Bibliography of reports on research sponsored by the NRC Office of Nuclear Regulatory Research, July--December 1976

International Nuclear Information System (INIS)

Buchanan, J.R.

1977-01-01

A bibliography of 148 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography

Bibliography of reports on research sponsored by the NRC office of nuclear regulatory research, July--December 1977

Energy Technology Data Exchange (ETDEWEB)

Buchanan, J.R.

1978-04-01

A bibliography of 198 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1977 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are arranged first by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.

NRC [Nuclear Regulatory Commission] safety research in support of regulation, 1987

International Nuclear Information System (INIS)

1988-05-01

This report, the third in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1987. The goal of this office is to ensure that research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

NRC safety research in support of regulation--FY 1989

International Nuclear Information System (INIS)

1990-04-01

This report, the fifth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1989. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

NRC safety research in support of regulation, FY 1991

International Nuclear Information System (INIS)

1992-04-01

This report, the seventh in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1991. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

NRC safety research in support of regulation, FY 1990

International Nuclear Information System (INIS)

1991-04-01

This report, the sixth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1990. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

NRC's geotechnical engineering research needs for the high-level waste repository program

International Nuclear Information System (INIS)

Gupta, D.C.; Philip, J.; Lorig, L.J.; Chowdhury, A.H.

1992-01-01

To develop the capability for independently assessing the US Department of Energy's (DOE's) geologic repository design within a limited time, the US Nuclear Regulatory Commission (NRC) staff needs to perform certain research well before receiving the license application. The NRC staff is using a number of factors to identify the areas that it needs to research. The staff assigns priorities to the needed research based on programmatic considerations and the significance of the work. In the geotechnical engineering field, the staff is conducting research in the following three areas: response of the repository to repeated strong ground motion, rock-mass sealing, and coupled thermo-hydro-mechanical interactions. In this paper, the NRC staff also presents the areas of additional research needed in the geotechnical engineering field

Bibliography of reports on research sponsored by the NRC Office of Nuclear Regulatory Research, November 1975--June 1976

Energy Technology Data Exchange (ETDEWEB)

Buchanan, J.R.

1976-09-30

A bibliography of 152 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period November 1975 through June 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.

Bibliography of reports on research sponsored by the NRC Office of Nuclear Regulatory Research, November 1975--June 1976

International Nuclear Information System (INIS)

Buchanan, J.R.

1976-01-01

A bibliography of 152 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period November 1975 through June 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography

NRC/AMRMC Resident Research Associateship Program

Science.gov (United States)

2018-05-01

2- 0010 Report Period: 02/06/2012-02/28/2018 4/11/2018, 12:17 PM During the reporting period, the National Academies of Sciences, Engineering , and...to advertise the NRC Research Associateship Programs included the following: 1) attendance at meetings of major scientific and engineering ...professional societies; 2) advertising in programs and career centers for these and other professional society meetings; 3) direct mailing and emailing of

USA NRC/RSR Data Bank System and Reactor Safety Research Data Repository (RSRDR)

International Nuclear Information System (INIS)

Maskewitz, B.F.; Bankert, S.F.

1979-01-01

The United States Nuclear Regulatory Commission (NRC), through its Division of Reactor Safety Research (RSR) of the Office of Nuclear Regulatory Research, has established the NRC/RSR Data Bank Program to collect, process, and make available data from the many domestic and foreign water reactor safety research programs. An increasing number of requests for data and/or calculations generated by NRC Contractors led to the initiation of the program which allows timely and direct access to water reactor safety data in a manner most useful to the user. The program consists of three main elements: data sources, service organizations, and a data repository

NRC - regulator of nuclear safety

International Nuclear Information System (INIS)

1997-01-01

The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations

Summary of NRC LWR safety research programs on fuel behavior, metallurgy/materials and operational safety

International Nuclear Information System (INIS)

Bennett, G.L.

1979-09-01

The NRC light-water reactor safety-research program is part of the NRC regulatory program for ensuring the safety of nuclear power plants. This paper summarizes the results of NRC-sponsored research into fuel behavior, metallurgy and materials, and operational safety. The fuel behavior research program provides a detailed understanding of the response of nuclear fuel assemblies to postulated off-normal or accident conditions. Fuel behavior research includes studies of basic fuel rod properties, in-reactor tests, computer code development, fission product release and fuel meltdown. The metallurgy and materials research program provides independent confirmation of the safe design of reactor vessels and piping. This program includes studies on fracture mechanics, irradiation embrittlement, stress corrosion, crack growth, and nondestructive examination. The operational safety research provides direct assistance to NRC officials concerned with the operational and operational-safety aspects of nuclear power plants. The topics currently being addressed include qualification testing evaluation, fire protection, human factors, and noise diagnostics

Summary and recommendations of the NRC/INEL Activated Carbon Testing Program

International Nuclear Information System (INIS)

Scarpellino, C.D.; Sill, C.W.

1986-01-01

The Committee on Nuclear Air and Gas Treatment (CONAGT) of the American Society of Mechanical Engineers (ASME) sponsored an interlaboratory testing program, round-robin, of nuclear-grade activated carbon. The results of this round-robin revealed gross differences in penetration of radio-labeled methyl iodide as measured by the various laboratories when using Method A of the ASTM D-3803-79 Standard. These differences prompted the Nuclear Regulatory Commission (NRC) to establish the NRC/INEL Activated Carbon Testing Program to determine the causes of these discrepancies and to provide recommendations that could lead to an accurate and reliable testing procedure that would ensure an adequate method for assessing the capability of activated carbon to remove radioiodine from gas streams within commercial nuclear power plants. The NRC/INEL Activated Carbon Testing Program has conducted formal and informal interlaboratory comparisons to identify problems with the test method and its application and to assess the effectiveness of changes to procedures and equipment voluntarily implemented by commercial laboratories to mitigate the disparity of test results. The results of the first formal NRC/INEL Interlaboratory Comparison (IC) essentially verified the CONAGT round-robin results despite the use of a detailed test protocol. This data indicated that many of the participating laboratories probably had been operating outside the ASTM specifications for relative humidity (RH) and flow. In addition, this process provided information which was used to modify the testing protocol employed for the second NRC/INEL Interlaboratory Comparison (IC-2) to make it more rugged and reliable. These changes to the protocol together with the results of INEL sensitivity testing are the basis for the recommendations presented

Summary of Chernobyl followup research activities

International Nuclear Information System (INIS)

1992-06-01

In NUREG-1251, ''Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States,'' April 1989, the NRC staff concluded that no immediate changes in NRC's regulations regarding design or operation of US commercial reactors were needed; however, it recommended that certain issues be considered further. NRC's Chernobyl followup research program consisted of the research tasks undertaken in response to the recommendations in NUREG-1251. It included 23 tasks that addressed potential lessons to be learned from the Chernobyl accident. This report presents summaries of NRC's Chernobyl followup research tasks. For each task, the Chernobyl-related issues are indicated, the work is described, and the staff's findings and conclusions are presented. More detailed reports concerning the work are referenced where applicable. This report closes out NRC's Chernobyl followup research program as such, but additional research will be conducted on some issues as needed. The report includes remarks concerning significant further activity with respect to the issues addressed

NRC safety research in support of regulation. Selected highlights

International Nuclear Information System (INIS)

1986-05-01

The report presents selected highlights of how research has contributed to the regulatory effort. It explains the research role of the NRC and nuclear safety research contributions in the areas of: pressure vessel integrity, piping, small- and large-break loss-of-coolant accidents, hydrogen and containment, source term analysis, seismic hazards and high-level waste management. The report also provides a summary of current and future research directions in support of regulation

NRC nuclear waste geochemistry 1983

International Nuclear Information System (INIS)

Alexander, D.H.; Birchard, G.F.

1984-05-01

The purpose of the meeting was to present results from NRC-sponsored research and to identify regulatory research issues which need to be addressed prior to licensing a high-level waste repository. Important summaries of technical issues and recommendations are included with each paper. The issue reflect areas of technical uncertainty addressed by the NRC Research program in geochemistry. The objectives of the NRC Research Program in geochemistry are to provide a technical basis for waste management rulemaking, to provide the NRC Waste Management Licensing Office with information that can be used to support sound licensing decisions, and to identify investigations that need to be conducted by DOE to support a license application. Individual papers were processed for inclusion in the Energy Data Base

NRC safety research in support of regulation, 1986

International Nuclear Information System (INIS)

1987-09-01

This report is the second in a series of annual reports responding to congressional inquiries as to the utilization of nuclear regulatory research. NUREG-1175, ''NRC Safety Research in Support of Regulation,'' published in May 1986, reported major research accomplishments between about FY 1980 and FY 1985. This report narrates the accomplishments of FY 1986 and does not restate earlier accomplishments. Earlier research results are mentioned in the context of current results in the interest of continuity. Both the direct contributions to scientific and technical knowledge and their regulatory applications, when there has been a definite regulatory outcome during FY 1986, have been described

Comments on the NRC Safety Research Program budget

International Nuclear Information System (INIS)

1979-07-01

This report includes comments on the budget levels and program plans for the supplemental request for FY 1980 to support research related to the accident at Three Mile Island, Unit 2 (TMI) as well as for the FY 1981 Budget. For both budgets, the funding levels considered by the ACRS are the original requests by RES and the Budget Review Group (BRG) markup as of July 10, 1979. In its current review of the NRC research program, the ACRS has given special attention to both the short- and long-term implications of the TMI accident and their significance to research for both the short- and long-term research programs

In vivo monitoring of nuclear research centre (NRC) workers. Vol. 4

Energy Technology Data Exchange (ETDEWEB)

Gomaa, M A; Ali, E M; Taha, T M [Radiation Protection Departion, Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt)

1996-03-01

Occupational workers of Nuclear research center (NRC) of atomic energy authority (AEA) working with radio-nuclides such as (Cs-137, I-131, and I-125) are monitored yearly. Individuals involved in routine work in hot laboratories are examined every three months. When an incident occurs, the workers involved are examined promptly. In order to measure internal contamination, the modified NRC-AEA whole body counter is used. More than hundred occupational workers had been examined in 1994. Results indicated that the annual limit of intake as recommended by ICRP was not exceeded. 3 figs., 3 tabs.

Current perspectives on performance assessment at the NRC

International Nuclear Information System (INIS)

Coplan, S.M.; Eisenberg, N.A.; Federline, M.V.; Randall, J.D.

1992-01-01

The Nuclear Regulatory Commission (NRC) staff is engaging in a number of activities involving performance assessment in order to support NRC's program in high-level waste management. Broad areas of activity include: (1) reactive work responding to products and activities of the Department of Energy (DOE), (2) proactive work, including development of an independent performance assessment capability, development of guidance for DOE, support for technical and programmatic integration, (3) a program of regulatory research, and (4) participation in a number of international activities. As the U.S. high-level waste program continues to mature, performance assessment is seen as playing a more prominent role in evaluating safety and focussing technical activities

NRC/RSR Data Bank Program description

International Nuclear Information System (INIS)

Bankert, S.F.

1979-01-01

The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., at Idaho National Engineering Laboratory. The NRC/RSR Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, and training and advisory services to users and the NRC. The NRC/RSR Data Bank Program and the capabilities of the data access software are described

Human Reliability Assessment and Human Performance Evaluation: Research and Analysis Activities at the U.S. NRC

International Nuclear Information System (INIS)

Ramey-Smith, A.M.

1998-01-01

The author indicates the themes of the six programs identified by the US NRC mission on human performance and human reliability activities. They aim at developing the technical basis to support human performance, at developing and updating a model of human performance and human reliability, at fostering national and international dialogue and cooperation efforts on human performance evaluation, at conducting operating events analysis and database development, and at providing support to human performance and human reliability inspection

NRC antitrust licensing actions, 1978--1996

International Nuclear Information System (INIS)

Mayer, S.J.; Simpson, J.J.

1997-09-01

NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC's competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC's antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission's Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission's antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC's antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs

NRC antitrust licensing actions, 1978--1996

Energy Technology Data Exchange (ETDEWEB)

Mayer, S.J.; Simpson, J.J.

1997-09-01

NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC`s competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC`s antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission`s Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission`s antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC`s antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs.

Preparation for Scaling Studies of Ice-Crystal Icing at the NRC Research Altitude Test Facility

Science.gov (United States)

Struk, Peter M.; Bencic, Timothy J.; Tsao, Jen-Ching; Fuleki, Dan; Knezevici, Daniel C.

2013-01-01

This paper describes experiments conducted at the National Research Council (NRC) of Canadas Research Altitiude Test Facility between March 26 and April 11, 2012. The tests, conducted collaboratively between NASA and NRC, focus on three key aspects in preparation for later scaling work to be conducted with a NACA 0012 airfoil model in the NRC Cascade rig: (1) cloud characterization, (2) scaling model development, and (3) ice-shape profile measurements. Regarding cloud characterization, the experiments focus on particle spectra measurements using two shadowgraphy methods, cloud uniformity via particle scattering from a laser sheet, and characterization of the SEA Multi-Element probe. Overviews of each aspect as well as detailed information on the diagnostic method are presented. Select results from the measurements and interpretation are presented which will help guide future work.

Current NRC activities related to MQA

Energy Technology Data Exchange (ETDEWEB)

Trottier, C.A.; Nellis, D.O. [Nuclear Regulatory Commission, Washington, DC (United States)

1993-12-31

The U.S. Nuclear Regulatory Commission`s (NRC`s) interest in measurement quality assurance (MQA) goes back to before 1963, when the Atomic Energy Commission (AEC) published a notice in the Federal Register concerning the need for establishing a Film Dosimetry Calibration Laboratory, and also provided a set of minimum performance criteria to be used by the laboratory in evaluating film dosimetry services used by licensees. The proposed laboratory was not established, but in 1967 the AEC contracted with Battelle`s Pacific Northwest Laboratory (PNL) to evaluate film dosimeter performance criteria and provide a basis for establishing a Film Dosimetry Calibration Laboratory if the study showed that it was needed. Then, in 1973, the Conference of Radiation Control Program Directors (CRCPD), concerned with the state of dosimetry processing and the lack of adequate standards, recommended that the National Bureau of Standards (NBS) direct a performance testing program for personnel dosimetry processing services. Later, in 1976, NRC asked PNL to conduct a study to evaluate the four existing performance standards for personnel dosimetry processing. One result of this study was that the HPSSC standard, which later became ANSI N13.11, was recommended as the standard for use in a national dosimetry processing program. The rest is common knowledge. With the support of numerous other federal agencies and the CRCPD, NRC published a regulation, effective in 1988, that required all processors of personnel dosimeters be accredited under the National Voluntary Laboratory Accreditation Program (NVLAP), operated by the NBS, which is now called the National Institute of Standards and Technology (NIST). At present, there are 75 dosimetry processing laboratories accredited under NVLAP. NRC has also been involved in extremity dosimeters, health physics survey instruments, bioassay measurements, electronic personnel dosimeters, and environmental monitoring around nuclear power plants.

Status report on NRC's current below regulatory concern activities

International Nuclear Information System (INIS)

Dragonette, K.S.

1988-01-01

The concept of below regulatory concern (BRC) is not new to the Nuclear Regulatory Commission (NRC) or its predecessor agency, the Atomic Energy Commission. The regulations and licensing decisions have involved limited and de facto decisions on BRC since the beginning. For example, consumer products containing radioactive materials have been approved for distribution to persons exempt from licensing for some time and procedures for survey and release of equipment have traditionally been a part of many licensees' radiation safety programs. However, these actions have generally been ad hoc decisions in response to specific needs and have not been necessarily consistent. The need to deal with this regulatory matter has been receiving attention from both Congress and the NRC Commissioners. NRC response has grown from addressing specific waste streams, to generic rulemaking for wastes, and finally to efforts to develop a broad generic BRC policy. Section 10 of the Low-Level Radioactive Waste Policy Amendments Act of 1985 addressed NRC actions on specific waste streams. In response, NRC issued guidance on rulemaking petitions for specific wastes. NRC also issued an advance notice of proposed rulemaking indicating consideration of Commission initiated regulations to address BRC wastes in a generic manner. The Commissioners have directed staff to develop an umbrella policy for all agency decisions concerning levels of risk or dose that do not require government regulation

Examples of NRC research products used in regulation

International Nuclear Information System (INIS)

Anderson, N.R.

1987-01-01

The key to effective research is a close relationship between information needs and research results. This can only be achieved by close cooperation between the researchers and the regulators. At the NRC, this relationship has matured over the years until now the researchers participate in definition of the information needs and the regulators help define the research programs. The more formal means of ensuring a close match between needs and results include joint research groups, oversight working groups, and a system of Research Information Letters (RILs). On an informal basis there are many day to day discussions and meetings on the various programs which ensure effective program guidance and early identification of significant findings. This paper describes both the formal and informal researcher/regulation interface and discusses some examples of how specific research programs are utilized in the regulatory process. Specific programs described are the pressurized thermal shock program, the seismic margins program and the Category 1 structures program. Other examples cited are the aging and life extension programs

NRC inspections of licensee activities to improve the performance of motor-operated valves

International Nuclear Information System (INIS)

Scarbrough, T.G.

1992-01-01

The NRC regulations require that components important to the safe operation of a nuclear power plant be treated in a manner that provides assurance of their proper performance. Despite these regulatory requirements, operating experience and research programs have raised concerns regarding the performance of motor-operated valves (MOVs) in nuclear power plants. In June 1990, the staff issued NUREG-1352, Action Plans for Motor-Operated Valves and Check Valves, which contains planned actions to organize the activities aimed at resolving the concerns about MOV performance. A significant task of the MOV action plan is the staff's review of the implementation of Generic Letter (GL) 89-10 (June 28, 1989), 'Safety-Related Motor-Operated Valve Testing and Surveillance,' and its supplements, by nuclear power plant licensees. The NRC staff has issued several supplements to GL 89-10 to provide additional guidance for use by licensees in responding to the generic letter. The NRC staff has conducted initial inspections of the GL 89-10 programs at most licensee facilities. This paper outlines some of the more significant findings of those inspections. For example, licensees who have begun differential pressure and flow testing have found some MOVs to require more thrust to operate than predicted by the standard industry equation with typical valve factors assumed in the past. The NRC staff has found weaknesses in licensee procedures for conducting the differential pressure and flow tests, the acceptance criteria for the tests in evaluating the capability of the MOV to perform its safety function under design basis conditions, and feedback of the test results into the methodology used by the licensee in predicting the thrust requirements for other MOVs. Some licensees have not made adequate progress toward resolving the MOV issue for their facilities within the recommended schedule of GL 89-10

NRC/RSR data bank program

International Nuclear Information System (INIS)

Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

1978-01-01

The United States Nuclear Regulatory Commission (NRC) has established at the Idaho National Engineering Laboratory (INEL) the NRC/Reactor Safety Research (RSR) Data Bank Program. The program is under the direction of EG and G Idaho, Inc., and is intended to provide the means of collecting, processing, and making available experimental data from the many water reactor safety research programs. The NRC/RSR Data Bank Program collects qualified engineering data on a prioritized basis from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users. The NRC/RSR Data Bank specializes in water reactor safety experimental data, but it has a number of other scientific applications where large amounts of numeric data are or will be available. As an example of size, a single water reactor safety test may generate 10 million data words. Future examples of the use of a data bank might be in gathering data on low head hydraulics, solar projects, and liquid metal reactor safety data

NRC/RSR Data Bank Program

International Nuclear Information System (INIS)

Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

1978-01-01

The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program at the Idaho National Engineering Laboratory (INEL). The program provides the means of collecting, storing, and making available experimental data from the many water reactor safety research programs in the United States and other countries. The program collects qualified engineering data on a prioritized basis from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users

NRC/RSR Data Bank Program

International Nuclear Information System (INIS)

Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

1978-01-01

The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program to provide a means of collecting, processing, and making available experimental data from the many domestic and foreign water reactor safety research programs. The NRC/RSR Data Bank Program collects qualified engineering data from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users. The program is designed to be user oriented to minimize the effort required to obtain and manipulate data of interest. The data bank concept and structure embodied in the data bank processing system are applicable to any program where large quantities of scientific (numeric) data are generated and require compiling, storage, and accessing in order to be collected and made available to multiple users. 3 figures

Risk-informed inservice test activities at the NRC

International Nuclear Information System (INIS)

Fischer, D.; Cheok, M.; Hsia, A.

1996-01-01

The operational readiness of certain safety-related components is vital to the safe operation of nuclear power plants. Inservice testing (IST) is one of the mechanisms used by licensees to ensure this readiness. In the past, the type and frequency of IST have been based on the collective best judgment of the NRC and industry in an ASME Code consensus process and NRC rulemaking process. Furthermore, IST requirements have not explicitly considered unique component and system designs and contribution to overall plant risk. Because of the general nature of ASME Code test requirements and non-reliance on risk estimates, current IST requirements may not adequately emphasize testing those components that are most important to safety and may overly emphasize testing of less safety significant components. Nuclear power plant licensees are currently interested in optimizing testing by applying resources in more safety significant areas and, where appropriate, reducing measures in less safety-significant areas. They are interested in maintaining system availability and reducing overall maintenance costs in ways that do not adversely affect safety. The NRC has been interested in using probabilistic, as an adjunct to deterministic, techniques to help define the scope, type and frequency of IST. The development of risk-informed IST programs has the potential to optimize the use of NRC and industry resources without adverse affect on safety

Risk-informed inservice test activities at the NRC

Energy Technology Data Exchange (ETDEWEB)

Fischer, D.; Cheok, M.; Hsia, A.

1996-12-01

The operational readiness of certain safety-related components is vital to the safe operation of nuclear power plants. Inservice testing (IST) is one of the mechanisms used by licensees to ensure this readiness. In the past, the type and frequency of IST have been based on the collective best judgment of the NRC and industry in an ASME Code consensus process and NRC rulemaking process. Furthermore, IST requirements have not explicitly considered unique component and system designs and contribution to overall plant risk. Because of the general nature of ASME Code test requirements and non-reliance on risk estimates, current IST requirements may not adequately emphasize testing those components that are most important to safety and may overly emphasize testing of less safety significant components. Nuclear power plant licensees are currently interested in optimizing testing by applying resources in more safety significant areas and, where appropriate, reducing measures in less safety-significant areas. They are interested in maintaining system availability and reducing overall maintenance costs in ways that do not adversely affect safety. The NRC has been interested in using probabilistic, as an adjunct to deterministic, techniques to help define the scope, type and frequency of IST. The development of risk-informed IST programs has the potential to optimize the use of NRC and industry resources without adverse affect on safety.

NRC plan for cleanup operations at Three Mile Island Unit 2

International Nuclear Information System (INIS)

Lo, R.; Snyder, B.J.

1980-07-01

The NRC plan defines the functional role of the NRC in cleanup operations at Three Mile Island Unit 2 to assure that agency regulatory responsibilities and objectives will be fulfilled. The plan outlines NRC functions in TMI-2 cleanup operations in the following areas: (1) the functional relationship of NRC to other government agencies, the public, and the licensee to coordinate activities, (2) the functional roles of these organizations in cleanup operations, (3) the NRC review and decision-making procedure for the licensee's proposed cleanup operation, (4) the NRC/licensee estimated schedule of major actions, and (5) NRC's functional role in overseeing implementation of approved licensee activities

75 FR 10526 - In the Matter of Mr. Lawrence E. Grimm; Order Prohibiting Involvement in NRC-Licensed Activities

Science.gov (United States)

2010-03-08

... NUCLEAR REGULATORY COMMISSION [IA-09-068; NRC-2010-0085] In the Matter of Mr. Lawrence E. Grimm; Order Prohibiting Involvement in NRC-Licensed Activities I Mr. Lawrence E. Grimm was employed as a... NIST-Boulder facility in accordance with the conditions specified therein. Mr. Grimm was listed on the...

Update of NRC uranium mill licensing activities

International Nuclear Information System (INIS)

Martin, J.B.

1978-01-01

Increased vigilance must be given to controlling emissions from active milling operations, particularly windblown tailings, to assure that the soon-to-be-effective EPA Fuel Cycle Standard is met. Comprehensive environmental monitoring programs will have to be developed to confirm that, in fact, the limit is met. Just as was the case last year, tailings management and disposal is still the major item of concern relating to uranium milling operations. As stated earlier, the NRC feels that below-grade disposal is the preferred method of tailings disposal in that it provides the greatest assurances of long-term isolation. In any event, tailings must be disposed of in such a way that no active care is required of disposal sites, to avoid committing future generations to a significant, lingering obligation to care for wastes generated to produce benefits which they will only indirectly receive, if at all. While the primary means of providing long-term isolation of tailings must be by physical barriers, as a prudent, supplementary measure of control, we are concluding in the GEIS on Uranium Milling that ownership of disposal sites by a Government agency is desirable. We expect a low level of continued surveillance at disposal sites with small expense involved. We are concluding that requiring operators to contribute on the order of $100,000 per disposal site to cover ongoing expenses would be the most apropriate means of conforming to the principle that the waste generator should pay full costs of waste disposal. We feel such an arrangement would be fair, simple, and efficient, favoring it over complicated schemes involving such things as taxes on product or tailings generated and continued management of ear-marked funds. Legislation is now pending in the Congress which would give NRC direct regulatory control over mill tailings and put into place the authorities needed to implement the long-term control and funding arrangements discussed above

Expression and purification of toxic anti-breast cancer p28-NRC chimeric protein

OpenAIRE

Soleimani, Meysam; Mirmohammad-Sadeghi, Hamid; Sadeghi-Aliabadi, Hojjat; Jahanian-Najafabadi, Ali

2016-01-01

Background: Chimeric proteins consisting of a targeting moiety and a cytotoxic moiety are now under intense research focus for targeted therapy of cancer. Here, we report cloning, expression, and purification of such a targeted chimeric protein made up of p28 peptide as both targeting and anticancer moiety fused to NRC peptide as a cytotoxic moiety. However, since the antimicrobial activity of the NRC peptide would intervene expression of the chimeric protein in Escherichia coli, we evaluated...

Cohort Profile : The National Academy of Sciences-National Research Council Twin Registry (NAS-NRC Twin Registry)

NARCIS (Netherlands)

Gatz, Margaret; Harris, Jennifer R.; Kaprio, Jaakko; McGue, Matt; Smith, Nicholas L.; Snieder, Harold; Spiro, Avron; Butler, David A.

The National Academy of Sciences-National Research Council Twin Registry (NAS-NRC Twin Registry) is a comprehensive registry of White male twin pairs born in the USA between 1917 and 1927, both of the twins having served in the military. The purpose was medical research and ultimately improved

The use of NPAR [Nuclear Plant Aging Research] results in plant inspection activities

International Nuclear Information System (INIS)

Gunther, W.; Taylor, J.

1989-01-01

The Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. A review of the NRC Inspection Program and discussions with NRC inspection personnel have revealed several areas where NPAR research results would be valuable to the inspector. This paper describes the NPAR information which can enhance inspection activities, and provides alternatives for making these pertinent research results available to the inspectors. The NRC Inspection Program emphasis is on evaluating the performance of licensees by focusing on requirements and standards associated with administrative, managerial, engineering, and operational aspects of licensee activities. The Program recognizes that licensees may satisfy NRC requirements differently, and therefore expresses inspection guidance in the form of performance objectives and evaluation criteria. for the resident and regional inspectors, procedures have been written covering various subject areas, such as operations, maintenance, and surveillance. Some of these procedures contain guidance related to aging degradation. The types of information generated by NPAR which were found to be relevant to inspection needs include the following: functional indicators; failure modes, causes, effects; stresses which cause degradation; maintenance recommendations; inspection prioritization. 3 refs

NRC closing remarks

International Nuclear Information System (INIS)

Coffman, F.

1994-01-01

This section contains the edited transcript of the NRC closing remarks made by Mr. Franklin Coffman (Chief, Human Factors Branch, Office of Nuclear Regulatory Research) and Dr. Cecil Thomas (Deputy Director, Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation). This editing consisted of minimal editing to correct grammar and remove extraneous references to microphone volume, etc

NRC overview: Repository QA

International Nuclear Information System (INIS)

Kennedy, J.E.

1988-01-01

The US Department of Energy (DOE) is on the threshold of an extensive program for characterizing Yucca Mountain in Nevada to determine if it is a suitable site for the permanent disposal of high-level nuclear waste. Earlier this year, the DOE published the Consultation Draft Site Characterization Plan for the Nevada site, which describes in some detail the studies that need to be performed to determine if the site is acceptable. In the near future, the final site characterization plan (SCP) is expected to be issued and large-scale site characterization activities to begin. The data and analyses that will result from the execution of that plan are expected to be the primary basis for the license application to the US Nuclear Regulatory Commission (NRC). Because of the importance of these data and analyses in the assessment of the suitability of the site and in the demonstration of that suitability in the NRC licensing process, the NRC requires in 10CFR60 that site characterization be performed under a quality assurance (QA) program. The QA program is designed to provide confidence that data are valid, retrievable, and reproducible. The documentation produced by the program will form an important part of the record on which the suitability of the site is judged in licensing. In addition, because the NRC staff can review only a selected portion of the data collected, the staff will need to rely on the system of controls in the DOE QA program

NRC perspective and experience on valve testing

International Nuclear Information System (INIS)

Eapen, P.K.

1990-01-01

Testing of safety related valves is one of the major activities at commercial nuclear power plants. In addition to Technical Specification, valve testing is required in 10 CFR 50.55a and 10 CFR 50 Appendix J. NRC inspectors (both resident and specialists) spend a considerable amount of time in following the valve test activities as part of their routine business. In the past, depending on a licensee's organizational structure, a valve could be tested more than three times to verify conformance with Technical Specifications, 10 CFR 50.55a, and 10 CFR 50 Appendix J. The regulatory reviewers were isolated from each other. Licensee test personnel were also not communicating among themselves. As a result, NRC inspectors found that certain valves in the IST program were inadequately tested. The typical licensee response was to say that this valve is exempted from testing under Appendix J. Others would say that the technical specification does not require fast closure of a valve in question. In addition to the above, the inspectors had to deal with exemption requests that were not dispositioned by the NRC. In the seventies there was a gentlemen's agreement to allow the licensee to do the testing in accordance with the exception, without waiting for the NRC approval. Needless to say when the new NRC inspection procedure was issued in March 1989 for implementation, the Regional inspectors had extremely difficult time to cope with the gray areas of valve testing. In August 1987, NRC Region I was reorganized and the special test program section was established to perform inspections in the IST area. This section was chartered to optimize resources and develop a meaningful inspection plan. The perspectives and insights used in the development of a detailed inspection plan is discussed below

Development of the NRC's Human Performance Investigation Process (HPIP)

International Nuclear Information System (INIS)

Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

1993-10-01

The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume III, is a detailed documentation of the development effort and the pilot training program

NRC regulatory agenda

International Nuclear Information System (INIS)

1990-10-01

The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has recently completed action or has proposed, or is considering action and of all petitions for rulemaking that the NRC has received that are pending disposition

NRC regulatory agenda

International Nuclear Information System (INIS)

1990-04-01

The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has recently completed action or has proposed, or is considering action and of all petitions for rulemaking that the NRC has received that are pending disposition

NRC plan for cleanup operations at Three Mile Island Unit 2

International Nuclear Information System (INIS)

Lo, R.; Snyder, B.

1982-02-01

This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities

76 FR 57006 - Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX; NRC Regulation of...

Science.gov (United States)

2011-09-15

... NUCLEAR REGULATORY COMMISSION 10 CFR Parts 30 and 150 [NRC-2011-0146] Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX; NRC Regulation of Military Operational Radium-226... published for public comment the proposed draft RIS 2011-XX; NRC Regulation of Military Operational Radium...

NRC Perspectives on Waste Incidental to Reprocessing Consultations and Monitoring - 13398

Energy Technology Data Exchange (ETDEWEB)

McKenney, Christepher A.; Suber, Gregory F.; Felsher, Harry D.; Mohseni, Aby [U.S. Nuclear Regulatory Commission, Mail Stop T8F5, 11545 Rockville Pike, Rockville, MD 20852 (United States)

2013-07-01

Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities in the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but

NRC Perspectives on Waste Incidental to Reprocessing Consultations and Monitoring - 13398

International Nuclear Information System (INIS)

McKenney, Christepher A.; Suber, Gregory F.; Felsher, Harry D.; Mohseni, Aby

2013-01-01

Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities in the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but largely

Comparison between Radiology Science Laboratory, Brazil (LCR) and National Research Council, Canada (NRC) of the absorbed dose in water using Fricke dosimetry

International Nuclear Information System (INIS)

Salata, Camila; David, Mariano Gazineu; Almeida, Carlos Eduardo de

2014-01-01

The absorbed dose to water standards for HDR brachytherapy dosimetry developed by the Radiology Science Laboratory, Brazil (LCR) and the National Research Council, Canada (NRC), were compared. The two institutions have developed absorbed dose standards based on the Fricke dosimetry system. There are significant differences between the two standards as far as the preparation and readout of the Fricke solution and irradiation geometry of the holder. Measurements were done at the NRC laboratory using a single Ir-192 source. The comparison of absorbed dose measurements was expressed as the ratio Dw(NRC)/Dw(LCR), which was found to be 1.026. (author)

Development of the NRC's Human Performance Investigation Process (HPIP)

International Nuclear Information System (INIS)

Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

1993-10-01

The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume I is a concise description of the need for the human performance investigation process, the process' components, the methods used to develop the process, the methods proposed to test the process, and conclusions on the process' usefulness

Development of the NRC's Human Performance Investigation Process (HPIP)

International Nuclear Information System (INIS)

Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

1993-10-01

The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause event at nuclear power plants. This document, Volume II, is a field manual for use by investigators when performing event investigations. Volume II includes the HPIP Procedure, the HPIP Modules, and Appendices that provide extensive documentation of each investigation technique

Survey by senior NRC management to obtain veiwpoints on the safety impact of regulatory activities from representative utilities operating and constructing nuclear power plants

International Nuclear Information System (INIS)

1981-08-01

A survey of licensee staff members representing the several organizational elements in different licensee corporate and plant staffs was conducted by senior NRC management to obtain licensee views on the potential safety consequences and impact of NRC regulatory activities. The comments received addressed the full scope of NRC activities and the negative impact of agency actions on licensee resources, staff performance, planning and scheduling, and organizational effectiveness. The findings of the survey is that the pace and nature of regulatory actions have created a potential safety problem which deserves further evaluation by the agency

NRC regulatory agenda

International Nuclear Information System (INIS)

1990-01-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

NRC influences on nuclear training

International Nuclear Information System (INIS)

Hannon, J.N.

1987-01-01

NRC influences on utility training programs through prescriptive requirements and evaluation of industry self-initiatives are discussed. NRC regulation and industry initiatives are complimentary and in some instances industry initiatives are replacing NRC requirements. Controls and feedback mechanisms designed to enhance positive NRC influences and minimize or eliminate negative influences are discussed. Industry and NRC efforts to reach an acceptable mix between regulator oversight and self-initiatives by the industry are recognized. Problem areas for continued cooperation to enhance training and minimize conflicting signals to industry are discussed. These areas include: requalification examination scope and content, depth of training and examination on emergency procedures; improved learning objectives as the basis for training and examination, and severe accident training

NRC regulation of DOE facilities

International Nuclear Information System (INIS)

Buhl, A.R.; Edgar, G.; Silverman, D.; Murley, T.

1997-01-01

The US Department of Energy (DOE), its contractors, and the Nuclear Regulatory Commission (NRC) are in for major changes if the DOE follows through on its intentions announced December 20, 1996. The DOE is seeking legislation to establish the NRC as the regulatory agency with jurisdiction over nuclear health, safety, and security at a wide range of DOE facilities. At this stage, it appears that as many as 200 (though not all) DOE facilities would be affected. On March 28, 1997, the NRC officially endorsed taking over the responsibility for regulatory oversight of DOE nuclear facilities as the DOE had proposed, contingent upon adequate funding, staffing resources, and a clear delineation of NRC authority. This article first contrasts the ways in which the NRC and the DOE carry out their basic regulatory functions. Next, it describes the NRC's current authority over DOE facilities and the status of the DOE's initiative to expand that authority. Then, it discusses the basic changes and impacts that can be expected in the regulation of DOE facilities. The article next describes key lessons learned from the recent transition of the GDPs from DOE oversight to NRC regulation and the major regulatory issues that arose in that transition. Finally, some general strategies are suggested for resolving issues likely to arise as the NRC assumes regulatory authority over DOE facilities

NRC regulatory agenda

International Nuclear Information System (INIS)

1991-04-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action or has proposed, or is considering action and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

NRC Regulatory Agenda

International Nuclear Information System (INIS)

1991-08-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action or has proposed, or is considering action and all petitions for rulemaking which have been received by the commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

NRC Regulatory Agenda

International Nuclear Information System (INIS)

1991-10-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

NRC regulatory agenda

International Nuclear Information System (INIS)

1993-04-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

NRC regulatory agenda

International Nuclear Information System (INIS)

1993-07-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter. The rules on which final action has been taken since March 31, 1993 are: Repeal of NRC standards of conduct; Fitness-for-duty requirements for licensees who possess, use, or transport Category I material; Training and qualification of nuclear power plant personnel; Monitoring the effectiveness of maintenance at nuclear power plants; Licensing requirements for land disposal of radioactive wastes; and Licensees' announcements of safeguards inspections

The use of NPAR [Nuclear Plant Aging Research] results in plant inspection activities

International Nuclear Information System (INIS)

Gunther, W.; Taylor, J.

1989-01-01

The US NRC's Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. Equipment and systems which have a propensity for age related degradation are identified, and methods for detecting and mitigating aging effects have been evaluated. As plants age, it becomes increasingly important that NRC inspectors be cognizant of plant aging phenomena. This paper describes the NPAR information which can enhance inspection activities, and provides a mechanism for making pertinent research available to the inspectors. 7 refs., 2 figs

NRC research on the application of advanced I and C technology to commercial nuclear power plants

International Nuclear Information System (INIS)

Gollei, K.R.; Hon, A.L.

1983-01-01

The operational safety and efficiency of commercial nuclear power plants (NPP's) could possibly be enhanced by utilizing advanced instrumentation and control technology developed by other industries. The NRC is interested in learning about new I and C technology that probably will or could be applied to new or existing plants. This would enable the NRC to be better prepared to evaluate the application without undue delays. It would also help identify any appropriate changes in NRC regulations or guidance necessary to facilitate the application of advanced IandC technology to NPP's. The NRC has initiated a project to work cooperatively with the advanced technology industry, power industry, EPRI, and technical organizations such as ISA toward this goal. This paper describes the objectives and plans of this cooperative effort. It summarizes the highlights of some of the advanced technology already being evaluated by NRC such as microprocessor applications, instruments to detect inadequate core cooling and other two-phase flow measurements, reactor noise surveillance and diagnostic techniques. This paper also suggests potential candidates for consideration such as utilization of advanced instruments for LOCA experiments. It also identifies some of the potential challenges facing the application of advanced technology to NPP's. It concludes that close cooperation between NRC and industry is essential for the success of such applications

Scientific activities 1980 Nuclear Research Center ''Democritos''

International Nuclear Information System (INIS)

1982-01-01

The scientific activities and achievements of the Nuclear Research Center Democritos for the year 1980 are presented in the form of a list of 76 projects giving title, objectives, responsible of each project, developed activities and the pertaining lists of publications. The 16 chapters of this work cover the activities of the main Divisions of the Democritos NRC: Electronics, Biology, Physics, Chemistry, Health Physics, Reactor, Scientific Directorate, Radioisotopes, Environmental Radioactivity, Soil Science, Computer Center, Uranium Exploration, Medical Service, Technological Applications, Radioimmunoassay and Training. (N.C.)

Annual technical meeting of the NRC cooperative severe accident research program

International Nuclear Information System (INIS)

Silver, E.G.

1993-01-01

This brief report summarizes the 1992 annual technical meeting of the NRC Cooperative Severe Accident Research Program (CSARP-92) held at the Hyatt Regency Hotel in Bethesda, Maryland, May 4-8, 1992. The report is taken mainly from coverage of the meeting published in the June 5, 1992, issue of Atomic Energy Clearinghouse. Results of this meeting are formalized at the Water Reactor Safety Information Meetings (WRSIM) that are held annually in October. Nuclear Safety summarizes the annual WRSIM meetings and provides a list of the presentations that were given. Interested readers are encouraged to review listed topics to identify specific topic areas in severe accident research. Sessions were held on in-vessel core melt progression; fuel-coolant interactions; fission-product behavior; direct containment heating; and severe accident code development, assessment, and validation. Summaries of the individual technical sessions and the current state of the art in these areas were given by the chairmen

Results from the Nuclear Plant Aging Research Program: Their use in inspection activities

International Nuclear Information System (INIS)

Gunther, W.; Taylor, J.

1990-09-01

The US NCR's Nuclear Plant Aging Research (NPAR) Program has determined the susceptibility to aging of components and systems, and the potential for aging to impact plant safety and availability. The NPAR Program also identified methods for detecting and mitigating aging in components. This report describes the NPAR results which can enhance NRC inspection activities. Recommendations are provided for communicating pertinent information to NRC inspectors. These recommendations are based on a detailed assessment of the NRC's Inspection Program, and feedback from resident and regional inspectors as described within. Examples of NPAR report summaries and aging inspection guides for components and systems are included. 13 refs., 3 figs., 4 tabs

NRC/UBC Node

Energy Technology Data Exchange (ETDEWEB)

Ellis-Perry, B. [Univ. of British Columbia, Vancouver, British Columbia (Canada); Yogendran, Y. [NRC Inst. for Fuel Cell Innovation, Vancouver, British Columbia (Canada)

2004-07-01

'Full text:' In the search for cleaner, more sustainable energy sources, many of the most promising breakthroughs have been in hydrogen technology. However, this promise will remain unfulfilled without public interest and enthusiasm, and without the infrastructure to support the technology. In order to get there, we have to test, perfect, and demonstrate technology that is safe and affordable, and we must do so in practical, familiar settings. Ideally, such settings should be easily accessible to the engineers, planners, and architects of tomorrow while providing a showcase for hydrogen technology that will attract the general public. This place is the NRC/UBC Hydrogen Node. The UBC campus in Point Grey is home to leading edge, internationally recognized researchers in a range of disciplines, both within the University and at the NRC Institute for Fuel Cell Innovation. On average, 40,000 students, faculty, and staff use the campus every day; UBC graduates go on to leadership positions in communities around the globe. Its spectacular setting makes UBC a popular destination for thousands of visitors from around the world. In 2006 UBC will host the World Urban Forum, and in 2010 it will be one of the sites for the Vancouver-Whistler Olympic Games. UBC and its South Campus neighbourhoods are developing as a model sustainable community, offering an excellent opportunity to develop and showcase hydrogen infrastructure and technology in a real-life, attractive setting that will be seen by thousands of people around the world. UBC's facilities, location, and Trek 2010 commitment to excellence in learning, research, and sustainability make it an ideal location for such a project. The H2 Village at UBC will be an integrated hydrogen demonstration project, linked to the hydrogen highway. This project is bringing together leading companies, researchers, and government agencies committed to making the refinement and early adoption of safe hydrogen technology a

NRC/UBC Node

International Nuclear Information System (INIS)

Ellis-Perry, B.; Yogendran, Y.

2004-01-01

'Full text:' In the search for cleaner, more sustainable energy sources, many of the most promising breakthroughs have been in hydrogen technology. However, this promise will remain unfulfilled without public interest and enthusiasm, and without the infrastructure to support the technology. In order to get there, we have to test, perfect, and demonstrate technology that is safe and affordable, and we must do so in practical, familiar settings. Ideally, such settings should be easily accessible to the engineers, planners, and architects of tomorrow while providing a showcase for hydrogen technology that will attract the general public. This place is the NRC/UBC Hydrogen Node. The UBC campus in Point Grey is home to leading edge, internationally recognized researchers in a range of disciplines, both within the University and at the NRC Institute for Fuel Cell Innovation. On average, 40,000 students, faculty, and staff use the campus every day; UBC graduates go on to leadership positions in communities around the globe. Its spectacular setting makes UBC a popular destination for thousands of visitors from around the world. In 2006 UBC will host the World Urban Forum, and in 2010 it will be one of the sites for the Vancouver-Whistler Olympic Games. UBC and its South Campus neighbourhoods are developing as a model sustainable community, offering an excellent opportunity to develop and showcase hydrogen infrastructure and technology in a real-life, attractive setting that will be seen by thousands of people around the world. UBC's facilities, location, and Trek 2010 commitment to excellence in learning, research, and sustainability make it an ideal location for such a project. The H2 Village at UBC will be an integrated hydrogen demonstration project, linked to the hydrogen highway. This project is bringing together leading companies, researchers, and government agencies committed to making the refinement and early adoption of safe hydrogen technology a reality

76 FR 54986 - NRC Enforcement Policy

Science.gov (United States)

2011-09-06

... NUCLEAR REGULATORY COMMISSION 10 CFR Chapter I [NRC-2011-0209] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Proposed enforcement policy revision; request for comment. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission) is soliciting comments from interested...

76 FR 76192 - NRC Enforcement Policy

Science.gov (United States)

2011-12-06

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0273] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Proposed enforcement policy revision; request for comment. SUMMARY: The U.S. Nuclear... licensees, vendors, and contractors), on proposed revisions to the NRC's Enforcement Policy (the Policy) and...

NRC Reviewer Aid for Evaluating the Human Factors Engineering Aspects of Small Modular Reactors

International Nuclear Information System (INIS)

OHara, J.M.; Higgins, J.C.

2012-01-01

Small modular reactors (SMRs) are a promising approach to meeting future energy needs. Although the electrical output of an individual SMR is relatively small compared to that of typical commercial nuclear plants, they can be grouped to produce as much energy as a utility demands. Furthermore, SMRs can be used for other purposes, such as producing hydrogen and generating process heat. The design characteristics of many SMRs differ from those of current conventional plants and may require a distinct concept of operations (ConOps). The U.S. Nuclear Regulatory Commission (NRC) conducted research to examine the human factors engineering (HFE) and the operational aspects of SMRs. The research identified thirty potential human-performance issues that should be considered in the NRC's reviews of SMR designs and in future research activities. The purpose of this report is to support NRC HFE reviewers of SMR applications by identifying some of the questions that can be asked of applicants whose designs have characteristics identified in the issues. The questions for each issue were identified and organized based on the review elements and guidance contained in Chapter 18 of the Standard Review Plan (NUREG-0800), and the Human Factors Engineering Program Review Model (NUREG-0711).

Results from the Nuclear Plant Aging Research Program: Their use in inspection activities

Energy Technology Data Exchange (ETDEWEB)

Gunther, W.; Taylor, J. (Brookhaven National Lab., Upton, NY (USA))

1990-09-01

The US NCR's Nuclear Plant Aging Research (NPAR) Program has determined the susceptibility to aging of components and systems, and the potential for aging to impact plant safety and availability. The NPAR Program also identified methods for detecting and mitigating aging in components. This report describes the NPAR results which can enhance NRC inspection activities. Recommendations are provided for communicating pertinent information to NRC inspectors. These recommendations are based on a detailed assessment of the NRC's Inspection Program, and feedback from resident and regional inspectors as described within. Examples of NPAR report summaries and aging inspection guides for components and systems are included. 13 refs., 3 figs., 4 tabs.

Respirator studies for the Nuclear Regulatory Commission (NRC)

International Nuclear Information System (INIS)

Skaggs, B.J.; Fairchild, C.I.; DeField, J.D.; Hack, A.L.

1985-01-01

A project of the Health, Safety and Environment Division is described. The project provides the NRC with information of respiratory protective devices and programs for their licensee personnel. The following activities were performed during FY 1983: selection of alternate test aerosols for quality assurance testing of high-efficiency particulate air respirator filters; evaluation of MAG-1 spectacles for use with positive and negative-pressure respirators; development of a Manual of Respiratory Protection in Emergencies Involving Airborne Radioactive Materials, and technical assistance to NRC licensees regarding respirator applications. 2 references, 1 figure

NRC Information No. 89-89: Event notification worksheets

International Nuclear Information System (INIS)

Rossi, C.E.

1992-01-01

The NRC ''Event Notification Worksheet,'' NRC Form 361, has been revised to assist the NRC Headquarters Operations Officers in obtaining adequate information for evaluation of significant events reported to the NRC Operations Center. The new forms more accurately reflect the event classifications and the 10 CFR 50.72 categories that must be reported. A copy of the new worksheet is enclosed for your reference. NRC Form 361 can be ordered from the NRC Information and Records Management Branch

Utilizing the National Research Council's (NRC) Conceptual Framework for the Next Generation Science Standards (NGSS): A Self-Study in My Science, Engineering, and Mathematics Classroom

Science.gov (United States)

Corvo, Arthur Francis

Given the reality that active and competitive participation in the 21 st century requires American students to deepen their scientific and mathematical knowledge base, the National Research Council (NRC) proposed a new conceptual framework for K--12 science education. The framework consists of an integration of what the NRC report refers to as the three dimensions: scientific and engineering practices, crosscutting concepts, and core ideas in four disciplinary areas (physical, life and earth/spaces sciences, and engineering/technology). The Next Generation Science Standards (NGSS ), which are derived from this new framework, were released in April 2013 and have implications on teacher learning and development in Science, Technology, Engineering, and Mathematics (STEM). Given the NGSS's recent introduction, there is little research on how teachers can prepare for its release. To meet this research need, I implemented a self-study aimed at examining my teaching practices and classroom outcomes through the lens of the NRC's conceptual framework and the NGSS. The self-study employed design-based research (DBR) methods to investigate what happened in my secondary classroom when I designed, enacted, and reflected on units of study for my science, engineering, and mathematics classes. I utilized various best practices including Learning for Use (LfU) and Understanding by Design (UbD) models for instructional design, talk moves as a tool for promoting discourse, and modeling instruction for these designed units of study. The DBR strategy was chosen to promote reflective cycles, which are consistent with and in support of the self-study framework. A multiple case, mixed-methods approach was used for data collection and analysis. The findings in the study are reported by study phase in terms of unit planning, unit enactment, and unit reflection. The findings have implications for science teaching, teacher professional development, and teacher education.

Occupational radiation exposures at NRC-licensed facilities

International Nuclear Information System (INIS)

Brooks, B.G.

1980-01-01

For the past ten years, the Nuclear Regulatory Commission and its predecessor, the Atomic Energy Commission, have required certain licensees to routinely submit two types of occupational radiation exposure reports: termination and annual reports. Each licensee engaged in any one of the activities: (1) operation of nuclear power reactors, (2) industrial radiography, (3) fuel fabrication, processing and reprocessing, and (4) large supply of byproduct material, is required to submit an annual statistical report and a termination report for each monitored employee who ends his employment or work assignment. A new regulation now requires all NRC licensees to submit annual reports for the years 1978 and 1979. These reports have been collected, computerized and maintained by the Commission at Oak Ridge, Tennessee. They are useful to the NRC in the evaluation of the risk of radiation exposure associated with the related activities. (author)

NRC performance indicator program

International Nuclear Information System (INIS)

Singh, R.N.

1987-01-01

The performance indicator development work of the US Nuclear Regulatory Commission (NRC) interoffice task group involved several major activities that included selection of candidate indicators for a trial program, data collection and review, validation of the trial indicators, display method development, interactions with the industry, and selection of an optimum set of indicators for the program. After evaluating 27 potential indicators against certain ideal attributes, the task group selected 17 for the trial program. The pertinent data for these indicators were then collected from 50 plants at 30 sites. The validation of the indicators consisted of two primary processes: logical validity and statistical analysis. The six indicators currently in the program are scrams, safety system actuations, significant events, safety system failures, forced outage rate, and equipment forced outages per 100 critical hours. A report containing data on the six performance indicators and some supplemental information is issued on a quarterly basis. The NRC staff is also working on refinements of existing indicators and development of additional indicators as directed by the commission

The NRC measurement verification program

International Nuclear Information System (INIS)

Pham, T.N.; Ong, L.D.Y.

1995-01-01

A perspective is presented on the US Nuclear Regulatory Commission (NRC) approach for effectively monitoring the measurement methods and directly testing the capability and performance of licensee measurement systems. A main objective in material control and accounting (MC and A) inspection activities is to assure the accuracy and precision of the accounting system and the absence of potential process anomalies through overall accountability. The primary means of verification remains the NRC random sampling during routine safeguards inspections. This involves the independent testing of licensee measurement performance with statistical sampling plans for physical inventories, item control, and auditing. A prospective cost-effective alternative overcheck is also discussed in terms of an externally coordinated sample exchange or ''round robin'' program among participating fuel cycle facilities in order to verify the quality of measurement systems, i.e., to assure that analytical measurement results are free of bias

NRC regulatory information conference: Proceedings

International Nuclear Information System (INIS)

1989-09-01

This volume of the report provides the proceedings from the Nuclear Regulatory Commission (NRC) Regulatory Information Conference that was held at the Mayflower Hotel, Washington, DC, on April 18, 19, and 20, 1989. This conference was held by the NRC and chaired by Dr. Thomas E. Mosley, Director, Office of Nuclear Reactor Regulations (NRR) and coordinated by S. Singh Bajwa, Chief, Technical Assistance Management Section, NRR. There were approximately 550 participants from nine countries at the conference. The countries represented were Canada, England, Italy, Japan, Mexico, Spain, Taiwan, Yugoslavia, and the United States. The NRC staff discussed with nuclear industry its regulatory philosophy and approach and the bases on which they have been established. Furthermore, the NRC staff discussed several initiatives that have been implemented recently and their bases as well as NRC's expectations for new initiatives to further improve safety. The figures contained in Appendix A to the volume correspond to the slides that were shown during the presentations. Volume 2 of this report contains the formal papers that were distributed at the beginning of the Regulatory Information Conference and other information about the conference

Spent nuclear fuel project multi-canister overpack, additional NRC requirements

International Nuclear Information System (INIS)

Garvin, L.J.

1998-01-01

The US Department of Energy (DOE), established in the K Basin Spent Nuclear Fuel Project Regulatory Policy, dated August 4, 1995 (hereafter referred to as the Policy), the requirement for new Spent Nuclear Fuel (SNF) Project facilities to achieve nuclear safety equivalency to comparable US Nuclear Regulatory Commission (NRC)-licensed facilities. For activities other than during transport, when the Multi-Canister Overpack (MCO) is used and resides in the Canister Storage Building (CSB), Cold Vacuum Drying (CVD) facility or Hot Conditioning System, additional NRC requirements will also apply to the MCO based on the safety functions it performs and its interfaces with the SNF Project facilities. An evaluation was performed in consideration of the MCO safety functions to identify any additional NRC requirements needed, in combination with the existing and applicable DOE requirements, to establish nuclear safety equivalency for the MCO. The background, basic safety issues and general comparison of NRC and DOE requirements for the SNF Project are presented in WHC-SD-SNF-DB-002

75 FR 60485 - NRC Enforcement Policy Revision

Science.gov (United States)

2010-09-30

... NUCLEAR REGULATORY COMMISSION [NRC-2008-0497] NRC Enforcement Policy Revision AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement. SUMMARY: The Nuclear Regulatory Commission (NRC or Commission) is publishing a major revision to its Enforcement Policy (Enforcement Policy or Policy) to...

NRC Waste Incidental to Reprocessing Program: Overview of Consultation and Monitoring Activities at the Idaho National Laboratory and the Savannah River Site - What We Have Learned - 12470

Energy Technology Data Exchange (ETDEWEB)

Suber, Gregory [Nuclear Regulatory Commission (United States)

2012-07-01

In 2005 the U.S. Nuclear Regulatory Commission (NRC) began to implement a new set of responsibilities under the Ronald W. Reagan National Defense Authorization Act (NDAA) of Fiscal Year 2005. Section 3116 of the NDAA requires the U.S. Department of Energy (DOE) to consult with the NRC for certain non-high level waste determinations and also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2005, the NRC staff began consulting with DOE and completed reviews of draft waste determinations for salt waste at the Savannah River Site. In 2006, a second review was completed on tank waste residuals including sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center Tank Farm at the Idaho National Laboratory. Monitoring Plans were developed for these activities and the NRC is actively monitoring disposal actions at both sites. NRC is currently in consultation with DOE on the F-Area Tank Farm closure and anticipates entering consultation on the H-Area Tank Farm at the Savannah River Site. This paper presents, from the NRC perspective, an overview of how the consultation and monitoring process has evolved since its conception in 2005. It addresses changes in methods and procedures used to collect and develop information used by the NRC in developing the technical evaluation report and monitoring plan under consultation and the implementation the plan under monitoring. It will address lessons learned and best practices developed throughout the process. The NDAA has presented significant challenges for the NRC and DOE. Past and current successes demonstrate that the NDAA can achieve its intended goal of facilitating tank closure at DOE legacy defense waste sites. The NRC believes many of the challenges in performing the WD reviews have been identified and addressed. Lessons learned have been collected and documented throughout the review process. Future success will be contingent on each agencies commitment to

NRC perspectives on the digital system review process

International Nuclear Information System (INIS)

Mauck, J.L.

1998-01-01

Since about 1988, the USNRC has been involved in the review of digital retrofits to instrumentation and control (I and C) systems in nuclear power plants. Initially, this involvement was limited but with the advent of the 1990s, NRC involvement has become greater because of increased interest in and application of digital systems as existing analog systems become obsolete. Criteria for the design of such systems to ensure safety has been promulgated over the years and the USNRC has been actively involved both nationally and internationally with this effort. With the publication of the Zion Eagle 21 Safety Evaluation Report in 1992, Generic Letter 95-02 in April 1995 which endorses EPRI guidance document TR-102348 on digital upgrades and the latest revision to Regulatory Guide 1.152 which endorses IEEE 7.4.3.2-1993; a basic digital system review process was established. The NRC supplemented this review process with recently issued inspection procedures for use by NRC inspectors when conducting onsite reviews of digital modifications. In addition, the NRC undertook a major effort to codify the above guidance and the experience gained from digital system reviews of both operating plant modifications and advanced reactor designs, over these years into a revision to Standard Review Plan, (SRP), NUREG-0800, Chapter 7, Instrumentation and Control. This SRP revision was published in June, 1997, and included new SRP sections, branch technical positions and six new regulatory guides endorsing IEEE standards on software quality. The NRC staff believes that a stable digital system review process is now in place. (author)

Water reactor safety research program. A description of current and planned research

International Nuclear Information System (INIS)

1978-07-01

The U.S. Nuclear Regulatory Commission (NRC) sponsors confirmatory safety research on lightwater reactors in support of the NRC regulatory program. The principal responsibility of the NRC, as implemented through its regulatory program is to ensure that public health, public safety, and the environment are adequately protected. The NRC performs this function by defining conditions for the use of nuclear power and by ensuring through technical review, audit, and follow-up that these conditions are met. The NRC research program provides technical information, independent of the nuclear industry, to aid in discharging these regulatory responsibilities. The objectives of NRC's research program are the following: (1) to maintain a confirmatory research program that supports assurance of public health and safety, and public confidence in the regulatory program, (2) to provide objectively evaluated safety data and analytical methods that meet the needs of regulatory activities, (3) to provide better quantified estimates of the margins of safety for reactor systems, fuel cycle facilities, and transportation systems, (4) to establish a broad and coherent exchange of safety research information with other Federal agencies, industry, and foreign organization. Current and planned research toward these goals is described

Assessment of the NRC Enforcement Program

International Nuclear Information System (INIS)

Lieberman, J.; Coblentz, L.

1995-04-01

On May 12, 1994, the Executive Director for Operations (EDO) established a Review Team composed of senior NRC managers to re-examine the NRC enforcement program. A copy of the Review Team's charter is enclosed as Appendix A. This report presents the Team's assessment. The purpose of this review effort are: (1) to perform an assessment of the NRC's enforcement program to determine whether the defined purposes of the enforcement program are appropriate; (2) to determine whether the NRC's enforcement practices and procedures for issuing enforcement actions are consistent with those purposes; and (3) to provide recommendations on any changes the Review Team believes advisable. In accordance with its charter, the Review Team considered the following principal issues in conducting its assessment of the enforcement program: the balance between providing deterrence and incentives (both positive and negative) for the identification and correction of violations; the appropriateness of NRC sanctions; whether the commission should seek statutory authority to increase the amount of civil penalties; whether the NRC should use different enforcement policies and practices for different licensees (e.g., materials licensees in contrast to power reactors or large fuel facilities); and whether the commission should establish open enforcement conferences as the normal practice

Impacts of NRC programs on state and local governments

International Nuclear Information System (INIS)

Nussbaumer, D.A.; Lubenau, J.O.

1983-12-01

This document reports the results of an NRC staff examination of the impacts of NRC regulatory programs on State and local governments. Twenty NRC programs are identified. For each, the source of the program (e.g., statutory requirement) and NRC funding availability are described and the impacts upon State and local governments are assessed. Recommendations for NRC monitoring and assessing impacts and for enhancing NRC staff awareness of the impacts are offered

NRC inventory of dams

International Nuclear Information System (INIS)

Lear, G.E.; Thompson, O.O.

1983-01-01

The NRC Inventory of Dams has been prepared as required by the charter of the NRC Dam Safety Officer. The inventory lists 51 dams associated with nuclear power plant sites and 14 uranium mill tailings dams (licensed by NRC) in the US as of February 1, 1982. Of the 85 listed nuclear power plants (148 units), 26 plants obtain cooling water from impoundments formed by dams. The 51 dams associated with the plants are: located on a plant site (29 dams at 15 plant sites); located off site but provide plant cooling water (18 dams at 11 additional plant sites); and located upstream from a plant (4 dams) - they have been identified as dams whose failure, and ensuing plant flooding, could result in a radiological risk to the public health and safety. The dams that might be considered NRC's responsibility in terms of the federal dam safety program are identified. This group of dams (20 on nuclear power plant sites and 14 uranium mill tailings dams) was obtained by eliminating dams that do not pose a flooding hazard (e.g., submerged dams) and dams that are regulated by another federal agency. The report includes the principal design features of all dams and related useful information

10 CFR 2.709 - Discovery against NRC staff.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Discovery against NRC staff. 2.709 Section 2.709 Energy... Rules for Formal Adjudications § 2.709 Discovery against NRC staff. (a)(1) In a proceeding in which the NRC staff is a party, the NRC staff will make available one or more witnesses, designated by the...

NRC assessment of the high-level waste repository quality assurance program

International Nuclear Information System (INIS)

Kennedy, J.E.

1987-01-01

As part of its licensing responsibilities, the NRC is independently reviewing the DOE quality assurance program applied to the site characterization phase activities. Data collected and other information generated during this phase of the program will ultimately be used in a license application to demonstrate the suitability of one site for long-term isolation of waste. They must therefore fall under the quality assurance program to provide confidence in their adequacy. This NRC review consists of three main activities: development of staff guidance on quality assurance measures appropriate for site characterization activities; review of DOE QA plans and procedures; and audits and other reviews of the implementation of the program

Nuclear regulation. NRC's security clearance program can be strengthened

International Nuclear Information System (INIS)

Fultz, Keith O.; Kruslicky, Mary Ann; Bagnulo, John E.

1988-12-01

Because of the national security implications of its programs, the Nuclear Regulatory Commission (NRC) investigates the background of its employees and consultants as well as others to ensure that they are reliable and trustworthy. If the investigation indicates that an employee will not endanger national security, NRC grants a security clearance that allows access to classified information, material, and facilities. NRC also requires periodic checks for some clearance holders to ensure their continued clearance eligibility. The Chairman, Subcommittee on Environment, Energy, and Natural Resources, House Committee on Government Operations, asked GAO to review NRC's personnel security clearance program and assess the procedures that NRC uses to ensure that those who operate nuclear power plants do not pose a threat to the public. The Atomic Energy Act of 1954 requires NRC to conduct background investigations of its employees and consultants as well as others who have access to classified information, material, or facilities. To do this, NRC established a personnel security clearance program. Under NRC policies, a security clearance is granted after the Office of Personnel Management (OPM) or the Federal Bureau of Investigation checks the background of those applying for an NRC clearance. NRC also periodically reassesses the integrity of those holding the highest level clearance. NRC employees, consultants, contractors, and licensees as well as other federal employees hold approximately 10,600 NRC clearances. NRC does not grant clearances to commercial nuclear utility employees unless they require access to classified information or special nuclear material. However, the utilities have voluntarily established screening programs to ensure that their employees do not pose a threat to nuclear plants. NRC faces a dilemma when it hires new employees. Although its policy calls for new hires to be cleared before they start work, the security clearance process takes so long

Army Medical Research and Materiel Command Resident Research Associateship Program

Science.gov (United States)

2018-05-01

Unlimited 13. SUPPLEMENTARY NOTES 14. ABSTRACT During this reporting period, the NRC promoted research opportunities at AMRMC institutes through a... productivity of these Associates is listed in the technical report. 15. SUBJECT TERMS- Associateship program, post-doc, awards 16. SECURITY CLASSIFICATION OF...following activities in support of the subject contract: Outreach and Promotion The promotional schedule to advertise the NRC Research Associateship

NRC comprehensive records disposition schedule

International Nuclear Information System (INIS)

1983-05-01

Effective January 1, 1982, NRC will institute records retention and disposal practives in accordance with the approved Comprehensive Records Disposition Schedule (CRDS). CRDS is comprised of NRC Schedules (NRCS) 1 to 4 which apply to the agency's program or substantive records and General Records Schedules (GRS) 1 to 24 which apply to housekeeping or facilitative records. NRCS-I applies to records common to all or most NRC offices; NRCS-II applies to program records as found in the various offices of the Commission, Atomic Safety and Licensing Board Panel, and the Atomic Safety and Licensing Appeal Panel; NRCS-III applies to records accumulated by the Advisory Committee on Reactor Safeguards; and NRCS-IV applies to records accumulated in the various NRC offices under the Executive Director for Operations. The schedules are assembled functionally/organizationally to facilitate their use. Preceding the records descriptions and disposition instructions for both NRCS and GRS, there are brief statements on the organizational units which accumulate the records in each functional area, and other information regarding the schedules' applicability

REVIEW OF NRC APPROVED DIGITAL CONTROL SYSTEMS ANALYSIS

International Nuclear Information System (INIS)

Markman, D.W.

1999-01-01

Preliminary design concepts for the proposed Subsurface Repository at Yucca Mountain indicate extensive reliance on modern, computer-based, digital control technologies. The purpose of this analysis is to investigate the degree to which the U. S. Nuclear Regulatory Commission (NRC) has accepted and approved the use of digital control technology for safety-related applications within the nuclear power industry. This analysis reviews cases of existing digitally-based control systems that have been approved by the NRC. These cases can serve as precedence for using similar types of digitally-based control technologies within the Subsurface Repository. While it is anticipated that the Yucca Mountain Project (YMP) will not contain control systems as complex as those required for a nuclear power plant, the review of these existing NRC approved applications will provide the YMP with valuable insight into the NRCs review process and design expectations for safety-related digital control systems. According to the YMP Compliance Program Guidance, portions of various NUREGS, Regulatory Guidelines, and nuclear IEEE standards the nuclear power plant safety related concept would be applied to some of the designs on a case-by-case basis. This analysis will consider key design methods, capabilities, successes, and important limitations or problems of selected control systems that have been approved for use in the Nuclear Power industry. An additional purpose of this analysis is to provide background information in support of further development of design criteria for the YMP. The scope and primary objectives of this analysis are to: (1) Identify and research the extent and precedence of digital control and remotely operated systems approved by the NRC for the nuclear power industry. Help provide a basis for using and relying on digital technologies for nuclear related safety critical applications. (2) Identify the basic control architecture and methods of key digital control

Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 3, Development documentation

Energy Technology Data Exchange (ETDEWEB)

Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

1993-10-01

The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume III, is a detailed documentation of the development effort and the pilot training program.

76 FR 40755 - Impact of Reduced Dose Limits on NRC Licensed Activities; Solicitation of Public Comment

Science.gov (United States)

2011-07-11

... scientifically justified, to achieve greater alignment with the 2007 recommendations of the International... and image files of the NRC's public documents. If you do not have access to ADAMS or if there are... informed of all the benefits and burdens associated with further alignment of NRC's current radiation...

NRC TLD Direct Radiation Monitoring Network

International Nuclear Information System (INIS)

Struckmeyer, R.; McNamara, N.

1991-12-01

This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facilities throughout the country for the third quarter of 1991

Status of ECCS Acceptance Criteria Revision in U. S. NRC and Perspective

International Nuclear Information System (INIS)

Lee, Joosuk; Woo, Swengwoong

2013-01-01

Subsequently the NRC had conducted a fuel cladding research program to investigate the behavior of high burnup fuel cladding under LOCA conditions. This research program conducted at Argonne National Laboratory (ANL), as well as conducted as jointly-funded programs at the Kurchatov Institute and the Halden Reactor. From these programs, several important technical findings, listed in following section, for rule revision were obtained. On March 14, 2000, the Nuclear Energy Institute (NEI) submitted a petition for rulemaking (PRM) requesting that the NRC amend its regulations in 50.44 and 50.46 (PRM 50-71). The NEI petition stated that these regulations apply to only two specific zirconium-alloy fuel cladding materials (zircaloy and ZIRLO TM ). The NRC resolved PRM-50-71 by deciding that it should be considered in the following rulemaking process. Meanwhile, on March 15, 2007, Mark Leyse submitted a PRM to the NRC (PRM 50-84). The petitioner requests that the NRC conduct rulemaking in the following areas: Establish regulations that require licensees to operate light-water power reactors under conditions that are effective in limiting the thickness of crud and/or oxide layers. Amend Appendix K to Part 50 to explicitly require that steady-state temperature distribution and stored energy in the reactor fuel at the onset of a postulated LOCA be calculated by factoring in the role of the thermal resistance of crud and oxide layers. Amend 50.46 to specify a maximum allowable percentage of hydrogen content in the cladding. The NRC resolved PRM-50-84 by deciding that the petitioner's issues should be considered in the rulemaking process. On August 13, 2009, the NRC published an Advance Notice of Proposed Rulemaking (ANPR) to obtain stakeholder views on issues associated with amending 50.46. On March 1, 2012, and subsequently modified by the staff's June 1, 2012, SECY-12-0034 was submitted to the Commission to obtain approval to publish for public comment, and it was approved

Status of ECCS Acceptance Criteria Revision in U. S. NRC and Perspective

Energy Technology Data Exchange (ETDEWEB)

Lee, Joosuk; Woo, Swengwoong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-05-15

Subsequently the NRC had conducted a fuel cladding research program to investigate the behavior of high burnup fuel cladding under LOCA conditions. This research program conducted at Argonne National Laboratory (ANL), as well as conducted as jointly-funded programs at the Kurchatov Institute and the Halden Reactor. From these programs, several important technical findings, listed in following section, for rule revision were obtained. On March 14, 2000, the Nuclear Energy Institute (NEI) submitted a petition for rulemaking (PRM) requesting that the NRC amend its regulations in 50.44 and 50.46 (PRM 50-71). The NEI petition stated that these regulations apply to only two specific zirconium-alloy fuel cladding materials (zircaloy and ZIRLO{sup TM}). The NRC resolved PRM-50-71 by deciding that it should be considered in the following rulemaking process. Meanwhile, on March 15, 2007, Mark Leyse submitted a PRM to the NRC (PRM 50-84). The petitioner requests that the NRC conduct rulemaking in the following areas: Establish regulations that require licensees to operate light-water power reactors under conditions that are effective in limiting the thickness of crud and/or oxide layers. Amend Appendix K to Part 50 to explicitly require that steady-state temperature distribution and stored energy in the reactor fuel at the onset of a postulated LOCA be calculated by factoring in the role of the thermal resistance of crud and oxide layers. Amend 50.46 to specify a maximum allowable percentage of hydrogen content in the cladding. The NRC resolved PRM-50-84 by deciding that the petitioner's issues should be considered in the rulemaking process. On August 13, 2009, the NRC published an Advance Notice of Proposed Rulemaking (ANPR) to obtain stakeholder views on issues associated with amending 50.46. On March 1, 2012, and subsequently modified by the staff's June 1, 2012, SECY-12-0034 was submitted to the Commission to obtain approval to publish for public comment, and it

EPA Response to the National Research Council (NRC) Report - A Review of the Technical Basis of the Chemical and Pathogen Regulations for Biosolids

Science.gov (United States)

The NRC published two reports over a twenty year span. They concluded that there is no documented scientific evidence that sewage sludge regulations have failed to protect public health, but identified areas of research.

78 FR 5838 - NRC Enforcement Policy

Science.gov (United States)

2013-01-28

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0014] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Policy revision; issuance and request for comments. SUMMARY: The U.S. Nuclear Regulatory... Nuclear Regulatory Commission Enforcement Policy,'' December 30, 2009 (ADAMS Accession No. ML093200520);(2...

10 CFR 51.40 - Consultation with NRC staff.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Consultation with NRC staff. 51.40 Section 51.40 Energy....40 Consultation with NRC staff. (a) A prospective applicant or petitioner for rulemaking is encouraged to confer with NRC staff as early as possible in its planning process before submitting...

Future of Nuclear Power: NRC emergency preparedness licensing activities agenda

International Nuclear Information System (INIS)

Essig, T.H.

1995-01-01

This talk summary addresses the issue of how future policies of the NRC will affect nuclear power in areas such as construction, emergency preparedness, and licensing. Specific topics covered include the following: Emergent EP licensing issues for operating nuclear Power Plants; 10CFR Part 52 and the process for licensing of Advanced Light Water Reactors (ALWRs); and potential revisions to emergency preparedness programs for future nuclear power plants

Inspection methods for physical protection Task III review of other agencies' physical security activities for research reactors

International Nuclear Information System (INIS)

In Task I of this project, the current Nuclear Regulatory Commission (NRC) position-on physical security practices and procedures at research reactors were reviewed. In the second task, a sampling of the physical security plans was presented and the three actual reactor sites described in the security plans were visited. The purpose of Task III is to review other agencies' physical security activities for research reactors. During this phase, the actions, procedures and policies of two domestic and two foreign agencies other than the NRC that relate to the research reactor community were examined. The agencies examined were: International Atomic Energy Agency; Canadian Atomic Energy Control Board; Department of Energy; and American Nuclear Insurers

ITAAC Development for APR1400 NRC Design Certification

International Nuclear Information System (INIS)

Kim, Jin Kwon; Kim, Myoung Ki

2013-01-01

ITAAC (Inspections, Tests, Analyses and Acceptance Criteria) is essential document for Design Certification, which is certified by NRC and ruled as the Appendix of the 10 CFR Part 52. Approximately 870 ITAAC items were selected for APR1400 Design Certification to be submitted to NRC. In this paper, the code and standard related to ITAAC and process of ITACC development are discussed to seek the way to complete the best ITAAC to get the Design Certification of APR1400 from NRC through the lessons learned from other competitive applicants. For saving the time and manpower to complete ITAAC of APR1400 NRC DC and reduction of the RAIs (Request Additional Information) from NRC, we took advantage of the lessons learned from the competitive designs like US-APWR and AP1000 based on KNGR ITAAC. Finally new and different ITAAC from ITAAC of KNGR was developed for APR1400 DC from NRC. RG 1.206 and SRPs were applied first in Korea to the APR1400 DCD preparation. For testability and acceptability check, ITAAC V and V table was completed by the system designers. APR1400 DCD will be submitted by the end of September this year and we hope that NRC issues lees RAIs on ITAAC document

NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

Reports distributed under the NRC Light-Water Reactor Safety Research Foreign Technical Exchange Program. Volume III, January--June 1977

International Nuclear Information System (INIS)

Sharp, D.S.; Cottrell, W.B.

1977-01-01

Lists of documents exchanged during the first half of 1977 under agreements between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, and Japan are presented. During this period, the NRC received 41 reports from France, 29 from F. R. Germany, and 24 from Japan, and in return sent 107 U.S. reports to each of these three countries

Agency procedures for the NRC incident response plan. Final report

International Nuclear Information System (INIS)

1983-02-01

The NRC Incident Response Plan, NUREG-0728/MC 0502 describes the functions of the NRC during an incident and the kinds of actions that comprise an NRC response. The NRC response plan will be activated in accordance with threshold criteria described in the plan for incidents occurring at nuclear reactors and fuel facilities involving materials licensees; during transportation of licensed material, and for threats against facilities or licensed material. In contrast to the general overview provided by the Plan, the purpose of these agency procedures is to delineate the manner in which each planned response function is performed; the criteria for making those response decisions which can be preplanned; and the information and other resources needed during a response. An inexperienced but qualified person should be able to perform functions assigned by the Plan and make necessary decisions, given the specified information, by becoming familiar with these procedures. This rule of thumb has been used to determine the amount of detail in which the agency procedures are described. These procedures form a foundation for the training of response personnel both in their normal working environment and during planned emergency exercises. These procedures also form a ready reference or reminder checklist for technical team members and managers during a response

The NRC weighs public input on plant cleanup standards

International Nuclear Information System (INIS)

Simpson, J.

1993-01-01

In the wake of seven public open-quotes work-shopsclose quotes held around the country over the past several months, the Nuclear Regulatory Commission (NRC) is preparing to develop radiological criteria for decommissioning nuclear power plants. The criteria will apply to plants that operate for their normal lifespan, those that shut down prematurely, as well as a range of other NRC-licensed facilities, including materials licensees, fuel reprocessing and fabrication plants, and independent spent fuel storage installations. The criteria have been years in the making, and their progress is being monitored closely by the Environmental Protection Agency (EPA), which shares with the NRC the authority to regulate radiological hazards. Both agencies have made abortive attempts to promulgate standards in the past. The EPA's most recent proposal, dating from 1986, has yet to reach the final rule stage. The NCRC's 1990 policy statement, open-quotes Below Regulatory Concern,close quotes was overturned by the Energy Policy Act of 1992, a setback that prompted the Commission's call for open-quotes enhanced participatory rulemakingclose quotes-a.k.a., public meetings-last December. In its Rulemaking Issues Paper, the NRC outlined for discussion four open-quotes fundamentalclose quotes objectives as a basis for developing decommissioning criteria: (1) establishing limits above which the risks to the public are deemed open-quotes unacceptableclose quotes; (2) establishing open-quotes goalsclose quotes below which the risks to the public are deemed open-quotes trivialclose quotes; (3) establishing criteria for what is achievable using the open-quotes best availableclose quotes cleanup technology; and (4) removing all radioactivity attributable to plant activity. The NRC expects to publish a proposed rule and a draft generic environmental impact statement in April 1994; the final rule is scheduled for May 1995

Initial demonstration of the NRC`s capability to conduct a performance assessment for a High-Level Waste Repository

Energy Technology Data Exchange (ETDEWEB)

Codell, R.; Eisenberg, N.; Fehringer, D.; Ford, W.; Margulies, T.; McCartin, T.; Park, J.; Randall, J.

1992-05-01

In order to better review licensing submittals for a High-Level Waste Repository, the US Nuclear Regulatory Commission staff has expanded and improved its capability to conduct performance assessments. This report documents an initial demonstration of this capability. The demonstration made use of the limited data from Yucca Mountain, Nevada to investigate a small set of scenario classes. Models of release and transport of radionuclides from a repository via the groundwater and direct release pathways provided preliminary estimates of releases to the accessible environment for a 10,000 year simulation time. Latin hypercube sampling of input parameters was used to express results as distributions and to investigate model sensitivities. This methodology demonstration should not be interpreted as an estimate of performance of the proposed repository at Yucca Mountain, Nevada. By expanding and developing the NRC staff capability to conduct such analyses, NRC would be better able to conduct an independent technical review of the US Department of Energy (DOE) licensing submittals for a high-level waste (HLW) repository. These activities were divided initially into Phase 1 and Phase 2 activities. Additional phases may follow as part of a program of iterative performance assessment at the NRC. The NRC staff conducted Phase 1 activities primarily in CY 1989 with minimal participation from NRC contractors. The Phase 2 activities were to involve NRC contractors actively and to provide for the transfer of technology. The Phase 2 activities are scheduled to start in CY 1990, to allow Sandia National Laboratories to complete development and transfer of computer codes and the Center for Nuclear Waste Regulatory Analyses (CNWRA) to be in a position to assist in the acquisition of the codes.

NRC Licensing Status Summary Report for NGNP

Energy Technology Data Exchange (ETDEWEB)

Moe, Wayne Leland [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kinsey, James Carl [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-11-01

The Next Generation Nuclear Plant (NGNP) Project, initiated at Idaho National Laboratory (INL) by the U.S. Department of Energy (DOE) pursuant to provisions of the Energy Policy Act of 2005, is based on research and development activities supported by the Department of Energy Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of high temperature gas-cooled reactor (HTGR) technology. The HTGR is a helium-cooled and graphite moderated reactor that can operate at temperatures much higher than those of conventional light water reactor (LWR) technologies. The NGNP will be licensed for construction and operation by the Nuclear Regulatory Commission (NRC). However, not all elements of current regulations (and their related implementation guidance) can be applied to HTGR technology at this time. Certain policies established during past LWR licensing actions must be realigned to properly accommodate advanced HTGR technology. A strategy for licensing HTGR technology was developed and executed through the cooperative effort of DOE and the NRC through the NGNP Project. The purpose of this report is to provide a snapshot of the current status of the still evolving pre-license application regulatory framework relative to commercial HTGR technology deployment in the U.S. The following discussion focuses on (1) describing what has been accomplished by the NGNP Project up to the time of this report, and (2) providing observations and recommendations concerning actions that remain to be accomplished to enable the safe and timely licensing of a commercial HTGR facility in the U.S.

Public citizen slams NRC on nuclear inspections

International Nuclear Information System (INIS)

Newman, P.

1993-01-01

Charging the Nuclear Regulatory Commission with open-quotes abandoning tough regulation of the nuclear power industry,close quotes Public Citizen's Critical Mass Energy Project on Wednesday released a report asserting that NRC is shielding sensitive internal nuclear industry self-evaluations from public scrutiny. Based on their review of 56 Institute of Nuclear Power Operations reports and evaluations and comparing these to the NRC's Systematic Assessment of Licensee Performance reports for the same plants, it was concluded that the NRC failed to address issues raised in all eight areas evaluated by the INPO reports

Recommendations for NEAMS Engagement with the NRC: Preliminary Report

International Nuclear Information System (INIS)

Bernholdt, David E.

2012-01-01

The vision of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program is to bring a new generation of analytic tools to the nuclear engineering community in order to facilitate students, faculty, industry and laboratory researchers in investigating advanced reactor and fuel cycle designs. Although primarily targeting at advance nuclear technologies, it is anticipated that these new capabilities will also become interesting and useful to the nuclear regulator Consequently, the NEAMS program needs to engage with the Nuclear Regulatory Commission as the software is being developed to ensure that they are familiar with and ready to respond to this novel approach when the need arises. Through discussions between key NEAMS and NRC staff members, we tentatively recommend annual briefings to the Division of Systems Analysis in the NRC's Office of Nuclear Regulatory Research. However the NEAC subcommittee review of the NEAMS program may yield recommendations that would need to be considered before finalizing this plan.

Recommendations for NEAMS Engagement with the NRC: Preliminary Report

Energy Technology Data Exchange (ETDEWEB)

Bernholdt, David E [ORNL

2012-06-01

The vision of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program is to bring a new generation of analytic tools to the nuclear engineering community in order to facilitate students, faculty, industry and laboratory researchers in investigating advanced reactor and fuel cycle designs. Although primarily targeting at advance nuclear technologies, it is anticipated that these new capabilities will also become interesting and useful to the nuclear regulator Consequently, the NEAMS program needs to engage with the Nuclear Regulatory Commission as the software is being developed to ensure that they are familiar with and ready to respond to this novel approach when the need arises. Through discussions between key NEAMS and NRC staff members, we tentatively recommend annual briefings to the Division of Systems Analysis in the NRC's Office of Nuclear Regulatory Research. However the NEAC subcommittee review of the NEAMS program may yield recommendations that would need to be considered before finalizing this plan.

Assessment of current NRC/IE professional training program and recommendations for improvement

International Nuclear Information System (INIS)

Bartley, H.J.; Hagerup, J.E.; Harrison, O.J.; Heyer, F.H.K.; Kaas, I.W.; Schwartz, E.G.

1978-05-01

This document is the General Research Corporation (GRC) report on Task III: to assess the current NRC/IE professional training program and to provide recommendations for improvement. The major objectives of this task were to determine the overall effectiveness of the NRC/IE training program and to provide recommendations for improvements where appropriate. The research involved a review of course manuals and of student critiques, observation in the classroom and person to person interviews; it also included an evaluation of the assignment of instructors to the Career Management Branch. Findings addressed refresher training, retread training and initial training--with emphasis on the last of these. Conclusions are that: (1) The curriculum provides, in general, types and levels of training needed; (2) the mix of training methods used is correct; and (3) the training management is effective. However, the training facilities do not reflect a commitment to quality instruction nor is assignment as instructor to the Career Management Branch attractive to inspectors. Recommendations presented in the report are based upon the findings; all lie within the implementing authority of Headquarters NRC/IE

The NRC perspective on low-level radioactive waste disposal

International Nuclear Information System (INIS)

Thompson, H.L. Jr.; Knapp, M.R.

1987-01-01

This paper describes the Nuclear Regulatory Commission's (NRC) actions in response to the Low-Level Radioactive Waste Policy Amendments Act (the Act) and NRC's assistance to States and Compacts working to discharge their responsibilities under the Act. Three of NRC's accomplishments which respond explicitly to direction in the Act are highlighted. These are: development of the capability of expedited handling of petitions addressing wastes below regulatory concern (BRC); development of capability to review and process an application within fifteen months; and development of guidance on alternatives to shallow land burial. Certain NRC efforts concerning special topics related to the Act as well as NRC efforts to assist States and Compacts are summarized

Safeguards at NRC licensed facilities: Are we doing enough

International Nuclear Information System (INIS)

Asselstine, J.K.

1986-01-01

Safeguards at the Nuclear Regulatory Commission (NRC) facilities are discussed in this paper. The NRC is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 2, Investigators`s Manual

Energy Technology Data Exchange (ETDEWEB)

Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

1993-10-01

The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause event at nuclear power plants. This document, Volume II, is a field manual for use by investigators when performing event investigations. Volume II includes the HPIP Procedure, the HPIP Modules, and Appendices that provide extensive documentation of each investigation technique.

PRA research and the development of risk-informed regulation at the U.S. nuclear regulatory commission

International Nuclear Information System (INIS)

Siu, Nathan; Collins, Dorothy

2008-01-01

Over the years, Probabilistic Risk Assessment (PRA) research activities conducted at the U.S. Nuclear Regulatory Commission (NRC) have played an essential role in support of the agency's move towards risk-informed regulation. These research activities have provided the technical basis for NRC's regulatory activities in key areas; provided PRA methods, tools, and data enabling the agency to meet future challenges; supported the implementation of NRC's 1995 PRA Policy Statement by assessing key sources of risk; and supported the development of necessary technical and human resources supporting NRC's risk-informed activities. PRA research aimed at improving the NRC's understanding of risk can positively affect the agency's regulatory activities, as evidenced by three case studies involving research on fire PRA, Human Reliability Analysis (HRA), and Pressurized Thermal Shock (PTS) PRA. These case studies also show that such research can take a considerable amount of time, and that the incorporation of research results into regulatory practice can take even longer. The need for sustained effort and appropriate lead time is an important consideration in the development of a PRA research program aimed at helping the agency address key sources of risk for current and potential future facilities

10 CFR 2.1202 - Authority and role of NRC staff.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of NRC staff. 2.1202 Section 2.1202... ORDERS Informal Hearing Procedures for NRC Adjudications § 2.1202 Authority and role of NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings in its...

NRC sponsored rotating equipment vibration research: a program description and progress report

International Nuclear Information System (INIS)

Nitzel, M.E.

1986-01-01

The Idaho National Engineering Laboratory (INEL) is currently involved in a research project sponsored by the United States Nuclear Regulatory Commission (NRC) regarding operational vibration in rotating equipment. The object of this program is to assess the nature of vibrational failures and the effect that improved qualification standards may have in reducing the incidence of failure. In order to limit the scope of the initial effort, safety injection (SI) pumps were chosen as the component group for concentrated study. The task has been oriented to addressing the issues of whether certain SI pumps experience more failures than others, examining the dynamic environments in operation, examining the adequacy of current qualification standards, and examining what performance parameters could be used more efficiently to predict degradation or failure. Results of a literature search performed to survey SI pump failures indicate that failures are due to a diversity of causes, many of which may not be influenced by qualification criteria. Cooperative efforts have been undertaken with a limited number of nuclear utilities to describe the variety of possible operating environments and to analyze available data. The results of this analysis as they apply to the research issues are presented and possibilities for the future direction of the program are discussed

Reports distributed under the NRC Light-Water Reactor Safety Research Foreign Technical Exchange Program. Volume III, January--June 1977

Energy Technology Data Exchange (ETDEWEB)

Sharp, D.S.; Cottrell, W.B.

1977-09-19

Lists of documents exchanged during the first half of 1977 under agreements between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, and Japan are presented. During this period, the NRC received 41 reports from France, 29 from F. R. Germany, and 24 from Japan, and in return sent 107 U.S. reports to each of these three countries.

NRC perspectives on fuel cycle and safeguards

International Nuclear Information System (INIS)

Chapman, K.R.

1976-01-01

This paper discusses NRC's mandate in the field of safeguards and the thoughts of NRC on other newly emerging policy considerations. The status of some of the current issues facing the nuclear community and the regulatory staff in particular is touched on

Shift technical advisors: in the eyes of the NRC

International Nuclear Information System (INIS)

Crocker, L.P.

1981-01-01

Since January 1, 1980, the NRC has required that Shift Technical Advisors be on-shift at all operating nuclear power plants. The objective of the requirement is to assure that technical expertise is immediately available to each operating shift to assess off-normal events and to provide advice to control room personnel. Further, this advice and assistance is to be provided by an individual not responsible for control manipulations or for directing the activities of reactor operators. The long-term requirement for on-shift technical expertise is firm. However, the exact manner in which this expertise must be furnished has not been determined. Licensees have proposed various alternatives to meet this requirement. These proposals still are being reviewed by the NRC staff

NRC methods for evaluation of industry training

International Nuclear Information System (INIS)

Morisseau, D.S.; Koontz, J.L.; Persensky, J.J.

1987-01-01

On March 20, 1985, the Nuclear Regulatory Commission published the Policy Statement on Training and Qualification. The Policy Statement endorsed the INPO-managed Training Accreditation Program because it encompasses the five elements of performance-based training. This paper described the multiple methods that the NRC is using to monitor industry efforts to improve training and implement the NRC Policy Statement on Training and Qualification. The results of the evaluation of industry training improvement programs will be reviewed by the Commissioners in April 1987 to determine the nature of continuing NRC policy and programs for ensuring effective training for the US nuclear industry

NRC approach to evaluating training effectiveness in accordance with the policy statement on training

International Nuclear Information System (INIS)

Persensky, J.J.; Blumer, A.H.

1985-01-01

The activity of the past two years has provided an opportunity for the NRC to examine and realign the way in which it views the training process. In the process, it has provided the industry with an incentive to emphasize training as an opportunity for enlightened self-regulation. As a result, the NRC and industry perspectives on training have, for all intents and purposes, merged into a single performance orientation. This cooperation should provide the needed momentum towards improvements in training effectiveness. It is the NRC's goal to monitor this momentum and to encourage progress toward the ideal of systematic, performance-based training for all essential personnel in the nuclear industry

Significant NRC Enforcement Actions

Data.gov (United States)

Nuclear Regulatory Commission — This dataset provides a list of Nuclear Regulartory Commission (NRC) issued significant enforcement actions. These actions, referred to as "escalated", are issued by...

10 CFR 2.1505 - Role of the NRC staff.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Role of the NRC staff. 2.1505 Section 2.1505 Energy... Legislative Hearings § 2.1505 Role of the NRC staff. The NRC staff shall be available to answer any Commission or presiding officer's questions on staff-prepared documents, provide additional information or...

NRC Regulatory Agenda

International Nuclear Information System (INIS)

1989-07-01

This document is a compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

Overview of the NRC nuclear waste management program

International Nuclear Information System (INIS)

Malaro, J.C.

1976-01-01

The NRC has firmly established waste management as a high-priority effort and has made the commitment to act rapidly and methodically to establish a sound regulatory base for licensing waste management activities. We believe the priorities for NRC work in waste management are consistent with the needs of the overall national waste management program. Present licensing procedures and criteria are adequate for the short term, and priority attention is being given to the longer term, when the quantities of waste to be managed will be greater and licensing demands will increase. Recognizing that its decision will affect industry, other governmental jurisdictions, private interest groups, and the public at large, NRC has encouraged and will continue to encourage their participation in planning our program. We also recognize that the problems of nuclear waste management are international in scope. Many waste management problems (e.g., potential for contamination of oceans and atmosphere, need for isolation of some wastes for longer periods than governments and political boundaries have remained stable in the past), require a set of internationally acceptable and accepted solutions. The wastes from the U.S. nuclear industry will account for only about one third of the nuclear waste generated in the world. Therefore, we propose to cooperate and where appropriate take the lead in establishing acceptable worldwide policies, standards and procedures for handling nuclear wastes

Report to Congress on NRC emergency communications

Energy Technology Data Exchange (ETDEWEB)

NONE

1980-09-01

The accident at Three Mile Island highlighted the need for improved communications among the NRC and other organizations which respond to such emergencies. This report summarizes the communication problems identified by several major review groups after the accident, the status of corrective actions, and NRC plans to improve communications still further. (author)

Reports distributed under the NRC Light-Water Reactor Safety Research Foreign Technical Exchange Program. Volume IV, July--December 1977

International Nuclear Information System (INIS)

Sharp, D.S.; Cottrell, W.B.

1978-01-01

Lists of documents exchanged during the second half of 1977 under agreements between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, Japan, and the United Kingdom are presented. During this period, the NRC received 1 report from France, 40 from the Federal Republic of Germany, and 11 from Japan, and in return sent 112 U.S. reports to each of these three countries and 23 reports to the United Kingdom

NRC comprehensive records disposition schedule

International Nuclear Information System (INIS)

1982-07-01

Effective January 1, 1982, NRC will institute records retention and disposal practices in accordance with the approved Comprehensive Records Disposition Schedule (CRDS). CRDS is comprised of NRC Schedules (NRCS) 1 to 4 which apply to the agency's program or substantive records and General Records Schedules (GRS) 1 to 22 which apply to housekeeping or facilitative records. The schedules are assembled functionally/organizationally to facilitate their use. Preceding the records descriptions and disposition instructions for both NRCS and GRS, there are brief statements on the organizational units which accumulate the records in each functional area, and other information regarding the schedules' applicability

NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147

Energy Technology Data Exchange (ETDEWEB)

Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D. [U.S. Nuclear Regulatory Commission (United States)

2013-07-01

As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in

NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147

International Nuclear Information System (INIS)

Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D.

2013-01-01

As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in coordination with South

Reassessment of the NRC's program for protecting allegers against retaliation

International Nuclear Information System (INIS)

1994-01-01

On July 6, 1993, the Nuclear Regulatory Commission's (NRC's) Executive Director for Operations established a review team to reassess the NRC's program for protecting allegers against retaliation. The team evaluated the current system, and solicited comments from various NRC offices, other Federal agencies, licensees, former allegers, and the public. This report is subject to agency review. The report summarizes current processes and gives an overview of current problems. It discusses: (1) ways in which licensees can promote a quality-conscious work environment, in which all employees feel free to raise concerns without fear of retaliation; (2) ways to improve the NRC's overall handling of allegations; (3) the NRC's involvement in the Department of Labor process; (4) related NRC enforcement practices; and (5) methods other than investigation and enforcement that may be useful in treating allegations of potential or actual discrimination. Recommendations are given in each area

77 FR 30332 - Mr. James Chaisson; Order Prohibiting Involvement in NRC-Licensed Activities

Science.gov (United States)

2012-05-22

... industrial radiographic operations in accordance with conditions specified therein. The license was... NRC conducted a safety and security inspection of the use of byproduct material for industrial... requirements. Mr. Chaisson chose to store a radiographic exposure device at a leased facility on Elk Street in...

NRC comprehensive records disposition schedule. Revision 3

International Nuclear Information System (INIS)

1998-02-01

Title 44 US Code, ''Public Printing and Documents,'' regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ''Management and Use of Information and Records,'' and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ''Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ''NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA's General Records Schedule (dated August 1995)

NRC comprehensive records disposition schedule. Revision 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

NRC Regulatory Agenda

International Nuclear Information System (INIS)

1992-07-01

This document compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rule making which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

NRC/AMRMC Resident Research Associateship Program

Science.gov (United States)

2015-05-01

aspirate characterization for the support of large animal studies. Research in Veterinary Science; In preparation, expected submission February 2015...Activity of Norspermidine Against Clinical Orthopaedic Isolates. (Manuscript Submitted to BMC Microbiology ) Albach AM, Hardy SK, Chang DC, Garcia RG...American Society for Microbiology (ASM) General Meeting. San Francisco, CA. June 15-19,2012. Carlos J. Sanchez Jr. Biofilm-Derived Factors Reduce

General administrative activities

International Nuclear Information System (INIS)

Cottrell, W.B.

1982-01-01

Significant safety-related activities reported during March and April, which are not covered elsewhere in this issue, are summarized here. The Advisory Committee on Reactor Safeguards (ACRS) issued several reports on a variety of topics of current concern to the Nuclear Regulatory Commission (NRC). A recent NRC draft report identifies preliminary ranking of safety issues. The NRC is establishing a new Office of Investigations. The NRC also released a list of plants now under construction which it suspects will be canceled or indefinitely deferred. Four speeches by NRC Commissioners are summarized, as is the only Research Information Letter issued during the report period. Last is a listing of a variety of safety-related topics

NRC's object-oriented simulator instructor station

International Nuclear Information System (INIS)

Griffin, J.I.; Griffin, J.P.

1995-06-01

As part of a comprehensive simulator upgrade program, the simulator computer systems associated with the Nuclear Regulatory Commission's (NRC) nuclear power plant simulators were replaced. Because the original instructor stations for two of the simulators were dependent on the original computer equipment, it was necessary to develop and implement new instructor stations. This report describes the Macintosh-based Instructor Stations developed by NRC engineers for the General Electric (GE) and Babcock and Wilcox (B and W) simulators

NRC Regulatory Agenda: Quarterly report, October--December 1988

International Nuclear Information System (INIS)

1989-01-01

The NRC Regulatory Agenda is a compilation of all rules which the NRC has proposed or is considering action on, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission

General administrative activities

International Nuclear Information System (INIS)

Cottrell, W.B.

1980-01-01

Significant safety-related activities reported during September and October, which are not covered elsewhere in this issue, are summarized here. The Nuclear Regulatory Commission (NRC) has adopted an interim statement of policy on the licensing of nuclear power plants. Four speeches by NRC Commissioners are summarized. The Advisory Committee on Reactor Safeguards (ACRS) issued a review of the NRC Systematic Evaluation Program (SEP). The NRC also issued a policy statement on emergency planning guidance. Two Research Informantion Letters (RILs) issued during the report period are summarized. Last is a listing of developments on a variety os safety-related topics

NRC regulatory agenda

International Nuclear Information System (INIS)

1993-02-01

This document is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considered action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

NRC regulatory agenda

International Nuclear Information System (INIS)

1992-11-01

This document provides a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

NRC comprehensive records disposition schedule

International Nuclear Information System (INIS)

1992-03-01

Title 44 United States Code, ''Public Printing and Documents,'' regulations cited in the General Services Administration's (GSA) ''Federal Information Resources Management Regulations'' (FIRMR), Part 201-9, ''Creation, Maintenance, and Use of Records,'' and regulation issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter XII, Subchapter B, ''Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 2, contains ''NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 2 totally reorganizes the records schedules from a functional arrangement to an arrangement by the host office. A subject index and a conversion table have also been developed for the NRC schedules to allow staff to identify the new schedule numbers easily and to improve their ability to locate applicable schedules

SSI sensitivity studies and model improvements for the US NRC Seismic Safety Margins Research Program. Rev. 1

International Nuclear Information System (INIS)

Johnson, J.J.; Maslenikov, O.R.; Benda, B.J.

1984-10-01

The Seismic Safety Margins Research Program (SSMRP) is a US NRC-funded program conducted by Lawrence Livermore National Laboratory. Its goal is to develop a complete fully coupled analysis procedure for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. In Phase II of the SSMRP, the methodology was applied to the Zion nuclear power plant. Three topics in the SSI analysis of Zion were investigated and reported here - flexible foundation modeling, structure-to-structure interaction, and basemat uplift. The results of these investigations were incorporated in the SSMRP seismic risk analysis. 14 references, 51 figures, 13 tables

Memorandum of Understanding Between U.S. EPA Superfund and U.S. NRC

International Nuclear Information System (INIS)

Walker, Stuart

2008-01-01

The Environmental Protection Agency (EPA) Office of Superfund Remediation and Technology Innovation (OSRTI) and the Nuclear Regulatory Commission (NRC) are responsible for implementing the 'Memorandum of Understanding Between the Environmental Protection Agency and the Nuclear Regulatory Commission: Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites'. This paper provides a brief overview of the origin of the Memorandum of Understanding (MOU), the major features of the MOU, and how the MOU has been implemented site specifically. EPA and NRC developed the MOU in response to direction from the House Committee on Appropriations to EPA and NRC to work together to address the potential for dual regulation. The MOU was signed by EPA on September 30, 2002 and NRC on October 9, 2002. The two agencies had worked on the MOU since March 2000. While both EPA and NRC have statutory authority to clean up these sites, the MOU provides consultation procedures between EPA and NRC to eliminate dual regulation. Under the MOU, EPA and NRC identified the interactions of the two agencies for the decommissioning and decontamination of NRC-licensed sites and the ways in which those responsibilities will be exercised. Except for Section VI, which addresses corrective action under the Resource Conservation and Recovery Act (RCRA), this MOU is limited to the coordination between EPA, when acting under its CERCLA authority, and NRC, when a facility licensed by the NRC is undergoing decommissioning, or when a facility has completed decommissioning, and the NRC has terminated its license. EPA believes that implementation of the MOU between the two agencies will ensure that future confusion about dual regulation does not occur regarding the cleanup and reuse of NRC-licensed sites. NRC and EPA have so far exchanged MOU consultation letters on eight NRC-licensed sites. EPA has responded to each consultation request with a letter expressing its views on actions

A review of NRC staff uses of probabilistic risk assessment

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

The NRC staff uses probabilistic risk assessment (PRA) and risk management as important elements its licensing and regulatory processes. In October 1991, the NRC`s Executive Director for Operations established the PRA Working Group to address concerns identified by the Advisory Committee on Reactor Safeguards with respect to unevenness and inconsistency in the staff`s current uses of PRA. After surveying current staff uses of PRA and identifying needed improvements, the Working Group defined a set of basic principles for staff PRA use and identified three areas for improvements: guidance development, training enhancements, and PRA methods development. For each area of improvement, the Working Group took certain actions and recommended additional work. The Working Group recommended integrating its work with other recent PRA-related activities the staff completed and improving staff interactions with PRA users in the nuclear industry. The Working Group took two key actions by developing general guidance for two uses of PRA within the NRC (that is, screening or prioritizing reactor safety issues and analyzing such issues in detail) and developing guidance on basic terms and methods important to the staff`s uses of PRA.

A review of NRC staff uses of probabilistic risk assessment

International Nuclear Information System (INIS)

1994-03-01

The NRC staff uses probabilistic risk assessment (PRA) and risk management as important elements its licensing and regulatory processes. In October 1991, the NRC's Executive Director for Operations established the PRA Working Group to address concerns identified by the Advisory Committee on Reactor Safeguards with respect to unevenness and inconsistency in the staff's current uses of PRA. After surveying current staff uses of PRA and identifying needed improvements, the Working Group defined a set of basic principles for staff PRA use and identified three areas for improvements: guidance development, training enhancements, and PRA methods development. For each area of improvement, the Working Group took certain actions and recommended additional work. The Working Group recommended integrating its work with other recent PRA-related activities the staff completed and improving staff interactions with PRA users in the nuclear industry. The Working Group took two key actions by developing general guidance for two uses of PRA within the NRC (that is, screening or prioritizing reactor safety issues and analyzing such issues in detail) and developing guidance on basic terms and methods important to the staff's uses of PRA

Data Management Activities of Canada's National Science Library - 2010 Update and Prospective

Directory of Open Access Journals (Sweden)

Mary Zborowski

2011-01-01

Full Text Available NRC-CISTI serves Canada as its National Science Library (as mandated by Canada's Parliament in 1924 and also provides direct support to researchers of the National Research Council of Canada (NRC. By reason of its mandate, vision, and strategic positioning, NRC-CISTI has been rapidly and effectively mobilizing Canadian stakeholders and resources to become a lead player on both the Canadian national and international scenes in matters relating to the organization and management of scientific research data. In a previous communication (CODATA International Conference, 2008, the orientation of NRC-CISTI towards this objective and its short- and medium-term plans and strategies were presented. Since then, significant milestones have been achieved. This paper presents NRC-CISTI's most recent activities in these areas, which are progressing well alongside a strategic organizational redesign process that is realigning NRC-CISTI's structure, mission, and mandate to better serve its clients. Throughout this transformational phase, activities relating to data management remain vibrant.

10 CFR 2.1316 - Authority and role of NRC staff.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of NRC staff. 2.1316 Section 2.1316... ORDERS Procedures for Hearings on License Transfer Applications § 2.1316 Authority and role of NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings...

NRC performance assessment program

International Nuclear Information System (INIS)

Coplan, S.M.

1986-01-01

The U.S. Nuclear Regulatory Commission's (NRC) performance assessment program includes the development of guidance to the U.S. Department of Energy (DOE) on preparation of a license application and on conducting the studies to support a license application. The nature of the licensing requirements of 10 CFR Part 60 create a need for performance assessments by the DOE. The NRC and DOE staffs each have specific roles in assuring the adequacy of those assessments. Performance allocation is an approach for determining what testing and analysis will be needed during site characterization to assure that an adequate data base is available to support the necessary performance assessments. From the standpoint of establishing is implementable methodology, the most challenging performance assessment needed for licensing is the one that will be used to determine compliance with the U.S. Environmental Protection Agency's (EPA) containment requirement

Building beef cow nutritional programs with the 1996 NRC beef cattle requirements model.

Science.gov (United States)

Lardy, G P; Adams, D C; Klopfenstein, T J; Patterson, H H

2004-01-01

Designing a sound cow-calf nutritional program requires knowledge of nutrient requirements, diet quality, and intake. Effectively using the NRC (1996) beef cattle requirements model (1996NRC) also requires knowledge of dietary degradable intake protein (DIP) and microbial efficiency. Objectives of this paper are to 1) describe a framework in which 1996NRC-applicable data can be generated, 2) describe seasonal changes in nutrients on native range, 3) use the 1996NRC to predict nutrient balance for cattle grazing these forages, and 4) make recommendations for using the 1996NRC for forage-fed cattle. Extrusa samples were collected over 2 yr on native upland range and subirrigated meadow in the Nebraska Sandhills. Samples were analyzed for CP, in vitro OM digestibility (IVOMD), and DIP. Regression equations to predict nutrients were developed from these data. The 1996NRC was used to predict nutrient balances based on the dietary nutrient analyses. Recommendations for model users were also developed. On subirrigated meadow, CP and IVOMD increased rapidly during March and April. On native range, CP and IVOMD increased from April through June but decreased rapidly from August through September. Degradable intake protein (DM basis) followed trends similar to CP for both native range and subirrigated meadow. Predicted nutrient balances for spring- and summer-calving cows agreed with reported values in the literature, provided that IVOMD values were converted to DE before use in the model (1.07 x IVOMD - 8.13). When the IVOMD-to-DE conversion was not used, the model gave unrealistically high NE(m) balances. To effectively use the 1996NRC to estimate protein requirements, users should focus on three key estimates: DIP, microbial efficiency, and TDN intake. Consequently, efforts should be focused on adequately describing seasonal changes in forage nutrient content. In order to increase use of the 1996NRC, research is needed in the following areas: 1) cost-effective and

Optimization Conditions of Extracellular Proteases Production from a Newly Isolated Streptomyces Pseudogrisiolus NRC-15

Directory of Open Access Journals (Sweden)

El-Sayed E. Mostafa

2012-01-01

Full Text Available Microbial protease represents the most important industrial enzymes, which have an active role in biotechnological processes. The objective of this study was to isolate new strain of Streptomyces that produce proteolytic enzymes with novel properties and the development of the low-cost medium. An alkaline protease producer strain NRC-15 was isolated from Egyptian soil sample. The cultural, morphological, physiological characters and chemotaxonomic evidence strongly indicated that the NRC-15 strain represents a novel species of the genus Streptomyces, hence the name Strptomyces pseudogrisiolus NRC-15. The culture conditions for higher protease production by NRC-15 were optimized with respect to carbon and nitrogen sources, metal ions, pH and temperature. Maximum protease production was obtained in the medium supplemented with 1% glucose, 1% yeast extract, 6% NaCl and 100 μmol/L of Tween 20, initial pH 9.0 at 50 °C for 96 h. The current results confirm that for this strain, a great ability to produce alkaline proteases, which supports the use of applications in industry.

NRC Regulatory Agenda: Quarterly report, July-September 1987

International Nuclear Information System (INIS)

1987-11-01

The NRC Regulatory agenda is a compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received by the commission and are pending disposition by the commission. The regulatory agenda is updated and issued each quarter

NRC regulatory agenda: Quarterly report, April--June 1988

International Nuclear Information System (INIS)

1988-08-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

Safety Second: the NRC and America's nuclear power plants

International Nuclear Information System (INIS)

Adato, M.; MacKenzie, J.; Pollard, R.; Weiss, E.

1987-01-01

In 1975, Congress created the Nuclear Regulatory Commission (NRC). Its primary responsibility was to be the regulation of the nuclear power industry in order to maintain public health and safety. On March 28, 1979, in the worst commercial nuclear accident in US history, the plant at Three Mile Island began to leak radioactive material. How was Three Mile Island possible? Where was the NRC? This analysis by the Union of Concerned Scientists (UCS) of the NRC's first decade, points specifically to the factors that contributed to the accident at Three Mile Island. The NRC, created as a watchdog of the nuclear power industry, suffers from problems of mindset, says the UCS. The commission's problems are political, not technical; it repeatedly ranks special interests above the interest of public safety. This book critiques the NRC's performance in four specific areas. It charges that the agency has avoided tackling the most pervasive safety issues; has limited public participation in decision making and power plant licensing; has failed to enforce safety standards or conduct adequate regulation investigations; and, finally, has maintained a fraternal relationship with the industry it was created to regulate, serving as its advocate rather than it adversary. The final chapter offers recommendations for agency improvement that must be met if the NRC is to fulfill its responsibility for safety first

Grinding the Antitesting Ax: More Bias than Evidence behind NRC Panel's Conclusions

Science.gov (United States)

Hanushek, Eric A.

2012-01-01

In all the acrimonious discussion surrounding No Child Left Behind Act of 2001 (NCLB), surprisingly little attention has been given to the actual impact of that legislation and other accountability systems on student performance. Now a reputable body, a committee set up by the National Research Council (NRC), the research arm of the National…

NRC concerns about steam generator tube U-bend failures

International Nuclear Information System (INIS)

Dillon, R.L.

1981-01-01

This paper concerns itself with genralized NRC regulatory policy regarding SGT failures and staff reports and opinions which may tend to influence the developing policy specific to U-bend failures. The most significant analysis at hand in predicting NRC policy on SGT U-bend failures is Marsh's Evaluation of Steam Generator Tube Rupture Events. Marsh sets out to describe and analyze the five steam generator tube ruptures that are known to NRC. All have occurred in the period 1975 to 1980

Reassessment of the NRC`s program for protecting allegers against retaliation

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

On July 6, 1993, the Nuclear Regulatory Commission`s (NRC`s) Executive Director for Operations established a review team to reassess the NRC`s program for protecting allegers against retaliation. The team evaluated the current system, and solicited comments from various NRC offices, other Federal agencies, licensees, former allegers, and the public. This report is subject to agency review. The report summarizes current processes and gives an overview of current problems. It discusses: (1) ways in which licensees can promote a quality-conscious work environment, in which all employees feel free to raise concerns without fear of retaliation; (2) ways to improve the NRC`s overall handling of allegations; (3) the NRC`s involvement in the Department of Labor process; (4) related NRC enforcement practices; and (5) methods other than investigation and enforcement that may be useful in treating allegations of potential or actual discrimination. Recommendations are given in each area.

Armenian nuclear power plant: US NRC assistance programme for seismic upgrade and safety analysis

International Nuclear Information System (INIS)

Simos, N.; Perkins, K.; Jo, J.; Carew, J.; Ramsey, J.

2003-01-01

This paper summarizes the U.S. Nuclear Regulatory Commission's (US NRC) technical support program activities associated with the Armenian Nuclear Power Plant (ANPP) safety upgrade. The US NRC program, integrated within the overall IAEA-led initiative for safety re-evaluation of the WWER plants, has as its main thrust the technical support to the Armenian Nuclear Regulatory Authority (ANRA) through close collaboration with the scientific staff at Brookhaven National Laboratory (BNL). Several major technical areas of support to ANRA form the basis of the NRC program. These include the seismic re-evaluation and upgrade of the ANPP, safety evaluation of critical systems, and the generation of the Safety Analysis Report (SAR). Specifically, the seismic re-evaluation of the ANPP is part of a broader activity that involves the re-assessment of the seismic hazard at the site, the identification of the Safe Shutdown Equipment at the plant and the evaluation of their seismic capacity, the detailed modeling and analysis of the critical facilities at ANPP, and the generation of the Floor Response Spectra (FRS). Based on the new spectra that incorporate all new findings (hazard, site soil, structure, etc.), the overall capacity of the main structures and the seismic capacity of the critical systems are being re-evaluated. In addition, analyses of critical safe shutdown systems and safe shutdown processes are being performed to ensure both the capabilities of the operating systems and the enhancement of safety due to system upgrades. At present, one of the principal goals of the US NRC's regulatory assistance activities with ANRA is enhancing ANRA's regulatory oversight of high-priority safety issues (both generic and plant-specific) associated with operation of the ANPP. As such, assisting ANRA in understanding and assessing plant-specific seismic and other safety issues associated with the ANPP is a high priority given the ANPP's being located in a seismically active area

Overview of the NRC performance monitoring program

International Nuclear Information System (INIS)

Jordan, E.L.

1987-01-01

In response to the accident at Three Mile Island, the NRC developed the Systematic Assessment of Licensee Performance (SALP) Program to aid in the identification of those licensees that were more likely than others to have safety problems and to provide a rational basis for allocation of inspection resources. The NRC also has an ongoing program of screening and evaluating operating reactor event reports on a daily basis for promptly identifying safety problems. Although the SALP and event report evaluation programs have been successful in identifying potential performance problems, a concern developed recently about the adequacy and timeliness of NRC programs to detect poor or declining performance. The performance indicator program as approved by the commission is in the implementation phase. The program is expected to undergo refinements as new indicators are developed and experience is gained in the use of indicators

NRC Regulatory Agenda quarterly report, July--September 1993

International Nuclear Information System (INIS)

1993-10-01

The NRC Regulator Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

The NRC activities concerning Boraflex use in spent-fuel storage racks

International Nuclear Information System (INIS)

Kopp, L.I.

1996-01-01

The U.S. Nuclear Regulatory Commission (NRC) has issued several generic communications to the nuclear industry identifying two issues with respect to using Boraflex in spent-fuel storage racks. The first issue related to gamma-radiation-induced shrinkage of Boraflex and the potential to develop tears or gaps in the material. This phenomenon is typically accounted for in criticality analyses of spent-fuel storage racks. The second issue concerned long-term Boraflex performance throughout the intended service life of the racks as a result of both gamma irradiation and exposure to the wet pool environment

NRC nuclear-plant-analyzer concept and status at INEL

International Nuclear Information System (INIS)

Aguilar, F.; Wagner, R.J.

1982-01-01

The Office of Research of the US NRC has proposed development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes how we of the INEL envision the nuclear-plant analyzer. The paper also describes a pilot RELAP5 plant-analyzer project completed during the past year and current work. A great deal of analysis is underway to determine nuclear-steam-system response. System transient analysis being so complex, there is the need to present analytical results in a way that interconnections among phenomena and all the nuances of the transient are apparent. There is the need for the analyst to dynamically control system calculations to simulate plant operation in order to perform what if studies as well as the need to perform system analysis within hours of a plant emergency to diagnose the state of the stricken plant and formulate recovery actions. The NRC-proposed nuclear-plant analyzer can meet these needs

NRC's license renewal regulations

International Nuclear Information System (INIS)

Akstulewicz, Francis

1991-01-01

In order to provide for the continuity of the current generation of nuclear power plant operating licenses and at the same time ensure the health and safety of the public, and the quality of the environment, the US Nuclear Regulatory Commission (NRC) established a goal of developing and issuing regulations and regulatory guidance for license renewal in the early 1990s. This paper will discuss some of those activities underway to achieve this goal. More specifically, this paper will discuss the Commission's regulatory philosophy for license renewal and the two major license renewal rule makings currently underway. The first is the development of a new Part 54 to address procedural and technical requirements for license renewal; the second is a revision to existing Part 51 to exclude environmental issues and impacts from consideration during the license renewal process. (author)

Staged licensing: An essential element of the NRC's revised regulations

International Nuclear Information System (INIS)

Echols, F.S.

1997-01-01

Over the past several years, Congress has directed the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC), and the Environmental Protection Agency (EPA) to abandon their efforts to assess an array of potential candidate geologic repository sites for the permanent disposal of spent nuclear reactor fuel and high level radioactive waste, to develop generally applicable requirements for licensing geologic repositories, and to develop generally applicable radiation protection standards for geologic repositories, and instead to focus their efforts to determine whether a single site located at Yucca Mountain, Nevada can be developed as a geologic repository which providing reasonable assurance that public health and safety and the environment will be adequately protected. If the Yucca Mountain site is found to be suitable for development as a geologic repository, then at each stage of development DOE will have to provide the NRC with progressively more detailed information regarding repository design and long-term performance. NRC regulations reflect the fact that it will not be until the repository has been operated for a number of years that the NRC will be able to make a final determination as to long-term repository performance. Nevertheless, the NRC will be able to allow DOE to construct and operate a repository, provided that the NRC believes that the documented results of existing studies, together with the anticipated results from continuing and future studies, will enable the NRC to make a final determination that it has reasonable assurance that the repository system's long-term performance will not cause undue risk to the public. Thus, in its efforts to revise its current regulations to assure that the technical criteria are specifically applicable to the Yucca Mountain site, the NRC should also make sure that it preserves and clarifies the concept of staged repository development

NRC regualtory agenda. Semiannual report, July 1997--December 1997

International Nuclear Information System (INIS)

1998-02-01

The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition

Initial experience with the NRC significance determination process

International Nuclear Information System (INIS)

Madison, A.L.

2001-01-01

The U.S. Nuclear Regulatory Commission (NRC) has revamped its inspection, assessment, and enforcement programs for commercial nuclear power plants. The new oversight process uses more objective, timely, and safety-significant criteria in assessing performance, while seeking to more effectively and efficiently regulate the industry. The NRC tested the new process at thirteen reactors at nine sites across the country on a pilot basis in 1999 to identify what things worked well and what improvements were called for before beginning Initial Implementation at all US nuclear power plants on April 2, 2000. After a year of experience has been gained with the new oversight process at all US plants, the NRC anticipates making further improvements based on this wider experience. (author)

Initial experience with the NRC significance determination process

Energy Technology Data Exchange (ETDEWEB)

Madison, A.L. [Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission (United States)

2001-07-01

The U.S. Nuclear Regulatory Commission (NRC) has revamped its inspection, assessment, and enforcement programs for commercial nuclear power plants. The new oversight process uses more objective, timely, and safety-significant criteria in assessing performance, while seeking to more effectively and efficiently regulate the industry. The NRC tested the new process at thirteen reactors at nine sites across the country on a pilot basis in 1999 to identify what things worked well and what improvements were called for before beginning Initial Implementation at all US nuclear power plants on April 2, 2000. After a year of experience has been gained with the new oversight process at all US plants, the NRC anticipates making further improvements based on this wider experience. (author)

Safeguards at NRC licensed facilities: Are we doing enough

International Nuclear Information System (INIS)

Asselstine, J.K.

1986-01-01

The Nuclear Regulatory Commission is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

10 CFR 2.1403 - Authority and role of the NRC staff.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of the NRC staff. 2.1403 Section 2.1403... ORDERS Expedited Proceedings with Oral Hearings § 2.1403 Authority and role of the NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings in its own...

NRC high-level radioactive waste research at CNWRA, July--December 1992

International Nuclear Information System (INIS)

Sagar, B.; Ababou, R.; Ahola, M.

1993-07-01

Progress from July 1 to December 31, 1992 on the nine NRC-sponsored research projects conducted at the Center for Nuclear Waste Regulatory Analyses is described. Ion-exchange experiments between clinoptilolite and aqueous solutions of Na + and Sr 2+ and three applications of reaction-path modeling are described in the Unsaturated Mass Transport (Geochemistry) project. Numerical simulation of a laboratory-scale non-isothermal two-phase flow is discussed in the Thermohydrology chapter. Methods for estimating rock joint roughness coefficient are the focus of the Seismic Rock Mechanics project for which the Tilt Test, Tse and Cruden's equations, and fractal-based equations were tested and found to be unsatisfactory. In the Integrated Waste Package Experiments chapter, investigations of pit initiation and repassivation potential for alloys 825 and C-22 and stainless steel 304L and 316L are described. Testing of the BIGFLOW computer code and visualization of fracture topology is the theme of the Stochastic Hydrology project. Preliminary analysis of field data from the Akrotiri site in Greece is developed in the Geochemical Analogs project. Mechanistic modeling of sorption using the MINTEQA2 code is investigated as part of the Sorption project. Adaptive gridding and ''modified equations'' methods for solving the flow and transport equations are described in the Performance Assessment chapter. Finally, the Volcanism chapter focuses on using nonhomogeneous Poisson processes for estimating probability of volcanic events at the potential repository site

NRC study of control room habitability

International Nuclear Information System (INIS)

Hayes, J.J. Jr.; Muller, D.R.; Gammill, W.P.

1985-01-01

Since 1980, the Advisory Committee on Reactor Safeguards (ACRS) has held several meetings with the NRC staff to discuss the subject of control room habitability. Several meetings between the ACRS and the staff have resulted in ACRS letters that express specific concerns, and the staff has provided responses in reports and meetings. In June of 1983, the NRC Executive Director for Operations directed the Offices of Nuclear Reactor Regulation and Inspection and Enforcement to develop a plan to handle the issues raised by the ACRS and to report to him specific proposed courses of action to respond to the ACRS's concerns. The NRC control room habitability working group has reviewed the subject in such areas as NRR review process, transformation of control room habitability designs to as-built systems, and determination of testing protocol. The group has determined that many of the ACRS concerns and recommendations are well founded, and has recommended actions to be taken to address these as well as other concerns which were raised independent of the ACRS. The review has revealed significant areas where the approach presently utilized in reviews should be altered

NRC TLD Direct Radiation Monitoring Network

International Nuclear Information System (INIS)

Struckmeyer, R.; McNamara, N.

1992-06-01

The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network is operated by the NRC in cooperation with participating states to provide continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. Ambient radiation levels result from naturally occurring radionuclides present in the soil, cosmic radiation constantly bombarding the earth from outer space, and the contribution, if any, from the monitored facilities and other man-made sources. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the first quarter of 1992. All radiation measurements are made using small, passive detectors called thermoluminescent dosimeters (TLDs), which provide a quantitative measurement of the radiation levels in the area in which they are placed. Each site is monitored by arranging approximately 40 to 50 TLD stations in two concentric rings extending to about five miles from the facility. All TLD stations are outside the site boundary of the facility

NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

Information to licensees regarding two NRC Inspection Manual sections on resolution of degraded and nonconforming conditions and on operability (Generic Letter 91-18)

International Nuclear Information System (INIS)

Partlow, J.G.

1992-01-01

The NRC staff has issued two sections to be included in Part 9900, Technical Guidance, of the NRC Inspection Manual. The first is, ''Resolution of Degraded and Nonconforming Conditions.'' The second is, ''Operable/Operability: Ensuring the Functional Capability of a System or Component.'' Copies of the additions to the NRC Inspection Manual are provided for information only. No specific licensee actions are required. The additions to the NRC Inspection Manual are based upon previously issued guidance. However, because of the complexity involved in operability determinations and the resolution of degraded and nonconforming conditions, there have been differences in application by NRC staff during past inspection activities. Thus, the purpose of publishing this guidance is to ensure consistency in application of this guidance by the NRC. Regional inspection personnel have been briefed on this guidance. The NRC will conduct further training on these topics to ensure uniform staff understanding

NRC regulatory agenda: Quarterly report, April-June 1987

International Nuclear Information System (INIS)

1987-07-01

This compilation summarizes significant enforcement actions that have been resolved during one quarterly period and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

SU-A-210-02: Medical Physics Opportunities at the NRC

International Nuclear Information System (INIS)

Abogunde, M.

2015-01-01

The purpose of this student annual meeting is to address topics that are becoming more relevant to medical physicists, but are not frequently addressed, especially for students and trainees just entering the field. The talk is divided into two parts: medical billing and regulations. Hsinshun Wu – Why should we learn radiation oncology billing? Many medical physicists do not like to be involved with medical billing or coding during their career. They believe billing is not their responsibility and sometimes they even refuse to participate in the billing process if given the chance. This presentation will talk about a physicist’s long career and share his own experience that knowing medical billing is not only important and necessary for every young medical physicist, but that good billing knowledge could provide a valuable contribution to his/her medical physics development. Learning Objectives: The audience will learn the basic definition of Current Procedural Terminology (CPT) codes performed in a Radiation Oncology Department. Understand the differences between hospital coding and physician-based or freestanding coding. Apply proper CPT coding for each Radiation Oncology procedure. Each procedure with its specific CPT code will be discussed in detail. The talk will focus on the process of care and use of actual workflow to understand each CPT code. Example coding of a typical Radiation Oncology procedure. Special procedure coding such as brachytherapy, proton therapy, radiosurgery, and SBRT. Maryann Abogunde – Medical physics opportunities at the Nuclear Regulatory Commission (NRC) The NRC’s responsibilities include the regulation of medical uses of byproduct (radioactive) materials and oversight of medical use end-users (licensees) through a combination of regulatory requirements, licensing, safety oversight including inspection and enforcement, operational experience evaluation, and regulatory support activities. This presentation will explore the

SU-A-210-02: Medical Physics Opportunities at the NRC

Energy Technology Data Exchange (ETDEWEB)

Abogunde, M. [U.S. Nuclear Regulatory Commission (United States)

2015-06-15

The purpose of this student annual meeting is to address topics that are becoming more relevant to medical physicists, but are not frequently addressed, especially for students and trainees just entering the field. The talk is divided into two parts: medical billing and regulations. Hsinshun Wu – Why should we learn radiation oncology billing? Many medical physicists do not like to be involved with medical billing or coding during their career. They believe billing is not their responsibility and sometimes they even refuse to participate in the billing process if given the chance. This presentation will talk about a physicist’s long career and share his own experience that knowing medical billing is not only important and necessary for every young medical physicist, but that good billing knowledge could provide a valuable contribution to his/her medical physics development. Learning Objectives: The audience will learn the basic definition of Current Procedural Terminology (CPT) codes performed in a Radiation Oncology Department. Understand the differences between hospital coding and physician-based or freestanding coding. Apply proper CPT coding for each Radiation Oncology procedure. Each procedure with its specific CPT code will be discussed in detail. The talk will focus on the process of care and use of actual workflow to understand each CPT code. Example coding of a typical Radiation Oncology procedure. Special procedure coding such as brachytherapy, proton therapy, radiosurgery, and SBRT. Maryann Abogunde – Medical physics opportunities at the Nuclear Regulatory Commission (NRC) The NRC’s responsibilities include the regulation of medical uses of byproduct (radioactive) materials and oversight of medical use end-users (licensees) through a combination of regulatory requirements, licensing, safety oversight including inspection and enforcement, operational experience evaluation, and regulatory support activities. This presentation will explore the

Human Factors Regulatory Research Program Plan, FY 1989--FY 1992

International Nuclear Information System (INIS)

Coffman, F.; Persensky, J.; Ryan, T.; Ramey-Smith, A.; Goodman, C.; Serig, D.; Trager, E; Nuclear Regulatory Commission, Washington, DC; Nuclear Regulatory Commission, Washington, DC; Nuclear Regulatory Commission, Washington, DC

1989-10-01

This report describes the currently ongoing (FY 1989) and planned (FY 1989-1992) Human Factors Regulatory Research Program in the NRC Office of Nuclear Regulatory Research (RES). Examples of the influence of human factors on nuclear safety are presented, and the role of personnel is discussed. Current regulatory issues associated with human factors in the nuclear system and the purpose of the research plan are provided. The report describes the research process applied to the human factors research issues and the program activities: Personnel Performance Measurement, Personnel Subsystem, Human-System Interface. Organization and Management, and Reliability Assessment. The research being conducted within each activity is summarized along with the objectives, background information, and expected regulatory products. Budget and personnel forecasts are provided along with a summary of contractors performing some of the ongoing research. Appendices contain a chronology of human factors research at NRC, a description of the research approach, an update on human factors programs and initiatives in RES and other NRC offices, and the integration among these programs. 46 refs., 5 tabs

NRC high-level radioactive waste program. Annual progress report: Fiscal Year 1996

International Nuclear Information System (INIS)

Sagar, B.

1997-01-01

This annual status report for fiscal year 1996 documents technical work performed on ten key technical issues (KTI) that are most important to performance of the proposed geologic repository at Yucca Mountain. This report has been prepared jointly by the staff of the Nuclear Regulatory Commission (NRC) Division of Waste Management and the Center for Nuclear Waste Regulatory Analyses. The programmatic aspects of restructuring the NRC repository program in terms of KTIs is discussed and a brief summary of work accomplished is provided. The other ten chapters provide a comprehensive summary of the work in each KTI. Discussions on probability of future volcanic activity and its consequences, impacts of structural deformation and seismicity, the nature of of the near-field environment and its effects on container life and source term, flow and transport including effects of thermal loading, aspects of repository design, estimates of system performance, and activities related to the U.S. Environmental Protection Agency standard are provided

NRC program of inspection and enforcement

International Nuclear Information System (INIS)

LeDoux, J.C.; Rehfuss, C.

1978-01-01

The Nuclear Regulatory Commission (NRC) regulates civilian uses of nuclear materials to ensure the protection of the public health and safety and the environment. The Office of Inspection and Enforcement (IE) develops and implements the inspection, investigation, and enforcement programs for the NRC. The IE conducts inspection programs for reactors under construction and in operation, nuclear industry vendors, fuel facilities and users of nuclear materials, and all aspects of the safeguarding of facilities and materials. Recently the IE began implementing a program that will place inspectors on site at nuclear power reactors and will provide for national appraisal of licensee performance and for an evaluation of the effectiveness of the inspection programs

Friction correction for model ship resistance and propulsion tests in ice at NRC's OCRE-RC

Directory of Open Access Journals (Sweden)

Michael Lau

2018-05-01

Full Text Available This paper documents the result of a preliminary analysis on the influence of hull-ice friction coefficient on model resistance and power predictions and their correlation to full-scale measurements. The study is based on previous model-scale/full-scale correlations performed on the National Research Council - Ocean, Coastal, and River Engineering Research Center's (NRC/OCRE-RC model test data. There are two objectives for the current study: (1 to validate NRC/OCRE-RC's modeling standards in regarding to its practice of specifying a CFC (Correlation Friction Coefficient of 0.05 for all its ship models; and (2 to develop a correction methodology for its resistance and propulsion predictions when the model is prepared with an ice friction coefficient slightly deviated from the CFC of 0.05. The mean CFC of 0.056 and 0.050 for perfect correlation as computed from the resistance and power analysis, respectively, have justified NRC/OCRE-RC's selection of 0.05 for the CFC of all its models. Furthermore, a procedure for minor friction corrections is developed. Keywords: Model test, Ice resistance, Power, Friction correction, Correlation friction coefficient

NRC perspective on alternative disposal methods

International Nuclear Information System (INIS)

Pittiglio, C.L.; Tokar, M.

1987-01-01

In this paper is discussed an NRC staff strategy for the development of technical criteria and procedures for the licensing of various alternatives for disposal of low-level radioactive waste. Steps taken by the staff to identify viable alternative disposal methods and to comply with the requirements of the Low-Level Radioactive Waste Policy Amendments Act (LLRWPAA) of 1985 are also discussed. The strategy proposed by the NRC staff is to focus efforts in FY 87 on alternative concepts that incorporate concrete materials with soil or rock cover (e.g., below ground vaults and earth-mounded concrete bunkers), which several State and State Compacts have identified as preferred disposal options. While the NRC staff believes that other options, such as above ground vaults and mined cavities, are workable and licensable, the staff also believes, for reasons addressed in the paper, that it is in the best interest of the industry and the public to encourage standardization and to focus limited resources on a manageable number of alternative options. Therefore, guidance on above ground vaults, which are susceptible to long-term materials degradation due to climatological effects, and mined cavities, which represent a significant departure from the current experience base for low-level radioactive waste disposal, will receive minimal attention. 6 references

NRC Support for the Kalinin (VVER) probabilistic risk assessment

International Nuclear Information System (INIS)

Bley, D.; Diamond, D.J.; Chu, T.L.; Azarm, A.; Pratt, W.T.; Johnson, D.; Szukiewicz, A.; Drouin, M.; El-Bassioni, A.; Su, T.M.

1998-01-01

The US Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation have been working together since 1994 to carry out a probabilistic risk assessment (PRA) of a VVER-1000 in the Russian Federation. This was a recognition by both parties that this technology has had a profound effect on the discipline of nuclear reactor safety in the West and that the technology should be transferred to others so that it can be applied to Soviet-designed plants. The NRC provided funds from the Agency for International Development and technical support primarily through Brookhaven National Laboratory and its subcontractors. The latter support was carried out through workshops, by documenting the methodology to be used in a set of guides, and through periodic review of the technical activity. The result of this effort to date includes a set of procedure guides, a draft final report on the Level 1 PRA for internal events (excluding internal fires and floods), and progress reports on the fire, flood, and seismic analysis. It is the authors belief that the type of assistance provided by the NRC has been instrumental in assuring a quality product and transferring important technology for use by regulators and operators of Soviet-designed reactors. After a thorough review, the report will be finalized, lessons learned will be applied in the regulatory and operational regimes in the Russian Federation, and consideration will be given to supporting a containment analysis in order to complete a simplified Level 2 PRA

Performance testing of dosimetry processors, status of NRC rulemaking for improved personnel dosimetry processing, and some beta dosimetry and instrumentation problems observed by NRC regional inspectors

International Nuclear Information System (INIS)

Dennis, N.A.; Kinneman, J.D.; Costello, F.M.; White, J.R.; Nimitz, R.L.

1983-01-01

Early dosimetry processor performance studies conducted between 1967 and 1979 by several different investigators indicated that a significant percentage of personnel dosimetry processors may not be performing with a reasonable degree of accuracy. Results of voluntary performance testing of US personnel dosimetry processors against the final Health Physics Society Standard, Criteria for Testing Personnel Dosimetry Performance by the University of Michigan for the Nuclear Regulatory Commission (NRC) will be summarized with emphasis on processor performance in radiation categories involving beta particles and beta particles and photon mixtures. The current status of the NRC's regulatory program for improved personnel dosimetry processing will be reviewed. The NRC is proposing amendments to its regulations, 10 CFR Part 20, that would require its licensees to utilize specified personnel dosimetry services from processors accredited by the National Voluntary Laboratory Accreditation Program of the National Bureau of Standards. Details of the development and schedule for implementation of the program will be highlighted. Finally, selected beta dosimetry and beta instrumentation problems observed by NRC Regional Staff during inspections of NRC licensed facilities will be discussed

NRC quarterly [status] report

International Nuclear Information System (INIS)

1987-01-01

This report covers the third quarter of calendar year 1987. The NRC licensing activity during the period of this report included the issuance of a full-power license for Beaver Valley 2 on August 14, 1987, and operating license restricted to five percent power for South Texas Unit 1 on August 21, 1987. Additional licensing delay for Shoreham is projected due to complex litigation. Also, licensing delay may occur for Comanche Peak Unit 1, because the duration of the hearing is uncertain. Although a license authorizing fuel loading and precriticality testing for Seabrook Unit 1 has been issued, there is a projected delay for low-power licensing. Full-power licensing for Seabrook Unit 1 will be delayed due to offsite emergency preparedness issues. The length of the delay is not known at this time. With the exception of Seabrook and Shoreham, regulatory delays in this report are not impacted by the schedules for resolving off-site emergency preparedness issues

NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapters 2--13, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

Insights gained from NRC research investigations at the Maxey Flats LLW SLB facility

International Nuclear Information System (INIS)

O'Donnell, E.

1983-01-01

The NRC funded program of research at Maxey Flats was done to assist an Agreement State in assessing the performance of the site. That program has yielded both site specific insights and generic insights which are likely to be useful in licensing future sites. They are as follows: Site Specific Insights: (1) The principal pathway of water entry into burial trenches at Maxey Flats is through the trench caps. (2) Sampling of vegetation, soils, and streams adjoining the site indicates that the small but measureable amounts of radionuclides found offsite were from surface runoff or the site evaporator. (3) There is limited onsite subsurface movement of radionuclides where open fractures intersect burial trenches. Generic Insights: (1) Tritium in the plant transpiration stream appears useful for mapping trench boundaries. (2) Trees offer a promising means of monitoring subsurface radionuclide movement in fractured rocks of low permeability. (3) Complexing with EDTA appears to be a potentially important mechanism that increases mobility of such radionuclides as Co-60, Pu-238, Am-241, and Sr-90. (4) Changes in soil solution chemistry encountered as leachate moves from trenches generally reduce the solubility of migrating radionuclides. (5) Agronomic management techniques appear promising as a means to control deep water percolation through waste burial trench caps. 18 references

Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Packages

International Nuclear Information System (INIS)

1993-10-01

This directory contains a Report of NRC Approved Packages (Volume 1). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Congress, NRC mull utility access to FBI criminal files

International Nuclear Information System (INIS)

Ultroska, D.

1984-01-01

Experiences at Alabama Power Company and other nuclear utilities have promped a request for institutionalizing security checks of personnel in order to eliminated convicted criminals and drug users. The Nuclear Regulatory Commission (NRC), which could provide FBI criminal history information by submitting fingerprints, does not do so, and would require new legislation to take on that duty. Believing that current malevolent employees can be managed with existing procedures, NRC allows criminal background checks only on prospective employees in order to avoid a negative social impact on personnel. Legislation to transfer criminal histories to nuclear facilities is now pending, and NRC is leaning toward a request for full disclosure, partly because of terrorist threats and partly to save manpower time and costs in reviewing case histories

NRC as referee (reactor licensing following the Three Mile Island accident)

International Nuclear Information System (INIS)

Eisenhut, D.G.

1984-01-01

In this article, the NRC's licensing director reports on the progress made by US utilities in complying with the key regulations stemming from the Three Mile Island accident. Over 130 items must be improved at more than 65 reactors. The actions taken by France in response to its own analysis of the accident are discussed. New NRC requirements with regard to operational safety, design, and emergency-response capability are outlined. Nearly all the training, or software, items in Nureg-0737 (''Clarification of TMI Action Plan Requirements'') and more than half of the mechanical, or hardware, items have been completed at plants with operating reactors. The Committee to Review Generic Requirements was created to develop means for controlling the number and nature of NRC requirements placed on licensees. Probabilistic risk-assessment techniques were not widely used by the NRC until after the Three Mile Island accident. The NRC has directed licensees and applicants for operating licenses to conduct control-room design reviews to identify and correct human-engineering discrepancies. Includes 2 tables

Application of PLUTO Test Facility for U. S. NRC Licensing of a Fuel Assembly

Energy Technology Data Exchange (ETDEWEB)

Oh, Dongseok; Shin, Changhwan; Lee, Kanghee; Kang, Heungseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

The fuel assembly of the PLUS-7 loaded in the APR-1400 follows the same schedule. Meanwhile, In July 1998, the U.S. NRC adopted a research plan to address the effects of high burnup from a Loss of Coolant Accident (LOCA). From these programs, several important technical findings for rule revision were obtained. Based on the technical findings, the U. S. NRC has amended the 10 CFR 50.46 which will be proclaimed sooner or later. Through the amendment, a LOCA analysis on the fuel assembly has to show the safety at both a fresh and End of Life (EOL) state. The U. S. NRC has already required EOL effects on seismic/LOCA performance for a fuel assembly since 1998. To obtain U.S NRC licensing of a fuel assembly, based on the amendment of 10CFR50.46, a LOCA analysis of the fuel assembly has to show safety both fresh and EOL states. The proper damping factor of the fuel assembly measured at the hydraulic test loop for a dynamic model in a LOCA and a seismic analysis code are at least required. In this paper, we have examined the damping technologies and compared the test facility of PLUTO with others in terms of performance. PLUTO has a better performance on the operating conditions than any others.

NRC Response to an Act or Threat of Terrorism at an NRC-Licensed Facility

International Nuclear Information System (INIS)

Frank Congel

2000-01-01

The mandated response to a threat or act of terrorism at a U.S. Nuclear Regulatory Commission (NRC)-licensed facility was examined through a tabletop exercise in May 2000 and a limited field exercise in August 2000. This paper describes some of the new issues addressed and lessons learned from those exercises

NRC regulatory uses of PSA

International Nuclear Information System (INIS)

Murley, T.E.

1991-01-01

The publication in 1975 of WASH-1400, with its new probabilistic safety assessment (PSA) methodology, had the effect of presenting a pair of eyeglasses to a man with poor eyesight. Suddenly, it gave us a view of nuclear safety with a new clarity, and it allowed us to sort out the important safety issues from the unimportant. In the intervening years, PSA insights have permeated the fabric of nearly all our safety judgments. This acceptance can be seen from the following list of broad areas where the Nuclear Regulatory Commission (NRC) staff uses PSA insights and methodology: evaluating the safety significance of operating events and recommending safety improvements where warranted; requesting licensees to systematically look for design vulnerabilities in each operating reactor; evaluating the safety significance of design weaknesses or non-compliances when judging the time frame for necessary improvements; conducting sensitivity analyses to judge where safety improvements are most effective; assessing the relative safety benefits of design features for future reactors. In judging where PSA methodology can be improved to give better safety insights, it is believed that the following areas need more attention: better modeling of cognitive errors; more comprehensive modeling of accident sequences initiated from conditions other than full power; more comprehensive modeling of inter-system loss of coolant accident (ISLOCA) sequences. Although PSA is widely used in the staff's regulatory activities, the NRC deliberately chooses not to include probabilistic prescriptions in regulations or guidance documents. The staff finds the bottom line risk estimates to be one of the least reliable products of a PSA. The reason for this view is that PSA cannot adequately address cognitive errors nor assess the effects of a pervasive poor safety attitude

NRC licensing criteria for portable radwaste systems

International Nuclear Information System (INIS)

Hayes, J.J. Jr.

1983-01-01

The shortcomings of various components of the liquid and solid radwaste systems at nuclear power reactors has resulted in the contracting of the functions performed by these systems to various contractors who utilize portable equipment. In addition, some streams, for which treatment was not originally anticipated, have been processed by portable equipment. The NRC criteria applicable to portable liquid and solid radwaste systems is presented along with discussion on what is required to provide an adequate 10 CFR Part 50.59 review for those situations where changes are made to an existing system. The criteria the NRC is considering for facilities which may intend to utilize portable incinerators is also presented

Estimated incremental costs for NRC licensees to implement the US/IAEA safeguards agreement

International Nuclear Information System (INIS)

Clark, R.G.; Brouns, R.J.; Chockie, A.D.; Davenport, L.C.; Merrill, J.A.

1979-01-01

A study was recently completed for the US Nuclear Regulatory Commision (NRC) by the Pacific Northwest Laboratory (PNL) to identify the incremental cost of implementing the US/IAEA safeguards treaty agreement to eligible NRC licensees. Sources for the study were cost estimates from several licensees who will be affected by the agreement and cost analyses by PNL staff. The initial cost to all eligible licensees to implement the agreement is estimated by PNL to range from $1.9 to $7.2 million. The annual cost to these same licensees for the required accounting and reporting activities is estimated at $0.5 to $1.5 million. Annual inspection costs to the industry for the limited IAEA inspection being assumed is estimated at $80,000 to $160,000

NRC/FEMA operational response procedures for response to a commercial nuclear reactor accident

International Nuclear Information System (INIS)

1983-11-01

Procedures have been developed by the US Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) which provide the response teams of both agencies with the steps to be taken in responding to an emergency at a commercial nuclear power plant. The emphasis of these procedures is mainly on the interface between NRC and FEMA at their respective Headquarters and Regional Offices and at the various sites at which such an emergency could occur. Detailed procedures are presented that cover for both agencies, notification schemes and manner of activation, organizations at Headquaters and the site, interface procedures, coordination of onsite and offsite operations, the role of the Senior FEMA Official, and the cooperative efforts of each agency's public information staff

Regulatory decision with EPA/NRC/DOE/State Session (Panel)

Energy Technology Data Exchange (ETDEWEB)

O`Donnell, E.

1995-12-31

This panel will cover the Nuclear Regulatory Commission`s (NRC) proposed radiation limits in the Branch Technical Position on Low-Level Radioactive Waste Performance Assessment and the Environmental Protection Agency`s (EPA) draft regulation in Part 193. Representatives from NRC and EPA will discuss the inconsistencies in these two regulations. DOE and state representatives will discuss their perspective on how these regulations will affect low-level radioactive waste performance assessments.

Recommendations for NRC policy on shift scheduling and overtime at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lewis, P.M.

1985-07-01

This report contains the Pacific Northwest Laboratory's (PNL's) recommendations to the US Nuclear Regulatory Commission (NRC) for an NRC policy on shift scheduling and hours of work (including overtime) for control room operators and other safety-related personnel in nuclear power plants. First, it is recommended that NRC make three additions to its present policy on overtime: (1) limit personnel to 112 hours of work in a 14-day period, 192 hours in 28 days, and 2260 hours in one year; exceeding these limits would require plant manager approval; (2) add a requirement that licensees obtain approval from NRC if plant personnel are expected to exceed 72 hours of work in a 7-day period, 132 hours in 14 days, 228 hours in 28 days, and 2300 hours in one year; and (3) make the policy a requirement, rather than a nonbinding recommendation. Second, it is recommended that licensees be required to obtain NRC approval to adopt a routine 12-hour/day shift schedule. Third, it is recommended that NRC add several nonbinding recommendations concerning routine 8-hour/day schedules. Finally, because additional data can strengthen the basis for future NRC policy on overtime, five methods are suggested for collecting data on overtime and its effects. 44 refs., 10 tabs.

Recommendations for NRC policy on shift scheduling and overtime at nuclear power plants

International Nuclear Information System (INIS)

Lewis, P.M.

1985-07-01

This report contains the Pacific Northwest Laboratory's (PNL's) recommendations to the US Nuclear Regulatory Commission (NRC) for an NRC policy on shift scheduling and hours of work (including overtime) for control room operators and other safety-related personnel in nuclear power plants. First, it is recommended that NRC make three additions to its present policy on overtime: (1) limit personnel to 112 hours of work in a 14-day period, 192 hours in 28 days, and 2260 hours in one year; exceeding these limits would require plant manager approval; (2) add a requirement that licensees obtain approval from NRC if plant personnel are expected to exceed 72 hours of work in a 7-day period, 132 hours in 14 days, 228 hours in 28 days, and 2300 hours in one year; and (3) make the policy a requirement, rather than a nonbinding recommendation. Second, it is recommended that licensees be required to obtain NRC approval to adopt a routine 12-hour/day shift schedule. Third, it is recommended that NRC add several nonbinding recommendations concerning routine 8-hour/day schedules. Finally, because additional data can strengthen the basis for future NRC policy on overtime, five methods are suggested for collecting data on overtime and its effects. 44 refs., 10 tabs

NRC regulatory agenda. Seminnual progress report, January 1996--June 1996

International Nuclear Information System (INIS)

1996-08-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rule making which have been received by the Commission and are pending disposition by the Commission. The regulatory Agenda is updated and issued semiannually

Transition from Consultation to Monitoring-NRC's Increasingly Focused Review of Factors Important to F-Area Tank Farm Facility Performance - 13153

Energy Technology Data Exchange (ETDEWEB)

Barr, Cynthia; Grossman, Christopher; Alexander, George; Parks, Leah; Fuhrmann, Mark; Shaffner, James; McKenney, Christepher [U.S. NRC, Rockville, MD (United States); Pabalan, Roberto; Pickett, David [Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, TX (United States); Dinwiddie, Cynthia [Southwest Research Institute, San Antonio, TX (United States)

2013-07-01

In consultation with the NRC, DOE issued a waste determination for the F-Area Tank Farm (FTF) facility in March 2012. The FTF consists of 22 underground tanks, each 2.8 to 4.9 million liters in capacity, used to store liquid high-level waste generated as a result of spent fuel reprocessing. The waste determination concluded stabilized waste residuals and associated tanks and auxiliary components at the time of closure are not high-level and can be disposed of as LLW. Prior to issuance of the final waste determination, during the consultation phase, NRC staff reviewed and provided comments on DOE's revision 0 and revision 1 FTF PAs that supported the waste determination and produced a technical evaluation report documenting the results of its multi-year review in October 2011. Following issuance of the waste determination, NRC began to monitor DOE disposal actions to assess compliance with the performance objectives in 10 CFR Part 61, Subpart C. To facilitate its monitoring responsibilities, NRC developed a plan to monitor DOE disposal actions. NRC staff was challenged in developing a focused monitoring plan to ensure limited resources are spent in the most cost-effective manner practical. To address this challenge, NRC prioritized monitoring areas and factors in terms of risk significance and timing. This prioritization was informed by NRC staff's review of DOE's PA documentation, independent probabilistic modeling conducted by NRC staff, and NRC-sponsored research conducted by the Center for Nuclear Waste Regulatory Analyses in San Antonio, TX. (authors)

NRC [Nuclear Regulatory Commission] TLD [thermoluminescent dosimeter] direct radiation monitoring network

International Nuclear Information System (INIS)

Struckmeyer, R.; McNamara, N.

1989-09-01

This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the second quarter of 1989

NRC TLD direct radiation monitoring network: Progress report, April--June 1988

International Nuclear Information System (INIS)

Struckmeyer, R.; McNamara, N.

1988-09-01

This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the second quarter of 1988

nRC: non-coding RNA Classifier based on structural features.

Science.gov (United States)

Fiannaca, Antonino; La Rosa, Massimo; La Paglia, Laura; Rizzo, Riccardo; Urso, Alfonso

2017-01-01

Non-coding RNA (ncRNA) are small non-coding sequences involved in gene expression regulation of many biological processes and diseases. The recent discovery of a large set of different ncRNAs with biologically relevant roles has opened the way to develop methods able to discriminate between the different ncRNA classes. Moreover, the lack of knowledge about the complete mechanisms in regulative processes, together with the development of high-throughput technologies, has required the help of bioinformatics tools in addressing biologists and clinicians with a deeper comprehension of the functional roles of ncRNAs. In this work, we introduce a new ncRNA classification tool, nRC (non-coding RNA Classifier). Our approach is based on features extraction from the ncRNA secondary structure together with a supervised classification algorithm implementing a deep learning architecture based on convolutional neural networks. We tested our approach for the classification of 13 different ncRNA classes. We obtained classification scores, using the most common statistical measures. In particular, we reach an accuracy and sensitivity score of about 74%. The proposed method outperforms other similar classification methods based on secondary structure features and machine learning algorithms, including the RNAcon tool that, to date, is the reference classifier. nRC tool is freely available as a docker image at https://hub.docker.com/r/tblab/nrc/. The source code of nRC tool is also available at https://github.com/IcarPA-TBlab/nrc.

Berkeley Lab Pilot on External Regulation of DOE National Laboratories by the U.S. NRC

International Nuclear Information System (INIS)

Zeman, Gary H.

1999-01-01

The US Department of Energy and the US Nuclear Regulatory Commission entered into an agreement in November 1997 to pursue external regulation of radiation safety at DOE national laboratories through a Pilot Program of simulated regulation at 6-10 sites over a 2 year period. The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab), the oldest of the DOE national laboratories, volunteered and was selected as the first Pilot site. Based on the similarities and linkages between Berkeley Lab and nearby university research laboratories, Berkeley Lab seemed a good candidate for external regulation and a good first step in familiarizing NRC with the technical and institutional issues involved in regulating laboratories in the DOE complex. NRC and DOE team members visited Berkeley Lab on four occasions between October 1997 and January 1998 to carry out the Pilot. The first step was to develop a detailed Work Plan, then to carry out both a technical review of the radiation safety program and an examination of policy and regulatory issues. The Pilot included a public meeting held in Oakland, CA in December 1997. The Pilot concluded with NRC's assessment that Berkeley Lab has a radiation protection program adequate to protect workers, the public and the environment, and that it is ready to be licensed by the NRC with minor programmatic exceptions. A draft final report of the Pilot was prepared and circulated for comment as a NUREG document (dated May 7, 1998). The report's recommendations include extending NRC regulatory authority to cover all ionizing radiation sources (including accelerators, x-ray units, NARM) at Berkeley Lab. Questions remaining to be resolved include: who should be the licensee (DOE, the Lab, or both)?; dealing with legacy issues and NRC D and D requirements; minimizing dual oversight; quantifying value added in terms of cost savings, enhanced safety, and improved public perception; extrapolating results to other national laboratories; and

Directory of certificates of compliance for radioactive materials packages. Volume 1, Revision 17: Report of NRC approved packages

International Nuclear Information System (INIS)

1994-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Do recent data from the Seychelles Islands alter the conclusions of the NRC Report on the toxicological effects of methylmercury?

Directory of Open Access Journals (Sweden)

Jacobson Joseph L

2004-01-01

Full Text Available Abstract In 2000, the National Research Council (NRC, an arm of the National Academy of Sciences, released a report entitled, "Toxicological Effects of Methylmercury." The overall conclusion of that report was that, at levels of exposure in some fish- and marine mammal-consuming communities (including those in the Faroe Islands and New Zealand, subtle but significant adverse effects on neuropsychological development were occurring as a result of in utero exposure. Since the release of that report, there has been continuing discussion of the public health relevance of current levels of exposure to Methylmercury. Much of this discussion has been linked to the release of the most recent longitudinal update of the Seychelles Island study. It has recently been posited that these findings supercede those of the NRC committee, and that based on the Seychelles findings, there is little or no risk of adverse neurodevelopmental effects at current levels of exposure. In this commentary, members of the NRC committee address the conclusions from the NRC report in light of the recent Seychelles data. We conclude that no evidence has emerged since the publication of the NRC report that alters the findings of that report.

Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1978-03-01

Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase future decommissioning needs, the NRC staff began an in-depth review and re-evaluation of NRC's regulatory approach to decommissioning in 1975. Major technical studies on decommissioning have been initiated at Battelle Pacific Northwest Laboratory in order to provide a firm information base on the engineering methodology, radiation risks, and estimated costs of decommissioning light water reactors and associated fuel cycle facilities. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. The report sets forth in detail the NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

48 CFR 2009.100 - NRC policy.

Science.gov (United States)

2010-10-01

... noncompetitive award of contracts to organizations where former NRC employees have dominant management interests...) Contracts awarded noncompetitively under the Small Business Administration's 8(a) Program; (2) Individual... consulting with the Executive Director for Operations. This is in addition to any justification and approvals...

Typical NRC inspection procedures for model plant

International Nuclear Information System (INIS)

Blaylock, J.

1984-01-01

A summary of NRC inspection procedures for a model LEU fuel fabrication plant is presented. Procedures and methods for combining inventory data, seals, measurement techniques, and statistical analysis are emphasized

Directory of certificates of compliance for radioactive materials packages; Summary Report of NRC Approved Packages

International Nuclear Information System (INIS)

1980-12-01

This directory contains a Summary Report of NRC approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, and index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material using these packagings must be in accordance with the provisions of 49 CFR 173.393a and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them--that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

NRC proposes changes to nuke decommissioning funding rules

International Nuclear Information System (INIS)

Anon.

1993-01-01

The Nuclear Regulatory Commission (NRC) has proposed to amend its regulations to allow self-guarantee as a means of assuring adequate funding for nuclear plant decommissioning. It acted in response to a rulemaking petition filed by General Electric Co. and Westinghouse Electric Corp. The proposal would allow self-guarantees if certain conditions are met: Tangible net worth of at least $1 billion; Tangible net worth at least 10 times the present decommissioning cost estimate for all activities the utility is responsible for as a self-guaranteeing licensee and as parent guarantor; Domestic assets amounting to at least 90 percent of total assets or at least 10 times the present decommissioning cost estimate; A credit rating for the utility's most recent bond issuance of AAA, AA, or A (Standard ampersand Poor's), or Aaa, Aa, or A (Moody's). Additional requirements include that the utility licensee must have at least one class of equity securities registered under the Securities Exchange Act of 1934, and that an independent auditor must verify that the utility met the financial test. A utility also would be responsible for reporting any change in circumstances affecting the criteria used to meet the financial test, and would be responsible for meeting that test within 90 days of each financial year. The NRC will accept written comments until March 29, 1993

Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

Energy Technology Data Exchange (ETDEWEB)

Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2013-10-15

In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed.

Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

International Nuclear Information System (INIS)

Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki

2013-01-01

In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed

Safeguards Summary Event List (SSEL), pre-NRC through December 31, 1989

International Nuclear Information System (INIS)

1992-07-01

The Safeguards Summary Event List (SSEL), Vol. 1, provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC) which occurred and were reported from pre-NRC through December 31, 1989. Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

Status of U. S. NRC Actions for the Events of Fukushima Dacha NPP

International Nuclear Information System (INIS)

Kim, Donghak; Lee, Jaeyong; Kim, Myungki

2013-01-01

In this study, status of U. S. NRC actions for the events of Fukushima is studied by reviewing commission papers, orders, request for information (RFI), Interim Staff Guidance (ISG) issued by NRC, etc. In order to acquire design certification of the APR1400, status of U. S. NRC actions for the events of Fukushima Dacha NTT is reviewed. The NRC has determined and conducted the 38 recommendations for action including 31 NTTF recommendations and seven additional recommendations. The recommendations are divided into Tier 1, Tier 2 and Tier 3. Tier 1 and Tier 2 recommendations are implemented by three Orders, one request for information and two rule makings. To comply with three orders and one request for information, the NRC issued six ISGs and NEI issued three technical reports. The final rule on strengthening and integrating onsite emergency response capabilities will be issued in February 2016. Station blackout mitigating strategies rulemaking on SBO mitigation capability and on spent fuel pool instrumentation and makeup capability will proceed

Recent developments in NRC guidelines for atmosphere cleanup systems

International Nuclear Information System (INIS)

Bellamy, R.R.

1976-01-01

The Nuclear Regulatory Commission (NRC) maintains the policy of updating when necessary, its published guidance for the design of engineered safety feature (ESF) and normal ventilation systems. The guidance is disseminated by means of issuing new, or revisions to, existing Regulatory Guides, Standard Review Plans, Branch Technical Positions and Technical Specifications. A revised Regulatory Guide, new Technical Specifications and new Standard Review Plans with Branch Technical Positions for atmosphere cleanup systems are discussed. Regulatory Guide 1.52, ''Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants,'' was issued in July 1973. The major comments received from the nuclear industry since the guide was issued, NRC's experience in implementing the guide in recent license applications, status of operating plants in meeting the guidelines and NRC's continuing assessment of operating data and laboratory tests to assure that the guide reflects the latest technology are discussed

New security measures are proposed for N-plants: Insider Rule package is issued by NRC

International Nuclear Information System (INIS)

Anon.

1984-01-01

New rules proposed by the Nuclear Regulatory Commission (NRC) will require background investigations and psychological assessments of new job candidates and continual monitoring of the behavior of all power plant workers with access to sensitive areas. Licensees will have to submit an ''access authorization'' program for approval describing how they will conduct these security activities. The employee checks will go back five years to examine credit, educational, and criminal histories. Implementation of the rules could involve the Edison Electric Institute as an intermediary to funnel criminal checks from the Justice Department and FBI. The NRC is also considering a clarification of areas designated as ''vital'' because current designations may be too strict

Web-Based Training on Reviewing Dose Modeling Aspects of NRC Decommissioning and License Termination Plans

International Nuclear Information System (INIS)

LePoire, D.; Cheng, J.J.; Kamboj, S.; Arnish, J.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

2008-01-01

related to training, developing, and transferring knowledge to NRC staff on how to review dose-modeling portions of licensee-submitted DPs and LTPs. This project identified specific cases and examples, created easily updateable educational modules, represented material in an engaging format through animations, video, and graphics, and distributed information on how to perform these reviews in an accessible, web-based format. WBT promotes consistency in reviews and has the advantage of being able to be used as a resource to staff at any time. The WBT will provide reviewers with knowledge needed to perform risk-informed analyses (e.g., information related to development of realistic scenarios and use of probabilistic analysis). WBT on review of LTP or DP dose modeling will promote staff development, efficiency, and effectiveness in performing risk-informed, performance-based reviews of decommissioning activities at NRC-licensed facilities. One of the key advantages of this type of web-based training is that it can be loaded on-demand and can be reused indefinitely. In addition to the benefits of on-demand training, the modules can also be used for reference. The presentations are hosted on a web server that can be accessed by registered users at any time. Staff can return to a particular module to review the material long after they have completed the course

76 FR 48919 - NRC Enforcement Policy

Science.gov (United States)

2011-08-09

.... In all such cases when a licensee determines that an unplanned change during construction associated..., States, members of the public, and the regulated industry (i.e., reactor and materials licensees, vendors, and contractors), on construction-related topics addressed in this notice that the NRC staff is...

Pilot program: NRC severe reactor accident incident response training manual: US Nuclear Regulatory Commission response

International Nuclear Information System (INIS)

Sakenas, C.A.; McKenna, T.J.; Perkins, K.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

1987-02-01

This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. US Nuclear Regulatory Commission Response is the fifth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes NRC response modes, organizations, and official positions; roles of other federal agencies are also described briefly. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

NCR Research activities

International Nuclear Information System (INIS)

Beltracchi, L.

1994-01-01

This paper identifies and describes safety issues related to the design, development, and qualification of reliable digital computer systems for nuclear power plants. It also describes the U.S. Nuclear Regulatory Commission's research program on these issues. The paper discusses an evaluation of the initial standards for hard-wired based safety systems. The lessons learned in developing these standards provides guidance in the design and use of digital technology in nuclear power plants. Also, this evaluation discusses how the content of the standards should lead to a framework of design criteria and the related acceptance criteria that can be used for computer-based safety systems. The opinions and viewpoints expressed herein are the author's personal ones and they do not necessarily reflect the criteria, requirements, and guidelines of the U.S. Nuclear Regulatory Commission (NRC)

Presentation on NRC Regulatory Positions and guidelines

International Nuclear Information System (INIS)

Russell, W.T.

1994-01-01

The NRC staff recognizes the potential for enhanced safety and reliability that digital systems bring to the nuclear industry. The staff also recognizes the challenges to safety that are unique to digital systems implementation

NRC Information No. 90-01: Importance of proper response to self-identified violations by licensees

International Nuclear Information System (INIS)

Cunningham, R.E.

1992-01-01

NRC expects a high standard of compliance by its licensees and requires that licensees provide NRC accurate and complete information and that required records will also be complete and accurate in all material respects. Licensees should be aware of the importance placed by NRC on licensee programs for self detection, correction and reporting of violations or errors related to regulatory requirements. The General Statement of Policy and Procedures for NRC Enforcement Actions in Appendix C to 10 CFR Part 2 underscores the importance of licensees responding promptly and properly to self-identified violations in two ways. It is suggested that when a licensee identifies a violation involving an NRC-required record, the licensee should make a dated notation indicating identification, either on the record itself or other appropriate documentation retrievable for NRC review. The record with the self-identified violation noted should not be altered in any way to mask the correction. The licensee should determine the cause of the violation, correct the root cause of the violation, and document such findings in an appropriate manner. Licensees should also assure that if a report of the violation is required, the report is submitted to NRC in a timely manner. These actions will be considered by NRC in making any enforcement decision, and generally lead to lesser or no civil penalty

Abstracts: NRC Waste Management Program reports

Energy Technology Data Exchange (ETDEWEB)

Heckman, R.A.; Minichino, C.

1979-11-01

This document consists of abstracts of all reports published by the Nuclear Regulatory Commission (NRC) Waste Management Program at Lawrence Livermore Laboratory (LLL). It will be updated at regular intervals. Reports are arranged in numerical order, within each category. Unless otherwise specified, authors are LLL scientists and engineers.

Abstracts: NRC Waste Management Program reports

International Nuclear Information System (INIS)

Heckman, R.A.; Minichino, C.

1979-11-01

This document consists of abstracts of all reports published by the Nuclear Regulatory Commission (NRC) Waste Management Program at Lawrence Livermore Laboratory (LLL). It will be updated at regular intervals. Reports are arranged in numerical order, within each category. Unless otherwise specified, authors are LLL scientists and engineers

NRC/FEMA operational response procedures for response to a commercial nuclear reactor accident. Revision 1

International Nuclear Information System (INIS)

1985-02-01

Procedures have been developed by the US Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) which provide the response teams of both agencies with the steps to be taken in responding to an emergency at a commercial nuclear power plant. The emphasis of these procedures is mainly on the interface between NRC and FEMA at their respective Headquarters and Regional Offices and at the various sites at which such an emergency could occur. Detailed procedures are presented that cover for both agencies, notification schemes and manner of activation, organizations at Headquarters and the site, interface procedures, coordination of onsite and offsite operations, the role of the Senior FEMA Official, and the cooperative efforts of each agency's public information staff

NRC regulatory agenda: Semiannual report, January--June 1997. Volume 16, Number 1

International Nuclear Information System (INIS)

1997-08-01

The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition. The agenda consists of two sections that have been updated through June 30, 1997. Section 1, ''Rules,'' includes (A) rules on which final action has been taken since December 31, 1996, the closing date of the last NRC Regulatory Agenda; (B) rules published previously as proposed rules on which the Commission has not taken final action; (C) rules published as advance notices of proposed rulemaking for which neither a proposed nor final rule has been issued; and (D) unpublished rules on which the NRC expects to take action. Section 2, ''Petitions for Rulemaking,'' includes (A) petitions denied or incorporated into final rules since December 31, 1996; (B) petitions incorporated into proposed rules; and (C) petitions pending staff review

NRC regulatory agenda: Semiannual report, January--June 1995. Volume 14, Number 1

International Nuclear Information System (INIS)

1995-09-01

The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition. The agenda consists of two sections that have been updated through June 30, 1995. Section 1, ''Rules,'' includes (A) rules on which final action has been taken since December 30, 1994, the closing date of the last NRC Regulatory Agenda; (B) rules published previously as proposed rules on which the Commission has not taken final action; (C) rules published as advance notices of proposed rulemaking for which neither a proposed nor final rule has been issued; and (D) unpublished rules on which the NRC expects to take action. Section 2, ''Petitions for Rulemaking,'' includes (A) petitions denied or incorporated into final rules since December 30, 1994; (B) petitions incorporated into proposed rules; (C) petitions pending staff review, and (D) petitions with deferred action

NRC TLD Direct Radiation Monitoring Network. Progress report, January-June 1981

International Nuclear Information System (INIS)

1982-04-01

This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of 55 NRC-licensed facility sites throughout the country for the first half of 1981. The program objectives, scope, and methodology are given. The TLD system, dosimeter location, data processing scheme, and quality assurance program are outlined

Amalgamation of performance indicators to support NRC senior management reviews

International Nuclear Information System (INIS)

Wreathall, J.; Schurman, D.; Modarres, M.; Mosleh, A.; Anderson, N.; Reason, J.

1991-01-01

The purpose of this project is to develop a methodology for amalgamating performance indicators to provide an overall perspective on plant safety, as one input to Nuclear Regulatory Commission's (NRC) senior management reviews of plant safety. These reviews are used to adjust the level of oversight by NRC. Work completed to date includes the development of frameworks for relating indicator measures to safety, a classification scheme for performance indicators, and a mapping process to portray indicators in the frameworks

76 FR 10072 - Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX, Adequacy of Station...

Science.gov (United States)

2011-02-23

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0013] Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX, Adequacy of Station Electric Distribution System Voltages; Reopening of... (NRC's) Draft Regulatory Issue Summary 2011-XX, Adequacy of Station Electric Distribution System...

The use of U.S. NRC licensing practices for VVERs

International Nuclear Information System (INIS)

Popp, D.M.

2000-01-01

The licensing process for the upgraded Temelin I and C and Fuel designs were enhanced with the introduction of U.S. Nuclear Regulatory Commission, NRC practices. Specifically, the use of the NRC Regulatory Guide 1.70, 'Standard Format and Content Guide for Safety Analyses Reports' and NRC NUREG 0800, 'Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants', were beneficial in the development and review of Temelin licensing documentation. These standards have been used for the preparation and review of Safety Analysis Reports in the United States and also in a large number of licensing applications around the world. Both Regulatory Guide 1.70 and NUREG 0800 were developed to provide a predictable and structured approach to licensing. This paper discusses this approach and identifies the benefits to designers, writers of licensing documentation and reviewers of licensing documents. (author)

NRC Information No. 88-12: Overgreasing of electric motor bearings

International Nuclear Information System (INIS)

Rossi, C.E.

1992-01-01

NRC personnel observed accumulations of grease on the air vent screens of electric motors used for driving such rotating equipment as fans and pumps at the Millstone and Calvert Cliffs nuclear power plants. The grease appeared to have come from overgreasing of the electric motor bearings. Grease was forced out of the bearing seals, onto the stator windings and rotor, from where it either fell or was thrown onto the inside of the motor housing. Because of these observations, the NRC began an investigation into problems that have been caused in the past, or could be caused in the future, by the overgreasing of electric motor bearings. The NRC staff has solicited technical information and operating experience on the problems caused by the overgreasing of electric motor bearings from motor and bearing manufacturers, as well as from other licensees. Their responses are summarized in this discussion

NRC Consultation and Monitoring at the Savannah River Site: Focusing Reviews of Two Different Disposal Actions - 12181

Energy Technology Data Exchange (ETDEWEB)

Ridge, A. Christianne; Barr, Cynthia S.; Pinkston, Karen E.; Parks, Leah S.; Grossman, Christopher J.; Alexander, George W. [U.S. Nuclear Regulatory Commission (United States)

2012-07-01

Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2011, the NRC staff reviewed DOE performance assessments for tank closure at the F-Tank Farm (FTF) Facility and salt waste disposal at the Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) as part of consultation and monitoring, respectively. Differences in inventories, waste forms, and key barriers led to different areas of focus in the NRC reviews of these two activities at the SRS. Because of the key role of chemically reducing grouts in both applications, the evaluation of chemical barriers was significant to both reviews. However, radionuclide solubility in precipitated metal oxides is expected to play a significant role in FTF performance whereas release of several key radionuclides from the SDF is controlled by sorption or precipitation within the cementitious wasteform itself. Similarly, both reviews included an evaluation of physical barriers to flow, but differences in the physical configurations of the waste led to differences in the reviews. For example, NRC's review of the FTF focused on the modeled degradation of carbon steel tank liners while the staff's review of the SDF performance included a detailed evaluation of the physical degradation of the saltstone wasteform and infiltration-limiting closure cap. Because of the long time periods considered (i.e., tens of thousands of years), the NRC reviews of both facilities included detailed evaluation of the engineered chemical and physical barriers. The NRC staff reviews of residual waste disposal in the FTF and salt waste disposal in the SDF focused on physical barriers to flow and chemical barriers to

Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages

International Nuclear Information System (INIS)

1993-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

76 FR 57767 - Proposed Generic Communication; Draft NRC Generic Letter 2011-XX: Seismic Risk Evaluations for...

Science.gov (United States)

2011-09-16

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0204] Proposed Generic Communication; Draft NRC Generic Letter 2011-XX: Seismic Risk Evaluations for Operating Reactors AGENCY: Nuclear Regulatory Commission... FR 54507), that requested public comment on Draft NRC Generic Letter 2011- XX: Seismic Risk...

Safeguards Summary Event List (SSEL). Pre-NRC through June 30, 1981

International Nuclear Information System (INIS)

MacMurdy, P.; Davidson, J.; Lin, H.

1981-09-01

The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the U.S. Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, vandalism, arson, firearms, sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

NRC Regulatory Agenda semiannual report, July--December 1995. Volume 14, No. 2

International Nuclear Information System (INIS)

1996-02-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued semianually

NRC regulatory agenda: Semiannual report, July--December 1996. Volume 15, Number 2

International Nuclear Information System (INIS)

1997-03-01

The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued semiannually

USNRC HTGR safety research program overview

International Nuclear Information System (INIS)

Foulds, R.B.

1982-01-01

An overview is given of current activities and planned research efforts of the US Nuclear Regulatory Commission (NRC) HTGR Safety Program. On-going research at Brookhaven National Laboratory, Oak Ridge National Laboratory, Los Alamos National Laboratory, and Pacific Northwest Laboratory are outlined. Tables include: HTGR Safety Issues, Program Tasks, HTGR Computer Code Library, and Milestones for Long Range Research Plan

NRC TLD [thermoluminescent dosimeter] Direct Radiation Monitoring Network: Progress report, January-March 1988

International Nuclear Information System (INIS)

Struckmeyer, R.; McNamara, N.

1988-06-01

This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the first quarter of 1988

NRC staff site characterization analysis of the Department of Energy's Site Characterization Plan, Yucca Mountain Site, Nevada

International Nuclear Information System (INIS)

1989-08-01

This Site Characterization Analysis (SCA) documents the NRC staff's concerns resulting from its review of the US Department of Energy's (DOE's) Site Characterization Plan (SCP) for the Yucca Mountain site in southern Nevada, which is the candidate site selected for characterization as the nation's first geologic repository for high-level radioactive waste. DOE's SCP explains how DOE plans to obtain the information necessary to determine the suitability of the Yucca Mountain site for a repository. NRC's specific objections related to the SCP, and major comments and recommendations on the various parts of DOE's program, are presented in SCA Section 2, Director's Comments and Recommendations. Section 3 contains summaries of the NRC staff's concerns for each specific program, and Section 4 contains NRC staff point papers which set forth in greater detail particular staff concerns regarding DOE's program. Appendix A presents NRC staff evaluations of those NRC staff Consultation Draft SCP concerns that NRC considers resolved on the basis of the SCP. This SCA fulfills NRC's responsibilities with respect to DOE's SCP as specified by the Nuclear Waste Policy Act (NWPA) and 10 CFR 60.18. 192 refs., 2 tabs

NRC wants plant-specific responses on Thermo-Lag

International Nuclear Information System (INIS)

Anon.

1994-01-01

Dissatisfied with recent industry-backed efforts to assure fire safety at nuclear power plants, the Nuclear Regulatory Commission announced on November 24 that it would direct all nuclear plant owners to specify the actions they would take to assure that the use of the Thermo-Lag 330 fire barrier material would not lead to insufficient protection of electrical cables connected to safe-shutdown systems. Previously, the NRC had been content to let the matter wait until tests sponsored by the Nuclear Management and Resources Council (Numarc) could show whether Thermo-Lag, used and installed in certain ways, would provide sufficient protection, but the NRC and Numarc have disagreed over the test methodology, and the Numarc tests are now considered to be several months behind schedule

77 FR 49835 - Order Prohibiting Involvement in NRC-Licensed Activities; In the Matter of Mr. Joseph Quintanilla

Science.gov (United States)

2012-08-17

... governmental entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139; August 28, 2007). The E-Filing process requires participants to submit and serve all... procedures described below. To comply with the procedural requirements of E-Filing, at least 10 days prior to...

78 FR 66970 - In the Matter of Michael J. Buhrman; Order Prohibiting Involvement in NRC-Licensed Activities...

Science.gov (United States)

2013-11-07

... governmental entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all... procedures described below. To comply with the procedural requirements of E-Filing, at least ten 10 days...

NRC drug-free workplace plan. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-11-01

On September 15, 1986, President Reagan signed Executive Order 12564, establishing the goal of a Drug-Free Federal Workplace. The Order made it a condition of employment that all Federal employees refrain from using illegal drugs on or off duty. On July 11, 1987, Congress passed legislation affecting implementation of the Executive Order under Section 503 of the Supplemental Appropriations Act of 1987, Public Law 100-71 (the Act). The Nuclear Regulatory Commission first issued the NRC Drug Testing Plan to set forth objectives, policies, procedures, and implementation guidelines to achieve a drug-free Federal workplace, consistent with the Executive Order and Section 503 of the Act. Revision 1, titled, ``NRC Drug-Free Workplace Plan,`` supersedes the previous version and its supplements and incorporates changes to reflect current guidance from the Department of Justice, the Department of Health and Human Services, as well as other guidance.

NRC drug-free workplace plan. Revision 1

International Nuclear Information System (INIS)

1997-11-01

On September 15, 1986, President Reagan signed Executive Order 12564, establishing the goal of a Drug-Free Federal Workplace. The Order made it a condition of employment that all Federal employees refrain from using illegal drugs on or off duty. On July 11, 1987, Congress passed legislation affecting implementation of the Executive Order under Section 503 of the Supplemental Appropriations Act of 1987, Public Law 100-71 (the Act). The Nuclear Regulatory Commission first issued the NRC Drug Testing Plan to set forth objectives, policies, procedures, and implementation guidelines to achieve a drug-free Federal workplace, consistent with the Executive Order and Section 503 of the Act. Revision 1, titled, ''NRC Drug-Free Workplace Plan,'' supersedes the previous version and its supplements and incorporates changes to reflect current guidance from the Department of Justice, the Department of Health and Human Services, as well as other guidance

Safeguards Summary Event List (SSEL), Pre-NRC through December 31, 1985

International Nuclear Information System (INIS)

1987-02-01

The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, non-radiological sabotage, and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

Safeguards Summary Event List (SSEL): Pre-NRC through December 31, 1986

International Nuclear Information System (INIS)

1987-07-01

The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

CISTI'S Activities in Support of Scientific Data Management in Canada 2008-2010

Directory of Open Access Journals (Sweden)

Mary Zborowski

2009-03-01

Full Text Available In the Canadian research environment, it is difficult for researchers to effectively discover, access, and use data sets, except for those that are the most well known. Several recent reports have discussed the issues around "lost" data sets: those which are intended to be shared but cannot be identified and utilized effectively because of insufficient associated metadata. Both problems are approaching critical levels in Canada and internationally, a situation that is unacceptable because these data sets are often generated as a result of public funding. Solutions may involve providing support and training for researchers on how they can best collect and manage their data sets or developing gateways to scientific data sets. NRC-CISTI is the largest comprehensive source of scientific, technical, and medical information in North America, with a mandate to serve as Canada's national science library. Through its publishing arm, NRC Research Press, it is also Canada's foremost scientific publisher. NRC-CISTI is an organization with demonstrated expertise in metadata management, which, until recently, focused primarily on library and publishing contexts. However in November 2007, it formally committed to expand its agenda to address the management of scientific research data and the related critical needs of the research community. This paper presents NRC-CISTI's activities in this area. NRC-CISTI has begun by hosting forums in which the critical players (including the granting agencies mapped out targets and approaches. It has strengthened its own internal expertise regarding metadata and management of scientific data sets. Finally, NRC-CISTI is developing a gateway Web site which will provide access to Canadian scientific data sets and related metadata, tools, educational resources, and other informative and collaborative tools urgently needed by Canadian and international researchers. NRC-CISTI is the sponsoring body for the Canadian National

Building confidence in nuclear waste regulation: how NRC is adapting in response to stakeholder concerns

International Nuclear Information System (INIS)

Kotra, Janet P.

2004-01-01

Increasing public confidence in the U.S. Nuclear Regulatory Commission as an effective and independent regulator is an explicit goal of the Agency. When developing new, site-specific regulations for the proposed geologic repository at Yucca Mountain, Nevada, NRC sought to improve its efforts to inform and involve the public in NRC's decision-making process. To this end, NRC has made, and continues to make significant organizational, process and policy changes. NRC successfully applied these changes as it completed final regulations for Yucca Mountain, when introducing a draft license review plan for public comment, and when responding to public requests for information on NRC's licensing and hearing process. It should be understood, however, that these changes emerged, and continue to be applied, in the context of evolving agency concern for increasing stakeholder confidence reflected in institutional changes within the agency as a whole. (author)

NRC Information No. 91-29: Deficiencies identified during electrical distribution system functional inspections

International Nuclear Information System (INIS)

Rossi, C.E.

1992-01-01

During multidisciplinary inspections, the US Nuclear Regulatory Commission (NRC) has identified many deficiencies related to the electrical distribution system. To address these deficiencies, the NRC has developed an inspection to specifically evaluate the electrical distribution system. During the last year, the NRC completed eight EDSFIs, performing at least one in each of the several common deficiencies in the licensees' programs and in the electrical distribution systems as designed and configured at each plant. These deficiencies included inadequate ac voltages at the 480 Vac and 120 Vac distribution levels, inadequate procedures to test circuit breakers, and inadequate determinations and evaluations of setpoints

Final report of the NRC-Agreement State Working Group to evaluate control and accountability of licensed devices

International Nuclear Information System (INIS)

1996-10-01

US NRC staff acknowledged that licensees were having problems maintaining control over and accountability for devices containing radioactive material. In June 1995, NRC approved the staff's suggestion to form a joint NRC-Agreement State Working Group to evaluate the problem and propose solutions. The staff indicated that the Working Group was necessary to address the concerns from a national perspective, allow for a broad level of Agreement State input, and to reflect their experience. Agreement State participation in the process was essential since some Agreement States have implemented effective programs for oversight of device users. This report includes the 5 recommendations proposed by the Working Group to increase regulatory oversight, increase control and accountability of devices, ensure proper disposal, and ensure disposal of orphaned devices. Specifically, the Working Group recommends that: (1) NRC and Agreement States increase regulatory oversight for users of certain devices; (2) NRC and Agreement State impose penalties on persons losing devices; (3) NRC and Agreement States ensure proper disposal of orphaned devices; (4) NRC encourage States to implement similar oversight programs for users of Naturally-Occurring or Accelerator- Produced Material; and (5) NRC encourage non-licensed stakeholders to take appropriate actions, such as instituting programs for material identification

Final report of the NRC-Agreement State Working Group to evaluate control and accountability of licensed devices

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

US NRC staff acknowledged that licensees were having problems maintaining control over and accountability for devices containing radioactive material. In June 1995, NRC approved the staff`s suggestion to form a joint NRC-Agreement State Working Group to evaluate the problem and propose solutions. The staff indicated that the Working Group was necessary to address the concerns from a national perspective, allow for a broad level of Agreement State input, and to reflect their experience. Agreement State participation in the process was essential since some Agreement States have implemented effective programs for oversight of device users. This report includes the 5 recommendations proposed by the Working Group to increase regulatory oversight, increase control and accountability of devices, ensure proper disposal, and ensure disposal of orphaned devices. Specifically, the Working Group recommends that: (1) NRC and Agreement States increase regulatory oversight for users of certain devices; (2) NRC and Agreement State impose penalties on persons losing devices; (3) NRC and Agreement States ensure proper disposal of orphaned devices; (4) NRC encourage States to implement similar oversight programs for users of Naturally-Occurring or Accelerator- Produced Material; and (5) NRC encourage non-licensed stakeholders to take appropriate actions, such as instituting programs for material identification.

NRC confirmatory safety system testing in support of AP600 design review

International Nuclear Information System (INIS)

Rhee, G.S.; Bessette, D.E.; Shotkin, L.M.

1994-01-01

Westinghouse Electric Corporation has submitted the Advanced Passive 600 MWe (AP600) nuclear power plant design to the NRC for design certification. The Office of Nuclear Regulatory Research is proceeding to conduct confirmatory testing to help the NRC staff evaluate the AP600 safety system design. For confirmatory testing, it was determined that the cost-effective route was to modify an existing full-height, full-pressure test facility rather than build a new one. Thus, all the existing integral effects test facilities, both in the US and abroad, were screened to select the best candidate. As a result, the ROSA-V (Rig of Safety Assessment-V) test facility located in the Japan Atomic Energy Research Institute (JAERI) was chosen. However, because of some differences in design between the existing ROSA-V facility and the AP600, the ROSA-V is being modified to conform to the AP600 safety system design. The modification work will be completed by the end of this year. A series of facility characterization tests will then be performed in January 1994 for the modified part of the facility before the main test series is initiated in February 1994. A total of 12 tests will be performed in 1994 under Phase I of this cooperative program with JAERI. Phase II testing is being considered to be conducted in 1995 mainly for beyond-design-basis accident evaluation

NRC TLD Direct Radiation Monitoring Network

International Nuclear Information System (INIS)

Struckmeyer, R.

1994-03-01

This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1993. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

NRC TLD Direct Radiation Monitoring Network

International Nuclear Information System (INIS)

Struckmeyer, R.; McNamara, N.

1993-03-01

This report present the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1992. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

Safeguards summary event list (SSEL): Pre-NRC through December 31, 1987

International Nuclear Information System (INIS)

1988-07-01

The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, alcohol and drugs, and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

The use of NPAR results in plant inspection activities

International Nuclear Information System (INIS)

Gunther, W.; Taylor, J.

1990-01-01

The US Nuclear Regulatory Commission's (NRC's) Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. Equipment and systems which have a propensity for age related degradation are identified, and methods for detecting and mitigating aging effects have been evaluated. As plants age, it becomes increasingly important that NRC inspectors be cognizant of plant aging phenomena. This paper describes the NPAR information which can enhance inspection activities, and provides a mechanism for making pertinent research available to the inspectors

NRC Task Force report on review of the federal/state program for regulation of commercial low-level radioactive waste burial grounds

International Nuclear Information System (INIS)

1977-01-01

The underlying issue explored in this report is that of Federal vs State regulation of commercial radioactive waste burial grounds. The need for research and development, a comprehensive set of standards and criteria, a national plan for low-level waste management, and perpetual care funding are closely related to the central issue and are also discussed. Five of the six commercial burial grounds are regulated by Agreement States; the sixth is regulated solely by the NRC (NRC also regulates Special Nuclear Material at the sites). The sites are operated commercially. The operators contribute to the perpetual care funds for the sites at varying rates. The States have commitments for the perpetual care of the decommissioned sites except for one site, located on Federally owned land. Three conclusions are reached. Federal control over the disposal of low-level waste should be increased by requiring joint Federal/State site approval, NRC licensing, Federal ownership of the land, and a Federally administered perpetual care program. The NRC should accelerate the development of its regulatory program for the disposal of low-level waste. The undisciplined proliferation of low-level burial sites must be avoided. NRC should evaluate alternative disposal methods, conduct necessary studies, and develop a comprehensive low-level waste regulatory program (i.e., accomplish the above recommendations) prior to the licensing of new disposal sites

High-level-waste records management system: the NRC pilot project

International Nuclear Information System (INIS)

Bender, A.; Altomare, P.

1987-01-01

The US Nuclear Regulatory Commission (NRC) and the US Dept. of Energy (DOE) have agreed to develop a licensing support system (LSS) to address the records management requirements created by the Nuclear Waste Policy Act (NWPA). The NRC is planning to conduct a negotiated rule making the modify 10CFR2, including rules governing discovery, so that parties to the licensing process will use a single information management system as a source for all licensing-related documents. The successful demonstration of the pilot project has resulted in an operational on-line record management system for NRC-related HLW documents. Both incoming and outgoing documents are being scanned and stored on a mainframe system and on an optical disk. At this writing the optical disk portion of the system is being tested to evaluate its potential use as a future archival and distribution medium for licensing records. Experience gained from this project is being shared with other government agencies that are in the process of using similar technologies to come to grips with the complex records management problem endemic to our information-based society

NRC TLD Direct Radiation Monitoring Network

International Nuclear Information System (INIS)

Struckmeyer, R.; McNamara, N.

1991-04-01

This report presents the results of the NRC [Nuclear Regulatory Commission] Direct Radiation Monitoring Network for the fourth quarter of 1990. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs

Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1978-12-01

The present decommissioning regulations contained in Sections 50.33(f) and 50.82 of 10 CFR part 50 require applicants for power reactor operating licenses to demonstrate that they can obtain the funds needed to meet both operating costs and estimated costs of shutdown and decommissioning. The development of detailed, specific decommissioning plans for nuclear power plants is not currently required until the licensee seeks to terminate his operating license. Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase the need for future decommissionings, the NRC staff began an in-depth review and reevaluation of NRC's regulatory approach to decommissioning in 1975. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. In response to comments from the public and states, and to information gained during the initial stage of execution of the plan, several modifications of the plan are now required. The revised overall report sets forth in detail the current NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

Handbook for value-impact assessments of NRC regulatory actions

International Nuclear Information System (INIS)

Mullen, M.F.; DiPalo, A.J.

1985-01-01

According to current Nuclear Regulatory Commission (NRC) procedures, value-impact (cost-benefit) assessments must be prepared for all rulemaking actions and for a broad range of other regulatory requirements and guidance. Probabilistic risk assessment (PRA) methods furnish an important part of the information base for these assessments. PRA methods are frequently the principal quantitative tool for estimating the benefits (e.g., public risk reduction) of proposed regulatory actions. In December 1983, the NRC published A Handbook for Value-Impact Assessment, NUREG/CR-3568, which provides a set of systematic procedures for performing value-impact assessments. The Handbook contains methods, data, and sources of information that can assist the regulatory analyst in conducting such assessments. The use of probabilistic risk analysis to estimate the benefits of proposed regulatory actions is described. Procedures and methods are also given for evaluating the costs and other consequences associated with regulatory actions. The Handbook has been adopted by the NRC as the recommended guideline for value impact assessments. This paper presents the background, objectives, and scope of the Handbook, describes the value-impact assessment methods (including the use of probabilistic risk assessment to estimate benefits), and discusses a selection of current and planned applications, with examples to illustrate how the methods are used

NRC/AMRMC Resident Research Associateship Program

Science.gov (United States)

2018-05-01

data sources, gathering and maintaining the data needed, and completing and reviewing this collection of information. Send comments regarding this...with another U.S. government agency 0 Research/administrative position with foreign government agency 0 Research/teaching at US college/university 1

An appropriate level for reactor regulatory research

International Nuclear Information System (INIS)

Budnitz, R.J.; Kouts, H.J.C.

1986-01-01

In this brief paper the appropriate role for NRC's research program is set down, based on the experience of the last decade; and the broad outlines of an appropriate research program for the next decade are discussed. The two authors bring to this topic direct personal experience: they are two of only three former directors of NRC's research program in its history (the other was the last Saul Levine). The discussion considers only reactor safety research, although NRC's research program covers several other areas as well. Safeguards, environmental and health studies, waste management, and transportation are not covered

MutS and MutL are dispensable for maintenance of the genomic mutation rate in the halophilic archaeon Halobacterium salinarum NRC-1.

Directory of Open Access Journals (Sweden)

Courtney R Busch

Full Text Available BACKGROUND: The genome of the halophilic archaeon Halobacterium salinarum NRC-1 encodes for homologs of MutS and MutL, which are key proteins of a DNA mismatch repair pathway conserved in Bacteria and Eukarya. Mismatch repair is essential for retaining the fidelity of genetic information and defects in this pathway result in the deleterious accumulation of mutations and in hereditary diseases in humans. METHODOLOGY/PRINCIPAL FINDINGS: We calculated the spontaneous genomic mutation rate of H. salinarum NRC-1 using fluctuation tests targeting genes of the uracil monophosphate biosynthesis pathway. We found that H. salinarum NRC-1 has a low incidence of mutation suggesting the presence of active mechanisms to control spontaneous mutations during replication. The spectrum of mutational changes found in H. salinarum NRC-1, and in other archaea, appears to be unique to this domain of life and might be a consequence of their adaption to extreme environmental conditions. In-frame targeted gene deletions of H. salinarum NRC-1 mismatch repair genes and phenotypic characterization of the mutants demonstrated that the mutS and mutL genes are not required for maintenance of the observed mutation rate. CONCLUSIONS/SIGNIFICANCE: We established that H. salinarum NRC-1 mutS and mutL genes are redundant to an alternative system that limits spontaneous mutation in this organism. This finding leads to the puzzling question of what mechanism is responsible for maintenance of the low genomic mutation rates observed in the Archaea, which for the most part do not have MutS and MutL homologs.

Regulatory Multidimensionality of Gas Vesicle Biogenesis in Halobacterium salinarum NRC-1

Directory of Open Access Journals (Sweden)

Andrew I. Yao

2011-01-01

Full Text Available It is becoming clear that the regulation of gas vesicle biogenesis in Halobacterium salinarum NRC-1 is multifaceted and appears to integrate environmental and metabolic cues at both the transcriptional and posttranscriptional levels. The mechanistic details underlying this process, however, remain unclear. In this manuscript, we quantify the contribution of light scattering made by both intracellular and released gas vesicles isolated from Halobacterium salinarum NRC-1, demonstrating that each form can lead to distinct features in growth curves determined by optical density measured at 600 nm (OD600. In the course of the study, we also demonstrate the sensitivity of gas vesicle accumulation in Halobacterium salinarum NRC-1 on small differences in growth conditions and reevaluate published works in the context of our results to present a hypothesis regarding the roles of the general transcription factor tbpD and the TCA cycle enzyme aconitase on the regulation of gas vesicle biogenesis.

Status of NRC approval of EPRI electromagnetic interference susceptibility testing guidelines for digital equipment

International Nuclear Information System (INIS)

James, R.W.; Shank, J.W.; Yoder, C.

1996-01-01

Historically, nuclear power plants installing digital equipment have been required to conduct expensive, site-specific electromagnetic interference (EMI) surveys to demonstrate that EMI will not affect the operation of sensitive electronic equipment. Consequently, EPRI formed a Utility Working Group which developed a set of generic EMI susceptibility testing guidelines, which were published as an EPRI report in September 1994. These guidelines are based upon EMI survey data obtained from several different plants and include criteria for determining their applicability. The Working Group interacted with NRC staff to obtain NRC approval. In April 1996, the NRC issued a Safety Evaluation Report (SER) endorsing the guidelines as a valid means of demonstrating EMI compatibility. The issuance of this SER was conditional on issuing a revision to the EPRI EMI Guidelines. This paper summarizes the guidelines, the NRC SER, and the current status of Revision 1 to the report

NRC staff site characterization analysis of the Department of Energy`s Site Characterization Plan, Yucca Mountain Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-08-01

This Site Characterization Analysis (SCA) documents the NRC staff`s concerns resulting from its review of the US Department of Energy`s (DOE`s) Site Characterization Plan (SCP) for the Yucca Mountain site in southern Nevada, which is the candidate site selected for characterization as the nation`s first geologic repository for high-level radioactive waste. DOE`s SCP explains how DOE plans to obtain the information necessary to determine the suitability of the Yucca Mountain site for a repository. NRC`s specific objections related to the SCP, and major comments and recommendations on the various parts of DOE`s program, are presented in SCA Section 2, Director`s Comments and Recommendations. Section 3 contains summaries of the NRC staff`s concerns for each specific program, and Section 4 contains NRC staff point papers which set forth in greater detail particular staff concerns regarding DOE`s program. Appendix A presents NRC staff evaluations of those NRC staff Consultation Draft SCP concerns that NRC considers resolved on the basis of the SCP. This SCA fulfills NRC`s responsibilities with respect to DOE`s SCP as specified by the Nuclear Waste Policy Act (NWPA) and 10 CFR 60.18. 192 refs., 2 tabs.

The role of research in nuclear regulation: Opening remarks

International Nuclear Information System (INIS)

Taylor, J.M.

1997-01-01

More than 20 years ago, the Energy Reorganization Act of 1974 created the USNRC and that same act provided for an office of nuclear regulatory research. It's what is called a statutory office within the NRC. In providing for an NRC research program, our Congress had several things to say about the character of the research that would be performed. First, NRC should perform such research as is necessary for the effective performance of the Commission's licensing and related regulatory functions. Second, the research may be characterized as confirmatory reassessment related to the safe operation and the protection of commercial reactors and other nuclear materials. Third, the NRC should have an independent capability for developing and analyzing technical information related to reactor safety, safeguards, and environmental protection in support of both the licensing and regulatory processes. Fourth, the research should not go beyond the need for confirmatory assessment, because the NRC should never be place in a position of having generated and then having to defend basic design data of its own. This has been and continues to be the role of research at the NRC. Somewhat different purposes might apply for regulatory agencies in other countries. Several regulatory agencies are represented here on this panel, so some of these difference may be discussed

Perspective on US NRC Policy Issues Concerning Use of Risk Insights for Non-LWR

International Nuclear Information System (INIS)

Ha, Jun Su; Kim, In Goo; Huh, Chang Wook; Kim, Kyun Tae

2011-01-01

Since the PRA Implementation plan of US NRC (1994), PRA has been applied to all NPPs in USA and risk insights have been used for the regulation as a complement of the deterministic approaches. RIRIP (Risk-Informed Regulation Implementation Plan, 2000) and RPP (Risk-Informed and Performance-Based Plan, 2007) were announced by US NRC thereafter, which recommended enhanced use of risk insights. In the meantime, there have been lots of policy issues concerning use of risk insights for licensing Non-LWR designs, which will be discussed in this paper to understand the stream of perspectives on US NRC's approach

77 FR 33786 - NRC Enforcement Policy Revision

Science.gov (United States)

2012-06-07

... methods: Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2011... search, select ``ADAMS Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems... either 2.3.2.a. or b. must be met for the disposition of a violation as an NCV.'' The following new...

The evolution of the structure and application of U.S. NRC regulations and standards

International Nuclear Information System (INIS)

Murley, T.E.; Rosztoczy, Z.R.; McPherson, G.D.

1991-01-01

NRC regulations and standards and their implementation have evolved from early adaptations of conventional engineering practices to a mature, cohesive set of regulations that govern NRC regulation of nuclear power plant safety in the United States. From a simple set of rules and design criteria and from the standards of the professional engineering societies, a hierarchy of practices, standards, guides, rules and goals has developed. Resting on a foundation of industrial practices, this hierarchy rises through levels of national standards, regulatory guides and standard review plans, policy statements and NRC regulations. The licensing process is evolving today toward one that permits both site approval and standard design certification before the plant is constructed. At the present time, NRC is reviewing five standard designs for certification for a period of 15 years. NRC focuses its regulation of operating nuclear plants on inspections conducted from five regional offices. Resident inspectors, specialist inspectors, and multi-disciplinary inspection teams examine specific plant situations. The results of all these inspections are used to develop a complete understanding of a plant's physical condition, its operation, maintenance and management. To improve safe operation of nuclear plants in the U.S., a most important program, the Systematic Assessment of Licensee Performance, measures operational performance, using a broad spectrum of functional areas. (orig.)

Beef Species Symposium: an assessment of the 1996 Beef NRC: metabolizable protein supply and demand and effectiveness of model performance prediction of beef females within extensive grazing systems.

Science.gov (United States)

Waterman, R C; Caton, J S; Löest, C A; Petersen, M K; Roberts, A J

2014-07-01

Interannual variation of forage quantity and quality driven by precipitation events influence beef livestock production systems within the Southern and Northern Plains and Pacific West, which combined represent 60% (approximately 17.5 million) of the total beef cows in the United States. The beef cattle requirements published by the NRC are an important tool and excellent resource for both professionals and producers to use when implementing feeding practices and nutritional programs within the various production systems. The objectives of this paper include evaluation of the 1996 Beef NRC model in terms of effectiveness in predicting extensive range beef cow performance within arid and semiarid environments using available data sets, identifying model inefficiencies that could be refined to improve the precision of predicting protein supply and demand for range beef cows, and last, providing recommendations for future areas of research. An important addition to the current Beef NRC model would be to allow users to provide region-specific forage characteristics and the ability to describe supplement composition, amount, and delivery frequency. Beef NRC models would then need to be modified to account for the N recycling that occurs throughout a supplementation interval and the impact that this would have on microbial efficiency and microbial protein supply. The Beef NRC should also consider the role of ruminal and postruminal supply and demand of specific limiting AA. Additional considerations should include the partitioning effects of nitrogenous compounds under different physiological production stages (e.g., lactation, pregnancy, and periods of BW loss). The intent of information provided is to aid revision of the Beef NRC by providing supporting material for changes and identifying gaps in existing scientific literature where future research is needed to enhance the predictive precision and application of the Beef NRC models.

Critical power prediction by CATHARE2 of the OECD/NRC BFBT benchmark

Energy Technology Data Exchange (ETDEWEB)

Lutsanych, Sergii, E-mail: s.lutsanych@ing.unipi.it [San Piero a Grado Nuclear Research Group (GRNSPG), University of Pisa, Via Livornese 1291, 56122, San Piero a Grado, Pisa (Italy); Sabotinov, Luben, E-mail: luben.sabotinov@irsn.fr [Institut for Radiological Protection and Nuclear Safety (IRSN), 31 avenue de la Division Leclerc, 92262 Fontenay-aux-Roses (France); D’Auria, Francesco, E-mail: francesco.dauria@dimnp.unipi.it [San Piero a Grado Nuclear Research Group (GRNSPG), University of Pisa, Via Livornese 1291, 56122, San Piero a Grado, Pisa (Italy)

2015-03-15

Highlights: • We used CATHARE code to calculate the critical power exercises of the OECD/NRC BFBT benchmark. • We considered both steady-state and transient critical power tests of the benchmark. • We used both the 1D and 3D features of the CATHARE code to simulate the experiments. • Acceptable prediction of the critical power and its location in the bundle is obtained using appropriate modelling. - Abstract: This paper presents an application of the French best estimate thermal-hydraulic code CATHARE 2 to calculate the critical power and departure from nucleate boiling (DNB) exercises of the International OECD/NRC BWR Fuel Bundle Test (BFBT) benchmark. The assessment activity is performed comparing the code calculation results with available in the framework of the benchmark experimental data from Japanese Nuclear Power Engineering Corporation (NUPEC). Two-phase flow calculations on prediction of the critical power have been carried out both in steady state and transient cases, using one-dimensional and three-dimensional modelling. Results of the steady-state critical power tests calculation have shown the ability of CATHARE code to predict reasonably the critical power and its location, using appropriate modelling.

Interactive Computerized Based Training, In Radiation Protection at NRC-Negev

International Nuclear Information System (INIS)

Sberlo, E.; Krumbein, H.; Ankri, D.; Ben-Shachar, B.; Laichter, Y.; Weizer, G.; Adorarn, D.

1999-01-01

According to the rules of safety at the working places in Israel, all radiation employees in Israel should receive once a year a refreshing course in several areas of safety. At the NRC-Negev there are two kinds of radiation employees: the ''hot area'' employees, who work in an environment of radioactive materials or radiation machines and the ''old area'' employees (all the other employees in the NRC-Negev). One of the main goals of the Department of Human Resources Development and Training at the NRC-Negev was to organize safety refresher courses. All ''hot area'' employees received a training program of two days in safety subjects, each year. The ''cold area'' employees received the same course, each second year. The former training program included several lectures in radiation protection, health physics, biological effects of ionizing radiation, etc., as well as same lectures in industrial safety, fast aid, fee fighting, emergency procedures, etc. The safety refresher courses were given by Rental lectures. There were a lot of disadvantages in these frontal lectures: The lecturers are employees of the NRCN who had to stop their routine work in order to lecture; the lecturers had to carry out identical training for each course for a large group of workers; there was a lack of testing methods or any other certification for the employees. Recently, seven safety courseware were developed by the NRC-Negev and the CET (Centre for Educational Technology), in order to perform these safety refresher courses. The courseware are based on an interactive computerized training including tutorials and quiz. The tutorial is an interactive course in each subject. The employee gets a simple and clear explanation (including pictures). After each Morial there is a quiz which includes 7 American style questions. The first two courseware are for all the employees, the next 4 courseware for the ''hot area'' employees, and the seventh for the ''cold area'' employees (the seventh is a

10 CFR 51.104 - NRC proceeding using public hearings; consideration of environmental impact statement.

Science.gov (United States)

2010-01-01

... environmental impact statement. 51.104 Section 51.104 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED....104 NRC proceeding using public hearings; consideration of environmental impact statement. (a)(1) In... scope of NEPA and this subpart are in issue, the NRC staff may not offer the final environmental impact...

Safeguards Summary Event List (SSEL). Pre-NRC-June 30, 1985. Revision 11

International Nuclear Information System (INIS)

1986-01-01

The Safeguards Summary Event List (SSRL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, non-radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels. 12 figs

48 CFR 2009.570 - NRC organizational conflicts of interest.

Science.gov (United States)

2010-10-01

... conflicts of interest. 2009.570 Section 2009.570 Federal Acquisition Regulations System NUCLEAR REGULATORY COMMISSION COMPETITION AND ACQUISITION PLANNING CONTRACTOR QUALIFICATIONS Organizational Conflicts of Interest 2009.570 NRC organizational conflicts of interest. ...

Reassessment of NRC's dollar per person-rem conversion factor policy

International Nuclear Information System (INIS)

1995-12-01

The US Nuclear Regulatory Commission (NRC) has completed a review and analysis of its dollar per person-rem conversion factor policy. As a result of this review, the NRC has decided to adopt a $2000 per person-rem conversion factor, subject it to present worth considerations, and limit its scope solely to health effects. This is in contrast to the previous policy and staff practice of using an undiscounted $1000 per person-rem conversion factor that served as a surrogate for all offsite consequences (health and offsite property). The policy shift has been incorporated in ''Regulatory Analysis Guidelines of the US Nuclear Regulatory Commission,'' NUREG/BR-0058, Revision 2, November 1995

NRC new sustainable building

International Nuclear Information System (INIS)

Semczyszyn, D.

2004-01-01

'Full text:' The National Research Council Institute For Fuel Cell Innovation is relocating to a purpose-built 71,343 sq. Ft. (6598 sq. M) Research, Testing, Evaluation, and Industry Incubation Facility in the spring of 2006. The new facility will contain Hydrogen-ready laboratories, the existing relocated Hydrogen Safe Environmental Test Chamber, a hydrogen vehicle maintenance bay, a hydrogen vehicle refuelling station, and the following demonstration projects and features: 1. A Ground Source Heat Pump: This long-proven natural-source heating and cooling technology to provide climate control for the new IFCI's atrium and galleria. It is being designed by Keen Engineering of North Vancouver, BC. 2. 5 KW Solid Oxide Fuel Cell System: Fuelled by natural gas and in the future, from biomass, the fuel cell will also produce approximately 15 kW of waste heat, which will be captured and used to supply heat for the building. The Solid Oxide Fuel Cell will be supplied by Fuel Cell Technologies in Kingston, ON. 3. LEED Building certification: Attaining LEED 'green building' certification is considered an important complement to the plans for the new NRC-IFCI, because it will provide respected third-party verification of government's commitment to efficient building design and construction. Project architects Bunting Coady of Vancouver, BC believe the IFCI has strong potential to earn gold LEED certification. 4. Photovoltaic hydrogen source for back-up power fuel cell system: A photovoltaic array will capture energy from sunlight to power an electrolyzer that will produce and store hydrogen for a PEM fuel cell emergency backup power system. The electrolyzer will be provided by Hydrogenics of Mississauga, ON. Photovoltaics are being designed and installed by the British Columbia Institute of Technology. (author)

Public meeting on radiation safety for industrial radiographerss: remarks, questions and answers at five NRC regional meetings

International Nuclear Information System (INIS)

1978-11-01

Over the past several years thenumber of radiation overexposures experienced in the radiography industry has been higher than for any other single group of NRC licensees. To inform radiography licensees of NRC's concern fo these recurring overexposure incidents, NRC staff representatives met with licensees in a series of five regional meetings. At these meetings the staff presented prepared remarks and answered questions on NRC regulations and operations. The main purposes of the meetings were to express NRC's concern for the high incidence of overexposures, and to open a line of communication between the NRC and radiography licensees in an effort to achieve the common goal of improved radiation safety. The remarks presented by the staff and subjects discussed at these meetings included: the purpose, scope, findings and goals of the NRC inspection program; ways and means of incorporating safety into radiography operations; and case histories of overexposure incidents, with highlights of the causes and possible preventions. At each of the regional meetings the staff received a request for a copy of the prepared remarks and a consolidation of the questions and answers that were discussed. This document includes that information, and a copy is being provided to each organizaion or firm attending the regional meetings. Requests for other copies should be made in accordance with the directions printed inside the front cover of this document

NRC/AMRMC Resident Research Associateship Program

Science.gov (United States)

2016-04-27

stem-cell released molecule as a therapy in blast-injured retina Miller, Christine 2/4/2013-2/3/2016 1 Optimized protocol to isolate, identify, and...derived self-formed optic cups in laser-injured retina 7) SUMMARY OF RESEARCH DURING TENURE Itemize significant findings in concise form, utilizing key...during retinogenesis 5) Formulate a research plan on using stem-cell released molecule as a therapy in blast-injured retina (USMA Davies Fellow: please

Dependent failure analysis research for the US NRC Risk Methods Integration and Evaluation Program

International Nuclear Information System (INIS)

Bohn, M.P.; Stack, D.W.; Campbell, D.J.; Rooney, J.J.; Rasmuson, D.M.

1985-01-01

The Risk Methods Integration and Evaluation Program (RMIEP), which is being performed for the Nuclear Regulatory Commission by Sandia National Laboratories, has the goals of developing new risk assessment methods and integrating the new and existing methods in a uniform procedure for performing an in-depth probabilistic risk assessment (PRA) with consistent levels of analysis for internal, external, and dependent failure scenarios. An important part of RMIEP is the recognition of the crucial importance of dependent common cause failures (CCFs) and the pressing need to develop effective methods for analyzing CCFs as part of a PRA. The NRC-sponsored Integrated Dependent Failure Methodology Program at Sandia is addressing this need. This paper presents a preliminary approach for analyzing CCFs as part of a PRA. A nine-step procedure for efficiently screening and analyzing dependent failure scenarios is presented, and each step is discussed

Implementation study for the NRC Application and Development Facility

International Nuclear Information System (INIS)

Sherwood, R.J.; Ross, D.J.; Sasser, D.W.

1979-01-01

The Nuclear Regulatory Commission (NRC) has expressed the desire to establish an Application and Development Facility (ADF) for NRC Headquarters. The ADF is a computer system which will provide safeguards analysts access to safeguards analysis computer software. This report analyzes the issues, requirements and options available in the establishment of an ADF. The purpose and goals of the ADF are presented, along with some general issues to be considered in the implementation of such a system. A phased approach for ADF implementation, which will allow for the earliest possible access to existing codes and also allow for future expansion, is outlined. Several options for central computers are discussed, along with the characteristics and approximate costs for each. The report concludes with recommended actions proposed to start the development of the ADF

NRC Regulatory Agenda. Quarterly report, July-September 1985

International Nuclear Information System (INIS)

1985-10-01

The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed, or is considering action as well as those on which it has recently completed action, and all petitions for rulemaking which have been received and are pending disposition by the Commission

NRC Regulatory Agenda: Quarterly report, January--March 1988

International Nuclear Information System (INIS)

1988-07-01

The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed, or is considering action as well as those on which it has recently completed action, and all petitions for rulemaking which have been received and are pending disposition by the Commission

NRC Regulatory Agenda. Quarterly report, July-September 1982

International Nuclear Information System (INIS)

1982-10-01

The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received and are pending disposition by the Commission. The agenda consists of two sections. Section I, Rules, includes: (1) rules on which final action has been taken since June 30, the cutoff date of the last Regulatory Agenda; (2) rules published previously as proposed rules and on which the Commission has not taken final action; (3) rules published as advance notices of proposed rulemaking and for which neither a proposed nor final rule has been issued; and (4) unpublished rules on which the NRC expects to take action. Section II, Petitions for Rulemaking, includes: (1) Petitions incorporated into final rules or petitions denied since the cutoff date of the last Regulatory Agenda; (2) Petitions incorporated into proposed rules, (3) Petitions pending staff review; and (4) Petitions with deferred action

Joint US Geological Survey, US Nuclear Regulatory Commission workshop on research related to low-level radioactive waste disposal, May 4-6, 1993, National Center, Reston, Virginia; Proceedings

Science.gov (United States)

Stevens, Peter R.; Nicholson, Thomas J.

1996-01-01

This report contains papers presented at the "Joint U.S. Geological Survey (USGS) and U.S. Nuclear Regulatory Commission (NRC) Technical Workshop on Research Related to Low-Level Radioactive Waste (LLW) Disposal" that was held at the USGS National Center Auditorium, Reston, Virginia, May 4-6, 1993. The objective of the workshop was to provide a forum for exchange of information, ideas, and technology in the geosciences dealing with LLW disposal. This workshop was the first joint activity under the Memorandum of Understanding between the USGS and NRC's Office of Nuclear Regulatory Research signed in April 1992.Participants included invited speakers from the USGS, NRC technical contractors (U.S. Department of Energy (DOE) National Laboratories and universities) and NRC staff for presentation of research study results related to LLW disposal. Also in attendance were scientists from the DOE, DOE National Laboratories, the U.S. Environmental Protection Agency, State developmental and regulatory agencies involved in LLW disposal facility siting and licensing, Atomic Energy Canada Limited (AECL), private industry, Agricultural Research Service, universities, USGS and NRC.

Safeguards Summary Event List (SSEL), Pre-NRC through December 31, 1983. Rev. 9

International Nuclear Information System (INIS)

1984-06-01

The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing/allegedly stolen, transportation, tampering/vandalism, arson, firearms-related, radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

EPRI research on accident management

International Nuclear Information System (INIS)

Oehlberg, R.N.; Chao, J.

1991-01-01

The paper discusses Nuclear Regulatory Commission (NRC) efforts regarding severe reactor accident management and the Nuclear Management and Resources Council (NUMAEX), activities. (EPRI) Electric Power Research Institute accident management program consists of the two products just mentioned plus one related to severe accident plant status information and the MAAP 4.0 computer code. These are briefly discussed

Reports distributed in 1976 under the NRC Light-Water Reactor Safety Technical Exchange. Volume II

International Nuclear Information System (INIS)

Sharp, D.S.; Cottrell, W.B.

1977-01-01

Lists of documents exchanged in 1976 under agreement between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, and Japan are presented. In 1976 the NRC received 25 reports from France, 74 from F.R. Germany, and 39 from Japan, and in return sent 119 U.S. reports to France, 154 to F.R. Germany, and 155 to Japan

The Geotechnical Board National Research Council. [Annual] activities report, March 1, 1991--June 30, 1992

Energy Technology Data Exchange (ETDEWEB)

Smeallie, P.H.

1993-08-11

This report covers the activities of the Geotechnical Board and its two national committees, the US National Committee for Rock Mechanics (USNC/RM) and the US National Committee on Tunneling Technology (USNC/TT), for the period from March 1, 1991 to June 30, 1992. The report covers a 16-month period, through June of this year, to bring the reporting period in line with the National Research Council`s (NRC) fiscal year. Subsequent reports will cover the 12-month period July 1--June 30, unless individual contracts require otherwise. A description of the Geotechnical Board and its committees within the context of the National Academy of Sciences/National Research Council, as well as lists of current members of the board and national committees can be found in Attachment A.

Geotechnical engineering considerations in the NRC's review of uranium mill tailings remedial action plans

International Nuclear Information System (INIS)

Gillen, D.M.

1985-01-01

To reduce potential health hazards associated with inactive uranium mill tailings sites, the Department of Energy (DOE) is presently investigating and implementing remedial actions at 24 sites in the Uranium Mill Tailings Remedial Action Program (UMTRAP). All remedial actions must be selected and performed with the concurrence of the Nuclear Regulatory Commission (NRC). This paper provides a discussion of geotechnical engineering considerations during the NRC's preconcurrence review of proposed remedial action plans. In order for the NRC staff to perform an adequate geotechnical engineering review, DOE documents must contain a presentation of the properties and stability of all in-situ and engineered soil and rock which may affect the ability of the remedial action plans to meet EPA standards for long-term stability and control. Site investigations, laboratory testing, and remedial action designs must be adequate in scope and technique to provide sufficient data for the NRC staff to independently evaluate static and dynamic stability, settlement, radon attenuation through the soil cover, durability of rock for erosion protection, and other geotechnical engineering factors

NASA Langley Research Center outreach in astronautical education

Science.gov (United States)

Duberg, J. E.

1976-01-01

The Langley Research Center has traditionally maintained an active relationship with the academic community, especially at the graduate level, to promote the Center's research program and to make graduate education available to its staff. Two new institutes at the Center - the Joint Institute for Acoustics and Flight Sciences, and the Institute for Computer Applications - are discussed. Both provide for research activity at the Center by university faculties. The American Society of Engineering Education Summer Faculty Fellowship Program and the NASA-NRC Postdoctoral Resident Research Associateship Program are also discussed.

Directory of certificates of compliance for radioactive materials packages. Volume 3, Revision 14: Report of NRC approved quality assurance programs for radioactive materials packages

International Nuclear Information System (INIS)

1994-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Safeguards Summary Event List (SSEL). Pre-NRC through December 31, 1984. Revision 10

International Nuclear Information System (INIS)

1985-05-01

The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, non-radiological sabotage and miscellaneous. The information contained in the event descriptions in derived primarily from official NRC reporting channels

Licensing considerations in converting NRC-licensed non-power reactors from high-enriched to low-enriched uranium fuels

International Nuclear Information System (INIS)

Carter, R.E.

1985-01-01

During the mid-1970s, there was increasing concern with the possibility that highly enriched uranium (HEU), widely used in non-power reactors around the world, might be diverted from its intended peaceful uses. In 1982 the U.S. Nuclear Regulatory Commission (NRC) issued a policy statement that was intended to conform with the perceived international thinking, and that addressed the two relevant areas in which NRC has statutory responsibility, namely, export of special nuclear materials for non-USA non-power reactors, and the licensing of USA-based non-power reactors not owned by the Federal government. To further address the second area, NRC issued a proposed rule for public comment that would require all NRC-licensed non-power reactors using HEU to convert to low enriched uranium (LEU) fuel, unless they could demonstrate a unique purpose. Currently the NRC staff is revising the proposed rule. An underlying principle guiding the staff is that as long as a change in enrichment does not lead to safety-related reactor modifications, and does not involve an unreviewed safety question, the licensee could convert the core without prior NRC approval. At the time of writing this paper, a regulatory method of achieving this principle has not been finalized. (author)

Licensing considerations in converting NRC-licensed non-power reactors from high-enriched to low-enriched uranium fuels

Energy Technology Data Exchange (ETDEWEB)

Carter, R E

1985-07-01

During the mid-1970s, there was increasing concern with the possibility that highly enriched uranium (HEU), widely used in non-power reactors around the world, might be diverted from its intended peaceful uses. In 1982 the U.S. Nuclear Regulatory Commission (NRC) issued a policy statement that was intended to conform with the perceived international thinking, and that addressed the two relevant areas in which NRC has statutory responsibility, namely, export of special nuclear materials for non-USA non-power reactors, and the licensing of USA-based non-power reactors not owned by the Federal government. To further address the second area, NRC issued a proposed rule for public comment that would require all NRC-licensed non-power reactors using HEU to convert to low enriched uranium (LEU) fuel, unless they could demonstrate a unique purpose. Currently the NRC staff is revising the proposed rule. An underlying principle guiding the staff is that as long as a change in enrichment does not lead to safety-related reactor modifications, and does not involve an unreviewed safety question, the licensee could convert the core without prior NRC approval. At the time of writing this paper, a regulatory method of achieving this principle has not been finalized. (author)

A simple program to reduce the stress associated with NRC nuclear operator examinations

International Nuclear Information System (INIS)

Sajwau, T.; Chardos, S.

1988-01-01

The NRC license for nuclear reactor operators requires periodic written examinations to demonstrate ongoing technical competency. Poor performance raises a competency question and can affect the individuals' careers. Accordingly, the exams can be highly stressful events. Stress has been demonstrated to affect memory, perception, other cognitive attitudes, and test performance. The phenomenon of test anxiety is well known. Instead of a generic, broadly focused stress management approach, a sharply focused, two-part program was developed for TVA operators scheduled to take the NRC examination. The first part was presented early in preparatory training, and the second part was given just prior to the examination. The first part consisted of a simple model of stress found in exams, early warning signs of test stress, and tactics of stress management that were practical to use during the NRC exam itself

International cooperation during radiological emergencies. NRC program guidance for the provision of technical advice to foreign counterpart organizations

International Nuclear Information System (INIS)

Senseney, R.

1986-04-01

This report defines the scope, application, and limits of the technical cooperation the Nuclear Regulatory Commission (NRC) would provide, upon request, to a foreign regulatory agency in a nuclear emergency. It outlines the basis for such cooperation, offers a model written agreement, and describes recent cases of NRC assistance. It also identifies non-NRC sources of emergency advisory assistance available to foreign organizations

Applications of probabilistic techniques at NRC

International Nuclear Information System (INIS)

Thadani, A.; Rowsome, F.; Speis, T.

1984-01-01

The NRC is currently making extensive use of probabilistic safety assessment in the reactor regulation. Most of these applications have been introduced in the regulatory activities in the past few years. Plant Probabilistic Safety Studies are being utilized as a design tool for applications for standard designs and for assessment of plants located in regions of particularly high population density. There is considerable motivation for licenses to perform plant-specific probabilistic studies for many, if not all, of the existing operating nuclear power plants as a tool for prioritizing the implementation of the many outstanding licensing actions of these plants as well as recommending the elimination of a number of these issues which are judged to be insignificant in terms of their contribution to safety and risk. Risk assessment perspectives are being used in the priorization of generic safety issues, development of technical resolution of unresolved safety issues, assessing safety significance of proposed new regulatory requirements, assessment of safety significance of some of the occurrences at operating facilities and in environmental impact analyses of license applicants as required by the National Environmental Policy Act. (orig.)

NRC Bulletin No. 87-02, Supplement 1: Fastener testing to determine conformance with applicable material specifications

International Nuclear Information System (INIS)

Rossi, C.E.

1992-01-01

Item 5 of NRC Compliance Bulletin 87-02 requested that all holders of operating licenses or construction permits for nuclear power reactors information regarding the identity of the suppliers and manufacturers of the safety-related and non-safety-related fasteners selected for testing. After further consideration, the NRC has determined that it needs information regarding the identity of all vendors from which safety-related and non-safety-related fasteners have been obtained within the past 10 years, a reasonable period which will not put undue burden on addressees. This information will assist the NRC in determining whether nuclear facility fasteners in use have been supplied in accordance with their intended use. In addition, this information is needed so that the NRC can properly coordinate information with other government agencies concerned with problems identified in the quality of fasteners

Applying risk insights in US NRC reviews of integral pressurized water reactor designs

International Nuclear Information System (INIS)

Caruso, M.A.; Hilsmeier, T.; Kevern, T.A.

2012-01-01

In its Staff Requirements Memorandum (SRM) on COMGBJ-10-0004/COMGEA-10-0001, 'Use of Risk Insights to Enhance Safety Focus of Small Modular Reactor Reviews,' dated August 31, 2010 (ML102510405), the U.S. Nuclear Regulatory Commission (NRC) directed the NRC staff to more fully integrate the use of risk insights into pre-application activities and the review of small modular reactor (SMR) applications with near-term focus on integral pressurized water reactor (iPWR) designs. The Commission's objective is to align the review focus and resources with the risk-significant systems, structures, and components (SSCs) and other aspects of the design, that contribute most to safety in order to enhance the efficiency of the review process while still enabling a decision of reasonable assurance of the design's safety. The staff was directed to develop a design-specific, risk-informed review plan for each SMR to address pre-application and application review activities. The NRC staff submitted a response to the Commission which describes its approach for (1) using risk insights, consistent with current regulatory requirements, to assign SSCs to one of a limited set of graded categories, and (2) adjusting the scope and depth of current review plans--where possible--consistent with regulatory requirements and consistent with the applicable graded category. Because the staff's review constitutes an independent audit of the application, the staff may emphasize or de-emphasize particular aspects of its review guidance (i.e., Standard Review Plan), as appropriate and consistent with regulatory requirements, for the application being reviewed. The staff may propose justifications for not performing certain sections of the reviews called for by the applicable review plan. Examples of acceptable variations in the scope of a review can include reduced emphasis on SSC attributes such as reliability, availability, or functional performance when the SSC will be in the scope of a program

Pilot program: NRC severe reactor accident incident response training manual: Severe reactor accident overview

International Nuclear Information System (INIS)

McKenna, T.J.; Martin, J.A.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

1987-02-01

This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Severe Reactor Accident Overview is the second in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assesment. Each volume serves, respectively, as the text for a course of instruction in a series of courses. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

Safeguards Summary Event List (SSEL), pre-NRC through December 31, 1989

International Nuclear Information System (INIS)

1990-07-01

The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, alcohol and drugs (involving reactor operators, security force members, or management persons), and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

76 FR 54507 - Proposed Generic Communication; Draft NRC Generic Letter 2011-XX: Seismic Risk Evaluations for...

Science.gov (United States)

2011-09-01

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0204] Proposed Generic Communication; Draft NRC Generic... functions. SSCs in operating nuclear power plants are designed either in accordance with, or have been... nuclear reactors. The background information relevant to this GL includes the individual plant...

NRC/UBC fuelling station with intelligent compression

International Nuclear Information System (INIS)

Dada, A.; Boyd, B.; Law, L.; Semczyszyn, D.

2004-01-01

BOC Canada Ltd. will design, integrate and construct the second fueling station on the Hydrogen Highway. This station will be located at the National Research Council's Institute for Fuel Cell Innovation on the campus of the University of British Columbia. BOC's design will bring together an existing alkaline electrolyser, new compression, storage and dispensing. The station will be designed to serve fuel cell passenger vehicles using 350-bar storage. However, the flexible design concept will allow for many other user needs including the potential for servicing larger vehicles, as well as filling portable storage systems for use at satellite stations. The novel station design also offers the potential to fuel from multiple hydrogen sources. Together with NRC, this fueling station will be used to increase public, consumer and investor awareness of hydrogen technologies. Design and construction of this facility will assist in the development of industry codes and standards and familiarize authorities having jurisdiction with hydrogen fueling. The system concept offers the utmost attention to safety, novelty and flexibility. (author)

Pilot program: NRC severe reactor accident incident response training manual: Public protective actions: Predetermined criteria and initial actions

International Nuclear Information System (INIS)

Martin, J.A. Jr.; McKenna, T.J.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

1987-02-01

This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Public Protective Actions - Predetermined Criteria and Initial Actions is the fourth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume reviews public protective action criteria and objectives, their bases and implementation, and the expected public response. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

NRC Information No. 88-04: Inadequate qualification and documentation of fire barrier penetration seals

International Nuclear Information System (INIS)

Rossi, C.E.

1992-01-01

The current NRC review was prompted by reports, inspection findings, allegations, and other information that indicated the possibility that NRC requirements for fire barrier penetration seals were not being met in all aspects. The review included: evaluations of fire barrier penetration seal specifications and procedures developed by licensees, licensee agents, and licensee contractors; evaluations of various fire barrier penetration seal tests and test data; and inspections of various fire barrier penetrations seal designs and installations. The types of concerns identified to date and mentioned below are related to weaknesses in the implementation of NRC requirements and guidelines as related to fire barrier penetration seal design qualification. The NRC review also has identified a current practice that can affect the qualification status of installed seals. Plant modifications are being made that require running new cable and conduits through existing penetration seals. These modifications are generally being made without an associated technical review to ensure that the resulting penetration seal design configuration or design parameters are consistent with those validated by initial qualification tests. Over a period of time, numerous minor modifications to the same area could cumulatively result in a degraded fire barrier rating

NRC [Nuclear Regulatory Commission] perspective of software QA [quality assurance] in the nuclear history

International Nuclear Information System (INIS)

Weiss, S.H.

1988-01-01

Computer technology has been a part of the nuclear industry since its inception. However, it is only recently that computers have been integrated into reactor operations. During the early history of commercial nuclear power in the United States, the US Nuclear Regulatory Commission (NRC) discouraged the use of digital computers for real-time control and monitoring of nuclear power plant operation. At the time, this position was justified since software engineering was in its infancy, and horror stories on computer crashes were plentiful. Since the advent of microprocessors and inexpensive computer memories, significant advances have been made in fault-tolerant computer architecture that have resulted in highly reliable, durable computer systems. The NRC's requirement for safety parameter display system (SPDS) stemmed form the results of studies and investigations conducted on the Three Mile Island Unit 2 (TMI-2) accident. An NRC contractor has prepared a handbook of software QA techniques applicable to the nuclear industry, published as NUREG/CR-4640 in August 1987. Currently, the NRC is considering development of an inspection program covering software QA. Future efforts may address verification and validation as applied to expert systems and artificial intelligence programs

NRC ARDC Guidance Support Status Report

Energy Technology Data Exchange (ETDEWEB)

Holbrook, Mark R. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-07-01

This report provides a summary that reflects the progress and status of proposed regulatory design criteria for advanced non-light water reactor (LWR) designs in accordance with the Level 3 milestone M3AT-17IN2001013 in work package AT-17IN200101. These criteria have been designated as advanced reactor design criteria (ARDC) and they provide guidance to future applicants for addressing the general design criteria (GDC) that are currently applied specifically to LWR designs. This report provides a summary of Phase 2 activities related to the various tasks associated with ARDC development and the subsequent development of ARDC regulatory guidance for sodium fast reactor (SFR) and modular high-temperature gas-cooled reactor (HTGR) designs. Status Report Organization: Section 2 discusses the origin of the GDC and their application to LWRs. Section 3 addresses the objective of this initiative and how it benefits the advanced non-LWR reactor vendors. Section 4 discusses the scope and structure of the initiative. Section 5 provides background on the U.S. Department of Energy (DOE) ARDC team’s original development of the proposed ARDC that were submitted to the NRC for consideration. Section 6 provides a summary of recent ARDC Phase 2 activities. Appendices A through E document the DOE ARDC team’s public comments on various sections of the NRC’s draft regulatory guide DG–1330, “Guidance for Developing Principal Design Criteria for Non-Light Water Reactors.”

NRC ARDC Guidance Support Status Report

International Nuclear Information System (INIS)

Holbrook, Mark R.

2017-01-01

This report provides a summary that reflects the progress and status of proposed regulatory design criteria for advanced non-light water reactor (LWR) designs in accordance with the Level 3 milestone M3AT-17IN2001013 in work package AT-17IN200101. These criteria have been designated as advanced reactor design criteria (ARDC) and they provide guidance to future applicants for addressing the general design criteria (GDC) that are currently applied specifically to LWR designs. This report provides a summary of Phase 2 activities related to the various tasks associated with ARDC development and the subsequent development of ARDC regulatory guidance for sodium fast reactor (SFR) and modular high-temperature gas-cooled reactor (HTGR) designs. Status Report Organization: Section 2 discusses the origin of the GDC and their application to LWRs. Section 3 addresses the objective of this initiative and how it benefits the advanced non-LWR reactor vendors. Section 4 discusses the scope and structure of the initiative. Section 5 provides background on the U.S. Department of Energy (DOE) ARDC team’s original development of the proposed ARDC that were submitted to the NRC for consideration. Section 6 provides a summary of recent ARDC Phase 2 activities. Appendices A through E document the DOE ARDC team’s public comments on various sections of the NRC’s draft regulatory guide DG–1330, “Guidance for Developing Principal Design Criteria for Non-Light Water Reactors.”

HTGR safety research concerns at NRC

International Nuclear Information System (INIS)

Minogue, R.B.

1982-01-01

A general discussion of HTGR technical and safety-related problems is given. The broad areas of current research programs specific to the Fort St. Vrain reactor and applicable to HTGR technology are summarized

Canister storage building compliance assessment SNF project NRC equivalency criteria - HNF-SD-SNF-DB-003

International Nuclear Information System (INIS)

BLACK, D.M.

1999-01-01

This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria - HNF-SD-SNF-DE-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown. The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion

Nuclear plant aging research program activities

International Nuclear Information System (INIS)

Eissenberg, D.M.

1986-01-01

The objective of this program is to provide recommendations for use by NRC regarding the availability and capability of diagnostic methods for assuring the operational readiness of NPP safety systems and components

Disposition of recommendations of the National Research Council in the report ''Revitalizing Nuclear Safety Research''

International Nuclear Information System (INIS)

1988-06-01

On December 8, 1986, the Committee on Nuclear Safety Research of the National Research Council submitted its report, ''Revitalizing Nuclear Safety Research,'' to the US Nuclear Regulatory Commission (NRC). The Commission and its staff have carefully reviewed the Committee's report and have extensively examined the planning, implementation, and management of NRC research programs in order to respond most effectively to the Committee's recommendations. This report presents the Commission's view of the Committee's report and describes the actions that are under way in response to its recommendations

Review of NRC Regulatory processes and functions

International Nuclear Information System (INIS)

1980-01-01

The Advisory Committee on Reactor Safeguards (ACRS) has spent much time over many years observing and examining the NRC licensing process. The Committee is, consequently, in a position to comment on the situation, and it believes this review will be helpful to those examining the regulatory process by discussing how it works, where it is weak, and the opportunities for improvement. The Committee's review may also help put current proposals and discussions in perspective

Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

International Nuclear Information System (INIS)

Garvin, L.J.

1995-11-01

This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement

NRC levies $62 100 fee for FY 1993 on all licensees

International Nuclear Information System (INIS)

Anon.

1993-01-01

The Nuclear Regulatory Commission has issued its final rule on fee collections for fiscal year 1993, partly in response to a court decision that challenged the agency's FY 1991 fee schedule. Because the NRC must recover all of its annual budget - in excess of $500 million - through fees on licensees and users of agency services, those licensees and users are very sensitive about who shoulders how much of the burden. The new rule voids the previous NRC policy of exempting nonprofit educational institutions from the fee schedule, and the allocation of generic costs for low-level waste management to groups of licensees, rather than to individual licensees. The new rule went into effect on August 19

MHTGR demonstration role in the NRC design certification process

International Nuclear Information System (INIS)

Kelley, A.P. Jr.; Jones, G.

1986-01-01

A modular high-temperature gas-cooled reactor (MHTGR) design is being developed by the US HTGR Program. Because of the small size of the individual modules that would make up a commercial facility, it appears feasible to design and construct a single-module demonstration plant within the funding constraints on the public and private-sector program participants. Furthermore, the safety margins that can be made inherent to the design permit full-scale testing that could supply a new basis for demonstrating investment protection and safety adequacy to the public, the US Nuclear Regulatory Commission (NRC), and potential users. With this in mind, a Project Definition Study was sponsored by Gas-Cooled Reactor Associates and the Tennessee Valley Authority to study the potential benefits of undertaking such a demonstration project. One of the areas investigated was the potential benefits of such a facility in supporting the NRC design certification process, which is envisioned as a necessary commercialization step for the MHTGR

NRC staff review of licensee responses to pressure-locking and thermal-binding issue

Energy Technology Data Exchange (ETDEWEB)

Rathbun, H.J.

1996-12-01

Commercial nuclear power plant operating experience has indicated that pressure locking and thermal binding represent potential common mode failure mechanisms that can cause safety-related power-operated gate valves to fail in the closed position, thus rendering redundant safety-related systems incapable of performing their safety functions. In Generic Letter (GL) 95-07, {open_quotes}Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves,{close_quotes} the U.S. Nuclear Regulatory Commission (NRC) staff requested that nuclear power plant licensees take certain actions to ensure that valves susceptible to pressure locking or thermal binding are capable of performing their safety functions within the current licensing bases of the facility. The NRC staff has received summary information from licensees in response to GL 95-07 describing actions they have taken to prevent the occurrence of pressure locking and thermal binding. The NRC staff has developed a systematic process to help ensure uniform and consistent review of licensee submittals in response to GL 95-07.

Pilot program: NRC severe reactor accident incident response training manual. Overview and summary of major points

International Nuclear Information System (INIS)

McKenna, T.J.; Martin, J.A. Jr.; Giitter, J.G.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Watkins

1987-02-01

Overview and Summary of Major Points is the first in a series of volumes that collectively summarize the U.S. Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assessment. Other volumes in the series are: Volume 2-Severe Reactor Accident Overview; Volume 3- Response of Licensee and State and Local Officials; Volume 4-Public Protective Actions-Predetermined Criteria and Initial Actions; Volume 5 - U.S. Nuclear Regulatory Commission. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. The volumes have been organized into these training modules to accommodate the scheduling and duty needs of participating NRC staff. Each volume is accompanied by an appendix of slides that can be used to present this material

NRC safety research in support of regulation

International Nuclear Information System (INIS)

1994-06-01

This report, the ninth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1993. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with sound technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission's rules, regulatory guides, or other guidance

Scientific activities 1979

International Nuclear Information System (INIS)

1981-01-01

The scientific activities and achievements of the Nuclear Research Center Democritus for the year 1979 are presented in the form of a list of 78 projects giving title, objectives, commencement year, responsible of each project, developed activities and the pertaining lists of publications. The 15 chapters of this work cover the activities of the main Divisions of the Democritus NRC: Electronics, Biology, Physics, Chemistry, Health Physics, Reactor, Radioisotopes, Environmental Radioactivity, Soil Science, Computer Center, Uranium Exploration, Medical Service, Technological Applications and Training. (T.A.)

Compilation of fastener testing data received in response to NRC Compliance Bulletin 87-02

International Nuclear Information System (INIS)

Cwalina, G.C.; Conway, J.T.; Parker, L.B.

1989-06-01

On November 6, 1987, the Nuclear Regulatory Commission (NRC) issued Bulletin 87-02, ''Fastener Testing to Determine Conformance With Applicable Material Specifications,'' to all holders of operating licenses or construction permits for nuclear power reactors (licensees). The bulletin was issued so that the NRC staff could gather data to determine whether counterfeit fasteners are a problem in the nuclear power industry. The bulletin requested nuclear power plant owners to determine whether fasteners obtained from suppliers and/or manufacturers for use in their facilities meet the mechanical and chemical specifications stipulated in the procurement documents. The licensees were requested to sample a minimum of 10 safety-related and 10 non-safety-related fasteners (studs, bolts, and/or cap screws) and a sample of typical nuts that would be used with each fastener and to report the testing results to the NRC. The results of this study did not indicate a safety concern relating to the use of mismarked or counterfeit fasteners in the nuclear industry, but they did indicate a nonconformance rate of 8 to 12 percent for fasteners. The NRC staff is considering taking action to improve the effectiveness of receipt inspection and testing programs for all materials at nuclear power plants

The development of the advanced cryogenic radiometer facility at NRC

Science.gov (United States)

Gamouras, A.; Todd, A. D. W.; Côté, É.; Rowell, N. L.

2018-02-01

The National Research Council (NRC) of Canada has established a next generation facility for the primary realization of optical radiant power. The main feature of this facility is a new cryogenic electrical substitution radiometer with a closed-cycle helium cryocooler. A monochromator-based approach allows for detector calibrations at any desired wavelength. A custom-designed motion apparatus includes two transfer standard radiometer mounting ports which has increased our measurement capability by allowing the calibration of two photodetectors in one measurement cycle. Measurement uncertainties have been improved through several upgrades, including newly designed and constructed transimpedance amplifiers for the transfer standard radiometers, and a higher power broadband light source. The most significant improvements in uncertainty arise from the enhanced characteristics of the new cryogenic radiometer including its higher cavity absorptance and reduced non-equivalence effects.

NRC licensing requirements: DOD options

International Nuclear Information System (INIS)

Pike, W.J.; O'Reilly, P.D.

1982-09-01

This report describes the licensing process (both safety and environmental) that would apply if the Department of Defense (DOD) chooses to obtain licenses from the US Nuclear Regulatory Commission (NRC) for using nuclear energy for power and luminous sources. The specific nuclear energy sources being considered include: small or medium-size nuclear power reactors; radioisotopic thermoelectric generators with 90 Sr or 238 Pu; radioisotopic dynamic electric generators with 90 Sr or 238 Pu; and applications of radioisotopes for luminous sources (lights) with 3 H, 85 Kr, or 147 Pm. The steps of the licensing process are summarized in the following sections, with particular attention given to the schedule and level of effort necessary to support the process

Low-level mixed waste: An RCRA perspective for NRC licensees

International Nuclear Information System (INIS)

1990-08-01

The publication presents an overview of RCRA requirements for commercially-generated low-level mixed waste. It is designed for Nuclear Regulatory Commission (NRC) licensees who may not be familiar with EPA regulations that apply to their waste products

Evaluation of NRC maintenance team inspection reports for managing aging

International Nuclear Information System (INIS)

Fresco, A.; Gunther, W.

1991-01-01

A nuclear power plant's maintenance program is the principal vehicle through which age-related degradation is managed. Over the past two years, the NRC [Nuclear Regulatory Commission] has evaluated the maintenance program of every nuclear power plant in the U.S. The reports issued on these in-depth team inspections have been reviewed to ascertain the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear power plant systems, structures, and components. Selected results of this review are presented in this paper, including examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue are also discussed. 6 refs., 1 tab

Small Business Innovation Research Program. Program solicitation FY 1984

International Nuclear Information System (INIS)

1984-01-01

The Nuclear Regulatory Commission (NRC) invites science-based and high-technology small business firms to submit research proposals under this program solicitation entitled Small Business Innovation Research (SBIR). Firms with strong research capabilities in science or engineering in any of the following topic areas are encouraged to participate. NRC will support high-quality research proposals on important scientific or engineering problems and opportunities that could lead to significant advancement in the safety of nuclear operations or nuclear power plants. Objectives of the solicitation include stimulating technological innovation in the private sector, strengthening the role of small business in meeting Federal research and development needs, increasing the commercial application of NRC-supported research results, and improving the return on investment from Federally funded research for economic and social benefits to the Nation

Potential low-level waste disposal limits for activation products from fusion

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Peloquin, R.A.

1983-09-01

Hanford Engineering Development Laboratory (HEDL) scientists are involved in studies considering alternative construction materials for the first wall of commercial fusion reactors. To permit a comparison of radioactivity levels, both the level of activation and an acceptable limit for the radionuclides present must be known. Generic material composition guidelines can be developed using the US Nuclear Regulatory Commission (NRC) regulations governing the near-surface disposal of low-level radioactive wastes. These regulations consider wastes defined as containing source, special nuclear, or by-product materials arising from research, industrial, medical, and nuclear fuel-cycle activities. However, not all of the activation products produced in low-level wastes from fusion reactors are considered by the NRC in their regulations. The purpose of this report is to present potential low-level waste-disposal limits for ten radionuclides resulting from fusion reactor operations that are not considered in the NRC low-level waste regulations. These potential limits will be used by HEDL scientists to complete their generic material composition guidelines for the first wall of commercial fusion reactors

NRC Information Notice No. 91-29, Supplement 1: Deficiencies identified during electrical distribution system functional inspections

International Nuclear Information System (INIS)

Rossi, C.E.

1993-01-01

During multidiscipline inspections such as safety system functional inspections (SSFIs) or safety system outage modification inspections (SSOMIs), the NRC identified a number of deficiencies related to the electrical distribution system (EDS). As a result of these deficiencies, the NRC developed the EDSFI to specifically evaluate the EDS. Since 1989, the NRC has performed over 50 EDSFIs, and found design weaknesses in the following generic areas: (1) undervoltage relay setpoints for degraded grid conditions; (2) interrupting capacity of fault protection devices; (3) improper coordination of fault protection devices; (4) analysis of emergency diesel generator (EDG) capacity to power safety-related loads during postulated accidents; and (5) EDG mechanical interfaces. Each of these issues are discussed

Nuclear Security: Action May Be Needed to Reassess the Security of NRC-Licensed Research Reactors. Report to the Ranking Member, Subcommittee on National Security and Foreign Affairs, Committee on Oversight and Government Reform, House of Representatives. GAO-08-403

Science.gov (United States)

Aloise, Gene

2008-01-01

There are 37 research reactors in the United States, mostly located on college campuses. Of these, 33 reactors are licensed and regulated by the Nuclear Regulatory Commission (NRC). Four are operated by the Department of Energy (DOE) and are located at three national laboratories. Although less powerful than commercial nuclear power reactors,…

NRC/AMRMC Resident Research Associateship Program

Science.gov (United States)

2015-03-01

provided the administrative functions described in the contract Statement of Work. These functions included stipend payments, management of a major...Pain Management Clinic, focus on translational work from bench to bedside, clinical research involving opioid use and long term outcomes 2 Developed...They invited me to share American Holidays with them, like Thanksgiving, so that I had the possibility to experience traditions along with culinary

Stakeholder confidence in effective safety regulation. A regulator's view on the role of independent research capability

International Nuclear Information System (INIS)

Kotra, Janet; Mohanty, Sitakanto

2006-01-01

Analyses (CNWRA) as a conflict-free body of experts to assist the NRC in making independent judgements about the safety case of the nation's first geological repository for high-level radioactive waste. The CNWRA supports the NRC's regulatory mission with a wide range of independent technical expertise, computers, laboratories and field research. In addition to providing broad technical support to the NRC, CNWRA experts support the NRC's public meetings, open houses and other public outreach activities, assisting with the identification of key technical concepts and plain language communications concerning research findings and limitations. NRC sought to create a centre that would provide expertise that: - is competent, employing recognized experts, scientists and engineers, with in-depth knowledge of the scientific and technical issues related to the potential repository at Yucca Mountain; - is independent of the DOE, free from any potential conflict of interest, or appearance of such conflicts; - assures long-term continuity of technical support and the maintenance of corporate memory of the evolution of repository safety and regulatory issues; and - complements NRC's skill sets, avoiding gaps and overlaps in expertise between the NRC and CNWRA. NRC's reliance on independent expertise will assist in conveying to stakeholders that the NRC is able to challenge DOE assumptions and assertions and arrive at objective conclusions about the safety of the potential repository

Development of RESRAD probabilistic computer codes for NRC decommissioning and license termination applications

International Nuclear Information System (INIS)

Chen, S. Y.; Yu, C.; Mo, T.; Trottier, C.

2000-01-01

In 1999, the US Nuclear Regulatory Commission (NRC) tasked Argonne National Laboratory to modify the existing RESRAD and RESRAD-BUILD codes to perform probabilistic, site-specific dose analysis for use with the NRC's Standard Review Plan for demonstrating compliance with the license termination rule. The RESRAD codes have been developed by Argonne to support the US Department of Energy's (DOEs) cleanup efforts. Through more than a decade of application, the codes already have established a large user base in the nation and a rigorous QA support. The primary objectives of the NRC task are to: (1) extend the codes' capabilities to include probabilistic analysis, and (2) develop parameter distribution functions and perform probabilistic analysis with the codes. The new codes also contain user-friendly features specially designed with graphic-user interface. In October 2000, the revised RESRAD (version 6.0) and RESRAD-BUILD (version 3.0), together with the user's guide and relevant parameter information, have been developed and are made available to the general public via the Internet for use

78 FR 29159 - Electric Power Research Institute; Seismic Evaluation Guidance

Science.gov (United States)

2013-05-17

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0038] Electric Power Research Institute; Seismic... U.S. Nuclear Regulatory Commission (NRC) is issuing an endorsement letter of Electric Power Research... Fukushima Dai-ichi nuclear power plant in March 2011. Enclosure 1 to the 50.54(f) letter requests licensees...

Validação das equações do NRC (2001 para predição do valor energético de alimentos nas condições brasileiras Validation of NRC (2001 equations for estimation of energy value of feeds in Brazilian conditions

Directory of Open Access Journals (Sweden)

Marcos Antonio Lana Costa

2005-02-01

Full Text Available O estudo foi conduzido para estimar os valores energéticos (NDT de vários alimentos, concentrados e volumosos e validar as equações propostas pelo NRC (2001 por meio da comparação dos valores estimados por estas equações, com os observados, obtidos a partir da coleta total de fezes. Foram avaliados cinco alimentos concentrados (farelo de trigo, farelo de soja, fubá de milho, grão de soja e caroço de algodão e cinco volumosos (feno de capim-braquiária, silagem de milho, silagem pré-seca de capim-tifton, silagem de capim-elefante e capim-elefante utilizando-se 20 novilhos mestiços HolandêsxZebu. O procedimento de validação das variáveis avaliadas foi realizado por intermédio do ajuste do modelo de regressão linear simples dos valores preditos e observados. Os valores de NDT dos alimentos concentrados e volumosos observados e preditos pelas equações do NRC (2001 foram similares (P>0,05. Conclui-se que as equações do NRC (2001 foram adequadas para estimar o valor energético dos alimentos nas condições brasileiras.This research was developed to estimate the energy values (TDN of feeds, concentrate and roughage, through equations proposed by NRC (2001 and validate from the comparison among TDN values estimated by these equations and those observed in the total collection feces. Five concentrate feeds (wheat bran, soybean meal, corn ground, whole soybean and whole cotton seed an five roughage feeds (brachiaria hay, corn silage, tifton haylage, elephant grass silage and elephantgrass were evaluated by using 20 crossbred Holstein x Zebu steers. The procedure to validate the variables evaluated was done by adjusting models of simple linear regression using predicted and observed values. The observed and predicted value of TDN values for roughage and concentrate feeds were similar (P>0,05. It was concluded that the equations proposed by NRC (2001 were efficient to estimate the TDN values of feeds under brazilian conditions.

Uncertainty Methods Framework Development for the TRACE Thermal-Hydraulics Code by the U.S.NRC

International Nuclear Information System (INIS)

Bajorek, Stephen M.; Gingrich, Chester

2013-01-01

well defined. For example, in some new designs the regulatory figure of merit (FOM) has been the reactor vessel level rather than PCT or MLO. Thus, the methods developed by the NRC must be capable of being used for a wide range of plant designs and potential FOMs. Development and selection of an uncertainty methodology for the NRC was based on a review of available methods and a set of criteria considered important to agency goals and objectives. The criteria included regulatory acceptance of the statistical method, feasibility of implementation, extensibility of the methodology, ease of use and effort to perform analyses, and the effort to implement the methodology. Based on these criteria, an overall approach consistent with Code, Scaling, Applicability and Uncertainty (CSAU) but using order statistics is being adopted. To implement the methodology in an efficient manner, the Symbolic Nuclear Analysis Package (SNAP) has been modified to perform a Monte Carlo sampling of code input parameters, submit multiple cases for execution, and statistically evaluate the results. SNAP performs the statistical analysis using DAKOTA (Design and Analysis Tool-kit for Optimization and Tera-scale Applications), which is a code developed by the SANDIA national laboratories specifically for sensitivity and uncertainty analyses. This paper outlines the NRC approach to uncertainty, describes the tools and activities in progress, and presents the rationale for several decisions. (authors)

NRC/AMRMC Resident Research Associateship Program

Science.gov (United States)

2017-04-01

workshops and advertised in meeting literature, newsletters and websites or submitted materials for distribution. In addition, ads were placed in a...item follows: 9.8 Short-term value (lab)-Development of knowledge, skills, and research productivity at lab 9.7 Long-term value (career)-How your...REPORT 1) Associate Last or Family Name Cohen First Name Courtney M.I. A 2) FORWARDING Address (to which your tax statement will be mailed) Residence

Purification and characterization of gamma poly glutamic acid from newly Bacillus licheniformis NRC20.

Science.gov (United States)

Tork, Sanaa E; Aly, Magda M; Alakilli, Saleha Y; Al-Seeni, Madeha N

2015-03-01

γ-poly glutamic acid (γ-PGA) has received considerable attention for pharmaceutical and biomedical applications. γ-PGA from the newly isolate Bacillus licheniformis NRC20 was purified and characterized using diffusion distance agar plate, mass spectrometry and thin layer chromatography. All analysis indicated that γ-PGA is a homopolymer composed of glutamic acid. Its molecular weight was determined to be 1266 kDa. It was composed of L- and D-glutamic acid residues. An amplicon of 3050 represents the γ-PGA-coding genes was obtained, sequenced and submitted in genbank database. Its amino acid sequence showed high similarity with that obtained from B. licheniformis strains. The bacterium NRC 20 was independent of L-glutamic acid but the polymer production enhanced when cultivated in medium containing L-glutamic acid as the sole nitrogen source. Finally we can conclude that γ-PGA production from B. licheniformis NRC20 has many promised applications in medicine, industry and nanotechnology. Copyright © 2014 Elsevier B.V. All rights reserved.

Managing aging in nuclear power plants: Insights from NRC's maintenance team inspection reports

International Nuclear Information System (INIS)

Fresco, A.; Subudhi, M.

1994-01-01

Age-related degradation is managed through the maintenance program of a nuclear plant. From 1988 to 1991, the Nuclear Regulatory Commission (NRC) evaluated the maintenance program of every nuclear power plant in the United States. The authors reviewed 44 out of a total of 67 of the reports issued by the NRC on these in-depth team inspections. The reports were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components. The authors' conclusions are presented. 6 refs

NRC licensing of uranium enrichment plants

International Nuclear Information System (INIS)

Moran, B.W.

1991-01-01

The US Nuclear Regulatory Commission (NRC) is preparing a rule making that establishes the licensing requirements for low-enriched uranium enrichment plants. Although implementation of this rule making is timed to correspond with receipt of a license application for the Louisiana Energy Services centrifuge enrichment plant, the rule making is applicable to all uranium enrichment technologies. If ownership of the US gaseous diffusion plants and/or atomic vapor laser isotope separation is transferred to a private or government corporation, these plants also would be licensable under the new rule making. The Safeguards Studies Department was tasked by the NRC to provide technical assistance in support of the rule making and guidance preparation process. The initial and primary effort of this task involved the characterization of the potential safeguards concerns associated with a commercial enrichment plant, and the licensing issues associated with these concerns. The primary safeguards considerations were identified as detection of the loss of special nuclear material, detection of unauthorized production of material of low strategic significance, and detection of production of uranium enriched to >10% 235 U. The primary safeguards concerns identified were (1) large absolute limit of error associated with the material balance closing, (2) the inability to shutdown some technologies to perform a cleanout inventory of the process system, and (3) the flexibility of some technologies to produce higher enrichments. Unauthorized production scenarios were identified for some technologies that could prevent conventional material control and accounting programs from detecting the production and removal of 5 kg 235 U as highly enriched uranium. Safeguards techniques were identified to mitigate these concerns

NRC policy on future reactor designs

International Nuclear Information System (INIS)

1985-07-01

On April 13, 1983, the US Nuclear Regulatory Commission issued for public comment a ''Proposed Commission Policy Statement on Severe Accidents and Related Views on Nuclear Reactor Regulation'' (48 FR 16014). This report presents and discusses the Commission's final version of that policy statement now entitled, ''Policy Statement on Severe Reactor Accidents Regarding Future Designs and Existing Plants.'' It provides an overview of comments received from the public and the Advisory Committee on Reactor Safeguards and the staff response to these. In addition to the Policy Statement, the report discusses how the policies of this statement relate to other NRC programs including the Severe Accident Research Program; the implementation of safety measures resulting from lessons learned in the accident at Three Mile Island; safety goal development; the resolution of Unresolved Safety Issues and other Generic Safety Issues; and possible revisions of rules or regulatory requirements resulting from the Severe Accident Source Term Program. Also discussed are the main features of a generic decision strategy for resolving Regulatory Questions and Technical Issues relating to severe accidents; the development and regulatory use of new safety information; the treatment of uncertainty in severe accident decision making; and the development and implementation of a Systems Reliability Program for both existing and future plants to ensure that the realized level of safety is commensurate with the safety analyses used in regulatory decisions

PWR and BWR anticipated and abnormal plant transient research sponsored by the US Nuclear Regulatory Commission

International Nuclear Information System (INIS)

Beckner, W.D.; Sullivan, L.H.

1984-01-01

This chapter reviews the regulatory activities of the US NRC since the realization that anticipated transients with multiple failures (including operator actions) are the major contributors to risk from reactor operations and that the low probability design basis accidents (DBA) are relatively small contributors to risk. The Three Mile Island-2 accident demonstrated that anticipated transients, combined with multiple equipment and/or operator failures, can result in significant core damage. Topics considered include research in direct response to Three Mile Island-2, research in response to specific safety issues, and research to improve the overall understanding of transients (experimental facilities, computer codes). It is concluded that the US NRC has made significant progress in improving its ability to analyze and evaluate abnormal and anticipated transients

Verification of self-report of zygosity determined via DNA testing in a subset of the NAS-NRC twin registry 40 years later.

Science.gov (United States)

Reed, Terry; Plassman, Brenda L; Tanner, Caroline M; Dick, Danielle M; Rinehart, Shannon A; Nichols, William C

2005-08-01

The National Academy of Sciences -- National Research Council (NAS-NRC) twin panel, created nearly 50 years ago, had twin zygosity determined primarily via a similarity questionnaire that has been estimated to correctly classify at least 95% of twins. In the course of a study on the genetics of healthy ageing in the NAS-NRC twins, DNA was collected for genome-wide scanning and zygosity confirmation was examined in 343 participating pairs. The sample was supplemented from two other studies using NAS-NRC twins where one or both co-twins were suspected to have Alzheimer disease or another dementia, or Parkinson's disease. Overall 578 twin pairs with DNA were analyzed. Zygosity assignment for 96.8% (519/536) was confirmed via questionnaire. Among 42 pairs whose questionnaire responses were inconclusive for assigning zygosity, 50% were found to be monozygous (MZ) and 50% were dizygous (DZ). There was some evidence for greater misclassification of presumed DZ pairs in the healthy ageing study where participation favored pairs who were similar in having a favorable health history and willingness to volunteer without any element of perceived risk for a specific disease influencing participation.

The NRC and utility finances

International Nuclear Information System (INIS)

Byus, L.C.

1992-01-01

In a speech before the National Association of Regulatory Utility Commissioners in November 1991, Nuclear Regulatory Commission Chairman Ivan Selin presented what he called an open-quotes expansion of the concept of safety beyond our previous narrow bounds.close quotes He went on to explain, open-quotes To be seen as successful and safe operators of nuclear facilities, utilities must have safe and predictable cash flows.close quotes While there is little disagreement that the concepts of successful plant operations and financial strength go hand in hand, the relationship between the two is not clear. Which came first, successful operation of generating plants or financial strength? Selin's views on NRC involvement in financial aspects of utility operation in the United States are sure to stimulate debate on the issue

NRC Enforcement Policy Review, July 1995-July 1997

International Nuclear Information System (INIS)

Lieberman, J.; Pedersen, R.M.

1998-04-01

On June 30, 1995, the Nuclear Regulatory Commission (NRC) issued a complete revision of its General Statement of Policy and Procedure for Enforcement Action (Enforcement Policy) (60 FR 34381). In approving the 1995 revision to the Enforcement Policy, the Commission directed the staff to perform a review of its implementation of the Policy after approximately 2 years of experience and to consider public comments. This report represents the results of that review

National Research Council Research Associateships Program with Methane Hydrates Fellowships Program/National Energy Technology Laboratory

Energy Technology Data Exchange (ETDEWEB)

Basques, Eric O. [National Academy of Sciences, Washington, DC (United States)

2014-03-20

This report summarizes work carried out over the period from July 5, 2005-January 31, 2014. The work was carried out by the National Research Council Research Associateships Program of the National Academies, under the US Department of Energy's National Energy Technology Laboratory (NETL) program. This Technical Report consists of a description of activity from 2005 through 2014, broken out within yearly timeframes, for NRC/NETL Associateships researchers at NETL laboratories which includes individual tenure reports from Associates over this time period. The report also includes individual tenure reports from associates over this time period. The report also includes descriptions of program promotion efforts, a breakdown of the review competitions, awards offered, and Associate's activities during their tenure.

Chemical countermeasures: Dispersants overview of dispersant use (including application) and research issues

International Nuclear Information System (INIS)

Butler, J.N.

1992-01-01

I will attempt in twenty minutes to summarize the state of research on oil spill dispersants as I perceive it. The expertise I bring to this task includes 20 years of experience with the fate and effects of petroleum in the marine environment, including participation in the 1973 and 1981 NRC studies and three years as chairman of the NRC committee on oil spill dispersants. I More recently I served on a committee of the International Maritime Organization which reviewed the open-quotes Impact of oil and related chemicals and wastes on the marine environment.close quotes That report will be published this year. However, my statements in this paper are not made as a representative of either NRC or IMO. They are my own interpretation of scientific literature cited in the above reviews. Dispersants are chemical formulations, which include surface active agents, designed to decrease the interfacial tension between oil and water. Because the first attempts to disperse oil on a large scale, at the Torrey Canyon spill of 1967, used highly toxic degreasing agents, dispersants have an undeserved reputation for toxicity. In fact, for twenty years dispersant formulations have been developed with an emphasis on reducing their toxicity to marine life. The dispersal of oil in water has been documented in the laboratory by dozens of papers (see references in NRC 1989, pp 70-79), and in the field by dozens of studies (NRC 1989, pp 165- 193). The toxicity of commercial dispersant formulations (NRC 1989, pp 81-123) and dispersed oil (NRC 1989, pp 123-147) has been tested on a wide variety of marine organisms ranging from algae to salmonid fishes. The NRC review has been updated by the IMO/GESAMP (1992) study, but the conclusions remain unchanged

Funding for reactor decommissioning: the NRC perspective

International Nuclear Information System (INIS)

Wood, R.S.

1981-01-01

The cost of decommissioning a nuclear power plant is discussed. Four funding approaches that have received the most attention from the NRC are: prepayment into a trust fund of estimated decommissioning funds at the start of facility operation; annual contributions into a trust fund outside the control of the utility over the estimated life of a facility; internal reserve or sinking fund amortizations over the estimated life of a facility; and insurance or other surety mechanisms used separately or in conjunction with any of the first three mechanisms

Continuing the Conversation: Development of the U.S. NRC's Definition of Safety Culture and its Traits

International Nuclear Information System (INIS)

Barnes, Valerie; Koves, Ken

2012-01-01

Val Barnes gave a presentation on behalf of the US NRC and INPO. She summarised the work done by the US NRC to develop the US NRC Policy on Safety Culture. Stakeholder representatives were involved in panel sessions to develop a common definition of safety culture and define the traits of a positive safety culture. A survey-based validation study of the eight traits identified through the panel sessions was then conducted across the 63 US nuclear sites by INPO. The INPO study also examined the correlations between the safety culture traits and safety performance. Strong correlations were found for some factors (for example, the number of unplanned scrams correlated strongly with perceptions on management responsibility). The results of the survey supported the inclusion of an additional safety culture trait (questioning attitude) resulting in the following nine traits: - Leadership Safety Values and Actions. - Problem Identification and Resolution. - Personal Accountability. - Work Process. - Continuous Learning. - Environment for Raising Concerns. - Effective Safety Communication. - Respectful Work Environment. - Questioning Attitude. The US NRC has also issued a safety culture policy statement which provides the following definition: 'Nuclear safety culture is the core values and behaviors resulting from a collective commitment by leaders and individuals to emphasize safety over competing goals to ensure protection of people and the environment'. The US NRC and its regulated communities are now working on implementing the policy statement. It was concluded that the work carried out to develop the safety culture policy statement has helped to develop a common language and understanding amongst stakeholders

75 FR 6063 - Availability of NRC Open Government Web Site

Science.gov (United States)

2010-02-05

... ( http://www.nrc.gov/open ) will be available by February 6, 2010, and directs that, after February 10... http://www.regulations.gov Web site. FOR FURTHER INFORMATION CONTACT: James B. Schaeffer, Deputy..., 2010, and provided options for submitting comments by mail, fax, or at http://www.regulations.gov , but...

Essential and non-essential DNA replication genes in the model halophilic Archaeon, Halobacterium sp. NRC-1

Directory of Open Access Journals (Sweden)

DasSarma Shiladitya

2007-06-01

Full Text Available Abstract Background Information transfer systems in Archaea, including many components of the DNA replication machinery, are similar to those found in eukaryotes. Functional assignments of archaeal DNA replication genes have been primarily based upon sequence homology and biochemical studies of replisome components, but few genetic studies have been conducted thus far. We have developed a tractable genetic system for knockout analysis of genes in the model halophilic archaeon, Halobacterium sp. NRC-1, and used it to determine which DNA replication genes are essential. Results Using a directed in-frame gene knockout method in Halobacterium sp. NRC-1, we examined nineteen genes predicted to be involved in DNA replication. Preliminary bioinformatic analysis of the large haloarchaeal Orc/Cdc6 family, related to eukaryotic Orc1 and Cdc6, showed five distinct clades of Orc/Cdc6 proteins conserved in all sequenced haloarchaea. Of ten orc/cdc6 genes in Halobacterium sp. NRC-1, only two were found to be essential, orc10, on the large chromosome, and orc2, on the minichromosome, pNRC200. Of the three replicative-type DNA polymerase genes, two were essential: the chromosomally encoded B family, polB1, and the chromosomally encoded euryarchaeal-specific D family, polD1/D2 (formerly called polA1/polA2 in the Halobacterium sp. NRC-1 genome sequence. The pNRC200-encoded B family polymerase, polB2, was non-essential. Accessory genes for DNA replication initiation and elongation factors, including the putative replicative helicase, mcm, the eukaryotic-type DNA primase, pri1/pri2, the DNA polymerase sliding clamp, pcn, and the flap endonuclease, rad2, were all essential. Targeted genes were classified as non-essential if knockouts were obtained and essential based on statistical analysis and/or by demonstrating the inability to isolate chromosomal knockouts except in the presence of a complementing plasmid copy of the gene. Conclusion The results showed that ten

Report of the CIRRPC Executive Committee regarding EPA NESHAP regulations on radionuclides for medical research institutions and radiopharmaceutical manufacturers

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-06-01

There appears to be no compelling public health protection reason for EPA`s promulgation of NESHAP regulations to control air emissions of radioactive materials from NRC-licensed facilities engaged in activities associated with the practice and development of nuclear medicine. The NRC`s existing regulations provide the necessary controls for protection and EPA`s regulations would only add burdensome reporting requirements at substantial cost to medical treatment and diagnosis. Availability of nuclear medicine practice could be impacted and advancements through research delayed.

Overview of severe accident research at the USNRC

International Nuclear Information System (INIS)

Basu, S.; Ader, C.E.

1999-01-01

This paper summarizes the U.S. Nuclear Regulatory Commission's (USNRC) severe accident research activities, in particular, progress made in the past year toward the resolution and/or improved understanding of a number of severe accident issues. The direct containment heating (DCH) is nearing resolution for Combustion Engineering and Babcock and Wilcox type pressurized water reactors (PWRs) are well as for ice condensers. Additionally, two lower pressure DCH tests were conducted recently at the Sandia National Laboratories (SNL) under the NRC/IPSN/FzK sponsorship to provide data regarding intentional depressurization as an accident management strategy to mitigate DCH loads. In the area of lower head integrity, the experimental program to investigate boiling heat transfer on downward facing curved surfaces with insulation was completed. Finally, the SNL program investigating the creep rupture behavior of the lower head under the combined thermo-mechanical loading was completed recently. Additional lower head experiments at SNL are being planned as an OECD project. During the past year, the USNRC participated in two programs aimed at extending the data base on hydrogen combustion into more prototypic situations. Testing was performed at the Brookhaven National Laboratory (BNL) to investigate detonation transmission at elevated temperatures. In a cooperative program under the sponsorship of NRC/IPSN/FzK, Russian Research Center (RRC) investigated hydrogen combustion issues at large scale at the RUT facility. The experimental program at the SNL to examine the performance of Passive Autocatalytic Recombiners (PARs) was completed also this year. In the fuel-coolant interaction (FCI) area, the experimental work at the Argonne National Laboratory (ANL) to investigate chemical augmentation of FCI energetics was completed as was the experimental work at the University of Wisconsin (UW) involving one-dimensional propagation experiments (similar to KROTOS). The USNRC is

Web-based training related to NRC staff review of dose modeling aspects of license termination and decommissioning plans

International Nuclear Information System (INIS)

LePoire, D.; Arnish, J.; Cheng, J.J.; Kamboj, S.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

2007-01-01

final status surveys are addressed in the WBT. Realistic case examples are presented and analyzed including the abstraction of a realistic site into a conceptual model and computer model. A case history is also used to demonstrate development of NRC review documents such as requests for additional information (RAIs). To enhance the web-based training experience, audio, animations, linked documents, quizzes, and scripts are being integrated with a commercial web-based training package that supports simple navigation. The course is also being integrated into both existing and state-of-the-art learning management systems. A testing group is being utilized to identify and help resolve training issues prior to deployment of the course. When completed, the course can be accessed for credited training with required modules dependent on the job category of the training participant. The modules will also be accessible to NRC staff for review or refresher following initial course completion. WBT promotes consistency in reviews and has the advantage of being able to be used as a resource to staff at any time. The WBT provides reviewers with knowledge needed to perform risk-informed analyses (e.g., information related to development of realistic scenarios and use of probabilistic analysis). WBT on review of LTP or DP dose modeling promotes staff development, efficiency, and effectiveness in performing risk-informed, performance-based reviews of decommissioning activities at NRC-licensed facilities.

Safeguards Summary Event List (SSEL), pre-NRC through December 31, 1982

International Nuclear Information System (INIS)

1983-08-01

This document represents a revision of the list published December 1980 of safeguards-related events involving NRC licensees and licensed material. It summarizes events occurring between June 30, 1982 and December 31, 1982. Editorial changes to earlier pages are also included

U.S. NRC's generic issues program

International Nuclear Information System (INIS)

Kauffman, J.V.; Foster, J.W.

2008-01-01

The United States Nuclear Regulatory Commission (NRC) has a Generic Issues Program (GIP) to address Generic Issues (GI). A GI is defined as 'a regulatory matter involving the design, construction, operation, or decommissioning of several, or a class of, NRC licensees or certificate holders that is not sufficiently addressed by existing rules, guidance, or programs'. This rather legalistic definition has several practical corollaries: First, a GI must involve safety. Second, the issue must involve at least two plants, or it would be a plant-specific issue rather than a GI. Third, the potential safety question must not be covered by existing regulations and guidance (compliance). Thus, the effect of a GI is to potentially change the body of regulations and associated guidance (e.g., regulatory guides). The GIP was started in 1976, thus it is a relatively mature program. Approximately 850 issues have been processed by the program to date. More importantly, even after 30 years, new GIs continue to be proposed. The entire set of Generic Issues (GIs) is updated annually in NUREG-0933, 'A Prioritization of Generic Safety Issues'. GIs normally involve complex questions of safety and regulation. Efficient and effective means of addressing these issues are very important for regulatory effectiveness. If an issue proves to pose a genuine, significant safety question, then swift, effective, enforceable, and cost-effective action needs to be taken. Conversely, if an issue is of little safety significance, the issue should be dismissed in an expeditious manner, avoiding unnecessary expenditure of resources and regulatory burden or uncertainty. This paper provides a summary of the 5-stage program, from identification through the regulatory assessment stage. The paper also includes a discussion of the program's seven criteria, sources of proposed GIs, recent improvements, publicly available information, historical performance, and status of current GIs. (authors)

Analysis of NRC Regulatory Guide 1.21 Revision 2

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung Il; Yook, Dae Sik; Lee, Byung Soo [KINS, Daejeon (Korea, Republic of)

2015-05-15

It is essential to have a degree of uniformity in the methods used for measuring, evaluating, recording, and reporting data on radioactive material in effluents and solid wastes. For this purpose, the U.S. Nuclear Regulatory Commission (NRC) released a revised version of the Regulatory Guide 1.21 'Measuring, evaluating, and reporting radioactive material in liquid and gaseous effluents and solid waste' (revision 2) in 2009, updating the revision 1 version released in 1974. This study compares the previous revision 1 (1974) version with the revision 2 (2009) version to elaborate on the application of the guidelines to Korea. This study consists of an analysis of the 2009 Revision 2 version of the U.S. NRC Regulatory Guidelines 1.21 and an exposition of methods for its application in the domestic environment. Major revisions were made to allow for the adoption of a risk informed approach. Radionuclides with lower than 1% contribution to emission or radiation levels can be selected as principal radionuclides. Requirements for analysis of leaks and spills have been reinforced, with additional groundwater monitoring and hydrological data analysis becoming necessary.

Uranium recovery research sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory. Annual progress report, May 1982-May 1983

International Nuclear Information System (INIS)

Foley, M.G.; Opitz, B.E.; Deutsch, W.J.

1983-06-01

Pacific Northwest Laboratory (PNL) is currently conducting research for the US Nuclear Regulatory Commission (NRC) on uranium recovery process wastes for both active and inactive operations. NRC-sponsored uranium recovery research at PNL is focused on NRC regulatory responsibilities for uranium-recovery operations: license active milling and in situ extraction operations; concur on the acceptability of DOE remedial-action plans for inactive sites; and license DOE to maintain inactive sites following remedial actions. PNL's program consists of four coordinated projects comprised of a program management task and nine research tasks that address the critical technical and safety issues for uranium recovery. Specifically, the projects endeavor to find and evaluate methods to: prevent erosion of tailings piles and prevent radon release from tailings piles; evaluate the effectiveness of interim stabilization techniques to prevent wind erosion and transport of dry tailings from active piles; estimate the dewatering and consolidation behavior of slurried tailings to promote early cover placement; design a cover-protection system to prevent erosion of the cover by expected environmental stresses; reduce seepage into ground water and prevent ground-water degradation; control solution movement and reaction with ground water in in-situ extraction operations; evaluate natural and induced restoration of ground water in in-situ extraction operations; and monitor releases to the environment from uranium recovery facilities

Uranium recovery research sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory. Annual progress report, May 1982-May 1983

Energy Technology Data Exchange (ETDEWEB)

Foley, M.G.; Opitz, B.E.; Deutsch, W.J.; Peterson, S.R.; Gee, G.W.; Serne, R.J.; Hartley, J.N.; Thomas, V.W.; Kalkwarf, D.R.; Walters, W.H.

1983-06-01

Pacific Northwest Laboratory (PNL) is currently conducting research for the US Nuclear Regulatory Commission (NRC) on uranium recovery process wastes for both active and inactive operations. NRC-sponsored uranium recovery research at PNL is focused on NRC regulatory responsibilities for uranium-recovery operations: license active milling and in situ extraction operations; concur on the acceptability of DOE remedial-action plans for inactive sites; and license DOE to maintain inactive sites following remedial actions. PNL's program consists of four coordinated projects comprised of a program management task and nine research tasks that address the critical technical and safety issues for uranium recovery. Specifically, the projects endeavor to find and evaluate methods to: prevent erosion of tailings piles and prevent radon release from tailings piles; evaluate the effectiveness of interim stabilization techniques to prevent wind erosion and transport of dry tailings from active piles; estimate the dewatering and consolidation behavior of slurried tailings to promote early cover placement; design a cover-protection system to prevent erosion of the cover by expected environmental stresses; reduce seepage into ground water and prevent ground-water degradation; control solution movement and reaction with ground water in in-situ extraction operations; evaluate natural and induced restoration of ground water in in-situ extraction operations; and monitor releases to the environment from uranium recovery facilities.

NRC's limit on intake of uranium-ore dust

International Nuclear Information System (INIS)

McGuire, S.A.

1983-04-01

In 1960 the Atomic Energy Commission adopted an interim limit on the intake by inhalation of airborne uranium-ore dust. This report culminates two decades of research aimed at establishing the adequacy of that limit. The report concludes that the AEC underestimated the time that thorium-230, a constituent of uranium-ore dust, would remain in the human lung. The AEC assumed that thorium-230 in ore dust would behave like uranium with a 120-day biological half-life in the lung. This report concludes that the biological half-life is actually on the order of 1 year. Correcting the AEC's underestimate would cause a reduction in the permitted airborne concentration of uranium-ore dust. However, another factor that cancels the need for that reduction was found. The uranium ore dust in uranium mills was found to occur with very large particle sizes (10-micron activity median aerodynamic diameter). The particles are so large that relatively few of them are deposited in the pulmonary region of the lung, where they would be subject to long-term retention. Instead they are trapped in the upper regions of the respiratory tract, subsequently swallowed, and then rapidly excreted from the body through the gastrointestinal tract. The two effects are of about the same magnitude but in opposing directions. Thus the present uranium-ore dust intake limit in NRC regulations should provide a level of protection consistent with that provided for other airborne radioactive materials. The report recalculates the limit on intake of uranium-ore dust using the derived air concentrations (DAC) from the International Commission on Radiological Protection's recent Publication 30. The report concludes that the silica contained in uranium-ore dust is a greater hazard to workers than the radiological hazard

Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports

Energy Technology Data Exchange (ETDEWEB)

Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J. [Brookhaven National Lab., Upton, NY (United States)

1993-12-01

A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of 67 of the reports issued on these in-depth team inspections were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant systems, structures, and components. Relevant information was extracted from these inspection reports and sorted into several categories, including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

Assessment of US NRC fuel rod behavior codes to extended burnup

International Nuclear Information System (INIS)

Laats, E.T.; Croucher, D.W.; Haggag, F.M.

1982-01-01

The purpose of this paper is to report the status of assessing the capabilities of the NRC fuel rod performance codes for calculating extended burnup rod behavior. As part of this effort, a large spectrum of fuel rod behavior phenomena was examined, and the phenomena deemed as being influential during extended burnup operation were identified. Then, the experiment data base addressing these identified phenomena was examined for availability and completeness at extended burnups. Calculational capabilities of the NRC's steady state FRAPCON-2 and transient FRAP-T6 fuel rod behavior codes were examined for each of the identified phenomenon. Parameters calculated by the codes were compared with the available data base, and judgments were made regarding model performance. Overall, the FRAPCON-2 code was found to be moderately well assessed to extended burnups, but the FRAP-T6 code cannot be adequately assessed until more transient high burnup data are available

OECD/NRC BWR Turbine Trip Transient Benchmark as a Basis for Comprehensive Qualification and Studying Best-Estimate Coupled Codes

International Nuclear Information System (INIS)

Ivanov, Kostadin; Olson, Andy; Sartori, Enrico

2004-01-01

An Organisation for Economic Co-operation and Development (OECD)/U.S. Nuclear Regulatory Commission (NRC)-sponsored coupled-code benchmark has been initiated for a boiling water reactor (BWR) turbine trip (TT) transient. Turbine trip transients in a BWR are pressurization events in which the coupling between core space-dependent neutronic phenomena and system dynamics plays an important role. In addition, the available real plant experimental data make this benchmark problem very valuable. Over the course of defining and coordinating the BWR TT benchmark, a systematic approach has been established to validate best-estimate coupled codes. This approach employs a multilevel methodology that not only allows for a consistent and comprehensive validation process but also contributes to the study of different numerical and computational aspects of coupled best-estimate simulations. This paper provides an overview of the OECD/NRC BWR TT benchmark activities with emphasis on the discussion of the numerical and computational aspects of the benchmark

Comparisons of ANSI standards cited in the NRC standard review plan, NUREG-0800 and related documents

International Nuclear Information System (INIS)

Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Pawlowski, R.A.; Spiesman, J.B.

1995-11-01

This report provides the results of comparisons of the cited and latest versions of ANSI standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC's Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review

Comparisons of ASTM standards cited in the NRC standard review plan, NUREG-0800 and related documents

International Nuclear Information System (INIS)

Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Pawlowski, R.A.; Spiesman, J.B.

1995-10-01

This report provides the results of comparisons of the cited and latest versions of ASTM standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC's Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review

75 FR 64749 - Request for Comments on the Use of Electronic Signatures for NRC Documents Related to the Medical...

Science.gov (United States)

2010-10-20

... Pike, Rockville, Maryland. NRC's Agencywide Documents Access and Management System (ADAMS): Publicly... systems exclusively. NRC is seeking comments on acceptable forms of electronic signatures for documents... system that generates the electronic document must have functions that provide a legible document for the...

General statement of policy and procedures for NRC enforcement actions: Enforcement policy. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

This document includes the US Nuclear Regulatory Commission`s (NRC`s or Commission`s) revised General Statement of Policy and Procedure for Enforcement Actions (Enforcement Policy) as it was published in the Federal Register on May 13, 1998 (63 ER 26630). The Enforcement Policy is a general statement of policy explaining the NRC`s policies and procedures in initiating enforcement actions, and of the presiding officers and the Commission in reviewing these actions. This policy statement is applicable to enforcement matters involving the radiological health and safety of the public, including employees` health and safety, the common defense and security, and the environment.

General statement of policy and procedures for NRC enforcement actions: Enforcement policy. Revision 1

International Nuclear Information System (INIS)

1998-05-01

This document includes the US Nuclear Regulatory Commission's (NRC's or Commission's) revised General Statement of Policy and Procedure for Enforcement Actions (Enforcement Policy) as it was published in the Federal Register on May 13, 1998 (63 ER 26630). The Enforcement Policy is a general statement of policy explaining the NRC's policies and procedures in initiating enforcement actions, and of the presiding officers and the Commission in reviewing these actions. This policy statement is applicable to enforcement matters involving the radiological health and safety of the public, including employees' health and safety, the common defense and security, and the environment

The 1997 NRC IST workshops and the status of questions and issues directed to the ASME O and M committee

International Nuclear Information System (INIS)

DiBiasio, A.M.

1998-05-01

This paper describes the results of the four NRC Inservice Testing (IST) Workshops which were held in early 1997 pertaining to NRC Inspection Procedure P 73756, Inservice Testing of Pumps and Valves. It also presents the status of the ASME code committees' resolution of certain questions forwarded to the ASME by the NRC. These questions relate to code interpretations, inconsistencies in the code, and industry concerns that are most appropriately resolved through the ASME consensus process. The ASME committees reviewed the questions at their December 1997 and March 1998 code meetings. Of particular interest are those questions for which the ASME code committees did not agree with the NRC response. These questions, as well as those which the committees provided some additional insight or input, are presented in this paper

NRC TLD Direct Radiation Monitoring Network. Volume 5, No. 2. Progress report, April-June 1985

International Nuclear Information System (INIS)

Jang, J.; Kramaric, M.; Cohen, L.

1985-09-01

The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network provides continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the second quarter of 1985. A complete listing of the site facilities monitored is included

Policy issues raised by intervenor requests for financial assistance in NRC proceedings

International Nuclear Information System (INIS)

1975-01-01

The purpose of the report presented is to focus and develop the myriad issues raised by intervenor requests for financial assistance for the NRC's proposed rulemaking proceeding. The report analyzes and assesses the various alternatives open to the Commission, and collects relevant data and material which may be informative to those participating in and conducting the rulemaking. Three major questions are examined: (1) should the Commission, as a matter of policy choice, provide financial assistance to intervenors in NRC proceedings; (2) are there preferable alternatives to direct intervenor financial aid, such as the establishment of an office of public counsel or provision of other forms of Commission assistance; and (3) what are the legal, administrative and policy considerations involved in implementing a determination to award financial assistance to intervenors, should the Commission so decide

New NRC methodology for estimating biological risks from exposure to ionizing radiation

International Nuclear Information System (INIS)

Willis, C.A; Branagan, E.F.

1983-01-01

In licensing commercial nuclear power reactors, in the US Nuclear Regulatory Commission considers the potential health effects from the release of radioactive effluents. This entails reliance on epidemiological study results and interpretations. The BEIR III report is a principal source of information but as newer information becomes available, it is desirable to include this in NRC models. To facilitate both the estimation of potential health effects and the evaluation of epidemiological study results, the NRC has supported the development of a new computer code (SPAHR). This new code utilizes much more comprehensive demographic models than did the previously used codes (CAIRD and BIERMOD). SPAHR can accommodate variations in all the principal demographic statistics such as age distribution, age-specific computing risks, and sex ratio. Also SPAHR can project effects over a number of generations

Aging research

International Nuclear Information System (INIS)

Ross, D.F. Jr.

1988-01-01

The USNRC Office of Nuclear Regulatory Research has developed a program for nuclear plant aging research (NPAR) to achieve an understanding of nuclear plant aging, its potential effects on safety, and methods for its detection and mitigation, sufficient for addressing safety and regulatory issues and supporting regulatory decisions on issues. Specifically, the NRC has aggressive research and regulatory programs associated with aging effects on piping, steam generators, containments, structures, and electrical and mechanical systems and components. In addition to safety assessment for the original license period for nuclear power plants, this aging information will be extremely useful in providing technical bases for efficient and effective regulation associated with possible license extension. This paper discusses the major activities of USNRC sponsored aging research program and recommends an approach to manage and handle aging at nuclear power plants

Working draft regulatory guide on release criteria for decommissioning: NRC staff's draft for comment

International Nuclear Information System (INIS)

Daily, M.C.; Huffert, A.; Cardile, F.; Malaro, J.C.

1994-08-01

The Nuclear Regulatory Commission's (NRC) regulations in 10 CFR 20 are being amended to include radiological criteria for decommissioning of lands and structures at nuclear facilities. 10 CFR Part 20, Subpart E establishes criteria for the remediation of contaminated sites or facilities that will allow their release for future use with or without restrictions. The criteria include a Total Effective Dose Equivalent (TEDE) limit of 15 mrem/year (0.15 mSv/y) that should not be exceeded by an average individual among those who could potentially receive the greatest exposure from any residual activity within a facility or on a site. The criteria also require a licensee to reduce any residual radioactivity to as-low-as-reasonably-achievable (ALARA) levels. This staff draft guide describes acceptable procedures for determining the predicted dose level (PDL) from any residual radioactivity at the site. It describes the basic features of the calculational models and the associated default assumptions and parameter values the NRC staff would find acceptable in calculating PDLs. Appendices A, B, and C provide numerical values that can be used to estimate the dose from residual radioactivity remaining at a site. Since 10 CFR Part 20, Subpart E introduces several new concepts, definitions and discussions are included in a regulatory position concepts section of the guide to assist licensees in understanding some of the philosophy underlying the rule

Data report for the NRC/PNL Halden assembly IFA-431

International Nuclear Information System (INIS)

Hann, C.R.; Bradley, E.R.; Cunningham, M.E.; Lanning, D.D.; Marshall, R.K.; Williford, R.E.

1978-04-01

The report presents the in-reactor data collected from the NRC/PNL Halden Assembly IFA-431 as a part of the program entitled ''Experimental Verification of Steady State Fuel Codes,'' sponsored by the Fuel Behavior Research Branch of the USNRC. The purpose of this program is to reduce the uncertainties of calculating the thermal stored energy in an operating nuclear fuel rod. The report presents fuel centerline thermocouple readings, cladding elongation monitor readings, rod internal pressure readings, and neutron detector readings. The neutron detector readings were corrected to represent rod local powers at the thermocouple locations. These data are presented in the form of plots of the variables versus time during the irradiation period from June 1975 to February 1976. Also included are descriptions of the test rationale, assembly and rod designs, test facility, instrument array and calibration, and data processing methods. Topical reports discussing specific aspects and results of the data analysis are referenced

Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

International Nuclear Information System (INIS)

1987-05-01

Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions

75 FR 9444 - Agency Information Collection Activities: Proposed Collection; Comment Request

Science.gov (United States)

2010-03-02

... Utilization Facilities,'' specifies technical information and data to be provided to the NRC or maintained by... NUCLEAR REGULATORY COMMISSION [Docket No. NRC-2010-0063] Agency Information Collection Activities: Proposed Collection; Comment Request AGENCY: U.S. Nuclear Regulatory Commission (NRC). ACTION: Notice of...

U.S. Nuclear Regulatory Commission natural analogue research program

International Nuclear Information System (INIS)

Kovach, L.A.; Ott, W.R.

1995-01-01

This article describes the natural analogue research program of the U.S. Nuclear Regulatory Commission (US NRC). It contains information on the regulatory context and organizational structure of the high-level radioactive waste research program plan. It also includes information on the conditions and processes constraining selection of natural analogues, describes initiatives of the US NRC, and describes the role of analogues in the licensing process

NRC systematic evaluation program: seismic review

International Nuclear Information System (INIS)

Levin, H.A.

1980-01-01

The NRC Systematic Evaluation Program is currently making an assessment of the seismic design safety of 11 older nuclear power plant facilities. The general review philosophy and review criteria relative to seismic input, structural response, and equipment functionability are presented, including the rationale for the development of these guidelines considering the significant evolution of seismic design criteria since these plants were originally licensed. Technical approaches thought more realistic in light of current knowledge are utilized. Initial findings for plants designed to early seismic design procedures suggest that with minor exceptions, these plants possess adequate seismic design margins when evaluated against the intent of current criteria. However, seismic qualification of electrical equipment has been identified as a subject which requires more in-depth evaluation

EPRI/NRC-RES fire PRA guide for nuclear power facilities. Volume 1, summary and overview

International Nuclear Information System (INIS)

2004-01-01

This report documents state-of-the-art methods, tools, and data for the conduct of a fire Probabilistic Risk Assessment (PRA) for a commercial nuclear power plant (NPP) application. The methods have been developed under the Fire Risk Re-quantification Study. This study was conducted as a joint activity between EPRI and the U. S. NRC Office of Nuclear Regulatory Research (RES) under the terms of an EPRI/RES Memorandum of Understanding (RS.1) and an accompanying Fire Research Addendum (RS.2). Industry participants supported demonstration analyses and provided peer review of this methodology. The documented methods are intended to support future applications of Fire PRA, including risk-informed regulatory applications. The documented method reflects state-of-the-art fire risk analysis approaches. The primary objective of the Fire Risk Study was to consolidate recent research and development activities into a single state-of-the-art fire PRA analysis methodology. Methodological issues raised in past fire risk analyses, including the Individual Plant Examination of External Events (IPEEE) fire analyses, have been addressed to the extent allowed by the current state-of-the-art and the overall project scope. Methodological debates were resolved through a consensus process between experts representing both EPRI and RES. The consensus process included a provision whereby each major party (EPRI and RES) could maintain differing technical positions if consensus could not be reached. No cases were encountered where this provision was invoked. While the primary objective of the project was to consolidate existing state-of-the-art methods, in many areas, the newly documented methods represent a significant advancement over previously documented methods. In several areas, this project has, in fact, developed new methods and approaches. Such advances typically relate to areas of past methodological debate.

NRC review of passive reactor design certification testing programs: Overview, progress, and regulatory perspective

Energy Technology Data Exchange (ETDEWEB)

Levin, A.E.

1995-09-01

New reactor designs, employing passive safety systems, are currently under development by reactor vendors for certification under the U.S. Nuclear Regulatory Commission`s (NRC`s) design certification rule. The vendors have established testing programs to support the certification of the passive designs, to meet regulatory requirements for demonstration of passive safety system performance. The NRC has, therefore, developed a process for the review of the vendors` testing programs and for incorporation of the results of those reviews into the safety evaluations for the passive plants. This paper discusses progress in the test program reviews, and also addresses unique regulatory aspects of those reviews.

NRC staff preliminary analysis of public comments on advance notice of proposed rulemaking on emergency planning

International Nuclear Information System (INIS)

Peabody, C.A.; Hickey, J.W.N.

1980-01-01

The Nuclear Regulatory Commission (NRC) published an advance notice of proposed rulemaking on emergency planning on July 17, 1979 (44 FR 41483). In October and November 1979, the NRC staff submitted several papers to the Commission related to the emergency planning rulemaking. One of these papers was a preliminary analysis of public comments received on the advance notice (SECY-79-591B, November 13, 1979). This document consists of the preliminary analysis as it was submitted to the Commission, with minor editorial changes

Current role of the USNRC safety research program in support of the regulatory process

International Nuclear Information System (INIS)

Levine, S.

1979-01-01

The current role of the USNRC's safety research program is shown. Some aspects of this role in the wake of the TMI accident are discused as well as some historical perspective on the development of USNRC's program, its relationship with the NRC mission, an overview of the program activities and some recent research results, and finally the impact of the TMI accident in clarifiying needs for expedited and new research activities, including the need for a greatly enhanced use of probabilistic analysis techniques to improve the coherence of its regulatory process. (author)

Scientific activities 1977 and 1978

International Nuclear Information System (INIS)

1980-01-01

The scientific activities and achievements of the Nuclear Research Center Democritus for the years 1977 and 1978 are presented in the form of a list of 79 projects giving title, objectives, commencement year, responsible of each project and the pertaining lists of publications. The 14 chapters of this work cover the activities of the main Divisions of the Democritus NRC: Exploration of Radioactive Minerals, Computer Center, Environmental Radioactivity, Chemistry, Physics, Biology, Soil Science, Electronics, Reactor, Health Physics, Radioisotopes, Technological Applications and Medical Service. (T.A.)

Neutron spectral characterization of the NRC-HSST experiments

Energy Technology Data Exchange (ETDEWEB)

Stallmann, F. W.; Kam, F. B.K.

1979-01-01

Irradiation experiments are being performed for the US Nuclear Regulatory Commission (NRC) Heavy Section Steel Technology (HSST) program. Results of dosimetry performed in the second experiment have been previously reported. Similar procedures were followed in the third experiment. The experiences gained in these two experiments have led to modifications in the composition and distribution of foil dosimeters which monitor the neutron flux-spectra in the irradiated steel specimens. It is expected that in the new experiments much higher accuracies than previously possible can be achieved in the determination of irradiation damage parameters.

Neutron spectral characterization of the NRC-HSST experiments

International Nuclear Information System (INIS)

Stallmann, F.W.; Kam, F.B.K.

1979-01-01

Irradiation experiments are being performed for the US Nuclear Regulatory Commission (NRC) Heavy Section Steel Technology (HSST) program. Results of dosimetry performed in the second experiment have been previously reported. Similar procedures were followed in the third experiment. The experiences gained in these two experiments have led to modifications in the composition and distribution of foil dosimeters which monitor the neutron flux-spectra in the irradiated steel specimens. It is expected that in the new experiments much higher accuracies than previously possible can be achieved in the determination of irradiation damage parameters

Revised Severe Accident Research Program plan, FY 1990--1992

International Nuclear Information System (INIS)

1989-08-01

For the past 10 years, since the Three Mile Island accident, the NRC has sponsored an active research program on light-water-reactor severe accidents as part of a multi-faceted approach to reactor safety. This report describes the revised Severe Accident Research Program (SARP) and how the revisions are designed to provide confirmatory information and technical support to the NRC staff in implementing the staff's Integration Plan for Closure of Severe Accident Issues as described in SECY-88-147. The revised SARP addresses both the near-term research directed at providing a technical basis upon which decisions on important containment performance issues can be made and the long-term research needed to confirm and refine our understanding of severe accidents. In developing this plan, the staff recognized that the overall goal is to reduce the uncertainties in the source term sufficiently to enable the staff to make regulatory decisions on severe accident issues. However, the staff also recognized that for some issues it may not be practical to attempt to further reduce uncertainties, and some regulatory decisions or conclusions will have to be made with full awareness of existing uncertainties. 2 figs., 1 tab

The use of research results for effective aging management

International Nuclear Information System (INIS)

Gunther, W.E.; Taylor, J.H.

1989-01-01

The study of the degradation of structures, components, and systems due to aging is an important ongoing area of research in the nuclear industry. Efforts by the U.S. Nuclear Regulatory Commission (NRC) and the utility industry, through organizations such as the Electric Power Research Institute (EPRI), have produced substantial research results that can be used by inspectors and operators to effectively understand and manage the aging of nuclear power plants. One of the primary objectives of the NRC's Nuclear Plant Aging Research (NPAR) Program is to determine how aging affects the safety of nuclear power plants. This program uses operating experience, testing, and engineering analysis to identify failures caused by age-related degradation. Useful information on aging has also resulted from research being performed by the industry to support plant-life extension (PLEX). The EPRI program, for instance, is directed toward the resolution of issues related to materials and components. Degradation of equipment and systems due to aging can occur which, if unmitigated, could result in reduction of the nuclear power plant safety margin as the plant ages. This paper describes how aging research results may be used by plant operating management to effectively address the aging issue and by inspectors responsible for monitoring plant activities and programs

NRC Information Notice No. 93-25: Electrical penetration assembly degradation

International Nuclear Information System (INIS)

Grimes, B.K.

1993-01-01

In July 1987 and in October 1989, the licensee for the Trojan Nuclear Plant, the Portland and General Electric Company, reported problems with containment air leakage through its Bunker-Ramo electrical penetration assembly seals. In July and August 1991, the NRC inspected the use of containment electrical penetration assembly seals at Trojan and concluded that the licensee had not established an effective program for trending and evaluating electrical penetration assembly seal leakage. On October 28, 1991, while the plant was in a refueling outage, the licensee reported to the NRC that in the originally installed electrical penetration assemblies, the seal (polyurethane) and lubricant (Celvacen or Glycerin) materials were inappropriate for the application. The licensee concluded that these materials may cause seal degradation and that the seals may become degraded if subjected to design basis accident conditions for moisture or temperature. The licensee replaced the electrical penetration assembly seal with an environmentally qualified ethylene propylene rubber seal and added a silicone rubber backup O-ring to the outer face of each electrical penetration assembly module. The licensee subsequently replaced all the Bunker-Ramo electrical penetration assemblies with Conax assemblies

Research Project Control System (RPCS); research results utilization data as of 06/30/81. Status summary report

International Nuclear Information System (INIS)

1981-09-01

The report on 'Research Results Utilization' provides status and control information concerning the utilization of research results in the regulatory policies and practices of the NRC. Research Information Letters (RILs) are prepared by RES to transmit research results to NRC user offices upon completion of a substantial, coherent and reasonably complete body of experimental and/or analytical research work. Section 3.0 of this report lists the RILs issued to date, together with an identification of the research program manager and the research program element which generated the RIL. The potential applicability of each RIL to the regulatory process is also identified, and comments from the cognizant RES and user office staff are summarized which relate to the expected impact of the reported RILs on the regulatory process

Directory of Certificates of Compliance for Radioactive Materials Packages. Summary report of NRC approved packages. Volume 1, Revision 8

International Nuclear Information System (INIS)

1985-10-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages. Volume 1. Revision 9

International Nuclear Information System (INIS)

1986-10-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and Corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Sections 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages. Volume 1, Revision 7

International Nuclear Information System (INIS)

1984-11-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Implementation and interpretation of the NRC/IAEA transport regulations in the United States

International Nuclear Information System (INIS)

Shappert, L.B.

1987-01-01

For those materials used in the construction of spent fuel casks that are covered by the many available codes (ASME, ASTM, etc.), their acceptance by NRC can be expected to be straightforward. When materials are used that are not recognized by the codes, NRC has taken a more cautious attitude in their acceptance and approval. As mentioned earlier, they have initiated a number of studies involving ferritic steels, including DCI. More recently, they are organizing a panel of independent experts to consider all the data available and provide guidance as to whether these ferritic materials meet the safety requirements of the regulations and, if so, under what conditions. They will also be considering the testing that has been applied to casks fabricated from DCI and the likely margins of safety they possess. (orig./DG)

NRC-BNL Benchmark Program on Evaluation of Methods for Seismic Analysis of Coupled Systems

International Nuclear Information System (INIS)

Chokshi, N.; DeGrassi, G.; Xu, J.

1999-01-01

A NRC-BNL benchmark program for evaluation of state-of-the-art analysis methods and computer programs for seismic analysis of coupled structures with non-classical damping is described. The program includes a series of benchmarking problems designed to investigate various aspects of complexities, applications and limitations associated with methods for analysis of non-classically damped structures. Discussions are provided on the benchmarking process, benchmark structural models, and the evaluation approach, as well as benchmarking ground rules. It is expected that the findings and insights, as well as recommendations from this program will be useful in developing new acceptance criteria and providing guidance for future regulatory activities involving licensing applications of these alternate methods to coupled systems

Regulation of Federal radioactive waste activities. Summary of report to Congress on extending the Nuclear Regulatory Commission's licensing or regulatory authority to Federal radioactive waste storage and disposal activities

International Nuclear Information System (INIS)

Smith, R.D.

1979-09-01

The NRC Authorization Bill for FY 1979 directed NRC to conduct a study of extending the Commission's licensing or regulatory authority to include categories of existing and future Federal radioactive waste storage and disposal activities not presently subject to such authority. The report includes a complete listing and inventory of all radioactive waste storage and disposal activities now being conducted or planned by Federal agencies. The NRC study has attempted to present a general comparison of the relative hazards associated with defense-generated and commercial wastes. Options for extending Commission authority were developed and analyzed. The implications of NEPA were analyzed in the context of these options. The national security implications of extending NRC's regulatory authority over DOE programs are examined and evaluated. Costs and benefits are identified and assessed. The Commission's recommendations, based on the study, are to extend licensing authority over new DOE disposal activities involving transuranic wastes and non-defense low-level waste and to initiate a pilot program to test the feasibility of NRC playing a consultative role in the evaluation of existing DOE activities

Assessment of operational safety data in the Nuclear Regulatory Commission (NRC)

International Nuclear Information System (INIS)

Michelson, C.; Heltemes, C.J.

1981-01-01

The collection, assessment, and dissemination of operational safety data, including the Licensee Event Reports (LERs) is the principal activity of the NRC's Office for Analysis and Evaluation of Operational Data (AEOD). This office was recently formed to provide a dedication to this activity. It has been staffed and fully operational since April 1980. The office programs are evolving and include some new ideas and techniques to aid in the assessment of LERs. For example, the office is managing the development of a computer-based Sequence Coding and Search (SCS) procedure which will have the capability to store and retrieve the detail and individual sequences associated with each LER. Such events may be rather complex and involve a number of isolated or unrelated happenings associated with multiple systems and components with various causes, failure modes, and failure effects. Thus, the SCS system is particularly useful because it documents in a computer-retrievable form not only the principal occurrence, but also related component and system responses which precede, accompany, follow, or result from the principal occurrence. Also noteworthy is the Power Reactor Watch List which is being developed and monitored as a part of the AEOD program

Consolidation and Decomposition of APR1400 NRC Design Certification Processes for Collaborative and Accelerated Processing

Energy Technology Data Exchange (ETDEWEB)

Cho, Young Chul [FNC Technology Co., Yongin (Korea, Republic of); Kang, Deog Ji [KNHP, Daejeon (Korea, Republic of)

2016-05-15

KEPCO and KHNP are conducting APR1400 Design Certification from NRC. For the proper management of processes and information, a system called RIS (Regulatory Information management System) has been implemented by FNC from 2014, and it is on the final stage. In retaining the certification from NRC, RIS will be a very essential role by providing platform for collaborative and accelerated processing of responses to RAI (Request of Additional Information). Preparation of responses to RAI with this kind of systematic approach may be the first in the world. Westinghouse is doing manually and using MS Excel to collect the processing status. Where as, RIS will enable each member can do his own job and collect the status automatically. In this paper, how collaborative and accelerated processing of responses to RAI can be enabled will be described, and further enhancements will also be discussed. It handles MS Word directory with the help of VSTO. And with the help of Aspose.Total for .NET, the prepared response to RAI meets NRC's requirements. Through some further work and direct integration with requirement management solution, RIS can be expanded to cover a prior impact notice in case of DCD being altered.

NRC Regulatory Agenda. Quarterly report, October-December 1985. Volume 4, No. 4

International Nuclear Information System (INIS)

1986-03-01

The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed, or is considering action as well as those on which it has recently completed action, and all petitions for rulemaking which have been received and are pending disposition by the Commission

United States Nuclear Regulatory Commission research program on core debris/concrete interactions and ex-vessel fission-product release

International Nuclear Information System (INIS)

Burson, S.B.

1987-01-01

The study of core debris/concrete interaction phenomena has been a significant element of the NRC's Severe Accident Research Program for a number of years. The CORCON and VANESA codes used to predict the consequences of high-temperature debris attack on concrete and fission-product aerosol release are state-of-the-art computational tools. The major thrust of current NRC sponsored research focuses on the refinement, verification, and validation of these codes. An overview of the analytical and experimental aspects of the NRC research program is presented

Yucca Mountain program summary of research and technical review activities, July 1988--June 1989

International Nuclear Information System (INIS)

1989-11-01

The Desert Research Institute (DRI), through its Water Resources Center (WRC), since 1984 has supported the State of Nevada Nuclear Waste Project Office's activities related to the proposed high-level radioactive waste repository at Yucca Mountain on the Nevada Test Site (NTS). This effort is directed at providing the State Office with an unbiased evaluation of the Yucca Mountain Project (YMP) investigations performed by the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC). The overall objective is to determine independently whether or not the site meets the performance criteria defined by the Nuclear Waste Policy Act of 1982 and amendments for isolating and containing the wastes during emplacement and the proposed life of the repository. A particularly important area of concern with the proposed repository is the site's hydrology. The faculty of the DRI have long been involved with research throughout the State and have particular expertise in groundwater studies related to radionuclide migration and hydrologic safety of underground nuclear testing by DOE and predecessor agencies. In addition, we utilize laboratory personnel for chemical and isotopic analyses in both of the DRI-WMC water chemistry laboratories

The SARAF Project - Soreq Applied Research Accelerator Facility

International Nuclear Information System (INIS)

Nagler, A.; Mardor, I.; Berkovits, D.; Piel, C.

2004-01-01

The relevance of particle accelerators to society, in the use of their primary and secondary beams for the analysis of physical, chemical and biological samples and for modification of properties of materials, is well recognized and documented. Nevertheless, apart of the construction of small accelerators for nuclear research in the 1960's and 70's, Israel has so far neglected this important and growing field. Furthermore, there is an urgent need in Israel for a state of the art research facility to attract and introduce students to current advanced physics techniques and technologies and to train the next generation of experimental scientists in various branches and disciplines. Therefore, Soreq NRC recently initiated the establishment of a new accelerator facility, named SARAF Soreq Applied Research Accelerator Facility. SARAF will be a continuous wave (CW), proton and deuteron RF superconducting linear accelerator with variable energy (5 - 40 MeV) and current (0.04 -2 mA). SARAF is designed to enable hands-on maintenance, which means that its beam loss will be below 10 -5 for the entire accelerator. These specifications will place SARAF in line with the next generation of accelerators world wide. Soreq expects that this fact will attract the Israeli and international research communities to use this facility extensively. Soreq NRC intends to use SARAF for basic, medical and biological research, and non-destructive testing (NDT). Another major activity will be the research and development of radio-isotopes production techniques. Given the availability of high current (up to 2 mA) protons and deuterons, a major activity will be research and development of high power density (up to 80 kW on a few cm 2 ) irradiation targets

Current status of ground motions evaluation in seismic design guide for nuclear power facilities. Investigation on IAEA and US.NRC

International Nuclear Information System (INIS)

Nakajima, Masato; Ito, Hiroshi; Hirata, Kazuta

2009-01-01

Recently, IAEA (International Atomic Energy Agency) and US.NRC (US. Nuclear Regulatory Commission) published several standards and technical reports on seismic design and safety evaluation for nuclear power facilities. This report summarizes the current status of the international guidelines on seismic design and safety evaluation for nuclear power facilities in order to explore the future research topics. The main results obtained are as follows: 1 IAEA: (1) In the safety standard series, two levels are defined as seismic design levels, and design earthquake ground motion is determined corresponding to each seismic design level. (2) A new framework on seismic design which consists of conventional deterministic method and risk-based method is discussed in the technical report although the framework is not adopted in the safety guidelines. 2 USA: (1) US.NRC discusses a performance-based seismic design framework which has been originally developed by the private organization (American Society of Civil Engineers). (2) Design earthquakes and earthquake ground motion are mainly evaluated and determined based on probabilistic seismic hazard evaluations. 3 Future works: It should be emphasized that IAEA and US.NRC have investigated the implementation of risk-based concept into seismic design. The implementation of risk-based concept into regulation and seismic design makes it possible to consider various uncertainties and to improve accountability. Therefore, we need to develop the methods for evaluating seismic risk of structures, and to correlate seismic margin and seismic risk quantitatively. Moreover, the probabilistic method of earthquake ground motions, that is required in the risk-based design, should be applied to sites in Japan. (author)

Quality assurance records system for research and development activities in support of geologic repository programs

International Nuclear Information System (INIS)

Smith, J.W.; Ryder, D.E.

1987-01-01

The Pacific Northwest Laboratory (PNL), which is operated by Battelle Memorial Institute for the Department of Energy, is conducting site-specific research for all three candidate sites for the first geologic high-level waste repository, as well as generic research for the second repository. In conjunction with this effort, PNL has developed a quality assurance (QA) program that is applicable to all organizations that are performing research and development (R and D) activities in support of the repository programs. This QA program meets the basic and supplemental requirements of ANSI/ASME NQA-1-1983 and the Nuclear Regulatory Commission (NRC) Review Plan for QA Programs for Site Characterization of High Level Nuclear Waste Repositories. A key part of this program is the handling of QA records that may ultimately support the licensing process for the repository. This paper describes a QA records system that is flexible enough to accommodate several types of research, such as paper studies, test method development, site characterization studies, software development, and hardware design. In addition, the QA records system is acceptable to a variety of sponsors who have licensing concerns. The QA procedures and their relation to the requirements are described. Most important is the discussion on the approaches used to assure that the records are organized such that the user can readily recreate or defend data, conclusions, and recommendations resulting from the research

The Survival and Resistance of Halobacterium salinarum NRC-1, Halococcus hamelinensis, and Halococcus morrhuae to Simulated Outer Space Solar Radiation.

Science.gov (United States)

Leuko, S; Domingos, C; Parpart, A; Reitz, G; Rettberg, P

2015-11-01

Solar radiation is among the most prominent stress factors organisms face during space travel and possibly on other planets. Our analysis of three different halophilic archaea, namely Halobacterium salinarum NRC-1, Halococcus morrhuae, and Halococcus hamelinensis, which were exposed to simulated solar radiation in either dried or liquid state, showed tremendous differences in tolerance and survivability. We found that Hcc. hamelinensis is not able to withstand high fluences of simulated solar radiation compared to the other tested organisms. These results can be correlated to significant differences in genomic integrity following exposure, as visualized by random amplified polymorphic DNA (RAPD)-PCR. In contrast to the other two tested strains, Hcc. hamelinensis accumulates compatible solutes such as trehalose for osmoprotection. The addition of 100 mM trehalose to the growth medium of Hcc. hamelinensis improved its survivability following exposure. Exposure of cells in liquid at different temperatures suggests that Hbt. salinarum NRC-1 is actively repairing cellular and DNA damage during exposure, whereas Hcc. morrhuae exhibits no difference in survival. For Hcc. morrhuae, the high resistance against simulated solar radiation may be explained with the formation of cell clusters. Our experiments showed that these clusters shield cells on the inside against simulated solar radiation, which results in better survival rates at higher fluences when compared to Hbt. salinarum NRC-1 and Hcc. hamelinensis. Overall, this study shows that some halophilic archaea are highly resistant to simulated solar radiation and that they are of high astrobiological significance. Halophiles-Solar radiation-Stress resistance-Survival.

Seismic safety research program plan

International Nuclear Information System (INIS)

1985-06-01

This plan describes the safety issues, regulatory needs, and the research necessary to address these needs. The plan also discusses the relationship between current and proposed research within the NRC and research sponsored by other government agencies, universities, industry groups, professional societies, and foreign sources

Regulation of Federal radioactive waste activities. Report to Congress on extending the Nuclear Regulatory Commission's licensing or regulatory authority to Federal radioactive waste storage and disposal activities

International Nuclear Information System (INIS)

1979-09-01

The report contains two recommendations for extending the Commission's regulatory authority: (1) NRC licensing authority should be extended to cover all new DOE facilities for disposal of transuranic (TRU) waste and nondefense low-level waste. (2) A pilot program, focused on a few specific DOE waste management activities, should be established to test the feasibility of extending NRC regulatory authority on a consultative basis to DOE waste management activities not now covered by NRC's licensing authority or its extension as recommended in Recommendation 1

NRC TLD [Nuclear Regulatory Commission thermoluminescent dosimeter] direct radiation monitoring network

International Nuclear Information System (INIS)

Struckmeyer, R.; McNamara, N.

1990-03-01

This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1989. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

75 FR 21979 - NRC Region II Address and Main Telephone Number Changes

Science.gov (United States)

2010-04-27

... Region II Address and Main Telephone Number Changes AGENCY: Nuclear Regulatory Commission. ACTION: Final... address for its Region II office and to update the main telephone number. The Region II office move and... update the NRC Region II office street address and office main telephone number. The physical location of...

NRC safety research in support of regulation, FY 1992

International Nuclear Information System (INIS)

1993-05-01

This report, the eighth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1992. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that a number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with the technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission's rules, regulatory guides, or other guidance

Risk-based regulation - an NRC perspective and status

International Nuclear Information System (INIS)

King, T.L.; Murphy, J.A.

1993-01-01

The consideration of risk in regulatory decision making has traditionally been part of the US Nuclear Regulatory Commission's (NRC's) policy and practice. In the early days of regulation, this consideration was more qualitative in nature and was reflected in prescriptive/deterministic regulatory requirements. However, with the development of quantitative risk assessment methods, more detailed and comprehensive (although not complete) risk information on nuclear power plants is available to the designer, operator, and regulator. The availability of such information provides an opportunity to assess the need for change in the current regulatory structure and to develop future regulatory requirements in a less prescriptive, more performance-oriented fashion

NRC licensing speedup. Hearing before a Subcommittee of the Committee on Government Operations, House of Representatives, Ninety-Seventh Congress, First Session, June 18, 1981

International Nuclear Information System (INIS)

Anon.

1982-01-01

Joseph Hendrie, Acting Chairman of the Nuclear Regulatory Commission (NRC), was the principal witness at a June 18, 1981 hearing on whether the NRC is responsible for idling and delaying nuclear plants at a high cost to consumers. Congress is considering an interim licensing procedure that will allow plants to operate before safety hearings are completed. NRC evidence suggests that most plant delays are only projected ones, and that utilities must bear the blame for slippage in most construction schedules. Mr. Hendrie discussed the status of the nine impacted plants on the NRC list and outlined steps the Commission is taking to improve efficiency without impairing safety. His testimony and letters, statements, and other materials submitted for the record make up the hearing report

Inventory of Information Resources; A Comparison of the American Geological Institute (AGI) Pilot Project with the National Referral Center (NRC) Inventory.

Science.gov (United States)

Price, John F.

The National Referral Center (NRC) and its many services to the scientific and technical community are discussed in some detail as a preamble to a proposal of a cooperative arrangement between NRC and the American Geological Institute (AGI), its supporting societies, and all geoscientists in a combined effort to enlarge and maintain a…

NRC [Nuclear Regulatory Commission] staff evaluation of the General Electric Company Nuclear Reactor Study (''Reed Report'')

International Nuclear Information System (INIS)

1987-07-01

In 1975, the General Electric Company (GE) published a Nuclear Reactor Study, also referred to as ''the Reed Report,'' an internal product-improvement study. GE considered the document ''proprietary'' and thus, under the regulations of the Nuclear Regulatory Commission (NRC), exempt from mandatory public disclosure. Nonetheless, members of the NRC staff reviewed the document in 1976 and determined that it did not raise any significant new safety issues. The staff also reached the same conclusion in subsequent reviews. However, in response to recent inquiries about the report, the staff reevaluated the Reed Report from a 1987 perspective. This re-evaluation, documented in this staff report, concluded that: (1) there are no issues raised in the Reed Report that support a need to curtail the operation of any GE boiling water reactor (BWR); (2) there are no new safety issues raised in the Reed Report of which the staff was unaware; and (3) although certain issues addressed by the Reed Report are still being studied by the NRC and the industry, there is no basis for suspending licensing and operation of GE BWR plants while these issues are being resolved

NRC TLD Direct Radiation Monitoring Network. Progress report, October--December 1996

International Nuclear Information System (INIS)

Struckmeyer, R.

1997-03-01

This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1996. It provides the ambient radiation levels measured in the vicinity of 74 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs

PRISIM: A plant risk status information management system for NRC inspectors

International Nuclear Information System (INIS)

Reilly, H.J.; Glynn, J.C.; Campbell, D.J.

1987-01-01

The Plant Risk Status Information Management System (PRISIM) is a microcomputer program that presents results of probabilistic risk assessments (PRAs), and related information, for use by United States Nuclear Regulatory Commission (NRC) decisionmakers. Plant-specific PRISIMs have been developed for three nuclear plants in the United States. The usefulness of PRISIM for these plants is now under evaluation, and an improved PRISIM is being developed

NRC TLD Direct Radiation Monitoring Network. Progress report, October--December 1996

Energy Technology Data Exchange (ETDEWEB)

Struckmeyer, R.

1997-03-01

This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1996. It provides the ambient radiation levels measured in the vicinity of 74 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs.

Comparative analysis of DOE Order 5820.2A, NRC, and EPA radioactive and mixed waste management requirements

International Nuclear Information System (INIS)

1991-07-01

As directed by DOE-Headquarters and DOE-Idaho, the Radioactive Waste Technical Support Program (TSP) drafted an analysis of DOE Order 5820. 2A on ''Radioactive Waste Management'' to develop guidelines and criteria for revising the Order. This comparative matrix is a follow up to the earlier analysis. This matrix comparing the requirements of DOE Order 5820.2A with Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA) regulations was prepared at the request of EM-30. The matrix compares DOE Order 5820.2A with the following: NRC regulations in 10 CFR Part 61 on ''Licensing Requirements for Land Disposal of Radioactive Waste''; NRC regulations in 10 CFR Part 60 on ''Disposal of High-Level Radioactive Waste in Geologic Repositories''; EPA regulations in 40 CFR Part 191 on ''Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste''; EPA regulations in 40 FR Part 192 on ''Health and Environmental Protection Standards for Uranium and Thorium Mill Tailing''; and EPA regulations under the Resource Conservation and Recovery Act

Reliability and risk analysis methods research plan

International Nuclear Information System (INIS)

1984-10-01

This document presents a plan for reliability and risk analysis methods research to be performed mainly by the Reactor Risk Branch (RRB), Division of Risk Analysis and Operations (DRAO), Office of Nuclear Regulatory Research. It includes those activities of other DRAO branches which are very closely related to those of the RRB. Related or interfacing programs of other divisions, offices and organizations are merely indicated. The primary use of this document is envisioned as an NRC working document, covering about a 3-year period, to foster better coordination in reliability and risk analysis methods development between the offices of Nuclear Regulatory Research and Nuclear Reactor Regulation. It will also serve as an information source for contractors and others to more clearly understand the objectives, needs, programmatic activities and interfaces together with the overall logical structure of the program

NRC (2001 equations to predict the energy value of agroindustry byproducts in Brazilian northeast Equações do NRC (2001 para predição do valor energético de co-produtos da agroindústria no nordeste brasileiro

Directory of Open Access Journals (Sweden)

Arturo Bernardo Selaive Villarroel

2008-06-01

Full Text Available Fractions of carbohydrates and protein, and energy value estimative based in NRC (2001 equations, of agroindustry byproducts of cashew, passion fruit, melon, anatto seeds, pineapple and barbados cherry were evaluated. NRC (2001 equations were used to predict the energy value of the passion fruit, pineapple and barbados cherry using “in vivo” data. Carbohydrates fraction A + B1 ranged from 20.00 to 52.21% of the total carbohydrates, for melon and anatto seeds, respectively. Cashew and barbados cherry presented close values for the fraction B2 (11.88 and 14.25% and C (52.69 and 59.45% and, approximately three times lower of fraction B2 than the passion fruit and the pineapple (47.93 and 45.38%. It was concluded that the analyses of the fractions of carbohydrates and protein should be a laboratorial routine, since it consists in a simple analysis, inexpensive and allows the establishment of mechanicists parameters for feed evaluations. The observed values of TDN of ingredients and those predicted by NRC (2001 equations were similar, being appropriate to predict the energy value of feeds in Brazilian conditions.Objetivou-se, neste estudo, avaliar as frações de carboidratos e proteínas, e estimar o valor energético a partir das equações do NRC (2001 dos co-produtos da agroindústria do caju, maracujá, melão, urucum, abacaxi e acerola. Foi realizada a avaliação das equações do NRC (2001 para predição do valor energético do maracujá, abacaxi e acerola, a partir de dados in vivo. A fração A + B1 dos carboidratos variou de 20,00 a 52,21% dos carboidratos totais, para melão e urucum, respectivamente. O caju e a acerola apresentaram valores próximos para a fração B2 (11,88 e 14,25% e C (52,69 e 59,45% e, aproximadamente, três vezes menos fração B2 que o maracujá e o abacaxi (47,93 e 45,38%. O valor A da fração protéica (NNP variou de 5,01 a 33,02% para melão e urucum, respectivamente. A fração C da proteína foi menor

Component Fragility Research Program: Phase 1 component prioritization

International Nuclear Information System (INIS)

Holman, G.S.; Chou, C.K.

1987-06-01

Current probabilistic risk assessment (PRA) methods for nuclear power plants utilize seismic ''fragilities'' - probabilities of failure conditioned on the severity of seismic input motion - that are based largely on limited test data and on engineering judgment. Under the NRC Component Fragility Research Program (CFRP), the Lawrence Livermore National Laboratory (LLNL) has developed and demonstrated procedures for using test data to derive probabilistic fragility descriptions for mechanical and electrical components. As part of its CFRP activities, LLNL systematically identified and categorized components influencing plant safety in order to identify ''candidate'' components for future NRC testing. Plant systems relevant to safety were first identified; within each system components were then ranked according to their importance to overall system function and their anticipated seismic capacity. Highest priority for future testing was assigned to those ''very important'' components having ''low'' seismic capacity. This report describes the LLNL prioritization effort, which also included application of ''high-level'' qualification data as an alternate means of developing probabilistic fragility descriptions for PRA applications

NRC Confirmatory Testing Program for SBWR

International Nuclear Information System (INIS)

Han, J.T.; Bessette, D.E.; Shotkin, L.M.

1994-01-01

The objective of the NRC Confirmatory Testing Program for SBWR is to provide integral data for code assessment, which reasonably reproduce the important phenomena and processes expected in the SBWR under various loss-of-coolant accident (LOCA) and transient conditions. To achieve this objective, the Program consists of four coupled elements: (1) to design and construct an integral, carefully-scaled SBWR test facility at Purdue Univ., (2) to provide pre-construction RELAP5/CONTAIN predictions of the facility design, (3) to provide confirmatory data for code assessment, and (4) to assess the RELAP5/CONTAIN code with data. A description of the open-quotes preliminary designclose quotes of the Purdue test facility and test matrix is presented. The facility is scheduled to be built by December 1994. Approximately 50 tests will be performed from April 1995 through April 1996 and documented by interim data reports. A final and complete data report is scheduled to be published by July 31, 1996

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

A regulator's perspective on NRC's participation in the operations ampersand maintenance committees

International Nuclear Information System (INIS)

Wessman, R.H.

1996-01-01

As a regulator fairly new to the American Society of Mechanical Engineers (ASME) Operations and Maintenance (O ampersand M) Committee process, the author does not have a personal historical perspective as do many of the longer-term, and highly respected, members of the O ampersand M Committee. However, as Branch Chief of the Mechanical Engineering Branch, Division of Engineering, in the Office of Nuclear Reactor Regulation at the NRC for just over two years, he has responsibility for the regulatory agency's review of licensee actions involving the products that come from the efforts of the O ampersand M Committee, as well as responsibility for portions of the activities of interest to other ASME Code groups such as Section III, Section XI, and Qualification of Mechanical Equipment. As a result, the author has learned a great deal about the code process in a short time. Here he gives his perspectives on the process and provides a few thoughts on the direction for the future

LHCb - A SciFi production center in NRC KI FOR LHCb upgrade

CERN Multimedia

Shevchenko, Vladimir

2015-01-01

The Scintillating Fiber Tracker, SciFi for short, will be the main new tracking detector in LHCb. It will provide better than 100 µm spatial resolution, and high rate capability and radiation hardness enabling a fast, 40 MHz, trigger rate with a capability to withstand 50 fb$^{-1}$ integrated luminosity, delivered by LHC, without a major performance degradation. The main active element of the tracker is a scintillating fiber ribbon with the SiPM readout. The ribbons consist of 6 layers of the 250 µm scintillating fibers Kuraray SCSF-78MJ, assembled by winding and bound together by the epoxy glue. NRC Kurchatov Institute, Moscow, together with the colleagues from ITEP, CERN, TU of Dortmund and RWTH of Aachen are developing dedicated production centers with the aim to reach by 2016 production rate one ribbon per day per center, necessary to supply more than 1300 fibre ribbons (mats) needed for the new LHCb tracker.

Creation of nuclear research centres in new entrant countries

International Nuclear Information System (INIS)

Caoui, A.; Monnet, F.

2010-01-01

A number of prerequisites must be fulfilled before setting up a nuclear program in a new entrant country. This includes the training of future operating teams in the safety culture and the acquisition of the necessary technological knowledge. A NRC brings together the facilities and structures to meet this need. Similarly, prerequisites for the construction of an NRC in Maamora (Morocco) have been completed by AREVA. These include establishing the contract, constructing the nuclear research centre and above all, commissioning the facilities. This paper gives the feedback from the team formed by AREVA and CNESTEN on the adventure the construction of the NRC Maamora has been. (author)

Pump and valve research at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Haynes, H.D.

1992-01-01

Over the last several years, the Oak Ridge National Laboratory (ORNL) has carried out several aging assessments on pumps and valves under the NRC's Nuclear Plant Aging Research (NPAR) Program. In addition, ORNL has established an Advanced Diagnostic Engineering Research and Development Center (ADEC) in order to play a key role in the field of diagnostic engineering. Initial ADEC research projects have addressed problems that were identified, at least in part, by the NPAR and other NRC-sponsored programs. This paper summarizes the pump and valve related research that has been done at ORNL and describes in more detail several diagnostic techniques developed at ORNL which are new commercially available

NRC review of passive reactor design certification testing programs: Overview and regulatory perspective

International Nuclear Information System (INIS)

Levin, A.E.

1993-01-01

Reactor vendors are developing new designs for future deployment, including open-quotes passiveclose quotes light water reactors (LWRs), such as General Electric's (G.E.'s) simplified boiling water reactor (SBWR) and Westinghouse's AP600, which depend primarily on inherent processes, such as national convection and gravity feed, for safety injection and emergency core cooling. The U.S. Nuclear Regulatory Commission (NRC) has implemented a new process, certification of standardized reactor designs, for licensing these Plants. Part 52 of Title 10 of the Code of Federal Regulations (10CFR52) contains the requirements that vendors must meet for design certification. One important section, 10CFR52.47, reads open-quotes Certification of a standard design which . . . utilizes simplified, inherent, passive, or other innovative means to accomplish its safety functions will be granted only if: (1) The performance of each safety feature of the design has been demonstrated through either analysis, appropriate test programs, experience, or a combination thereof; (2) Interdependent effects among the safety features have been found acceptable by analysis, appropriate test programs, experience, or a combination thereof; and (3) Sufficient data exist on the safety features of the design to assess the analytical tools used for safety analyses. . . . The vendors have initiated programs to test innovative features of their designs and to develop data bases needed to validate their analytical codes, as required by the design certification rule. Accordingly, the NRC is reviewing and evaluating the vendors programs to ensure that they address adequately key issues concerning safety system performance. This paper provides an overview of the NRC's review process and regulatory perspective

Neutron activation procedures used for the calibration of a nitrogen-16 reactor power monitor

International Nuclear Information System (INIS)

Jester, W.A.; Daubenspeck, T.

2000-01-01

Personnel from the Pennsylvania State University's Breazeale Nuclear Reactor assisted NRC (Nuclear Research Corporation) personnel in calibrating a new MSL/ 16 N Nitrogen-16 Monitor. Neutron flux calibration procedures utilized and the results obtained for the production of a nitrogen-16 source of known activity for a BGO detector calibration are described. (author)

Annual report on the activities of National Reference Centers established on the basis of regional public health authorities of the Slovak Republic and the Office of Public Health of the Slovak Republic in 2009

International Nuclear Information System (INIS)

2010-01-01

A brief account of activities carried out by the National Reference Centers (NRC) established on the basis of regional public health authorities of the Slovak Republic and the Office of Public Health of the Slovak Republic in 2009 is presented. These activities are reported under the headings: (1) NRC for influenza; (2) NRC for arbovirus and hemorrhagic fever; (3) NRC for poliomyelitis; (4) NRC for meningococci; (5) NRC to monitor the resistance of microorganisms to antibiotics; (6) NRC for evaluation of late effects of chemical substances, methods of genetic toxicology; (7) NRC for hydrobiology; (8) NRC for ecotoxicology; (9) NRC for non-ionizing radiation; (10) NRC for hydrothermal microclimate; (11) NRC for exposure tests xenobiotics; (12) NRC for morbilli, rubella and parotitis; (13) NRC for environmental microbiology; (14) NRC on pesticide residues; (15) NRC for salmonella; (16) NRC health issues for urban air pollution; (17) NRC for microbial autovaccines; (18) NRC for noise and vibration; (19) Information Center for bacteriological (biological) and toxin weapons; (20) NRC for impact assessment of ambient air and air of enclosed spaces non-productive nature of population health; (21) NRC for toxoplasmosis; (22) NRC for exposure assessment and health risk; (23) NRC for pertussis and parapertussis; (24) NRC for syphilis; (25) NRC for hygienic drinking water problems; (26) NRC for listeriosis; (27) NRC for intestinal parasitosis; (28) NRC for diphtheria; (29) NRC for vibrionaceae; (30) NRC for environmental mycology; (31) NRC issues for fibrous dusts; (32) NRC for thermotolerant amoebae; (33) NRC issues for coal mines; (34) NRC for articles of daily use and packing materials; (35) NRC for haemophilus infections; (36) NRC for Legionella in the environment.

Annual report on the activities of National Reference Centers established on the basis of regional public health authorities of the Slovak Republic and the Office of Public Health of the Slovak Republic in 2008

International Nuclear Information System (INIS)

2009-02-01

A brief account of activities carried out by the National Reference Centers (NRC) established on the basis of regional public health authorities of the Slovak Republic and the Office of Public Health of the Slovak Republic in 2008 is presented. These activities are reported under the headings: (1) NRC for influenza; (2) NRC for arbovirus and hemorrhagic fever; (3) NRC for poliomyelitis; (4) NRC for meningococci; (5) NRC to monitor the resistance of microorganisms to antibiotics; (6) NRC for evaluation of late effects of chemical substances, methods of genetic toxicology; (7) NRC for hydrobiology; (8) NRC for ecotoxicology; (9) NRC for non-ionizing radiation; (10) NRC for hydrothermal microclimate; (11) NRC for exposure tests xenobiotics; (12) NRC for morbilli, rubella and parotitis; (13) NRC for environmental microbiology; (14) NRC on pesticide residues; (15) NRC for salmonella; (16) NRC for microbial autovaccines; (17) NRC health issues for urban air pollution; (18) NRC for noise and vibration; (19) Information Center for bacteriological (biological) and toxin weapons; (20) NRC for impact assessment of ambient air and air of enclosed spaces non-productive nature of population health; (21) NRC for toxoplasmosis; (22) NRC for exposure assessment and health risk; (23) NRC for pertussis and parapertussis; (24) NRC for syphilis; (25) NRC for hygienic drinking water problems; (26) NRC for listeriosis; (27) NRC for intestinal parasitosis; (28) NRC for diphtheria; (29) NRC for vibrionaceae; (30) NRC for environmental mycology; (31) NRC issues for fibrous dusts; (32) NRC for thermotolerant amoebae; (33) NRC issues for coal mines; (34) NRC for packaging materials; (35) NRC for haemophilus infections; (36) NRC for Legionella.

Terrestrial Analogs to Mars: NRC Community Panel Decadal Report

Science.gov (United States)

Farr, T. G.

2002-12-01

A report was completed recently by a Community Panel for the NRC Decadal Study of Solar System Exploration. The desire was for a review of the current state of knowledge and for recommendations for action over the next decade. The topic of this panel, Terrestrial Analogs to Mars, was chosen to bring attention to the need for an increase in analog studies in support of the increased pace of Mars exploration. It is well recognized that interpretations of Mars must begin with the Earth as a reference. The most successful comparisons have focused on understanding geologic processes on the Earth well enough to extrapolate to Mars' environment. Several facets of terrestrial analog studies have been pursued and are continuing. These studies include field workshops, characterization of terrestrial analog sites, instrument tests, laboratory measurements (including analysis of martian meteorites), and computer and laboratory modeling. The combination of all of these activities allows scientists to constrain the processes operating in specific terrestrial environments and extrapolate how similar processes could affect Mars. The Terrestrial Analogs for Mars Community Panel has considered the following two key questions: (1) How do terrestrial analog studies tie in to the overarching science questions about life, past climate, and geologic evolution of Mars, and (2) How can future instrumentation be used to address these questions. The panel considered the issues of data collection and archiving, value of field workshops, laboratory measurements and modeling, human exploration issues, association with other areas of solar system exploration, and education and public outreach activities. Parts of this work were performed under contract to NASA.

Software for automated tracking of open items at NRC

International Nuclear Information System (INIS)

DeWispelare, A.R.; Mackin, P.C.; Johnson, R.L.

1995-01-01

The Open Item Tracking System (OITS) was developed in response to the Nuclear Regulatory Commission (NRC) need for a reliable, easy to use automated database system, to track all open (awaiting resolution) items related to regulatory, institutional, and technical uncertainties for the Department of Energy's (DOE's) high-level waste (HLW) disposal program. The OITS system was integrated with the Regulatory Program Database (RPD) Version 1.1, resulting in the RPD/OITS Version 2.0 system. RPD/OITS is a network bases system with client server architecture and a graphical user interface. This paper outlines the system and results of its implementation

78 FR 28244 - Agency Information Collection Activities; Proposed Collection; Comment Request

Science.gov (United States)

2013-05-14

... Licensing of Production and Utilization Facilities,'' specifies technical information and data to be... NUCLEAR REGULATORY COMMISSION [Docket No. NRC-2013-0085] Agency Information Collection Activities; Proposed Collection; Comment Request AGENCY: Nuclear Regulatory Commission. ACTION: Notice of pending NRC...

Review and evaluation of the Nuclear Regulatory Commission Safety Research Program for Fiscal Years 1984 and 1985

International Nuclear Information System (INIS)

1983-02-01

This is the sixth report by the Advisory Committee on Reactor Safeguards (ACRS) that has been prepared in response to the Congressional requirement for an annual report on the Nuclear Regulatory Commission (NRC) Reactor Safety Research Program. Part I is a compilation of our general comments and recommendations regarding the NRC Safety Research Program, and includes budget recommendations and an identification of matters of special importance that deserve increased emphasis. It is intended to serve as an Executive Summary. Part II is divided into ten chapters, each of which represents a Decision Unit of the NRC research program. In each chapter, specific comments are included on the research involved in the Decision Unit, an assessment of priorities, and recommendations regarding new directions and levels of funding

Characterization of Extracellular Dextranase from a Novel Halophilic Bacillus subtilis NRC-B233b a Mutagenic Honey Isolate under Solid State Fermentation

Directory of Open Access Journals (Sweden)

Mona A. Esawy

2012-01-01

Full Text Available Bacillus subtilis NRC-B233b was isolated from Libyan honey sample proved to be a potent dextranase producer by applying solid state fermentation and utilizing corn flour as the sole carbon source. The optimized culture conditions for dextranase productions were 37°C, pH 10, 32 h, and 20% (v/w moisture content. A unique character of this isolate is its ability to produce steady dextranase irrespective to the presence of NaCl in the medium. The addition of 0.175 Mm CrCl3 increased the enzyme production by about 4.5 fold. Further improvement in enzyme production was achieved by simple UV mutation which increased the enzyme production up to about 2842 U/g. The crude extract has been partially purified about 112-fold from crude extract by only two purification steps involving ultra-filtration. The partially purified dextranase showed its maximum activity at pH 9.2 and 70°C. It retained full activity (100% at 75°C for one hour. Dextranase activity increased about 4 fold in the presence of 10% NaCl. This enzyme showed variable degradation effect on different types of dextran and its derivatives. The treatment of viscous sugar cane juice with the enzyme preparation resulted in clear visual dextran hydrolysis. These results suggest that the dextranase produced by Bacillus subtilis NRC-B233b is industrially applicable.

Comparisons of ANS, ASME, AWS, and NFPA standards cited in the NRC standard review plan, NUREG-0800, and related documents

International Nuclear Information System (INIS)

Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Spiesman, J.B.

1995-11-01

This report provides the results of comparisons of the cited and latest versions of ANS, ASME, AWS and NFPA standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC's Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review

Observations and recommendations for further research regarding environmentally assisted fatigue evaluation methods

Energy Technology Data Exchange (ETDEWEB)

Stevens, G.L.; Tregoning, R.L. [U.S. Nuclear Regulatory Commission (U.S. NRC), Rockville, MD (United States); Chopra, O.K. [Argonne National Laboratory, Argonne, IL (United States)

2014-07-01

The U.S. Nuclear Regulatory Commission (NRC) and Argonne National Laboratory (ANL) have completed research activities on environmentally assisted fatigue (EAF) methods. This work has led to a revision of NUREG/CR-6909 in its entirety, a draft of which is forthcoming for public review and comment. These activities addressed the following areas: - Air and water fatigue curves were re-developed using a much larger fatigue (ε-N) database. The additional data include an expansion in the ε-N data previously used by the NRC and ANL by as much as 50%. - The environmental fatigue multiplier (F{sub en}) expressions for carbon, low-alloy, stainless, and nickel-alloy steels were revised. - The revised F{sub en} expressions address comments from interested stakeholders related to: (a) the constants in previous F{sub en} expressions that results in F{sub en} values of approximately 2.0 even when the strain rate is very high or the temperature is very low, (b) the temperature dependence of the F{sub en} expression for carbon and low-alloy steels, and (c) the dependence of F{sub en} on water chemistry for austenitic stainless steels. - In addition, the appropriateness of a strain threshold and the possible effects of hold periods were evaluated. - The potential effects of dynamic strain aging (DSA) on cyclic deformation and environmental effects were discussed. - The revised F{sub en} expressions proposed were validated to the extent possible by comparing the results of five different experimental data sets obtained from fatigue tests that simulate actual plant conditions to estimates of fatigue usage adjusted for environmental effects using the updated F{sub en} expressions. In the course of performing the foregoing EAF research activities, the NRC and ANL observed several areas where further research could yield reduced conservatism in EAF evaluation. These include more refined, material-specific fatigue (S-N) curves, S-N curves for ferritic materials based on material tensile

Design basis for the NRC Operations Center

Energy Technology Data Exchange (ETDEWEB)

Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

1983-05-01

This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project.

Design basis for the NRC Operations Center

International Nuclear Information System (INIS)

Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

1983-05-01

This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project

Proceedings of the 23rd DOE/NRC nuclear air cleaning conference

Energy Technology Data Exchange (ETDEWEB)

First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

1995-02-01

The report contains the papers presented at the 23rd DOE/NRC Nuclear Air Cleaning Conference and the associated discussions. Major topics are: (1) nuclear air cleaning codes, (2) nuclear waste, (3) filters and filtration, (4) effluent stack monitoring, (5) gas processing, (6) adsorption, (7) air treatment systems, (8) source terms and accident analysis, and (9) fuel reprocessing. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

The U.S. Nuclear Regulatory Commission Thermal-Hydraulic Research Program: Maintaining expertise in a changing environment

International Nuclear Information System (INIS)

Sheron, B.W.; Shotkin, L.M.; Baratta, A.J.

1993-01-01

Throughout the 1970s and early 1980s, the U.S. Nuclear Regulatory Commission's (NRC's) thermal-hydraulic research program enjoyed ample funding, sponsored extensive experimental and analytical development programs, and attracted worldwide expertise. With the completion of the major experimental programs and with the promulgation of the revised emergency core-cooling system rule, both the funding and prominence of thermal-hydraulic research at the NRC have declined in recent years. This has led justifiably to the concern by some that the program may no longer have the minimal elements needed to maintain both expertise and world-class status. The purpose of this article is to describe the NRC's current thermal-hydraulic research program and to show how this program ensures maintenance of a viable, robust research effort and retention of needed expertise and international leadership

Energy Technology Division research summary 1997

International Nuclear Information System (INIS)

1997-01-01

reactors (LWRS) is funded by the US Nuclear Regulatory Commission (NRC). In addition to our ongoing work on environmentally assisted cracking and steam generator integrity, a major new multiyear program has been initiated to assess the performance of high-burnup fuel during loss-of-coolant accidents. The bulk of the NRC research work is carried out in four ET sections: Corrosion: Mechanics of Materials; Irradiation Performance: and Sensors, Instrumentation, and Nondestructive Evaluation. The Transportation of Hazardous Materials Section is the other main contributor; staff from that Section have worked closely with NRC staff to draft a new version of the NRC Standard Review Plan that will be used to provide guidance to NRC reviewers of applications for the renewal of nuclear plant licenses

Energy Technology Division research summary 1997.

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-21

nuclear reactors (LWRS) is funded by the US Nuclear Regulatory Commission (NRC). In addition to our ongoing work on environmentally assisted cracking and steam generator integrity, a major new multiyear program has been initiated to assess the performance of high-burnup fuel during loss-of-coolant accidents. The bulk of the NRC research work is carried out in four ET sections: Corrosion: Mechanics of Materials; Irradiation Performance: and Sensors, Instrumentation, and Nondestructive Evaluation. The Transportation of Hazardous Materials Section is the other main contributor; staff from that Section have worked closely with NRC staff to draft a new version of the NRC Standard Review Plan that will be used to provide guidance to NRC reviewers of applications for the renewal of nuclear plant licenses.

Components of the CCR4-NOT complex function as nuclear hormone receptor coactivators via association with the NRC-interacting Factor NIF-1.

Science.gov (United States)

Garapaty, Shivani; Mahajan, Muktar A; Samuels, Herbert H

2008-03-14

CCR4-NOT is an evolutionarily conserved, multicomponent complex known to be involved in transcription as well as mRNA degradation. Various subunits (e.g. CNOT1 and CNOT7/CAF1) have been reported to be involved in influencing nuclear hormone receptor activities. Here, we show that CCR4/CNOT6 and RCD1/CNOT9, members of the CCR4-NOT complex, potentiate nuclear receptor activity. RCD1 interacts in vivo and in vitro with NIF-1 (NRC-interacting factor), a previously characterized nuclear receptor cotransducer that activates nuclear receptors via its interaction with NRC. As with NIF-1, RCD1 and CCR4 do not directly associate with nuclear receptors; however, they enhance ligand-dependent transcriptional activation by nuclear hormone receptors. CCR4 mediates its effect through the ligand binding domain of nuclear receptors and small interference RNA-mediated silencing of endogenous CCR4 results in a marked decrease in nuclear receptor activation. Furthermore, knockdown of CCR4 results in an attenuated stimulation of RARalpha target genes (e.g. Sox9 and HoxA1) as shown by quantitative PCR assays. The silencing of endogenous NIF-1 also resulted in a comparable decrease in the RAR-mediated induction of both Sox9 and HoxA1. Furthermore, CCR4 associates in vivo with NIF-1. In addition, the CCR4-enhanced transcriptional activation by nuclear receptors is dependent on NIF-1. The small interference RNA-mediated knockdown of NIF-1 blocks the ligand-dependent potentiating effect of CCR4. Our results suggest that CCR4 plays a role in the regulation of certain endogenous RARalpha target genes and that RCD1 and CCR4 might mediate their function through their interaction with NIF-1.

Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank

International Nuclear Information System (INIS)

Scofield, N.R.; Hardy, H.A.; Laats, E.T.

1984-03-01

The United States NRC has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data that is to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the NRC. The NRC/DAE Data Bank and the capabilities of the data access software are described in this document

Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank

International Nuclear Information System (INIS)

Scofield, N.R.; Hardy, H.A.; Laats, E.T.

1983-02-01

The United States Nuclear Regulatory Commission (NRC) has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water safety research programs. Local direction of the program is provided by E G and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data that is to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the NRC. The NRC/DAE Data Bank and the capabilities of the data access software are described

Fungal communication requires the MAK-2 pathway elements STE-20 and RAS-2, the NRC-1 adapter STE-50 and the MAP kinase scaffold HAM-5.