|
|---|
Category:Memoranda
MONTHYEARML24004A0472024-01-31031 January 2024
U.S. Nuclear Regulatory Commission Summary of the November 16, 2023, Observation Public Meeting to Discuss Nuscale’S Us600 Exemption Request
ML20274A1082020-09-30030 September 2020
Summary of September 16, 2020 Public Meeting with NuScale Power, LLC to Discuss Operator Licensing Topics
ML20199M1492020-08-19019 August 2020
Memo Transmitting Summary of the July 15, 2020 Pre-Submittal Meeting with NuScale, LLC, Regarding Its Plans to Submit a Topical Report Using Automated Test System
ML20219A4112020-08-10010 August 2020
Summary of the May 28, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss NuScales Standard Design Application Control Room Staffing Topical Report-0520-69851
ML20210M0772020-07-28028 July 2020
Memo - Category 1 Public Meeting - Audit Exit NuScale Emergency Core Cooling System Boron Redistribution Issue and Applicable Design Changes
ML20160A2472020-07-28028 July 2020
Audit Summary Memo NuScale ECCS Boron Redistribution Issue
ML20176A1582020-07-10010 July 2020
Audit Summary 2019 Memo NuScale Chapter 15
ML20108F5082020-05-27027 May 2020
Summary of April 15 2020 Public Meeting on NuScale EPZ Sizing Methodology TR
ML20140A1892020-05-19019 May 2020
Public Meeting Summary May 14, 2020, NuScale Boron Redistribution Issue
ML20114E2162020-05-0404 May 2020
Summary of the April 1, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application
ML20114E0192020-04-27027 April 2020
Summary of the April 15, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application
ML20114E0392020-04-23023 April 2020
Meeting Summary for the April 21, 2020, Public Meeting to Discuss NuScale SDA Significance Review Process
ML20097C2292020-04-0707 April 2020
Summary of the March 9, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution
ML20072M7982020-03-19019 March 2020
Meeting Summary for the January 30, 2020, Public Meeting to Discuss NuScale SDA Regulatory Engagement Plan
ML20076D8852020-03-16016 March 2020
Summary Report for the January 2019 Regulatory Audit of NuScale Chapter 20
ML20072K5232020-03-11011 March 2020
Summary of the September 4, 2019, Public Teleconference with NuScale Power, Llc., Regarding Responses to Staff Requests for Additional Information (RAI) (52-048)
ML20059N6872020-03-0202 March 2020
Regulatory Audit Plan for NuScale DCA Chapters 6, 7, and 15
ML20054A0602020-02-28028 February 2020
Regulatory Audit Report for NuScale DCA Inadvertent Actuation Block (Iab) Operating Range Change
ML20049H1872020-02-18018 February 2020
Memo to ACRS Rea NON-LOCA TR SE
ML20049H5442020-02-18018 February 2020
Letter to NuScale NON-LOCA TR SER
ML20044E3522020-02-18018 February 2020
Memo to ACRS Rod Ejection Accident Methodology SER
ML20042E0242020-02-12012 February 2020
LOCA Topical Report Phase IV Audit Report - Public
ML20042E0392020-02-12012 February 2020
NON-LOCA Topical Report Phases 3 and 4 Audit Report
ML20010D1312020-01-16016 January 2020
Audit Summary Memo NuScale LOCA TR
ML19340A9712020-01-13013 January 2020
U.S. Nuclear Regulatory Commission Report of the Regulatory Follow-Up Audit Performed Between May 1, 2019, Through September 19, 2019, Regarding the Nuscale Stress and Fatigue Analysis of Major Design Components (Public)
ML19345E9362020-01-13013 January 2020
Summary of the December 9, 2019, Public Teleconference Meeting on Incorporation by Reference
ML19343C7562020-01-0808 January 2020
Generator Tube - Siet Audit Report (Public)
ML20006G4202020-01-0808 January 2020
ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapters 2, 8 and 12
ML19340A0152019-12-20020 December 2019
U.S. Nuclear Regulatory Commission'S Report of the Regulatory Audit Performed Between March 4, 2019, Through September 10, 2019, for Nuscale Power, LLC, Regarding Nuscale'S Power Module Leakage Flow Instability Analysis - Public Memo
ML20006G5752019-12-20020 December 2019
Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 8, Electric Power
ML19331A3972019-12-20020 December 2019
U.S. Nuclear Regulatory Commission Report of the Regulatory follow-up Audit Performed Between 8/22/19 - 9/24/19, Regarding NuScale Power, Seismic Category I Equipment and Environment Qualification of Electrical Equipment Specifications
ML20006G4892019-12-19019 December 2019
Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 2, Site Characteristics and Site Parameters
ML20006G7002019-12-19019 December 2019
Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 12, Radiation Protection
ML19340A0192019-12-19019 December 2019
U.S. Nuclear Regulatory Commission Report - Regulatory Audit Between 03/20/19 - 10/09/19 - Emergency Core Cooling System Valve Design Demonstration Testing and Follow-Up Items NuScale Power, LLC, Standard Plant Design Certification
ML19143A1042019-12-12012 December 2019
DCA - Safety Evaluation with No Open Items for Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors - Memo
ML19168A1382019-12-12012 December 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 3, Design of Structures, Systems, Components and Equipment
ML19169A2992019-12-11011 December 2019
Memo to ACRS Transmitting SER - Chapter 15
ML19169A1322019-12-10010 December 2019
Memo to ACRS Transmitting SER
ML19165A2792019-12-0909 December 2019
Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 1, Introduction and General Discussion
ML19168A1682019-12-0909 December 2019
Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 4, Reactor - Memo
ML19168A2002019-12-0909 December 2019
Memo to ACRS Transmitting SER - Chapter 6
ML19169A3142019-12-0404 December 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 16, Technical Specifications - Memo
ML19169A3322019-12-0404 December 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 20, Mitigation of Beyond-Design-Basis Events - Memo
ML19319C2322019-11-26026 November 2019
U.S. Nuclear Regulatory Commission Summary Report of Regulatory follow-up Audit of Design Documents for NuScale Containment Isolation Valves and Reactor Safety Valves
ML19169A2952019-11-26026 November 2019
Memo to ACRS Transmitting SER
ML19270G6762019-11-22022 November 2019
Audit Summary for the Regulatory Audit of NuScale Power, LLC, Final Safety Analysis Report Chapter 15, Transient and Accident Analyses, (Memo)
ML19169A1192019-11-22022 November 2019
Memo to ACRS Transmitting Phase 4 SER for Chapter 8
ML19169A2912019-11-22022 November 2019
Memo to ACRS Transmitting SER
ML19162A2732019-11-15015 November 2019
LLC, Design Certification Application Memo - Safety Evaluation with No Open Items for Chapter 18, Human Factors Engineering
ML19162A0962019-11-13013 November 2019
Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 2, Site Characteristics and Site Parameters
2024-01-31
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 December 19, 2019 MEMORANDUM TO: Peter Riccardella, Chairman Advisory Committee on Reactor Safeguards FROM: David Petti, Member /RA/
NuScale Subcommittee Advisory Committee on Reactor Safeguards
SUBJECT:
PROPOSED RECOMMENDATION FOR ACRS REVIEW OF NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR CHAPTER 12, RADIATION PROTECTION In response to the Committees request, I have reviewed the NRC staffs safety evaluation report (SER) with no open items for Chapter 12, Radiation Protection, dated November 15, 2019 (ML19318E303). This memo documents my recommended course of action concerning further review of this chapter of the design certification application (DCA) and the staffs associated safety evaluation.
SER Phase 4 Summary Chapter 12 of the SER documents the staffs review of Revision 2 of Chapter 12, Radiation Protection, of the NuScale DCA , Part 2, Final Safety Analysis Report (ML18310A326).
Chapter 12 discusses four aspects of radiation protection: 1) assuring that occupational radiation exposures are as low as reasonably achievable; 2) determining projected radiation sources during normal operations, anticipated operational occurrences, and accident conditions; 3) establishing radiation protection design features (shielding, ventilation, radioactivity monitoring systems, and contamination controls); and 4) providing the basis for the dose assessment for normal operation and post-accident sampling and analysis. Operational considerations on the implementation of a radiation protection program are also included but outside the scope of the DCA review and will be addressed by a combined license (COL) applicant.
The Phase 2 SER for this chapter (ML19015A137) identified open items which NuScale has addressed through information submitted on the docket. All the open items have been satisfactorily closed. In addition, the Phase 2 SER for this chapter identified confirmatory items with proposed changes submitted on the docket, which the staff found acceptable.
D. Petti In several cases, NuScale stated that they did not intend to revise Tier 1 Chapter 4 of the application to include design interface items or to complete the design. Therefore, the NRC staff has recommended that the Commission include language in the proposed rule clarifying that the NRC is not making a finding on the adequacy of those parts of the design to achieve the safety function of limiting offsite and onsite dose. Specifically, these items are:
- Radiation shielding for the Nuclear Power Module (NPM) to Reactor Building Steam Gallery penetrations; and
- Design features and analysis for leakage of systems outside of containment (containment evacuation system, containment flood and drain system, and post-accident sampling system) used for combustible gas monitoring, that may have highly radioactive fluid following an accident.
If adopted by the Commission, these items will need to be addressed by a future combined license (COL) applicant.
Applicable Concerns from ACRS Phase 3 Letter Report Our letter noted there are potentially risk-significant items in the NuScale design that are not yet fully developed and recommended that requirements be included in the DCA to ensure that the licensed NuScale plant will perform as credited. We observed that there are numerous COL Items identified in Chapter 12 and we stated that it is important that NuScale provide sufficient information regarding how such requirements should be met.
We observed that this is particularly important when the DCA credits such design features.
Our letter also identified several issues, such as post-shutdown crud burst; resin transfer piping sizes; RCS flow rate changes; radiation fields around the top of the containment vessel; source term and related information during degasifying reactors for shutdown; and ultimate heat sink pool temperature assumptions for airborne activity source terms.
Many of these issues were addressed by the applicant in subsequent interactions with the staff. As noted above, the staff did not make a finding about the adequacy of the design on several items for which additional information was not provided.
We pointed out that the source term analyses used in this Chapter depended on the NuScale source term methodology. This methodology was documented in Topical Report, TR-0915-17565, Revision 3, Accident Source Term Methodology, and reviewed by the ACRS in our source term focus area meeting.
Staff Response to ACRS Letter Report The staff response to our initial conclusion indicated that they expected further enhancement of the DCA descriptions in risk-significant areas, consistent with the objectives of the design certification process. As noted above, the staff did not make a finding about the adequacy of the plant in areas where additional design information was not provided.
D. Petti Open Items from Phase 3 Requiring Further ACRS Review There were numerous open items that were closed in Phase 4. I have reviewed how these items were addressed in the staff Phase 4 SER, and I do not recommend further ACRS review.
Recommendation Many of the Chapter 12 issues that we identified in our Phase 3 letter report were addressed by the applicant in subsequent interactions with the staff. In cases where the applicant did not provide additional design information, the staff did not make a finding about the adequacy of the plant and proposed that these items be identified by the Commission in the final rule on the NuScale design. These design features are addressed in our source term focus area review.
As lead reviewer for NuScale DCA Chapter 12, I recommend that the Committee not perform any additional Phase 5 review of this chapter.
D. Petti December 19, 2019
SUBJECT:
PROPOSED RECOMMENDATION FOR ACRS REVIEW OF NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH NO OPEN ITEMS FOR CHAPTER 12, RADIATION PROTECTION Package No.: ML20006G700 Accession No: ML20006G325 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 DPetti (LBurkhart for)
DATE 12/19/2019 12/19/2019 12/19/2019 12/19/2019 OFFICIAL RECORD COPY