ML20044D589: Difference between revisions
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 February 21, 2020 MEMORANDUM TO: Ho K. Nieh, Director Office of Nuclear Reactor Regulation FROM: | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 February 21, 2020 MEMORANDUM TO: Ho K. Nieh, Director Office of Nuclear Reactor Regulation FROM: | ||
Advisory Committee on Reactor Safeguards | Scott W. Moore, Executive Director /RA/ | ||
Advisory Committee on Reactor Safeguards | |||
==SUBJECT:== | ==SUBJECT:== | ||
ACRS REVIEW OF NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR CHAPTERS 1, 3, 4, 6, 9, 13, 14, 15, 16, 18, 19 AND 20 During the 670th meeting of the Advisory Committee on Reactor Safeguards, February 5-7, 2020, the Committee reviewed the staffs safety evaluation with no open items for Chapter 1, Introduction and General Description of the Plant, Chapter 3, Design of Structures, Systems and Components, Chapter 4, Reactor, Chapter 6, Engineered Safety Features, Chapter 9, Auxiliary Systems, Chapter 13, Conduct of Operations, Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, Chapter 15, Transient and Accident Analyses, Chapter 16, Technical Specifications, Chapter 18, Human Factors Engineering, Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation, and Chapter 20, Mitigation of Beyond-Design-Basis Events, of the NuScale design certification application. | ACRS REVIEW OF NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR CHAPTERS 1, 3, 4, 6, 9, 13, 14, 15, 16, 18, 19 AND 20 During the 670th meeting of the Advisory Committee on Reactor Safeguards, February 5-7, 2020, the Committee reviewed the staffs safety evaluation with no open items for Chapter 1, Introduction and General Description of the Plant, Chapter 3, Design of Structures, Systems and Components, Chapter 4, Reactor, Chapter 6, Engineered Safety Features, Chapter 9, Auxiliary Systems, Chapter 13, Conduct of Operations, Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, Chapter 15, Transient and Accident Analyses, Chapter 16, Technical Specifications, Chapter 18, Human Factors Engineering, Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation, and Chapter 20, Mitigation of Beyond-Design-Basis Events, of the NuScale design certification application. | ||
The Committee reviewed and voted to accept recommendations from individual members who were assigned as lead reviewers for each Chapter. The Committee decided that no further briefings by the staff beyond the scheduled focus area evaluations are needed to support the Committees review of Chapters 1, 3, 4, 6, 13, 14, 16, 18, and 19 of the NuScale design certification application. The Committee requests a briefing by the staff on selected topics from Chapters 9, 15, and 20 as described in the associated attachments. The Committee will inform the Commission of its findings on these matters relative to the requirements of 10 CFR 52.53 in a subsequent letter. | The Committee reviewed and voted to accept recommendations from individual members who were assigned as lead reviewers for each Chapter. The Committee decided that no further briefings by the staff beyond the scheduled focus area evaluations are needed to support the Committees review of Chapters 1, 3, 4, 6, 13, 14, 16, 18, and 19 of the NuScale design certification application. The Committee requests a briefing by the staff on selected topics from Chapters 9, 15, and 20 as described in the associated attachments. The Committee will inform the Commission of its findings on these matters relative to the requirements of 10 CFR 52.53 in a subsequent letter. | ||
This completes the Committee chapter lead reviews of the advanced safety evaluation report chapters in accordance with the Committees letter of September 25, 2019. The Committee is on track to finish its safety review by June 23, 2020. | This completes the Committee chapter lead reviews of the advanced safety evaluation report chapters in accordance with the Committees letter of September 25, 2019. The Committee is on track to finish its safety review by June 23, 2020. | ||
Attachments: | |||
Chapter lead recommendations for further ACRS review of the NuScale DCA Phase 4 Safety Evaluation with no open items for: | Chapter lead recommendations for further ACRS review of the NuScale DCA Phase 4 Safety Evaluation with no open items for: | ||
: 1. Chapter 1, Introduction and General Description of the Plant (ML20050D019) | : 1. Chapter 1, Introduction and General Description of the Plant (ML20050D019) | ||
| Line 37: | Line 40: | ||
: 10. Chapter 18, Human Factors Engineering (ML20050G994) | : 10. Chapter 18, Human Factors Engineering (ML20050G994) | ||
: 11. Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation (ML20049A046) | : 11. Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation (ML20049A046) | ||
: 12. Chapter 20, Mitigation of Beyond-Design-Basis Events (ML20049D685) | : 12. Chapter 20, Mitigation of Beyond-Design-Basis Events (ML20049D685) | ||
==References:== | ==References:== | ||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 1, Introduction and General Description of the Plant, December 9, 2019 (ML20013D437). | U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 1, Introduction and General Description of the Plant, December 9, 2019 (ML20013D437). | ||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 3, Design of Structures, Systems and Components, January 8, 2020 (ML19337A787). | U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 3, Design of Structures, Systems and Components, January 8, 2020 (ML19337A787). | ||
| Line 47: | Line 49: | ||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 9, Auxiliary Systems, December 10, 2019 (ML19170A126). | U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 9, Auxiliary Systems, December 10, 2019 (ML19170A126). | ||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 13.1-13.5, Conduct of Operations, October 17, 2019 (ML19165A286). | U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 13.1-13.5, Conduct of Operations, October 17, 2019 (ML19165A286). | ||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 13.6-13.7, Conduct of Operations, December 16, 2019 (ML19182A241). | U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 13.6-13.7, Conduct of Operations, December 16, 2019 (ML19182A241). | ||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, January 8, 2020 (ML19267A086). | |||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 15, Transient and Accident Analyses, January 28, 2020 (ML20028D595). | U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 15, Transient and Accident Analyses, January 28, 2020 (ML20028D595). | ||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 16, Technical Specifications, December 27, 2019 (ML19330E020). | U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 16, Technical Specifications, December 27, 2019 (ML19330E020). | ||
| Line 56: | Line 58: | ||
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 20, Mitigation of Beyond-Design-Basis Events, December 5, 2019 (ML19338B783). | U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 20, Mitigation of Beyond-Design-Basis Events, December 5, 2019 (ML19338B783). | ||
Advisory Committee on Reactor Safeguards, Proposed Focus Area Review Approach of the Advanced Safety Evaluation Report With No Open Items for the Design Certification Application of the NuScale Small Modular Reactor, September 25, 2019 (ML19269B682). | Advisory Committee on Reactor Safeguards, Proposed Focus Area Review Approach of the Advanced Safety Evaluation Report With No Open Items for the Design Certification Application of the NuScale Small Modular Reactor, September 25, 2019 (ML19269B682). | ||
cc: R. Taylor, NRR A. Bradford, NRR M. Dudek, NRR G. Cranston, NRR P. Chowdhury, NRR O. Tabatabai, NRR G. Tesfaye, NRR B. Bavol, NRR Marieliz Johnson, NRR R. Franovich, NRR | cc: R. Taylor, NRR A. Bradford, NRR M. Dudek, NRR G. Cranston, NRR P. Chowdhury, NRR O. Tabatabai, NRR G. Tesfaye, NRR B. Bavol, NRR Marieliz Johnson, NRR R. Franovich, NRR | ||
February 21, 2020 | |||
==SUBJECT:== | ==SUBJECT:== | ||
ACRS REVIEW OF NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR CHAPTERS 1, 3, 4, 6, 9, 13, 14, 15, 16, 18, 19 AND 20 Package No.: ML20044D595 Accession No: ML20044D589 | ACRS REVIEW OF NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR CHAPTERS 1, 3, 4, 6, 9, 13, 14, 15, 16, 18, 19 AND 20 Package No.: ML20044D595 Accession No: ML20044D589 Publicly Available Y Sensitive N Viewing Rights: | ||
DATE | NRC Users or ACRS Only or See Restricted distribution *via email OFFICE ACRS/TSB SUNSI Review ACRS/TSB ACRS NAME MSnodderly MSnodderly LBurkhart (MSnodderly for) | ||
SMoore DATE 2/20/2020 2/20/2020 2/20/2020 2/21/2020 OFFICIAL RECORD COPY}} | |||
Latest revision as of 13:28, 19 December 2024
| ML20044D589 | |
| Person / Time | |
|---|---|
| Issue date: | 02/21/2020 |
| From: | Scott Moore Advisory Committee on Reactor Safeguards |
| To: | Ho Nieh Office of Nuclear Reactor Regulation |
| Snodderly, M, ACRS | |
| Shared Package | |
| ML20044D595 | List: |
| References | |
| Download: ML20044D589 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 February 21, 2020 MEMORANDUM TO: Ho K. Nieh, Director Office of Nuclear Reactor Regulation FROM:
Scott W. Moore, Executive Director /RA/
Advisory Committee on Reactor Safeguards
SUBJECT:
ACRS REVIEW OF NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR CHAPTERS 1, 3, 4, 6, 9, 13, 14, 15, 16, 18, 19 AND 20 During the 670th meeting of the Advisory Committee on Reactor Safeguards, February 5-7, 2020, the Committee reviewed the staffs safety evaluation with no open items for Chapter 1, Introduction and General Description of the Plant, Chapter 3, Design of Structures, Systems and Components, Chapter 4, Reactor, Chapter 6, Engineered Safety Features, Chapter 9, Auxiliary Systems, Chapter 13, Conduct of Operations, Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, Chapter 15, Transient and Accident Analyses, Chapter 16, Technical Specifications, Chapter 18, Human Factors Engineering, Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation, and Chapter 20, Mitigation of Beyond-Design-Basis Events, of the NuScale design certification application.
The Committee reviewed and voted to accept recommendations from individual members who were assigned as lead reviewers for each Chapter. The Committee decided that no further briefings by the staff beyond the scheduled focus area evaluations are needed to support the Committees review of Chapters 1, 3, 4, 6, 13, 14, 16, 18, and 19 of the NuScale design certification application. The Committee requests a briefing by the staff on selected topics from Chapters 9, 15, and 20 as described in the associated attachments. The Committee will inform the Commission of its findings on these matters relative to the requirements of 10 CFR 52.53 in a subsequent letter.
This completes the Committee chapter lead reviews of the advanced safety evaluation report chapters in accordance with the Committees letter of September 25, 2019. The Committee is on track to finish its safety review by June 23, 2020.
Attachments:
Chapter lead recommendations for further ACRS review of the NuScale DCA Phase 4 Safety Evaluation with no open items for:
- 1. Chapter 1, Introduction and General Description of the Plant (ML20050D019)
- 2. Chapter 3, Design of Structures, Systems and Components (ML20054B758)
- 3. Chapter 4, Reactor (ML20049A007)
- 4. Chapter 6, Engineered Safety Features (ML20044D549)
- 5. Chapter 9, Auxiliary Systems (ML20044D648)
- 6. Chapter 13, Conduct of Operations (ML20050G994)
- 7. Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria (ML20054B888)
- 8. Chapter 15, Transient and Accident Analyses (ML20044D532)
- 9. Chapter 16, Technical Specifications (ML20054B988)
- 10. Chapter 18, Human Factors Engineering (ML20050G994)
- 11. Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation (ML20049A046)
- 12. Chapter 20, Mitigation of Beyond-Design-Basis Events (ML20049D685)
References:
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 1, Introduction and General Description of the Plant, December 9, 2019 (ML20013D437).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 3, Design of Structures, Systems and Components, January 8, 2020 (ML19337A787).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 4, Reactor, January 16, 2020 (ML19336B593).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 6, Engineered Safety Features, December 9, 2019 (ML19343A027).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 9, Auxiliary Systems, December 10, 2019 (ML19170A126).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 13.1-13.5, Conduct of Operations, October 17, 2019 (ML19165A286).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 13.6-13.7, Conduct of Operations, December 16, 2019 (ML19182A241).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria, January 8, 2020 (ML19267A086).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 15, Transient and Accident Analyses, January 28, 2020 (ML20028D595).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 16, Technical Specifications, December 27, 2019 (ML19330E020).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 18, Human Factors Engineering, December 16, 2019 (ML19340A065).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation, December 12, 2019 (ML19143A106).
U. S. Nuclear Regulatory Commission, NuScale Power, LLC, Design Certification Application - Safety Evaluation With No Open Items for Chapter 20, Mitigation of Beyond-Design-Basis Events, December 5, 2019 (ML19338B783).
Advisory Committee on Reactor Safeguards, Proposed Focus Area Review Approach of the Advanced Safety Evaluation Report With No Open Items for the Design Certification Application of the NuScale Small Modular Reactor, September 25, 2019 (ML19269B682).
cc: R. Taylor, NRR A. Bradford, NRR M. Dudek, NRR G. Cranston, NRR P. Chowdhury, NRR O. Tabatabai, NRR G. Tesfaye, NRR B. Bavol, NRR Marieliz Johnson, NRR R. Franovich, NRR
February 21, 2020
SUBJECT:
ACRS REVIEW OF NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR CHAPTERS 1, 3, 4, 6, 9, 13, 14, 15, 16, 18, 19 AND 20 Package No.: ML20044D595 Accession No: ML20044D589 Publicly Available Y Sensitive N Viewing Rights:
NRC Users or ACRS Only or See Restricted distribution *via email OFFICE ACRS/TSB SUNSI Review ACRS/TSB ACRS NAME MSnodderly MSnodderly LBurkhart (MSnodderly for)
SMoore DATE 2/20/2020 2/20/2020 2/20/2020 2/21/2020 OFFICIAL RECORD COPY