Perspectives on Containment Performance Improvement Based on the IPEs

Perspectives on Containment Performance Improvement Based on the IPEs PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 15

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Book Description
Generic Letter 88-20, {open_quotes}Individual Plant Examination (IPE) for Severe Accident Vulnerabilities - 10CFR 50.54(f), {close_quotes} was issued by the NRC on November 23, 1988. In addition to assessing the core damage frequency from severe accidents, licensees were requested to report the results of their analyses regarding containment performance. Supplements to the Generic Letter forwarded technical insights obtained by the NRC staff through its Containment Performance Improvement (CPI) program. At this time, most of the IPEs have been submitted by the licensees. In a follow-on effort to support regulatory activities, the NRC staff with assistance from Brookhaven National Laboratory, has initiated a program involving a global examination of the containment performance results documented in the IPEs. The objective is to identify insights of potential generic safety significance relative to plant design, operation and maintenance, as well as to assess response to the previously forwarded CPI insights. The containment performance results of the IPEs are being categorized for commonalities and differences for different reactor and containment types. Preliminary results show that not only differences in plant design but also the methods, data, boundary conditions, and assumptions used in the different IPEs have a major impact on the containment performance results obtained. This paper presents preliminary results regarding the differences in containment performance observed in the IPEs and discusses some of the underlying reasons for these differences.

Perspectives on Containment Performance Improvement Based on the IPEs

Perspectives on Containment Performance Improvement Based on the IPEs PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 15

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Book Description
Generic Letter 88-20, {open_quotes}Individual Plant Examination (IPE) for Severe Accident Vulnerabilities - 10CFR 50.54(f), {close_quotes} was issued by the NRC on November 23, 1988. In addition to assessing the core damage frequency from severe accidents, licensees were requested to report the results of their analyses regarding containment performance. Supplements to the Generic Letter forwarded technical insights obtained by the NRC staff through its Containment Performance Improvement (CPI) program. At this time, most of the IPEs have been submitted by the licensees. In a follow-on effort to support regulatory activities, the NRC staff with assistance from Brookhaven National Laboratory, has initiated a program involving a global examination of the containment performance results documented in the IPEs. The objective is to identify insights of potential generic safety significance relative to plant design, operation and maintenance, as well as to assess response to the previously forwarded CPI insights. The containment performance results of the IPEs are being categorized for commonalities and differences for different reactor and containment types. Preliminary results show that not only differences in plant design but also the methods, data, boundary conditions, and assumptions used in the different IPEs have a major impact on the containment performance results obtained. This paper presents preliminary results regarding the differences in containment performance observed in the IPEs and discusses some of the underlying reasons for these differences.

Containment Performance Perspectives Based on IPE Results

Containment Performance Perspectives Based on IPE Results PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 11

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Book Description
Perspectives on Containment Performance were obtained from the accident progression analyses, i.e. level 2 PRA analyses, found in the IPE submittals. Insights related to the containment failure modes, the releases associated with those failure modes, and the factors responsible for the types of containment failures and release sizes reported were gathered. The results summarized here are discussed in detail in volumes 1 and 2 of NUREG 1560. 3 refs., 4 figs.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 654

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Advances in Safety and Reliability

Advances in Safety and Reliability PDF Author: C. Guedes Soares
Publisher: Elsevier
ISBN: 0080552153
Category : Technology & Engineering
Languages : en
Pages : 791

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Book Description
These three volumes comprise the papers presented at the ESREL '97 International Conference on Safety and Reliability held in Lisbon, Portugal, 17-20 June 1997. The purpose of the annual ESREL conferences is to provide a forum for the presentation of technical and scientific papers covering both methods and applications of safety and reliability to a wide range of industrial sectors and technical disciplines and, in so doing, to enhance cross-fertilization between them. A broad view is taken of safety and reliability which includes probabilistically-based methods, or, more generally, methods that deal with the quantification of the uncertainty in the knowledge of the real world and with decision-making under this uncertainty. The areas covered include: design and product liability; availability, reliability and maintainability; assessment and management of risks to technical systems; health and the environment; and mathematical methods of reliability and statistical analysis of data. The organization of the book closely follows the sessions of the conference with each of the three volumes containing papers from two parallel sessions, comprising a total of 270 papers by authors from 35 countries.

Nuclear Safety

Nuclear Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 930

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Proceedings of the International Topical Meeting on Advanced Reactors Safety

Proceedings of the International Topical Meeting on Advanced Reactors Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 658

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News Releases

News Releases PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 468

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Comanche Peak Steam Electric Station Units 1-2, Operation

Comanche Peak Steam Electric Station Units 1-2, Operation PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 28

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Nuclear Regulatory Commission Issuances

Nuclear Regulatory Commission Issuances PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 918

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Proceedings of the International Topical Meeting on Safety of Operating Reactors, San Francisco, California, October 11-14, 1998

Proceedings of the International Topical Meeting on Safety of Operating Reactors, San Francisco, California, October 11-14, 1998 PDF Author:
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 560

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