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| {{#Wiki_filter:}} | | {{#Wiki_filter:April 17, 2020 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd. |
| | Glen Allen, VA 23060-6711 |
| | |
| | ==SUBJECT:== |
| | SURRY NUCLEAR POWER STATION, UNITS 1 AND 2 AND NORTH ANNA POWER STATION UNITS 1 AND 2 - AUDIT RE: PROPOSED LICENSE AMENDMENT REQUEST FOR THE ADDITION OF WESTINGHOUSE TOPICAL REPORT WCAP-16996-P-A, REVISION 1, TO THE CORE OPERATING LIMITS REPORT (EPID L-2019-LLA-0243 AND EPID L-2019-LLA-0236) |
| | |
| | ==Dear Mr. Stoddard:== |
| | |
| | By letters dated October 30, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML19309D196 and ML19309D197), Dominion Energy Virginia (Dominion), submitted a license amendment request for Surry Nuclear Power Station (Surry), |
| | Units 1 and 2 and North Anna Power Station (North Anna), Units 1 and 2. The proposed amendments request the addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1,to the Core Operating Limits Report. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff will conduct a regulatory audit to support its review of the proposed license amendments. The audit is planned to be conducted remotely or on-site at Surry to facilitate access to the licensees probabilistic risk assessment (PRA) models, documentation, and technical experts. The NRC staff intends to start the audit on April 22, 2020, and the logistics and scope of the audit plan enclosed. |
| | If you have any questions, please contact me by telephone at (301) 415-5897 or by e-mail at vaughn.thomas@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Vaughn V. Thomas, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281; 50-338 and 50-339 |
| | |
| | ==Enclosures:== |
| | |
| | (1) Audit Plan (2) Appendix A: Audit Topics cc: Listserv |
| | |
| | AUDIT PLAN LARGE BREAK LOSS-OF-COOLANT ACCIDENT METHODOLOGY DOMINION ENERGY VIRGINIA NORTH ANNA POWER STATION, UNITS 1 AND 2 DOCKETS NOS. 50-338 AND 50-339 AND SURRY POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-280 AND 50-281 |
| | |
| | ==1.0 BACKGROUND== |
| | |
| | By letters dated October 30, 2019, Dominion Energy (the licensee) submitted license amendment requests (LARs) for Surry and North Anna Power Stations Units 1 and 2, respectively. The proposed amendments request the addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1, Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology), to the list of methodologies approved for reference in the Core Operating Limits Report (COLR). |
| | The U.S. Nuclear Regulatory Commission (NRC) staff is currently performing a detailed review of the proposed license amendment requests. Due to the complexity of the proposed amendment, the NRC staff has determined that an audit is needed to help resolve the complex technical issues rather than issuing several rounds of requests for additional information (RAI). |
| | The NRC staff is requesting a regulatory audit in accordance with the Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, Regulatory Audits, dated October 31, 2019 (ADAMS Accession No. ML19226A274), for the NRC staff to gain a better understanding of the licensee's calculations and other aspects supporting the LARs. The audit is for voluntary submittals pursuant to 10 CFR 50.90 for Surry Units, 1 and 2, and North Anna, Units 1 and 2. |
| | 2.0 REGULATORY AUDIT SCOPE A regulatory audit is conducted with the intent to gain understanding, to verify information and/or to identify information that will require docketing to support the basis for the proposed licensing or regulatory decision. |
| | The regulatory bases for the NRC are the requirements contained in the Title10, Energy, of the Code of Federal Regulation (10 CFR), Section 50.46, Acceptance Criteria for Emergency Core Cooling Systems (ECCS) for Light Water Nuclear Power Reactors. |
| | Enclosure 1 |
| | |
| | 3.0 REGULATORY AUDIT SCOPE AND METHODOLOGY The audit will cover the following documents and topics: |
| | * Calculation notes and related documentation supporting the license amendment requests |
| | * Criteria and methods used in the LBLOCA [Large Break Loss-of-Coolant Accident] |
| | analyses 4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT The NRC audit team will require access to personnel knowledgeable in all aspects of the LARs and any documentation which supports the license amendment requests. Specific areas of discussion and relevant questions are included in Appendix A of this audit plan. The NRC staff requests the licensee provide the supporting documents electronically (i.e., internet SharePoint) to support a remote audit. |
| | 5.0 TEAM ASSIGNMENTS The audit will be conducted by NRC staff from NRR, Division of Safety Systems (DSS), Nuclear Systems Performance Branch (SNSB). The NRC audit team consists of: |
| | Fred Forsaty, Technical Reviewer Vaughn Thomas, Project Manager Ed Miller, Project Manager 6.0 LOGISTICS The Division of Operating Reactor Licensing (DORL) PM will schedule an entrance meeting for this audit and an exit meeting based on a mutually agreed upon date and time. The DORL PM will provide updates to the licensee upon request and facilitate any additional request the technical staff may have to the licensee. |
| | 7.0 DELIVERABLES A regulatory audit summary will be issued within 60 days after the completion of the audit and exit meeting with the licensee. The summary will use the NRR Office Instruction, LIC-111, Regulatory Audits. Any additional information needed to support the safety evaluation that was identified from the audit will be transmitted to the licensee from DORL as requests for additional information. |
| | |
| | ==8.0 REFERENCES== |
| | : 1. Sartain, Mark, Vice President, Virginia Electric Power Company (Dominion Energy Virginia), letter to U.S. NRC, "Virginia Electric and Power Company North Anna Station Units 1 and 2 Proposed License Amendment Request Addition of Analytical Methodology to the Core Operating Limits Report For A Full Spectrum Loss of Coolant Accident (FSLOCA), dated October 30, 2019 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML19309D197. |
| | : 2. Sartain, Mark, Vice President, Virginia Electric Power Company (Dominion Energy Virginia), letter to U.S. NRC, "Virginia Electric and Power Company North Anna Station Units 1 and 2 Proposed License Amendment Request Addition of Analytical Methodology to the Core Operating Limits Report For A Large Break Loss of Coolant Accident (LBLOCA), dated October 30, 2019 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML19309D196. |
| | : 4. U.S. NRC Office Instruction, LIC-111, Revision 1, Regulatory Audits, dated October 31, 2019 (ADAMS Accession No. ML19226A274). |
| | |
| | Appendix A: Audit Topics |
| | : 1. Any relationships or dependencies between this license amendment request (LAR) and the VA Power SBLOCA (Small Break Loss-of-Coolant Accident) LAR (ADAMS Accession No. ML18198A118, dated July 12, 2018, EPID NOS. L-2018-LLA-0215). |
| | : 2. The power shape as described in this LAR and its consistency with or deviation from the current final safety analysis report (FSAR) |
| | : 3. Explain and justify deletion of Technical Specification (TS) 6.2.C in the Surry LAR. |
| | : 4. ECCS pump curve used in this application. Is this pump curve similar to the one used in the current FSAR accident analyses? of the LAR |
| | : 5. Compliance to Limitation and Condition Number 3 concerning the minimum initial temperature associated with normal full power is modeled. |
| | : 6. Compliance to Limitation and Condition Number 5 concerning details of the maximum analyzed assembly and rod length-average burnups used in the analysis in this LAR. |
| | : 7. Compliance to Limitation and Condition Number 12 concerning the approach used in modeling the bounding and plant-specific dynamic pressure loss from the steam generator secondary side to the main steam safety valves. |
| | : 8. Compliance to Limitation and Condition Number 13 concerning specific modeling of the upper head spray nozzle requirements. |
| | : 9. Compliance to Limitation and Condition Number 15 concerning uncertainty method used. |
| | : 10. Assumptions used in Tables 1 through 4 and consistency with the input assumptions used in the current FSAR analysis. Please explain the differences and the possible impacts to the new analysis results. |
| | : 11. For Figure 6, explain the presence of the double peaks in the mass flow rate verses time after break. |
| | : 12. For Figure 7, explain the sharp peak in the pressure verses time after break. |
| | Enclosure 2 |
| | |
| | ML20099F873 *via email OFFICE NRR/DORL/ LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/SNSB/BC* |
| | NAME VThomas KGoldstein JBorromeo DATE 03/07/2020 04/15/2020 03/07/2020 OFFICE NRR/DORL/LPL2-1/BC* NRR/DORL/ LPL2-1/PM NAME MMarkley VThomas DATE 04/17/2020 04/17/2020}} |
Letter Sequence Other |
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EPID:L-2019-LLA-0236, Emergency Core Cooling System Model Change Pursuant to the Requirements of 10 CFR 50.46 Submittal Schedule Commitment Change (Approved, Closed) EPID:L-2019-LLA-0243, Emergency Core Cooling System Model Change Pursuant to the Requirements of 10 CFR 50.46 Submittal Schedule Commitment Change (Approved, Closed) |
|
MONTHYEARML19214A0472019-07-30030 July 2019 Emergency Core Cooling System Model Change Pursuant to the Requirements of 10 CFR 50.46 Submittal Schedule Commitment Change Project stage: Request ML19309D1972019-10-30030 October 2019 Proposed License Amendment Request Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident Project stage: Request ML19309D1962019-10-30030 October 2019 Proposed License Amendment Request Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident (LBLOCA) Project stage: Request ML20099F8732020-04-17017 April 2020 Audit Proposed License Amendment Request for the Addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1 (EPID L-2019-LLA-0243 and EPID L-2019-LLA-0236 Project stage: Other ML20272A2272020-10-23023 October 2020 Audit Summary: Proposed License Amendment Request for the Addition of Westinghouse Topical Report Project stage: Other ML20301A4522020-10-28028 October 2020 Non-Proprietary, Issuance of Amendment Nos. 300 and 300 to Revise Technical Specifications 6.2.C, Core Operating Limits Report Project stage: Approval ML20302A1792020-10-29029 October 2020 Non-Proprietary, Issuance of Amendment Nos. 286 and 269 to Revise Technical Specifications to Allow Usage of a Full Spectrum Loss of Coolant Accident Methodology Project stage: Approval 2020-10-23
[Table View] |
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Category:Audit Plan
MONTHYEARML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML23223A0402023-08-25025 August 2023 Audit Plan License Amendment Request for Revision of the Emergency Plan to Support Relocation of the Technical Support Center ML23152A0432023-06-22022 June 2023 Audit Plan License Amendment Requests to Change Emergency Plan Staff Augmentation Times ML23117A0952023-05-10010 May 2023 Audit Plan License Amendment Request to Support Relocation of the Technical Support Center ML23062A4662023-03-0808 March 2023 License Renewal Second Environmental Site Audit Plan Regarding the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application ML22255A1862022-10-0303 October 2022 Tornado Classification of the Fuel Handling Trolley Support Structure License Amendment Request Audit Plan ML22250A4672022-09-15015 September 2022 Turbine Building Wind Loading Basis Change Audit Plan ML22004A2872022-01-14014 January 2022 Technical Specification Section 3.4.A.4 Change of Post Loss-of-Coolant Accident Chemical Buffer Audit Plan ML20337A0222020-12-0404 December 2020 License Renewal Severe Accident Mitigation Alternatives Audit Plan Regarding the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application (EPID No.: L-2020-SLE-0000) (Docket No.: 50-338 and 50-339) ML20322A0522020-11-19019 November 2020 License Renewal Environmental Site Audit Plan Regarding the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application ML20276A1922020-10-0909 October 2020 Subsequent License Renewal Aging Management Audit Plan ML20099F8732020-04-17017 April 2020 Audit Proposed License Amendment Request for the Addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1 (EPID L-2019-LLA-0243 and EPID L-2019-LLA-0236 ML19338C6902019-12-10010 December 2019 Audit Plan License Amendment Request for Small Break Loss of Coolant Accident Methodology (Epids L-2018-LLA-0195 and L-2018-LLA-0215) ML19220A5552019-08-13013 August 2019 Audit Proposed License Amendment Request for the Addition of 24-Hour Associated with the Technical Specification Completion Time for an Inoperable Reactor Trip (EPID-L-2019-LLA-0110) ML19165A0172019-07-0303 July 2019 Audit Plan License Amendment Request for Flood Protection Dike Modification ML19098A8102019-04-17017 April 2019 On-Site Regulatory Audit Regarding the Subsequent License Renewal Application Review (EPID Nos. L-2018-RNW-0023 and L-2018-RNW-0024) ML19044A5562019-03-0404 March 2019 License Renewal Environmental Site Audit Plan Regarding the Surry Power Station, Units 1 and 2, Subsequent License Renewal Application ML19044A6592019-03-0404 March 2019 License Renewal Severe Accident Mitigation Alternatives Audit Plan Regarding the Surry Power Station, Unit Nos. 1 and 2, Subsequent License Renewal Application ML19015A2432019-01-22022 January 2019 Plan for the In-Office Regulatory Audit Regarding the Subsequent License Renewal Application Review (EPID Nos. L-2018-RNW-0023 and L-2018-RNW-0024) ML18319A1842018-11-26026 November 2018 Plan for the Operating Experience Audit Regarding the Subsequent License Renewal Application Review (EPID Nos. L-2018-RWN-0023 and L-2018-RNW-0024 ML17177A4462017-07-0606 July 2017 Audit Plan for Licensee Responses Concerning Seismic Hazard Reevaluations Related to Request for Information -(50.54(F) Letter) Regarding Recommendation 2.1 of the Near-Term Task Force ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16098A5302016-04-14014 April 2016 Audit Plan - Application for Amendment North Anna Power Station, Units 1 and 2. the Proposed License Amendment Revises the Issues Identified in Westinghouse Documents NSAL-09-5, Rev 1 and NSAL-15-1 ML16091A4542016-04-12012 April 2016 Audit Plan Regarding Application for License Amendment, Issues Identified in Westinghouse Documents NSAL-09-05, REV1 and NSAL-15-1 ML15153A1602015-06-15015 June 2015 Nuclear Regulatory Commission Plan for the Audit of Virginia Electric and Power Company'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Surry Power Station, Units 1 and 2 ML14356A0032015-02-10010 February 2015 Audit of Licensee Responses to the Expedited Seismic Evaluation Process to Support Implementation of Near-Term Task Force Recommendation 2.1, Seismic ML14343A1412014-12-11011 December 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14189A3202014-07-0808 July 2014 Plan to Audit the Regional Response Center Proof of Concept Demonstration with Surry Power Station Regarding Implementation of Phase 3 Related to Order EA-12-049 (Mitigating Strategies) L-12-049, Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 (TAC Nos. MF0998, MF0999, MF0986, and MF0987)2014-04-24024 April 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 (TAC Nos. MF0998, MF0999, MF0986, and MF0987) ML14112A3022014-04-24024 April 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 2024-03-21
[Table view] Category:Letter
MONTHYEARML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant ML24206A0902024-07-24024 July 2024 Owners Activity Report ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20240112024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report 2024-08-08
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change ML23181A1352023-08-22022 August 2023 Issuance of Amendment Nos. 295 and 278 License Amendment Request to Remove the Refueling Water Chemical Addition Tank and Change the Containment Sump Ph Buffer ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23100A0652023-04-25025 April 2023 Issuance of Amendment Nos. 310 and 310, Regarding Turbine Building Tornado Classification ML23107A2212023-04-10010 April 2023 Amendment Turbine Building Wind Load Basis Reclassification License Amendment Request - State Consultation No Comment ML23030B8472023-03-10010 March 2023 Issuance of Amendment Nos. 309 and 309, License Amendment Request Regarding a 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability ML22336A1822022-12-27027 December 2022 Virginia Electric and Power Company Correction of Documentation Error Amendment No. 295 Adopt TSTF-490, Revision 0, and Update Alternative Source Term Analyses ML22250A4672022-09-15015 September 2022 Turbine Building Wind Loading Basis Change Audit Plan ML22193A2952022-08-26026 August 2022 Issuance of Amendment Nos. 308 and 308 License Amendment Request for Removal of the Refueling Water Chemical Addition Tank and Containment Sump, Ph Buffer Change and Safety Evaluation ML22202A0472022-07-25025 July 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Surry Technical Specification Change Auxiliary Feedwater Allowed Outage Time ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22068A0712022-03-22022 March 2022 Issuance of Amendment Nos. 292 and 275 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21323A1742021-12-22022 December 2021 Issuance of Amendment Nos. 289 and 272 to Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A ML21253A0632021-11-19019 November 2021 Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis ML21188A1742021-10-26026 October 2021 Issuance of Amendment Nos. 305 and 305 Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21232A2172021-10-19019 October 2021 Issuance of Amendment Nos. 288 and 271 to Revise Technical Specifications Battery Surveillance Testing ML21175A1852021-08-20020 August 2021 Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines ML20091L9822021-05-0404 May 2021 SLR License ML20325A0952021-03-19019 March 2021 Issuance of Amendment to Revise Technical Specifications to Allow Usage of a Small Break Loss of Coolant Accident Methodology (Non-Proprietary) ML20293A1602020-12-0808 December 2020 Issuance of Amendment Nos. 301 and 301 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20148M3592020-12-0808 December 2020 Issuance of Amendment Nos. 302 and 302 to Revise Technical Specifications Figure 3.1 1, Surry Units 1 and 2 Reactor Coolant System Heatup Limitations, and Figure 3.1-2, Surry Units 1 and 2 Reactor Coolant System ML20302A1792020-10-29029 October 2020 Non-Proprietary, Issuance of Amendment Nos. 286 and 269 to Revise Technical Specifications to Allow Usage of a Full Spectrum Loss of Coolant Accident Methodology ML20301A4522020-10-28028 October 2020 Non-Proprietary, Issuance of Amendment Nos. 300 and 300 to Revise Technical Specifications 6.2.C, Core Operating Limits Report ML20309A5912020-10-14014 October 2020 Pre-Submittal Meeting for License Amendment Requests to Implement Batch Framatome 15 X 15 AGORA-5A-I (Agora) Fuel at Surry Power Station Units 1 and 2 (SPS) - Slides ML20085G9642020-05-19019 May 2020 Issuance of Amendments Nos. 298 and 298 to Revise Technical Specifications Table 3.7-1, Reactor Trip Instrument Operating Conditions, for an Addition of 24-Hour Completion Time for an Inoperable Rector Trip Breaker ML20115E2372020-05-0707 May 2020 Issuance of Exigent Amendments Nos. 299 and 299, to Revise TS 6.4.Q, Steam Generator (SG) Program, to Allow a One-Time Deferral of the Inspection of Surry Unit 2 Sg B Spring 2020 Refueling Outage ML20099F8732020-04-17017 April 2020 Audit Proposed License Amendment Request for the Addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1 (EPID L-2019-LLA-0243 and EPID L-2019-LLA-0236 ML20058F9662020-03-16016 March 2020 Issuance of Amendment Nos. 297 and 297 to Revise Technical Specifications 3.16, Emergency Power System, to Allow a One Time 14-Day Allowed Outage Time for Replacement of 5-KV Cables Associated with Reserve Station ML19319A5832020-01-17017 January 2020 Issuance of Amendment Nos. 285 and 268 to Revise Technical Specifications Regarding Emergency Diesel Generator Maximum Voltage Limits ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19274C9982019-11-13013 November 2019 Issuance of Amendments Regarding Installation of Water Headers in Flood Protection Dike ML19238A1272019-09-12012 September 2019 Issuance of Amendment Nos. 282 and 265 to Revise Technical Specifications Regarding Open Phase Protection ML19028A3842019-06-12012 June 2019 Issuance of Amendment Nos. 295 and 295 to Adopt TSTF-490, Revision 0, and Update Alternative Source Term Analyses (EPID-L-2018-LLA-0068) ML19031B2272019-02-27027 February 2019 Issuance of Amendment Nos. 281, 264, 294, and 294 to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes ML18290A8522018-11-27027 November 2018 Issuance of Amendments 280, 263 to Revise Technical Specifications Regarding Ventilation System Surveillance Requirements in Accordance with TSTF-522 ML18261A0992018-10-0505 October 2018 Issuance of Amendments. Request to Revise Technical Specifications Section 3.16 Emergency Power System Regarding a Temporary 21 Day Allowed Outage Time ML18180A1972018-07-27027 July 2018 Issuance of Amendments to Revise Technical Specifications Regarding New and Spent Fuel Storage (CAC Nos. MF9712 and MF9713, EPID L-2017-LLA-0240) ML18106A0072018-05-0303 May 2018 Issuance of Amendments Regarding Open Phase Protection Per NRC Bulletin 2012 01 (CAC Nos. MF9805, MF9806; EPID L-2017-LLA-0238) ML17326A2252018-02-0909 February 2018 Issuance of Amendments Regarding License Amendment Request to Revise Residual Heat Removal and Component Cooling System Technical Specifications Requirements (CAC Nos. MF9124 and MF9125; EPID L-2017-LLA-0166) ML17170A1832017-07-28028 July 2017 Issuance of Amendments Regarding the Extension of the Emergency Service Water Pump Allowed Outage Time, Surry Power Station, Units 1 and 2 ML17100A2532017-05-31031 May 2017 Issuance of Amendments Regarding Extension of Technical Specification 3.14, Service Water Flow Path Allowed Outage Times and Deletion of Expired Temporary Service Water Jumper Requirements (CAC Nos. MF7746... ML17039A5132017-05-10010 May 2017 Issuance of Amendment Nos. 288 and 288 Regarding Technical Specification Changes to Expand Primary Grade Water Lockout Requirements in TS 3.2.E (CAC Nos. MF7716 and MF7717). 08/10/2017 ML16252A4782016-10-17017 October 2016 Issuance of Amendments Revising Technical Specifications to Address the Issue Identified in Westinghouse NSAL-09-5, Revision 1, and NSAL-15-1, Revision 0 ML16202A0682016-07-14014 July 2016 Proposed Licensed Amendment Request Emergency Service Water Pump Allowed Outage Time Extension ML16042A1732016-02-29029 February 2016 Issuance of Amendments for Generic Letter 2008-01 (Gas Accumulation) 2024-07-17
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April 17, 2020 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT:
SURRY NUCLEAR POWER STATION, UNITS 1 AND 2 AND NORTH ANNA POWER STATION UNITS 1 AND 2 - AUDIT RE: PROPOSED LICENSE AMENDMENT REQUEST FOR THE ADDITION OF WESTINGHOUSE TOPICAL REPORT WCAP-16996-P-A, REVISION 1, TO THE CORE OPERATING LIMITS REPORT (EPID L-2019-LLA-0243 AND EPID L-2019-LLA-0236)
Dear Mr. Stoddard:
By letters dated October 30, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML19309D196 and ML19309D197), Dominion Energy Virginia (Dominion), submitted a license amendment request for Surry Nuclear Power Station (Surry),
Units 1 and 2 and North Anna Power Station (North Anna), Units 1 and 2. The proposed amendments request the addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1,to the Core Operating Limits Report.
The U.S. Nuclear Regulatory Commission (NRC) staff will conduct a regulatory audit to support its review of the proposed license amendments. The audit is planned to be conducted remotely or on-site at Surry to facilitate access to the licensees probabilistic risk assessment (PRA) models, documentation, and technical experts. The NRC staff intends to start the audit on April 22, 2020, and the logistics and scope of the audit plan enclosed.
If you have any questions, please contact me by telephone at (301) 415-5897 or by e-mail at vaughn.thomas@nrc.gov.
Sincerely,
/RA/
Vaughn V. Thomas, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281; 50-338 and 50-339
Enclosures:
(1) Audit Plan (2) Appendix A: Audit Topics cc: Listserv
AUDIT PLAN LARGE BREAK LOSS-OF-COOLANT ACCIDENT METHODOLOGY DOMINION ENERGY VIRGINIA NORTH ANNA POWER STATION, UNITS 1 AND 2 DOCKETS NOS. 50-338 AND 50-339 AND SURRY POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-280 AND 50-281
1.0 BACKGROUND
By letters dated October 30, 2019, Dominion Energy (the licensee) submitted license amendment requests (LARs) for Surry and North Anna Power Stations Units 1 and 2, respectively. The proposed amendments request the addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1, Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology), to the list of methodologies approved for reference in the Core Operating Limits Report (COLR).
The U.S. Nuclear Regulatory Commission (NRC) staff is currently performing a detailed review of the proposed license amendment requests. Due to the complexity of the proposed amendment, the NRC staff has determined that an audit is needed to help resolve the complex technical issues rather than issuing several rounds of requests for additional information (RAI).
The NRC staff is requesting a regulatory audit in accordance with the Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, Regulatory Audits, dated October 31, 2019 (ADAMS Accession No. ML19226A274), for the NRC staff to gain a better understanding of the licensee's calculations and other aspects supporting the LARs. The audit is for voluntary submittals pursuant to 10 CFR 50.90 for Surry Units, 1 and 2, and North Anna, Units 1 and 2.
2.0 REGULATORY AUDIT SCOPE A regulatory audit is conducted with the intent to gain understanding, to verify information and/or to identify information that will require docketing to support the basis for the proposed licensing or regulatory decision.
The regulatory bases for the NRC are the requirements contained in the Title10, Energy, of the Code of Federal Regulation (10 CFR), Section 50.46, Acceptance Criteria for Emergency Core Cooling Systems (ECCS) for Light Water Nuclear Power Reactors.
Enclosure 1
3.0 REGULATORY AUDIT SCOPE AND METHODOLOGY The audit will cover the following documents and topics:
- Calculation notes and related documentation supporting the license amendment requests
- Criteria and methods used in the LBLOCA [Large Break Loss-of-Coolant Accident]
analyses 4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT The NRC audit team will require access to personnel knowledgeable in all aspects of the LARs and any documentation which supports the license amendment requests. Specific areas of discussion and relevant questions are included in Appendix A of this audit plan. The NRC staff requests the licensee provide the supporting documents electronically (i.e., internet SharePoint) to support a remote audit.
5.0 TEAM ASSIGNMENTS The audit will be conducted by NRC staff from NRR, Division of Safety Systems (DSS), Nuclear Systems Performance Branch (SNSB). The NRC audit team consists of:
Fred Forsaty, Technical Reviewer Vaughn Thomas, Project Manager Ed Miller, Project Manager 6.0 LOGISTICS The Division of Operating Reactor Licensing (DORL) PM will schedule an entrance meeting for this audit and an exit meeting based on a mutually agreed upon date and time. The DORL PM will provide updates to the licensee upon request and facilitate any additional request the technical staff may have to the licensee.
7.0 DELIVERABLES A regulatory audit summary will be issued within 60 days after the completion of the audit and exit meeting with the licensee. The summary will use the NRR Office Instruction, LIC-111, Regulatory Audits. Any additional information needed to support the safety evaluation that was identified from the audit will be transmitted to the licensee from DORL as requests for additional information.
8.0 REFERENCES
- 1. Sartain, Mark, Vice President, Virginia Electric Power Company (Dominion Energy Virginia), letter to U.S. NRC, "Virginia Electric and Power Company North Anna Station Units 1 and 2 Proposed License Amendment Request Addition of Analytical Methodology to the Core Operating Limits Report For A Full Spectrum Loss of Coolant Accident (FSLOCA), dated October 30, 2019 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML19309D197.
- 2. Sartain, Mark, Vice President, Virginia Electric Power Company (Dominion Energy Virginia), letter to U.S. NRC, "Virginia Electric and Power Company North Anna Station Units 1 and 2 Proposed License Amendment Request Addition of Analytical Methodology to the Core Operating Limits Report For A Large Break Loss of Coolant Accident (LBLOCA), dated October 30, 2019 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML19309D196.
- 4. U.S. NRC Office Instruction, LIC-111, Revision 1, Regulatory Audits, dated October 31, 2019 (ADAMS Accession No. ML19226A274).
Appendix A: Audit Topics
- 1. Any relationships or dependencies between this license amendment request (LAR) and the VA Power SBLOCA (Small Break Loss-of-Coolant Accident) LAR (ADAMS Accession No. ML18198A118, dated July 12, 2018, EPID NOS. L-2018-LLA-0215).
- 2. The power shape as described in this LAR and its consistency with or deviation from the current final safety analysis report (FSAR)
- 3. Explain and justify deletion of Technical Specification (TS) 6.2.C in the Surry LAR.
- 4. ECCS pump curve used in this application. Is this pump curve similar to the one used in the current FSAR accident analyses? of the LAR
- 5. Compliance to Limitation and Condition Number 3 concerning the minimum initial temperature associated with normal full power is modeled.
- 6. Compliance to Limitation and Condition Number 5 concerning details of the maximum analyzed assembly and rod length-average burnups used in the analysis in this LAR.
- 7. Compliance to Limitation and Condition Number 12 concerning the approach used in modeling the bounding and plant-specific dynamic pressure loss from the steam generator secondary side to the main steam safety valves.
- 8. Compliance to Limitation and Condition Number 13 concerning specific modeling of the upper head spray nozzle requirements.
- 9. Compliance to Limitation and Condition Number 15 concerning uncertainty method used.
- 10. Assumptions used in Tables 1 through 4 and consistency with the input assumptions used in the current FSAR analysis. Please explain the differences and the possible impacts to the new analysis results.
- 11. For Figure 6, explain the presence of the double peaks in the mass flow rate verses time after break.
- 12. For Figure 7, explain the sharp peak in the pressure verses time after break.
Enclosure 2
ML20099F873 *via email OFFICE NRR/DORL/ LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/SNSB/BC*
NAME VThomas KGoldstein JBorromeo DATE 03/07/2020 04/15/2020 03/07/2020 OFFICE NRR/DORL/LPL2-1/BC* NRR/DORL/ LPL2-1/PM NAME MMarkley VThomas DATE 04/17/2020 04/17/2020