was protected with harmonised quarantine measures from the introduction of Colorado beetle. A new era started both in Europe and in Hungary with the devastation caused by Phylloxera vastatrix in vineyards. In 1876, the Act 29 definitely specified the measures to be taken for preventing the spread of the pest and the damages caused by it; and it was proclaimed in both Chambers of the Parliament. This incident resulted basically in the launching for the establishment of an independent plant protection institution. In l880, the National Committee on Phylloxera, then in 1881, the National Experimental Station for Phylloxera was set up, this latter considered as the first nucleus of the Hungarian plant protection organisation. The international plant protection convention, concluded in 1929 and signed by our country, had a great role in the history of the development of the plant protection organisation. Hungary agreed to establish an official plant protection organization which should consist of a plant protection service and a research institute. In compliance with the Ministerial Decree 49.000/1932 the Hungarian Plant Protection Service was set up which can now be taken for the first organisation of the uniform national plant protection administration system. Plant protection stations were established in 1954. The plant phenological observation network was run by the plant protection administration but financially was maintained by OMSZ therefore the main aim of the phenological

The manual of a computer software 'FBR Plant Planning Design Prototype System'

International Nuclear Information System (INIS)

2003-10-01

This is a manual of a computer software 'FBR Plant Planning Design Prototype System', which enables users to conduct case studies of deviated FBR design concepts based on 'MONJU'. The calculations simply proceed as the user clicks displayed buttons, therefore step-by-step explanation is supposed not be necessary. The following pages introduce only particular features of this software, i.e, each interactive screens, functions of buttons and consequences after clicks, and the quitting procedure. (author)

Decommissioning Planning during the Operation of the Loviisa NPP. Planning, Management and Organizational Aspects

Energy Technology Data Exchange (ETDEWEB)

Tuunanen, J. P.; Eurajoki, T. E.E., [Fortum Power and Heat Ltd, Nuclear Waste Espoo (Finland)

2013-08-15

The first decommissioning plan for Loviisa nuclear power plant was written already in 1980's, when the plant had just started operation. The plan has been updated in 5-6 years intervals and this work still continues towards the final decommissioning plan. The decommissioning plan is based on immediate dismantling option and final disposal of decommissioning waste to the extension of the on site final disposal facility for low and intermediate level waste. The decommissioning planning has been organized as an independent project, which is realised in close cooperation with Fortum's research programme on radioactive waste management. The plant personnel are involved in the planning work through providing operating experience on contamination and activation of systems, structures and components. Later in the decommissioning phase the plant personnel will form the main part of the decommissioning organization. (author)

An incident leading to contamination of the beaches near to the British Nuclear Fuels Limited Windscale and Calder Works, Sellafield November 1983

International Nuclear Information System (INIS)

1984-01-01

The report falls into the sections: executive summary; the inquiry; background to Sellafield operations (history; statutory control); the incident in the reprocessing plant (B205) (plant description; plant procedure; lead up to the incident; detection of the incident; conclusions concerning the incident); the effect on operations in the effluent treatment plant and sea discharge plant (B242/B241) (plant description; plant procedure; events in B242/B241 following the incident in B205; conclusions concerning operations in B242/B241); the effect on operations in the medium active liquid storage plant (B211) (plant description; events in B211 following transfer of waste from B242/B241; conclusions concerning the transfer of waste to B211); environmental aspects (description of events; conclusions concerning environmental aspects); compliance with the liquid waste disposal authorisation; conclusions and recommendations. (U.K.)

The thematic plant life assessment network (PLAN)

Energy Technology Data Exchange (ETDEWEB)

Hurst, R C; McGarry, D [EC/JRC Institute for Advanced Materials, Petten (Netherlands); Pedersen, H H [Brite Euram DG XII, Brussels (Belgium)

1999-12-31

The Plant Life Assessment Network (PLAN) is a Brite Euram Type II Thematic Network, initiated by the European Commission to facilitate structured co-operation between all cost shared action projects already funded by the Commission which fall under this common technical theme. The projects involved address a multiplicity of problems associated with plant life assessment and are drawn from Brite-Euram, Standards, Measurement and Testing, Nuclear Fission Safety and Esprit EC programmes. The main aim of the Network is to initiate, maintain and monitor a fruitful co-operation process between completed, ongoing and future EC R and D projects, thereby promoting improved cross fertilization and enhanced industrial exploitation of R and D results. As the project is in its infancy, this presentation covers the background to the initiative in some detail. In particular two key aspects are highlighted, namely, the requirement of the EC to launch such a network in the area of plant life assessment including its evolution from two small Thematic Research Actions and, secondly, the mechanism for structuring the Network in an ordered and proven way along the lines of the EC/JRC European Networks, PISC, NESC, AMES, ENIQ, ENAIS and EPERC. The operating and financial structure of the Network is detailed with reference made to the role of the executive Steering Committee, The Network Project Leader and the Network Financial Co-ordinator. Each of the 58 projects involved in the Network, representing a wide range of industrial sectors and disciplines, is distributed in terms of their efforts between 4 disciplinary Clusters covering Inspection, Instrumentation and Monitoring, Structural Mechanics and Maintenance. For each of these Clusters, an expert has been appointed as a Project Technical Auditor to support the elected Cluster Co-ordinator to define Cluster Tasks, which contribute to the overall objectives of the project. From the Project Representatives, Cluster Task Leaders and

The thematic plant life assessment network (PLAN)

Energy Technology Data Exchange (ETDEWEB)

Hurst, R.C.; McGarry, D. [EC/JRC Institute for Advanced Materials, Petten (Netherlands); Pedersen, H.H. [Brite Euram DG XII, Brussels (Belgium)

1998-12-31

The Plant Life Assessment Network (PLAN) is a Brite Euram Type II Thematic Network, initiated by the European Commission to facilitate structured co-operation between all cost shared action projects already funded by the Commission which fall under this common technical theme. The projects involved address a multiplicity of problems associated with plant life assessment and are drawn from Brite-Euram, Standards, Measurement and Testing, Nuclear Fission Safety and Esprit EC programmes. The main aim of the Network is to initiate, maintain and monitor a fruitful co-operation process between completed, ongoing and future EC R and D projects, thereby promoting improved cross fertilization and enhanced industrial exploitation of R and D results. As the project is in its infancy, this presentation covers the background to the initiative in some detail. In particular two key aspects are highlighted, namely, the requirement of the EC to launch such a network in the area of plant life assessment including its evolution from two small Thematic Research Actions and, secondly, the mechanism for structuring the Network in an ordered and proven way along the lines of the EC/JRC European Networks, PISC, NESC, AMES, ENIQ, ENAIS and EPERC. The operating and financial structure of the Network is detailed with reference made to the role of the executive Steering Committee, The Network Project Leader and the Network Financial Co-ordinator. Each of the 58 projects involved in the Network, representing a wide range of industrial sectors and disciplines, is distributed in terms of their efforts between 4 disciplinary Clusters covering Inspection, Instrumentation and Monitoring, Structural Mechanics and Maintenance. For each of these Clusters, an expert has been appointed as a Project Technical Auditor to support the elected Cluster Co-ordinator to define Cluster Tasks, which contribute to the overall objectives of the project. From the Project Representatives, Cluster Task Leaders and

The Tricastin incident; L'incident du Tricastin

Energy Technology Data Exchange (ETDEWEB)

Nifenecker, H.

2008-07-01

The author comments the incident which occurred on the Tricastin site in July 2008: the release of 30 cubic meters of a uranium-containing solution. First, he recalls the international nuclear event scale, outlines that the Tricastin is not a nuclear power plant, that uranium is more a chemical toxic product than a radiological toxic product. After having briefly recalled some dose threshold values, he discusses the presence of uranium in the environment, and states that the event is actually a non-event which has been in fact magnified by the media

Preparedness for and response to a radiological or nuclear incident

International Nuclear Information System (INIS)

Norman Coleman, C.

2014-01-01

Public health and medical planning for a nuclear or radiological incident requires a complex, multi-faceted systematic approach involving federal, state and local governments, private sector organizations, academia, industry, international partners and individual experts and volunteers. The approach developed by the U.S. Department of Health and Human Services in collaboration with other U.S. Departments is the result of efforts from government and non-government experts that connect the available capabilities, resources, guidance tools, underlying concepts and science into the Nuclear Incident Medical Enterprise (NlME). It is a systems approach that can be used to support planning for, response to, and recovery from the effects of a nuclear incident. Experience is gained in exercises specific to radiation but also from other mass casualty incidents as there are many principles and components in common. Resilience and the ability to mitigate the consequences of a nuclear incident are enhanced by effective planning, preparation and training, timely response, clear communication, and continuous improvements based on new science, technology, experience and ideas. Recognizing that preparation for a radiological or nuclear incident will be a lower priority for healthcare workers and responders due to other demands, the Radiation Emergency Medical Management website has been developed with the National Library of Medicine. This includes tools for education and training, just-in-time medical management and triage among others. Most of the components of NIME are published in the peer review medical and disaster medicine literature to help ensure high quality and accessibility. While NIME is a continuous work-in-progress, the current status of the public health and medical preparedness and response for a nuclear incident is presented. (author)

Ornamental Plants of Home Garden along the Coridor of Kopendukuh Village, Banyuwangi, East Java-Indonesia as a Basis for Ecotourism Planning

Directory of Open Access Journals (Sweden)

Maic A.L. Sihombing

2015-02-01

Full Text Available Home garden is a habitat for many plants species which are important in planning and management of tourism in rural area. Ornamental plants have crucial function to increase the appearance of homes and buildings through landscaping. The purpose of this study is to analyze ornamental plants species which grow in the home garden along the corridor of Kopendukuh Village as one of the potential attractions of tourism development. The observation of ornamental plants diversity was carried out at home gardens along the rural coridor of Kopendukuh Village. Totally, there are about 10 home gardens were assessed. In each home gardens, plans species were recorded and identified systematically. Qualitative analysis was performed using analysis of sociability, vitality, and periodicity. Result of the survey confirm that home garden is home of about 40 ornamental plants species. These species came from 24 family. About 59% of the ornamental species was classified as individual plant species live in small groups, 28% of ornamental plant was classified as shrubs. About 65% of are ornamental plant without flowers and seeds.  The diversity of plants in home garden needs special attention, especially in order to increase settlement visual quality. Keywords: Kopendukuh, ornamental plant, sociability, vitality, periodicity.

Plutonium Finishing Plant (PFP) Treatment and Storage Unit Waste Analysis Plan

International Nuclear Information System (INIS)

PRIGNANO, A.L.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Plutonium Finishing Plant Treatment and Storage Unit (PFP Treatment and Storage Unit) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (4)(a) and (5). The PFP Treatment and Storage Unit is an interim status container management unit for plutonium bearing mixed waste radiologically managed as transuranic (TRU) waste. TRU mixed (TRUM) waste managed at the PFP Treatment and Storage Unit is destined for the Waste Isolation Pilot Plant (WIPP) and therefore is not subject to land disposal restrictions [WAC 173-303-140 and 40 CFR 268]. The PFP Treatment and Storage Unit is located in the 200 West Area of the Hanford Facility, Richland Washington (Figure 1). Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Ergonomics aspects of tree-planting using 'multipot' technology.

Science.gov (United States)

Giguère, D; Bélanger, R; Gauthier, J M; Larue, C

1993-08-01

The highlights of a descriptive study on the ergonomics and occupational health and safety aspects of tree-planting in Québec are presented. The study was planned to consider the most representative geographical sites, planting technologies, and planting organizations. Semi-directed interviews were made with a mixed group of 48 male and female tree-planters and physiological measurements were made on four male planters. Tools and other equipment were also examined. An analysis of the work identified the main elements of the planting cycle, and the high cardiac rate in the working planters was related more to his manual transportation of seedlings and travel on rough paths than to planting per se. A tree-planter will typically travel 2.4 km carrying 16.8 kg of material and equipment in order to plant an average of 1245 seedlings daily. One out of two interviewed planters reported having a work-related accident or incident during his or her lifetime planting career. The body parts reported most frequently injured were the lower extremities (knee, foot, ankle), the skin, the eyes, and the wrist. Recommendations on the development of appropriate tools and footwear for tree-planters and for further research on repetitive strain injury induced by tree-planting have been made.

1997 annual ground control operating plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1997-02-01

This plan presents background information and a working guide to assist Mine Operations and Engineering in developing strategies for addressing ground control issues at the Waste Isolation Pilot Plant (WIPP). With the anticipated receipt of waste in late 1997, this document provides additional detail to Panel 1 activities and options. The plan also serves as a foundation document for development and revision of the annual long-term ground control plan. Section 2.0 documents the current status of all underground excavations with respect to location, geology, geometry, age, ground support, operational use, projected life, and physical conditions. Section 3.0 presents the methods used to evaluate ground conditions, including visual observations of the roof, ribs, and floor, inspection of observation holes, and review of instrumentation data. Section 4.0 lists several ground support options and specific applications of each. Section 5.0 discusses remedial ground control measures that have been implemented to date. Section 6.0 presents projections and recommendations for ground control actions based on the information in Sections 2.0 through 5.0 of this plan and on a rating of the critical nature of each specific area. Section 7.0 presents a summary statement, and Section 8.0 includes references. Appendix A provides an overview and critique of ground control systems that have been, or may be, used at the site. Because of the dynamic nature of the underground openings and associated geotechnical activities, this plan will be revised as additional data are incorporated

Emergency planning requirements and short-term countermeasures for commercial nuclear power plants in the United States

International Nuclear Information System (INIS)

Kantor, F.; Hogan, R.; Mohseni, A.

1995-01-01

Since the accident at the Three Mile Island Unit, the United States Nuclear Regulatory's Commission (NRC's) emergency planning regulations are now considered and an important part of the regulatory framework for protecting the public health and safety. Many aspects of the countermeasures are presented: Emergency Planning Zones (EPZ), off-Site emergency planning and preparedness, responsibilities of nuclear power plants operators and states and local government. Finally, protective action recommendations are given as well as the federal response to an emergency. The authors noted that the use of potassium iodide is not considered as an effective countermeasure for the public protection in the US. (TEC). 1 fig

The nuclear emergency plans

International Nuclear Information System (INIS)

Fuertes Menendez, M. J.; Gasco Leonarte, L.; Granada Ferrero, M. J.

2007-01-01

Planning of the response to emergencies in nuclear plants is regulated by the Basic Nuclear Emergency Plan (PLABEN). This basic Plan is the guidelines for drawing up, implementing and maintaining the effectiveness of the nuclear power plant exterior nuclear emergency plans. The five exterior emergency plans approved as per PLABEN (PENGUA, PENCA, PENBU, PENTA and PENVA) place special emphasis on the preventive issues of emergency planning, such as implementation of advance information programs to the population, as well as on training exercises and drills. (Author)

Epidemiology, Incidence and Mortality of Breast Cancer in Asia.

Science.gov (United States)

Ghoncheh, Mahshid; Momenimovahed, Zohre; Salehiniya, Hamid

2016-01-01

Breast cancer is the most common malignancy in women around the world. Information on the incidence and mortality of breast cancer is essential for planning health measures. This study aimed to investigate the incidence and mortality of breast cancer in the world using age-specific incidence and mortality rates for the year 2012 acquired from the global cancer project (GLOBOCAN 2012) as well as data about incidence and mortality of the cancer based on national reports. It was estimated that 1,671,149 new cases of breast cancer were identified and 521,907 cases of deaths due to breast cancer occurred in the world in 2012. According to GLOBOCAN, it is the most common cancer in women, accounting for 25.1% of all cancers. Breast cancer incidence in developed countries is higher, while relative mortality is greatest in less developed countries. Education of women is suggested in all countries for early detection and treatment. Plans for the control and prevention of this cancer must be a high priority for health policy makers; also, it is necessary to increase awareness of risk factors and early detection in less developed countries.

Fault diagnosis technology of nuclear power plant based on weighted degree of grey incidence of optimized entropy

International Nuclear Information System (INIS)

Kong Yan; Li Zhenjie; Ren Xin; Wang Chuan

2012-01-01

Nuclear power plants (NPPs) are very complex grey system, in which faults and signs have not certain corresponding connection, so it's hard to diagnose the faults. A model based on weighted degree of grey incidence of optimized entropy was proposed according to the problem. To validate the system, some simulation experiments about the typical faults of condenser of NPPs were conducted. The results show that the system's conclusion is right, and the system's velocity is fast which can satisfy diagnosis in real time, and with the distinctive features such as good stability, high resolution rate and so on. (authors)

Hospital organizational response to the nuclear accident at Three Mile Island: implications for future-oriented disaster planning

International Nuclear Information System (INIS)

Maxwell, C.

1982-01-01

The 1979 nuclear accident at Three Mile Island (TMI) near Harrisburg, Pennsylvania, caused severe organizational problems for neighboring health care institutions. Dauphin County, just north of TMI, contained four hospitals ranging in distance from 9.5 to 13.5 miles from the stricken plant. Crash plans put into effect within 48 hours of the initial incident successfully reduced hospital census to below 50 per cent of capacity, but retained bedridden and critically ill patients within the risk-zone. No plans existed for area-wide evacuation of hospitalized patients. Future-oriented disaster planning should include resource files of host institution bed capacity and transportation capabilities for the crash evacuation of hospitalized patients during non-traditional disasters

Distribution, incidence and severity of viral diseases of yam ...

African Journals Online (AJOL)

A survey was conducted in major yam cultivation zones in Côte d'Ivoire in 2009 to determine the incidence, severity of viral diseases, and viruses associated with the infected plants. Incidence and severity of the viral diseases were estimated based on symptoms. Enzyme-linked immunosorbent assay (ELISA) and ...

From the incident command center oil spills from Hurricanes Katrina and Rita

Energy Technology Data Exchange (ETDEWEB)

Guidry, R.J. [Lousiana Oil Spill Coordinator' s Office, Baton Rouge, LA (United States)

2006-07-01

Approximately 30.2 million litres of oil were discharged during Hurricanes Katrina and Rita. A total of 230 incidents were reported to the state's spill response community, including ruptured pipelines, damaged and moved storage tanks, refineries, and sunken vessels. By January 2006, industry had reported the recovery of 14.7 million litres of oil. After Hurricane Rita, a further 234 off- and onshore incidents were reported. This paper presented a chronology from August 26 2005 through to June 2006 of clean-up activities for both hurricanes, with specific reference to logistic and communications issues associated with working in environments that are difficult to access due to damaged transportation infrastructure. An outline of the Louisiana Oil Spill Coordinator's Office's role in the incidents was presented, as well as an overview of the Louisiana State Contingency Plan. It was noted that the lack of communications systems caused considerable difficulties for responders. It was concluded that responses to hurricanes can be made more effective by having all response communities incident command structure (ICS)-trained with a thorough knowledge of the National Response Plan as it relates to the National Contingency Plan. Ensuring that plans are operational, having clear lines of authority on all hurricane-related issues, and having a robust communications plan were recommended, as well as the ability to respond without communications.

From the incident command center oil spills from Hurricanes Katrina and Rita

International Nuclear Information System (INIS)

Guidry, R.J.

2006-01-01

Approximately 30.2 million litres of oil were discharged during Hurricanes Katrina and Rita. A total of 230 incidents were reported to the state's spill response community, including ruptured pipelines, damaged and moved storage tanks, refineries, and sunken vessels. By January 2006, industry had reported the recovery of 14.7 million litres of oil. After Hurricane Rita, a further 234 off- and onshore incidents were reported. This paper presented a chronology from August 26 2005 through to June 2006 of clean-up activities for both hurricanes, with specific reference to logistic and communications issues associated with working in environments that are difficult to access due to damaged transportation infrastructure. An outline of the Louisiana Oil Spill Coordinator's Office's role in the incidents was presented, as well as an overview of the Louisiana State Contingency Plan. It was noted that the lack of communications systems caused considerable difficulties for responders. It was concluded that responses to hurricanes can be made more effective by having all response communities incident command structure (ICS)-trained with a thorough knowledge of the National Response Plan as it relates to the National Contingency Plan. Ensuring that plans are operational, having clear lines of authority on all hurricane-related issues, and having a robust communications plan were recommended, as well as the ability to respond without communications

Reevaluation of the emergency planning zone for nuclear power plants in Taiwan using MACCS2 code

International Nuclear Information System (INIS)

Wu, J.; Yang, Y.-M.; Chen, I.-J.; Chen, H.-T.; Chuang, K.-S.

2006-01-01

According to government regulations, the emergency planning zone (EPZ) of a nuclear power plant (NPP) must be designated before operation and reevaluated every 5 years. Corresponding emergency response planning (ERP) has to be made in advance to guarantee that all necessary resources are available under accidental releases of radioisotope. In this study, the EPZ for each of the three operating NPPs, Chinshan, Kuosheng, and Maanshan, in Taiwan was reevaluated using the MELCOR Accident Consequence Code System 2 (MACCS2) developed by Sandia National Laboratory. Meteorological data around the nuclear power plant were collected during 2003. The source term data including inventory, sensible heat content, and timing duration, were based on previous PRA information of each plant. The effective dose equivalent and thyroid dose together with the related individual risk and societal risk were calculated. By comparing the results to the protective action guide and related safety criteria, 1.5, 1.5, and 4.5 km were estimated for Chinshan, Kuosheng, and Maanshan NPPs, respectively. We suggest that a radius of 5.0 km is a reasonably conservative value of EPZ for each of the three operating NPPs in Taiwan

System model for evaluation of an emergency response plan for a nuclear power plant based on an assessment of nuclear emergency exercises

International Nuclear Information System (INIS)

Silva, Marcos Vinicius C.; Medeiros, Jose A.C.C.

2011-01-01

Nuclear power plants are designed and built with systems dedicated to provide a high degree of protection to its workers, the population living in their neighborhoods and the environment. Among the requirements for ensuring safety there are the existence of the nuclear emergency plan. Due to the relationship between the actions contemplated in the emergency plan and the nuclear emergency exercise, it becomes possible to assess the quality of the nuclear emergency plan, by means of emergency exercise evaluation, The techniques used in this work aim at improving the evaluation method of a nuclear emergency exercise through the use of performance indicators in the evaluation of the structures, actions and procedures involved. The proposed model enables comparisons between different moments of an emergency plan directed to a nuclear power plant as well as comparisons between plans dedicated to different facilities. (author)

System model for evaluation of an emergency response plan for a nuclear power plant based on an assessment of nuclear emergency exercises

Energy Technology Data Exchange (ETDEWEB)

Silva, Marcos Vinicius C.; Medeiros, Jose A.C.C. [Universidade Federal do Rio de Janeiro (PEN/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Engenharia Nuclear

2011-07-01

Nuclear power plants are designed and built with systems dedicated to provide a high degree of protection to its workers, the population living in their neighborhoods and the environment. Among the requirements for ensuring safety there are the existence of the nuclear emergency plan. Due to the relationship between the actions contemplated in the emergency plan and the nuclear emergency exercise, it becomes possible to assess the quality of the nuclear emergency plan, by means of emergency exercise evaluation, The techniques used in this work aim at improving the evaluation method of a nuclear emergency exercise through the use of performance indicators in the evaluation of the structures, actions and procedures involved. The proposed model enables comparisons between different moments of an emergency plan directed to a nuclear power plant as well as comparisons between plans dedicated to different facilities. (author)

Detailed semantic analyses of human error incidents occurring at nuclear power plant in USA (interim report). Characteristics of human error incidents occurring in the period from 1992 to 1996

International Nuclear Information System (INIS)

Hirotsu, Yuko; Tsuge, Tadashi; Sano, Toshiaki; Takano, Kenichi; Gouda, Hidenori

2001-01-01

CRIEPI has been conducting detailed analyses of all human error incidents at domestic nuclear power plants (NPPs) collected from Japanese Licensee Event Reports (LERs) using J-HPES (Japanese version of HPES) as an analysis method. Results obtained by the analyses have been stored in J-HPES database. Since 1999, human error incidents have been selected from U.S. LERs, and they are analyzed using J-HPES. In this report, the results, which classified error action, cause, and preventive measure, are summarized for U.S. human error cases occurring in the period from 1992 to 1996. It was suggested as a result of classification that the categories of error action were almost the same as those of Japanese human error cases. Therefore, problems in the process of error action and checkpoints for preventing errors will be extracted by analyzing both U.S. and domestic human error cases. It was also suggested that the interrelations between error actions, causes, and organizational factors could be identified. While taking these suggestions into consideration, we will continue to analyze U.S. human error cases. (author)

B Plant Complex waste management training plan. Revision 1

International Nuclear Information System (INIS)

Beam, T.G.

1994-01-01

This training program is designed to comply with all applicable federal, state and US Department of Energy-Richland Operations Office training requirements. The training program complies with requirements contained within WAC 173-303-330 for the development of a written dangerous waste training program. The training program is designed to prepare personnel to manage and maintain waste treatment, storage and disposal (TSD) units, as well as generator units, in a safe, effective, efficient and environmentally sound manner. In addition to preparing employees to manage and maintain TSD and generator units under normal conditions, the training program ensures that employees are prepared to respond in a prompt and effective manner should an emergency occur. The training plan also identifies specific individuals holding key waste management positions at B Plant Complex

Meticulous plans make plant sail

International Nuclear Information System (INIS)

Anon.

1984-01-01

It takes about five years for a top nuclear builder in the US to bring in a new plant. In Japan, they'd already be working on the second unit. The reasons why the Japanese can construct a nuclear power plant 2-7 years ahead of their US counterparts is discussed

Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 3

International Nuclear Information System (INIS)

G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

2006-01-01

This is the 2006 update (Revision 3) of the NGNP Materials Research and Development Program Plan. This law established that the U.S Department of Energy (DOE) Secretary of Energy shall establish a ''Next Generation Nuclear Plant'' (NGNP) project. The NGNP project named in the Act was given the following attributes and guiding principles to manage its development: (1) The NGNP consists of research, development, design (R and DD), construction, and operation of a prototype reactor to generate electricity and hydrogen; (2) The project shall be managed by the DOE Office of Nuclear Energy; (3) The Idaho National Laboratory (INL) shall be the lead DOE laboratory for the NGNP; (4) The INL shall establish collaborations with selected institutions of higher education, other research institutes and international researchers; (5) The INL shall organize an industrial consortium of partners for cost-shared R and DD, construction; (6) The project shall be sited at the INL; (7) The project shall be licensed by the Nuclear Regulatory Commission (NRC) and by July, 2008 the NRC and DOE shall jointly submit a licensing strategy to Congress; (8) The project shall be organized to maximize technical interchange with the nuclear power industry, nuclear power plant construction firms, the chemical process industry and to seek international cooperation, participation and contributions; (9) The Nuclear Energy Research Advisory Committee (NERAC) shall review all program plans for the NGNP; (10) Phase 1 of the project (selection of hydrogen production technology, conduct R and DD and initial design activities) shall be completed no later than September 30, 2011; (11) Phase 2 of the project (continue R and DD, develop final design, apply for a license, construct and start operations) shall be completed by September 30, 2021; and (12) Provision for authorization of appropriations was made. As a result of the direction provided, the INL and the DOE issued an NGNP Preliminary Project Management

78 FR 53155 - Endangered and Threatened Wildlife and Plants; Recovery Plan for Phyllostegia hispida; Addendum...

Science.gov (United States)

2013-08-28

... downlisting and delisting of the species and its removal from the Federal List of Endangered and Threatened..., the species must be managed to control threats (e.g., feral ungulates and invasive plants) and be... availability of our final recovery plan for Phyllostegia hispida (no common name) under the Endangered Species...

Planning of occupational dose reduction at BWR power plant by past dose record analysis combined with on-site workers' idea analysis

International Nuclear Information System (INIS)

Konno, T.; Taira, J.; Hayashida, T.; Suzuki, A.; Hayashi, K.; Kato, S.; Ishikawa, T.; Konno, T.; Hayashi, K.

2011-01-01

In order to establish a plan for occupational dose reduction at operating plants, outage inspection works that involve high-dose exposure were selected and a determination of the major causes of high-dose exposure made by plant-by-plant comparison of doses received during inspection works. The comparison was made to investigate the relationship between exposure and the volume of objects to be inspected, working time and man-hour of each work process and ambient dose rates at work areas. In parallel with this, an analysis has also been carried out on 400 data items in a questionnaire survey conducted on relevant individuals, including foremen, radiation safety personnel, on-site workers and plant designers regarding ideas for dose reduction methods. With combination of these two analyses, matters that require improvement will be highlighted, then modification of equipment or revision of work procedures necessary for occupational dose reduction will be planned by plant designers through review. (authors)

Organizational factors and nuclear power plant safety

International Nuclear Information System (INIS)

Haber, S.B.

1995-01-01

There are many organizations in our society that depend on human performance to avoid incidents involving significant adverse consequences. As our culture and technology have become more sophisticated, the management of risk on a broad basis has become more and more critical. The safe operation of military facilities, chemical plants, airlines, and mass transit, to name a few, are substantially dependent on the performance of the organizations that operate those facilities. The nuclear power industry has, within the past 15 years, increased the attention given to the influence of human performance in the safe operation of nuclear power plants (NPP). While NPPs have been designed through engineering disciplines to intercept and mitigate events that could cause adverse consequences, it has been clear from various safety-related incidents that human performance also plays a dominant role in preventing accidents. Initial efforts following the 1979 Three Mile Island incident focused primarily on ergonomic factors (e.g., the best design of control rooms for maximum performance). Greater attention was subsequently directed towards cognitive processes involved in the use of NPP decision support systems and decision making in general, personnel functions such as selection systems, and the influence of work scheduling and planning on employees' performance. Although each of these approaches has contributed to increasing the safety of NPPS, during the last few years, there has been a growing awareness that particular attention must be paid to how organizational processes affect NPP personnel performance, and thus, plant safety. The direct importance of organizational factors on safety performance in the NPP has been well-documented in the reports on the Three Mile Island and Chernobyl accidents as well as numerous other events, especially as evaluated by the U.S. Nuclear Regulatory Commission (NRC)

76 FR 3648 - NIMS Training Plan

Science.gov (United States)

2011-01-20

...] NIMS Training Plan AGENCY: Federal Emergency Management Agency, DHS. ACTION: Notice of availability... comments on the NIMS Training Plan. This plan defines National Incident Management System (NIMS) national... sustaining NIMS training. In addition to delineating responsibilities and actions, the NIMS Training Plan...

Program plan for future regulatory activity in nuclear-power-plant maintenance

International Nuclear Information System (INIS)

Badalamente, R.V.

1982-10-01

The intent of this paper is to describe the results of a study of nuclear power plant (NPP) maintenance conducted by Battelle's Pacific Northwest Laboratories (PNL) for the Nuclear Regulatory Commission (NRC). The purpose of the study for the NRC was to determine problems affecting human performance in NPP maintenance, pinpoint those which adversely affect public health and safety, review strategies for overcoming the problems, and suggest the direction that regulatory activities should take. Results of the study were presented to the NRC (Division of Human Factors Safety) in the form of a recommended program plan for future regulatory activity in NPP maintenance

Incidence of ozone symptoms on vegetation within a National Wildlife Refuge in New Jersey, USA

International Nuclear Information System (INIS)

Davis, Donald D.; Orendovici, Teodora

2006-01-01

During 1993-1996 and 2001-2003, we evaluated the percentage of plants (incidence) exhibiting ozone-induced foliar symptoms on vegetation within a National Wildlife Refuge located along the Atlantic Ocean coast of New Jersey, USA. Incidence varied among plant species and years. Bioindicator plants most sensitive to ozone, across all years, included native common milkweed (Asclepias syriaca) and wild grape (Vitis spp.), as well as introduced tree-of-heaven (Ailanthus altissima). Less sensitive bioindicators included Virginia creeper (Parthenocissus quinquefolia) and winged sumac (Rhus coppolina). Black cherry (Prunus serotina) and sassafras (Sassafras albidum) were least sensitive. The greatest incidence of ozone symptoms, across all plant species, occurred in 1996, followed by 2001 > 1995 > 1994 > 1993 > 2003 > 2002. A model was developed that showed a statistically significant relationship between incidence of ozone symptoms and the following parameters: plant species, Palmer Drought Severity Index, and the interaction of W126 x N100 measures of ambient ozone. - Vegetation in a National Wildlife Refuge containing a Class I wilderness area exhibits foliar symptoms from ambient ozone

Incidence of ozone symptoms on vegetation within a National Wildlife Refuge in New Jersey, USA

Energy Technology Data Exchange (ETDEWEB)

Davis, Donald D. [Department of Plant Pathology, Ecology Program, Penn State Institutes of the Environment, Pennsylvania State University, University Park, PA 16803 (United States)]. E-mail: ddd2@psu.edu; Orendovici, Teodora [Department of Plant Pathology, Ecology Program, Penn State Institutes of the Environment, Pennsylvania State University, University Park, PA 16803 (United States)

2006-10-15

During 1993-1996 and 2001-2003, we evaluated the percentage of plants (incidence) exhibiting ozone-induced foliar symptoms on vegetation within a National Wildlife Refuge located along the Atlantic Ocean coast of New Jersey, USA. Incidence varied among plant species and years. Bioindicator plants most sensitive to ozone, across all years, included native common milkweed (Asclepias syriaca) and wild grape (Vitis spp.), as well as introduced tree-of-heaven (Ailanthus altissima). Less sensitive bioindicators included Virginia creeper (Parthenocissus quinquefolia) and winged sumac (Rhus coppolina). Black cherry (Prunus serotina) and sassafras (Sassafras albidum) were least sensitive. The greatest incidence of ozone symptoms, across all plant species, occurred in 1996, followed by 2001 > 1995 > 1994 > 1993 > 2003 > 2002. A model was developed that showed a statistically significant relationship between incidence of ozone symptoms and the following parameters: plant species, Palmer Drought Severity Index, and the interaction of W126 x N100 measures of ambient ozone. - Vegetation in a National Wildlife Refuge containing a Class I wilderness area exhibits foliar symptoms from ambient ozone.

Participation of the ININ in the external radiological emergency plan of the Laguna Verde power plant; Participacion del ININ en el plan de emergencia radiologica externo de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Martinez S, R; Cervini L, A [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1991-07-01

The planning of performances in radiological emergencies, with the object of reducing the consequences as much as possible on the population to accidental liberations of radioactive material coming from Nuclear power plant, it has been of main interest in the nuclear community in the world. In Mexico it has not been the exception, since with the setting in march of the Laguna Verde nuclear power plant exists an executive program of planning for emergencies that it outlines the activities to follow trending to mitigate the consequences that are derived of this emergency. As integral part of this program this the External Plan of Radiological Emergency (PERE) that covers the emergencies that could leave the frontiers of the Laguna Verde power plant. In the PERE it settles down the planning, address and control of the preparation activities, response and recovery in emergencies, as well as the organization and coordination of the institutions that participate. The National Institute of Nuclear Research (ININ), like integral part of these institutions in the PERE, has an infrastructure that it allows to participate in the plan in a direct way in the activities of 'Control of the radiological exhibition the response personnel and control of water and foods' and of support way and consultant ship in the activities of 'Monitoring, Classification and decontamination of having evaluated' and 'Specialized medical radiological attention'. At the moment the ININ has a radiological mobile unit and this conditioning a second mobile unit to carry out part of the activities before mentioned; also accounts with 48 properly qualified people that directly intervene in the plan. In order to guarantee an adequate response in the PERE an organization it has been structured like that of the annex as for the personnel, transport, team, procedures and communication system, with the objective always of guaranteeing the security and the population's health in emergency situations in the

A five-year history of hazardous materials incidents in Chester County, PA

International Nuclear Information System (INIS)

Shorten, C.V.; McNamara, J.

1993-01-01

The Emergency Planning and Community Right-to-Know Act (EPCRA) of 1986 established Local Emergency Planning Committees (LEPCs) to oversee emergency response planning at the community level. In Pennsylvania, each county was assigned its own LEPC, and Chester County held its first LEPC meeting on October 15, 1987. From the data of that meeting through September 1992, 300 hazardous materials incidents have been reported. The majority of these incidents were met with fire department response, but several warranted response by hazardous materials teams. This report presents an analysis of the database of reported hazardous materials incidents in Chester County, including chemical identification, amount released, type of response, location, and trends. Over 235 of the reported spills were either gasoline, diesel fuel, home heating oil, or kerosene, often in five to 50 gallon amounts from transportation accidents. A number of extremely hazardous substance (EHS) incidents were reported, however, including sulfuric acid, chlorine, ammonia, phosphorus, formaldehyde, bromine, methyl mercaptan, and hydrofluoric acid. The most commonly released EHS's were ammonia and chlorine. The number of hazardous materials incidents reported in Chester County increased from only 14 in 1988 to 95 in 1991, with 67 in 1992 through September. This dramatic increase is attributable to both increased reporting and an increased number of incidents. This database clearly indicates both the success of EPCRA reporting system and the magnitude of hazardous materials incidents in this part of Pennsylvania

Resource Conservation and Recovery Act (RCRA) contingency plan for hazardous waste treatment, storage, and disposal units at the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

1994-08-01

The Y-12 RCRA Contingency Plan will be continually reviewed and revised if any of the following occur: the facility permit is revised, the plan is inadequate in an emergency, the procedures can be improved, the operations of the facility change in a way that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Management Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste treatment, storage, or disposal units. The 90-day accumulation areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

Incidence of Listeria spp. in Ready-to-Eat Food Processing Plant Environments Regulated by the U.S. Food Safety and Inspection Service and the U.S. Food and Drug Administration.

Science.gov (United States)

Reinhard, Robert G; Kalinowski, Robin M; Bodnaruk, Peter W; Eifert, Joseph D; Boyer, Renee R; Duncan, Susan E; Bailey, R Hartford

2018-06-07

A multiyear survey of 31 ready-to-eat (RTE) food processing plants in the United States was conducted to determine the incidence of Listeria spp. in various RTE production environments. Samples were collected from 22 RTE plants regulated by the U.S. Department of Agriculture's Food Safety and Inspection Service (FSIS) and from 9 RTE food plants regulated by the U.S. Department of Health and Human Services' Food and Drug Administration (FDA). Only nonfood contact surfaces in the RTE manufacturing areas with exposed RTE product were sampled. Each sample was individually analyzed for the presence of Listeria spp. by using a PCR-based rapid assay. In total, 4,829 samples were collected from various locations, including freezers, equipment framework, floors, walls, wall-floor junctures, drains, floor mats, doors, and cleaning tools. Nine (29%) of the facilities had zero samples positive for Listeria spp. in the production environment, whereas 22 (71%) had one or more samples positive for Listeria spp. The total incidence of Listeria spp. in all RTE food plants was 4.5%. The positive rate in plants regulated by the FSIS ranged from 0 to 9.7%, whereas the positive rate in plants regulated by the FDA ranged from 1.2 to 36%.

Phased Restoration Plan for Degraded Land in North Korea by the Clustered Distribution Pattern of Suitable Afforestation Plants

Science.gov (United States)

Lee, S. G.; Lee, W. K.; Choi, H. A.; Yoo, H.; Song, C.; Son, Y.; Cha, S.; Bae, S. W.

2017-12-01

Degraded forest of North Korea (DPRK; The Democratic People's Republic of Koprea) is not only confined itself, it could cause serious problem in Korean Peninsula. The importance of restoration for degraded land has increased to improve an healthy ecosystem and solve a shortage of food in North Korea lately. On the other hand, although effort of North Korea government, degraded problem have consistently got worse. There are two main reasons it does not show effectively. The most critical one is absence of technique and information to restore, they concentrate urgent problem which is related to a poor food supply. The other problem is that they demand an efficiency plan in a short period. In these aspect, this study aims selecting suitable tree by spatial characteristics and establishing phased restoration plan to support policy decision about a degraded land in North Korea. The suitable tree for restoration is taken from references which involve natural plant distribution of North and South Korea (ROK; Republic of Korea). Optimal environmental predicted map is deducted from accumulated data of plant physiology whose endemic environmental optimal range individually. It is integrated a map by order of priorities that first is suitable tree species according to the region, and second is clustering distribution rate in a same species. The two types of priority is applied to weighting method. The research result shows that 23 afforestation species fit to restore, and lager distributed plants agree with the major species in Korean Peninsula. The integrated map considers weight of priorities, and it appears that Picea jezoensis is matched the widest. The integrated map shows a view of suitable restoration according to the space, but this is finespun to utilize in a policy. Therefore It provides 3 step plan to support policy decision by Block Statistics, as 12.5km (long-term general plan), 5km (medium-term detailed plan), 1km (short-term implementation plan).

Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography

Energy Technology Data Exchange (ETDEWEB)

Youngen, G.

1988-10-01

The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant`s operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ``onsite`` response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world`s collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously.

Cancer incidence in an area contaminated with radionuclides near a nuclear installation

International Nuclear Information System (INIS)

Johnson, C.J.

1981-01-01

Exposures of a large population in the Denver area to plutonium and other radionuclides in the exhaust plumes from the Rocky Flats (nuclear weapons) plant date back to 1953. Anglo cancer incidence in 1969-1971 was evaluated in census tracts with and without contamination in the Denver area (1970 pop. 1 019 130). Cancer incidence in males was 24% higher, and in females, 10% higher in the suburban area(pop. 154 170) with most contamination nearest the plant, compared to the unexposed area (pop. 423 870), also predominantly suburban, which had virtually the same age-adjusted incidence rate for all cancer as the state. Excess cases of cancer were due to more cases than expected of leukemia, lymphoma and myeloma and cancer of the lung, thyroid, breast, esophagus, stomach and colon, a pattern similar to that obs- erved in the survivors of Hiroshima and Nagasaki. The ratio of these cancers to all other cancer was 17.6% higher in males and 11.9% higher in females in the area near the plant. Cancer of the gonads (especially the testes), liver, and, in females, pancreas and brain contributed to the higher incidence of all cancer in areas near the plant. (Auth.)

Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). DOE plans to conduct experiments in the WIPP during a Test Phase of approximately 5 years. These experiments will be conducted to reduce the uncertainties associated with the prediction of several processes (e.g., gas generation) that may influence repository performance. The results of the experiments will be used to assess the ability of the WIPP to meet regulatory requirements for the long-term protection of human health and the environment from the disposal of TRU wastes. 37 refs., 25 figs., 18 tabs

Analysis of offsite Emergency Planning Zones (EPZs) for the Rocky Flats Plant

International Nuclear Information System (INIS)

Petrocchi, A.J.; Zimmerman, G.A.

1994-01-01

During Phase 3 of the EPZ project, a sitewide analysis will be performed applying a spectrum-of-accidents approach to both radiological and nonradiological hazardous materials release scenarios. This analysis will include the MCA but will be wider in scope and will produce options for the State of Colorado for establishing a bounding EPZ that is intended to more comprehensively update the interim, preliminary EPZ developed in Phase 2. EG ampersand G will propose use of a hazards assessment methodology that is consistent with the DOE Emergency Management Guide for Hazards Assessments and other methods required by DOE orders. This will include hazards, accident, safety, and risk analyses. Using this methodology, EG ampersand G will develop technical analyses for a spectrum of accidents. The analyses will show the potential effects from the spectrum of accidents on the offsite population together with identification of offsite vulnerable zones and areas of concern. These analyses will incorporate state-of-the-art technology for accident analysis, atmospheric plume dispersion modeling, consequence analysis, and the application of these evaluations to the general public population at risk. The analyses will treat both radiological and nonradiological hazardous materials and mixtures of both released accidentally to the atmosphere. DOE/RFO will submit these results to the State of Colorado for the State's use in determining offsite emergency planning zones for the Rocky Flats Plant. In addition, the results will be used for internal Rocky Flats Plant emergency planning

The National Institute of Nuclear Research (ININ) and its participation in the External Radiological Emergency Plans at Laguna Verde Power plant

International Nuclear Information System (INIS)

Suarez, G.

1998-01-01

In this article it is described the form in which the ININ participates in the External Radiological Emergency Plan at Laguna Verde Power plant. It is set the objective, mission and organization of this plan. The responsibilities and activities that plan has assigned are mentioned also the organization to fulfil them and the obtained results during 9 years of participation. (Author)

Nuclear fuel reprocessing deactivation plan for the Idaho Chemical Processing Plant, Revision 1

International Nuclear Information System (INIS)

Patterson, M.W.

1994-10-01

The decision was announced on April 28, 1992 to cease all United States Department of Energy (DOE) reprocessing of nuclear fuels. This decision leads to the deactivation of all fuels dissolution, solvent extraction, krypton gas recovery operations, and product denitration at the Idaho Chemical Processing Plant (ICPP). The reprocessing facilities will be converted to a safe and stable shutdown condition awaiting future alternate uses or decontamination and decommissioning (D ampersand D). This ICPP Deactivation Plan includes the scope of work, schedule, costs, and associated staffing levels necessary to achieve a safe and orderly deactivation of reprocessing activities and the Waste Calcining Facility (WCF). Deactivation activities primarily involve shutdown of operating systems and buildings, fissile and hazardous material removal, and related activities. A minimum required level of continued surveillance and maintenance is planned for each facility/process system to ensure necessary environmental, health, and safety margins are maintained and to support ongoing operations for ICPP facilities that are not being deactivated. Management of the ICPP was transferred from Westinghouse Idaho Nuclear Company, Inc. (WINCO) to Lockheed Idaho Technologies Company (LITCO) on October 1, 1994 as part of the INEL consolidated contract. This revision of the deactivation plan (formerly the Nuclear Fuel Reprocessing Phaseout Plan for the ICPP) is being published during the consolidation of the INEL site-wide contract and the information presented here is current as of October 31, 1994. LITCO has adopted the existing plans for the deactivation of ICPP reprocessing facilities and the plans developed under WINCO are still being actively pursued, although the change in management may result in changes which have not yet been identified. Accordingly, the contents of this plan are subject to revision

Test to prove the resistance to incidents of components of electric and control systems in the safety containment of nuclear power plants

International Nuclear Information System (INIS)

1982-01-01

The marginal program for proving the suitability of safety-relevant components of electric and control systems in the safety containment during a loss-of-coolant incident is described. Variant test conditions are established in the component-specific test program. Special attention has been paid to the representation of the course of pressure and temperature for the performance test of the valve room of the Nuclear Power Plant Philippsburg 2. (DG) [de

Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 4. Radiological emergency response planning for nuclear power plants in California

International Nuclear Information System (INIS)

Yen, W.W.S.

1977-01-01

This report reviews the state of emergency response planning for nuclear power plants in California. Attention is given to the role of Federal agencies, particularly the Nuclear Regulatory Commission, in planning for both on and off site emergency measures and to the role of State and local agencies for off site planning. The relationship between these various authorities is considered. Existing emergency plans for nuclear power plants operating or being constructed in California are summarized. The developing role of the California Energy Resources Conservation and Development Commission is examined

Using ProModel as a simulation tools to assist plant layout design and planning: Case study plastic packaging factory

OpenAIRE

Pochamarn Tearwattanarattikal; Suwadee Namphacharoen; Chonthicha Chamrasporn

2008-01-01

This study is about the application of a Simulation Model to assist decision making on expanding capacity and plant layout design and planning. The plant layout design concept is performed first to create the physical layouts then the simulation model used to test the capability of plant to meet various demand forecast scena. The study employed ProModel package as a tool, using the model to compare the performances in term of % utilization, characteristics of WIP and ability to meet due date....

Answering the request for emergency assistance worldwide. The Incident and Emergency Centre (IEC)

International Nuclear Information System (INIS)

2007-01-01

In 2005, the IAEA announced the establishment of a fully integrated Incident and Emergency Centre (IEC). The functions of the IEC include coordinating prompt assistance to requesting States in the case of a nuclear security incident. As the global focal point for international preparedness, communication and response to nuclear and radiological incidents or emergencies irrespective of their cause, the IEC stands at the centre of coordinating effective and efficient activities worldwide. The IEC's work includes the evaluation of emergency plans and assistance in their development. The Centre also develops accident classifications based on plant conditions and supports effective communication between neighbouring countries. In addition, it develops various response procedures and facilitates national exercises on response to reactor emergencies. This includes training a broad range of IAEA staff to respond to emergencies as well as training of external experts. Response to incidents and emergencies can involve the exchange of information, provision of advice and/or the coordination of field response. In order to coordinate a global response, the IEC hosts a Response Assistance Network (RANET) under which Member States, Parties to the Emergency Conventions and relevant international organizations are able to register their response capabilities. This network aims to facilitate assistance in case of a nuclear or radiological incident or emergency in a timely and effective manner. An important component of the global emergency response system is the notification and reporting arrangements and systems operated by the IEC. The IEC operates systems that are reliable and secure. Member States, Non-Member States and international organizations have historically reported events and requests for assistance to the IAEA through the ENATOM arrangements using the ENAC web site, phone or fax. Under these arrangements, States have nominated Competent Authorities and National Warning

The national response plan and radioactive incident monitoring network (RIMNET)

International Nuclear Information System (INIS)

Jones, M.W.

1989-01-01

The Department of the Environment is responsible through Her Majesty's Inspectorate of Pollution for co-ordination of the Government's response to overseas nuclear incidents. This paper describes the contingency arrangements that have been set up for this purpose. (author)

Resource Conservation and Recovery Act (RCRA) general contingency plan for hazardous waste treatment, storage, and disposal units at the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

Skaggs, B.E.

1993-11-01

The Y-12 RCRA Contingency Plan will be continually reviewed and revised if any of the following occur: the facility permit is revised, the plan is inadequate in an emergency, the procedures herein can be improved, the operations of the facility change in a way that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Management Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste treatment, storage, or disposal units. The 90-day accumulation areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

Incidence of plant cover over the autotrophic nitrifying bacteria population in a fragment of Andean forest

International Nuclear Information System (INIS)

Gonzalez, Xiomara; Gonzalez, L; Varela, A; Ahumada, J A

1999-01-01

It was determined the incidence of plant cover (forest vs. pasture), on the autotrophy nitrifying bacteria, through the effect of biotic factors (radical exudate) and abiotic factors (temperature, ph and humidity), in a high mountain cloud forest fragment. The site of study was located near La Mesa (Cundinamarca) municipality. The temperature of soil was measured in situ, and soil samples were collected and carried to the laboratory for pH and humidity percentage measurements. Serial soil dilution method was used for plating samples on a selective culture medium with ammonium sulphate as nitrogen source, in order to estimate the autotrophic nitrifying bacteria population levels. Grown colonies were examined macro and microscopically. The quantity of nitrates produced by bacteria cultured in vitro was determined spectra-photometrical. In relation to the abiotic factors, there was no significant differences of pH between both plant covers, but there were significant for soil humidity and temperature (p<0.05). There were highly significant differences with respect to the bacteria population levels (p<0.0001) and with respect to nitrate production. This suggests a higher bacterial activity in the under forest cover. The radical exudate from both types of plant cover reduced the viability of bacteria in vitro, from 1:1 to 1:30 exudate bacteria proportions. In the soils physical and chemical analysis, it was found a higher P and Al concentrations, and a higher CIC and organic matter content under the forest cover. It is suggested the importance of this functional group in this ecosystem

Computerized radiation treatment planning

International Nuclear Information System (INIS)

Laarse, R. van der.

1981-01-01

Following a general introduction, a chain consisting of three computer programs which has been developed for treatment planning of external beam radiotherapy without manual intervention is described. New score functions used for determination of optimal incidence directions are presented and the calculation of the position of the isocentre for each optimum combination of incidence directions is explained. A description of how a set of applicators, covering fields with dimensions of 4 to 20 cm, for the 6 to 20 MeV electron beams of a MEL SL75-20 linear accelerator was developed, is given. A computer program for three dimensional electron beam treatment planning is presented. A microprocessor based treatment planning system for the Selectron remote controlled afterloading system for intracavitary radiotherapy is described. The main differences in treatment planning procedures for external beam therapy with neutrons instead of photons is discussed. A microprocessor based densitometer for plotting isodensity lines in film dosimetry is described. A computer program for dose planning of brachytherapy is presented. Finally a general discussion about the different aspects of computerized treatment planning as presented in this thesis is given. (Auth.)

Lesson learned from two radiological incidents in industrial radiography in Iran

International Nuclear Information System (INIS)

Samimi, Bijan; Deevband Mohammad, Reza; Kardan Mohammad, Reza; Eshraghi, Ahmad

2006-01-01

This paper discussed two incidents occurred in Iran, follow-up investigations as well as lessons learned. Two Industrial Gamma Radiography Projectors (I.G.R.P.) included Ir-192 source with activities 24 and 30 Curies respectively were stolen. One of them was stolen in an industrial area with high security provision and the other one has been stolen at the home town without any security provision. The lessons learned from these incidents are discussed and the results are proposed as recommendations. Investigations show that the reasons for these incidents are as follows: 1. Insufficient training programs for radiographers. 2. Lack of specific emergency procedure for this type of incident in the company. 3. Not efficient National Emergency Plan for this type of threat. 4. Lack of technical and administrative measures to separate radioactive sources from unauthorized persons. 5. Lack of security plan in the company. 6. Insufficient supervision of Radiation Protection Officer (R.P.O.) or responsible person at the site. (authors)

Lesson learned from two radiological incidents in industrial radiography in Iran

Energy Technology Data Exchange (ETDEWEB)

Samimi, Bijan; Deevband Mohammad, Reza; Kardan Mohammad, Reza; Eshraghi, Ahmad [National Radiation Protection Department (NRPD) Atomic Energy Organization of Iran (AEOI) (Iran, Islamic Republic of)

2006-07-01

This paper discussed two incidents occurred in Iran, follow-up investigations as well as lessons learned. Two Industrial Gamma Radiography Projectors (I.G.R.P.) included Ir-192 source with activities 24 and 30 Curies respectively were stolen. One of them was stolen in an industrial area with high security provision and the other one has been stolen at the home town without any security provision. The lessons learned from these incidents are discussed and the results are proposed as recommendations. Investigations show that the reasons for these incidents are as follows: 1. Insufficient training programs for radiographers. 2. Lack of specific emergency procedure for this type of incident in the company. 3. Not efficient National Emergency Plan for this type of threat. 4. Lack of technical and administrative measures to separate radioactive sources from unauthorized persons. 5. Lack of security plan in the company. 6. Insufficient supervision of Radiation Protection Officer (R.P.O.) or responsible person at the site. (authors)

Quality assurance in the planning and construction of components for nuclear power plants and large chemical plants

International Nuclear Information System (INIS)

Doerling

1975-01-01

High safety technical requirements must be demanded of the components of these plants to avoid economical hazards and to protect life and health. These requirements necessitate that each phase of the task completion, i.e. in planning, construction, fabrication and assembly, be carried out systematically and totally in order to produce a component with optimum quality. Quality assurance cannot then merely be a quality control in a conventional sense carried out during fabrication. It is much more an aimed procedure which is oriented to the functional requirements of the components - or rather to the function carrier. The concept presented on the quality assurance gives me the right as a constructor to treat this subject. (orig./LH) [de

Plan for support of large-plant (post-CRBR) needs in large-leak sodium-water reaction area

International Nuclear Information System (INIS)

Whipple, J.C.

1980-03-01

Work in the large leak test and analysis area of steam generator development has been carried out at GE-ARSD under 189a SG037 since 1973. The currently planned master schedule for the SG037 program is shown. Principal activities are the large leak testing program being carried out at the Large Leak Test Rig and the analysis methods development. The plan for supporting the large plant (post-CRBR) needs in the large leak sodium-water reaction area is outlined. Most of the needs will be answered in the current SG037 large leak program

Literature review on medical incident command.

Science.gov (United States)

Rimstad, Rune; Braut, Geir Sverre

2015-04-01

It is not known what constitutes the optimal emergency management system, nor is there a consensus on how effectiveness and efficiency in emergency response should be measured or evaluated. Literature on the role and tasks of commanders in the prehospital emergency services in the setting of mass-casualty incidents has not been summarized and published. This comprehensive literature review addresses some of the needs for future research in emergency management through three research questions: (1) What are the basic assumptions underlying incident command systems (ICSs)? (2) What are the tasks of ambulance and medical commanders in the field? And (3) How can field commanders' performances be measured and assessed? A systematic literature search in MEDLINE, PubMed, PsycINFO, Embase, Cochrane Central Register of Controlled Trials, Cochrane Library, ISI Web of Science, Scopus, International Security & Counter Terrorism Reference Center, Current Controlled Trials, and PROSPERO covering January 1, 1990 through March 1, 2014 was conducted. Reference lists of included literature were hand searched. Included papers were analyzed using Framework synthesis. The literature search identified 6,049 unique records, of which, 76 articles and books where included in qualitative synthesis. Most ICSs are described commonly as hierarchical, bureaucratic, and based on military principles. These assumptions are contested strongly, as is the applicability of such systems. Linking of the chains of command in cooperating agencies is a basic difficulty. Incident command systems are flexible in the sense that the organization may be expanded as needed. Commanders may command by direction, by planning, or by influence. Commanders' tasks may be summarized as: conducting scene assessment, developing an action plan, distributing resources, monitoring operations, and making decisions. There is considerable variation between authors in nomenclature and what tasks are included or highlighted

The flooding incident at the Aagesta pressurized heavy water nuclear power plant

International Nuclear Information System (INIS)

Dahlgren, C.

1996-03-01

This work is an independent investigation of the consequences of the flooding incident at the Aagesta HPWR, Stockholm in May 1969. The basis for the report is an incident in which, due to short circuits in the wiring because of flooding water, the ECCS is momentarily subjected to a pressure much higher than designed for. The hypothetical scenario analyzed here is the case in which the ECCS breaks due to the high pressure. As a consequence of the break, the pressure and the water level in the reactor vessel decrease. The report is divided into three parts; First the Aagesta HPWR is described as well as the chronology of the incident, an analysis of the effects of a hypothetical break in the ECCS is then developed. The second part is a scoping analysis of the incident, modeling the pressure decrease and mass flow rate out of the break. The heat-up of the core, and the core degradation was modeled as well. The third part is formed by a RELAP5/MOD3.1 modeling of the Aagesta HPWR. 18 refs

Distributed continuous energy scheduling for dynamic virtual power plants

International Nuclear Information System (INIS)

Niesse, Astrid

2015-01-01

This thesis presents DynaSCOPE as distributed control method for continuous energy scheduling for dynamic virtual power plants (DVPP). DVPPs aggregate the flexibility of distributed energy units to address current energy markets. As an extension of the Virtual Power Plant concept they show high dynamics in aggregation and operation of energy units. Whereas operation schedules are set up for all energy units in a day-ahead planning procedure, incidents may render these schedules infeasible during execution, like deviation from prognoses or outages. Thus, a continuous scheduling process is needed to ensure product fulfillment. With DynaSCOPE, software agents representing single energy units solve this problem in a completely distributed heuristic approach. Using a stepped concept, several damping mechanisms are applied to allow minimum disturbance while continuously trying to fulfill the product as contracted at the market.

EAP-based critical incident stress management: utilization of a practice-based assessment of incident severity level in responding to workplace trauma.

Science.gov (United States)

DeFraia, Gary S

2013-01-01

Central to the field of trauma psychology is assessment of the impact of critical incidents on individuals, as measured by individual symptoms of stress. Accordingly, the trauma literature reflects a proliferation of clinical impact of event scales. Workplace incidents however, affect not only individual employees, but also work organizations, requiring a multi-level response. Critical incident stress management (CISM) is the most prevalent multi-level incident response strategy utilized by organizations, often through specialized CISM units operating within their employee assistance programs (EAPs). While EAP-based CISM units seeks to support both individuals and organizations, studies focused on individual stress dominate the literature, mirroring assessment scales that tend to emphasize clinical as opposed to organizational practice. This research contributes to less-prevalent studies exploring incident characteristics as disruptive to organizations, rather than clinical symptoms as disruptive to individuals. To measure incident disruption, an EAP-based CISM unit developed a critical incident severity scale. By analyzing this unit's extensive practice database, this exploratory study examines how critical incident severity level varies among various types of incidents. Employing the methodology of clinical data mining, this practice-based research generates evidence-informed practice recommendations in the areas of EAP-based CISM intake assessment, organizational consultation and incident response planning.

Safety evaluation by living probabilistic safety assessment. Procedures and applications for planning of operational activities and analysis of operating experience

International Nuclear Information System (INIS)

Johanson, Gunnar; Holmberg, J.

1994-01-01

Living Probabilistic Safety Assessment (PSA) is a daily safety management system and it is based on a plant-specific PSA and supporting information systems. In the living use of PSA, plant status knowledge is used to represent actual plant safety status in monitoring or follow-up perspective. The PSA model must be able to express the risk at a given time and plant configuration. The process, to update the PSA model to represent the current or planned configuration and to use the model to evaluate and direct the changes in the configuration, is called living PSA programme. The main purposes to develop and increase the usefulness of living PSA are: Long term safety planning: To continue the risk assessment process started with the basic PSA by extending and improving the basic models and data to provide a general risk evaluation tool for analyzing the safety effects of changes in plant design and procedures. Risk planning of operational activities: To support the operational management by providing means for searching optimal operational maintenance and testing strategies from the safety point of view. The results provide support for risk decision making in the short term or in a planning mode. The operational limits and conditions given by technical specifications can be analyzed by evaluating the risk effects of alternative requirements in order to balance the requirements with respect to operational flexibility and plant economy. Risk analysis of operating experience: To provide a general risk evaluation tool for analyzing the safety effects of incidents and plant status changes. The analyses are used to: identify possible high risk situations, rank the occurred events from safety point of view, and get feedback from operational events for the identification of risk contributors. This report describes the methods, models and applications required to continue the process towards a living use of PSA. 19 tabs, 20 figs

Study of a proposal for the insertion of operational experience as a tool for support the training plan for nuclear power plants

International Nuclear Information System (INIS)

Fonseca, Renato Alves da

2009-05-01

The main objectives of this work are: to determine, through the operational experience analysis of Angra 1 nuclear power plant, the plant operational vulnerabilities that affect its staff training and to propose a modeling to plan a training program to address these vulnerabilities. This analysis utilizes the Angra 1 document entitled 'Ocorrencia de Relato Obrigatorio', which reports the plant event occurrences. Through this document, as well as the opinion of specialists on the most probably root causes of the reported events, the backdrop of the operational experience analysis of internal events was built. The modeling using the SAT method and has as a guideline the internal operational experience analysis. Moreover, this modeling encompasses techniques of event and second generation human reliability analysis, both specific of the nuclear area. The development of this work shows that: the internal operational experience analysis provides a realistic view of the vulnerabilities present in the plant in all areas (technical and organizational), which must be addressed to the plan of the training program and the modeling, based on realistic view of the plant, is dynamic, not linear, and is always up to date on events in the plant, its causes and consequences. (author)

Severity scale for incidents and accidents in French nuclear power plant

International Nuclear Information System (INIS)

Dupuis, M.C.; Guimbail, H.; Debes, M.; Roels, C.

1988-10-01

All countries operating nuclear power stations have developed systems for declaring and analyzing incidents occurring when the stations are in service. These systems, are inevitably extensive and complex, as the search for perfection in terms of operating safety leads not only to identification and analysis of incidents which are evidenced by their consequences, but also to identification of all those other incidents which have not had repercussions, but which nevertheless constitute precursor events for more serious situations. For example in France, a system based on safety significance criteria has been in service since the early 1980s, and is applied and operated by EDF and the safety authorities. While experts obtain maximum benefit from this system, public opinion and the relay points constituted by the media are somewhat at a loss, being unable to discriminate in the mass of non-hierarchized information which may come their way, between what is genuinely important and what is less important or even totally unimportant. For this reason, the CSSIN recommended examination of a severity scale, simple to understand and easy to use, which could be employed to classify all incidents and which could become, in due course, as familiar to all of us as the Richter seismic scale is today. We will now examine the composition of this scale, applied on an experimental basis by the Minister for Industry for a period of about one and a half years, as from 20th April 1988

Plutonium Finishing Plant Treatment and Storage Unit Dangerous Waste Training Plan

International Nuclear Information System (INIS)

ENTROP, G.E.

2000-01-01

The training program for personnel performing waste management duties pertaining to the Plutonium Finishing Plant (PFP) Treatment and Storage Unit is governed by the general requirements established in the Plutonium Finishing Plant Dangerous Waste Training Plan (PFP DWTP). The PFP Treatment and Storage Unit DWTP presented below incorporates all of the components of the PFP DWTP by reference. The discussion presented in this document identifies aspects of the training program specific to the PFP Treatment and Storage Unit. The training program includes specifications for personnel instruction through both classroom and on-the-job training. Training is developed specific to waste management duties. Hanford Facility personnel directly involved with the PFP Treatment and Storage Unit will receive training to container management practices, spill response, and emergency response. These will include, for example, training in the cementation process and training pertaining to applicable elements of WAC 173-303-330(1)(d). Applicable elements from WAC 173-303-330(1)(d) for the PFP Treatment and Storage Unit include: procedures for inspecting, repairing, and replacing facility emergency and monitoring equipment; communications and alarm systems; response to fires or explosions; and shutdown of operations

Brazilian nuclear power plants decommissioning plan for a multiple reactor site

Energy Technology Data Exchange (ETDEWEB)

Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R., E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas. Programa de Pos-Graduacao em Energia e Engenharia da Energia

2015-07-01

Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

Brazilian nuclear power plants decommissioning plan for a multiple reactor site

International Nuclear Information System (INIS)

Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R.

2015-01-01

Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

Landscape Planning of Schoolyards

Science.gov (United States)

Kopeva, A.; Khrapko, O.; Ivanova, O.

2017-11-01

The optimal landscape architecture planning of schoolyards allows for creation of favorable conditions for children personal development and physical fitness. The key principles of schoolyard landscape planning, same as for other areas intended for children, are as follows: establishment of a favorable microclimate, safety, aesthetic and educational environment. Green spaces play an essential role in this respect as they are essential to sanitary, hygienic, structural, and spatial planning performing decorative, artistic, cognitive, and educational functions in these areas. Various types of landscape plantings are used in school areas: borders, lawns, beds, vines, ornamental arrangements, and various potted plants. Children’s safety is the key principle when selecting a landscape design type and the plants’ range. Any allergenic, poisonous, thorny, strong-smelling or life-threatening plants are excluded. Plants on school grounds can serve as visual aids for studies. Drought-resistant, attractive, colorful, abundantly blooming plants with variable leaf texture are preferred. Ornamental trees and shrubs as well as perennials and annuals provide a broad plant range for school grounds.

Incidence and Mortality and Epidemiology of Breast Cancer in the World.

Science.gov (United States)

Ghoncheh, Mahshid; Pournamdar, Zahra; Salehiniya, Hamid

2016-01-01

Breast cancer is the most common malignancy in women around the world. Information on the incidence and mortality of breast cancer is essential for planning health measures. This study aimed to investigate the incidence and mortality of breast cancer in the world using age-specific incidence and mortality rates for the year 2012 acquired from the global cancer project (GLOBOCAN 2012) as well as data about incidence and mortality of the cancer based on national reports. It was estimated that 1,671,149 new cases of breast cancer were identified and 521,907 cases of deaths due to breast cancer occurred in the world in 2012. According to GLOBOCAN, it is the most common cancer in women, accounting for 25.1% of all cancers. Breast cancer incidence in developed countries is higher, while relative mortality is greatest in less developed countries. Education of women is suggested in all countries for early detection and treatment. Plans for the control and prevention of this cancer must be a high priority for health policy makers; also, it is necessary to increase awareness of risk factors and early detection in less developed countries.

Constitution of an incident database suited to statistical analysis and examples

International Nuclear Information System (INIS)

Verpeaux, J.L.

1990-01-01

The Nuclear Protection and Safety Institute (IPSN) has set up and is developing an incidents database, which is used for the management and analysis of incidents encountered in French PWR plants. IPSN has already carried out several incidents or safety important events statistical analysis, and is improving its database on the basis of the experience it gained from this various studies. A description of the analysis method and of the developed database is presented

Protecting chemical plants against terrorist attacks: a review

NARCIS (Netherlands)

Khakzad Rostami, N.; Reniers, G.L.L.M.E.

2015-01-01

Protection of hazardous establishments such as chemical plants intentional incidents has drawn attention from safety and security experts since 9/11 terrorist attacks in the U.S. Although major steps have been taken since, the recent intentional incidents in two chemical plants in France in June and

Stranded Fuel, Orphan Sites, Dead Plants: Transportation Planning Considerations After the BRC Report - 13393

Energy Technology Data Exchange (ETDEWEB)

Thrower, Alex W. [The Thrower Group LLC, Richmond, VA (United States)

2013-07-01

The author explores transportation, packaging and storage questions related to a primary recommendation of the Blue Ribbon Commission on America's Nuclear Future; i.e., that fuel from shutdown plants be removed to consolidated storage as soon as possible to enable final decommissioning and beneficial re-use of those sites. The paper discusses the recommendations of the BRC, the implications and challenges that implementing those recommendations present, and provides recommended solutions for beginning the multi-year planning, coordination, material acquisition, and communications processes that will be needed to move fuel from shutdown plants when a destination site becomes available. Removal of used nuclear fuel from shutdown reactor sites (which are serving no other purpose other than storing SNF and GTCC, at considerable expense) was a central recommendation of the BRC, for a number of reasons. This recommendation was one of the most widely acclaimed that the Commission put forward. However, there are significant challenges (such as availability of fuel canister overpacks, lack of infrastructure, handling constraints and others) that will need to be addressed, apart from the critically important identification of a suitable and workable storage destination site. Resolving these logistical challenges will need to begin even before a destination site is identified, given the long lead-times required for planning and procurement. Based on information available today, it is possible to make informed predictions about what will be needed to modify existing contractual arrangements with utilities, address equipment and infrastructure needs, and begin working with states, tribes and local governments to start initial preparation needs. If DOE, working with industry and other experienced parties, can begin planning and acquisition activities in the near term, overall schedule risk can be reduced and potential cost avoidance achieved. The most immediate benefit will

Stranded Fuel, Orphan Sites, Dead Plants: Transportation Planning Considerations After the BRC Report - 13393

International Nuclear Information System (INIS)

Thrower, Alex W.

2013-01-01

The author explores transportation, packaging and storage questions related to a primary recommendation of the Blue Ribbon Commission on America's Nuclear Future; i.e., that fuel from shutdown plants be removed to consolidated storage as soon as possible to enable final decommissioning and beneficial re-use of those sites. The paper discusses the recommendations of the BRC, the implications and challenges that implementing those recommendations present, and provides recommended solutions for beginning the multi-year planning, coordination, material acquisition, and communications processes that will be needed to move fuel from shutdown plants when a destination site becomes available. Removal of used nuclear fuel from shutdown reactor sites (which are serving no other purpose other than storing SNF and GTCC, at considerable expense) was a central recommendation of the BRC, for a number of reasons. This recommendation was one of the most widely acclaimed that the Commission put forward. However, there are significant challenges (such as availability of fuel canister overpacks, lack of infrastructure, handling constraints and others) that will need to be addressed, apart from the critically important identification of a suitable and workable storage destination site. Resolving these logistical challenges will need to begin even before a destination site is identified, given the long lead-times required for planning and procurement. Based on information available today, it is possible to make informed predictions about what will be needed to modify existing contractual arrangements with utilities, address equipment and infrastructure needs, and begin working with states, tribes and local governments to start initial preparation needs. If DOE, working with industry and other experienced parties, can begin planning and acquisition activities in the near term, overall schedule risk can be reduced and potential cost avoidance achieved. The most immediate benefit will

Production planning of combined heat and power plants with regards to electricity price spikes : A machine learning approach

OpenAIRE

Fransson, Nathalie

2017-01-01

District heating systems could help manage the expected increase of volatility on the Nordic electricity market by starting a combined heat and power production plant (CHP) instead of a heat only production plant when electricity prices are expected to be high. Fortum Värme is interested in adjusting the production planning of their district heating system more towards high electricity prices and in their system there is a peak load CHP unit that could be utilised for this purpose. The econom...

Survey of malignant tumor incidence and mortality characteristics among the residents in Fuqing from 2007 to 2009

International Nuclear Information System (INIS)

Chen Tiehui; Peng Xian'e; Hu Zhijian; Xue Feng; Zeng Zhichang; Zhang Xiuxia; Shi Xishun; Xue Changgao; Sun Quanfu; Zhou Tianshu

2014-01-01

Objective: To investigate distribution characteristics of malignant tumor incidence and mortality among the local residents before the operation of Fuqing nuclear power plant, in Fujian province. Methods: A retrospective survey of malignant tumor incidence and mortality in Fuqing residents from 2007 to 2009 was carried out. The incidence and mortality distribution characteristics of total malignant tumors and main malignant tumors associated with nuclear radiation was analyzed. Results: The annual malignant tumors incidence and mortality rates were 148.65/10"5 and 114.96/10"5, respectively. Liver cancer, stomach cancer, lung cancer, esophagus cancer and colorectal cancer ranked the top five. Leukemia incidence and mortality rates were 3.77/10"5 and 2.61/10"5, respectively. Thyroid cancer incidence and mortality rates were 6.95/10"5 and 0.46/10"5, respectively. Conclusions: Esophageal carcinoma and lung cancer are the main malignant tumors in Fuqing city before the operation of the nuclear power plant. Leukemia incidence and mortality rates are both lower in Fuqing city than the national average level, but thyroid cancer incidence and mortality rates are both higher than the national average level. Surveillance of malignant tumors and death causes should proceeding continuously in Fuqing city, in order to evaluate the operation of nuclear power plant on local population health. (authors)

Project Management Plan Solution Stabilization

International Nuclear Information System (INIS)

SATO, P.K.

1999-01-01

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Solutions Stabilization subproject. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Integrated Project Management Plan (IPMP) for the Plutonium Finishing Plant Stabilization and Deactivation Project, HNF-3617. This project plan is the top-level definitive project management document for the PFP Solution Stabilization subproject. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Solution Stabilization subproject. Any deviations to the document must be authorized through the appropriate change control process

Project Management Plan Solution Stabilization

Energy Technology Data Exchange (ETDEWEB)

SATO, P.K.

1999-08-31

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Solutions Stabilization subproject. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Integrated Project Management Plan (IPMP) for the Plutonium Finishing Plant Stabilization and Deactivation Project, HNF-3617. This project plan is the top-level definitive project management document for the PFP Solution Stabilization subproject. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Solution Stabilization subproject. Any deviations to the document must be authorized through the appropriate change control process.

Maintenance implementation plan for the Plutonium Finishing Plant. Revision 3

International Nuclear Information System (INIS)

Meldrom, C.A.

1996-03-01

This document outlines the Maintenance Implementation Plan (MIP) for the Plutonium Finishing Plant (PFP) located at the Hanford site at Richland, Washington. This MIP describes the PFP maintenance program relative to DOE order 4330.4B. The MIP defines the key actions needed to meet the guidelines of the Order to produce a cost-effective and efficient maintenance program. A previous report identified the presence of significant quantities of Pu-bearing materials within PFP that pose risks to workers. PFP's current mission is to develop, install and operate processes which will mitigate these risks. The PFP Maintenance strategy is to equip the facility with systems and equipment able to sustain scheduled PFP operations. The current operating run is scheduled to last seven years. Activities following the stabilization operation will involve an Environmental Impact Statement (EIS) to determine future plant activities. This strategy includes long-term maintenance of the facility for safe occupancy and material storage. The PFP maintenance staff used the graded approach to dictate the priorities of the improvement and upgrade actions identified in Chapter 2 of this document. The MIP documents PFP compliance to the DOE 4330.4B Order. Chapter 2 of the MIP follows the format of the Order in addressing the eighteen elements. As this revision is a total rewrite, no sidebars are included to highlight changes

Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography

International Nuclear Information System (INIS)

Youngen, G.

1988-10-01

The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant's operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ''onsite'' response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world's collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously

78 FR 17709 - Endangered and Threatened Wildlife and Plants; Recovery Plan for Rogue and Illinois Valley Vernal...

Science.gov (United States)

2013-03-22

... localities for implementing actions, while the recovery actions describe a process for implementing... DEPARTMENT OF THE INTERIOR Fish and Wildlife Service [FWS-R1-ES-2012-N198; FXES11130100000C2-123-FF01E00000] Endangered and Threatened Wildlife and Plants; Recovery Plan for Rogue and Illinois Valley Vernal...

A practical approach to incident prevention and mitigation

Energy Technology Data Exchange (ETDEWEB)

Smith, Kevin; Williams, Pat [KBC Advanced Technologies, Surrey (United Kingdom)

2012-07-01

Our industry has taken grand interest in improving safety in the last few decades, particularly of our process operations. This has resulted in significant improvements in overall industry safety statistics. Despite this improvement in our efforts, incidents still occur where people are injured, and these tragic incidents may even be fatal. Organizations have implemented various programs to lessen the chance of these incidents occurring, three of which are most commonly: check the box, minimize legal liability, and take a practical approach. Most often it is the practical approach that proves to influence the most improvements because it is an approach focused on the employees and the organizations business needs together. The plants that show the most safety are to no surprise run by reliable individuals. Usually, the causes of incidents stem from a failure to perform and maintain basic procedures. The answers to each plant's safety dilemmas are not found in any one program, but instead lie in understanding the anatomy of what it means to be safe. Only when that is understood can a solution be constructed and catered to the entire physiology of the problem. There are three basic tenants that need to be considered in any safety improvement strategy in order for it to be effective: capability, awareness and motivation. The third is further comprised of two factors that should not be overlooked: desire and accountability. Therefore, process safety is not driven by fancy software or rigid structure programs. It is apparent that several factors come into play when implementing safer practices. The focus of these practices should be on manufacturing employees. When improvement efforts are focused on activities and behaviors whose implementation is practical in a plant environment and address the three main areas of the anatomy, the likelihood of success increases substantially. (author)

Collaborating With Parents of Children With Chronic Conditions and Professionals to Design, Develop and Pre-pilot PLAnT (the Parent Learning Needs and Preferences Assessment Tool).

Science.gov (United States)

Nightingale, Ruth; Wirz, Lucy; Cook, Wendy; Swallow, Veronica

This study aimed to design, develop and pre-pilot an assessment tool (PLAnT) to identify parents' learning needs and preferences when carrying out home-based clinical care for their child with a chronic condition. A mixed methods, two-phased design was used. Phase 1: a total of 10 parents/carers and 13 professionals from six UK's children's kidney units participated in qualitative interviews. Interview data were used to develop the PLAnT. Eight of these participants subsequently took part in an online survey to refine the PLAnT. Phase 2: thirteen parents were paired with one of nine professionals to undertake a pre-pilot evaluation of PLAnT. Data were analyzed using the Framework approach. A key emergent theme identifying parents' learning needs and preferences was identified. The importance of professionals being aware of parents' learning needs and preferences was recognised. Participants discussed how parents' learning needs and preferences should be identified, including: the purpose for doing this, the process for doing this, and what would the outcome be of identifying parents' needs. The evidence suggests that asking parents directly about their learning needs and preferences may be the most reliable way for professionals to ascertain how to support individual parents' learning when sharing management of their child's chronic condition. With the increasing emphasis on parent-professional shared management of childhood chronic conditions, professionals can be guided by PLAnT in their assessment of parents' learning needs and preferences, based on identified barriers and facilitators to parental learning. Copyright © 2017 Elsevier Inc. All rights reserved.

Implementation of the National Incident Management System (NIMS)/Incident Command System (ICS) in the Federal Radiological Monitoring and Assessment Center(FRMAC) - Emergency Phase

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

Homeland Security Presidential Directive HSPD-5 requires all federal departments and agencies to adopt a National Incident Management System (NIMS)/Incident Command System (ICS) and use it in their individual domestic incident management and emergency prevention, preparedness, response, recovery, and mitigation programs and activities, as well as in support of those actions taken to assist state and local entities. This system provides a consistent nationwide template to enable federal, state, local, and tribal governments, private-sector, and nongovernmental organizations to work together effectively and efficiently to prepare for, prevent, respond to, and recover from domestic incidents, regardless of cause, size, or complexity, including acts of catastrophic terrorism. This document identifies the operational concepts of the Federal Radiological Monitoring and Assessment Center's (FRMAC) implementation of the NIMS/ICS response structure under the National Response Plan (NRP). The construct identified here defines the basic response template to be tailored to the incident-specific response requirements. FRMAC's mission to facilitate interagency environmental data management, monitoring, sampling, analysis, and assessment and link this information to the planning and decision staff clearly places the FRMAC in the Planning Section. FRMAC is not a mitigating resource for radiological contamination but is present to conduct radiological impact assessment for public dose avoidance. Field monitoring is a fact-finding mission to support this effort directly. Decisions based on the assessed data will drive public protection and operational requirements. This organizational structure under NIMS is focused by the mission responsibilities and interface requirements following the premise to provide emergency responders with a flexible yet standardized structure for incident response activities. The coordination responsibilities outlined in the NRP are based on the NIMS

Risk factors for radiotherapy incidents and impact of an online electronic reporting system

International Nuclear Information System (INIS)

Chang, David W.; Cheetham, Lynn; Marvelde, Luc te; Bressel, Mathias; Kron, Tomas; Gill, Suki; Tai, Keen Hun; Ball, David; Rose, William; Silva, Linas; Foroudi, Farshad

2014-01-01

Background and purpose: To ascertain the rate, type, significance, trends and the potential risk factors associated with radiotherapy incidents in a large academic department. Materials and methods: Data for all radiotherapy activities from July 2001 to January 2011 were reviewed from radiotherapy incident reporting forms. Patient and treatment data were obtained from the radiotherapy record and verification database (MOSAIQ) and the patient database (HOSPRO). Logistic regression analyses were performed to determine variables associated with radiotherapy incidents. Results: In that time, 65,376 courses of radiotherapy were delivered with a reported incident rate of 2.64 per 100 courses. The rate of incidents per course increased (1.96 per 100 courses to 3.52 per 100 courses, p < 0.001) whereas the proportion of reported incidents resulting in >5% deviation in dose (10.50 to 2.75%, p < 0.001) had decreased after the introduction of an online electronic reporting system. The following variables were associated with an increased rate of incidents: afternoon treatment time, paediatric patients, males, inpatients, palliative plans, head-and-neck, skin, sarcoma and haematological malignancies. In general, complex plans were associated with higher incidence rates. Conclusion: Radiotherapy incidents were infrequent and most did not result in significant dose deviation. A number of risk factors were identified and these could be used to highlight high-risk cases in the future. Introduction of an online electronic reporting system resulted in a significant increase in the number of incidents being reported

Plans for treating the liquid wastes from an ammonia/urea/sulfur plant

Energy Technology Data Exchange (ETDEWEB)

Padula, R.C.; Amaral, S.P.

1980-03-01

Plans for treating the liquid wastes from an ammonia/urea/sulfur plant under construction near the Araucaria Refinery of Petroleo Brasileiro S.A. include sending the clean rain water directly to the Barigui River (A Class 3 river suitable for domestic water supply after corrective treatment, preservation of fauna and flora, and animal drinking water); collecting contaminated and process wastewater and subjecting them to equilization, flocculation, flotation, nitrification, decantation, denitrification, rapid aeration, and decantation treatments; and disposing of the sludge in a sanitary landfill. The sewage will undergo biological treatment or be sent to an oxidation poond. The pollution load and the allowed pollutant levels in the effluents are given.

Waste Isolation Pilot Plant Environmental Monitoring Plan

International Nuclear Information System (INIS)

2008-01-01

U.S. Department of Energy (DOE) Order 450.1, Environmental Protection Program, requires each DOE site to conduct environmental monitoring. Environmental monitoring at the Waste Isolation Pilot Plant (WIPP) is conducted in order to: (a) Verify and support compliance with applicable federal, state, and local environmental laws, regulations, permits, and orders; (b) Establish baselines and characterize trends in the physical, chemical, and biological condition of effluent and environmental media; (c) Identify potential environmental problems and evaluate the need for remedial actions or measures to mitigate the problems; (d) Detect, characterize, and report unplanned releases; (e) Evaluate the effectiveness of effluent treatment and control, and pollution abatement programs; and (f) Determine compliance with commitments made in environmental impact statements, environmental assessments, safety analysis reports, or other official DOE documents. This Environmental Monitoring Plan (EMP) explains the rationale and design criteria for the environmental monitoring program, extent and frequency of monitoring and measurements, procedures for laboratory analyses, quality assurance (QA) requirements, program implementation procedures, and direction for the preparation and disposition of reports. Changes to the environmental monitoring program may be necessary to allow the use of advanced technology and new data collection techniques. This EMP will document changes in the environmental monitoring program. Guidance for preparation of EMPs is contained in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance.

Particular intervention plan of the Areva La Hague facility - 2012 edition

International Nuclear Information System (INIS)

2012-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Areva NC La Hague fuel reprocessing plant (located on the territories of Beaumont-Hague, Digulleville, Herqueville, Jobourg and Omonville-la-Petite towns, Manche, France) which comprises the totally decommissioned UP2 400 unit, and the UP2 800 production unit still in operation

The Equivalent Uniform Dose as a severity metric for radiation treatment incidents

International Nuclear Information System (INIS)

Dunscombe, Peter B.; Iftody, Sandra; Ploquin, Nicolas; Ekaette, Edidiong U.; Lee, Robert C.

2007-01-01

In allocating resources within a risk management program, ideally we would like to know both the probabilities and consequences of potential incidents. We simulate, on a treatment planning computer, several commonly reported incidents in radiation treatment and explore their consequences for the EUDs of targets and organs at risk

Cancer incidence in the environment of nuclear power plants

International Nuclear Information System (INIS)

Heller, W.

2008-01-01

An epidemiological study of cancer in children in the environment of nuclear power plants has been written on behalf of the German Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU) and the Federal Office for Radiation Protection (BfS). The study is a case controlled study based on the German Register of Cancer in Children. The most important outcome of the study is the finding that a connection can be observed in Germany between the proximity to a nuclear power plant of the place of living and the risk of a child to develop cancer in the 5 th year of life. The magnitude of this risk was calculated to be approximately 0.2%, i.e., out of a total of 13,373 cases of cancer, 29 would be attributable to living within the 5 km zone around a nuclear power plant. This finding demands an explanation. The study proper cannot serve as a material witness because it had not been designed to establish cause and effect relations between the risk and potential origins. The expert consultants frankly state that current knowledge about radiation biology and epidemiology in principle does not allow the ionizing radiation emitted by German nuclear power plants in normal operation to be interpreted as the cause. Whether confounders, selection or chance play a role in the observed and documented finding cannot be explained for good by the study. However, although representing an honorable acquittal, the study produces a different effect in the public mind. What is remembered is the link between nuclear power plants and cancer in children. (orig.)

Risk-based design of process plants with regard to domino effects and land use planning.

Science.gov (United States)

Khakzad, Nima; Reniers, Genserik

2015-12-15

Land use planning (LUP) as an effective and crucial safety measure has widely been employed by safety experts and decision makers to mitigate off-site risks posed by major accidents. Accordingly, the concept of LUP in chemical plants has traditionally been considered from two perspectives: (i) land developments around existing chemical plants considering potential off-site risks posed by major accidents and (ii) development of existing chemical plants considering nearby land developments and the level of additional off-site risks the land developments would be exposed to. However, the attempts made to design chemical plants with regard to LUP requirements have been few, most of which have neglected the role of domino effects in risk analysis of major accidents. To overcome the limitations of previous work, first, we developed a Bayesian network methodology to calculate both on-site and off-site risks of major accidents while taking domino effects into account. Second, we combined the results of risk analysis with Analytic Hierarchical Process to design an optimal layout for which the levels of on-site and off-site risks would be minimum. Copyright © 2015 Elsevier B.V. All rights reserved.

Maintenance planning support method for nuclear power plants based on collective decision making

International Nuclear Information System (INIS)

Shimizu, Shunichi; Sakurai, Shoji; Takaoka, Kazushi; Kanemoto, Shigeru; Fukutomi, Shigeki

1992-01-01

Inspection and maintenance planning in nuclear power plants is conducted by decision making based on experts' collective consensus. However, since a great deal of time and effort is required to reach a consensus among expert judgments, the establishment of effective decision making methods is necessary. Therefore, the authors developed a method for supporting collective decision making, based on a combination of three types of decision making methods; the Characteristic Diagram method, Interpretative Structural Modeling method, and the Analytic Hierarchy Process method. The proposed method enables us to determine the evaluation criteria systematically for collective decision making, and also allows extracting collective decisions using simplified questionnaires. The proposed method can support reaching a consensus of groups effectively through the evaluation of collective decision structural models and their characteristics. In this paper, the effectiveness of the proposed method was demonstrated through its application to the decision making problem concerning whether or not the improved ultrasonic testing equipment should be adopted at nuclear power plants. (author)

Medical management of three workers following a radiation exposure incident

International Nuclear Information System (INIS)

House, R.A.; Sax, S.E.; Rumack, E.R.; Holness, D.L.

1992-01-01

The medical management of three individuals involved in an exposure incident to whole-body radiation at a nuclear generating plant of a Canadian electrical utility is described. The exposure incident resulted in the two highest whole-body radiation doses ever received in a single event by workers in a Canadian nuclear power plant. The individual whole-body doses (127.4 mSv, 92.0 mSv, 22.4 mSv) were below the threshold for acute radiation sickness but the exposures still presented medical management problems related to assessment and counseling. Serial blood counting and lymphocyte cytogenetic analysis to corroborate the physical dosimetry were performed. All three employees experienced somatic symptoms due to stress and one employee developed post-traumatic stress disorder. This incident indicates that there is a need in such radiation exposure accidents for early and continued counseling of exposed employees to minimize the risk of development of stress-related symptoms

Critical analysis of major incidents risks in civil nuclear energy

International Nuclear Information System (INIS)

2000-09-01

The differences existing between the PWR type reactors and the RBMK type reactors are explained as well as the risk associated to each type when it exists. The Ines scale, tool to give the level of an accident gravity comprises seven levels, the number seven is the most serious and corresponds to the Chernobyl accident; The number zero is of no consequence but must be mentioned as a matter of form. The incidents from 1 to 3 concern increasing incidents, affecting the nuclear power plant but not the external public. The accidents from 4 to 7 have a nature to affect the nuclear power plant and the environment. An efficient tool exists between nuclear operators it is made of the reports on incidents encountered by close reactors. Two others type reactors are coming, the high temperature type reactors and the fast neutrons reactors. different risks are evoked, terrorism, proliferation, transport and radioactive wastes. (N.C.)

Medical management of three workers following a radiation exposure incident

Energy Technology Data Exchange (ETDEWEB)

House, R.A.; Sax, S.E.; Rumack, E.R.; Holness, D.L. (Department of Occupational and Environmental Health, St. Michael' s Hospital, Toronto, Ontario (Canada))

1992-01-01

The medical management of three individuals involved in an exposure incident to whole-body radiation at a nuclear generating plant of a Canadian electrical utility is described. The exposure incident resulted in the two highest whole-body radiation doses ever received in a single event by workers in a Canadian nuclear power plant. The individual whole-body doses (127.4 mSv, 92.0 mSv, 22.4 mSv) were below the threshold for acute radiation sickness but the exposures still presented medical management problems related to assessment and counseling. Serial blood counting and lymphocyte cytogenetic analysis to corroborate the physical dosimetry were performed. All three employees experienced somatic symptoms due to stress and one employee developed post-traumatic stress disorder. This incident indicates that there is a need in such radiation exposure accidents for early and continued counseling of exposed employees to minimize the risk of development of stress-related symptoms.

Critical review of the national action plans (NAcP) of the EU stress tests on nuclear power plants

International Nuclear Information System (INIS)

Becker, Oda; Lorenz, Patricia

2013-04-01

The Fukushima catastrophe was the horrible result of decades of mistaken safety philosophy, a very lax safety regulation under strong industry influence on the regulators - not only in Japan. The first shock led to the honest attempt to change this, to also involve events which are definitely possible but were kept out of the safety cases by using probabilities. When it was possible to ''prove'' an event as having too low probability, it could be ignored. On 12 October 2012, Tokyo Electric Power Co (TEPCO) admitted that the company had failed to prevent the Fukushima accident, reversing its earlier statement that the accident could not have been foreseen. A TEPCO task force has identified several factors that had led to the accident in March 2011 [NW 18/10/2012]: TEPCO did not learn a lesson from the incident in France of loss of off-site power due to flooding at the Blayais NPP on December 27, 1999, furthermore no safety measures aimed at preventing and mitigating a severe accident had been adopted since 2002. The task force attributed those facts to multiple root causes: - First, the management assumed a severe accident was extremely unlikely in Japan, and feared that retrofitting safety systems would increase anxiety among the public, especially among the residents near the plant. - TEPCO also feared safety retrofitting would require a costly shutdown period. The TEPCO task force also underlined that there were not enough engineers at the site who were familiar with safety systems' designs, operation manuals and their locations. Basically all circumstances leading to the Fukushima accident exist for the European NPP as well - only the tsunami risk does not apply for all NPP but e.g. for several UK NPPs. However the risk of flooding events or of earthquakes exists to a different extent for all NPPs. Also common to all NPPs: the operators insist on the low probabilities to avoid high investments and anti-nuclear activities of the public, very much as the same

Critical review of the national action plans (NAcP) of the EU stress tests on nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Becker, Oda; Lorenz, Patricia

2013-04-15

The Fukushima catastrophe was the horrible result of decades of mistaken safety philosophy, a very lax safety regulation under strong industry influence on the regulators - not only in Japan. The first shock led to the honest attempt to change this, to also involve events which are definitely possible but were kept out of the safety cases by using probabilities. When it was possible to ''prove'' an event as having too low probability, it could be ignored. On 12 October 2012, Tokyo Electric Power Co (TEPCO) admitted that the company had failed to prevent the Fukushima accident, reversing its earlier statement that the accident could not have been foreseen. A TEPCO task force has identified several factors that had led to the accident in March 2011 [NW 18/10/2012]: TEPCO did not learn a lesson from the incident in France of loss of off-site power due to flooding at the Blayais NPP on December 27, 1999, furthermore no safety measures aimed at preventing and mitigating a severe accident had been adopted since 2002. The task force attributed those facts to multiple root causes: - First, the management assumed a severe accident was extremely unlikely in Japan, and feared that retrofitting safety systems would increase anxiety among the public, especially among the residents near the plant. - TEPCO also feared safety retrofitting would require a costly shutdown period. The TEPCO task force also underlined that there were not enough engineers at the site who were familiar with safety systems' designs, operation manuals and their locations. Basically all circumstances leading to the Fukushima accident exist for the European NPP as well - only the tsunami risk does not apply for all NPP but e.g. for several UK NPPs. However the risk of flooding events or of earthquakes exists to a different extent for all NPPs. Also common to all NPPs: the operators insist on the low probabilities to avoid high investments and anti-nuclear activities of the public

Outline of construction planning on No. 2 Reactor of the Shika Nuclear Power Plant

International Nuclear Information System (INIS)

Nakagawa, Tetsuro; Kadoki, Shuichi; Kubo, Tetsuji

1999-01-01

The Hokuriku Electric Co., Ltd. carries out the expansion of the Shika Nuclear Power Plant No.2 (ABWR) to start its in March 2006. It is situated in north neighboring side of No. 1 reactor under operation at present, and its main buildings are planned to position a reactor building at mountain side and a turbine building at sea side as well as those in the No. 1 reactor. And, cooling water for steam condenser was taken in from an intake opening built at north side of the lifting space situated at the front of the power plant, and discharged into seawater from a flashing opening positioned about 600 m offing. Here were described on outline of main civil engineering such as base excavation engineering, concrete caisson production, oceanic establishment engineering, and facility for steam condenser, and characteristics of the engineering. (G.K.)

Expansion planning for electrical generating systems

International Nuclear Information System (INIS)

1984-01-01

The guidebook outlines the general principles of electric power system planning in the context of energy and economic planning in general. It describes the complexities of electric system expansion planning that are due to the time dependence of the problem and the interrelation between the main components of the electric system (generation, transmission and distribution). Load forecasting methods are discussed and the principal models currently used for electric system expansion planning presented. Technical and economic information on power plants is given. Constraints imposed on power system planning by plant characteristics (particularly nuclear power plants) are discussed, as well as factors such as transmission system development, environmental considerations, availability of manpower and financial resources that may affect the proposed plan. A bibliography supplements the references that appear in each chapter, and a comprehensive glossary defines terms used in the guidebook

Digital Architecture Planning Model

International Nuclear Information System (INIS)

Oxstrand, Johanna Helene; Al Rashdan, Ahmad Yahya Mohammad; Bly, Aaron Douglas; Rice, Brandon Charles; Fitzgerald, Kirk; Wilson, Keith Leon

2016-01-01

As part of the U.S. Department of Energy's Light Water Reactor Sustainability Program, the Digital Architecture (DA) Project focuses on providing a model that nuclear utilities can refer to when planning deployment of advanced technologies. The digital architecture planning model (DAPM) is the methodology for mapping power plant operational and support activities into a DA that unifies all data sources needed by the utilities to operate their plants. The DA is defined as a collection of information technology capabilities needed to support and integrate a wide spectrum of real-time digital capabilities for performance improvements of nuclear power plants. DA can be thought of as integration of the separate instrumentation and control and information systems already in place in nuclear power plants, which are brought together for the purpose of creating new levels of automation in plant work activities. A major objective in DAPM development was to survey all key areas that needed to be reviewed in order for a utility to make knowledgeable decisions regarding needs and plans to implement a DA at the plant. The development was done in two steps. First, researchers surveyed the nuclear industry in order to learn their near-term plans for adopting new advanced capabilities and implementing a network (i.e., wireless and wire) infrastructure throughout the plant, including the power block. Secondly, a literature review covering regulatory documents, industry standards, and technical research reports and articles was conducted. The objective of the review was to identify key areas to be covered by the DAPM, which included the following: 1. The need for a DA and its benefits to the plant 2. Resources required to implement the DA 3. Challenges that need to be addressed and resolved to implement the DA 4. Roles and responsibilities of the DA implementation plan. The DAPM was developed based on results from the survey and the literature review. Model development