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Category:Legal-Affidavit
[Table view] Category:Letter
MONTHYEARML24038A0322024-02-0707 February 2024 (Vcsns), Unit 1, 10 CFR 21 Report - Emergency Diesel Generator Flash Contactor Relay IR 05000395/20230042024-01-31031 January 2024 Integrated Inspection Report 05000395/2023004 ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping IR 05000395/20240112024-01-17017 January 2024 Notification of VC Summer Station Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000395/2024011 ML23361A1042023-12-21021 December 2023 Inservice Testing Program for Pumps and Valves Fifth Interval Update and Associated Relief and Alternative Requests IR 05000395/20230912023-12-21021 December 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letternrc Inspection Report 05000395/2023091 ML23354A1802023-12-20020 December 2023 301 Examination Report with Cover Letter ML23347A0492023-12-12012 December 2023 Technical Specification Bases Changes Updated Through November 2023 ML23334A2462023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23334A2372023-11-30030 November 2023 (Vvsns), Unit 1 - Annual Commitment Change Summary Report ML23332A1942023-11-28028 November 2023 (Vcsns), Unit 1, Correction of Typographical Error in License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23317A2242023-11-0909 November 2023 (Vcsns), Unit 1 - License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23289A1172023-11-0303 November 2023 Tribal Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1152023-11-0303 November 2023 Ltr to R. Nelson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1162023-11-0303 November 2023 Ltr to W. Emerson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA IR 05000395/20234032023-11-0101 November 2023 Material Control and Accounting Program Inspection Report 05000395/2023403 Cover IR 05000395/20230032023-11-0101 November 2023 Integrated Inspection Report 05000395/2023003 ML23284A1792023-10-16016 October 2023 Subsequent License Renewal Application Online Reference Portal ML23275A0142023-10-11011 October 2023 SLRA - Acceptance and Opportunity for Hearing - Letter ML23284A1662023-10-10010 October 2023 (Vcsns), Unit 1 - Request for Regulatory Conference; (EA-23-093) IR 05000395/20230902023-10-0404 October 2023 NRC Inspection Report 05000395/2023090 and Preliminary Yellow Finding and Apparent Violation IR 05000395/20230112023-09-27027 September 2023 Focused Engineering Inspection Report 05000395/2023011 ML23250A3112023-09-20020 September 2023 Request to Revise Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23235A0432023-09-0505 September 2023 Receipt and Availability of the Subsequent License Renewal Application IR 05000395/20234012023-08-30030 August 2023 Security Baseline Inspection Report 05000395/2023401 ML23242A1192023-08-29029 August 2023 (Vcsns), Unit 1 - Inservice Inspection (ISI) Owner'S Activity Report (OAR) for Refueling Outage 27 ML23243B0362023-08-25025 August 2023 Request for FEMA Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20230052023-08-23023 August 2023 Updated Inspection Plan for Virgil C. Summer Nuclear Station (Report 05000395 2023005) ML23233A1752023-08-17017 August 2023 Application for Subsequent Renewed Operating License IR 05000395/20230022023-08-14014 August 2023 Integrated Inspection Report - Integrated Inspection Report 05000395/2023002 and Apparent Violation IR 05000395/20230102023-08-12012 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000395/2023010 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000395/20234412023-07-17017 July 2023 95001 Supplemental Inspection Report 05000395/2023441 and Follow Up Assessment Letter ML23190A0012023-07-0909 July 2023 Special Report 2023-003 Inoperable Radiation Monitoring Instrumentation Channel ML23187A5092023-07-0606 July 2023 Request for Federal Emergency Management Agency Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23173A1052023-06-22022 June 2023 Special Report 2023-002 Inoperable Loose-Part Monitoring System Channel ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23159A2332023-06-0808 June 2023 License Amendment Request - Emergency Response Organization Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes ML23156A3092023-06-0505 June 2023 Requalification Program Inspection Virgil C. Summer Nuclear Station Unit 1 - 05000395/2023003 2024-02-07
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML22353A5462022-12-19019 December 2022 (Vcsns), Unit 1 - Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request ML22300A2202022-10-27027 October 2022 (VCSNS) Unit 1, Alternative Request Rr-4-26 Application for Alternative Request - Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval (Volumetric Examination) RAI ML22020A2262022-01-20020 January 2022 Response to Request for Additional Information to License Amendment Request LAR-20-203 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency ML21180A4052021-06-29029 June 2021 (Vcsns), Unit 1 - Supplement to Request for Additional Information Regarding RF-25 Stem Generator Tube Inspection Report ML21168A2612021-06-17017 June 2021 (Vcsns), Unit 1 - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors - Final Supplemental Response ML21154A1802021-06-0303 June 2021 Response to NRC Request for Additional Information Regarding RGF-25 Steam Generator Tube Inspection Report ML21007A3232021-01-0707 January 2021 License Amendment Request LAR-20-142 Request for Technical Specification Change Technical Specification 3.6.4, Containment Isolation Valves Response to Request for Additional Information (RAI) ML21007A3402021-01-0707 January 2021 (Vcsns), Unit 1 - License Amendment Request LAR-20-176 Update of Analytical Method to the Core Operating Limits Report with the Full Spectrum Loss of Coolant Accident Approach - Response to Request for Additional Info ML20349A3262020-12-14014 December 2020 (Vcsns), Unit 1 - Response to NRC Request for Additional Information Regarding RF-24 Steam Generator Tube Inspection Report ML19282E2612019-10-0909 October 2019 Response to Follow-Up Question to PRA RAI 03, License Amendment Request - LAR-16-01490 NFPA 805 Program Revisions ML19224B1152019-08-12012 August 2019 Response to NRC Follow-Up Question PRA RAI 03, License Amendment Request - LAR-16-01490 NFPA 805 Program Revisions ML19119A3652019-04-29029 April 2019 (Vcsns), Unit 1 - License Amendment Request - LAR-16-01490, NFPA 805 Program Revisions: Response to Request for Additional Information ML19071A3572019-03-11011 March 2019 Request for License Amendment to Virgil C. Summer Nuclear Station Technical Specification 3.8.2., D.C. Sources - Operating, Surveillance Requirements 4.8.2.1.b.2 and 4.8.2.1.c.3 - Request for Additional Information RC-18-0116, (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information2018-09-11011 September 2018 (Vcsns), Unit 1 - Request for a One-Time Extension to the Surveillance Frequency 4.4.4.6 of the Core Exit Temperature Instrumentation - Response to Request for Additional Information RC-18-0100, (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information2018-08-22022 August 2018 (Vcsns), Unit 1 - Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit: Response to Request for Additional Information RC-18-0090, (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request...2018-07-12012 July 2018 (Vcsns), Unit 1 - Relief Request RR-4-16, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Response to Request... RC-18-0084, Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Requ2018-07-0303 July 2018 Virgil C Summer Nuclear Station (Vcsns), Unit 1 - Relief Request RR-4-15, Request for Alternative to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Laws in Moderate Energy Class 2 or 3 Piping Response to Reques RC-18-0046, License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information2018-04-19019 April 2018 License Amendment Request LAR-14-01541 Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change Request for Additional Information RC-18-0036, (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information2018-04-0202 April 2018 (Vcsns), Unit 1 - Relief Request RR-4-13, Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds - Response to Request for Additional Information RC-17-0134, Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 12017-09-27027 September 2017 Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 1 RC-17-0093, License Amendment Request - LAR-15-01424 Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times, Response To.2017-07-0606 July 2017 License Amendment Request - LAR-15-01424 Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times, Response To. RC-17-0088, Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times - Response to Request for Additional Information2017-06-22022 June 2017 Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times - Response to Request for Additional Information RC-17-0032, Spent Fuel Evaluation Supplemental Report, Response to NRC for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2017-03-30030 March 2017 Spent Fuel Evaluation Supplemental Report, Response to NRC for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident ML17087A1512017-03-28028 March 2017 Response to Request for Additional Information on VC Summer Sfpli RC-17-0019, Response to Request for Additional Information Regarding License Amendment Request LAR-15-01424, Implementation of WCAP-15376-P-A, Revision 12017-02-0606 February 2017 Response to Request for Additional Information Regarding License Amendment Request LAR-15-01424, Implementation of WCAP-15376-P-A, Revision 1 RC-16-0147, VC Summer Nuclear Station, Unit 1, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Pursuant to Title 10 9f the Code of Federal Regulations 05.54(f)2016-11-0303 November 2016 VC Summer Nuclear Station, Unit 1, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools Pursuant to Title 10 9f the Code of Federal Regulations 05.54(f) ML16235A2422016-08-18018 August 2016 Response to Request for Information for Triennial Fire Protection Baseline Inspection RC-16-0091, Response to Request for Additional Information on Relief Request RR-III-12 Proposed Alternative Inspection Requirements for Piping Welds2016-06-0202 June 2016 Response to Request for Additional Information on Relief Request RR-III-12 Proposed Alternative Inspection Requirements for Piping Welds RC-16-0077, Relief Request RR-III-12, Proposed Alternative Inspection Requirements for Piping Welds - Response to Request for Additional Information2016-05-0606 May 2016 Relief Request RR-III-12, Proposed Alternative Inspection Requirements for Piping Welds - Response to Request for Additional Information RC-16-0046, Response to Request for Additional Information on Relief Request RR-III-2, Proposed Alternative Inspection Requirements for Piping Welds2016-03-18018 March 2016 Response to Request for Additional Information on Relief Request RR-III-2, Proposed Alternative Inspection Requirements for Piping Welds RC-16-0036, License Amendment Request - LAR-15-01424 - Implementation of WCAP-15376-P-A, Revision 1, Response to Request for Supplemental Information2016-03-0707 March 2016 License Amendment Request - LAR-15-01424 - Implementation of WCAP-15376-P-A, Revision 1, Response to Request for Supplemental Information RC-16-0031, License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Supplement Response2016-03-0404 March 2016 License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Supplement Response RC-16-0039, Exigent License Amendment Request - LAR (16-00848), Technical Specification Change Request for Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B - Response to Request for Additional..2016-03-0303 March 2016 Exigent License Amendment Request - LAR (16-00848), Technical Specification Change Request for Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B - Response to Request for Additional.. RC-16-0001, V.C. Summer, Report of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information2016-01-22022 January 2016 V.C. Summer, Report of Full Compliance with March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information RC-16-0006, Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis2016-01-14014 January 2016 Response to Request for Additional Information to License Amendment Request - LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis RC-15-0186, Response to Request for Information (NRC Inspection Report No. 05000395/2015404)2015-11-11011 November 2015 Response to Request for Information (NRC Inspection Report No. 05000395/2015404) IR 05000395/20154042015-11-11011 November 2015 V.C. Summer, Unit 1 - Response to Request for Information (NRC Inspection Report No. 05000395/2015404) RC-15-0160, Response to Request for Information (NRC Inspection Report No. 05000395/2015404)2015-09-25025 September 2015 Response to Request for Information (NRC Inspection Report No. 05000395/2015404) ML15310A0762015-09-21021 September 2015 Response to Request for Information to Support the Cyber Security Inspection RC-15-0142, License Amendment Request, LAR 12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information2015-09-10010 September 2015 License Amendment Request, LAR 12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis, Response to Request for Additional Information RC-15-0116, Response to NRC Request for Information Baseline Radiation Safety Inspection2015-07-13013 July 2015 Response to NRC Request for Information Baseline Radiation Safety Inspection 2022-12-19
[Table view] |
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PROPRIETARY INFORMATION-WITHHOLD UNDER 10 CFR 2.390 Dominion Energy South Carolina, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Dominion Energy.com Energy January 7, 2021 Attn: Document Control Desk Serial No.: 20-431 U. S. Nuclear Regulatory Commission NRAMG: RO Washington, DC 20555-0001 Docket No.: 50-395 License No.: NPF-12 DOMINION ENERGY SOUTH CAROLINA, INC. {DESC)
VIRGIL C. SUMMER NUCLEAR STATION {VCSNS) UNIT 1 LICENSE AMENDMENT REQUEST LAR-20-176 "UPDATE OF ANALYTICAL METHOD TO THE CORE OPERATING LIMITS REPORT WITH THE FULL SPECTRUM LOSS OF COOLANT ACCIDENT APPROACH" RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION {RAI)
By letter dated June 4, 2020 (Agencywide Documents Access and Management System Package Accession No. ML20156A303), Dominion Energy South Carolina, Inc. (DESC),
submitted a license amendment request to revise Technical Specifications (TS) Section 6.9.1.11, "Core Operating Limits Report," for Virgil C. Summer Nuclear Station (VCSNS),
Unit 1. VCSNS is proposing to replace currently approved methods with the full spectrum loss of coolant accident analysis (FSLOCA) approach.
In an email dated December 7, 2020 from Mr. Vaughn Thomas, the VCSNS NRC Project Manager, to Mr. Yan Gao of Dominion Energy, the Nuclear Regulatory Commission (NRC) staff requested additional information to facilitate their review of the subject LAR.
The NRC's request for additional information (RAI) and DESC's responses are provided in the Enclosures to this letter. contains information proprietary to Westinghouse Electric Company, LLC
("Westinghouse"), and is supported by an Affidavit (Enclosure 3) signed by Westinghouse, the owner of the information. The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the NRC's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the NRC's regulations.
Correspondence with respect to the copyright or proprietary aspects of the information provided in the enclosures to this letter or the supporting Westinghouse Affidavit should reference CAW-20-5122 (Enclosure 3) and should be addressed to Zachary S. Harper, Manager, Licensing Engineering, Westinghouse Electric Company, 1000 Westinghouse Drive, Suite 165, Cranberry Township, Pennsylvania 16066. The non-proprietary version of the RAI responses is provided in Enclosure 2.
Enclosure 1 contains information that is being withheld from public disclosure under 1 O CFR 2.390. U pon se paration from Enclosure 1, this pga e is decontrolled.
Serial No.20-431 Docket No. 50-395 Page 2 of 3 Should you have any questions, please contact Mr. Yan Gao at (804) 273-2768.
Respectfully, Mark D. Sartain Vice President - Nuclear Engineering & Fleet Support COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mr. Mark D. Sartain, who is Vice President - Nuclear Engineering and Fleet Support, of Dominion Energy South Carolina, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 7+h. day of J:iuav-1 ,2021.
My Commission Expires: 1-i.! 31/J.if .
CRAIG D SLY Notary Public Notary Public Commonwealth of Virginia Reg.# 7518653 My Commission Expires December 31, 2 one
Enclosure:
- Response to NRC Request for Additional Information (Proprietary) : Response to NRC Request for Additional Information (Non-Proprietary) : Westinghouse Affidavit for Withholding Proprietary Information
Serial No.20-431 Docket No. 50-395 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 Mr. Vaughn Thomas NRC Project Manager U.S. Nuclear Regulatory Commission Mail Stop 04 F-12 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector V. C. Summer Nuclear Station Ms. Anuradha Nair-Gimmi Bureau of Environmental Health Services South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Mr. G. J. Lindamood Santee Cooper - Nuclear Coordinator V. C. Summer Nuclear Station
Serial No.20-431 Docket No. 50-395 Enclosure 2 Response to NRC Request for Additional Information (Non-Proprietary)
Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)
Serial No.20-431 Docket No. 50-395 Enclosure 2 - RAI Response: Page 1 of 4 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION UPDATE OF ANALYTICAL METHOD TO THE CORE OPERATING LIMITS REPORT WITH THE FULL SPECTRUM LOSS OF COOLANT ACCIDENT APPROACH DOMINION ENERGY SOUTH CAROLINA, INC. (DESC)
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 1.0 NRC REQUEST FOR ADDITIONAL INFORMATION (RAI) [2.41 Regulatory Basis The regulatory bases for the following LOCA related requests for additional information (RAls) are the requirements contained in 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," insofar as they establish the requirements and acceptance criteria for emergency core cooling system (ECCS) design, and for the evaluation models (EMs) used to evaluate ECCS performance during a hypothetical LOCA. Specific considerations include 10 CFR 50.46(a)(1 )(i) requires the use of an acceptable EM to evaluate ECCS performance under the conditions of a hypothetical LOCA, and 10 CFR 50.46(a)(1 )(ii) allows for the development of an EM that conforms to the required and acceptable features specified in Appendix K to 10 CFR 50. 10 CFR 50.46(a)(1)(i) also requires ECCS cooling performance to be calculated for a number of postulated LOCAs of different sizes, locations, and other properties sufficient to provide assurance that the *most severe hypothetical LOCAs are calculated.
Acceptance criteria set forth in paragraph (b) of 10 CFR 50.46, and the results of the ECCS evaluation must show that the acceptance criteria are met. Among others, these include requirements related to peak cladding temperature (PCT), maximum cladding oxidation, and maximum hydrogen generation.
Background
The licensee planned to transition from the current statistically based Best Estimate Large Break LOCA and deterministically based Small Break LOCA methods to a state-of-the-art, unified, and approved Full Spectrum LOCA approach (Reference 2). The proposed change will involve a change of VCSNS current Technical Specification 6.9.1.11, "Core Operating Limits Report," analytical methods Item (c). The proposed change in analysis methods also will fulfill the South Carolina Electric and Gas (now Dominion Energy South Carolina) commitment to address fuel pellet thermal conductivity degradation (TCD) as described in Nuclear Regulatory Commission Information Notice 2011-21, by replacing the previous PAD3.4 and PAD4.0 fuel thermal performance codes with the updated and approved PADS cod~ in the LOCA analyses.
The aforementioned Full Spectrum LOCA approach was adopted by Westinghouse to complete an analysis with the FULL SPECTRUM' loss-of-coolant accident (FSLOCA ')
evaluation model (EM) for VCSNS. This LAR requests approval to apply the Westinghouse FSLOCA EM.
Serial No.20-431 Docket No. 50-395 Enclosure 2 - RAI Response: Page 2 of 4 RAl-1; Axial Power Difference VCSNS TS LCO 3.2.1 requires the axial power difference (APO) be maintained within the allowed operational space specified in COLR as based on the Relaxed Axial Offset Control (RAOC) or within the target band specified in the COLR about the target flux difference during base load operation. Based on WCAP-16996, Figure 25.2-13, the staff has a concern that the axial power distributions created in FSLOCA EM library for VCSNS analysis may not sufficiently reflect the VCSNS reactor design. The licensee is requested to provide assurance that the axial power distributions created in FSLOCA EM library for VCSNS analysis are consistent with, or bound, those allowed by VCSNS TS LCO 3.2.1.
RAl-2; Operator Action No operator actions are described in the transient descriptions or sequences of events.
The licensee is requested to confirm that all assumed accident mitigation features occur automatically or discuss any operator actions that may be taken during the time spans as considered in the analyses.
1.1 DESCNCSNS Response RAl-1 Response The library of axial power distributions used in the VCSNS analysis with the FULL SPECTRUM' loss-of-coolant accident (FSLOCA ') evaluation model (EM) was generated using the methodology described in Section 25.2.1.4 of WCAP-16996-P-A, Revision 1 [2 .1]. [
]a,c Per Item 1.0e in Table 1 of the License Amendment Request Technical Evaluation (Attachment 4 to Agencywide Documents Access and Management System (ADAMS)
Accession No. ML20156A303 [2.2]), the VCSNS FSLOCA EM analysis supports an AFD band of -12% to +10% at 100% power. (Note that the FSLOCA EM analysis supports a wider AFD band than the most recent COLR, which allows an AFD band of -8% to 8% at 100% power per Figure 3 of ADAMS Accession No. ML20147A596 [2.3].) [
p,c Therefore, the power distributions created in FSLOCA EM library for VCSNS analysis are consistent with, or bound, those allowed by VCSNS TS LCO 3.2.1.
Serial No.20-431 Docket No. 50-395 Enclosure 2 - RAI Response: Page 3 of 4 a,c Figuni 1: [
RAl-2 Response The VCSNS FSLOCA analysis does not directly credit any operator actions. Safety system actuation occurs automatically due to the reactor trip and engineered safety feature actuation systems. In addition, the analysis does not require any new operator
Serial No.20-431 Docket No. 50-395 Enclosure 2 - RAI Response: Page 4 of 4 actions or the modification of existing operator actions in order to satisfy the applicable acceptance criteria of 10 CFR 50.46.
A continuous action step that directs operators to trip the Reactor Coolant Pumps (RCP) following a Small Break LOCA within 5 minutes of meeting a trip criterion is included in VCSNS Emergency Operating Procedures (EOPs). Additional information regarding the modeling of RCP operation within the methodological requirements of FSLOCA is contained on page B-983 of the Appendices of WCAP 16996-P-A, Revision 1 [2.1].
2.0 REFERENCES
2.1 WCAP-16996-P-A, Revision 1, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology),"
November 2016 2.2 ADAMS Accession No. ML20156A303, "Dominion Energy South Carolina (DESC),
Virgil C. Summer Nuclear Station (VCSNS) Unit 1 License Amendment Request, Update of Analytical Method to The Core Operating Limits Report with The FULL SPECTRUM Loss of Coolant Accident Approach," June 2020 2.3 ADAMS Accession No. ML20147A596, "Dominion Energy South Carolina, Inc.,
Virgil C. Summer Nuclear Station Unit 1, Core Operating Limits Report (COLR) for Cycle 26," May 2020 2.4 ADAMS Accession # ML20342A382, Request for Additional Information 2.5 Email from Mr. Vaughn Thomas (NRG) to Mr. Yan Gao (DESC) dated December 7, 2020, "Final RAI for Summer FS LOCA LAR"
Serial No.20-431 Docket No. 50-395 Enclosure 3 Westinghouse Affidavit for Withholding Proprietary Information Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Dominion Energy South Carolina, Inc. (DESC)
Serial No.20-431 Docket No. 50-395 Enclosure 3: Page 1 of 3 AFFIDAVIT (CAW-20-5122)
COMMONWEALTH OF PENNSYLVANIA:
COUNTY OF BUTLER:
(1) I, Zachary S_ Harper. have been specifically delegated and authorized to apply for withholding and execute this Affidavit on behalf of\"\lestingbouse Electric Company LLC 0.V estinghonse).
(2) I am requesting the proprietary portion,:; of CGE-20-27-P be withheld from public disclosure under 10 CFR 2-390.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged, or as confidential commercial or financial information.
(4) Purniant to 10 CFR 2390, the following is .famished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld_
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Vlestinghouse and is not customarily disclosed to the public.
(ii) The information sought to he withheld is being transmitted to the Commission in confidence and, to Westinghouse's knowledge, is not available in public sources.
(iii) Westinghouse notes that a showing of substantial harm is no longer an applicable criterion for analyzing whether a document should be withheld from public disclosure_ Nevertheless, public disclosure of this proprietary information is likely to cause substa11tial harm to the competitive position of\Vestinghouse because it would enhance the ability of competitors to provide similar technical evaluation justifications and licensing defense services for commercial power :reactors without commensurate expenses_ Also, public disclosure of1he information would enable
Serial No.20-431 Docket No. 50-395 Enclosure 3: Page 2 of 3 others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
(5) \Vestinghouse has policies in place to identify proprietary information. Under that system, 111.fonnation is held in confidence if it falls i11 one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, strncture, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from \Vestinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, strncture, tool, method, etc.), the application of which data secures a competitive economic advantage (e.g .. by optimization or improved marketability).
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production capacities,, budget levels, or commet"cial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or foture \Vestinghouse or customer funded development plans and programs of potential commercial value to
\Vestinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
Serial No.20-431 Docket No. 50-395 Enclosure 3: Page 3 of 3 (6) 111c attached docu1mmts are bracketed and marked to indicate the bases for withholding. The justification for withholding is indicated in both versions by 1mmns of lowcr~ca..1e letters (a) thwugh (fJ kx:ated us a superscript immediately foUowing the bracket'i cncfosing each item or infhrrnation being identified as proprfotacy or in the m.urgin opposite such information. 'lnt-sc lowcr--casc letters refcr te) tlw types of information Westinghouse customarily holds in confidence identified in s..-ctfons (S)(a) through (0 or this Affidavit, I declare that the avcrmcnts of fact set forth in this Affidavit are true and correct to the best tlfmy knowledge, infrnmation, and belief.
I declare under penalty of perjury that the foregoing is true and correct.
Licensing l~ttgineering