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Sample records for safety commission rsk

  1. Recommendations of the Reactor Safety Commission (RSK) 1981-1983. Vol. 5

    International Nuclear Information System (INIS)

    1984-02-01

    Since the reorganization of the RSK in 1971 the recommendations are published in the ''Bundesanzeiger'' (BAnz). This makes the work of the RSK transparent for the public. After publication of the recommendations in the Bundesanzeiger, the Office of the RSK publishes them once more as a summary report by order of the Federal Minister of Interior. The reports are divided generally into two parts: Part I contains the recommendations which are given by the RSK; part II contains the official notices concerning the RSK. There is also a subject index. In addition volume 5 contains as part III all papers which were held on the occasion of the 25th anniversary of the Reactor Safety Commission. (orig./HP) [de

  2. Recommendations of the Reactor Safety Commission (RSK) 1975-1977. Vol. 3

    International Nuclear Information System (INIS)

    Schneider, M.

    1978-08-01

    After the recommendations are published in the 'Bundesanzeiger' the Office of the RSK publishes them as a closed report, by order of the Federal Minister of the Interior. The reports are devided in two parts: Part I contains the recommendations which are given by the RSK; part II contains the official notices concerning the RSK. There also is a subject index. Three volumes are published by now: Volume 1: IRS-A-9 (December 1975), Recommendations of the RSK 1971 to 1974 (68th to 96th meeting), pages: I-1 to I-116 and II-1 to II-23 appendix a: RSK-guide lines for PWR, edition 04.74; Volume 2: IRS-A-11 (August 1976), Recommendations of the RSK 1974 to 1975, (97th to 105th meeting), pages: I-117 to I-145; Volume 3: GRS-12 (August 1978), Recommendations of the RSK 1975 to 1977 (106th to 129th meeting), pages: I-146 to I-276 and II-24 to II-25. Volume 3 also contains the recommendation on German Fuel Cycle Center which was given by the Reactor Safety Commision (RSK) in community with the Radiological Protection Commission (SSK), in autumn 1977. (orig./HP) 891 HP [de

  3. RSK-guidelines for PWR reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The RSK guidelines for PWA reactors of April 24, 1974, have been revised and amended in this edition. The RSK presents a summary of safety requirements to be observed in the design, construction, and operation of PWR reactors in the form of guidelines. From January 1979 onwards these guidelines will be the basis of siting and safety considerations for new PWR reactors, and newly built nuclear power plants will have to form these guidelines. They are not binding for existing nuclear power plants under construction or in operation. It will be a matter of individual discussion whether or not the guidelines will be applied in these plants. The main purpose of the guidelines is to facilitate discussion among RSK members and to give early information on necessary safety requirements. If the guidelines are observed by producers and operators, the RSK will make statements on individual projects at short notice. (orig./HP) [de

  4. Reactor Safety Commission Code of Practice for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    1990-01-01

    The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

  5. Announcement of recommendations of the Reaktor-Sicherheitskommission. As of 24 July 1997. Joint recommendations of RSK and GPR for safety requirements of future nuclear PWR-type power plants. English versions published in the years 1995 through 1997

    International Nuclear Information System (INIS)

    1997-01-01

    The recommendations, most parts given in English, refer to the European Pressurized Water Reactor (EPR) and have been established by the German RSK (reactor safety commission), the corresponding French organization GPR and the German SSK (radiation protection commission). This publication continues earlier joint recommendations by the national bodies, last published by the German BMU (responsible German ministry) on 5 May 1995, in BAnz. page 7452. The safety recommendations establish the basis for further activities in the Franco-German project for development of the EPR, a PWR type reactor of the next generation. (CB) [de

  6. Announcement of recommendations by the Reactor Safety Commission (RSK), presented at its 184. meeting on March 23, 1983

    International Nuclear Information System (INIS)

    1983-01-01

    The Reactor Safety Commission concluded that from the safety engineering point of view there are no misgivings about granting a licence under atomic energy law for away-from-reactor storage and operation of the transport container store at Ahaus and Gorleben. (orig.) [de

  7. RSK2 is a modulator of craniofacial development.

    Directory of Open Access Journals (Sweden)

    Virginie Laugel-Haushalter

    Full Text Available BACKGROUND: The RSK2 gene is responsible for Coffin-Lowry syndrome, an X-linked dominant genetic disorder causing mental retardation, skeletal growth delays, with craniofacial and digital abnormalities typically associated with this syndrome. Craniofacial and dental anomalies encountered in this rare disease have been poorly characterized. METHODOLOGY/PRINCIPAL FINDINGS: We examined, using X-Ray microtomographic analysis, the variable craniofacial dysmorphism and dental anomalies present in Rsk2 knockout mice, a model of Coffin-Lowry syndrome, as well as in triple Rsk1,2,3 knockout mutants. We report Rsk mutation produces surpernumerary teeth midline/mesial to the first molar. This highly penetrant phenotype recapitulates more ancestral tooth structures lost with evolution. Most likely this leads to a reduction of the maxillary diastema. Abnormalities of molar shape were generally restricted to the mesial part of both upper and lower first molars (M1. Expression analysis of the four Rsk genes (Rsk1, 2, 3 and 4 was performed at various stages of odontogenesis in wild-type (WT mice. Rsk2 is expressed in the mesenchymal, neural crest-derived compartment, correlating with proliferative areas of the developing teeth. This is consistent with RSK2 functioning in cell cycle control and growth regulation, functions potentially responsible for severe dental phenotypes. To uncover molecular pathways involved in the etiology of these defects, we performed a comparative transcriptomic (DNA microarray analysis of mandibular wild-type versus Rsk2-/Y molars. We further demonstrated a misregulation of several critical genes, using a Rsk2 shRNA knock-down strategy in molar tooth germs cultured in vitro. CONCLUSIONS: This study reveals RSK2 regulates craniofacial development including tooth development and patterning via novel transcriptional targets.

  8. Safety evaluation of the nuclear power plant at Cattenom

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    This is a systematic compilation of the material which was dealt with at the level of the German-French Commission (on questions of the safety of nuclear installations) in this discussions about the nuclear power plant at Cattenom. As a supplement to the report published already in 1982, the Commission has officially released its deliberation results on the subjects constructive safety measures, radiological effects, and precautions in case of an emergency. The allegations according to which the installation is wanting in safety are countered by the joint statement of the chairmen of GPR (Permanent Group on Reactors) and RSK (German Commission on Reactor Safety) of August 29, 1986. (HSCH) [de

  9. Essential role of RSK2 in c-Fos-dependent osteosarcoma development.

    Science.gov (United States)

    David, Jean-Pierre; Mehic, Denis; Bakiri, Latifa; Schilling, Arndt F; Mandic, Vice; Priemel, Matthias; Idarraga, Maria Helena; Reschke, Markus O; Hoffmann, Oskar; Amling, Michael; Wagner, Erwin F

    2005-03-01

    Inactivation of the growth factor-regulated S6 kinase RSK2 causes Coffin-Lowry syndrome in humans, an X-linked mental retardation condition associated with progressive skeletal abnormalities. Here we show that mice lacking RSK2 develop a progressive skeletal disease, osteopenia due to impaired osteoblast function and normal osteoclast differentiation. The phenotype is associated with decreased expression of Phex, an endopeptidase regulating bone mineralization. This defect is probably not mediated by RSK2-dependent phosphorylation of c-Fos on serine 362 in the C-terminus. However, in the absence of RSK2, c-Fos-dependent osteosarcoma formation is impaired. The lack of c-Fos phosphorylation leads to reduced c-Fos protein levels, which are thought to be responsible for decreased proliferation and increased apoptosis of transformed osteoblasts. Therefore, RSK2-dependent stabilization of c-Fos is essential for osteosarcoma formation in mice and may also be important for human osteosarcomas.

  10. RSK2-induced stress tolerance enhances cell survival signals mediated by inhibition of GSK3β activity

    International Nuclear Information System (INIS)

    Lee, Cheol-Jung; Lee, Mee-Hyun; Lee, Ji-Young; Song, Ji Hong; Lee, Hye Suk; Cho, Yong-Yeon

    2013-01-01

    Highlights: •We demonstrated a novel function of RSK2 in stress tolerance. •RSK2 deficiency enhanced apoptosis by calcium stress. •RSK2-mediated GSK3β phosphorylation at serine 9 increased calcium-induced stress tolerance. •Calcium stress-induced apoptosis inhibited by adding back of RSK2 into RSK2 −/− MEFs. -- Abstract: Our previous studies demonstrated that RSK2 plays a key role in cell proliferation and transformation induced by tumor promoters such as epidermal growth factor (EGF) in mouse and human skin cells. However, no direct evidence has been found regarding the relationship of RSK2 and cell survival. In this study, we found that RSK2 interacted and phosphorylated GSK3β at Ser9. Notably, GSK3β phosphorylation at Ser9 was suppressed in RSK2 −/− MEFs compared with RSK2 +/+ MEFs by stimulation of EGF and calcium ionophore A23187, a cellular calcium stressor. In proliferation, we found that RSK2 deficiency suppressed cell proliferation compared with RSK2 +/+ MEFs. In contrast, GSK3β −/− MEFs induced the cell proliferation compared with GSK3β +/+ MEFs. Importantly, RSK2 −/− MEFs were induced severe cellular morphology change by A23187 and enhanced G1/G0 and sub-G1 accumulation of the cell cycle phase compared with RSK2 +/+ MEFs. The sub-G1 induction in RSK2 −/− MEFs by A23187 was correlated with increase of cytochrome c release, caspase-3 cleavage and apoptotic DNA fragmentation compared with RSK2 +/+ MEFs. Notably, return back of RSK2 into RSK2 −/− MEFs restored A23187-induced morphological change, and decreased apoptosis, apoptotic DNA fragmentation and caspase-3 induction compared with RSK2 −/− /mock MEFs. Taken together, our results demonstrated that RSK2 plays an important role in stress-tolerance and cell survival, resulting in cell proliferation and cancer development

  11. Recommendations of the Reaktorsicherheitskommission (RSK) for the period 1978 to 1980. Vol. 4

    International Nuclear Information System (INIS)

    Neusser, P.

    1981-06-01

    Since the RSK has been newly established and reorganized in 1971 by the then responsible Federal Minister of Education and Science, the recommendations are published in the 'Bundesanzeiger' (BAZ). This makes the work of the RSK transparent for the public. After the recommendations have been published in the 'Bundesanzeiger', the Office of the RSK publishes them once more as a summary report by order of the Federal Minister of the Interior. The reports are divided into two parts: Part I contains the recommendations which are given by the RSK; part II contains the official notices concerning the RSK. There is also a subject index. Four volumes have been published by now. (orig./HP) [de

  12. Computational and Biochemical Discovery of RSK2 as a Novel Target for Epigallocatechin Gallate (EGCG.

    Directory of Open Access Journals (Sweden)

    Hanyong Chen

    Full Text Available The most active anticancer component in green tea is epigallocatechin-3-gallate (EGCG. Protein interaction with EGCG is a critical step for mediating the effects of EGCG on the regulation of various key molecules involved in signal transduction. By using computational docking screening methods for protein identification, we identified a serine/threonine kinase, 90-kDa ribosomal S6 kinase (RSK2, as a novel molecular target of EGCG. RSK2 includes two kinase catalytic domains in the N-terminal (NTD and the C-terminal (CTD and RSK2 full activation requires phosphorylation of both terminals. The computer prediction was confirmed by an in vitro kinase assay in which EGCG inhibited RSK2 activity in a dose-dependent manner. Pull-down assay results showed that EGCG could bind with RSK2 at both kinase catalytic domains in vitro and ex vivo. Furthermore, results of an ATP competition assay and a computer-docking model showed that EGCG binds with RSK2 in an ATP-dependent manner. In RSK2+/+ and RSK2-/- murine embryonic fibroblasts, EGCG decreased viability only in the presence of RSK2. EGCG also suppressed epidermal growth factor-induced neoplastic cell transformation by inhibiting phosphorylation of histone H3 at Ser10. Overall, these results indicate that RSK2 is a novel molecular target of EGCG.

  13. Official communication of the Safety Commission

    CERN Multimedia

    DG Unit

    2009-01-01

    The Prevention and Training section of the Safety Commission, would like to inform you that the new Safety Awareness course for newcomers will replace the welcome video in building 55 as of 2 April. The 3 levels (‘Safety at CERN’, ‘General Risks’ and ‘Specific Risks’) followed by 3 tests will determine access to CERN. Thanks to the SIR (Safety Information Registration, http://sir.cern.ch) application, it will be possible for you to follow the awareness course from your computer. For more information, go to the Safety Commission web site: http://safety-commission.web.cern.ch

  14. Official communication of the Safety Commission

    CERN Multimedia

    DG Unit

    2009-01-01

    We, the Prevention and Training section of the Safety Commission, would like to inform you that the new Safety Awareness course for newcomers will replace the welcome video in building 55 as of the 2nd April. The 3 levels (‘Safety at CERN’, ‘General Risks’ and ‘Specific Risks’) followed by 3 tests will determine access to CERN. Thanks to the SIR (Safety Information Registration, http://sir.cern.ch) application, it will be possible for you to follow the awareness course from your computer. For more information, go to the Safety Commission web site: http://safety-commission.web.cern.ch

  15. Permanent Commission for Health and Safety

    CERN Multimedia

    Association du personnel

    2007-01-01

    The mandate of the Staff Association's permanent commission for Health and Safety is to examine all aspects of health and safety related to the working environment at CERN. In no way does it wish to be a substitute for the official bodies that are responsible for these matters. The Commission's aim is to formulate remarks on and make proposals about these questions to the relevant bodies and the CERN Management. Its main focus is the safety of the CERN staff but it is also concerned with the safety of the installations and of the CERN environment. The Commission reports to the Staff Council and the Executive Committee of the Staff Association.

  16. Identification of quercitrin as an inhibitor of the p90 S6 ribosomal kinase (RSK): structure of its complex with the N-terminal domain of RSK2 at 1.8 Å resolution

    Energy Technology Data Exchange (ETDEWEB)

    Derewenda, Urszula; Artamonov, Mykhaylo; Szukalska, Gabriela; Utepbergenov, Darkhan; Olekhnovich, Natalya [University of Virginia, Charlottesville, VA 22908-0736 (United States); Parikh, Hardik I.; Kellogg, Glen E. [Virginia Commonwealth University, Richmond, VA 23298-0540 (United States); Somlyo, Avril V.; Derewenda, Zygmunt S., E-mail: zsd4n@virginia.edu [University of Virginia, Charlottesville, VA 22908-0736 (United States)

    2013-02-01

    The crystal structure of quercitrin, a naturally occurring flavonol glycoside, has been determined in a complex with the N-terminal kinase domain of murine RSK2. The structure revealed that quercitrin inhibits the RSK2 kinase in the same fashion as another known inhibitor, SL0101. Members of the RSK family of kinases constitute attractive targets for drug design, but a lack of structural information regarding the mechanism of selective inhibitors impedes progress in this field. The crystal structure of the N-terminal kinase domain (residues 45–346) of mouse RSK2, or RSK2{sup NTKD}, has recently been described in complex with one of only two known selective inhibitors, a rare naturally occurring flavonol glycoside, kaempferol 3-O-(3′′,4′′-di-O-acetyl-α-l-rhamnopyranoside), known as SL0101. Based on this structure, it was hypothesized that quercitrin (quercetin 3-O-α-l-rhamnopyranoside), a related but ubiquitous and inexpensive compound, might also act as an RSK inhibitor. Here, it is demonstrated that quercitrin binds to RSK2{sup NTKD} with a dissociation constant (K{sub d}) of 5.8 µM as determined by isothermal titration calorimetry, and a crystal structure of the binary complex at 1.8 Å resolution is reported. The crystal structure reveals a very similar mode of binding to that recently reported for SL0101. Closer inspection shows a number of small but significant differences that explain the slightly higher K{sub d} for quercitrin compared with SL0101. It is also shown that quercitrin can effectively substitute for SL0101 in a biological assay, in which it significantly suppresses the contractile force in rabbit pulmonary artery smooth muscle in response to Ca{sup 2+}.

  17. Identification of quercitrin as an inhibitor of the p90 S6 ribosomal kinase (RSK): structure of its complex with the N-terminal domain of RSK2 at 1.8 Å resolution

    International Nuclear Information System (INIS)

    Derewenda, Urszula; Artamonov, Mykhaylo; Szukalska, Gabriela; Utepbergenov, Darkhan; Olekhnovich, Natalya; Parikh, Hardik I.; Kellogg, Glen E.; Somlyo, Avril V.; Derewenda, Zygmunt S.

    2013-01-01

    The crystal structure of quercitrin, a naturally occurring flavonol glycoside, has been determined in a complex with the N-terminal kinase domain of murine RSK2. The structure revealed that quercitrin inhibits the RSK2 kinase in the same fashion as another known inhibitor, SL0101. Members of the RSK family of kinases constitute attractive targets for drug design, but a lack of structural information regarding the mechanism of selective inhibitors impedes progress in this field. The crystal structure of the N-terminal kinase domain (residues 45–346) of mouse RSK2, or RSK2 NTKD , has recently been described in complex with one of only two known selective inhibitors, a rare naturally occurring flavonol glycoside, kaempferol 3-O-(3′′,4′′-di-O-acetyl-α-l-rhamnopyranoside), known as SL0101. Based on this structure, it was hypothesized that quercitrin (quercetin 3-O-α-l-rhamnopyranoside), a related but ubiquitous and inexpensive compound, might also act as an RSK inhibitor. Here, it is demonstrated that quercitrin binds to RSK2 NTKD with a dissociation constant (K d ) of 5.8 µM as determined by isothermal titration calorimetry, and a crystal structure of the binary complex at 1.8 Å resolution is reported. The crystal structure reveals a very similar mode of binding to that recently reported for SL0101. Closer inspection shows a number of small but significant differences that explain the slightly higher K d for quercitrin compared with SL0101. It is also shown that quercitrin can effectively substitute for SL0101 in a biological assay, in which it significantly suppresses the contractile force in rabbit pulmonary artery smooth muscle in response to Ca 2+

  18. Commissioning of research reactors. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

  19. Phosphoproteomic Analysis of KSHV-Infected Cells Reveals Roles of ORF45-Activated RSK during Lytic Replication.

    Directory of Open Access Journals (Sweden)

    Denis Avey

    2015-07-01

    Full Text Available Kaposi's Sarcoma-Associated Herpesvirus (KSHV is an oncogenic virus which has adapted unique mechanisms to modulate the cellular microenvironment of its human host. The pathogenesis of KSHV is intimately linked to its manipulation of cellular signaling pathways, including the extracellular signal-regulated kinase (ERK mitogen-activated protein kinase (MAPK pathway. We have previously shown that KSHV ORF45 contributes to the sustained activation of both ERK and p90 ribosomal S6 kinase (RSK, a major functional mediator of ERK/MAPK signaling during KSHV lytic replication. ORF45-activated RSK is required for optimal KSHV lytic gene expression and progeny virion production, though the underlying mechanisms downstream of this activation are still unclear. We hypothesized that the activation of RSK by ORF45 causes differential phosphorylation of cellular and viral substrates, affecting biological processes essential for efficient KSHV lytic replication. Accordingly, we observed widespread and significant differences in protein phosphorylation upon induction of lytic replication. Mass-spectrometry-based phosphoproteomic screening identified putative substrates of ORF45-activated RSK in KSHV-infected cells. Bioinformatic analyses revealed that nuclear proteins, including several transcriptional regulators, were overrepresented among these candidates. We validated the ORF45/RSK-dependent phosphorylation of several putative substrates by employing KSHV BAC mutagenesis, kinase inhibitor treatments, and/or CRISPR-mediated knockout of RSK in KSHV-infected cells. Furthermore, we assessed the consequences of knocking out these substrates on ORF45/RSK-dependent regulation of gene expression and KSHV progeny virion production. Finally, we show data to support that ORF45 regulates the translational efficiency of a subset of viral/cellular genes with complex secondary structure in their 5' UTR. Altogether, these data shed light on the mechanisms by which KSHV ORF45

  20. 76 FR 7853 - Patient Safety Organizations: Voluntary Delisting From Oregon Patient Safety Commission

    Science.gov (United States)

    2011-02-11

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety Organizations: Voluntary Delisting From Oregon Patient Safety Commission AGENCY: Agency for Healthcare Research and Quality (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: Oregon Patient Safety Commission: AHRQ...

  1. Kaempferol targets RSK2 and MSK1 to suppress ultraviolet radiation-induced skin cancer

    Science.gov (United States)

    Langfald, Alyssa; Yang, Ge; Zhang, Yi; Yu, Dong Hoon; Kim, Myoung Ok; Lee, Mee-Hyun; Li, Haitao; Bae, Ki Beom; Kim, Hong-Gyum; Ma, Wei-Ya; Bode, Ann M.; Dong, Ziming; Dong, Zigang

    2014-01-01

    Solar ultraviolet (SUV) irradiation is a major factor in skin carcinogenesis, the most common form of cancer in the USA. The mitogen-activated protein (MAP) kinase cascades are activated by SUV irradiation. The 90 kDa ribosomal S6 kinase (RSK) and mitogen and stress activated protein kinase (MSK) proteins constitute a family of protein kinases that mediate signal transduction downstream of the MAP kinase cascades. In this study, phosphorylation of RSK and MSK1 was up-regulated in human squamous cell carcinoma (SCC) and solar UV-treated mouse skin. Kaempferol, a natural flavonol, found in tea, broccoli, grapes, apples and other plant sources, is known to have anticancer activity, but its mechanisms and direct target(s) in cancer chemoprevention are unclear. Kinase array results revealed that kaempferol inhibited RSK2 and MSK1. Pull-down assay results, ATP competition and in vitro kinase assay data revealed that kaempferol interacts with RSK2 and MSK1 at the ATP-binding pocket and inhibits their respective kinase activities. Mechanistic investigations showed that kaempferol suppresses RSK2 and MSK1 kinase activities to attenuate solar UV-induced phosphorylation of CREB and histone H3 in mouse skin cells. Kaempferol was a potent inhibitor of solar UV-induced mouse skin carcinogenesis. Further analysis showed that skin from the kaempferol-treated group exhibited a substantial reduction in solar UV-induced phosphorylation of cAMP response element-binding protein (CREB), c-Fos and histone H3. Overall, our results identify kaempferol as a safe and novel chemopreventive agent against solar UV-induced skin carcinogenesis that acts by targeting RSK2 and MSK1. PMID:24994661

  2. Kaempferol targets RSK2 and MSK1 to suppress UV radiation-induced skin cancer.

    Science.gov (United States)

    Yao, Ke; Chen, Hanyong; Liu, Kangdong; Langfald, Alyssa; Yang, Ge; Zhang, Yi; Yu, Dong Hoon; Kim, Myoung Ok; Lee, Mee-Hyun; Li, Haitao; Bae, Ki Beom; Kim, Hong-Gyum; Ma, Wei-Ya; Bode, Ann M; Dong, Ziming; Dong, Zigang

    2014-09-01

    Solar UV (SUV) irradiation is a major factor in skin carcinogenesis, the most common form of cancer in the United States. The MAPK cascades are activated by SUV irradiation. The 90 kDa ribosomal S6 kinase (RSK) and mitogen and stress-activated protein kinase (MSK) proteins constitute a family of protein kinases that mediate signal transduction downstream of the MAPK cascades. In this study, phosphorylation of RSK and MSK1 was upregulated in human squamous cell carcinoma (SCC) and SUV-treated mouse skin. Kaempferol, a natural flavonol, found in tea, broccoli, grapes, apples, and other plant sources, is known to have anticancer activity, but its mechanisms and direct target(s) in cancer chemoprevention are unclear. Kinase array results revealed that kaempferol inhibited RSK2 and MSK1. Pull-down assay results, ATP competition, and in vitro kinase assay data revealed that kaempferol interacts with RSK2 and MSK1 at the ATP-binding pocket and inhibits their respective kinase activities. Mechanistic investigations showed that kaempferol suppresses RSK2 and MSK1 kinase activities to attenuate SUV-induced phosphorylation of cAMP-responsive element binding protein (CREB) and histone H3 in mouse skin cells. Kaempferol was a potent inhibitor of SUV-induced mouse skin carcinogenesis. Further analysis showed that skin from the kaempferol-treated group exhibited a substantial reduction in SUV-induced phosphorylation of CREB, c-Fos, and histone H3. Overall, our results identify kaempferol as a safe and novel chemopreventive agent against SUV-induced skin carcinogenesis that acts by targeting RSK2 and MSK1. ©2014 American Association for Cancer Research.

  3. Role and regulation of 90 kDa ribosomal S6 kinase (RSK) in signal transduction

    DEFF Research Database (Denmark)

    Frödin, M; Gammeltoft, S

    1999-01-01

    ), which were among the first substrates of ERK to be discovered and which has proven to be a ubiquitous and versatile mediator of ERK signal transduction. RSK is composed of two functional kinase domains that are activated in a sequential manner by a series of phosphorylations. Recently, a family of RSK......-related kinases that are activated by ERK as well as p38 MAPK were discovered and named mitogen- and stress-activated protein kinases (MSK). A number of cellular functions of RSK have been proposed. (1) Regulation of gene expression via association and phosphorylation of transcriptional regulators including c...

  4. RSK3 is required for concentric myocyte hypertrophy in an activated Raf1 model for Noonan syndrome.

    Science.gov (United States)

    Passariello, Catherine L; Martinez, Eliana C; Thakur, Hrishikesh; Cesareo, Maria; Li, Jinliang; Kapiloff, Michael S

    2016-04-01

    Noonan syndrome (NS) is a congenital disorder resulting from mutations of the Ras-Raf signaling pathway. Hypertrophic cardiomyopathy associated with RAF1 "RASopathy" mutations is a major risk factor for heart failure and death in NS and has been attributed to activation of MEK1/2-ERK1/2 mitogen-activated protein kinases. We recently discovered that type 3 p90 ribosomal S6 kinase (RSK3) is an ERK effector that is required, like ERK1/2, for concentric myocyte hypertrophy in response to pathological stress such as pressure overload. In order to test whether RSK3 also contributes to NS-associated hypertrophic cardiomyopathy, RSK3 knock-out mice were crossed with mice bearing the Raf1(L613V) human NS mutation. We confirmed that Raf1(L613V) knock-in confers a NS-like phenotype, including cardiac hypertrophy. Active RSK3 was increased in Raf1(L613V) mice. Constitutive RSK3 gene deletion prevented the Raf1(L613V)-dependent concentric growth in width of the cardiac myocyte and attenuated cardiac hypertrophy in female mice. These results are consistent with RSK3 being an important mediator of ERK1/2-dependent growth in RASopathy. In conjunction with previously published data showing that RSK3 is important for pathological remodeling of the heart, these data suggest that targeting of this downstream MAP-kinase pathway effector should be considered in the treatment of RASopathy-associated hypertrophic cardiomyopathy. Copyright © 2016 Elsevier Ltd. All rights reserved.

  5. Functional characterization of human RSK4, a new 90-kDa ribosomal S6 kinase, reveals constitutive activation in most cell types

    DEFF Research Database (Denmark)

    Dümmler, Bettina A; Hauge, Camilla; Silber, Joachim

    2005-01-01

    characterization of a predicted new human RSK homologue, RSK4. We showed that RSK4 is a predominantly cytosolic protein with very low expression and several characteristics of the RSK family kinases, including the presence of two functional kinase domains and a C-terminal docking site for ERK. Surprisingly......, however, in all cell types analyzed, endogenous RSK4 was maximally (constitutively) activated under serum-starved conditions where other RSKs are inactive due to their requirement for growth factor stimulation. Constitutive activation appeared to result from constitutive phosphorylation of Ser232, Ser372...

  6. The Protein Kinase RSK Family - Roles in Prostate Cancer

    National Research Council Canada - National Science Library

    Lannigan, Deborah

    2006-01-01

    The Ser/Thr protein kinase p90-kDa ribosomal S6 kinase (RSK) is an important downstream effector of mitogen-activated protein kinase but its roles in prostate cancer have not been previously examined...

  7. Magnolin inhibits cell migration and invasion by targeting the ERKs/RSK2 signaling pathway

    International Nuclear Information System (INIS)

    Lee, Cheol-Jung; Lee, Mee-Hyun; Yoo, Sun-Mi; Choi, Kyung-Il; Song, Ji-Hong; Jang, Jeong-Hoon; Oh, Sei-Ryang; Ryu, Hyung-Won; Lee, Hye-Suk; Surh, Young-Joon; Cho, Yong-Yeon

    2015-01-01

    Magnolin is a natural compound abundantly found in Magnolia flos, which has been traditionally used in oriental medicine to treat headaches, nasal congestion and anti-inflammatory reactions. Our recent results have demonstrated that magnolin targets the active pockets of ERK1 and ERK2, which are important signaling molecules in cancer cell metastasis. The aim of this study is to evaluate the effects of magnolin on cell migration and to further explore the molecular mechanisms involved. Magnolin-mediated signaling inhibition was confirmed by Western blotting using RSK2 +/+ and RSK2 −/− MEFs, A549 and NCI-H1975 lung cancer cells, and by NF-κB and Cox-2 promoter luciferase reporter assays. Inhibition of cell migration by magnolin was examined by wound healing and/or Boyden Chamber assays using JB6 Cl41 and A549 human lung cancer cells. The molecular mechanisms involved in cell migration and epithelial-to-mesenchymal transition were determined by zymography, Western blotting, real-time PCR and immunocytofluorescence. Magnolin inhibited NF-κB transactivation activity by suppressing the ERKs/RSK2 signaling pathway. Moreover, magnolin abrogated the increase in EGF-induced COX-2 protein levels and wound healing. In human lung cancer cells such as A549 and NCI-H1975, which harbor constitutive active Ras and EGFR mutants, respectively, magnolin suppressed wound healing and cell invasion as seen by a Boyden chamber assay. In addition, it was observed that magnolin inhibited MMP-2 and −9 gene expression and activity. The knockdown or knockout of RSK2 in A549 lung cancer cells or MEFs revealed that magnolin targeting ERKs/RSK2 signaling suppressed epithelial-to-mesenchymal transition by modulating EMT marker proteins such as N-cadherin, E-cadherin, Snail, Vimentin and MMPs. These results demonstrate that magnolin inhibits cell migration and invasion by targeting the ERKs/RSK2 signaling pathway. The online version of this article (doi:10.1186/s12885-015-1580-7) contains

  8. Safety of Nuclear Power Plants: Commissioning and Operation

    International Nuclear Information System (INIS)

    2011-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  9. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2017-01-01

    This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

  10. Safety Commission databases support

    CERN Document Server

    Petit, S; CERN. Geneva. TS Department

    2005-01-01

    A collaboration project between the Safety Commission (SC) and the Controls, Safety and Engineering databases group (TS/CSE) started last year. The aim of this collaboration is to transfer several SC applications from their local environments onto the D7i-MTF EDMS framework, for which the TS/CSE group is responsible. Different domains of activity and projects have been defined in the areas of equipment management, safety inspections, accidents and risks management. Priorities have been established in collaboration with SC. This paper presents the new Safety Inspections Management system (SIM) which will be put in production before the summer 2005 and reviews the constraints of both the users and the development and operational framework that needed to be taken into account. The technical solutions adopted to assure a successful production start-up and operation of the SIM system are described. Progress on other on-going projects and plans for the next year are also reported.

  11. Ribosomal Protein S6 Kinase (RSK-2 as a central effector molecule in RON receptor tyrosine kinase mediated epithelial to mesenchymal transition induced by macrophage-stimulating protein

    Directory of Open Access Journals (Sweden)

    Zhang Rui-Wen

    2011-05-01

    Full Text Available Abstract Background Epithelial to mesenchymal transition (EMT occurs during cancer cell invasion and malignant metastasis. Features of EMT include spindle-like cell morphology, loss of epithelial cellular markers and gain of mesenchymal phenotype. Activation of the RON receptor tyrosine kinase by macrophage-stimulating protein (MSP has been implicated in cellular EMT program; however, the major signaling determinant(s responsible for MSP-induced EMT is unknown. Results The study presented here demonstrates that RSK2, a downstream signaling protein of the Ras-Erk1/2 pathway, is the principal molecule that links MSP-activated RON signaling to complete EMT. Using MDCK cells expressing RON as a model, a spindle-shape based screen was conducted, which identifies RSK2 among various intracellular proteins as a potential signaling molecule responsible for MSP-induced EMT. MSP stimulation dissociated RSK2 with Erk1/2 and promoted RSK2 nuclear translocation. MSP strongly induced RSK2 phosphorylation in a dose-dependent manner. These effects relied on RON and Erk1/2 phosphorylation, which is significantly potentiated by transforming growth factor (TGF-β1, an EMT-inducing cytokine. Specific RSK inhibitor SL0101 completely prevented MSP-induced RSK phosphorylation, which results in inhibition of MSP-induced spindle-like morphology and suppression of cell migration associated with EMT. In HT-29 cancer cells that barely express RSK2, forced RSK2 expression results in EMT-like phenotype upon MSP stimulation. Moreover, specific siRNA-mediated silencing of RSK2 but not RSK1 in L3.6pl pancreatic cancer cells significantly inhibited MSP-induced EMT-like phenotype and cell migration. Conclusions MSP-induced RSK2 activation is a critical determinant linking RON signaling to cellular EMT program. Inhibition of RSK2 activity may provide a therapeutic opportunity for blocking RON-mediated cancer cell migration and subsequent invasion.

  12. Safety of Nuclear Power Plants: Commissioning and Operation

    International Nuclear Information System (INIS)

    2011-01-01

    The safety of a nuclear power plant is ensured by means of proper site selection, design, construction and commissioning, and the evaluation of these, followed by proper management, operation and maintenance of the plant. In a later phase, a proper transition to decommissioning is required. The organization and management of plant operations ensures that a high level of safety is achieved through the effective management and control of operational activities. This publication is a revision of the Safety Requirements publication Safety of Nuclear Power Plants: Operation, which was issued in 2000 as IAEA Safety Standards Series No. NS-R-2. The purpose of this revision was to restructure Safety Standards Series No. NS-R-2 in the light of new operating experience and new trends in the nuclear industry; to introduce new requirements that were not included in Safety Standards Series No. NS-R-2 on the operation of nuclear power plants; and to reflect current practices, new concepts and technical developments. This update also reflects feedback on the use of the standards, both from Member States and from the IAEA's safety related activities. The publication is presented in the new format for Safety Requirements publications. The present publication reflects the safety principles of the Fundamental Safety Principles. It has been harmonized with IAEA Safety Standards Series No. GS-R-3 on The Management System for Facilities and Activities. Guidance on the fulfilment of the safety requirements is provided in supporting Safety Guides. The terminology used in this publication is defined and explained in the IAEA Safety Glossary. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the safety objective and safety principles that are established in the Fundamental Safety Principles. This

  13. Selective alteration of adult hippocampal neurogenesis and impaired spatial pattern separation performance in the RSK2-deficient mouse model of Coffin-Lowry syndrome.

    Science.gov (United States)

    Castillon, Charlotte; Lunion, Steeve; Desvignes, Nathalie; Hanauer, André; Laroche, Serge; Poirier, Roseline

    2018-07-01

    Adult neurogenesis is involved in certain hippocampus-dependent cognitive functions and is linked to psychiatric diseases including intellectual disabilities. The Coffin-Lowry syndrome (CLS) is a developmental disorder caused by mutations in the Rsk2 gene and characterized by intellectual disabilities associated with growth retardation. How RSK2-deficiency leads to cognitive dysfunctions in CLS is however poorly understood. Here, using Rsk2 Knock-Out mice, we characterized the impact of RSK2 deficiency on adult hippocampal neurogenesis in vivo. We report that the absence of RSK2 does not affect basal proliferation, differentiation and survival of dentate gyrus adult-born neurons but alters the maturation progression of young immature newborn neurons. Moreover, when RSK2-deficient mice were submitted to spatial learning, in contrast to wild-type mice, proliferation of adult generated neurons was decreased and no pro-survival effect of learning was observed. Thus, learning failed to recruit a selective population of young newborn neurons in association with deficient long-term memory recall. Given the proposed role of the dentate gyrus and of adult-generated newborn neurons in hippocampal-dependent pattern separation function, we explored this function in a delayed non-matching to place task and in an object-place pattern separation task and report severe deficits in spatial pattern separation in Rsk2-KO mice. Together, this study reveals a previously unknown role for RSK2 in the early stages of maturation and learning-dependent involvement of adult-born dentate gyrus neurons. These alterations associated with a deficit in the ability of RSK2-deficient mice to finely discriminate relatively similar spatial configurations, may contribute to cognitive dysfunction in CLS. Copyright © 2018 Elsevier Inc. All rights reserved.

  14. BI-D1870 is a specific inhibitor of the p90 RSK (ribosomal S6 kinase) isoforms in vitro and in vivo

    DEFF Research Database (Denmark)

    Sapkota, Gopal P; Cummings, Lorna; Newell, Felicity S

    2007-01-01

    ), which then mediate many of the physiological processes that are regulated by these extracellular agonists. It can be difficult to assess the individual functions of each AGC kinase because their substrate specificities are similar. Here we describe the small molecule BI-D1870, which inhibits RSK1, RSK2......, RSK3 and RSK4 in vitro with an IC(50) of 10-30 nM, but does not signi-ficantly inhibit ten other AGC kinase members and over 40 other protein kinases tested at 100-fold higher concentrations. BI-D1870 is cell permeant and prevents the RSK-mediated phorbol ester- and EGF (epidermal growth factor......)-induced phosphoryl-ation of glycogen synthase kinase-3beta and LKB1 in human embry-onic kidney 293 cells and Rat-2 cells. In contrast, BI-D1870 does not affect the agonist-triggered phosphorylation of substrates for six other AGC kinases. Moreover, BI-D1870 does not suppress the phorbol ester- or EGF...

  15. Nuclear safety research at the European Commission's Joint Research Centre

    International Nuclear Information System (INIS)

    Toerroenen, K.

    2003-01-01

    Nuclear power plants currently generate some 35 % of electricity used in the European Union and applicant countries. Nuclear safety will therefore remain a priority for the EU, particularly in view of enlargement, the need to monitor ageing nuclear installations and the licencing of advanced new reactor systems. The European Commission's Joint Research Centre (JRC), with its long involvement and recognised competence in nuclear safety related activities, provides direct support to the European Commission services responsible for nuclear safety and civil protection. (author)

  16. Assessment of basic safety issues

    International Nuclear Information System (INIS)

    Queniart, D.

    1996-01-01

    Work on the French-German common safety approach for future nuclear power plants continued in 1994 to allow for more detailed discussion of some major issues, taking into account the options provided by the industry for the EPR (European Pressurized water Reactor) project, as described in the document entitled 'Conceptual Safety Features Review File'. Seven meetings of a GPR/RSK advisory experts subgroup, six GPR/RSK plenary sessions and six meetings of the safety authorities (DFD) dealt with the following topics: design of the systems and use of probabilistic approaches, application of a 'break preclusion' approach to the main primary pipings, protection against external hazards (aircraft crashes, explosions, earthquakes), provisions with respect to accidents involving core melt and to containment design, radiological consequences of reference accidents and accidents involving core melt at low pressure. The important aspects of the joint policy are recalled in the presentation. The whole set of GPR/RSK recommendations were agreed by the French and German safety authorities during the DFD meetings of 1994 and early 1995. The utilities decided to begin the basic design phase in February, 1995. Work is now continuing to develop the common French-German approach for future nuclear power plants, in the same way as before. In 1995, this mainly covers the design of the containment and of the systems, but also new issues such as the protection against secondary side overpressurization, radiological protection of workers and radioactive wastes. (J.S.). 3 figs., 1 tab

  17. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

  18. RSK is a principal effector of the RAS-ERK pathway for eliciting a coordinate promotile/invasive gene program and phenotype in epithelial cells

    DEFF Research Database (Denmark)

    Doehn, Ulrik; Hauge, Camilla; Frank, Scott R

    2009-01-01

    The RAS-stimulated RAF-MEK-ERK pathway confers epithelial cells with critical motile and invasive capacities during development, tissue regeneration, and carcinoma progression, often via promoting the epithelial-mesenchymal transition (EMT). Many mechanisms by which ERK exerts this control remain...... elusive. We demonstrate that the ERK-activated kinase RSK is necessary to induce mesenchymal motility and invasive capacities in nontransformed epithelial and carcinoma cells. RSK is sufficient to induce certain motile responses. Expression profiling analysis revealed that a primary role of RSK...... to stimulate motility and invasion. These findings uncover a mechanism whereby the RAS-ERK pathway controls epithelial cell motility by identifying RSK as a key effector, from which emanate multiple highly coordinate transcription-dependent mechanisms for stimulation of motility and invasive properties....

  19. Insights into the Inhibition of the p90 Ribosomal S6 Kinase (RSK) by the Flavonol Glycoside SL0101 from the 1.5 Å Crystal Structure of the N-Terminal Domain of RSK2 with Bound Inhibitor

    Energy Technology Data Exchange (ETDEWEB)

    Utepbergenov, Darkhan; Derewenda, Urszula; Olekhnovich, Natalya; Szukalska, Gabriela; Banerjee, Budhaditya; Hilinski, Michael K.; Lannigan, Deborah A.; Stukenberg, P. Todd; Derewenda, Zygmunt S. (Lodz - Poland); (UV)

    2012-09-11

    The p90 ribosomal S6 family of kinases (RSK) are potential drug targets, due to their involvement in cancer and other pathologies. There are currently only two known selective inhibitors of RSK, but the basis for selectivity is not known. One of these inhibitors is a naturally occurring kaempferol-a-l-diacetylrhamnoside, SL0101. Here, we report the crystal structure of the complex of the N-terminal kinase domain of the RSK2 isoform with SL0101 at 1.5 {angstrom} resolution. The refined atomic model reveals unprecedented structural reorganization of the protein moiety, as compared to the nucleotide-bound form. The entire N-lobe, the hinge region, and the aD-helix undergo dramatic conformational changes resulting in a rearrangement of the nucleotide binding site with concomitant formation of a highly hydrophobic pocket spatially suited to accommodate SL0101. These unexpected results will be invaluable in further optimization of the SL0101 scaffold as a promising lead for a novel class of kinase inhibitors.

  20. Safety of Nuclear Power Plants: Commissioning and Operation (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  1. Safety of Nuclear Power Plants: Commissioning and Operation (French Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  2. Safety of Nuclear Power Plants: Commissioning and Operation. Arabic Edition

    International Nuclear Information System (INIS)

    2011-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  3. Plant specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events

    International Nuclear Information System (INIS)

    2011-01-01

    The German Parliament requested (17 March 2011) a comprehensive inspection of German nuclear power plants. For this purpose independent expert commissions should perform a new risk analysis of all German NPPS and nuclear installations with respect to the lessons learned from the Fukushima (Japan) events and other extraordinary damage scenarios. The Reactor safety commission (RSK) was assigned by the German Bundesamt fuer Strahlenschutz to develop a catalogue of requirements for this safety inspection. The contribution summarizes the required inspection volume (status 30.03.2011) including the following events: natural events like earth quakes, floods, weather-based consequences and possible superposition. Additionally the following assumptions have to be considered: event independent postulated common failures or systematic faults, station blackout larger than 2 hours, long-term failure of the auxiliary cooling water supply; aggravating boundary conditions for the performance of emergency measures (non-availability of power supply), hydrogen generation and detonation hazard, restricted personnel availability, non-accessibility due to high radiation levels, impeded technical support from outside. (orig.)

  4. Application of genetic algorithm - multiple linear regressions to predict the activity of RSK inhibitors

    Directory of Open Access Journals (Sweden)

    Avval Zhila Mohajeri

    2015-01-01

    Full Text Available This paper deals with developing a linear quantitative structure-activity relationship (QSAR model for predicting the RSK inhibition activity of some new compounds. A dataset consisting of 62 pyrazino [1,2-α] indole, diazepino [1,2-α] indole, and imidazole derivatives with known inhibitory activities was used. Multiple linear regressions (MLR technique combined with the stepwise (SW and the genetic algorithm (GA methods as variable selection tools was employed. For more checking stability, robustness and predictability of the proposed models, internal and external validation techniques were used. Comparison of the results obtained, indicate that the GA-MLR model is superior to the SW-MLR model and that it isapplicable for designing novel RSK inhibitors.

  5. Regulatory requirements for demonstration of the achieved safety level at the Mochovce NPP before commissioning

    International Nuclear Information System (INIS)

    Lipar, M.

    1997-01-01

    A review of regulatory requirements for demonstration of the achieved safety level at the Mochovce NPP before commissioning is given. It contains licensing steps in Slovakia during commissioning; Status and methodology of Mochovce safety analysis report; Mochovce NPP safety enhancement program; Regulatory body policy towards Mochovce NPP safety enhancement; Recent development in Mochovce pre-operational safety enhancement program review and assessment process; Licensing steps in Slovakia during commissioning

  6. Canadian Nuclear Safety Commission's intern program

    International Nuclear Information System (INIS)

    Gilmour, P.E.

    2002-01-01

    The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

  7. The Canadian Nuclear Safety Commission's financial guarantee requirements

    International Nuclear Information System (INIS)

    Ferch, R.

    2006-01-01

    The Nuclear Safety and Control Act gives the Canadian Nuclear Safety Commission (CNSC) the legal authority to require licensees to provide financial guarantees in order to meet the purposes of the Act. CNSC policy and guidance with regard to financial guarantees is outlined, and the current status of financial guarantee requirements as applied to various CNSC licensees is described. (author)

  8. Safety improvement and results of commissioning of Mochovce NPP WWER 440/213

    International Nuclear Information System (INIS)

    Lipar, M.

    1998-01-01

    Mochovce NPP is the last one of this kind and compared to its predecessors, it is characterized by several modifications which contribute to the improvement of the safety level. In addition based on Nuclear Regulatory Authority requirements and based on documents: - IAEA - Safety Issues and their ranking for NPP WWER 440/213, - IAEA - Safety Improvement of Mochovce NPP Project Review Mission, - Riskaudit - Evaluation of the Mochovce NPP Safety Improvements. Additional safety measures have been implemented before commissioning. The consortium EUCOM (FRAMATOME - SIEMENS), SKODA Praha, ENERGOPROJEKT Praha, Russian organizations and VUJE Trnava Nuclear Power Plants research institute were selected for design and implementation of the safety measures. The papers summarized, safety requirements, safety measures implemented, results of commissioning and results of safety analysis report evaluation. (author)

  9. Convention on nuclear safety report by the government of the Federal Republic of Germany for the second extraordinary meeting in August 2012

    International Nuclear Information System (INIS)

    2012-01-01

    The nuclear consequences of the earthquake disaster in Japan represent a profound change for the peaceful use of nuclear power, also in Germany. In the light of these events, the German Federal Government, together with the Prime Ministers of the Laender in which NPPs are operated had reviewed the safety of all German NPPs by the German Reactor Safety Commission in close collaboration with the competent nuclear regulatory authorities of the Laender and, through an Ethics Commission on ''Secure Energy Supply'', also started a dialogue among the German society on the risks involved in the use of nuclear power and on the possibility of an accelerated transition to the age of renewable energies. Taking into account the results of the Reactor Safety Commission and the Ethics Commission on ''Secure Energy Supply'' as well as the absolute priority of nuclear safety, the Federal Government decided to terminate the use of nuclear power at the earliest possible date. The amendments in the Atomic Energy Act that went into force in August 2011 induce the progressive abandonment of electricity generation by NPPs in Germany by the end of 2022 at the latest. Germany took an active part in the assessment of the robustness of the NPPs in Europe (EU stress test) under the leadership of the European Nuclear Safety Regulators Group (ENSREG). The results of these reviews show that the German plants partly have considerable safety margins and that additional precautionary measures have been taken in order to prevent (preventive measures) or limit (mitigative measures) the effects of the beyond-design-basis events considered in the reviews. Based on the results of the plant-specific reviews, the RSK has derived first recommendations for further examinations. Some plant-specific improvement measures are already in implementation or planned. The results of the EU stress test will be taken into account in future RSK recommendations. On behalf of the BMU, the Gesellschaft fuer Anlagen- und

  10. 29 CFR 2200.108 - Official Seal of the Occupational Safety and Health Review Commission.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Official Seal of the Occupational Safety and Health Review... Occupational Safety and Health Review Commission. The seal of the Commission shall consist of: A gold eagle... background, encircled by a white band edged in black and inscribed “Occupational Safety and Health Review...

  11. Defective synaptic transmission and structure in the dentate gyrus and selective fear memory impairment in the Rsk2 mutant mouse model of Coffin-Lowry syndrome.

    Science.gov (United States)

    Morice, Elise; Farley, Séverine; Poirier, Roseline; Dallerac, Glenn; Chagneau, Carine; Pannetier, Solange; Hanauer, André; Davis, Sabrina; Vaillend, Cyrille; Laroche, Serge

    2013-10-01

    The Coffin-Lowry syndrome (CLS) is a syndromic form of intellectual disability caused by loss-of-function of the RSK2 serine/threonine kinase encoded by the rsk2 gene. Rsk2 knockout mice, a murine model of CLS, exhibit spatial learning and memory impairments, yet the underlying neural mechanisms are unknown. In the current study, we examined the performance of Rsk2 knockout mice in cued, trace and contextual fear memory paradigms and identified selective deficits in the consolidation and reconsolidation of hippocampal-dependent fear memories as task difficulty and hippocampal demand increase. Electrophysiological, biochemical and electron microscopy analyses were carried out in the dentate gyrus of the hippocampus to explore potential alterations in neuronal functions and structure. In vivo and in vitro electrophysiology revealed impaired synaptic transmission, decreased network excitability and reduced AMPA and NMDA conductance in Rsk2 knockout mice. In the absence of RSK2, standard measures of short-term and long-term potentiation (LTP) were normal, however LTP-induced CREB phosphorylation and expression of the transcription factors EGR1/ZIF268 were reduced and that of the scaffolding protein SHANK3 was blocked, indicating impaired activity-dependent gene regulation. At the structural level, the density of perforated and non-perforated synapses and of multiple spine boutons was not altered, however, a clear enlargement of spine neck width and post-synaptic densities indicates altered synapse ultrastructure. These findings show that RSK2 loss-of-function is associated in the dentate gyrus with multi-level alterations that encompass modifications of glutamate receptor channel properties, synaptic transmission, plasticity-associated gene expression and spine morphology, providing novel insights into the mechanisms contributing to cognitive impairments in CLS. Copyright © 2013 Elsevier Inc. All rights reserved.

  12. Lessons learned from exchanges between the french and german safety authorities. Comparison of the safety levels achieved for reactors built in these two countries

    International Nuclear Information System (INIS)

    Droulers, Y.

    1988-12-01

    It is important to emphasize, right at the beginning, the exceptional extent of the assessment work performed over several years on the nuclear power plants in each country (exchange of confidential documents, communication of incidents during the plant building stage, specialist visits to the site, joint reports by the Franco-German Commission on all important safety problems). The D.F.K. (Franco-German Commission) has been the official framework for these exchanges since 1976 (the exchanges relating to FESSENHEIM and its ''twin'' plant NECKARWESTHEIM 1 began as far back as 1973 and were pursued, when construction of CATTENOM began, by a comparison with PHILIPPSBURG). Apart from its annual plenary session, it presently comprises 6 standing working groups dealing respectively with general safety problems (including primary system technology problems and exchanges on incidents discussed by two subcommittees), emergency plans, radiation protection problems, radioactive waste, fuel cycle installations, fast breeder reactors. It is also worth noting the regular meetings held by the standing groups of experts (GPR and RSK), which have enabled periodical assessment of the extent to which the approaches of the two countries to the main safety problems are tending to converge (severe accidents, operating feedback, containment, followup on the TMI and CHERNOBYL accidents, etc) and the exchanges between the IPSN and the GRS on the corresponding research programs

  13. Catalogue of requirements for a plant-specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events; Anforderungskatalog fuer anlagenbezogene Ueberpruefungen deutscher Kernkraftwerke unter Beruecksichtigung der Ereignisse in Fukushima-I (Japan)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-03-30

    The catalogue of requirements for a plant-specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events worked out by the German RSK (reactor safety commission) includes the following inspection topics: natural events like earth quakes, floods, weather-based consequences and possible superposition; civilization-based events like airplane crash, gas release, reactor accident consequences for neighboring units, terroristic impacts, external attacks on computer-based control systems. Further event-independent assumptions have to be considered: station blackout, long-term emergency power supply requirement, failure of auxiliary cooling water supply, efficacy of preventive measures, aggravating boundary conditions for the performance of emergency measures.

  14. Toward introduction of risk informed safety regulation. Nuclear Safety Commission taskforce's interim report

    International Nuclear Information System (INIS)

    2006-01-01

    Nuclear Safety Commission's taskforce on 'Introduction of Safety Regulation Utilizing Risk Information' completed the interim report on its future subjects and directions in December 2005. Although current safety regulatory activities have been based on deterministic approach, this report shows the risk informed approach is expected to be very useful for making nuclear safety regulation and assurance activities reasonable and also for appropriate allocation of regulatory resources. For introduction of risk informed regulation, it also recommends pileups of experiences with gradual introduction and trial of the risk informed approach, improvement of plant maintenance rules and regulatory requirements utilizing risk information, and establishment of framework to assure quality of risk evaluation. (T. Tanaka)

  15. 75 FR 52046 - Development of U.S. Nuclear Regulatory Commission Safety Culture Policy Statement: Public Meeting

    Science.gov (United States)

    2010-08-24

    ... is working towards increasing the attention that is given to safety culture as part of its efforts to... NUCLEAR REGULATORY COMMISSION Development of U.S. Nuclear Regulatory Commission Safety Culture..., Nevada hearing facility to solicit comments on the revision of its draft safety culture policy statement...

  16. Specific RSK kinase inhibition by dibenzyl trisulfide and implication for therapeutic treatment of cancer.

    Science.gov (United States)

    Lowe, Henry I C; Facey, Caroline O B; Toyang, Ngeh J; Bryant, Joseph L

    2014-04-01

    The Jamaican "Guinea Hen Weed" (Petiveria alliacea L.) plant has been traditionally used in folklore medicine to treat a variety of diseases including cancer. In the present study we investigated on the therapeutic feasibility of dibenzyl trisulfide (DTS) (isolated from the Jamaican Guinea Hen Weed) as a potent small-molecule kinase inhibitor to treat cancer. We investigated the inhibitory effects of DTS against a large panel of kinases using a well-established competitive binding assay. Cell proliferation data were obtained using the WST-1 colorimetric assay. DTS inhibited the activity of the C-terminal kinase domain of RSK1 (80% compared to control) with a Kd of 1.3 μM. Anti-proliferative effects of DTS were observed in small lung, pancreatic, breast, and prostate cancer cells with IC50 values ranging from 0.34-0.84 μM. We have identified DTS as a highly selective and isoform-specific RSK1 kinase inhibitor with broad cancer therapeutic potential.

  17. Findings by the Commission Evaluating Nuclear Safety and Repository Research in Germany

    International Nuclear Information System (INIS)

    Sandtner, W.; Closs, K.D.

    2000-01-01

    The Commission Evaluating Nuclear Safety and Repository Research in Germany, which had been appointed by the German Federal Ministry of Economics on September 24, 1999, submitted its report. Here is the gist of the Commission's findings: Irrespective of the criteria established with the political decision to terminate the use of nuclear power in Germany, competence in nuclear safety must be maintained over the next few decades. Only in this way can the government perform its duty and make provisions for the future, and can the safety of nuclear facilities and waste management pathways be ensured in accordance with the international state of the art. In view of the considerable reduction in funding in recent years and also in future, measures must be taken to ensure that further decreases in-roject funding and institutionalized government financing are excluded so as to avoid further declines in terms of manpower and competence in this field. Reactor safety and repository research must be financed at a level allowing the federal government to discharge its legal duties. The full report by the Commission, with its annexes, is available on the GRS web site (http://www.grs.de) as a PDF file. (orig.) [de

  18. In vitro dynamics of supra-posomal structures in RSK4 rat sarcoma cells

    Czech Academy of Sciences Publication Activity Database

    Veselý, Pavel; Blase, C.; Matoušková, Eva; Sukhorukov, V.; Bereiter-Hahn, J.

    2005-01-01

    Roč. 40, č. 1 (2005), s. 36 ISSN 0035-9017. [Cytokinematics 2004. International Symposium on Microscopy of Live Cells in the Post Genomics Era /8./. 05.09.2004-07.09.2004, Hradec Králové] Institutional research plan: CEZ:AV0Z5052915 Keywords : RSK4 rat sarcoma cells * podosomes Subject RIV: EB - Genetics ; Molecular Biology

  19. Convention on nuclear safety report by the government of the Federal Republic of Germany for the second extraordinary meeting in August 2012; Uebereinkommen ueber nukleare Sicherheit. Bericht der Regierung der Bundesrepublik Deutschland fuer die Zweite ausserordentliche Tagung im August 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-25

    The nuclear consequences of the earthquake disaster in Japan represent a profound change for the peaceful use of nuclear power, also in Germany. In the light of these events, the German Federal Government, together with the Prime Ministers of the Laender in which NPPs are operated had reviewed the safety of all German NPPs by the German Reactor Safety Commission in close collaboration with the competent nuclear regulatory authorities of the Laender and, through an Ethics Commission on ''Secure Energy Supply'', also started a dialogue among the German society on the risks involved in the use of nuclear power and on the possibility of an accelerated transition to the age of renewable energies. Taking into account the results of the Reactor Safety Commission and the Ethics Commission on ''Secure Energy Supply'' as well as the absolute priority of nuclear safety, the Federal Government decided to terminate the use of nuclear power at the earliest possible date. The amendments in the Atomic Energy Act that went into force in August 2011 induce the progressive abandonment of electricity generation by NPPs in Germany by the end of 2022 at the latest. Germany took an active part in the assessment of the robustness of the NPPs in Europe (EU stress test) under the leadership of the European Nuclear Safety Regulators Group (ENSREG). The results of these reviews show that the German plants partly have considerable safety margins and that additional precautionary measures have been taken in order to prevent (preventive measures) or limit (mitigative measures) the effects of the beyond-design-basis events considered in the reviews. Based on the results of the plant-specific reviews, the RSK has derived first recommendations for further examinations. Some plant-specific improvement measures are already in implementation or planned. The results of the EU stress test will be taken into account in future RSK recommendations. On behalf of the

  20. Management of fire and industrial safety - challenges during commissioning of a NPP

    International Nuclear Information System (INIS)

    Maiti, Subhaschandra; Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

    2006-01-01

    Construction and commissioning period of NPP are reduced world over drastically by stringent schedule for financial and economic reasons. For meeting the schedule, commissioning of components and systems are started immediate after installation, while construction activities are continued in parallel at the same place. Parallel activities' and 'Time Constraint' have brought new challenges to 'Management of Fire and Industrial Safely' during commissioning. An innovative approach was used during such phase of commissioning of TAPP-3 and 4. This paper outlines challenges encountered during this phase and special approach and measures used to meet those challenges. This paper also outlines problems encountered during implementation of these measures and subsequent change in approach to ensure smooth and safe execution of activities. Primarily, challenges were conflicting requirements by various agencies to carryout commissioning in parallel with construction activities concurrently. Main challenges were related to fall hazard, chemical hazard, fire hazard, electrical safety, work in confined space, housekeeping problem. Moreover it was within exclusion zone of another operating plant, which added one more dimension to those challenges. Conventional Safely management approach was little short to resolve these challenges. Such challenges were envisaged; analyzed and innovative measures were arrived at. Along with conventional safely analysis like Job Safely or Hazard Analysis (JSA or JHA), Accident Analysis, Accident Trend Analysis, Fire Hazard Analysis (FHA), innovative method like 'Area-Job- Hazard Charting' and 'Ratio Analysis' were used to understand activity dependent time varying hazard scenarios. Based on this analysis, decision were taken to change various existing elements of safely management like safety organizations; standard operating procedures (SOP); emergency operating procedures (EOP); resource allocation, planning and scheduling; safely training; safely

  1. Ordinance of 14 March 1983 concerning the Federal Commission for the Safety of Nuclear Installations

    International Nuclear Information System (INIS)

    1983-01-01

    The Frederal Council issued a new Ordinance concerning the Federal Commission for the Safety of Nuclear Installations. This Ordinance replaces an Ordinance of 13 June 1960 and takes into account the distribution of tasks decided several years ago between the Commission, which operates on a part-time basis, and the principal Division for the Safety of Nuclear Installations attached to the Federal Office of Energy. (NEA) [fr

  2. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  3. The body of nuclear safety rules in Germany. Tasks, problems, perspectives from the point of view of a manufacturer

    International Nuclear Information System (INIS)

    Orth, K.H.

    1993-01-01

    The paper discusses a manufacturer's point of view, industry's interests and aspects in connection with the evolution and definition of KTA safety rules, stating a certain field of tension between RSK recommendations and the KTA safety rules. Developments within the EU faster expectations for better harmonisation of safety guides and rules. (HP) [de

  4. A combination of SILAC and nucleotide acyl phosphate labelling reveals unexpected targets of the Rsk inhibitor BI-D1870.

    Science.gov (United States)

    Edgar, Alexander J; Trost, Matthias; Watts, Colin; Zaru, Rossana

    2014-02-01

    Protein kinase inhibitors frequently have interesting effects that cannot be fully ascribed to the intended target kinase(s) but identifying additional targets that might explain the effects is not straightforward. By comparing two different inhibitors of the Rsk (p90 ribosomal S6 kinase) kinases, we found that the increasingly used compound BI-D1870 had biological effects in murine DCs (dendritic cells) that could not be solely ascribed to Rsk or other documented targets. We assessed the ability of BI-D1870 and a second Rsk inhibitor, BIX 02565 to protect enzyme active sites from reaction with biotinylated nucleotide acyl phosphates. Using SILAC (stable isotope labelling by amino acids in cell culture)-labelled DC lysates as a source of enzyme targets, we identify several kinases that interact with BI-D1870 but not with BIX 02565. We confirmed that these kinases, including Slk, Lok and Mst1, are inhibited by BI-D1870 but to a much lesser extent by BIX 02565 and that phosphorylation of some of their substrates is blocked by BI-D1870 in living cells. Our results suggest that the BI-D1870 inhibitor should be used with caution. The SILAC-based methodology we used should be useful for further comparative unbiased profiling of the target spectrum of kinase inhibitors with interesting biological effects under conditions that closely mimic those found in cells. © 2014 The author(s).

  5. Reactor safety: a discussion by officials of the Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Anders, W.A.; Rusche, B.C.; Stello, V. Jr.; Minogue, R.B.

    1976-01-01

    William A. Anders, Chairman of the Nuclear Regulatory Commission (NRC), and several senior officials spoke to the Joint Committee on Atomic Energy on the subject of nuclear safety, improvements in reactor plant safety, and quality assurance. The NRC, during its first year of organization, has developed new initiatives to improve safety and safeguards regulations. Anders stressed that NRC is not stifling internal discussion of opposing views, that it has been honest with the public, and that operating reactors are meeting rigorous safety standards. Other speakers discussed comparative safety of old and new reactors. Backfitting of older plants with new features is done when substantial safety protection can be added, but detuning an integrated system is not done indiscriminately. Officials of NRC do not agree with former General Electric employees, who testified that the regulatory procedure is inadequate. Safety improvements since August 28, 1962 and outlines of the review process are included in the Appendixes

  6. Report by USSR survey mission of Nuclear Safety Commission

    International Nuclear Information System (INIS)

    1990-01-01

    The USSR survey mission of Nuclear Safety Commission drew up and presents the report as follows. In relation to the accident in Chernobyl Nuclear Power Station in USSR, in order to investigate into the present status of the countermeasures for nuclear power safety in USSR and to exchange opinion, the USSR survey mission inspected nuclear power station facilities and visited the government organs, research institutes and others in USSR. The survey mission comprised 13 members, and went to Moscow, Kiev and two nuclear power station sites, from October 22 to November 1, 1989, for 11 days. At present in USSR, 49 nuclear power plants of about 35 GWe are in operation, and by 2000, the operation of more nuclear power plants of about 30 GWe is needed, but due to the change of social situation in USSR, its attainment seems to be difficult. The plan of nuclear power generation in USSR, the ensuring of safety in general, the recent countermeasures for improving safety, the effect of the accident in Chenobyl Nuclear Power Station on health and so on are reported. The detailed record of the visit to Zaporozhe and Chernobyl Nuclear Power Stations and 7 other research institutes and government organs is given. (K.I.)

  7. The European Commission proposes changes to the directive on nuclear safety

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    The European Commission proposes changes in the ancient European directive on nuclear safety in order to europeanize nuclear safety. The first proposal is to submit all European nuclear facilities to a control every 6 years by a board of foreign experts. Another proposal is to impose that every new power plant should be designed so that the radiological impact of an accident should be limited to the facility itself. The same proposal would impose for every nuclear plant the presence of an emergency center resistant to radiation, earthquakes and floods. The reporting of any incident occurring in a nuclear plant would be made compulsory. The decision to extend the operating life of a nuclear plant would be suspended to the results of a compulsory safety test. (A.C.)

  8. ERK and RSK regulate distinct steps of a cellular program that induces transition from multicellular epithelium to single cell phenotype

    Czech Academy of Sciences Publication Activity Database

    Čáslavský, Josef; Klímová, Zuzana; Vomastek, Tomáš

    2013-01-01

    Roč. 25, č. 12 (2013), s. 2743-2751 ISSN 0898-6568 R&D Projects: GA ČR GA204/09/0614; GA ČR GA13-06405S Institutional support: RVO:61388971 Keywords : MAPK/ERK * RSK * Polarity Subject RIV: EE - Microbiology, Virology Impact factor: 4.471, year: 2013

  9. Action by the European Commission to promote nuclear safety outside the territory of the Union

    International Nuclear Information System (INIS)

    Joulia, J.P.

    2010-01-01

    The TACIS programme to improve nuclear safety in Central and Eastern Europe and the former USSR has now entered its final phase. A new programme 'the Instrument for Nuclear Safety Cooperation (INSC)' has been launched and its aim is to promote nuclear safety in all third-party countries. Support for improvement of the regulatory framework and the effectiveness of the bodies in charge of nuclear safety is a key element. Within the European Commission, the 'Europe, Southern Mediterranean, Middle East and Neighbourhood policy' Directorate, belonging to the AIDCO General Directorate, is tasked with implementation. (author)

  10. ILK recommendation on the avoidance of dependent failures of digital I and C protection systems

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    In German nuclear power plants, the instrumentation and control (I and C) technology with the highest importance to safety is essentially hard-wired. In future, digital I and C systems will be put into use as a result of their manifold and sufficiently known advantages. The German Reactor Safety Commission (RSK) has published guidelines on digital safety instrumentation and control in 1996. The ILK welcomes the approach of NPP licensees to digitalize safety I and C functions with graded importance for safety first to gain experience with this new technology. Beyond the requirements laid out by the RSK-guidelines, the ILK recommends the following approach: - Different approaches should be taken in the definition and validation of I and C functions. - The specifications of a safety I and C system should cover all requirements. - If a safety I and C system (cat. 1) is only partly digitalized, then the remaining hardwired part should ideally remain in function. - If this is not the case, then the I and C functions should have functional diversity. - In case the category 1 safety I and C systems are to be entirely digitalized, then the system should be carried out in a functionally diversified way, or equivalent measures should be taken. - Diversified I and C functions should be processed by physically separate equipment. (orig.) [de

  11. The U.S. Nuclear Regulatory Commission seismic safety research program

    International Nuclear Information System (INIS)

    Kenneally, R.M.; Guzy, D.J.; Murphy, A.J.

    1988-01-01

    The seismic safety research program sponsored by the U.S. Nuclear Regulatory Commission is directed toward improving the evaluation of potential earthquake effects on nuclear power plant operations. The research has been divided into three major program areas: earth sciences, seismic design margins, and fragilities and response. A major thrust of this research is to assess plant behavior for seismic events more severe and less probable than those considered in design. However, there is also research aimed at improving the evaluation of earthquake input and plant response at plant design levels

  12. Outreach at the Canadian Nuclear Safety Commission - An Aboriginal Peoples' Perspective

    International Nuclear Information System (INIS)

    Lojk, R.; Ben Belfakhel, M.

    2006-01-01

    Established by the Nuclear Safety and Control Act (NSCA) that came into force in May 2000, the Canadian Nuclear Safety Commission (CNSC) is an independent federal agency that reports to Parliament through the Minister of Natural Resources. The CNSC regulates all uses of nuclear energy and nuclear materials from the production, to use, to the final disposition of any nuclear substances. Under the NSCA, the CNSC has the mandate to: - Regulate the development, production and use of nuclear energy and materials to protect the health, safety, security and environment; - Regulate production, possession and use of nuclear substances, prescribed equipment and prescribed information; - Implement measures respecting international commitments on the peaceful use of nuclear energy and substances; - Disseminate scientific, technical and regulatory information concerning CNSC activities. The main regulatory activities include setting regulatory standards, issuing licenses, verifying compliance and communicating with stakeholders and the public. These activities are accomplished by the work of two independent entities: a commission of up to seven members and a staff of about 500 employees. The Commission is an independent, quasi-judicial tribunal that provides licensing decisions on nuclear-related activities in a public forum. The President of the tribunal is the CEO of the CNSC staff organization. CNSC's regulatory philosophy is based on two principles: - Those persons and organizations subject to the NSCA and its Regulations are directly responsible for ensuring that the regulated activities that they engage in are managed so as to protect health, safety, security and the environment and to respect Canada's international commitments on the peaceful use of nuclear energy. - The CNSC is responsible to the public for regulating persons and organisations subject to the Nuclear Safety and Control Act and regulations to assure that they are properly discharging their obligations

  13. Recent achievement within the French-German safety approach for future PWRs

    International Nuclear Information System (INIS)

    Gros, G.; Rollinger, F.; Frisch, W.; Simon, M.

    1999-12-01

    The development of the common French-German safety approach was accomplished on three working levels: the technical safety organisations GRS and IPSN provided the technical basis, the advisory groups GPR and RSK developed common recommendations, and the authorities BMU and DSIN adopted and issued the recommendations. The general safety approach issued in May 1993 contains safety objectives, general principles and some technical principles for future PWRs. Based on this general approach, more detailed recommendations have been developed in 1994 on key issues. The following period from 1995 on was characterised by a further refinement of the recommendations and the treatment of some new subjects such as digital I and C, man-machine-interface and core design. (authors)

  14. Recommendations of the Reactor Safety Commission, 1971--1974

    International Nuclear Information System (INIS)

    The Reactor Safety Commission (RSC) of the German Federal Republic was created in 1958 by the then Federal Minister for Atomic Energy and Hydroeconomy. Its task included the advising of the Federal Minister responsible for protection of the population from possible dangers occurring during peaceful utilization of nuclear energy and in all matters of the safety of nuclear oriented installations. The RSC consists of independent experts from differing specialty areas. The results of their consultations are passed on in recommendations to the appropriate Federal Minister. Since the reappointment and reorganization of the RSC in the year 1971 by the then Federal Minister for Education and Science, the recommendations have been published in the ''Federal Gazette.'' The report presented is divided into two parts with a three part appendix. All recommendations of the RSC made since the reorganization (68th Meeting on 3 November 1971) until expiration of the last appointment, (96th Meeting on 25 July 1974) are compiled in the first section. The second part contains all announcements of the RSC which have appeared in the ''Federal Gazette.'' These concern training, agenda, as well as current members. Appendix A includes the ''Guidelines for Pressurized Water Reactors'' approved in the 93rd Meeting on 24 April 1974. Two key word listings follow in Sections B and C of the Appendix. The report was prepared in behalf of the Federal Minister of the Interior through the Office of the RSC assigned to the Institute for Reactor Safety of the Technical Inspection Association (IRS). The report is continued at regular intervals following each meeting period

  15. The commissioning of nuclear power plants

    International Nuclear Information System (INIS)

    1989-09-01

    The objectives and requirements to be met in commissioning nuclear power plants are presented. The objective of commissioning is to ensure that each component, subsystem, system, or structure in a plant will be capable of fulfilling its design requirements throughout its design life. The requirements for commissioning are: the preparation of a detailed, comprehensive, documented program to demonstrate that all components, systems and structures relevant to safety meet design intent; documented evidence that safety systems are fully operable and can meet design requirements; and, appropriate documentation of the actual state or behaviour of all components, systems and structures relevant to safety. All systems must be included in the commissioning program. Whenever possible, full safety system test should be performed. If a full system in situ test is not possible, alternative means are suggested. (8 refs.)

  16. Role of the team of scientific and technical commissioning support (TSTCS) during Mochovce NPP unit 3 and 4 commissioning

    International Nuclear Information System (INIS)

    Hermansky, J.; Prachar, M.; Sedlacek, M.; Petenyi, V.

    2011-01-01

    The Team of Scientific and Technical Commissioning Support (TSTCS) shall provide an independent support for the Mochovce NPP 3 and 4 Commissioning Department during Mochovce Units 3 and 4 commissioning. This independent support will be in line with the Mochovce NPP 3 and 4 Directive 'Non-active tests and commissioning' and it will be carried out in form of professional and expert works focusing on supervision of fulfilment of requirements for nuclear safety observance. The TSTCS duty to provide for such services during NPP commissioning is specified by Slovak Regulatory Body legislation. The independent TSTCS will supervise; - fulfilment of requirements for nuclear safety during preparation and implementation of commissioning tests; -scientific and technical level of commissioning programmes, and reflection on nuclear safety requirements in commissioning programmes,- commissioning process and test results. Main standpoints of the Team activities for individual unit commissioning stages will be; - assesment of the selected programs of functional tests in installations having an impact on nuclear safety and evaluation of the results of these tests; - assesment of the programs of physics and power commissioning, - assesment of the unit preparedness before fuel loading start; - assesment of the unit preparedness for performing initial criticality and low power commissioning and power commissioning stages; - evaluation of the results of physics and power commissioning stages and sub-stages; - final evaluation of the results from implementing the physics and power commissioning stages. The paper also presents a short description of the Team scope activities, the Team organisation, and a procedure for issuing of standpoints to individual unit commissioning stages. (Authors)

  17. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1992-01-01

    This is the thirty-sixth volume of issuances (1-396) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Boards, Administrative Law Judges, and Office Directors. It covers the period from July 1, 1992-December 31, 1992. Atomic Safety and Licensing Boards are authorized by Section 191 of the Atomic Energy Act of 1954. These Boards, comprised of three members conduct adjudicatory hearings on applications to construct and operate nuclear power plants and related facilities and issue initial decisions which, subject to internal review and appellate procedures, become the final Commission action with respect to those applications. Boards are drawn from the Atomic Safety and Licensing Board Panel, comprised of lawyers, nuclear physicists and engineers, environmentalists, chemists, and economists. The Atomic Energy Commission first established Licensing Boards in 1962 and the Panel in 1967

  18. Impact Assessment Road Safety Action Programme : assessment for mid term review : final report. Report on behalf of the European Commission, Directorate-General Energy and Transport.

    NARCIS (Netherlands)

    ECORYS Transport & SWOV Institute for Road Safety Research

    2006-01-01

    In 2003 the Commission published Saving 20000 lives on our roads, a shared responsibility, also known as the third European Road Safety Action Programme (RSAP). The RSAP describes concrete actions and proposals for actions by the Commission aimed at realising the target for improving road safety as

  19. Period1 gates the circadian modulation of memory-relevant signaling in mouse hippocampus by regulating the nuclear shuttling of the CREB kinase pP90RSK.

    Science.gov (United States)

    Rawashdeh, Oliver; Jilg, Antje; Maronde, Erik; Fahrenkrug, Jan; Stehle, Jörg H

    2016-09-01

    Memory performance varies over a 24-h day/night cycle. While the detailed underlying mechanisms are yet unknown, recent evidence suggests that in the mouse hippocampus, rhythmic phosphorylation of mitogen-activated protein kinase (MAPK) and cyclic adenosine monophosphate response element-binding protein (CREB) are central to the circadian (~ 24 h) regulation of learning and memory. We recently identified the clock protein PERIOD1 (PER1) as a vehicle that translates information encoding time of day to hippocampal plasticity. We here elaborate how PER1 may gate the sensitivity of memory-relevant hippocampal signaling pathways. We found that in wild-type mice (WT), spatial learning triggers CREB phosphorylation only during the daytime, and that this effect depends on the presence of PER1. The time-of-day-dependent induction of CREB phosphorylation can be reproduced pharmacologically in acute hippocampal slices prepared from WT mice, but is absent in preparations made from Per1-knockout (Per1(-/-) ) mice. We showed that the PER1-dependent CREB phosphorylation is regulated downstream of MAPK. Stimulation of WT hippocampal neurons triggered the co-translocation of PER1 and the CREB kinase pP90RSK (pMAPK-activated ribosomal S6 kinase) into the nucleus. In hippocampal neurons from Per1(-/-) mice, however, pP90RSK remained perinuclear. A co-immunoprecipitation assay confirmed a high-affinity interaction between PER1 and pP90RSK. Knocking down endogenous PER1 in hippocampal cells inhibited adenylyl cyclase-dependent CREB activation. Taken together, the PER1-dependent modulation of cytoplasmic-to-nuclear signaling in the murine hippocampus provides a molecular explanation for how the circadian system potentially shapes a temporal framework for daytime-dependent memory performance, and adds a novel facet to the versatility of the clock gene protein PER1. We provide evidence that the circadian clock gene Period1 (Per1) regulates CREB phosphorylation in the mouse hippocampus

  20. Hypoxia-induced invadopodia formation involves activation of NHE-1 by the p90 ribosomal S6 kinase (p90RSK.

    Directory of Open Access Journals (Sweden)

    Fabrice Lucien

    Full Text Available The hypoxic and acidic microenvironments in tumors are strongly associated with malignant progression and metastasis, and have thus become a central issue in tumor physiology and cancer treatment. Despite this, the molecular links between acidic pH- and hypoxia-mediated cell invasion/metastasis remain mostly unresolved. One of the mechanisms that tumor cells use for tissue invasion is the generation of invadopodia, which are actin-rich invasive plasma membrane protrusions that degrade the extracellular matrix. Here, we show that hypoxia stimulates the formation of invadopodia as well as the invasive ability of cancer cells. Inhibition or shRNA-based depletion of the Na(+/H(+ exchanger NHE-1, along with intracellular pH monitoring by live-cell imaging, revealed that invadopodia formation is associated with alterations in cellular pH homeostasis, an event that involves activation of the Na(+/H(+ exchange rate by NHE-1. Further characterization indicates that hypoxia triggered the activation of the p90 ribosomal S6 kinase (p90 RSK, which resulted in invadopodia formation and site-specific phosphorylation and activation of NHE-1. This study reveals an unsuspected role of p90RSK in tumor cell invasion and establishes p90RS kinase as a link between hypoxia and the acidic microenvironment of tumors.

  1. Safety and risk questions following the nuclear incidents and accidents in Japan. Summary final report

    International Nuclear Information System (INIS)

    Mildenberger, Oliver

    2015-03-01

    After the nuclear accidents in Japan, GRS has carried out in-depth investigations of the events. On the one hand, the accident sequences in the affected units have been analysed from various viewpoints. On the other hand, the transferability of the findings to German plants has been examined to possibly make recommendations for safety improvements. The accident sequences at Fukushima Daiichi have been traced with as much detail as possible based on all available information. Additional insights have been drawn from thermohydraulic analyses with the GRS code system ATHLET-CD/COCOSYS focusing on the events in units 2 and 3, e.g. with regard to core damage and the state of the containments in the first days of the accident sequence. In-depth investigations have also been carried out on topics such as natural external hazards, electrical power supply or organizational measures. In addition, methodological studies on further topics related with the accidents have been performed. Through a detailed analysis of the relevant data from the events in Japan, the basis for an in-depth examination of the transferability to German plants was created. It was found that an implementation of most of the insights gained from the investigations had already been initiated as part of the GRS information notice 2012/02. Further findings have been communicated to the federal government and introduced into other relevant bodies, e.g. the Nuclear Safety Standards Committee (KTA) or the Reactor Safety Commission (RSK).

  2. Safety in nuclear power plant operation, including commissioning and decommissioning. A code of practice

    International Nuclear Information System (INIS)

    1978-01-01

    Safe operation of a nuclear power plant postulates satisfactory siting, design, construction and commissioning, together with proper management and operation of the plant. This Code of Practice deals with the safety aspects of management, commissioning, operation and decommissioning of the plant. It forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to land-based stationary thermal neutron power plants. It has been prepared for the use of those responsible for the operation of stationary nuclear power plants, the main function of which is the generation of electrical and/or thermal power, and for the use of those responsible for regulating the operation of such plants. It is not intended for application to reactors used solely for experimental or research purposes. The provisions in the Code are designed to provide assurance that operational activities are carried out without undue radiological hazard to the general public and to persons on the site. It should be understood that the provisions in the Code set forth minimum requirements which shall be met in order to achieve safe operation of a nuclear power plant

  3. The Canadian Nuclear Safety Commission Compliance Program for Uranium Mines and Mills

    Energy Technology Data Exchange (ETDEWEB)

    Schryer, D., E-mail: denis.schryer@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Saskatoon, Saskatchewan (Canada)

    2014-05-15

    The Canadian Nuclear Safety Commission (CNSC) is the principal nuclear regulator in Canada. The CNSC is empowered through the Nuclear Safety and Control Act (NSCA) and its associated regulations, to regulate the entire nuclear cycle which includes: uranium mining and milling, uranium refining and processing, fuel fabrication, power generation and nuclear waste management. A CNSC uranium mine licence is required by a proponent to site, prepare, construct, operate, decommission and abandon this nuclear facility. The CNSC licence is the legal instrument that authorizes the regulated activities and incorporates conditions and regulatory controls. Following a favourable Commission Tribunal decision to issue a licence to authorize the licensed activities, CNSC develops and executes a compliance plan of the licensee’s programs and procedures. The CNSC compliance plan is risk-informed and applies its resources to the identified higher risk areas. The compliance program is designed to encourage compliance by integrating three components: promotion, verification and enforcement and articulates the CNSC expectations to attain and maintain compliance with its regulatory requirements. The licensee performance is assessed through compliance activities and reported to the Commission to inform the licensing process during licence renewal. The application of the ongoing compliance assessment and risk management model ensures that deviations from impact predictions are addressed in a timely manner. The Uranium Mines and Mills Division of the CNSC are preparing to meet the challenges of the planned expansion of their Canadian uranium mining industry. The presentation will discuss these challenges and the measures required to address them. The Uranium Mines and Mills Division (UMMD) have adopted a structured compliance framework which includes formal procedures to conduct site inspections. New UMMD staff are trained to apply the regulations to licensed sites and to manage non

  4. 75 FR 81236 - Consumer Product Safety Act: Notice of Commission Action Lifting Stay of Enforcement of...

    Science.gov (United States)

    2010-12-27

    ... action with respect to non-children's products subject to CPSC regulations pertaining to vinyl plastic... pertaining to vinyl plastic film, carpets and rugs, and clothing textiles on January 26, 2011. FOR FURTHER... Reduction, U.S. Consumer Product Safety Commission, 4330 East West Highway, Bethesda, Maryland 20814; e-mail...

  5. Joint Commission

    Science.gov (United States)

    ... for the latest publication of The Joint Commission Journal on Quality and Patient Safety (JQPS). . How We Work Process improvement program breeds quality culture, empowers staff An article in Quality Progress, June ...

  6. Impact Assessment Road Safety Action Programme : assessment for mid term review : final report. Report on behalf of the European Commission, Directorate-General Energy and Transport.

    OpenAIRE

    ECORYS Transport & SWOV Institute for Road Safety Research

    2006-01-01

    In 2003 the Commission published Saving 20000 lives on our roads, a shared responsibility, also known as the third European Road Safety Action Programme (RSAP). The RSAP describes concrete actions and proposals for actions by the Commission aimed at realising the target for improving road safety as set in the White Paper (European Transport Policy for 2010: time to decide, 2001), namely halving the number of road deaths by 2010. Improving road safety in the EU is clearly a joint responsibilit...

  7. Safety Culture Evaluation at Research Reactors of Pakistan Atomic Energy Commission

    International Nuclear Information System (INIS)

    Qamar, M.A.; Saeed, A.; Shah, J.H.

    2016-01-01

    The concept of safety culture was presented by IAEA in document INSAG-4 (1991), delineated as “assembly of characteristics and attitudes in organizations and individuals which establish that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance”. The purpose of this paper is to describe the evaluation of safety culture at research reactors of the Pakistan Atomic Energy Commission (PAEC). Evaluating the safety culture of a particular organization poses some challenges which can be resolved by using safety culture evaluation models like those of Sachein (1992) and Harber-Barrier(1998). In PAEC, safety culture is the integral part of management system which not only promotes safety culture throughout the organization but also enhances its significance. To strengthen the safety culture, PAEC is also participating in a number of international and regional meetings of IAEA regarding safety culture. PAEC and the national regulator Pakistan Nuclear Regulatory Authority (PNRA) are also arranging workshops, peer reviews, sharing operational experiences and interacting with IAEA missions to enhance its capabilities in the field of safety culture. The Directorate General of Safety (DOS) is a corporate office of PAEC for safety and regulatory matters. DOS is in the process of implementing a program to evaluate safety culture at nuclear installations of PAEC to ensure that safety culture is included as a vital segment of the Integral Management System of the establishment. In this regard, training sessions and lectures on safety culture evaluation are normally conducted in PAEC for awareness and enhancement of the safety culture program. Safety culture is also addressed in PNRA Regulations like PAK-909 and PAK-913. In this paper we will focus on the safety culture evaluation in our research reactors, i.e., PARR-1 and PARR-2. The evaluation results will be based on observations, interviews of employees, group discussions

  8. Independent Commission for Radiological Protection and Nuclear Safety CIPRSN: Balance, obligations and future prospects

    International Nuclear Information System (INIS)

    Gieb, M.; Meruje, M. M; Sena Lino, A.

    2010-01-01

    This article summarizes the historical context of the regulatory situation in Portugal that led to the creation of the technical team of the Independent Commission for Radiological Protection and Nuclear Safety (CIPRSN), recalls its early works, and highlights the current work of some members of the team on the self-assessment of the national regulatory system of radiological protection and nuclear safety. The result of this self-assessment allows a detailed analysis of current problems and makes it possible to outline the future work plan of the technical team. It is hoped that this work may contribute to an improvement of the system, especially in view of new international and European legal instruments which are currently under implementation. (author)

  9. Royal Order of 15 October 1979 creating and organising an Interministerial Commission for Nuclear Safety and State Security in the Nuclear Field

    International Nuclear Information System (INIS)

    1979-01-01

    This Royal Order setting up an Interministerial Commission for Nuclear Safety and State Security provides for the duties of the Commission. These are, in particular, to seek the means to ensure the protection of workers against the hazards which might arise from nuclear activities by co-ordinating the work of the ministerial departments concerned. The Commission is composed of representatives of ministries and bodies involved in that field. (NEA) [fr

  10. Review and evaluation of the Nuclear Regulatory Commission safety research program for Fiscal Year 1983. Report to the Congress

    International Nuclear Information System (INIS)

    1982-02-01

    Public Law 95-209 includes a requirement that the Advisory Committee on Reactor Safeguards submit an annual report to Congress on the safety research program of the Nuclear Regulatory Commission. This report presents the results of the ACRS review and evaluation of the NRC safety research program for Fiscal Year 1983. The report contains a number of comments and recommendations

  11. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1981-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  12. Yellin's review of the Nuclear Regulatory Commission's Reactor Safety Study: comment

    International Nuclear Information System (INIS)

    Wilson, R.

    1976-01-01

    Joel Yellin (Bell J. Economics, Vol. 7, No. 1 (Spr. 1976)) reviewed the Reactor Safety Study (WASH-1400, or Rasmussen Report) published by the Nuclear Regulatory Commission and makes several criticisms. Wilson finds that some of these criticisms are much overstated, while others, although valid, are mainly criticisms of presentation. To be useful for public policy, reactor risks--and indeed all nuclear risks--must be compared with other risks society faces. Wilson feels that the Rasmussen Report is weak in these comparisons, primarily because there exist few estimates of risk in other places, but that the comparisons he does make indeed confirm that the risk is smaller than Yellin suggests. 20 references

  13. Proposal for the award of a contract for the supply, installation, commissioning and maintenance of the LHC access safety system

    CERN Document Server

    2005-01-01

    This document concerns the award of a contract for the supply, installation, commissioning and maintenance of the LHC access safety system. The Finance Committee is invited to agree to the negotiation of a contract with the consortium CEGELEC CENTRE EST (FR) â?" CEGELEC (NL) â?" SEMER (FR), the lowest bidder, for the supply, installation, commissioning and maintenance for five years of the LHC access safety system for a total amount of 891 423 euros (1 367 633 Swiss francs), subject to revision for inflation for the maintenance of the system from 1 January 2007, with an option for the supply of safety PLCs for a total amount of 894 951 euros (1 373 046 Swiss francs), not subject to revision, bringing the total amount to 1 786 374 euros (2 740 679 CHF).The rate of exchange used is that stipulated in the tender.

  14. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1981-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

  15. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

  16. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

  17. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1987-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1990-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1986-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1987-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  3. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1989-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Danials of Petitions for Rulemaking (DPRM)

  4. Nuclear regulatory commission issuances

    International Nuclear Information System (INIS)

    1989-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-01-01

    This report includes the issuance received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1986-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  8. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1990-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1988-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  12. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-06-01

    This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  14. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1989-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1989-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  17. Nuclear regulatory commission issuances

    International Nuclear Information System (INIS)

    1990-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1987-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1990-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety And Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1985-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1990-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  3. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1988-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Safety requirements of the BMU to be met in final storage of heat-producing waste: An evaluation

    International Nuclear Information System (INIS)

    Thomauske, Bruno

    2009-01-01

    On August 12, 2008, The German Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU) published a draft of July 29, 2008 of the ''Safety Requirements to Be Met in Final Storage of Heat-producing Radioactive Waste.'' As announced by the BMU, these safety requirements are to bring up to the state of the art the safety criteria of 1983. Over a couple of years, efforts had been made to adapt the criteria to the internationally accepted standard as demanded by the Advisory Committees on Reactor Safeguards (RSK) and Radiation Protection (SSK). There is no waste management concept underlying the safety requirements. As a consequence, the draft should be withdrawn by the Federal Ministry for the Environment and replaced by a version revised from scratch and offering assured quality. (orig./GL)

  5. Systems reliability analyses and risk analyses for the licencing procedure under atomic law

    International Nuclear Information System (INIS)

    Berning, A.; Spindler, H.

    1983-01-01

    For the licencing procedure under atomic law in accordance with Article 7 AtG, the nuclear power plant as a whole needs to be assessed, plus the reliability of systems and plant components that are essential to safety are to be determined with probabilistic methods. This requirement is the consequence of safety criteria for nuclear power plants issued by the Home Department (BMI). Systems reliability studies and risk analyses used in licencing procedures under atomic law are identified. The stress is on licencing decisions, mainly for PWR-type reactors. Reactor Safety Commission (RSK) guidelines, examples of reasoning in legal proceedings and arguments put forth by objectors are also dealt with. Correlations are shown between reliability analyses made by experts and licencing decisions by means of examples. (orig./HP) [de

  6. Nuclear Regulatory Commission Staff practice and procedure digest. Commission, Appeal Board and Licensing Board Decision, July 1972 - June 1995

    International Nuclear Information System (INIS)

    1996-04-01

    This is the seventh edition of the Nuclear Regulatory Commission (NRC) Staff Practice and Procedure Digest. It contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 1995 interpreting the NRC rules of practice in 10 CFR part 2

  7. Safe LHC beam commissioning

    International Nuclear Information System (INIS)

    Uythoven, J.; Schmidt, R.

    2007-01-01

    Due to the large amount of energy stored in magnets and beams, safety operation of the LHC is essential. The commissioning of the LHC machine protection system will be an integral part of the general LHC commissioning program. A brief overview of the LHC Machine Protection System will be given, identifying the main components: the Beam Interlock System, the Beam Dumping System, the Collimation System, the Beam Loss Monitoring System and the Quench Protection System. An outline is given of the commissioning strategy of these systems during the different commissioning phases of the LHC: without beam, injection and the different phases with stored beam depending on beam intensity and energy. (author)

  8. 16 CFR 1009.8 - Policy on establishing priorities for Commission action.

    Science.gov (United States)

    2010-01-01

    ... involves an analysis of the extent to which the product and other factors such as consumer behavior are... Commission action. 1009.8 Section 1009.8 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION GENERAL... action. (a) This document states the Consumer Product Safety Commission's policy on establishing...

  9. Energy. Health, environment, and safety hazards. Final report from the Energy Commission. Energi. Haelso- miljoe- och saekerhetsrisker. Slutbetaenkande av energikommissionen

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The Swedish Energy Commission in its main report (''Energy'', SOU 1978:17) presented its considerations and put forward its proposals for a Swedish Energy policy for the next decade. This report contains complementary information on health hazards, risks of major accidents and sabotage, and problems of waste management. The presentation takes the form of a comparison of such risks in relation to different sources of energy. The Commission is not unanimous in its estimates of the relative hazards of different energysystems. The Commission recommends the initiation of a large number of studies concerning the possible ways the increase the safety and reduce the adverse effects of energy production.

  10. 29 CFR 2200.92 - Review by the Commission.

    Science.gov (United States)

    2010-07-01

    ... Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH REVIEW COMMISSION RULES OF PROCEDURE Posthearing Procedures § 2200.92 Review by the Commission. (a) Jurisdiction of the Commission; issues on... Commission to review the entire case. The issues to be decided on review are within the discretion of the...

  11. Nuclear Regulatory Commission Issuances, November 1980

    International Nuclear Information System (INIS)

    1980-11-01

    Contents: Issuances of the Nuclear Regulatory Commission; Issuances of the Atomic Safety and Licensing Appeal Boards; Issuances of the Atomic Safety and Licensing Boards; and Issuances of the Directors Denial

  12. Nuclear Regulatory Commission Issuances, December 1980

    International Nuclear Information System (INIS)

    1980-12-01

    Contents: Issuances of the Nuclear Regulatory Commission; Issuances of the Atomic Safety and Licensing Appeal Boards; Issuances of the Atomic Safety and Licensing Boards; and Issuances of the Directors Denial

  13. Nuclear Regulatory Commission issuances, October 1993

    International Nuclear Information System (INIS)

    1993-10-01

    This document contains a Commission issuance in which the Commission denies the petitioners' motion to quash or modify a subpoena issued by the NRC staff in the course of an investigation to determine if the petitioners' have violated NRC regulations and to determine if safety-related problems exist at NRC-licensed facilities. The pertinent regulations and the Commission's Memorandum and Order are included

  14. Amendment of the atomic energy basic law and other related laws and establishment of the nuclear safety commission

    International Nuclear Information System (INIS)

    Ochi, Kenji

    1978-01-01

    The Atomic Energy Basic Law and related several laws were amended in the recent diet session. The amendment of the laws was requested after the radiation leakage from nuclear-powered ship ''Mutsu''. The reform of administrative system of atomic energy development and utilization are consisted of two important points: one is to establish the Nuclear Safety Commission for strengthening nuclear safety administration, and the other is to give an authority to each ministry or agency to regulate nuclear power reactor from the establishment to operation according to its original mission. (author)

  15. Commissioning and Operational Experience in Power Reactor Fuel Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Pradhan, S., E-mail: spradhan@barctara.gov.in [Tarapur Based Reprocessing Plant, Bhabha Atomic Research Centre, Tarapur (India)

    2014-10-15

    After completing design, construction, commissioning, operation and maintenance experience of the reprocessing plants at Tarapur, Mumbai and Kalpakkam a new reprocessing plant is commissioned and put into operation at BARC, Tarapur since 2011. Subsequent to construction clearance, commissioning of the plant is taken in many steps with simultaneous review by design and safety committees. In spite of vast experience, all the staff was retrained in various aspects of process and utility operations and in operation of innovative changes incorporated in the design. Operating personnel are licensed through an elaborate procedure consisting of various check lists followed by personnel interview. Commissioning systems were divided in sub-systems. Sub-systems were commissioned independently and later integrated testing was carried out. For commissioning, extreme operating conditions were identified in consultation with designers and detailed commissioning procedures were made accordingly. Commissioning was done in different conditions to ensure safety, smooth operation and maintainability. Few modifications were carried out based on commissioning experience. Technical specifications for operation of the plant are made in consultation with designers and reviewed by safety committees. Operation of the plant was carried out after successful commissioning trials with Deep Depleted Uranium (DDU). Emergency operating procedures for each design basis accident were made. Performance of various systems, subsystems are quite satisfactory and the plant has given very good capacity factor. (author)

  16. Nuclear Regulatory Commission issuances, May 1982

    International Nuclear Information System (INIS)

    1982-01-01

    This report includes the issuances received during the specified period from the Commission, the Atomic Safety and Licensing Appeal Boards, the Atomic Safety and Licensing Boards, the Administrative Law Judge, the Directors' Decision, and the Denials of Petitions for Rulemaking

  17. Mehrzweckforschungsreaktor Karlsruhe (MZFR)

    International Nuclear Information System (INIS)

    1976-01-01

    The RSK is of the opinion that the proposed additional emergency cooling system can present an improvement in safety. Furthermore, the RSK starts from the fact that the measures required for the present system - improvements in the accident instrumentation, fitting control devices, annual in-service inspections - are already adequately catered for in the design. (orig.) [de

  18. CRASH - Community Road Accident System Homepage : feasibility study on a European Road Safety Information System, financially supported by the European Commission.

    NARCIS (Netherlands)

    Brouwer, M. Poppe, F. Blokpoel, A. & Kars, V.

    2000-01-01

    This report is the result of a feasibility study, financially supported by the European Commission. The study investigated the possibilities for the development and maintenance of a European Road Safety Information System with relevant and internationally comparable information. Recommendations on

  19. Nuclear Regualtory Commission Issuances, October 1981

    International Nuclear Information System (INIS)

    1981-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Denial (DD), and the Denial of Petitions for Rulemaking

  20. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1989-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety nd Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  1. Nuclear Regulatory Commission issuances

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This report includes the issuances received during the specified period from Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

  2. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1994-03-01

    This report includes the issuances received during the specified period from Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  3. Nuclear Regulatory Commission issuances, July 1988

    International Nuclear Information System (INIS)

    1988-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission Issuances, October 1986

    International Nuclear Information System (INIS)

    1986-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances, May 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear Regulatory Commission issuances, September 1987

    International Nuclear Information System (INIS)

    1987-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission issuances, April 1989

    International Nuclear Information System (INIS)

    1989-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  8. Nuclear Regulatory Commission issuances, July 1989

    International Nuclear Information System (INIS)

    1989-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances, March 1989

    International Nuclear Information System (INIS)

    1989-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission issuances, May 1989

    International Nuclear Information System (INIS)

    1989-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances, May 1990

    International Nuclear Information System (INIS)

    1990-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  12. Nuclear Regulatory Commission issuances, August 1990

    International Nuclear Information System (INIS)

    1990-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission issuances, October 1989

    International Nuclear Information System (INIS)

    1989-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  14. Nuclear Regulatory Commission issuances, June 1987

    International Nuclear Information System (INIS)

    1987-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decision (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances, April 1987

    International Nuclear Information System (INIS)

    1987-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission Issuances, August 1986

    International Nuclear Information System (INIS)

    1986-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  17. Nuclear Regulatory Commission issuances, November 1988

    International Nuclear Information System (INIS)

    1988-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission Issuances, March 1990

    International Nuclear Information System (INIS)

    1990-01-01

    The report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Nuclear Regulatory Commission issuances, November 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Nuclear Regulatory Commission issuances, June 1990

    International Nuclear Information System (INIS)

    1990-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances, December 1990

    International Nuclear Information System (INIS)

    1990-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission issuances, December 1989

    International Nuclear Information System (INIS)

    1989-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  3. Nuclear Regulatory Commission issuances, February 1989

    International Nuclear Information System (INIS)

    1989-02-01

    This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances, February 1985

    International Nuclear Information System (INIS)

    1985-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances, November 1990

    International Nuclear Information System (INIS)

    1990-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1993-08-01

    This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors; Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission Issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  8. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1996-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission Issuance

    International Nuclear Information System (INIS)

    1994-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-11-01

    This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  12. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1994-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1992-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  14. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1994-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1991-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  17. Canadian Nuclear Safety Commission 2003-2004 estimates. Part III - report on plans and priorities

    International Nuclear Information System (INIS)

    2003-01-01

    The Commission replace the Atomic Energy Control Board in 2000 as Canada's independent agency which regulates the use of nuclear energy and materials to protect health, safety, security, and the environment. This report is an individual expenditure plan that provides details on a business line basis and contains information on objectives, initiatives, and planned results, including links to related resource requirements over a three-year period. It also provides details on human resource requirements, major capital projects, grants and contributions, and net program costs. Introductory sections with a minister's message are followed by sections giving a departmental or organization overview; plans, results, activities, resources, and initiatives, as applicable; and financial information

  18. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2016-01-01

    This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

  19. Playground Safety

    Science.gov (United States)

    ... Prevention Fall Prevention Playground Safety Poisoning Prevention Road Traffic Safety Sports Safety Get Email Updates To receive ... at the Consumer Product Safety Commission’s Playground Safety website . References U.S. Consumer Product Safety Commission. Injuries and ...

  20. Nuclear Regulatory Commission issuances, April 1991

    International Nuclear Information System (INIS)

    1991-04-01

    This report includes the issuances received during the specified period (April 1991) from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Commissioning of Temelin NPP as seen by scientific supervisory group

    International Nuclear Information System (INIS)

    Svoboda, C.

    2003-01-01

    Scientific Supervisory Group worked during the Temelin NPP commissioning process as an independent supervisor. The main tasks and main results of its activity are described in this contribution. The characteristic common features of commissioning process and most important events from the Scientific Supervisory Group point of view are presented. In April 1999 the Czech Power Utility with the objective to achieve maximum level of nuclear safety and quality within the NPP Temelin commissioning procedures has established a special body / Scientific Supervisory Group and requested Nuclear Research Institute Rez plc to perform the required function. The Scientific Supervisory Group proceeds in accordance with its Statute and provides an independent specialised professional and expert work focused on nuclear safety assurance, assesment of the selected documentation related to plant preparedness for the individual commissioning stages, and, of course. on assessment of the commissioning tests results. While performing its function the Scientific Supervisory Group is guided by the Atomic Act and the relevant Directives of State Office for Nuclear Safety; its activities are in compliance with the applicable IAEA recommendations (Authors)

  2. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1982-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

  3. 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

  4. Safety and risk questions following the nuclear incidents and accidents in Japan. Summary final report; Sicherheits- und Risikofragen im Nachgang zu den nuklearen Stoer- und Unfaellen in Japan. Zusammenfassender Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Mildenberger, Oliver

    2015-03-15

    After the nuclear accidents in Japan, GRS has carried out in-depth investigations of the events. On the one hand, the accident sequences in the affected units have been analysed from various viewpoints. On the other hand, the transferability of the findings to German plants has been examined to possibly make recommendations for safety improvements. The accident sequences at Fukushima Daiichi have been traced with as much detail as possible based on all available information. Additional insights have been drawn from thermohydraulic analyses with the GRS code system ATHLET-CD/COCOSYS focusing on the events in units 2 and 3, e.g. with regard to core damage and the state of the containments in the first days of the accident sequence. In-depth investigations have also been carried out on topics such as natural external hazards, electrical power supply or organizational measures. In addition, methodological studies on further topics related with the accidents have been performed. Through a detailed analysis of the relevant data from the events in Japan, the basis for an in-depth examination of the transferability to German plants was created. It was found that an implementation of most of the insights gained from the investigations had already been initiated as part of the GRS information notice 2012/02. Further findings have been communicated to the federal government and introduced into other relevant bodies, e.g. the Nuclear Safety Standards Committee (KTA) or the Reactor Safety Commission (RSK).

  5. Nuclear Regulatory Commission issuances. Volume 23, No. 3

    International Nuclear Information System (INIS)

    1986-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), and the Directors' Decisions (DD)

  6. Nuclear Regulatory Commission issuance, pages 933-1089

    International Nuclear Information System (INIS)

    1981-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Denial (DD), and the Denial of Petitions for Rulemaking

  7. 16 CFR 1031.6 - Extent and form of Commission involvement in the development of voluntary standards.

    Science.gov (United States)

    2010-01-01

    ..., engineering support, and information and education programs) and administrative assistance (e.g., travel costs... SAFETY COMMISSION GENERAL COMMISSION PARTICIPATION AND COMMISSION EMPLOYEE INVOLVEMENT IN VOLUNTARY... goals and objectives with regard to voluntary standards and improved consumer product safety; responding...

  8. Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission`s dispositions

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Norio; Suzudo, Tomoaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-09-01

    Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission`s (USNRC`s) responses to the recommendations made by the NRC`s study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC`s dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

  9. International co-operation in safety matters within the framework of the Commission of the European Communities

    International Nuclear Information System (INIS)

    Vinck, W.; Balz, W.; Essler, W.; Tolley, B.; Gabolde, J.

    1981-01-01

    European Community (EC) countries realize that their energy demand cannot be met without a nuclear component, which is almost a necessity owing to its major economic advantages. Two typical areas where the Commission has stimulated intense international co-operation are as follows: The first broad area deals with efforts towards a gradual harmonization of regulatory health and safety practices and requirements for reactors of an industrially developed type, more specifically (light) water-cooled reactors. The second area concerns joint research programmes and co-ordination activities in research on nuclear safety (LWRs and LMFBRs). These two broad areas are closely interconnected. Information is also given on the existing network of bilateral and multilateral arrangements for the exchange of information of interest to the EC. In conclusion, some problems are highlighted where improvements could be made or where it seems crucial that increased international co-operation and especially agreement should come about. (author)

  10. Continuity and enhancement of quality management during commissioning of W7-X

    Energy Technology Data Exchange (ETDEWEB)

    Vilbrandt, Reinhard, E-mail: reinhard.vilbrandt@ipp.mpg.de; Bosch, Hans-Stephan; Feist, Jost-Henrich; Klinger, Thomas

    2015-10-15

    Highlights: • Commissioning follows the W7-X structure into appropriate components, subsystems and systems. • Local and integrated commissioning steps are carried out alternately. • An exact and detailed preparation of all commissioning is absolutely necessary. • Templates support instruction manuals, safety analyses, and commissioning instructions. • Because of safety special attention must be paid to the first putting into service. - Abstract: The commissioning of Wendelstein 7-X, the first numerically optimized stellarator, is a new phase in the project. The general planning and execution of the commissioning of the entire W7-X system follow its structure into appropriate components, subsystems and systems. The approach for taking these systems into operation will lead to so-called local commissioning which is usually executed for individual systems in connection with the necessary peripheral devices and auxiliary systems. The subsequent step-wise testing and commissioning of the systems in connection with the central device of W7-X, including the central safety control, and the central data acquisition system is performed in the second step, the so-called integrated commissioning. This leads directly to the preparation of first plasma operation. New organizational and quality management elements have been added to the running system, or existing, proven tools have been modified. The major new organizational structures and tasks and the quality planning and assurance tools are described in more detail. The experience during the first commissioning steps of the vacuum and cryogenic systems is outlined.

  11. Experience relevant to safety obtained from reactor decommissioning operations in the French Atomic Energy Commission

    International Nuclear Information System (INIS)

    Giraudel, B.; Langlois, G.

    1979-01-01

    From among the nuclear facilities constructed in France the authors cite eight large reactors, ranging from critical assemblies to power reactors, that have been finally shut-down since 1965. A brief account is given of the way in which the various operations were carried out after the final control rod drop, a distinction being drawn between the shut-down proper and the containment and dismantling work. A description is also given, from the technical and regulatory standpoint, of the final stage attained, and mention is made of French safety arrangements and of the part played by the safety services during decommissioning operations. Among the lessons derived from French experience, the authors mention the completion of operations without any serious safety problems, and with guarantees for the protection of personnel and the population as a whole, by conventional techniques; the advantage of planning decommissioning operations from the very beginning of construction of the facilities; and the importance of filing descriptive documents. In view of the experience gained, the French Atomic Energy Commission has devised internal procedures for facilitating the application of regulations governing the shut-down and decommissioning phases, which are aimed at preserving surveillance procedures similar to those in force during normal operation. (author)

  12. U.S. Nuclear Regulatory Commission Safety Culture Oversight

    International Nuclear Information System (INIS)

    Sieracki, D. J.

    2016-01-01

    The NRC recognises that it is important for all organizations performing or overseeing regulated activities to establish and maintain a positive safety culture commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The NRC’s approach to safety culture is based on the premise that licencees bear the primary responsibility for safety. The NRC provides oversight of safety culture through expectations detailed in policy statements, safety culture assessor training for NRC inspectors, the oversight process, and the Allegations and Enforcement Programs. The NRC’s Safety Culture Policy Statement (SCPS) sets forth the Commission’s expectation that individuals and organizations establish and maintain a positive safety culture commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The SCPS is not a regulation. It applies to all licencees, certificate holders, permit holders, authorisation holders, holders of quality assurance program approvals, vendors and suppliers of safety-related components, and applicants for a licence, certificate, permit, authorisation, or quality assurance program approval, subject to NRC authority.

  13. 16 CFR 1015.10 - Commission report of actions to Congress.

    Science.gov (United States)

    2010-01-01

    ... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Commission report of actions to Congress. 1015.10 Section 1015.10 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION GENERAL PROCEDURES FOR... U.S.C. 552(a) § 1015.10 Commission report of actions to Congress. On or before February 1 of each...

  14. Experience gained during commissioning and trial operation of Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    GaL, P.; Adamica, T.; Marosik, V.; Rehak, A.

    2000-01-01

    In this paper authors describe the experience gained during commissioning and trial operation of Mochovce NPP (EMO). The first year of EMO operation from the point of view of safety and reliability was successful. Evidently we were challenged with certain problems characteristic to this stage of operation which resulted in automatic reactor shutdown. There were 11 automatic shutdowns in 1998 by action of the quick emergency protection AO-1 and two manual shutdowns by the AO-1 key. In 1999, there were 6 automatic shutdowns by action of the quick emergency protection AO-1. Three of them was connected to the falsely activated binary signal of MCP switch of, in two cases the reason came out from the turbo-generator (TG) cooling water system. Very positive trend in the operation of both units shows the fact that during all commissioning period of the second unit there were only three automatic reactor shutdowns by the signal AO-1. All these actions were done in frame of commissioning tests. All causes which activated the automatic unit shutdowns were found out and rectified, the overall tuning of the cooling water system is on the process now. The solution of this problem is possible only power commissioning, and in the stage of the trial operation had no direct impacts on the nuclear, radiation, or technical safety respectively. In 1998 two events according to the INES scale after second unit commissioning because of two unit links of the cooling water system. The operational events during the commissioning tests, start-up tests, physical commissioning, were ranked the category 1 ('Action of SIS U040 p po <8,34 MPa at the system 2 and 3' and 'Breaching the L and C'). In 1999 only events occurred that were ranked in the category safety insignificant events and lower (category 0, or off the scale respectively). In the frame of the safety culture principles adopted, such as critical attitude, exact and careful approach, and communication, these problems were given the

  15. Recombinant streptokinase vs phenylephrine-based suppositories in acute hemorrhoids, randomized, controlled trial (THERESA-3)

    Science.gov (United States)

    Hernández-Bernal, Francisco; Castellanos-Sierra, Georgina; Valenzuela-Silva, Carmen M; Catasús-Álvarez, Karem M; Valle-Cabrera, Roselin; Aguilera-Barreto, Ana; López-Saura, Pedro A

    2014-01-01

    AIM: To compare the efficacy and safety of recombinant streptokinase (rSK) and phenylephrine-based suppositories in acute hemorrhoidal disease. METHODS: A multicenter (14 sites), randomized (1:1), open, parallel groups, active controlled trial was done. After inclusion, subjects with acute symptoms of hemorrhoids, who gave their written, informed consent to participate, were centrally randomized to receive, as outpatients, rSK (200000 IU) or 0.25% phenylephrine suppositories, which had different organoleptic characteristics. Treatment was administered by the rectal route, one unit every 6 h during 48 h for rSK, and up to a maximum of 5 d (20 suppositories) for phenylephrine. Evaluations were performed at 3, 5 and 10 d post-inclusion. The main end-point was the 5th-day complete clinical response (disappearance of pain and edema, and ≥ 70% reduction of the lesion size). Time to response and need for thrombectomy were secondary efficacy variables. Adverse events were evaluated too. RESULTS: 5th day complete response rates were 83/110 (75.5%) and 36/110 (32.7%) with rSK and phenylephrine suppositories, respectively. This 42.7% difference (95%CI: 30.5-54.2) was highly significant (P hemorrhoidal illness, with an adequate safety profile. PMID:24587636

  16. Commissioning quality assurance for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-09-01

    This standard contains the requirements for the quality assurance program applicable to the commissioning phase of a nuclear power plant. This standard embodies the relevant quality assurance requirements of CSA Standard CAN3-N286.0, and is the governing Standard for commissioning quality assurance activities in the event of any conflicting requirements. This Standard applies to the commissioning of safety-related equipment, systems, and structures as identified by the owner. It may be applied to other equipment, systems, and structures at the discretion of the owner. 1 fig.

  17. Commissioning quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    1986-09-01

    This standard contains the requirements for the quality assurance program applicable to the commissioning phase of a nuclear power plant. This standard embodies the relevant quality assurance requirements of CSA Standard CAN3-N286.0, and is the governing Standard for commissioning quality assurance activities in the event of any conflicting requirements. This Standard applies to the commissioning of safety-related equipment, systems, and structures as identified by the owner. It may be applied to other equipment, systems, and structures at the discretion of the owner. 1 fig

  18. 78 FR 29392 - Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied...

    Science.gov (United States)

    2013-05-20

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0098] Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied on for Safety AGENCY: Nuclear Regulatory Commission. ACTION... (NRC) is issuing for public comment Draft Regulatory Issue Summary (RIS) 2013-XX, ``Embedded Digital...

  19. Nuclear Regulatory Commission issuances, Volume 18, No. 5

    International Nuclear Information System (INIS)

    1983-11-01

    This report includes the issuances received during November, 1983, from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  20. Nuclear Regulatory Commission Issuances. Volume 22, No. 1

    International Nuclear Information System (INIS)

    1985-07-01

    This report includes the issuances received during July 1985 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances. Volume 22, No. 5

    International Nuclear Information System (INIS)

    1985-11-01

    This report includes the issuances received during November 1985 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission Issuances. Opinions and decisions of the Nuclear Regulatory Commission with selected orders: July 1, 1992--December 31, 1992, Volume 36, Pages 1--396

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    This is the thirty-sixth volume of issuances (1-396) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Boards, Administrative Law Judges, and Office Directors. It covers the period from July 1, 1992-December 31, 1992. Atomic Safety and Licensing Boards are authorized by Section 191 of the Atomic Energy Act of 1954. These Boards, comprised of three members conduct adjudicatory hearings on applications to construct and operate nuclear power plants and related facilities and issue initial decisions which, subject to internal review and appellate procedures, become the final Commission action with respect to those applications. Boards are drawn from the Atomic Safety and Licensing Board Panel, comprised of lawyers, nuclear physicists and engineers, environmentalists, chemists, and economists. The Atomic Energy Commission first established Licensing Boards in 1962 and the Panel in 1967.

  3. Nuclear Regulatory Commission issuances. Vol. 16, No. 5

    International Nuclear Information System (INIS)

    1982-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances. Volume 17, No. 4

    International Nuclear Information System (INIS)

    1983-04-01

    This report includes the issuances received during the specified period from the Commission (CLi), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission Issuances. Volume 23, No. 1

    International Nuclear Information System (INIS)

    1986-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear Regulatory Commission issuances. Volume 20, No. 4

    International Nuclear Information System (INIS)

    1984-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission issuances. Volume 22, No. 6

    International Nuclear Information System (INIS)

    1985-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  8. Nuclear Regulatory Commission issuances. Volume 20, No. 2

    International Nuclear Information System (INIS)

    1984-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances. Volume 21, No. 6

    International Nuclear Information System (INIS)

    1985-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission issuances. Volume 21, No. 5

    International Nuclear Information System (INIS)

    1985-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances. Vol. 16, No. 4

    International Nuclear Information System (INIS)

    1982-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

  12. Nuclear Regulatory Commission issuances. Vol. 16, No. 1

    International Nuclear Information System (INIS)

    1982-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

  13. Nuclear Regulatory Commission Issuances. Volume 23, No. 2

    International Nuclear Information System (INIS)

    1986-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  14. COMMISSIONING AND DETECTOR PERFORMANCE GROUPS (DPG)

    CERN Multimedia

    Tiziano Camporesi

    Pit commissioning activities The last 4 months have seen various major achievements in hardware commissioning, global data taking, readiness of the DPGs to deal with LHC data flows and alignment and calibration workflows. Since February, the global commissioning has been characterized on the one side by more and more of the final CMS detector becoming available for global readout and triggering and on the other side by consolidation of many of the central software infrastructure and of most of the services infrastructure. The reliability of services like cooling, power, gas has markedly improved with respect to what we observed in the second half of 2007.   Of particular note are the delivery of all low voltage power supplies, the commissioning of the final power distribution, the progressive commissioning ( still ongoing)  of the Detector Safety System and of the associated DCS early warning and alarm system. On the detector side, while already we are used to seeing all of HCAL being exe...

  15. The Canadian Nuclear Safety Commission regulatory process for decommissioning a uranium mining facility

    International Nuclear Information System (INIS)

    Scissons, K.; Schryer, D.M.; Goulden, W.; Natomagan, C.

    2002-01-01

    The Canadian Nuclear Safety Commission (CNSC) regulates uranium mining in Canada. The CNSC regulatory process requires that a licence applicant plan for and commit to future decommissioning before irrevocable decisions are made, and throughout the life of a uranium mine. These requirements include conceptual decommissioning plans and the provision of financial assurances to ensure the availability of funds for decommissioning activities. When an application for decommissioning is submitted to the CNSC, an environmental assessment is required prior to initiating the licensing process. A case study is presented for COGEMA Resources Inc. (COGEMA), who is entering the decommissioning phase with the CNSC for the Cluff Lake uranium mine. As part of the licensing process, CNSC multidisciplinary staff assesses the decommissioning plan, associated costs, and the environmental assessment. When the CNSC is satisfied that all of its requirements are met, a decommissioning licence may be issued. (author)

  16. Atomic Energy Commission reports. Volume 6. Opinions and decisions of the Atomic Energy Commission with selected orders, January 1, 1973 to December 31, 1973

    International Nuclear Information System (INIS)

    1974-01-01

    Issuances of the Atomic Energy Commission, the Atomic Safety and Licensing Appeal Boards, the Atomic Safety and Licensing Boards, and the Board of Contract Appeals including the Contract Adjustment Board are presented. (U.S.)

  17. Guidelines for residential commissioning

    Energy Technology Data Exchange (ETDEWEB)

    Wray, Craig P.; Walker, Iain S.; Sherman, Max H.

    2003-01-31

    Currently, houses do not perform optimally or even as many codes and forecasts predict, largely because they are field assembled and there is no consistent process to identify problems or to correct them. Residential commissioning is a solution to this problem. This guide is the culmination of a 30-month project that began in September 1999. The ultimate objective of the project is to increase the number of houses that undergo commissioning, which will improve the quality, comfort, and safety of homes for California citizens. The project goal is to lay the groundwork for a residential commissioning industry in California focused on end-use energy and non-energy issues. As such, we intend this guide to be a beginning and not an end. Our intent is that the guide will lead to the programmatic integration of commissioning with other building industry processes, which in turn will provide more value to a single site visit for people such as home energy auditors and raters, home inspectors, and building performance contractors. Project work to support the development of this guide includes: a literature review and annotated bibliography, which facilitates access to 469 documents related to residential commissioning published over the past 20 years (Wray et al. 2000), an analysis of the potential benefits one can realistically expect from commissioning new and existing California houses (Matson et al. 2002), and an assessment of 107 diagnostic tools for evaluating residential commissioning metrics (Wray et al. 2002). In this guide, we describe the issues that non-experts should consider in developing a commissioning program to achieve the benefits we have identified. We do this by providing specific recommendations about: how to structure the commissioning process, which diagnostics to use, and how to use them to commission new and existing houses. Using examples, we also demonstrate the potential benefits of applying the recommended whole-house commissioning approach to

  18. Nuclear Regulatory Commission issuances, September 1995. Volume 42, Number 3

    International Nuclear Information System (INIS)

    1995-09-01

    This book contains an issuance of the Atomic Safety and Licensing Board and a Director's Decision, both of the US Nuclear Regulatory Commission. The issuance concerns the dismissal of a case by adopting a settlement reached by the Staff of the Nuclear Regulatory Commission and a Radiation Safety Officer of a hospital in which the safety officer pled guilty to deliberate misconduct. The Director's Decision was to deny a petition to impose a fine on Tennessee Valley Authority concerning alleged harassment of the petitioner and to appoint an independent arbitration board to review all past complaints filed against TVA concerning the Watts Bar Nuclear Plant

  19. Nuclear Regulatory Commission issuances, September 1995. Volume 42, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This book contains an issuance of the Atomic Safety and Licensing Board and a Director`s Decision, both of the US Nuclear Regulatory Commission. The issuance concerns the dismissal of a case by adopting a settlement reached by the Staff of the Nuclear Regulatory Commission and a Radiation Safety Officer of a hospital in which the safety officer pled guilty to deliberate misconduct. The Director`s Decision was to deny a petition to impose a fine on Tennessee Valley Authority concerning alleged harassment of the petitioner and to appoint an independent arbitration board to review all past complaints filed against TVA concerning the Watts Bar Nuclear Plant.

  20. Indexes to Nuclear Regulatory Commission issuances, January-March 1987

    International Nuclear Information System (INIS)

    1987-09-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document

  1. Safety requirements to be met in final storage of heat-producing waste an evaluation of the BMU draft

    International Nuclear Information System (INIS)

    Thomauske, B.

    2008-01-01

    The German Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU) on August 12, 2008 published a July 29, 2008 draft of the ''Safety Requirements to Be Met in Final Storage of Heat-producing Radioactive Waste.'' As announced by the BMU, these safety requirements are to bring up to the state of the art the safety criteria of 1983. Over a couple of years, efforts had been made to adapt the criteria to the internationally accepted standard as demanded by the Advisory Committees on Reactor Safeguards (RSK) and Radiation Protection (SSK). The main changes made by the BMU are the introduction of a phased procedure in building repositories. A phased plans approval procedure under the Atomic Energy Act has been foreseen by the Ministry for this purpose. In addition, the draft provides for the introduction of a risk-based goal of protection. To ensure retrievability of the waste, the casks are to have a demonstrated service life of 500 years. The BMU draft safety requirements are unable to bring the safety criteria of 1983 up to the current state of the art. Here are the key points of criticism: - A risk-based goal of protection is introduced. The yardstick to be applied is to be defined in a guideline yet to be elaborated. As a consequence, the draft lacks substance. - As in licensing of nuclear facilities, the licensing procedure provides for a phased plans approval procedure for exploration. This analogy does not exist, as exploration is not the first phase of the plant to be built but a measure which is a precondition for obtaining a permit for construction and operation. - The information contained in the draft indicates that, contrary to international recommendations, it tightens the goal of protection by more than one order of magnitude. - The requirements to be met by the casks because of retrievability impose constraints on solutions optimized for safety in emplacement technology. - The risk-based approach is not mature and is

  2. Nuclear Regulatory Commission issuances, April 1994

    International Nuclear Information System (INIS)

    1994-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  3. Nuclear Regulatory Commission issuances, June 1992

    International Nuclear Information System (INIS)

    1992-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  4. Nuclear Regulatory Commission issuances, December 1991

    International Nuclear Information System (INIS)

    1991-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  5. Nuclear Regulatory Commission issuances, January 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Defense (DD), and the Denials of Petitions for Rulemaking (DPRM)

  6. Nuclear Regulatory Commission issuances, May 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  7. Nuclear Regulatory Commission issuances, July 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  8. Nuclear Regulatory Commission issuances, December 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  9. Nuclear Regulatory Commission issuances, December 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  10. Nuclear Regulatory Commission issuances, September 1992

    International Nuclear Information System (INIS)

    1992-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  11. Nuclear Regulatory Commission issuances, February 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  12. Nuclear Regulatory Commission issuances, March 1993

    International Nuclear Information System (INIS)

    1993-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission issuances, July 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  14. Nuclear Regulatory Commission issuances, August 1992

    International Nuclear Information System (INIS)

    1992-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances, August 1991

    International Nuclear Information System (INIS)

    1991-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances, February 1993

    International Nuclear Information System (INIS)

    1993-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  17. Nuclear Regulatory Commission issuances, November 1992

    International Nuclear Information System (INIS)

    1992-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  18. Nuclear Regulatory Commission issuances, April 1993

    International Nuclear Information System (INIS)

    1993-04-01

    This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  19. Uncertainty Evaluation of Best Estimate Calculation Results

    International Nuclear Information System (INIS)

    Glaeser, H.

    2006-01-01

    Efforts are underway in Germany to perform analysis using best estimate computer codes and to include uncertainty evaluation in licensing. The German Reactor Safety Commission (RSK) issued a recommendation to perform uncertainty analysis in loss of coolant accident safety analyses (LOCA), recently. A more general requirement is included in a draft revision of the German Nuclear Regulation which is an activity of the German Ministry of Environment and Reactor Safety (BMU). According to the recommendation of the German RSK to perform safety analyses for LOCA in licensing the following deterministic requirements have still to be applied: Most unfavourable single failure, Unavailability due to preventive maintenance, Break location, Break size and break type, Double ended break, 100 percent through 200 percent, Large, medium and small break, Loss of off-site power, Core power (at accident initiation the most unfavourable conditions and values have to be assumed which may occur under normal operation taking into account the set-points of integral power and power density control. Measurement and calibration errors can be considered statistically), Time of fuel cycle. Analysis using best estimate codes with evaluation of uncertainties is the only way to quantify conservatisms with regard to code models and uncertainties of plant, fuel parameters and decay heat. This is especially the case for approaching licensing limits, e.g. due to power up-rates, higher burn-up and higher enrichment. Broader use of best estimate analysis is therefore envisaged in the future. Since some deterministic unfavourable assumptions regarding availability of NPP systems are still used, some conservatism in best-estimate analyses remains. Methods of uncertainty analyses have been developed and applied by the vendor Framatome ANP as well as by GRS in Germany. The GRS development was sponsored by the German Ministry of Economy and Labour (BMWA). (author)

  20. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

  1. The preparation and implementation of the commissioning of Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Huang Jinyuan

    1993-05-01

    The commissioning test of Qinshan Nuclear Power Plant is summarized. The preparation stage includes the organizations, commissioning programme, network planning, commissioning items, management procedures, responsibilities and interfaces between divisions, products ordering and supplying, personal training, quality assurance and the review and supervision by National Nuclear Safety Administration etc. The implementation stage includes the commissioning programme planning, intermediate hand-over inspection of the system and equipment, inspecting conditions and setting organizations for commissioning, the transition from commissioning to operating. Finally, some experiences in the commissioning test are presented in the article

  2. Regulation of chemical safety at fuel cycle facilities by the United States Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Ramsey, Kevin M.

    2013-01-01

    When the U.S. Nuclear Regulatory Commission (NRC) was established in 1975, its regulations were based on radiation dose limits. Chemical hazards rarely influenced NRC regulations. After the Three Mile Island reactor accident in 1979, the NRC staff was directed to address emergency planning at non-reactor facilities. Several fuel cycle facilities were ordered to submit emergency plans consistent with reactor emergency plans because no other guidance was available. NRC published a notice that it was writing regulations to codify the requirements in the Orders and upgrade the emergency plans to address all hazards, including chemical hazards. The legal authority of NRC to regulate chemical safety was questioned. In 1986, an overfilled uranium hexafluoride cylinder ruptured and killed a worker. The NRC staff was directed to address emergency planning for hazardous chemicals in its regulations. The final rule included a requirement for fuel cycle facilities to certify compliance with legislation requiring local authorities to establish emergency plans for hazardous chemicals. As with emergency planning, NRC's authority to regulate chemical safety during routine operations was limited. NRC established memoranda of understanding (MOUs) with other regulatory agencies to encourage exchange of information between the agencies regarding occupational hazards. In 2000, NRC published new, performance-based, regulations for fuel cycle facilities. The new regulations required an integrated safety analysis (ISA) which used quantitative standards to assess chemical exposures. Some unique chemical exposure cases were addressed while implementing the new regulations. In addition, some gaps remain in the regulation of hazardous chemicals at fuel cycle facilities. The status of ongoing efforts to improve regulation of chemical safety at fuel cycle facilities is discussed. (authors)

  3. Summary of the contributions to reactor safety research commissioned by the Republic of Austria and done by the Forschungszentrum Seibersdorf from 1987 to 1990

    International Nuclear Information System (INIS)

    Sonneck, G.; Sdouz, G.

    1991-09-01

    In 1987 the Forschungszentrum Seibersdorf was commissioned by the Republic of Austria with the collaboration in the Nuclear Safety Research Index, the OECD-LOFT-Programme and the International Coordinated Assessment and Application Programme (ICAAP). This report summarises the work done from 1987 to 1990, mainly in the field of thermal hydraulics, fuel rod behaviour and source term. Besides some analyses for experiments done in loops based on BWRs and PWRs of western design the work concentrated on safety researchs for WWERS. (Authors)

  4. 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

  5. Nuclear Regulatory Commission issuances, September 1988

    International Nuclear Information System (INIS)

    1988-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

  6. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1997-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  7. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1997-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  8. Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1994-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  9. Nuclear Regulatory Commission issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance.

  10. Recombinant streptokinase vs phenylephrine-based suppositories in acute hemorrhoids, randomized, controlled trial (THERESA-3).

    Science.gov (United States)

    Hernández-Bernal, Francisco; Castellanos-Sierra, Georgina; Valenzuela-Silva, Carmen M; Catasús-Álvarez, Karem M; Valle-Cabrera, Roselin; Aguilera-Barreto, Ana; López-Saura, Pedro A

    2014-02-14

    To compare the efficacy and safety of recombinant streptokinase (rSK) and phenylephrine-based suppositories in acute hemorrhoidal disease. A multicenter (14 sites), randomized (1:1), open, parallel groups, active controlled trial was done. After inclusion, subjects with acute symptoms of hemorrhoids, who gave their written, informed consent to participate, were centrally randomized to receive, as outpatients, rSK (200000 IU) or 0.25% phenylephrine suppositories, which had different organoleptic characteristics. Treatment was administered by the rectal route, one unit every 6 h during 48 h for rSK, and up to a maximum of 5 d (20 suppositories) for phenylephrine. Evaluations were performed at 3, 5 and 10 d post-inclusion. The main end-point was the 5(th)-day complete clinical response (disappearance of pain and edema, and ≥ 70% reduction of the lesion size). Time to response and need for thrombectomy were secondary efficacy variables. Adverse events were evaluated too. 5(th) day complete response rates were 83/110 (75.5%) and 36/110 (32.7%) with rSK and phenylephrine suppositories, respectively. This 42.7% difference (95%CI: 30.5-54.2) was highly significant (P suppositories showed a significant advantage over a widely used over-the-counter phenylephrine preparation for the treatment of acute hemorrhoidal illness, with an adequate safety profile.

  11. C/EBPβ-LAP*/LAP Expression Is Mediated by RSK/eIF4B-Dependent Signalling and Boosted by Increased Protein Stability in Models of Monocytic Differentiation.

    Directory of Open Access Journals (Sweden)

    René Huber

    Full Text Available The transcription factor C/EBPβ plays a key role in monocytic differentiation and inflammation. Its small isoform LIP is associated with proliferation at early premonocytic developmental stages and regulated via mTOR-dependent signalling. During later stages of (premonocytic differentiation there is a considerable increase in the large C/EBPβ isoforms LAP*/LAP which inhibit proliferation thus supporting terminal differentiation. Here, we showed in different models of monocytic differentiation that this dramatic increase in the LAP*/LAP protein and LAP/LIP ratio was accompanied by an only modest/retarded mRNA increase suggesting an important role for (posttranslational mechanisms. We found that LAP*/LAP formation was induced via MEK/RSK-dependent cascades, whereas mTOR/S6K1 were not involved. Remarkably, LAP*/LAP expression was dependent on phosphorylated eIF4B, an acceleratory protein of RNA helicase eIF4A. PKR inhibition reduced the expression of eIF4B and C/EBPβ in an eIF2α-independent manner. Furthermore, under our conditions a marked stabilisation of LAP*/LAP protein occurred, accompanied by reduced chymotrypsin-like proteasome/calpain activities and increased calpastatin levels. Our study elucidates new signalling pathways inducing LAP*/LAP expression and indicates new alternative PKR functions in monocytes. The switch from mTOR- to RSK-mediated signalling to orchestrate eIF4B-dependent LAP*/LAP translation, accompanied by increased protein stability but only small mRNA changes, may be a prototypical example for the regulation of protein expression during selected processes of differentiation/proliferation.

  12. C/EBPβ-LAP*/LAP Expression Is Mediated by RSK/eIF4B-Dependent Signalling and Boosted by Increased Protein Stability in Models of Monocytic Differentiation

    Science.gov (United States)

    Christmann, Martin; Friesenhagen, Judith; Westphal, Andreas; Pietsch, Daniel; Brand, Korbinian

    2015-01-01

    The transcription factor C/EBPβ plays a key role in monocytic differentiation and inflammation. Its small isoform LIP is associated with proliferation at early premonocytic developmental stages and regulated via mTOR-dependent signalling. During later stages of (pre)monocytic differentiation there is a considerable increase in the large C/EBPβ isoforms LAP*/LAP which inhibit proliferation thus supporting terminal differentiation. Here, we showed in different models of monocytic differentiation that this dramatic increase in the LAP*/LAP protein and LAP/LIP ratio was accompanied by an only modest/retarded mRNA increase suggesting an important role for (post)translational mechanisms. We found that LAP*/LAP formation was induced via MEK/RSK-dependent cascades, whereas mTOR/S6K1 were not involved. Remarkably, LAP*/LAP expression was dependent on phosphorylated eIF4B, an acceleratory protein of RNA helicase eIF4A. PKR inhibition reduced the expression of eIF4B and C/EBPβ in an eIF2α-independent manner. Furthermore, under our conditions a marked stabilisation of LAP*/LAP protein occurred, accompanied by reduced chymotrypsin-like proteasome/calpain activities and increased calpastatin levels. Our study elucidates new signalling pathways inducing LAP*/LAP expression and indicates new alternative PKR functions in monocytes. The switch from mTOR- to RSK-mediated signalling to orchestrate eIF4B-dependent LAP*/LAP translation, accompanied by increased protein stability but only small mRNA changes, may be a prototypical example for the regulation of protein expression during selected processes of differentiation/proliferation. PMID:26646662

  13. Nuclear Regulatory Commission issuances. Volume 47, Number 3

    International Nuclear Information System (INIS)

    1998-03-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The two issuances included here are: (1) the Commission issuance to the US Enrichment Corporation and (2) the Director's Decision to the North Atlantic Energy Service Corporation

  14. Canada's regulatory framework: The Canadian Nuclear Safety Commission's regulatory framework

    International Nuclear Information System (INIS)

    Howard, D.

    2011-01-01

    This paper will discuss the Canadian Nuclear Safety Commission and Canada's Regulatory Framework with respect to Low- and Intermediate-Level Radioactive Waste. The management of low and intermediate level radioactive waste must be ensured in a consistent, environmentally responsible and economical manner throughout its lifecycle -- from its production to the final disposal option. Radioactive waste has been produced in Canada since the early 1930s when the first radium/uranium mine began operating at Port Radium in the Northwest Territories. Pitchblende ore was transported from the Port Radium mine to Port Hope, Ontario where it was refined to produce radium for medical purposes. At present, radioactive waste is generated in Canada from the various stages and uses associated with the nuclear fuel cycle from uranium mining/milling to nuclear reactor operations to radioisotope manufacture and use. The Canadian Nuclear Safety Commission (CNSC regulates the use of nuclear energy and materials to protect the health, safety and security of Canadians and the environment; and to implement Canada's international commitments on the peaceful use of nuclear energy. The CNSC was established in 2000 under the Nuclear Safety and Control Act and reports to Parliament through the Minister of Natural Resources. The CNSC was created to replace the former Atomic Energy Control Board (AECB), which was founded in 1946. Under the Nuclear Safety and Control Act, CNSC's mandate involves four major areas: regulation of the development, production and use of nuclear energy in Canada to protect health, safety and the environment; regulation of the production, possession, use and transport of nuclear substances, and the production, possession and use of prescribed equipment and prescribed information; implementation of measures respecting international control of the development, production, transport and use of nuclear energy and substances, including measures respecting the

  15. Recombinant streptokinase suppositories in the treatment of acute haemorrhoidal disease. Multicentre randomized double-blind placebo-controlled trial (THERESA-2).

    Science.gov (United States)

    Hernández-Bernal, F; Valenzuela-Silva, C M; Quintero-Tabío, L; Castellanos-Sierra, G; Monterrey-Cao, D; Aguilera-Barreto, A; López-Saura, P

    2013-11-01

    A four-arm multicentre randomized double-blind placebo-controlled trial was undertaken to assess the effect and safety of suppositories containing recombinant streptokinase (rSK) at two dose levels (100,000 IU and 200,000 IU) with sodium salicylate (SS) compared with placebo and SS for the treatment of acute haemorrhoidal disease. Patients with acute symptoms of haemorrhoids were randomized to four treatment groups: (I) placebo, (II) SS, (III) SS + rSK 100,000 IU and (IV) SS + rSK 200,000 IU per suppository. Inpatient treatment was by four suppositories given every 6 h to discharge at 24 h. Evaluations were made at the time of discharge (24 h) and at 3, 5 and 20 days later. The main end-point was the degree of relief of pain, oedema and reduction in the size of the lesion by 90% on day 5. Adverse events and the occurrence of anti-SK antibodies were also determined. Eighty patients were included. Respective response rates in the four groups were 16%, 30%, 25% and 52%. In the last group there was a significant difference (36.8%) compared with control (95% CI 7.0-58.4%). The time to response was significantly shorter (median 5 days) in the 200,000 IU rSK group with respect to the others. There were no adverse events attributable to the treatment. No increase in anti-SK antibodies was detected 20 days after treatment. Suppositories with 200,000 IU rSK showed a significant improvement in symptoms of acute haemorrhoids, with an adequate safety profile. Colorectal Disease © 2013 The Association of Coloproctology of Great Britain and Ireland.

  16. Indexes to Nuclear Regulatory Commission issuances, January--March 1989

    International Nuclear Information System (INIS)

    1989-07-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

  17. Overview of Recent Activities on Safety Culture and Human and Organizational Factors Carried Out at the Joint Research Centre of the European Commission

    International Nuclear Information System (INIS)

    Stručić, M.; Manna, G.

    2016-01-01

    The Institute for Energy and Transport (IET) of the Joint Research Centre (JRC) of the European Commission (EC) is since more than ten years active in the field of Safety Culture (SC) and Human and Organizational Factors (HOF). Several activities related to SC and HOF have been and are carried out in the frame of the EU Nuclear Safety Clearinghouse for Operating Experience Feedback (Clearinghouse). The Clearinghouse was established in 2008 to enhance nuclear safety through the lessons learned from NPP events, and to provide help in Operational Experience Feedback (OEF) process primarily to nuclear safety Regulatory Authorities and to their Technical Support Organizations within the EU. Additionally to these activities, during the Fukushima accident, Clearinghouse has been regularly providing reports on the status and progress of the accident to the EU Regulatory Authorities. Moreover, experts, selected from the JRC staffing, were directly engaged in the EU-wide risk and safety assessments of nuclear power plants known as “the Stress Tests”.

  18. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest: Commission, Appeal Board and Licensing Board decisions, July 1972--March 1992

    International Nuclear Information System (INIS)

    1993-02-01

    This 5th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to March 31, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  19. United States Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board and Licensing Board decisions, July 1972--December 1991

    International Nuclear Information System (INIS)

    1992-11-01

    This 4th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to December 31, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  20. Standard for administration of stable iodine pilulae. Standard of the nuclear safety commission, action for accident in TEPCO Fukushima-1 and recent European trends

    International Nuclear Information System (INIS)

    Ishihara, Hiroshi

    2011-01-01

    Preventive taking of stable-iodine tablets is effective to avoid thyroid gland disorder due to internal exposure to the radioactive iodine if radioactive iodine is released outside by any nuclear accident. In Japan, the Nuclear Safety Commission proposed the standard of the preventive taking in 2002, and, at the Fukushima Daiichi nuclear disaster, the head of the local task force instructed to take on the recommendation from the Commission. Author described the action principle of stable-iodine tablets, present concept for the preventive taking, recent change of the concept in Europe for the preventive taking, and some precepts which have shown in past Fukushima Daiichi nuclear disaster. (J.P.N.)

  1. International nuclear safety experts complete IAEA peer review of German regulatory system

    International Nuclear Information System (INIS)

    2008-01-01

    policies, the regulatory framework and activities identified by the IRRS team were: Both BMU and UM BW have high quality and experienced staff, which are supported by experienced and competent technical support organizations. Both organizations have a high commitment to learning and self improvement; The team has also made recommendations and suggestions related to areas where the regulatory system as a whole could be improved. Examples include: There is room for improving information exchange and communication between the Federal and State regulatory bodies. Such enhanced communication would also lead to increased mutual trust and public confidence. In order to fulfill their regulatory responsibilities, BMU and UM BW should be staffed appropriately and develop a plan for a succession planning strategy. It could be very beneficial for the regulatory system, and helpful for worldwide learning, if all German 'Laender' (states) with nuclear power plants also took the opportunity to benefit from the experience of an IRRS mission, including making self- assessments against international best practice. The peer review consisted of an analysis of technical regulatory information, interviews, and discussions with key personnel at BMU and UM BW, as well as with regulatory inspectors at Neckarwestheim-1 Nuclear Power Plant to witness a regulatory inspection. Regulatory aspects were also discussed with Federal Minister Sigmar Gabriel and Minister Tanja Goenner of Baden-Wuerttemberg. Other organisations such as the Federal Office for Radiation Protection (BFS), the Reactor Safety Commission (RSK), the technical support organisation Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS), and the Nuclear Safety Standards Commission (ILK) were also involved. (author)

  2. Overview of Nuclear Fuel-Cycle Policy and the Role of the Nuclear Safety Commission in Japan

    International Nuclear Information System (INIS)

    Higashi, K.; Nishinosono, S.

    2008-01-01

    Since the first generation of electricity by the Japan Power Demonstration Reactor in 1963, Japan has been extensively developing nuclear technologies solely for peaceful purposes. The country now operates 55 nuclear power plants consisted of BWRs and PWRs. Although Japan is one of the largest consumers of energy in the world, the country has very limited domestic energy resources. Therefore, Japan considers the nuclear power generation very important as plutonium and uranium recovered from spent fuels can be used in new nuclear fuels as quasi-domestic energy resource. For recycle use of nuclear fuels, the establishment of nuclear fuel recycling technologies including reprocessing technologies is essential. Since 1977, Japan has been recovering plutonium and uranium by a small scale reprocessing plant built by French technology. Recently, 800 ton/year scale commercial reprocessing plant is under construction. After overcoming the current technical problem in the vitrification facility, the commercial plant is expected to be in full operation soon. Concerning the disposal of radioactive wastes, which arises from nuclear utilization, sallow land disposal has already been implemented and medium depth (50 to 100 m) disposal plan is in progress. For high-level waste, possible candidate sites for disposal are being sought. In this paper, the statuses of nuclear power plants and of nuclear fuel cycle facilities in Japan are summarized. As safety is essential for these nuclear installations, safety regulations in Japan are briefly presented from the viewpoint of Nuclear Safety Commission. Furthermore, as the most significant recent safety issue in Japan, the impacts of the large near-site earthquake hit Kashiwazaki-Kariwa NPP last July are reported.(author)

  3. Nuclear Regulatory Commission issuances

    International Nuclear Information System (INIS)

    1996-04-01

    This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services

  4. Nuclear Regulatory Commission issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services.

  5. Recent Cases: Administrative Law--Occupational Safety and Health Act

    Science.gov (United States)

    Harvard Law Review, 1976

    1976-01-01

    Implications of the Occupational Safety and Health Act of 1970 are described in two cases: Brennan v. Occupational Safety and Health Review Commission (Underhill Construction Corp.), and Anning-Johnson Co. v. United States Occupational Safety and Health Review Commission. (LBH)

  6. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  7. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2003-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  8. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  9. Nuclear safety research

    International Nuclear Information System (INIS)

    1996-01-01

    The topics 'Large-sized PWR-NPP Safety Techniques Research',and 'The Key Techniques Research on the Safety Supervision and Control for Operation of Nuclear Installations' have been adopted as an apart of 'the National 9th five Year Programs for Tacking the Key Scientific and Technical Topics' which are organized by the State Planning Commission (SPC) and State Science and Technology Commission (SSTC) respectively, and have obtained a financial support from them. To play a better role with the limited fund, the NNSA laid special stress on selecting key sub-topics on nuclear safety, and carefully choosing units which would undertake sub-topics and signing technical contracts with them

  10. Resolution proposal for the creation of an inquiry commission about the safety and transparency risks generated by the opening of the capital and the privatization of the French nuclear industry

    International Nuclear Information System (INIS)

    2004-12-01

    The privatization of the French nuclear industry leads to three types of risks: the dilution of decision prerogatives (need of long-term investment for maintenance and safety purposes which are incompatible with immediate profits), incompatibility between private control and safety, and speculation (need of stable and durable financing for a sustainable safety). For these reasons, the French house of commons has created an inquiry commission about the safety and transparency risks linked with the capital opening and privatization of the French nuclear industry. (J.S.)

  11. COMMISSIONING AND DETECTOR PERFORMANCE GROUPS

    CERN Document Server

    T. Camporesi

    The major progress made during the last months has been in the consolidation of services for the +endcaps and three barrel wheels (YB+2, YB+1 and YB0): all subdetectors have now final power connections (including Detector Safety protection), the gas systems have been commissioned for all gas detectors (the recirculation is not yet activated for the RPC though) and detector cooling has also been commissioned. Their integration with final services is the necessary condition for being able to operate larger fractions the detector. Recent weeks have seen full HCAL, more than 50% of EB and full wheels of DTs and CSC being operated using final services. This has not yet translated into major progress of global integration due to major interruptions of central services, which have not allowed the necessary debugging and commissioning time to all the subdetec¬tors and central activities like DAQ and trigger. Moreover the running in of the final central services has introduced instabilities related to the co...

  12. Nuclear Regulatory Commission issuances: August 1994. Volume 40, Number 2

    International Nuclear Information System (INIS)

    1994-08-01

    This report contains the collected issuances of the US Nuclear Regulatory Commission for the month of August, 1994. The report includes issuances of the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Some of the entities involved include Gulf States Utility company, Sequoyah Fuels Corporation and General Atomics, Georgia Power Company, and Arizona Public Service Company

  13. Nuclear Regulatory Commission issuances, Volume 47, No. 1

    International Nuclear Information System (INIS)

    1998-01-01

    This report includes the issuances received during the specified period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking

  14. Nuclear Regulatory Commission issuances, April 1986. Volume 23, No. 4

    International Nuclear Information System (INIS)

    1986-04-01

    This report includes the issuances recieved during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances, December 1982. Vol. 16, No. 6

    International Nuclear Information System (INIS)

    1982-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances, June 1986. Volume 23, No. 6

    International Nuclear Information System (INIS)

    1986-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  17. 16 CFR 1115.8 - Compliance with product safety standards.

    Science.gov (United States)

    2010-01-01

    ... applicable mandatory consumer product safety standards and to report to the Commission any products which do.... 1115.8 Section 1115.8 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SUBSTANTIAL PRODUCT HAZARD REPORTS General Interpretation § 1115.8 Compliance with...

  18. Recombinant streptokinase vs hydrocortisone suppositories in acute hemorrhoids: A randomized controlled trial.

    Science.gov (United States)

    Hernández-Bernal, Francisco; Castellanos-Sierra, Georgina; Valenzuela-Silva, Carmen M; Catasús-Álvarez, Karem M; Martínez-Serrano, Osmany; Lazo-Diago, Odalys C; Bermúdez-Badell, Cimara H; Causa-García, José R; Domínguez-Suárez, Juan E

    2015-06-21

    To compare the efficacy and safety of recombinant streptokinase (rSK) vs hydrocortisone acetate-based suppositories in acute hemorrhoidal disease. A multicenter (11 sites), randomized (1:1:1), open, controlled trial with parallel groups was performed. All participating patients gave their written, informed consent. After inclusion, patients with acute symptoms of hemorrhoids were centrally randomized to receive, as outpatients, by the rectal route, suppositories of rSK 200000 IU of one unit every 8 h (first 3 units) and afterwards every 12 h until 8 administrations were completed (schedule A), one unit every 8 h until 6 units were completed (schedule B), or 25 mg hydrocortisone acetate once every 8 h up to a maximum of 24 administrations. Evaluations were performed at 3, 5, and 10 d post-inclusion. The main end-point was the 5(th)-day response (disappearance of pain and bleeding, and ≥ 70% reduction of the lesion size). Time to response and need for thrombectomy were secondary efficacy variables. Adverse events were also evaluated. Groups were homogeneous with regards to demographic and baseline characteristics. Fifth day complete response rates were 156/170 (91.8%; 95%CI: 87.3-96.2), 155/170 (91.2%; 95%CI: 86.6%-95.7%), and 46/170 (27.1%; 95%CI: 20.1%-34.0%) with rSK (schedule A and B) and hydrocortisone acetate suppositories, respectively. These 64.6% and 63.9% differences (95%CI: 56.7%-72.2% and 55.7%-72.0%) were highly significant (P hemorrhoid classification) showed a statistically significant advantage for the rSK groups. Thrombectomy was necessary in 4/251 and 14/133 patients with baseline thrombosis in the rSK and hydrocortisone acetate groups, respectively (P hemorrhoidal illness, as well as having an adequate safety profile.

  19. Preparation of physics commissioning of Mochovce units 3 and 4

    International Nuclear Information System (INIS)

    Sedlacek, M.; Chrapciak, V.

    2010-01-01

    The Project 'Mochovce Units 3 and 4 Completion' started in 2009 and it will be finished in 2013. VUJE, Inc. is one of the five main Project contractors for the Nuclear Island and it is responsible, inter alia, for Mochovce Units 3 and 4 commissioning. The commissioning of Units 3 and 4 includes the stages of Physics Commissioning and Power Commissioning. This paper deals with the preparation of Mochovce Units 3 and 4 Physics Commissioning. In the paper there is presented a preparation of some commissioning documents, e.g. 'Quality Assurance Programme', 'Commissioning Programme', 'Stage Programme for Physics Commissioning', 'Test working programmes', 'Neutron-physics characteristics for Physics and Power Commissioning', etc. The scope of Physics Commissioning is presented by list of tests. For assessment of tests results so-called three-level acceptance criteria will be applied: realization, design and safety criteria. In the paper there are also presented computer codes, which will be used for neutron-physics characteristics calculation and the fuel loading scheme for the reactor core of Mochovce Unit 3. (Authors)

  20. Nuclear Regulatory Commission issuances: Volume 39, Number 6

    International Nuclear Information System (INIS)

    1994-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). Issuances of the Nuclear Regulatory Commission include: (1) Advanced Medical Systems, Inc.; (2) Henry Allen, Diane Marrone, and Susan Settino; and (3) Westinghouse Electric Corporation. Issuances of the Atomic Safety and Licensing Boards include: (1) Sequoyah Fuels Corporation and General Atomics Corporation and (2) Umetco Minerals Corporation. Issuances of Director's Decisions include: (1) Advanced Medical Systems, Inc., and (2) Boston Edison Company and all boiling water reactors. The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  1. Indexes to Nuclear Regulatory Commission issuances, July-September 1983

    International Nuclear Information System (INIS)

    1983-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as guide to the issuances

  2. White paper on nuclear safety in 1981

    International Nuclear Information System (INIS)

    1981-01-01

    The measures to research, develop and utilize atomic energy in Japan have been strengthened since the Atomic Energy Act was instituted in 1955, always on the major premise of securing the safety. The Nuclear Safety Commission established in October, 1978, has executed various measures to protect the health and safety of the nation as the center of the atomic energy safety regulation administration in Japan. Now, the Nuclear Safety Commission has published this annual report on atomic energy safety, summarizing various activities for securing the safety of atomic energy since its establishment to the end of March, 1981. This report is the inaugural issue, and the course till the Nuclear Safety Commission has made its start is also described. The report is composed of general remarks, response to the TMI accident, the safety regulation and security of nuclear facilities, the treatment and disposal of radioactive wastes, the investigation of environmental radioactivity, the countermeasures for preventing disasters around nuclear power stations and others, the research on the safety of atomic energy, international cooperation, and the improvement of the basis for securing the safety. Various related materials are attached. (Kako, I.)

  3. Load bearing capacities and elastic-plastic behavior of reactor vessel internals

    International Nuclear Information System (INIS)

    Watanabe, Keita; Nagase, Ryuichi

    2017-01-01

    Radial Support Keys (RSKs) are installed at the bottom of Reactor Vessel Internal (RVI) of Pressurized Water Reactor (PWR) and fit into Core Support Lugs of Reactor Pressure Vessel (RPV). This structure provides reactor core horizontal support and transmits the loads between RVI and RPV. RSK is one of the critical parts of RVI from the view point of earthquake-proof safety. In order to assure the structural integrity of Nuclear Reactor in case of massive earthquake, load bearing capacities of RSK are confirmed by static loading tests with reduced-scale mockups. In addition, collapse loads of actual components calculated by Limit Analyses are conservative enough compared to the load bearing capacities confirmed by the test. Thus, the methodology to calculate collapse load by Limit Analysis is applicable to evaluation of structural integrity for RSK. (author)

  4. Indexes to Nuclear Regulatory Commission issuances, January-June 1987

    International Nuclear Information System (INIS)

    1988-02-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  5. Indexes to Nuclear Regulatory Commission issuances, July-December 1986

    International Nuclear Information System (INIS)

    1987-07-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  6. Indexes to Nuclear Regulatory Commission issuances, July-September 1986

    International Nuclear Information System (INIS)

    1987-06-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  7. Indexes to Nuclear Regulatory Commission issuances, July-December 1987

    International Nuclear Information System (INIS)

    1988-04-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  8. Indexes to Nuclear Regulatory Commission issuances, January-June 1982

    International Nuclear Information System (INIS)

    1982-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  9. Indexes to Nuclear Regulatory Commission issuances, July--December 1989

    International Nuclear Information System (INIS)

    1990-05-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  10. Improved safety at CERN

    CERN Multimedia

    2006-01-01

    As announced in Weekly Bulletin No. 43/2006, a new approach to the implementation of Safety at CERN has been decided, which required taking some managerial decisions. The guidelines of the new approach are described in the document 'New approach to Safety implementation at CERN', which also summarizes the main managerial decisions I have taken to strengthen compliance with the CERN Safety policy and Rules. To this end I have also reviewed the mandates of the Safety Commission and the Safety Policy Committee (SAPOCO). Some details of the document 'Safety Policy at CERN' (also known as SAPOCO42) have been modified accordingly; its essential principles, unchanged, remain the basis for the safety policy of the Organisation. I would also like to inform you that I have appointed Dr M. Bona as the new Head of the Safety Commission until 31.12.2008, and that I will proceed soon to the appointment of the members of the new Safety Policy Committee. All members of the personnel are deemed to have taken note of the d...

  11. Nuclear Regulatory commission issuances, Volume 42, No. 5

    International Nuclear Information System (INIS)

    1995-11-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  12. Nuclear Regulatory Commission issuances. Volume 42, No. 6

    International Nuclear Information System (INIS)

    1995-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  13. Nuclear Regulatory Commission issuances, Volume 45, No. 2

    International Nuclear Information System (INIS)

    1997-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Director's Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  14. Nuclear Regulatory Commission issuances. Volume 42, No. 4

    International Nuclear Information System (INIS)

    1995-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  15. Nuclear Regulatory Commission issuances. Volume 42, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  16. Nuclear Regulatory Commission issuances. Volume 38, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors; Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

  17. White paper on nuclear safety in 2005

    International Nuclear Information System (INIS)

    2006-04-01

    The white paper consists of four parts. The first part described the outline of international discussions on safety culture and activities promoted by utilities and regulatory bodies in Japan. The second part explained the main activities of the Nuclear Safety Commission of Japan and nuclear regulatory authorities on nuclear safety regulation. The third part introduced various activities for ensuring overall nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster measures at nuclear facilities, progress in nuclear research, nuclear safety regulation by risk-informed utilization, environmental radiation surveys, international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission of Japan. (J.P.N.)

  18. Report of nuclear utility industry responses to Kemeny Commission recommendations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-02-15

    The purpose of this paper is to provide a report of nuclear utility industry progress in responding to the recommendations of the President's Commission on the Accident at Three Mile Island (The Kemeny Commission). On April 11, 1979, in response to TMI, President Carter established a Commission to conduct '.... a comprehensive study and investigation of the recent accident involving the nuclear power facility on Three Mile Island in Pennsylvania'. The Commission was chaired by Dr. John G. Kemeny, then President of Dartmouth College. (A list of all members of The Kemeny Commission is provided in Attachment to the Appendix ). The report of the commission's findings and recommendations was transmitted to the President in October 1979. During this same period, the nuclear utility industry responded to TMI by creating the Institute of Nuclear Power Operations (INPO) with a mission to promote the highest levels of safety and reliability - to promote excellence - in the operation of nuclear electric generating plants. In addition, the Nuclear Safety Analysis Center (NSAC) was established at the Electric Power Research Institute (EPRI to evaluate the accident and assist in determining the best industry response. In a White House paper (and press release) of December 7 1979, the President announced that he agreed fully with the spirit and intent of al the Kemeny Commission recommendations and requested that the industry and The Nuclear Regulatory Commission (NRC) comply with the recommendations. The President also recognized the industry initiative in establishing INPO and called for several actions involving the Institute; the President directed the Department of Energy and other government agencies to provide assistance to INPO and the industry. An overall status of the nuclear utility industry responses to Kemeny Commission recommendations in the key areas directly related to nuclear plant operations is provided below. A more detailed status of industry responses to the

  19. Report of nuclear utility industry responses to Kemeny Commission recommendations

    International Nuclear Information System (INIS)

    1989-02-01

    The purpose of this paper is to provide a report of nuclear utility industry progress in responding to the recommendations of the President's Commission on the Accident at Three Mile Island (The Kemeny Commission). On April 11, 1979, in response to TMI, President Carter established a Commission to conduct '.... a comprehensive study and investigation of the recent accident involving the nuclear power facility on Three Mile Island in Pennsylvania'. The Commission was chaired by Dr. John G. Kemeny, then President of Dartmouth College. (A list of all members of The Kemeny Commission is provided in Attachment to the Appendix ). The report of the commission's findings and recommendations was transmitted to the President in October 1979. During this same period, the nuclear utility industry responded to TMI by creating the Institute of Nuclear Power Operations (INPO) with a mission to promote the highest levels of safety and reliability - to promote excellence - in the operation of nuclear electric generating plants. In addition, the Nuclear Safety Analysis Center (NSAC) was established at the Electric Power Research Institute (EPRI to evaluate the accident and assist in determining the best industry response. In a White House paper (and press release) of December 7 1979, the President announced that he agreed fully with the spirit and intent of al the Kemeny Commission recommendations and requested that the industry and The Nuclear Regulatory Commission (NRC) comply with the recommendations. The President also recognized the industry initiative in establishing INPO and called for several actions involving the Institute; the President directed the Department of Energy and other government agencies to provide assistance to INPO and the industry. An overall status of the nuclear utility industry responses to Kemeny Commission recommendations in the key areas directly related to nuclear plant operations is provided below. A more detailed status of industry responses to the

  20. Present activities of the Nuclear Energy Commission in the field of safety of radiation sources and security of radioactive materials in Mongolia

    International Nuclear Information System (INIS)

    Oyuntulkhuur, N.

    2001-01-01

    The Radiation Safety Department of the Nuclear Energy Commission (NEC) is a regulatory body in Mongolia established in 1997. The paper gives a general overview of the main activities of the NEC on regulatory control of radiation sources in Mongolia. Mongolia declared itself a nuclear-weapon-free zone in 1992. Legal framework and waste management issues are described. The regulatory authority's co-operation with other agencies in radiation protection is also presented in this paper. (author)

  1. The extent and influence of Asbestos Safety Awareness training among managers who had previously commissioned an asbestos survey in their workplace buildings

    OpenAIRE

    HICKEY, Jane; SAUNDERS, Jean; DAVERN, Peter

    2015-01-01

    A telephone survey was conducted among a sample of managers (n=30) in Ireland who had previously commissioned an asbestos survey in their workplace buildings. The aims of the telephone survey were to examine the extent to which managers had completed Asbestos Safety Awareness (ASA) training, and to assess how such training might influence (i) their instinctive thoughts on asbestos, and (ii) their approach to aspects of asbestos management within their buildings. Managers’ motivations for comm...

  2. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1992-02-01

    This revision of the sixth edition of the NRC Practice and Procedure Digest contains a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to March 31, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  3. Nuclear Regulatory Commission issuances. Volume 22, No. 4

    International Nuclear Information System (INIS)

    1985-10-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

  4. White paper on nuclear safety in 2000

    International Nuclear Information System (INIS)

    2001-04-01

    This report is composed of three parts and a subjective part Part 1 includes special articles on the measures for the security of nuclear safety and the future problems described from the beginning of the security. Taking consideration that there exists potential risk in the utilization of nuclear energy in addition to the previous accidents in the area of nuclear energy, future measures to take for safety security were discussed as well as the reorganization of government facilities. In addition, the measures for nuclear safety according to the special nuclear disaster countermeasure law and the future problems were described. In Part 2, the trend of nuclear safety in 2000 and the actual effects of 'the basic principle for the countermeasures of the hour' proposed by the nuclear safety commission were outlined. Moreover, the activities of the commission in 2000 were briefly described. In Part 3, various activities for security of nuclear safety, the safety regulation system and the disaster protection system in nuclear facilities, nuclear safety researches in Japan were described in addition to international cooperation as to nuclear safety. Finally, various materials related to the nuclear safety commission, and the materials on the practical activities for nuclear safety were listed in the subjective part. (M.N.)

  5. Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank. Revision 3

    International Nuclear Information System (INIS)

    Hardy, H.A.; Laats, E.T.

    1985-03-01

    The United States Nuclear Regulatory Commission (USNRC) 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 to be used by code development and assessment groups in meeting the code correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the USNRC. The NRC/DAE Data Bank and the capabilities of the data access software are described in this document

  6. Nuclear Regulatory Commission issuances, March 1975

    International Nuclear Information System (INIS)

    1975-04-01

    Reactor licensing actions taken by the Nuclear Regulatory Commission, the Atomic Safety and Licensing Appeal Board and the Atomic Safety and Licensing Boards for March 1975 are presented. Action was included for the following reactors: Big Rock Point Nuclear Plant; West Valley Reprocessing Plant; Limerick Generating Station, Units 1 and 2; Midland Plants, Units 1 and 2; Wolf Creek Generating Station, Unit 1; Monticello Nuclear Generating Plant, Unit 1; Douglas Point Nuclear Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Vermont Yankee Nuclear Power Station; and WPPSS Hanford Units 1 and 4. (U.S.)

  7. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1992-08-01

    This 2nd revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to September 30, 1991, interpreting the NRC's Rules of Pratice in 10 CFR Part 2

  8. United States Nuclear Regulatory Commission Staff practice and procedure digest

    International Nuclear Information System (INIS)

    1990-08-01

    This Revision Number 7 of the fifth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period July 1, 1972 to March 31, 1990, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  9. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1992-05-01

    This 2nd revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to June 30, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  10. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1993-08-01

    This 7th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to September 30, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  11. United States Nuclear Regulatory Commission Staff practice and procedure digest

    International Nuclear Information System (INIS)

    1993-05-01

    This 6th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to June 30, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

  12. Nuclear Regulatory Commission issuances, May 1993

    International Nuclear Information System (INIS)

    1993-05-01

    This report contains the issuances received during the specified period (May 1993) from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not deemed a part of these opinions or have any independent legal significance. Contents of this document include an Issuance of the Nuclear Regulatory Commission with respect to the Sacramento Municipal Utility District and Issuances of Directors' Decisions concerning the Interstate Nuclear Service Corporation; Niagara Mohawk Power Corporation; and Texas Utilities Electric Company, et al. and All Nuclear Power Plants with Thermo-Lag Fire Barriers

  13. Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Chinese Edition)

    International Nuclear Information System (INIS)

    2014-01-01

    This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

  14. Radiation protection and safety of radiation sources: International basic safety standards. General safety requirements. Pt. 3 (French Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

  15. Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Arabic Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

  16. Description of data-sources used in SafetyCube, Deliverable 3.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Hagström, L. Thomson, R. Hermitte, T. Weijermars, W. Bos, N. Talbot, R. Thomas, P. Dupont, E. Martensen, H. Bauer, R. Hours, M. Høye, E. Jänsch, M. Murkovic, A. Niewöhner, W. Papadimitriou, E. Pérez, C. Phan, V. Usami, D. & Vázquez-de-Prada, J.

    2017-01-01

    Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

  17. Kemeny commission report. Comments by NPC (Nuclear Power Company)

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Following the accident at Three Mile island in March 1979 the Nuclear Power Company (NPC) has made evaluations of the available information and carried out preliminary investigations of the implications of the accident for all UK AGR's and for the PWR design. The results are summarized. Recommendations of the President's Commission are discussed with especial reference to those under the following headings: (1) The utility and its suppliers. (2) Training of operating personnel. (3) Technical assessment. It is concluded that while many of the relevant recommendations in the report of the President's Commission are already satisfied by UK practices for nuclear safety, and are being applied by NPC in their current programmes of work on AGR's and PWR's it is realised that it is of the utmost importance that complacent attitudes to safety are not allowed to develop. The accident at TMI and report of the Commision have provided a sharp reminder of the necessity to maintain unremitting vigilance in all aspects of design, construction and operation which are involved with the safety of the public and operators.

  18. H.R. 5448: a bill to amend the Atomic Energy Act of 1954, as amended, to reorganize the functions of the Nuclear Regulatory Commission by abolishing the Commission and in its place establishing the Nuclear Regulation and Safety Agency. Introduced in the House of Representatives, Ninety-Ninth Congress, Second Session, August 15, 1986

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    The Omnibus Nuclear Safety Act of 1986 amends the Atomic Energy Act of 1954 by replacing the Nuclear Regulatory Commission with a new entity, the Nuclear Regulation and Safety Agency. The purposes are to promote an energy policy that is better coordinated and more consistent with the protection of public health and safety. The new agency would also expedite licensing for construction and operation of nuclear power plants by using pre-approved standardized designs and sites

  19. Indexes to Nuclear Regulatory Commission issuances, January--June 1989

    International Nuclear Information System (INIS)

    1989-09-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats. These formats are case named index digests and headers, legal citations index, subject index, and facility index

  20. Work and safety managements for on-site installation, commissioning, tests by EU of quench protection circuits for JT-60SA

    International Nuclear Information System (INIS)

    Yamauchi, Kunihito; Okano, Jun; Shimada, Katsuhiro; Ohmori, Yoshikazu; Terakado, Tsunehisa; Matsukawa, Makoto; Koide, Yoshihiko; Kobayashi, Kazuhiro; Ikeda, Yoshitaka; Fukumoto, Masahiro; Kushita, Kouhei N.

    2016-03-01

    The superconducting Satellite Tokamak machine “JT-60SA” under construction in Naka Fusion Institute is an international collaborative project between Japan Atomic Energy Agency (JAEA) as the Implementing Agency (IA) of Japan (JA) and Fusion for Energy (F4E) as the IA of Europe (EU). The contributions for this project are based on the supply of components, and thus European manufacturer shall conduct the installation, commissioning and tests on Naka site under the general supervision by F4E via the designated institute in each EU nation. This means that JAEA had an issue to manage the works by European workers and their safety although there is no direct contract. This report describes the approaches for the work and safety managements, which were agreed with EU after the negotiation, and the completed on-site works for Quench Protection Circuits (QPC) as the first experience for EU in JT-60SA project. (author)

  1. Scientific management of the commissioning of the Temelin NPP

    International Nuclear Information System (INIS)

    Pazdera, F.; Vasa, I.; Svoboda, C.

    2002-01-01

    A Scientific Supervisory Group (SSG) for the commissioning of the Temelin nuclear power plant was set up by the statutory body of CEZ, a.s. (utility which holds responsibility for the start-up of the plant pursuant to Act No. 18/1997). The SSG provides support to the operator through expertise in nuclear safety assurance and nuclear power plant commissioning. Nuclear Research Institute Rez plc was appointed to this function. The article gives the definition and explains the statute of the SSG, highlights its main tasks and responsibilities, and presents the main results of activities of the SSG. The mission of the International Scientific Council for the Commissioning of the Temelin NPP is also briefly outlined. (author)

  2. Indexes to Nuclear Regulatory Commission issuances, January 1, 1980--December 31, 1985

    International Nuclear Information System (INIS)

    1989-11-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

  3. The extent and influence of Asbestos Safety Awareness training among managers who had previously commissioned an asbestos survey in their workplace buildings.

    Science.gov (United States)

    Hickey, Jane; Saunders, Jean; Davern, Peter

    2015-01-01

    A telephone survey was conducted among a sample of managers (n=30) in Ireland who had previously commissioned an asbestos survey in their workplace buildings. The aims of the telephone survey were to examine the extent to which managers had completed Asbestos Safety Awareness (ASA) training, and to assess how such training might influence (i) their instinctive thoughts on asbestos, and (ii) their approach to aspects of asbestos management within their buildings. Managers' motivations for commissioning the asbestos survey were also identified. The study found that ASA-trained managers (n=11) were not significantly more likely to work in larger organisations or in organisations which operated an accredited management system. Though ASA-trained managers' instinctive thoughts on asbestos were of a slightly poorer technical quality compared with those of non-ASA-trained managers, they were still significantly more cognisant of their responsibilities towards those of their employees at specific risk of asbestos exposure. Most managers (n=28) commissioned the asbestos survey to satisfy a pre-requisite of external contractors for commencing refurbishment/demolition work in their buildings. Given its potential to positively influence the occupational management of asbestos, the authors recommend the general promotion of suitably tailored ASA-training programmes among building managers and external contractors alike.

  4. Barsebaeck power plant - safety and emergency measures

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    A Swedish-Danish Committee on safety at the Swedish nuclear power plant Barsebaeck was established in 1979 in order to evaluate the nuclear safety at Barsebaeck with a view to the reactor accident at the Three-Mile-Island nuclear power plant March 28, 1979. According to the committees mandate the investigations of the Kemeny Commission, the Rogouin investigation, investigations of the American Nuclear Regulatory Commission, and the Swedish report ''Safe nuclear power'' have been taken into consideration by the Committee. Furthermore, it has formed the basis for the Committees work that the authority responsibility for the safety at Barsebaeck lies with the Swedish authorities, and that these authorities have evaluated the safety aspects before the permissions for operation of the Barsebaeck power plant were given and hereafter currently in connection with the inspection of the power plant. The report prepared by the Commission treats aspects as: a) Nuclear safety at the Barsebaeck power plant, b) reactor safety and emergency provisions, c) common elements in the emergency provision situation in Sweden and Denmark, d) ongoing investigations on course of events during accidents and release limiting safety systems. (BP)

  5. Course of atomic energy safety during ten years

    International Nuclear Information System (INIS)

    1988-10-01

    The Nuclear Safety Commission started in the autumn of 1978 as the result of reexamining the system of atomic energy safety regulation in order to deal with the national criticism against the promotion of atomic energy that arose after the radiation leak accident on the nuclear ship 'Mutsu' 1974. For the development of atomic energy, it is indispensable to obtain the understanding and trust of nation on the safety of atomic energy as clearly shown in the Atomic Energy Act and in the background of founding and the policy of hte Nuclear Safety Commission. The Nuclear Safety Commission has carried out the safety examination for the permission of installing nuclear facilities, the decision of guidelines for the examination, the holding of public hearing, the promotion of safety research and so on. In this book, the reform of the system of atomic energy safety regulation, the countermeasures after TMI accident, the public hearing and others taking root, the further heightening of reliability of LMRs, efforts for operation managment and environment safety, the substantiating of the research on atomic energy safety, the diversification of the objects of safety regulation, the treatment and disposal of radioactive waste, the countermeasures after the chernobyl-4 accident and the positive promotion of international cooperation are described. (Kako, I.)

  6. 77 FR 8257 - Sunshine Act Open Commission Meeting

    Science.gov (United States)

    2012-02-14

    ... Safety and Title: The Proposed Extension of Part 4 Homeland Security. of the Commission's Rules Regarding Outage Reporting to Interconnected Voice Over Internet Protocol Service Providers and Broadband Internet... outage reporting under Part IV of the rules to interconnected Voice over Internet Protocol (VoIP) service...

  7. Regulatory view on licensing and commissioning of Temelin NPP

    International Nuclear Information System (INIS)

    Drabova, D.; Boehm, K.; Brandejs, P.; Tipek, Z.

    2004-01-01

    The competencies delegated to the Czech State Office for Nuclear Safety by Czech legislation are highlighted and the history of construction and commissioning of the Temelin nuclear power plant in relation to the licensing process is described. (P.A.)

  8. 75 FR 73946 - Worker Safety and Health Program: Safety Conscious Work Environment

    Science.gov (United States)

    2010-11-30

    ... Environment AGENCY: Office of the General Counsel, Department of Energy (DOE). ACTION: Notice of denial of... Nuclear Regulatory Commission's ``Safety-Conscious Work Environment'' guidelines as a model. DOE published.... Second, not only would instituting a ``Safety-Conscious Work Environment'' by regulation be redundant...

  9. Activities of the MPA Stuttgart in connection with QA of nuclear power plants

    International Nuclear Information System (INIS)

    Maier, H.J.

    1980-01-01

    The MPA Stuttgart (Institute of Testing of Materials, University of Stuttgart) is concerned with quality assurance of german nuclear power plants, additional to the technical inspection organizations and the plant owners. The orders are given by state authorities, federal authorities and the RSK (reactor security commission). There are shown some examples of this work, concerning with materials and testing of materials. (orig./RW)

  10. United State Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board, and Licensing Board decisions, July 1972--June 1988

    International Nuclear Information System (INIS)

    1989-04-01

    This fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 30, 1988 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This edition replaces in their entirety earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through June 30, 1988

  11. White paper on nuclear safety in 2004

    International Nuclear Information System (INIS)

    2005-05-01

    The white paper consists of four parts. The first part described the regulation of nuclear facility decommissioning and the clearance level at which the decommissioned waste materials are not necessarily treated as radioactive materials. The second part explained the main operations of the nuclear safety regulation of the Nuclear Safety Commission and the regulatory bodies in 2004 and Mihama unit 3 accident. The third part introduced various activities for the general preservation of nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster preparedness of nuclear facilities, progress in nuclear research, environmental radiation surveys and international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission. (J.P.N.)

  12. High Glucose Concentration Stimulates NHE-1 Activity in Distal Nephron Cells: the Role of the Mek/Erk1/2/p90RSK and p38MAPK Signaling Pathways

    Directory of Open Access Journals (Sweden)

    Juliana Martins da Costa-Pessoa

    2014-02-01

    Full Text Available Aims: In models of diabetes, distal nephron cells contribute to glucose uptake and oxidation. How these cells contribute to the use of glucose for the regulation of H+ extrusion remains unknown. We used Madin-Darby Canine Kidney (MDCK cells to investigate the effect of acute or chronic high glucose concentration on the abundance and activity of the Na+/H+ exchanger (NHE-1. Methods: Using RT-PCR, we also evaluated the mRNA expression for sodium glucose co-transporters SGLT1 and SGLT2. Protein abundance was analyzed using immunoblotting, and intracellular pH (pHi recovery was evaluated using microscopy in conjunction with the fluorescent probe BCECF/AM. The Na+-dependent pHi recovery rate was monitored with HOE-694 (50 µM and/or S3226 (10 µM, specific NHE-1 and NHE-3 inhibitors. Results: MDCK cells did not express the mRNA for SGLT1 or SGLT2 but did express the GLUT2, NHE-1 and NHE-3 proteins. Under control conditions, we observed a greater contribution of NHE-1 to pHi recovery relative to the other H+ transporters. Acute high glucose treatment increased the HOE-694-sensitive pHi recovery rate and p-Erk1/2 and p90RSK abundance. These parameters were reduced by PD-98059, a Mek inhibitor (1 µM. Chronic high glucose treatment also increased the HOE-694-sensitive pHi recovery rate and p-p38MAPK abundance. Both parameters were reduced by SB-203580, a p38MAPK inhibitor (10 µM. Conclusion: These results suggested that extracellular high glucose stimulated NHE-1 acutely and chronically through Mek/Erk1/2/p90RSK and p38MAPK pathways, respectively.

  13. Off-site emergency preparedness activities within the European Commission

    International Nuclear Information System (INIS)

    Kelly, G.N.

    1998-01-01

    Increasing attention is being given by the European Commission to off-site emergency preparedness as part of its broader contribution to improving nuclear safety in Eastern Europe. The main initiatives being taken or planned by the Commission in this area are summarised. Particular attention is given to two topics: Firstly, the development of the RODOS (Real-time On-line DecisiOn Support) system for supporting off-site emergency management in the event of a nuclear accident; and, secondly, the work of an Inter-Service Group on nuclear Off-Site Emergency Preparedness (OSEP) in Eastern Europe that has been established within the Commission. The contribution that each is making to improving emergency preparedness, both in Eastern Europe and in Europe more widely, is described. (orig.)

  14. European commission contribution to improving off-site emergency preparedness

    International Nuclear Information System (INIS)

    Kelly, G.N.

    1996-01-01

    Increasing attention is being given by the European Commission to off-site emergency preparedness as part of its broader contribution to improving nuclear safety in Eastern Europe. The main initiatives being taken or planned by the Commission in this area are summarized. Particular attention is given to two topics: firstly, the development of the RODOS (Real-time On-line Decision Support) system for supporting off-site emergency management in the event of a nuclear accident; and, secondly, the work of an Inter-Service Group on nuclear Off-Site Emergency Preparedness (OSEP) in Eastern Europe that has recently been established within the Commission. The contribution that each is making to improving emergency preparedness, both in Eastern Europe and in Europe more widely, is described

  15. Commissioning an Engineering Scale Coal Gasifier

    Energy Technology Data Exchange (ETDEWEB)

    Reid, Douglas J.; Bearden, Mark D.; Cabe, James E.

    2010-07-01

    This report explains the development, commissioning, and testing of an engineering scale slagging coal gasifier at PNNL. The initial objective of this project was to commission the gasifier with zero safety incidents. The commissioning work was primarily an empirical study that required an engineering design approach. After bringing the gasifier on-line, tests were conducted to assess the impact of various operating parameters on the synthesis gas (syngas) product composition. The long-term intent of this project is to produce syngas product for use by internal Pacific Northwest National Laboratory (PNNL) researchers in catalyst, materials, and instrumentation development. Future work on the project will focus on improving the reliability and performance of the gasifier, with a goal of continuous operation for greater than 4 hours using coal feedstock. In addition, alternate designs that allow for increased flexibility regarding the fuel sources that can be used for syngas production is desired. Continued modifications to the fuel feed system will be pursued to address these goals. Alternative feed mechanisms such as a coal/methanol slurry are being considered.

  16. Indexes to Nuclear Regulatory Commission issuances, January--March 1996

    International Nuclear Information System (INIS)

    1996-01-01

    This publication is the 1st quarter 1996 index to issuances by the US NRC. These include issuances by the Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking

  17. Indexes to Nuclear Regulatory Commission issuances, July--September 1997

    International Nuclear Information System (INIS)

    1998-01-01

    This digest and index lists the Nuclear Regulatory Commission (NRC) issuances for July to September 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking. There are five sections to this index: (1) case name index, (2) headers and digests, (3) legal citations index, (4) subject index, and (5) facility index. The digest provides a brief narrative of the issue, including the resolution of the issue and any legal references used for resolution

  18. Traffic legislation and safety in Europe concerning the moped and the A1 category (125 cc) motorcycle : a literature and questionnaire study commissioned by the Swedish National Road Administration

    NARCIS (Netherlands)

    Schoon, C.C.

    2004-01-01

    A study, commissioned by the Swedish National Road Administration, of the safety aspects of mopeds and the light motorcycle A1 category (max. 125 cc) has been carried out. The study consists of a comparison of European countries. An important part of the information was gathered using questionnaires

  19. Implementation of safety goals in NRC's regulatory process

    International Nuclear Information System (INIS)

    Murley, T.E.

    1985-01-01

    In May 1983 the Nuclear Regulatory Commission issued a policy statement on Safety Goals For Nuclear Power Plant Operation. The Commission at the same time judged that a two-year evaluation period was necessary to judge the effectiveness of the goals and design objectives, and directed the staff to develop information and understanding as to how to further define and use the design objectives and the cost-benefit guidelines. In carrying out the Commission's mandate, the staff framed three major questions to be addressed during the safety goal evaluation period. These three questions are: 1) to what extent is it practical to use safety goals in the regulatory process. 2) Should the quantitative design objectives be modified or supplemented. If so, how. 3) How should the safety goals be implemented at the end of the evaluation period. The staff's conclusions are discussed

  20. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest: Commission, Appeal Board and Licensing Board decisions, July 1972-December 1986

    International Nuclear Information System (INIS)

    1987-11-01

    This Revision 6 of the fourth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1986, interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 6 replaces in part earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through December 31, 1986

  1. United States Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board and Licensing Board decisions, July 1972--December 1989

    International Nuclear Information System (INIS)

    1990-06-01

    This Revision 6 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1989 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 6 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through December 31, 1989

  2. United States Nuclear Regulatory Commission Staff practice and procedure digest: Commission, Appeal Board and Licensing Board Decisions, July 1972-March 1987

    International Nuclear Information System (INIS)

    1987-12-01

    This Revision 7 of the fourth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to March 31, 1987 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 7 replaces in part earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through March 31, 1987

  3. United States Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board and Licensing Board decisions, July 1972--September 1988

    International Nuclear Information System (INIS)

    1989-04-01

    This Revision 1 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to September 30, 1988 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 1 replaces in part earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through September 30, 1988

  4. Indexes to Nuclear Regulatory Commission issuances, July--December 1988

    International Nuclear Information System (INIS)

    1989-04-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, legal citations index, subject index, and facility index

  5. Indexes to Nuclear Regulatory Commission issuances, July--September 1988

    International Nuclear Information System (INIS)

    1989-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These information elements are displayed in one or more of five separate formats. These formats are case name index, digests and headers, legal citations index, subject index and facility index

  6. Specific problems and practical experience of regulatory inspection during commissioning in the United Kingdom

    International Nuclear Information System (INIS)

    Lewis, G.

    1977-01-01

    The commissioning of nine Magnox and two Advanced Gas-cooled Reactor Nuclear Power Plants in the United Kingdom during the last sixteen years under the regulatory control of the Nuclear Installations Inspectorate of the Health and Safety Executive has been based on a Stage Approval Philosophy starting with proof-testing of the primary gas circuit and concluding with tests on the reactor at full power. The practical experience gained during this period has enabled the Nuclear Installations Inspectorate to rationalise the procedures and test requirements without comporomising safety standards. The Operating Rules and Maintenance Schedules are approved for commissioning and during this period are reviewed for their adequacy for future power operation of the plant. The organisation, documentation, test procedures and the commissioning programme used for the Advanced Gas-cooled Reactors are briefly explained. (author)

  7. The Commission's research action programme on the development of nuclear fission energy

    International Nuclear Information System (INIS)

    1984-01-01

    For its 'Framework Programme 1984-1987' the Commission has defined the major goals for a European Scientific and Technical Strategy. One of the means to reduce the energy dependence of the Community, which is an important objective, is to favour the development of nuclear fission energy. As electricity production by nuclear reactors has reached industrial maturity, the Community activities are directed mainly to safety aspects, in order to ensure the protection of workers and the general public, against hazards linked to operations in the nuclear fuel cycle. A description of the main features of the five sub-programmes on nuclear fission energy is given below; these programmes are: reactor safety; nuclear fuels and actinides research; management of radioactive waste; safeguarding and management of fissile materials; decommissioning of nuclear installations. The research and development work is carried out either by the Commission's Joint Research Center or by organizations and companies of the Member Countries, with the Commission's financial support. (author)

  8. An emergent proposal on the Committee of Uranium Processing Factory Criticality Accident Survey of the Nuclear Safety Commission. A meantime report dated on November 5, 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The Nuclear Safety Commission was received a decision on thorough investigations of accident reason on criticality accident at the Tokai-mura uranium processing factory of the JCO Incorporation occurred on September 30, 1999, to establish the Committee of Uranium Processing Factory Criticality Accident Survey to elucidate its reason thoroughly and contribute to set up a sufficient reforming prevention countermeasure. This Committee judged that it was important to propose a countermeasure directly obtainable by grasping some fact relations clarified before now as soon as possible and intended to conduct this meantime report of 'emergent proposal' by arrangement of such fact relations. Here were described on accidental conditions and their effects, response to the accident (on prevention of the accident), its reasons and their relating conditions, and some emergent proposals. In the last items, safety security at accidental site, health countermeasures to residents and others, establishment of safety security for nuclear business workers and others, and reconstruction on safety regulation in national government. (G.K.)

  9. Indexes to Nuclear Regulatory Commission issuances, July-December 1985. Volume 22, Index 2

    International Nuclear Information System (INIS)

    1986-03-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

  10. Indexes to Nuclear Regulatory Commission issuances, July-September 1981. Index 1

    International Nuclear Information System (INIS)

    1981-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  11. Overview of the Nuclear Regulatory Commission's safety research program

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1989-01-01

    Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

  12. European vehicle passive safety network

    NARCIS (Netherlands)

    Wismans, J.S.H.M.; Janssen, E.G.

    1999-01-01

    The general objective of the European Vehicle Passive Safety Network is to contribute to the reduction of the number of road traffic victims in Europe by passive safety measures. The aim of the road safety policy of the European Commission is to reduce the annual total of fatalities to 18000 in

  13. The reorganisation of the French Atomic Energy Commission

    International Nuclear Information System (INIS)

    Glaize, G.

    1977-01-01

    The Atomic Energy Commission (CEA) has somewhat distinctive features when compared to other French public administrations. The Commission had been designed, when created in 1945, as a body very close to the Head of Government with, at the same time, great freedom of action; these two aspects demonstrated the importance accorded to its duties and the desire to assure its efficiency. The evolution of the Commission subsequently resulted in reducing these differences and strengthening the ministerial supervision as well as the role of the Administrator-General as compared with that of the High Commissioner. In the 1970s the Commission's structures developed in another direction, in view of the reorientation of its duties in the perspective of the development of the private nuclear sector and the increasing importance of nuclear safety questions. This reorganisation resulted in the creation of fairly autonomous operational units and a number of subsidiary bodies and specialised institutes. The outcome of this exercise has been to give the CEA a very diversified structure which is not as centralised as previously. (NEA) [fr

  14. Nuclear Regulatory Commission issuances, March 1995. Volume 41, No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  15. Nuclear Regulatory Commission issuances, May 1995. Volume 41, No. 5

    International Nuclear Information System (INIS)

    1995-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  16. Nuclear Regulatory Commission issuances, March 1995. Volume 41, No. 3

    International Nuclear Information System (INIS)

    1995-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  17. Nuclear Regulatory Commission issuances, May 1995. Volume 41, No. 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  18. Nuclear Regulatory Commission issuances, April 1994. Volume 39, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

  19. Nuclear Regulatory Commission issuances, December 1994. Volume 40, No. 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

  20. Nuclear Regulatory Commission issuances, September 1994. Volume 40, No. 3

    International Nuclear Information System (INIS)

    1994-01-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

  1. Nuclear Regulatory Commission issuances, February 1996: Volume 43, No. 2

    International Nuclear Information System (INIS)

    1996-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  2. Nuclear Regulatory Commission issuances, February 1996: Volume 43, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

  3. Commission of the European Communities review of fast reactor activities, March 1981

    Energy Technology Data Exchange (ETDEWEB)

    Balz, W [Commission of the European Communities, Brussels (Belgium)

    1981-05-01

    The Commission of the European Communities continued its activities in the field of fast reactors development essentially in the frame of the Fast Reactor Coordinating Committee (FRCC) and by execution of a Reactor Programme at its Joint Research Center (JRC). The study was concerned with introducing fast reactors into European Community, elaboration of preliminary safety criteria and guidelines for typical fast reactor accidents; codes and standards; LMFBR safety, fuel, fuel cycle safety.

  4. Commission of the European Communities review of fast reactor activities, March 1981

    International Nuclear Information System (INIS)

    Balz, W.

    1981-01-01

    The Commission of the European Communities continued its activities in the field of fast reactors development essentially in the frame of the Fast Reactor Coordinating Committee (FRCC) and by execution of a Reactor Programme at its Joint Research Center (JRC). The study was concerned with introducing fast reactors into European Community, elaboration of preliminary safety criteria and guidelines for typical fast reactor accidents; codes and standards; LMFBR safety, fuel, fuel cycle safety

  5. 47 CFR 95.1125 - RF safety.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false RF safety. 95.1125 Section 95.1125 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PERSONAL RADIO SERVICES Wireless Medical Telemetry Service (WMTS) General Provisions § 95.1125 RF safety. Portable devices...

  6. Safety goals for nuclear power

    International Nuclear Information System (INIS)

    Fischhoff, B.

    1984-02-01

    The key policy question in managing hazardous technologies is often some variant of How safe is safe enough. The US Nuclear Regulatory Commission has recently broached this topic by adopting safety goals defining acceptable risk levels for nuclear power plants. These goals are analyzed here with a general theory of standard setting (Fischhoff, 1983) which asks: (1) Are standards an appropriate policy tool in this case. (2) Can the Commission's safety philosophy be defended. (3) Do the operational goals capture that philosophy. The anlaysis shows the safety goals proposal to be sophisticated in some respects, incomplete in others. More generally, it points to difficulties with the concept of acceptable risk and any attempt to build policy instruments around it. Although focused on the NRC's safety goals, the present analysis is a prototype of what can be learned by similarly detailed consideration of other standards, not only for nuclear power but also for other hazardous technologies, as well as for issues unrelated to safety

  7. Microbiological safety cabinets, cytotoxic safety cabinets. Choice and use

    International Nuclear Information System (INIS)

    Balty, I.; Belhanini, B.; Clermont, H.; Cornu, J.C.; Jacquet, M.A.; Texte, J.C.

    2003-01-01

    Drawn up by a working group composed of prevention professionals, manufacturers and control bodies, this guide is intended to help those responsible for safety in laboratories choose and acquire materials responding to the intended protection objectives. It provides recommendations for the commissioning and control of these materials as well as for their use. After a description of the operational characteristics of safety cabinets, this guide looks at the important points to be taken into account when ordering, accepting and commissioning equipment adapted to precise needs. It also covers verification of correct operation and provides a number of common sense rules relative to precautions for use. Material cleaning and decontamination is described briefly on account of the very specialized character of this activity. Detailed information relative to this subject should be sought in the literature. (authors)

  8. 76 FR 23810 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response...

    Science.gov (United States)

    2011-04-28

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response Interoperability Center Public Safety Advisory Committee Meeting AGENCY... Fullano, Associate Chief, Public Safety and Homeland Security Bureau, Federal Communications Commission...

  9. Nuclear Regulatory Commission issuances. Volume 47, Number 2

    International Nuclear Information System (INIS)

    1998-02-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). They involve: 21st Century Technologies, Inc.; Hydro Resources, Inc.; Northeast Utilities; and Northern States Power Company

  10. Proposal of resolution to create an inquiry commission on the french nuclear power plants reliability in case or earthquakes and on the safety, information and warning procedures in case of incidents

    International Nuclear Information System (INIS)

    2003-01-01

    This short paper presents the reasons of the creation of parliamentary inquiry commission of 30 members, on the reliability of the nuclear power plants in France in case of earthquakes and on the safety, information and warning procedures in case of accidents. (A.L.B.)

  11. 47 CFR 90.1420 - Failure to comply with the NSA or the Commission's rules.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Failure to comply with the NSA or the... § 90.1420 Failure to comply with the NSA or the Commission's rules. (a) Failure to comply with the Commission's rules or the terms of the NSA may warrant cancelling the Public Safety Broadband License. The...

  12. Fuel Receiving and Storage Station. Nuclear Regulatory Commission's safety evaluation report

    International Nuclear Information System (INIS)

    1976-01-01

    The safety evaluation report covers design of structures, components, equipment, and systems; nuclear criticality safety; radiological safety; accident analysis; conduct of operations; quality assurance; common defense and security; financial qualifications; financial protection and indemnity requirements; and technical specifications

  13. 47 CFR 90.1335 - RF safety.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false RF safety. 90.1335 Section 90.1335 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Wireless Broadband Services in the 3650-3700 MHz Band § 90.1335 RF safety...

  14. A procedure for the analysis of errors of commission in a Probabilistic Safety Assessment of a nuclear power plant at full power

    International Nuclear Information System (INIS)

    Julius, J.; Jorgenson, E.; Parry, G.W.; Mosleh, A.M.

    1995-01-01

    This paper describes an analytical procedure that has been developed to facilitate the identification of errors of commission for inclusion in a Probabilistic Safety Assessment (PSA) of a nuclear power plant operating at full power. The procedure first identifies the opportunities for error by determining when operators are required to intervene to bring the plant to a safe condition following a transient, and then identifying under what conditions this is likely to occur using a model of the causes of error. In order to make the analysis practicable, a successive screening approach is used to identify those errors with the highest potential of occurrence. The procedure has been applied as part of a PSA study, and the results of that application are summarized. For the particular plant to which the procedure was applied, the conclusion was that, because of the nature of the procedures, the high degree of redundancy in the instrumentation, the operating practices, and the control board layouts, the potential for significant errors of commission is low

  15. United States Nuclear Regulatory Commission staff practice and procedure digest. Commission, Appearl Board and Licensing Board decisions, July 1972-June 1985. Digest No. 4

    International Nuclear Information System (INIS)

    1986-01-01

    This edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period July 1, 1972 to June 30, 1985 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This edition replaces earlier editions and supplements and includes appropriate changes reflecting the amendment to the Rules of Practice effective June 30, 1985

  16. Indexes to Nuclear Regulatory Commission issuances, January--March 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

    This document provides digests and indexes for issuances of the Nuclear Regulatory Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors Decisions, and the Decisions on Petitions for Rulemaking. These indexes and digests are intended to serve as a guide to the issuances.

  17. Indexes to Nuclear Regulatory Commission issuances, January--March 1997

    International Nuclear Information System (INIS)

    1997-01-01

    This document provides digests and indexes for issuances of the Nuclear Regulatory Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors Decisions, and the Decisions on Petitions for Rulemaking. These indexes and digests are intended to serve as a guide to the issuances

  18. Management and organization in nuclear power plant safety

    International Nuclear Information System (INIS)

    Osborn, R.N.

    1983-08-01

    In the immediate aftermath of the Three Mile Island accident, the Nuclear Regulatory Commission-sponsored investigations of the relation between human issues and safety tended to focus on individual and, at most, group level phenomena. This initial bottom up view of organizational safety has continued to be investigated by the Nuclear Regulatory Commission, as evidence by the four previous papers. Recently, however, work has begun which adopts a top down management/organization approach to nuclear power plant safety. This paper reports on the research, to date, on this focus

  19. 47 CFR 101.1425 - RF safety.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false RF safety. 101.1425 Section 101.1425 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES FIXED MICROWAVE... safety. MVDDS stations in the 12.2-12.7 GHz frequency band do not operate with output powers that equal...

  20. Nuclear Regulatory Commission issuances: Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1 - December 31, 1996. Volume 44, Pages 1 - 432

    International Nuclear Information System (INIS)

    1997-01-01

    The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. Issuances are referred to as follows: Commission--CLI, Atomic Safety and Licensing Boards--LBP, Administrative Law Judges--ALJ, Directors' Decisions--DD, and Decisions on Petitions for Rulemaking--DPRM

  1. Nuclear Regulatory Commission issuances: Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1--December 31, 1996. Volume 44, Pages 1--432

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. Issuances are referred to as follows: Commission--CLI, Atomic Safety and Licensing Boards--LBP, Administrative Law Judges--ALJ, Directors` Decisions--DD, and Decisions on Petitions for Rulemaking--DPRM.

  2. 1990 Recommendations of the International Commission on Radiological Protection adopted by the Commission in November 1990

    International Nuclear Information System (INIS)

    1991-01-01

    This publication represents a completely new set of basic recommendations, outdating ICRP Publication 26. They aim to: a) take account of new biological information and of trends in setting safety standards; b) improve the presentation of the recommendations: c) maintain as much stability in the recommendations as is consistent with the new information. The recommendations cover quantities, biological aspects, the conceptual framework of radiological protection, proposed and continuing practices (occupational, medical and public exposure) and implementation of the Commission's Recommendations. (UK)

  3. 47 CFR 101.1525 - RF safety.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false RF safety. 101.1525 Section 101.1525 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES FIXED MICROWAVE SERVICES Service and Technical Rules for the 70/80/90 GHz Bands § 101.1525 RF safety. Licensees in the 70...

  4. Evaluation of power commissioning of the Mochovce Unit 1 demonstration run

    International Nuclear Information System (INIS)

    Sarvaic, I.; Miskolci, M.

    1998-01-01

    The document contains evaluation of the 144 hour demonstration run of the Mochovce Unit 1. In the document, the courses and results of additional tests in this phase of power commissioning are summarized, evaluation of the performance of important systems and equipment of the unit is carried out, as well as of the compliance with Limits and Conditions in the course of the demonstration run. On this basis, conclusions are drawn and recommendations given for the unit to by ready for trial operation. The evaluation was developed by the scientific management of the Mochovce commissioning providing an independent support for the operators for supervising the commissioning tasks from the point of nuclear safety

  5. Safety first. Yes, but which safety?; Primat der Sicherheit. Ja, aber welche Sicherheit ist gemeint?

    Energy Technology Data Exchange (ETDEWEB)

    Roehlig, Klaus-Juergen [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Endlagerforschung; Eckhardt, Anne [risicare GmbH, Zollikerberg (Switzerland)

    2017-09-01

    The site selection law in Germany and the final report of the final repository commission state the central objective to find a repository site that will guarantee safety for the next million of years. Decision makers, concerned and interested people have obviously different opinions and acceptance criteria with respect to the tools for the demonstration of safety (safety case). Possible solutions for a broad acceptance of safety definitions are discussed.

  6. Dissemination material template, Deliverable 2.2 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Tros, M. & Houtenbos, M.

    2016-01-01

    Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

  7. Problems and experience of regulatory review associated with plant construction and commissioning

    International Nuclear Information System (INIS)

    Commander, W.

    1979-01-01

    The work of the Assessment Branch of NII covering the regulatory review during design safety assessment, construction, commissioning and operation is described commencing with the nuclear licensing procedure through licence variations and conditions attached to the licence, to the final stages of plant construction up to commercial operation and full power production. The importance of the application of safety assessment principles is outlined, the importance of the Safety Inspectorate Schedule described, and the need to retain organisational and regulatory flexibility emphasised. (author)

  8. New Safety rules

    CERN Multimedia

    Safety Commission

    2008-01-01

    The revision of CERN Safety rules is in progress and the following new Safety rules have been issued on 15-04-2008: Safety Procedure SP-R1 Establishing, Updating and Publishing CERN Safety rules: http://cern.ch/safety-rules/SP-R1.htm; Safety Regulation SR-S Smoking at CERN: http://cern.ch/safety-rules/SR-S.htm; Safety Regulation SR-M Mechanical Equipment: http://cern.ch/safety-rules/SR-M.htm; General Safety Instruction GSI-M1 Standard Lifting Equipment: http://cern.ch/safety-rules/GSI-M1.htm; General Safety Instruction GSI-M2 Standard Pressure Equipment: http://cern.ch/safety-rules/GSI-M2.htm; General Safety Instruction GSI-M3 Special Mechanical Equipment: http://cern.ch/safety-rules/GSI-M3.htm. These documents apply to all persons under the Director General’s authority. All Safety rules are available at the web page: http://www.cern.ch/safety-rules The Safety Commission

  9. Nuclear Regulatory Commission Issuances. Volume 42, No. 1, Pages 1--45

    International Nuclear Information System (INIS)

    1995-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

  10. Indexes to Nuclear Regulatory Commission issuances, July-December 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: case name index; digests and headers; legal citations index; subject index; and facility index

  11. Indexes to Nuclear Regulatory Commission issuances, January--June 1991

    International Nuclear Information System (INIS)

    1991-10-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: Case name index, digest and headers, legal citations index, subject index, and facility index

  12. Indexes to Nuclear Regulatory Commission issuances, January--March 1991

    International Nuclear Information System (INIS)

    1991-06-01

    Digests and indexes for Issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, logical citations index, subject index and facility index

  13. Indexes to Nuclear Regulatory Commission issuances, January-March 1982

    International Nuclear Information System (INIS)

    1982-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. This information is displayed in one or more of five separate formats arranged as follows: case name index; digests and headers; legal citations index; subject index; and facility index

  14. Indexes to Nuclear Regulatory Commission issuances, January--June 1990

    International Nuclear Information System (INIS)

    1990-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALI), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, legal citations index, subject index, and facility index

  15. Indexes to Nuclear Regulatory Commission issuances, July--September 1990

    International Nuclear Information System (INIS)

    1990-12-01

    Digests and indexes for issuances of the commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. The information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, legal citations index, subject index, and facility index

  16. Indexes to Nuclear Regulatory Commission issuances, July--December 1990

    International Nuclear Information System (INIS)

    1991-03-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers legal citations index, subject index, and facility index

  17. Indexes to Nuclear Regulatory Commission Issuances, January--June 1994

    International Nuclear Information System (INIS)

    1994-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  18. The Cold War legacy of regulatory risk analysis: The Atomic Energy Commission and radiation safety

    Science.gov (United States)

    Boland, Joseph B.

    From its inception in 1946 the Atomic Energy Commission pioneered the use of risk analysis as a mode of regulatory rationality and political rhetoric, yet historical treatments of risk analysis nearly always overlook the important role it played in the administration of atomic energy during the early Cold War. How this absence from history has been achieved and why it characterizes most historical accounts are the subjects of Chapter II. From there, this study goes on to develop the thesis that the advent of the atomic bomb was a world-shattering event that forced the Truman administration to choose between two novel alternatives: (1) movement towards global governance based initially on cooperative control of atomic energy or (2) unsparing pursuit of nuclear superiority. I refer to these as nuclear internationalism and nuclear nationalism, respectively. Each defined a social risk hierarchy. With the triumph of nuclear nationalism, nuclear annihilation was designated the greatest risk and a strong nuclear defense the primary means of prevention. The AEC's mission in the 1950s consisted of the rapid development of a nuclear arsenal, continual improvements in weapons technologies, and the promotion of nuclear power. The agency developed a risk-based regulatory framework through its dominant position within the National Committee on Radiation Protection. It embraced a technocratic model of risk analysis whose articulation and application it controlled, largely in secret. It used this to undergird a public rhetoric of reassurance and risk minimization. In practice, safety officials adjusted exposure levels within often wide parameters and with considerable fluidity in order to prevent safety concerns from interfering with operations. Secrecy, the political climate of the time, and a lack of accountability enabled the agency to meld technical assessments with social value judgments in a manner reflective of nuclear nationalism's risk hierarchy. In the late fifties

  19. Nuclear Regulatory Commission issuances: Volume 46, Number 6

    International Nuclear Information System (INIS)

    1997-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decision (DD), and the Decision on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  20. Nuclear Regulatory Commission issuances. Volume 46, Number 1

    International Nuclear Information System (INIS)

    1997-07-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  1. Nuclear Regulatory Commission issuances: Volume 46, Number 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decision (DD), and the Decision on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance.

  2. Nuclear Regulatory Commission issuances, Volume 45, No. 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance.

  3. Nuclear Regulatory Commission issuances. Volume 46, Number 2

    International Nuclear Information System (INIS)

    1997-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  4. Nuclear Regulatory Commission issuances, Volume 45, No. 5

    International Nuclear Information System (INIS)

    1997-05-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  5. United States Nuclear Regulatory Commission Staff practice and procedure digest

    International Nuclear Information System (INIS)

    1991-12-01

    This sixth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This sixth edition replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through December 31, 1990

  6. A Response to Proposed Equal Employment Opportunity Commission Regulations on Employer-Sponsored Health, Safety, and Well-Being Initiatives.

    Science.gov (United States)

    2016-03-01

    The aim of this study was to identify areas of consensus in response to proposed Equal Employment Opportunity Commission Americans with Disabilities Act of 1990 and Genetic Information Nondiscrimination Act of 2008 regulations on employer-sponsored health, safety, and well-being initiatives. The consensus process included review of existing and proposed regulations, identification of key areas where consensus is needed, and a methodical consensus-building process. Stakeholders representing employees, employers, consulting organizations, and wellness providers reached consensus around five areas, including adequate privacy notice on how medical data are collected, used, and protected; effective, equitable use of inducements that influence participation in programs; observance of reasonable alternative standards; what constitutes reasonably designed programs; and the need for greater congruence between federal agency regulations. Employee health and well-being initiatives that are in accord with federal regulations are comprehensive, evidence-based, and are construed as voluntary by employees and regulators alike.

  7. Nuclear reactors. Use of the protection system for non-safety purposes (International Electrotechnical Commission Standard Publication 639:1979)

    International Nuclear Information System (INIS)

    Stefanik, J.

    1996-01-01

    This standard applies to the protection system of a nuclear reactor and, more especially, to all interconnections between a reactor protection system (as defined and explained in International Electrotechnical Commission Publication 231 A, first supplement to Publication 231, General Principles of Nuclear Reactor Instrumentation) and all other systems and equipment not part of the protection system, except: a) the physical connection between sensors of the protection system and the physical variables that they monitor, such as for example, thermo wells, moderating medium for neutron sensors, etc.; b) the electrical connection between the protection system and the reactor control rods or other safety mechanism; c) the electrical and pneumatic connections to the power distribution system (mains) and pneumatic supplies that supply power to the protection system. Although many clauses relate to all reactor protection systems, this standard applies mainly to protection systems in nuclear power reactors

  8. Indexes to Nuclear Regulatory Commission Issuances

    International Nuclear Information System (INIS)

    1996-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and licensing Board Panel (LBP), the Administrative Law Judges (ALJ) the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index; Headers and Digests; Legal Citations Index; Subject Index; and Facility Index

  9. Indexes to Nuclear Regulatory Commission Issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and licensing Board Panel (LBP), the Administrative Law Judges (ALJ) the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM) are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements are displayed in one or more of five separate formats arranged as follows: Case Name Index; Headers and Digests; Legal Citations Index; Subject Index; and Facility Index.

  10. 77 FR 12054 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2012-02-28

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal..., Associate Bureau Chief, Public Safety and Homeland Security Bureau, Federal Communications Commission, 445...

  11. Arrangement between the US Nuclear Regulatory Commission (USNRC) and the Belgian Government for Exchange of Technical Information in Regulatory Matters and in Cooperation in Safety Research and in Standards Development

    International Nuclear Information System (INIS)

    1978-01-01

    This Arrangement was concluded on 6 June 1978 between the United States Nuclear Regulatory Commission and the Belgian Government for exchange of technical information in regulatory matters and in co-operation in safety research and in standards development. Both Parties agree to exchange, as available, technical information related to the regulation of safety and the environmental impact of designated nuclear energy facilities and to safety research of designated types of nuclear facilities. As regards co-operation in safety research, the execution of joint programmes and projects under which activities are divided between the two Parties will be agreed on a case by case basis. The Parties further agree to co-operate in the development of regulatory standards applicable to the designated nuclear facilities. The Arrangement is valid for 5 years and may be extended. (NEA) [fr

  12. 76 FR 10898 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response...

    Science.gov (United States)

    2011-02-28

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory..., Public Safety and Homeland Security Bureau, Federal Communications Commission, 445 12th Street, SW., Room..., Public Safety and Homeland Security Bureau. [FR Doc. 2011-4398 Filed 2-25-11; 8:45 am] BILLING CODE 6712...

  13. Safety of Research Reactors. Specific Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This Safety Requirements publication establishes requirements for all main areas of safety for research reactors, with particular emphasis on requirements for design and operation. It explains the safety objectives and concepts that form the basis for safety and safety assessment for all stages in the lifetime of a research reactor. Technical and administrative requirements for the safety of new research reactors are established in accordance with these objectives and concepts, and they are to be applied to the extent practicable for existing research reactors. The safety requirements established in this publication for the management of safety and regulatory supervision apply to site evaluation, design, manufacturing, construction, commissioning, operation (including utilization and modification), and planning for decommissioning of research reactors (including critical assemblies and subcritical assemblies). The publication is intended for use by regulatory bodies and other organizations with responsibilities in these areas and in safety analysis, verification and review, and the provision of technical support.

  14. Nuclear power reactor safety

    International Nuclear Information System (INIS)

    Pon, G.A.

    1976-10-01

    This report is based on the Atomic Energy of Canada Limited submission to the Royal Commission on Electric Power Planning on the safety of CANDU reactors. It discusses normal operating conditions, postulated accident conditions, and safety systems. The release of radioactivity under normal and accident conditions is compared to the limits set by the Atomic Energy Control Regulations. (author)

  15. National symposium on commissioning and operating experiences in heavy water plants and associated chemical industries [Preprint volume

    International Nuclear Information System (INIS)

    1992-02-01

    A symposium on commissioning and operating experiences in heavy water plants and associated chemical industries (SCOPEX-92) was organised to share the experience and exchange the ideas among plant operators, designers, consultants and vendors in the areas of operation, commissioning and equipment performance. This pre-print volume has been brought out as an integrated source of information on commissioning and operation of heavy water plants. The following aspects of heavy water plants are covered: commissioning and operation, instrumentation and control, and safety and environment. (V.R.)

  16. Decision no. 2011-DC-0224 of the French nuclear safety authority from May 5, 2011, ordering the French atomic energy and alternative energies commission (CEA) to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the French atomic energy commission (CEA). (J.S.)

  17. Indexes to Nuclear Regulatory Commission issuances, July-September 1982. Vol. 16. Index 1

    International Nuclear Information System (INIS)

    1982-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  18. 78 FR 17140 - Upholstered Furniture Fire Safety Technology; Meeting and Request for Comments

    Science.gov (United States)

    2013-03-20

    ... retardant (FR) chemicals, specialty fibers/fabrics without FR chemicals, inherently fire resistant materials... Furniture Fire Safety Technology; Meeting and Request for Comments AGENCY: Consumer Product Safety... Commission (CPSC, Commission, or we) is announcing its intent to hold a meeting on upholstered furniture fire...

  19. 75 FR 9899 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

    Science.gov (United States)

    2010-03-04

    ... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council; Notice of Public Meeting... Analysis Division, Public Safety and Homeland Security Bureau, Federal Communications Commission, 445 12th...

  20. 47 CFR 27.52 - RF safety.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false RF safety. 27.52 Section 27.52 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES MISCELLANEOUS WIRELESS COMMUNICATIONS SERVICES Technical Standards § 27.52 RF safety. Licensees and manufacturers are subject to the...

  1. The safety of nuclear power plants

    International Nuclear Information System (INIS)

    Berg, J.O.

    1980-01-01

    A general presentation is given of reactor safety philosophy and risk analysis. The Rasmussen report (WASH-1400) is discussed and also the Lewis Commission's evaluation of that report. The future developments in reactor safety technology are outlined with emphasis on quality assurance. (JIW)

  2. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1990-11-01

    This Revision 8 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 30, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 8 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through June 30, 1990

  3. Aim, mode of work and main recommendations of the Commission Energies 2050

    International Nuclear Information System (INIS)

    Anon.

    2012-01-01

    The Commission Energies 2050 has led an analysis of various scenarios concerning the energy mix for electricity production in France. The aim was to shed light on the future investment needed. The Commission has released 8 recommendations: 1) to develop a culture of energy saving and energy efficiency; 2) to quantify any decision in energy policy by considering its impacts on cost, on public financing needs, on commercial balance, on jobs and on environment; 3) to consider only safety concerns to close a nuclear plant; 4) to have a policy of truth concerning the real cost of energy; 5) to propose to the European partners new rules for the energy market in order to allow the investment needed and to give consistency to all the players; 6) to propose a worldwide standardization at the highest level of the nuclear safety rules; 7) to develop coordinated research programs concerning all the aspects of energy: sustainable aspect, storage, safety,... and 8) to continue developing a long-term prospect for nuclear power. (A.C.)

  4. EU stresstest national report of Germany. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-15

    The European Council concluded in March that the safety of all EU nuclear plants should be reviewed on the basis of a comprehensive and transparent risk assessment (''stress test''). The German Bundestag (Federal Parliament) called upon the German Federal Government on 17{sup th} March 2011 to conduct a comprehensive review of the safety requirements for the German nuclear power plants. The competent Federal Ministry asked its advisory body, the RSK, to perform this review. The findings of the RSK safety review were presented to the public on 17{sup th} May 2011. ENSREG published the scope and modalities for comprehensive risk and safety assessments of EU nuclear power plants on 13{sup th} May 2011. This ''Declaration of ENSREG'' determines the concept, methodology and time schedule of the EU stress test. The BMU as the federal regulator in Germany asked the Laender authorities to initiate the EU stress tests according to the ENSREG Declaration. The ''stress tests'' were started by all German licensees with the self-commitment to deliver the progress report by 15{sup th} August 2011 and the final report by 31{sup st} October 2011. The structure of the German national report follows mainly the chapters according to the ENSREG Declaration. In addition detailed insights from the broader scope and specific methodology of the RSK safety review are also included in the chapters. In chapter 6 are in particular insights from the RSK safety review related to initiating events caused by man-made hazards, such as an aircraft crash, terrorist attack or cyber attacks. The licensee progress reports and the certificates by the competent federal state regulators reflect an interim state. Further work is planned and should take additional guidance to be given by ENSREG into account. The Federal State authorities have so far reviewed the licensee reports in terms of completeness, the adequate application of the ENSREG

  5. Evaluation of power commissioning of the Mochovce Unit 1 power level up to 100 % Nnom

    International Nuclear Information System (INIS)

    Sarvaic, I.; Mickolci, M.

    1998-01-01

    The document contains an evaluation of the power phase of power commissioning of the Mochovce Unit 1 in the phase up to the power level of 100 % N nom .In the document, the courses and results of tests in this phase of power commissioning are summarized, evaluation of the performance of important systems and equipment of the unit is carried out, and the compliance with Limits and Conditions in the course of the phase is assessed. On this basis, conclusions are drawn and recommendations for the unit to be ready for subsequent phases of the power commissioning. The evaluation was developed by the scientific management of the Mochovce commissioning providing an independent support for the operators for supervising the commissioning tasks from the point of nuclear safety

  6. Commissioning of cryogenic system for China Spallation Neutron Source

    Science.gov (United States)

    Ye, Bin; He, Chongchao; Li, Na; Ding, Meiying; Wang, Yaqiong; Yu, Zhang; He, Kun

    2017-12-01

    China Spallation Neutron Source(CSNS) cryogenic system provides supercritical cryogenic hydrogen to neutron moderators, including a helium refrigerator, hydrogen loop and hydrogen safety equipment. The helium refrigerator is provided by Linde with cooling capacity of 2200 W at 20 K. Hydrogen loop system mainly includes cryogenic hydrogen pipes, hydrogen circulator cold-box and accumulator cold-box. Cryogenic hydrogen pump, ortho-para convertor, helium-hydrogen heat-exchanger, hydrogen heater and accumulator are integrated in hydrogen circulation cold-box, and accumulator cold-box. Hydrogen safety equipment includes safety valves, rupture disk, hydrogen sensor, flame detector and other equipment to ensure that cryogenic system in dangerous situations will go down, vents, or takes other measures. The cryogenic system commissioning work includes four steps. First, in order to test the refrigerating capacity of refrigerator, when acceptance testing, refrigerator internal heater was used as thermal load. Second, using simulation load as heat load of moderator, hydrogen loop use helium instead of hydrogen, and cooled down to 20 K, then re-warming and test the leak detection of hydrogen loop system. Third, base on the step 2, using hydrogen as working medium, and optimized the control logic. Forth, cryogenic system with the moderators joint commissioning. Now, cryogenic system is connected with the moderators, and the forth step will be carried out in the near future.

  7. Road Safety Data, Collection, Transfer and Analysis DaCoTa. Deliverable 0.1: Final project report.

    NARCIS (Netherlands)

    Thomas, P. Hill, J. Morris, A.P. Welsh, R. Talbot, R. Muhlrad, N. Vallet, G. Yannis, G. Papadimitriou, E. Evgenikos, P. Dupont, E. Martensen, H. Hermitte, T. Bos, N. & Aarts, L.

    2015-01-01

    The European Road Safety Observatory was established European Commission and first announced in the 2001 Transport White Paper1. It was further developed in the 2003 Road Safety Action Plan 2 where the Commission announced it was to establish a new European Road Safety Observatory (ERSO) to

  8. Seeking a safety culture

    International Nuclear Information System (INIS)

    Lee, T.

    1993-01-01

    Human organisational failure has been shown to play a significant role in major accidents world-wide in both the nuclear and non-nuclear industries. A recent report called Organising for Safety, published by The Health and Safety Commission, suggests that the nuclear industry should give organisational factors the same emphasis as it does the reduction of equipment failures and individual error. (Author)

  9. A word from the DG: Improved safety at CERN

    CERN Multimedia

    2006-01-01

    One of the important objectives of my term of office is improving safety at CERN. My consideration of safety issues over the last few months, in conjunction with the Safety Commission and the Heads of Department, has led me to define a new approach for the implementation of safety policy at CERN. It is not a question of changing the safety policy and the basic safety rules laid down in document 'Safety Policy at CERN' (SAPOCO 42) but, rather, of improving the way they are applied by clarifying the roles of everyone concerned. The existing safety policy and rules have yet to be fully implemented. Some people continue to think, for example, that safety implementation only concerns the Safety Commission (SC). In reality, as SAPOCO 42 clearly specifies, safety is the responsibility of each and every individual. This means that each person in charge of a task is also responsible for guaranteeing its safe completion by implementing all the necessary measures. To enhance the awareness of this responsibility and t...

  10. Licensing of the OPAL reactor during construction and commissioning

    International Nuclear Information System (INIS)

    Summerfield, M.

    2007-01-01

    This paper presents a description of the licensing activities associated with the construction and commissioning of the Australian Nuclear Science and Technology Organisation's (ANSTO) OPAL reactor. It addresses the Construction Licence, the interface between ANSTO, INVAP (the contractor with responsibility for design and construction of the facility) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA, the Australian nuclear regulator) during the construction of OPAL, specific licensing issues that have arisen during the construction and commissioning process, and the Operating Licence Application. Particular emphasis will be given to the way in which the licensing process is integrated into the overall project program and the lessons learnt that may be of benefit to other licensees and regulators

  11. A comparison of some Mexican/U.S. safety regulations

    Energy Technology Data Exchange (ETDEWEB)

    Bunner, W.R. [Training Associates, Columbus, OH (United States)

    1994-12-31

    In the US, safety and hygiene began to be enforced broadly with the formation of the US Department of Labor`s, Occupational Safety and Health Administration (OSHA) in 1970. In Mexico, the 1917 Constitution required companies to protect their workers against safety and hygiene hazards in the workplace. Additional requirements were added with the Federal Labor Law of 1931. General safety and hygiene regulations were added in 1934. Modern-day federal labor law in Mexico requires the creation of mixed safety and hygiene commissions in all industries. However, only about 114,000 workplaces have registered mixed commissions. In a similar vein, the most favored OSHA reform bill in the US proposes to require safety and health committees in all work places. At this time such committees are common in larger companies but not in smaller ones.

  12. Indexes to Nuclear Regulatory Commission issuances, July-December 1984. Volume 20, Index 2

    International Nuclear Information System (INIS)

    1985-03-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking for the period July-December 1984 are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

  13. Safety of nuclear fuel cycle facilities. Safety requirements

    International Nuclear Information System (INIS)

    2008-01-01

    This publication covers the broad scope of requirements for fuel cycle facilities that, in light of the experience and present state of technology, must be satisfied to ensure safety for the lifetime of the facility. Topics of specific reference include aspects of nuclear fuel generation, storage, reprocessing and disposal. Contents: 1. Introduction; 2. The safety objective, concepts and safety principles; 3. Legal framework and regulatory supervision; 4. The management system and verification of safety; 5. Siting of the facility; 6. Design of the facility; 7. Construction of the facility; 8. Commissioning of the facility; 9. Operation of the facility; 10. Decommissioning of the facility; Appendix I: Requirements specific to uranium fuel fabrication facilities; Appendix II: Requirements specific to mixed oxide fuel fabrication facilities; Appendix III: Requirements specific to conversion facilities and enrichment facilities

  14. Investigation of conditions inside the reactor building annulus of a PWR plant of KONVOI type in case of severe accidents with increased containment leakages

    International Nuclear Information System (INIS)

    Bakalov, Ivan; Sonnenkalb, Martin

    2018-01-01

    Improvements of the implemented severe accident management (SAM) concepts have been done in all operating German NPPs after the Fukushima Daiichi accidents following recommendations of the German Reactor Safety Commission (RSK) and as a result of the stress test being performed. The efficiency of newly developed severe accident management guidelines (SAMG) for a PWR KONVOI reference plant related to the mitigation of challenging conditions inside the reactor building (RB) annulus due to increased containment leakages during severe accidents have been assessed. Based on two representative severe accident scenarios the releases of both hydrogen and radionuclides into the RB annulus have been predicted with different boundary conditions. The accident scenarios have been analysed without and with the impact of several SAM measures (already planned or proposed in addition), which turned out to be efficient to mitigate the consequences. The work was done within the frame of a research project financially supported by the Federal Ministry BMUB.

  15. Investigation of conditions inside the reactor building annulus of a PWR plant of KONVOI type in case of severe accidents with increased containment leakages

    Energy Technology Data Exchange (ETDEWEB)

    Bakalov, Ivan [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Berlin (Germany); Sonnenkalb, Martin [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany)

    2018-02-15

    Improvements of the implemented severe accident management (SAM) concepts have been done in all operating German NPPs after the Fukushima Daiichi accidents following recommendations of the German Reactor Safety Commission (RSK) and as a result of the stress test being performed. The efficiency of newly developed severe accident management guidelines (SAMG) for a PWR KONVOI reference plant related to the mitigation of challenging conditions inside the reactor building (RB) annulus due to increased containment leakages during severe accidents have been assessed. Based on two representative severe accident scenarios the releases of both hydrogen and radionuclides into the RB annulus have been predicted with different boundary conditions. The accident scenarios have been analysed without and with the impact of several SAM measures (already planned or proposed in addition), which turned out to be efficient to mitigate the consequences. The work was done within the frame of a research project financially supported by the Federal Ministry BMUB.

  16. Addressing issues raised by stakeholders: evolving practices at the Canadian Nuclear Safety Commission (CNSC)

    International Nuclear Information System (INIS)

    Flavelle, Peter

    2004-01-01

    request of community groups, in 1994 the AECB began to publish the Radiation Index to provide information to the public on radiation exposure from Canadian nuclear generating stations. The proliferation of environmental assessment documents has lead the CNSC to develop EA summaries to simplify information for interested stakeholders and to direct them to where more detailed information can be found. The CNSC created Report Cards on Nuclear Power Plants in response to a recommendation of the Auditor General of Canada for a more transparent reporting of the status of nuclear power plants. Extensive stakeholder consultation is an integral part of developing new or amending existing regulations. It took three years of consultations to develop the regulations pursuant to the Nuclear Safety and Control Act. Subsequent amendments to those regulations also receive stakeholder scrutiny, and in some instances the implementation of regulations is modified in response to stakeholder consultation. Furthermore, the drafting of every Regulatory Policy, Standard and Guide includes stakeholder review and formal dispositioning of stakeholder comments as part of the Regulatory Documents Development Process. In summary, operations and practices at the Canadian Nuclear Safety Commission have been evolving in response to changing societal expectations and in response to issues and concerns expressed by stakeholders about the nuclear industry and nuclear regulation in Canada

  17. 75 FR 22291 - Safety Standard for Toddler Beds

    Science.gov (United States)

    2010-04-28

    ... Kiss, Division of Human Factors, Directorate for Engineering Sciences, Consumer Product Safety... testing requirements to address those types of incidents. Accordingly, the Commission proposes a new 16.... With this in mind, the Commission proposes two alternative labels that address the entrapment hazard...

  18. Notification of the commission on the eco-toxicity of chemical substances; Avis de la commission d'evaluation de l'ecotoxicite des substances chimiques

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The french commission on the evaluation of the chemical substances eco-toxicity, published recommendations concerning the use of additives for the automotive fuels, for the cooling circuit of electric power plants and for gases against fire. The risks for the public health are analysed and safety precautions are asked. (A.L.B.)

  19. Environmental monitoring and independent analysis: the experience of the local information commission in Cadarache

    International Nuclear Information System (INIS)

    Foucher, M.

    2010-01-01

    The 2006 Act on 'Open Access to Information and Nuclear Safety' provides free access to nuclear installations data and submits nuclear facilities to an independent administrative authority, the ASN (French Nuclear Safety Authority). A local information committee (CLI - Commission locale d'informations) has been set up for each nuclear facility. It includes all the parties involved and may commission expert studies and environmental measurement tests from independent laboratories. Prompted by environmental organizations, the Cadarache CLI commissioned a CRIIRAD (Commission de Recherche et d'Informations Independantes sur la Radioactivite) fact-finding survey in 2008-2009 to evaluate the environmental impact of the CEA/Cadarache installations since they were created. This study points to a moderate present impact, though a lack of data makes it impossible to reconstruct environmental impact prior to 1979. A set of guidelines are put forward to assess the past impact in greater detail and to lessen the current impact even further. Following this study, additional steps to minimize this impact will be taken by CEA/Cadarache inside the facilities, and by the relevant LCI outside the installations. Developing independent expert skills is a major challenge for CLIs to gain better knowledge of nuclear activities and improve their local management. (author)

  20. The House of Commons of Canada, Bill C-23 : An act to establish the Canadian Nuclear Safety Commission and to make consequential amendments to other acts

    International Nuclear Information System (INIS)

    1996-01-01

    This enactment replaces the Atomic Energy Control Act with a modern statute to provide for more explicit and effective regulation of nuclear energy. While the existing Act encompasses both the regulatory and developmental aspects of nuclear activities, this enactment disconnects the two functions and provides a distinct identity to the regulatory agency. It replaces the Atomic Energy Control Board with the Canadian Nuclear Safety Commission, underlining its separate role from that of Atomic Energy of Canada Ltd., the federal research, development and marketing organization for nuclear energy

  1. Opinions and decisions of the Atomic Energy Commission with selected orders. Progress report, July 1, 1972--December 31, 1972

    International Nuclear Information System (INIS)

    1974-01-01

    Issuances of the Atomic Energy Commission, the Atomic Safety and Licensing Board, the Atomic Safety and Licensing Appeal Board, and the Board of Contract Appeals during the period July through December 1972 are presented

  2. Development of French technical safety regulations: safety fundamental rules

    International Nuclear Information System (INIS)

    Lebouleux, P.

    1982-09-01

    The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operations of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation pratice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS -or a letter- can also give the result of the examination of the constructor and operator code (RCC) by safety authorities

  3. Development of French technical safety regulations: safety fundamental rules

    International Nuclear Information System (INIS)

    Lebouleux, P.

    1983-01-01

    The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operating of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridicial sense; they are called Regles Fondamentales de Surete (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS - or a letter - can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

  4. 77 FR 73345 - Safety Standard for Bedside Sleepers

    Science.gov (United States)

    2012-12-10

    ... durable infant or toddler products, in consultation with representatives of consumer groups, juvenile... Commission (Commission or CPSC) to promulgate consumer product safety standards for durable infant or toddler... marking, labeling, and instructional literature of the proposed rule should be directed to the Office of...

  5. 47 CFR 80.1109 - Distress, urgency, and safety communications.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Distress, urgency, and safety communications. 80.1109 Section 80.1109 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Global Maritime Distress and Safety System (GMDSS...

  6. Nuclear Regulatory Commission issuances, April 1995. Volume 41, Number 4

    International Nuclear Information System (INIS)

    1995-04-01

    This book contains issuances of the Nuclear Regulatory Commission and of the Atomic Safety and Licensing Boards, and an issuance of the Director's decision. The issuances concern a petition filed by Dr. James E Bauer seeking interlocutory Commission review of the Atomic Safety and Licensing Board's order imposing several restrictions on Dr. Bauer; a denial of an Interveners' Petition for Review addressing the application of Babcock and Wilcox for a renewal of its Special Nuclear Materials License; granting a motion for a protective order, by Sequoyah Fuel Corporation and General Atomics, limiting the use of the protected information to those individuals participating in the litigation and for the purposes of the litigation only; granting a Petitioner's petition for leave to intervene and request for a hearing concerning Georgia Institute of Technology (Georgia Tech Research Reactor) renewal of a facility license; and a denial of a petition filed by Mr. Ted Dougherty requesting a shutdown of the San Onofre Nuclear Generating Station based on concerns regarding the vulnerability of the plant to earthquakes and defensibility of the plant to a terrorist threat

  7. Comparison of hydrogen generation for TVSM and TVSA fuel assemblies for water water energy reactor (VVER)-1000

    International Nuclear Information System (INIS)

    Stefanova, A.E.; Groudev, P.P.; Atanasova, B.P.

    2009-01-01

    This paper presents the results received during investigation of hydrogen generation for both types fuel assemblies-the old modernistic type of fuel assemblies (TVSM) and recently installed new one alternative type of fuel assemblies (TVSA) in case of severe accident. There are some differences between both types FAs. They have different geometry as well as different burnable poisons. To investigate behavior of new fuel assemblies during the severe conditions it have been performed comparison of fuel behavior of old type TVSM fuel assembly to new one TVSA. To perform this investigation it has been used MELCOR 'input model' for Kozloduy Nuclear Power Plant (KNPP) VVER 1000. The model was developed by Institute for Nuclear Research and Nuclear Energy-Bulgarian Academy of Sciences (INRNE-BAS) for investigation of severe accident scenarios and Probabilistic Safety Analyses (PSA) level 2. The model provides a significant analytical capability for the Bulgarian technical specialists, working in the field of the NPP safety, for analysis of core and containment damaged states and the estimation of radionuclides release outside fuel cladding. It was accepted criteria for vessel integrity about hydrogen concentration to be 8%. This criterion was based on the decision of RSK (Germany commission for reactor safety). Generally based on the received results it was made conclusion that using both types of fuel assemblies it was not disturbance safety conditions of NPP

  8. EU stresstest national report of Germany. Implementation of the EU stress tests in Germany

    International Nuclear Information System (INIS)

    2011-01-01

    The European Council concluded in March 2011 that the safety of all EU nuclear plants should be reviewed on the basis of a comprehensive and transparent risk assessment (''stress test''). In addition to the European initiative, all countries with operating nuclear power plants indicated the performance of immediate safety reviews to take into account any lessons already learned or to be learned from the Fukushima Dai-ichi accident of 11 th March 2011. The German Bundestag (Federal Parliament) called upon the German Federal Government on 17 th March 2011 to conduct a comprehensive review of the safety requirements for the German nuclear power plants. The competent Federal Ministry asked its advisory body, the RSK, to perform this review. The findings of the RSK safety review were presented to the public on 17 th May 2011. For the European stress tests, ENSREG published the scope and modalities for comprehensive risk and safety assessments of EU nuclear power plants on 13 th May 2011. This ''Declaration of ENSREG'' determines the concept, methodology and time schedule of the EU stress test. Detailed requirements on content and structure of the reports and the planned peer reviews in 2012 were developed under the leadership of ENREG and agreed at its meeting on 11 th October 2011. The BMU as the federal regulator in Germany asked the Laender nuclear regulatory authorities to initiate the EU stress tests according to the ENSREG Declaration. A joint meeting of BMU, Laender authorities, expert organisations and the licensees of the German nuclear power plants took place on 30 th June 2011 to agree on the scope and the procedure of stress tests in Germany. It was also decided to take the 30 th June 2011 as the reference date for the plants in operation, regardless future decisions on the possible limitation of the operating time by amendment to the Atomic Energy Act which were in the legislative procedure at that time. The ''stress tests'' were started by all German

  9. Health and safety in the nuclear age

    International Nuclear Information System (INIS)

    1988-01-01

    In their Communication to the Council on the development of Community measures for the application of Chapter III of the Euratom Treaty - Health and safety (COM(86) 434 final) the Commission of the European Communities announced their intention to initiate a 'Standing Conference on Health and Safety in the Nuclear Age' in order to contribute to an increase of information on nuclear activities. Following this proposition, the Commission (Directorate-General for Employment, Social Affairs and Education, Health and Safety Directorate) organized the first meeting of this Standing Conference in Luxembourg on 5, 6 and 7 October 1987 with the theme 'Information for the public and the media on health protection and safety with regard to nuclear activities'. About 120 participants representing scientific experts, the media, the bodies concerned with environmental or consumer protection, the social partners and interested national and international organizations, took part in this conference. It was the first time at European Community level that a meeting allowed an exchange of positions on the health problems related to ionizing radiation by all the parties interested in this subject. The Commission was asked to pursue this dialogue in order to improve the perception of citizens of the Community of the potential risks and the methods of protection brought into force in the nuclear field

  10. White paper on nuclear safety in 1993. 1993 ed.

    International Nuclear Information System (INIS)

    1994-01-01

    When the development and utilization of nuclear power are advanced, the securing of safety is the prerequisite. The Nuclear Safety Commission has promoted the various important measures which become the basis for securing the safety, such as the execution of strict safety examination, the preparation and perfection of the guidelines which are used for safety examination, the holding of public hearings, the investigation of failures and troubles, and the reflection of the obtained learnings to the countermeasures for securing the safety. Since nuclear power facilities contain radioactive substances, the prevention of their abnormal release to surrounding environment is the fundamental of securing the safety. The policy of coping with severe accidents was determined after Three Mile Island accident and Chernobyl accident, and the concrete investigation is carried out. In this year, the abandonment of radioactive waste in ocean by Russia was a large problem. In this book, the Nuclear Safety Commission in the last one year and the securing of safety related to the utilization of plutonium for power reactors are reported. Various related materials are attached. (K.I.)

  11. Installation and commissioning of operation nuclear power plant reactor protection system modernization project

    International Nuclear Information System (INIS)

    Lu Weiwei

    2010-01-01

    Qinshan Nuclear Power Plant is the first nuclear power plant in mainland China; it is also the first one which realizes the modernization of analog technology based Reactor Protection System in the operation nuclear power plant of China. The implementation schedule is the shortest one which use same digital technology platform (TELEPERM XS of AREVA NP) to modifying the safety class I and C system in the world, the whole project spent 28 months from equipment contract signed to putting system into operation. It open up a era for operation nuclear power plant using mature digital technology to make safety class I and C system modernization in China. The important practical significance of this successful project is very obvious. This article focus on two important project stage--equipment installation and system commissioning, it is based on a large number of engineering implementation fact, it covers the problems and solutions happened during the installation and commission. The purpose of the article is to share the experience and lessons of safety I and C system modernization for other operation nuclear power plant. (authors)

  12. Indexes to Nuclear Regulatory Commission issuances, January-June 1986. Volume 23, Index 2

    International Nuclear Information System (INIS)

    1986-01-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats. These formats are case name index, digests and headers, legal citations index, subject index, and facility index

  13. Indexes to Nuclear Regulatory Commission Issuances, July-September 1985. Volume 22, Index 1

    International Nuclear Information System (INIS)

    1985-12-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. The period from July through September 1985 is covered

  14. Indexes to Nuclear Regulatory Commission issuances, January 1, 1986-- December 31, 1990

    International Nuclear Information System (INIS)

    1992-11-01

    Digests and indexes for issuances of the commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats arranged as follows: Case name index; digests and headers; legal citations index; subject index; and facility index

  15. Period1 gates the circadian modulation of memory-relevant signaling in mouse hippocampus by regulating the nuclear shuttling of the CREB kinase pP90RSK

    DEFF Research Database (Denmark)

    Rawashdeh, Oliver; Jilg, Antje; Maronde, Erik

    2016-01-01

    , the presence of PER1 in hippocampal neurons is a prerequisite for the time-of-day-dependent phosphorylation of CREB, as it regulates the shuttling of pP90RSK into the nucleus. Representative immunofluorescence images show a temporal difference in phosphorylated cAMP response element-binding protein (p...... activation. Taken together, the PER1-dependent modulation of cytoplasmic-to-nuclear signaling in the murine hippocampus provides a molecular explanation for how the circadian system potentially shapes a temporal framework for daytime-dependent memory performance, and adds a novel facet to the versatility......CREB; green color) levels in all regions of the dorsal hippocampus between a wild-type C3H mouse (WT; left) and a Period1-knockout (Per1−/−; right) mouse. Images were taken 2 h after lights on, thus, when fluctuating levels of pCREB peak in WT mouse hippocampus. Insets show a representative hippocampal neuron...

  16. Safety and licensing issues for Indian PHWRs

    International Nuclear Information System (INIS)

    Srinivasan, G.R.; Das, M.

    1997-01-01

    India has achieved competency in design, construction, commissioning and operation of Pressurized Heavy Water Reactor based Nuclear Power Plants and has completed more than 120 reactor operating years with an extremely satisfactory safety record. In this paper, the safety management in NPCIL and operational safety aspects are discussed, licensing and regulatory approach is described and some of the main safety issues for Indian PHWRs are brought out. (author)

  17. United States Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board, and Licensing Board decisions issued from July 1, 1972 through March 31, 1986

    International Nuclear Information System (INIS)

    1986-10-01

    A digest is given of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to March 31, 1986, interpreting the NRC's Rules of Practice. Parts of earlier editions and supplements are replaced, and amendments to the Rules of Practice effective through March 31, 1986 are reflected. The material included deals with applications, prehearing matters, hearings, post-hearing matters, appeals, and decisions related to general matters. Decisions are indexed by facility, citation, CFR, statutes, case law, and other legal citations

  18. Special committee review of the Nuclear Regulatory Commission's severe accident risks report (NUREG--1150)

    International Nuclear Information System (INIS)

    Kouts, H.J.C.; Apostolakis, G.; Kastenberg, W.E.; Birkhofer, E.H.A.; Hoegberg, L.G.; LeSage, L.G.; Rasmussen, N.C.; Teague, H.J.; Taylor, J.J.

    1990-08-01

    In April 1989, the Nuclear Regulatory Commission's (NRC) Office of Nuclear Regulatory Research (RES) published a draft report ''Severe Accident Risks: An Assessment for Five US Nuclear Power Plants,'' NUREG-1150. This report updated, extended and improved upon the information presented in the 1974 ''Reactor Safety Study,'' WASH-1400. Because the information in NUREG-1150 will play a significant role in implementing the NRC's Severe Accident Policy, its quality and credibility are of critical importance. Accordingly, the Commission requested that the RES conduct a peer review of NUREG-1150 to ensure that the methods, safety insights and conclusions presented are appropriate and adequately reflect the current state of knowledge with respect to reactor safety. To this end, RES formed a special committee in June of 1989 under the provisions of the Federal Advisory Committee Act. The Committee, composed of a group of recognized national and international experts in nuclear reactor safety, was charged with preparing a report reflecting their review of NUREG-1150 with respect to the adequacy of the methods, data, analysis and conclusions it set forth. The report which precedes reflects the results of this peer review

  19. Nuclear Regulatory Commission issuances: June 1995. Volume 41, Number 6

    International Nuclear Information System (INIS)

    1995-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decision on Petitions for Rulemaking (DPRM). This report contains four issuances by the CLI, 5 issuances by the LBP, and 1 issuance by the DD

  20. Nuclear Regulatory Commission issuances: June 1995. Volume 41, Number 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decision on Petitions for Rulemaking (DPRM). This report contains four issuances by the CLI, 5 issuances by the LBP, and 1 issuance by the DD.

  1. United States Nuclear Regulatory Commission staff practice and procedure digest. Commission, Appeal Board and Licensing Board decisions, July 1972-September 1985. Digest No. 4, Revision No. 1

    International Nuclear Information System (INIS)

    1986-04-01

    This Revision 1 of the fourth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to September 30, 1985 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 1 replaces earlier editions and supplements and includes appropriate changes reflecting the admendments to the Rules of Practice effective through September 20, 1985

  2. Management of National Nuclear Power Programs for assured safety

    Energy Technology Data Exchange (ETDEWEB)

    Connolly, T.J. (ed.)

    1985-01-01

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

  3. Management of National Nuclear Power Programs for assured safety

    International Nuclear Information System (INIS)

    Connolly, T.J.

    1985-01-01

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA)

  4. Safety standards and safety record of nuclear power plants

    International Nuclear Information System (INIS)

    Davis, A.B.

    1984-01-01

    This paper focuses on the use of standards and the measurement and enforcement of these standards to achieve safe operation of nuclear power plants. Since a discussion of the safety standards that the Nuclear Regulatory Commission (NRC) uses to regulate the nuclear power industry can be a rather tedious subject, this discussion will provide you with not only a description of what safety standards are, but some examples of their application, and various indicators that provide an overall perspective on safety. These remarks are confined to the safety standards adopted by the NRC. There are other agencies such as the Environmental Protection Agency, the Occupational Safety and Health Administration, and the state regulatory agencies which impact on a nuclear power plant. The NRC has regulatory authority for the commercial use of the nuclear materials and facilities which are defined in the Atomic Energy Act of 1954 to assure that the public health and safety and national security are protected

  5. Identifying Neurofibromin-Specific Regulatory Nodes for Therapeutic Targeting in NF1

    Science.gov (United States)

    2016-10-01

    Neurofibromin, Spred1, Spred2, neurofibromatosis, therapeutic targeting 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT 18. NUMBER OF PAGES 19a...PKC iota , NLK, CHK1, CHK2, RSK1, RSK2, RSK3, RSK4, ICK, PCTK1, CAMKK2, SRPK2, COT, DYRK2, GRK1, PKC mu, PKC nu, PKC theta, PKC zeta, IKK alpha, IKK

  6. United States Nuclear Regulatory Commission staff practice and procedure digest

    International Nuclear Information System (INIS)

    1991-02-01

    This Revision 9 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to September 30, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 9 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through September 30, 1990. This edition of the Digest was prepared by attorneys from Aspen Systems Corporation pursuant to Contract number 18-89-346. Persons using this Digest are placed on notice that it may not be used as an authoritative citation in support of any position before the Commission or any of its adjudicatory tribunals. Persons using this Digest are also placed on notice that it is intended for use only as an initial research tool, that it may, and likely does, contain errors, including errors in analysis and interpretation of decisions, and that the user should not rely on the Digest analyses and interpretations but must read, analyze and rely on the user's own analysis of the actual Commission, Appeal Board and Licensing Board decisions cited. Further, neither the United States, the Nuclear Regulatory Commission, Aspen Systems Corporation, nor any of their employees makes any expressed or implied warranty or assumes liability or responsibility for the accuracy, completeness or usefulness of any material presented in the Digest. The Digest is roughly structured in accordance with the chronological sequence of the nuclear facility licensing process as set forth in Appendix A to 10 CFR Part 2. Those decisions which did not fit into that structure are dealt with in a section on general matters. Where appropriate, particular decisions are indexed under more than one heading. (JF)

  7. Definition of user needs and “hot topics”, Deliverable 2.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Hagström, L. Thomson, R. Skogsmo, I. Houtenbos, M. Durso, C. Thomas, P. Elvik, R. & Wismans, J.

    2016-01-01

    Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policymakers and stakeholders to select and implement the most appropriate

  8. Indexes to Nuclear Regulatory Commission issuances, January-June 1984. Vol. 19, Index 2

    International Nuclear Information System (INIS)

    1984-11-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats: case name index, digests and headers, legal citations index, subject index, and facility index

  9. Indexes to Nuclear Regulatory Commission issuances, January--March 1994. Volume 39, Index 1

    International Nuclear Information System (INIS)

    1994-07-01

    Digests and indexes for issuances of the Commission, Atomic Safety and Licensing Board Panel, Administrative Law Judges, Directors' Decisions, and Denials of Petitions for Rulemaking are presented in this document. They are intended to serve as a guide to the issuances

  10. Preparation for commissioning of nuclear plant with reference to British Nuclear Fuels Plc fuel handling plant project

    International Nuclear Information System (INIS)

    Bamber, D.R.

    1987-01-01

    The new Fuel Handling Plant at British Nuclear Fuels Sellafield is part of a Pound 550M complex which provides facilities for the receipt, storage and mechanical preparation of both Magnox and A.G.R. fuel. The plant is very large and complex with considerable use of computer based process control systems, providing for physical and nuclear safety. The preparation of such plant for active commissioning necessitates a great many physical checks and technical evaluations in support of its safety case. This paper describes arrangements for plant commissioning checks, against the regulatory framework and explains the physical preparations necessary for their timely accomplishment. (author)

  11. Preparation for commissioning of nuclear plant with reference to British Nuclear Fuels Plc fuel handling plant project

    International Nuclear Information System (INIS)

    Bamber, D.

    1987-01-01

    The new Fuel Handing Plant at British Nuclear Fuels Sellafield is part of a Pound 550M complex which provides facilities for the receipt, storage and mechanical preparation of both magnox and A.G.R. fuel. The plant is very large and complex with considerable use of computer based process control systems, providing for physical and nuclear safety. The preparation of such plant for ''active'' commissioning necessitates a great many physical checks and technical evaluations in support of its safety case. This paper describes arrangements for plant commissioning checks, against the regulatory framework and explains the physical preparations necessary for their timely accomplishment. (author)

  12. Chilean Nuclear Energy Commission dosimetric information system

    International Nuclear Information System (INIS)

    Guerrero Vallejos, Patricia Andrea

    1997-01-01

    This thesis discusses the nuclear radiation that people who work with radioactive material is exposed to and its control by the Chilean Nuclear Energy Commission. A full analysis of the System is presented with information about the Commission and the Department of Nuclear and Radiological Safety which runs the System. Ana analysis of the System is presented in order to obtain requirements. Management flow diagrams, the processes involved and current problems experienced by the users are described. A design logic is modeled producing Data Flow Diagrams (DFD). based on this physical design, or, Model of Physical Data, is prepared including tables, attributes, types of data, primary and foreign keys. A description is presented of how the System is implemented, the tools that are used and how the testing phase is carried out. The Dosimetry System meets the criteria for a Software Engineering project, where the basic cycle was used as a working methodology. The System developed supports the dosimetric control of people exposed to radioactive material. (author)

  13. Thirteenth Semiannual Report of the Commission to the Congress, January 1953

    Energy Technology Data Exchange (ETDEWEB)

    Dean, Gordon

    1953-01-31

    The document represents the thirteenth semiannual Atomic Energy Commission (AEC) report to Congress. The report sums up the major activities and developments in the national atomic energy program covering the period July - December 1952. Part two focuses on the annual financial report, while part three covers public safety in continental weapons tests.

  14. Safety Training: Basic Safety and Access Courses

    CERN Multimedia

    Antonella Vignes

    2005-01-01

    Objective The purpose of the basic safety courses is to increase awareness for everyone working on the CERN site (CERN staff, associates, outside companies, students and apprentices) of the various existing on-site hazards, and how to recognize and avoid them. Safety course changes The current organization for basic safety courses is changing. There will be two main modifications: the organization of the courses and the implementation of a specific new training course for the LHC machine during the LHC tests and hardware commissioning phase. Organizational changes This concerns the existing basic safety training, currently called level1, level2 and level3. Under the new procedure, a video will be projected in registration building 55 and will run every day at 14.00 and 15.00 in English. The duration of the video will be 50 minutes. The course contents will be the same as the slides currently used, plus a video showing real situations. With this new organization, attendees will systematically follow the...

  15. Safety Training: basic safety and access courses

    CERN Multimedia

    2005-01-01

    Objective The purpose of the basic safety courses is to increase awareness for everyone working on the CERN site (CERN staff, associates, outside companies, students and apprentices) of the various hazards existing on site, and how to recognise and avoid them. Safety course changes The current organisation of basic safety courses is changing. There will be two main modifications: the organisation of the courses and the implementation of a specific new training course for the LHC machine during the LHC tests and hardware commissioning phase. Organisational changes This concerns the existing basic safety training, currently called level 1, level 2 and level 3. Under the new procedure, a video will be projected in registration building 55 and will run every day at 14.00 and 15.00 in English. The duration of the video will be 50 minutes. The course contents will be the same as the slides currently used, plus a video showing real situations. With this new organization, participants will systematically follow...

  16. UPSAT guidelines. 1996 edition. Reference document for IAEA Uranium Productions Safety Assessment Teams (UPSATs)

    International Nuclear Information System (INIS)

    1996-05-01

    The IAEA Uranium Production Safety Assessment Team (UPSAT) programme provides advice and assistance to Member States to enhance the safety and environmental performance of uranium production facilities during construction, commissioning and operation. Sound design and construction are prerequisite for the safe and environmentally responsible operation of uranium mines and mills. However, the safety of the facility depends ultimately on sound policies, procedures and practices; on the capability and reliability of the construction, commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. The UPSAT guidelines have been developed in the following areas: (1) management, organization and administration; (2) training and qualification; (3) operation (4) maintenance; (5) safety, fire protection, emergency planning, and preparedness; (6) radiation protection; (7) environmental monitoring programme; (8) construction management; (9) commissioning and decommissioning

  17. Nuclear Regulatory Commission issuances, June 1997. Volume 45, Number 6

    International Nuclear Information System (INIS)

    1997-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  18. 16 CFR 1115.5 - Reporting of failures to comply with a voluntary consumer product safety standard relied upon by...

    Science.gov (United States)

    2010-01-01

    ... voluntary consumer product safety standard relied upon by the Commission under section 9 of the CPSA. 1115.5 Section 1115.5 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SUBSTANTIAL PRODUCT HAZARD REPORTS General Interpretation § 1115.5 Reporting of failures to comply...

  19. Indexes to Nuclear Regulatory Commission issuances, January--June 1992

    International Nuclear Information System (INIS)

    1992-09-01

    Digests and indexes for insurances of the Commission (CLI), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM) are presented in this document. These information elements are displayed in one or more of five separate formats arranged as follows: Case name index; digests and headers; legal citations index; subject index; and facility index

  20. Some Main Results of Commissioning of the Dalat Research Reactor with Low Enriched Fuel

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Luong Ba Vien; Pham Van Lam; Le Vinh Vinh; Huynh Ton Nghiem

    2014-01-01

    After completion of design calculation of the Dalat Nuclear Research Reactor (DNRR) for conversion from high-enriched uranium fuel (HEU) to low-enriched uranium (LEU) fuel, the commissioning programme for DNRR with entire core loaded with LEU fuel was successfully carried out from 24 November 2011 to 13 January 2012. The experimental results obtained during the implementation of commissioning programme showed a good agreement with design calculations and affirmed that the DNRR with LEU core have met all safety and exploiting requirements. (author)

  1. Report of the ASSET (Assessment of Safety Significant Events Team) mission to the Cernavoda nuclear power plant in Romania 8-12 August 1994 Division of Nuclear Safety. Root cause analysis of a significant event that occurred during commissioning of unit 1

    International Nuclear Information System (INIS)

    1994-01-01

    The IAEA Assessment of Safety Significant Events Team (ASSET) report presents the results of the team's investigation of a significant event that occurred during commissioning of Unit 1 of Cernavoda nuclear power plant. The results, conclusions and suggestions presented herein reflect the views of the ASSET experts. They are provided for consideration by the responsible authorities in Romania. The ASSET team's views presented in this report are based on visits to the plant, on review of documentation made available by the operating organization and on discussions with utility personnel. The report is intended to enhance operational safety at Cernavoda by proposing improvements to the policy for the prevention of incidents at the plant. The report includes, as a usual practice, the official response of the Regulatory Body and Operating Organization to the ASSET recommendations. Figs

  2. Criticality Safety in the Handling of Fissile Material. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-05-15

    This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The guidance and recommendations are applicable to both regulatory bodies and operating organizations. The objectives of criticality safety are to prevent a self-sustained nuclear chain reaction and to minimize the consequences of this if it were to occur. The Safety Guide makes recommendations on how to ensure subcriticality in systems involving fissile materials during normal operation, anticipated operational occurrences, and, in the case of accident conditions, within design basis accidents, from initial design through commissioning, operation, and decommissioning and disposal.

  3. 10 CFR 34.42 - Radiation Safety Officer for industrial radiography.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Radiation Safety Officer for industrial radiography. 34.42 Section 34.42 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION... Radiation Safety Officer for industrial radiography. The RSO shall ensure that radiation safety activities...

  4. Indexes to Nuclear Regulatory Commission Issuances, January-March 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors Denials (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: Case name (owners of facility), Full text reference (volume and pagination), Issuance number, Issues raised by appellants, Legal citations (cases, regulations, and statutes), Name of facility, Docket number, Subject matter of issues and/or rulings, Type of hearing (for construction permit, operating license, etc.), and Type of issuance

  5. Access to information on nuclear safety in some Western countries. Additional expertise commissioned by the Public Debate National Commission

    International Nuclear Information System (INIS)

    Marignac, Y.; Schneider, Th.; Drouet, F.

    2006-01-01

    The authors report the analysis of procedures implemented in different western countries (Switzerland, Finland, United Kingdom, Germany, Sweden and United States) about the access to information on nuclear safety in the broad sense, i.e. as far as population protection against accidental or malevolent situations is concerned. They aimed at analysing how these procedures conciliate pluralism and comprehensive debate while preserving national and industrial interests as well as population's confidence. For each country, they present the different pubic bodies or agencies in charge of nuclear installations and nuclear safety, the existing legal framework related to information on government and nuclear activities, and give examples of information related to nuclear safety (incident or accident concerning nuclear power station or radioactive wastes). The comparative analysis considers different issues: access to information, and pluralist expertise

  6. Nuclear Regulatory Commission issuances, April 1995. Volume 41, Number 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This book contains issuances of the Nuclear Regulatory Commission and of the Atomic Safety and Licensing Boards, and an issuance of the Director`s decision. The issuances concern a petition filed by Dr. James E Bauer seeking interlocutory Commission review of the Atomic Safety and Licensing Board`s order imposing several restrictions on Dr. Bauer; a denial of an Interveners` Petition for Review addressing the application of Babcock and Wilcox for a renewal of its Special Nuclear Materials License; granting a motion for a protective order, by Sequoyah Fuel Corporation and General Atomics, limiting the use of the protected information to those individuals participating in the litigation and for the purposes of the litigation only; granting a Petitioner`s petition for leave to intervene and request for a hearing concerning Georgia Institute of Technology (Georgia Tech Research Reactor) renewal of a facility license; and a denial of a petition filed by Mr. Ted Dougherty requesting a shutdown of the San Onofre Nuclear Generating Station based on concerns regarding the vulnerability of the plant to earthquakes and defensibility of the plant to a terrorist threat.

  7. Nuclear Regulatory Commission issuances. Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1, 1994--December 31, 1994. Volume 40, Pages 1--387

    International Nuclear Information System (INIS)

    1994-01-01

    The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. This book covers the following: issuances of the NRC; issuances of the Atomic Safety and Licensing Boards; and issuances of Directors' decisions

  8. Nuclear Regulatory Commission issuances. Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1, 1994--December 31, 1994. Volume 40, Pages 1--387

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    The hardbound edition of the Nuclear Regulatory Commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. This book covers the following: issuances of the NRC; issuances of the Atomic Safety and Licensing Boards; and issuances of Directors` decisions.

  9. The European community and nuclear safety

    International Nuclear Information System (INIS)

    Brinkhorst, L.J.

    1992-01-01

    Full text: Since the inception of the EURATOM Treaty (1957) the use of nuclear power has made an enormous progress. The nuclear sector has become a very important component of the production of energy. Prisoner of its success further development of the use of nuclear energy is confronted with the challenge of ensuring its integration within the framework of modern environment protection concepts. The link between the radiation protection objective and the responsibilities of the State's Authorities in the control of the design and operation of nuclear industrial facilities has become evident. On the other hand, the evolution in the perception of the transfrontier character of the nuclear risk by the population and. the drive for the political integration of Europe have led the Community Member States to an increasing concentration between their nuclear policy-making organs and in particular between their Nuclear Safety Authorities It is quite natural that the Community institutions, the Council of Ministers and the Commission and more recently the European Parliament have become active hosts and catalysts of the concentration of the Member States on the nuclear safety objectives which are at the source of the protection of the population and of the environment. The joint efforts of the Member States and the Commission have led to a reinforcement of the process of harmonisation of safety requirements for nuclear installations at Community level. A parallel concentration effort has been done by Community Member States concerning the back-end of the fuel cycle, in particular radioactive waste management. The European Community meets the conditions to become a key driving force for nuclear safety progress beyond its region because of the advanced stage of nuclear safety in the Community which includes the flexibility and completeness of its fuel cycle and the long experience of Community institutions in the promotion of harmonisation of safety objectives, criteria and

  10. The UNO Aviation Monograph Series: Aviation Security: An Annotated Bibliography of Responses to the Gore Commission

    Science.gov (United States)

    Carrico, John S.; Schaaf, Michaela M.

    1998-01-01

    This monograph is a companion to UNOAI Monograph 96-2, "The Image of Airport Security: An Annotated Bibliography," compiled in June 1996. The White House Commission on Aviation Safety and Security, headed by Vice President Al Gore, was formed as a result of the TWA Flight 800 crash in August 1996. The Commission's final report included 31 recommendations addressed toward aviation security. The recommendations were cause for security issues to be revisited in the media and by the aviation industry. These developments necessitated the need for an updated bibliography to review the resulting literature. Many of the articles were written in response to the recommendations made by the Gore Commission. "Aviation Security: An Annotated Bibliography of Responses to the Gore Commission" is the result of this need.

  11. Nuclear Regulatory Commission Issuances. Volume 45, No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This report includes the issuances received in March 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 10 issuances were received: Louisiana Energy Services (2 issuances); Illinois Power Company and Soyland Power Cooperative; Ralph. L. Tetrick; University of Cincinnati; Consumers Power Company; Entergy Operations, Inc.; Georgia Power Company; Westinghouse Electric Corporation; and Wisconsin Electric Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

  12. Nuclear Regulatory Commission Issuances. Volume 45, No. 3

    International Nuclear Information System (INIS)

    1997-03-01

    This report includes the issuances received in March 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. 10 issuances were received: Louisiana Energy Services (2 issuances); Illinois Power Company and Soyland Power Cooperative; Ralph. L. Tetrick; University of Cincinnati; Consumers Power Company; Entergy Operations, Inc.; Georgia Power Company; Westinghouse Electric Corporation; and Wisconsin Electric Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  13. Twenty-first Semiannual Report of the Commission to the Congress, January 1957

    Energy Technology Data Exchange (ETDEWEB)

    Strauss, Lewis L.

    1957-01-31

    The document represents the twenty-first semiannual Atomic Energy Commission (AEC) report to Congress. The report sums up the major activities and developments in the national atomic energy program covering the period July - December 1956. A special part two of this semiannual report addresses specifically Radiation Safety in Atomic Energy Activities.

  14. Advanced Photon Source experimental beamline Safety Assessment Document: Addendum to the Advanced Photon Source Accelerator Systems Safety Assessment Document (APS-3.2.2.1.0)

    International Nuclear Information System (INIS)

    1995-01-01

    This Safety Assessment Document (SAD) addresses commissioning and operation of the experimental beamlines at the Advanced Photon Source (APS). Purpose of this document is to identify and describe the hazards associated with commissioning and operation of these beamlines and to document the measures taken to minimize these hazards and mitigate the hazard consequences. The potential hazards associated with the commissioning and operation of the APS facility have been identified and analyzed. Physical and administrative controls mitigate identified hazards. No hazard exists in this facility that has not been previously encountered and successfully mitigated in other accelerator and synchrotron radiation research facilities. This document is an updated version of the APS Preliminary Safety Analysis Report (PSAR). During the review of the PSAR in February 1990, the APS was determined to be a Low Hazard Facility. On June 14, 1993, the Acting Director of the Office of Energy Research endorsed the designation of the APS as a Low Hazard Facility, and this Safety Assessment Document supports that designation

  15. Indexes to Nuclear Regulatory Commission issuances, January-March 1984. Volume 19, Index 1

    International Nuclear Information System (INIS)

    1984-01-01

    Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements are displayed in one or more of five separate formats: Case Name Index, Digests and Headers, Legal Citations Index, Subject Index, and Facility Index

  16. 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

  17. Review of the Initial Phases of the LHC Power Converter Commissioning

    CERN Document Server

    Nisbet, D

    2008-01-01

    The LHC requires more than 1700 power converter systems that supply between 60A and 13kA of precisely regulated current to the superconducting magnets. For the first time at CERN these converters have been installed underground in close proximity to many other accelerator systems. In addition to the power converters themselves, many utilities such as air and water cooling, electrical power, communication networks and magnet safety systems needed to be installed and commissioned as a single system. Due to the complexity of installing and commissioning such a large infrastructure, with inevitable interaction between the different systems, a three phase test strategy was developed. The first phase comprised the manufacture, integration and reception tests of all converter sub-systems necessary for powering. The second phase covered the commissioning of all the power converters installed in their final environment with the utilities. The third phase will add the superconducting magnets and will not be covered by ...

  18. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest. Commission, Appeal Board and Licensing Board decisions, July 1972-December 1985. Digest No. 4, Revision No. 2

    International Nuclear Information System (INIS)

    1986-08-01

    This Revision 2 of the fourth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period July 1, 1972 to December 31, 1985, interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 2 replaces in part earlier editions and supplements and includes appropriate changes reflecting the amendment to the Rules of Practice effective December 31, 1985. Topics covered include prehearing and posthearing matters, herings, appeals, and general matters

  19. KKP 1. Report to inform the Reactor Safety Commission

    International Nuclear Information System (INIS)

    1987-01-01

    This report goes into details of the operation during its reporting period, giving the total activity in the primary events. Radiation exposure, activities, dose rates of persons, collective doses from activity and radioactive emission to water and waste air are given. Account is given of all modifications or extensions made on safety-related parts of the plant, on controls and regulation. (DG) [de

  20. Road safety in Poland : a contribution to the improvement of road safety in Poland in the framework of the GAMBIT project.

    NARCIS (Netherlands)

    Brouwer, M. Koornstra, M.J. Mulder, J.A.G. & Wegman, F.C.M.

    1995-01-01

    This report describes a SWOV Institute for Road Safety Research study. The study was commissioned: (1) to give a general opinion on the "GAMBIT" project contents; and (2) to express an expectation about the future traffic safety development in Poland. The SWOV contribution has been realized within