Letter Sequence Other |
|---|
|
|
MONTHYEARML19220A5552019-08-13013 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)
Project stage: Other
ML19350A0042019-12-12012 December 2019
License Amendment Request Addition of 24-Hour Completion Time for an Inoperable Reactor Trip Breaker Response to NRC Request for Additional Information
Project stage: Response to RAI
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
Project stage: Approval
2019-08-13
[Table View] |
Similar Documents at Surry |
|---|
Category:Audit Plan
MONTHYEARML23152A0432023-06-22022 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
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
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)
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
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
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
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)
2023-06-22
[Table view]
Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024
Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401
IR 05000280/20230102024-01-18018 January 2024
Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010
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
ML24003A9022024-01-0303 January 2024
Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction
IR 05000280/20233012023-12-28028 December 2023
NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301
ML23283A3052023-12-20020 December 2023
Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary)
ML23352A3692023-12-18018 December 2023
Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change
ML23334A2342023-11-30030 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
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
IR 05000280/20230032023-10-25025 October 2023
Integrated Inspection Report 05000280/2023003 and 05000281/2023003
ML23286A0372023-10-13013 October 2023
Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J
ML23285A0922023-10-12012 October 2023
Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests
ML23277A1172023-10-0303 October 2023
Operator Licensing Examination Approval 05000280/2023301 and 05000281/2023301
ML23230A0502023-10-0202 October 2023
5 of the Quality Assurance Topical Report - Review of Program Changes
ML23256A2672023-09-21021 September 2023
Review of the Fall 2022 Steam Generator Tube Inspection Report
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
IR 05000280/20220042023-09-0101 September 2023
Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004
ML23244A0142023-08-30030 August 2023
Inservice Inspection Owner'S Activity Report
IR 05000280/20230052023-08-23023 August 2023
Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005)
ML23226A1862023-08-10010 August 2023
Proposed License Amendment Request - Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation
ML23220A1492023-08-0707 August 2023
Independent Spent Fuel Storage Installation - Submittal of Cask Registrations for Spent Fuel Storage
ML23220A1482023-08-0707 August 2023
Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information
IR 05000280/20230022023-08-0404 August 2023
Integrated Inspection Report 05000280/2023002 and 05000281/2023002
ML23208A0922023-07-26026 July 2023
Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response
ML23207A1102023-07-26026 July 2023
NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
ML23198A0322023-07-18018 July 2023
Regulatory Audit Report Regarding Review of License Amendment to Modify Emergency Plan Staff Augmentation Times
ML23193A9382023-07-18018 July 2023
Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML23173A0602023-07-11011 July 2023
Audit Summary for License Amendment Request Revision of the Emergency Plan to Support Relocation of the Technical Support Center
ML23136B1392023-06-29029 June 2023
Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications
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
ML23152A0432023-06-22022 June 2023
Audit Plan License Amendment Requests to Change Emergency Plan Staff Augmentation Times
ML23153A1732023-06-16016 June 2023
Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement
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
ML23151A6612023-05-31031 May 2023
ES-2.1-1, Surry 2023-301 Corporate Notification Letter (Revised)
ML23167B0072023-05-31031 May 2023
Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary
ML23117A0952023-05-10010 May 2023
Audit Plan License Amendment Request to Support Relocation of the Technical Support Center
ML23130A3742023-05-10010 May 2023
Request to Delay NRC Intial Licensing Examination
2024-02-06
[Table view] |
Text
August 13, 2019 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 - AUDIT RE: 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)
Dear Mr. Stoddard:
By letter dated May 15, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19143A201), Dominion Energy Virginia (Dominion), submitted a license amendment request regarding the Surry Nuclear Power Station (Surry), Units 1 and 2.
The proposed amendment would revise the licensing basis of Surry regarding the addition of 24-hour completion time for an inoperable reactor trip breaker.
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 models, documentation, and technical experts. The NRC staff intends to start the audit on August 14, 2019, and the logistics and scope of the audit plan enclosed.
If you have any questions, please contact me by telephone at (301) 415-2481 or by e-mail at Ed.Miller@nrc.gov.
Sincerely,
/RA/
G. Edward Miller, Project Manager Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281
Enclosure:
Audit Plan cc: Listserv
AUDIT PLAN ADDITION OF 24-HOUR COMPLETE TIME FOR AN INOPERABLE REACTOR TRIP BREAKER AMENDMENT DOMINION ENERGY VIRGINIA SURRY POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-280 AND 50-281
1.0 BACKGROUND
By letter to the U. S. Nuclear Regulatory Commission (NRC) dated May 15, 2019 (Reference 1), Virginia Electric and Power Company (Dominion Energy Virginia) submitted a license amendment request (LAR) for Surry Nuclear Station, Units 1 and 2, to extend the Technical Specification completion time associated with an inoperable reactor trip breaker for an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This change is based on Westinghouse Commercial Atomic Power (WCAP)-15376-P-A, Revision 1, "Risk-Informed Assessment of the RTS [reactor trip system]
and ESFAS [engineered safety features actuation system] Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times," which the NRC staff approved by letter dated December 20, 2002 (Reference 2). WCAP-15376-P-A provides justification for changes in the NRC-approved Technical Specification Task Force (TSTF)-411, Revision 1, "Surveillance Test Interval Extensions for Components of the Reactor Protection System (WCAP-15376-P)"
(Reference 3).
The NRC staffs review of the LAR has commenced in accordance with the Office of Nuclear Reactor Regulations (NRRs) Office Instruction LIC-101, License Amendment Review Procedures, (Reference 4).
The NRC staff has determined that a regulatory audit of the LAR should be conducted in accordance with NRR Office Instruction LIC-111, Regulatory Audits,(Reference 5), for the staff to gain a better understanding of the licensees proposed risk-informed application for consistency with the approved WCAP-15376-P-A, TSTF-411, and to verify the acceptability of the probabilistic risk assessment (PRA) used for the risk application (i.e., Regulatory Guide (RG)1.200, Appendix X to Nuclear Energy Institute (NEI) 05-04, 07-12, 12-13, etc.).
The basis of this audit hinges upon the voluntary submittal pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90 for the Surry Nuclear Station, Units 1 and 2, LAR dated May 15, 2019.
2.0 REGULATORY AUDIT SCOPE The NRC staff will review the PRA acceptability described in the LAR and the conformance with TSTF-411. The audit team will discuss audit questions with the licensee and identify any additional information or clarifications that is necessary for the licensee to supplement its application for the staff to reach a licensing decision.
3.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT The NRC audit team will require access to personnel knowledgeable in all aspects of the LAR, including the PRAs used to perform the risk analysis and relevant plant documentation or procedures (i.e., Fire, Internal Events, Internal Flood, Seismic) used to support the submittal.
The NRC staff requests the licensee provide the following information electronically (i.e.,
internet SharePoint) to support a remote audit. If determined that a remote audit is not feasible, at a minimum, a hardcopy and electronic copy of the following documentation should be available to the audit team on the first day of the staffs arrival for the audit onsite.
Documents All self-assessments of the PRA models, and Facts and Observations closure reports Documentation of changes to the PRA models with justification of PRA upgrades/PRA maintenance 4.0 TEAM ASSIGNMENTS The audit will be conducted by NRC staff from NRR, Division of Risk Assessment, PRA Licensing Branch-A and NRC contractors from the Pacific Northwest National Laboratories (PNNL). If the audit is conducted remotely, additional NRC staff may participate as observers, including NRR technical reviewers and project managers (PMs). The NRC audit team leader will be Karen Cotton, project manager with the Division of Operating Reactor Licensing (DORL) and the NRC technical lead will be Adrienne Brown (NRR, Reliability and Risk Analyst).
5.0 LOGISTICS The 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.
6.0 SPECIAL REQUESTS If the audit is conducted remotely, the NRC audit team will require the following to support the regulatory audit:
Access to an internet SharePoint portal to review the requested materials in Section 3.0 of this audit plan.
7.0 DELIVERABLES A regulatory audit summary will be issued 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 (Dominion Energy Virginia), Surry Power Station, Units 1 and 2, letter to, Amendment for Addition of 24-Hour Completion Time for an Inoperable Reactor Trip Braker, dated May 15, 2019 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML19143A201.
- 2. Ruland, William H., Director, NRC, Letter to Robert Bryan, Westinghouse Owners Group, Tennessee Valley Authority, Acceptance for Referencing of Topical Report WCAP-15376-P, Rev. 0, Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times, December 20, 2002, (ADAMS Accession No. ML023540534).
- 3. Excel Services for U.S. Nuclear Regulatory Commission, Technical Specification Task Force (TSTF) 411 - Surveillance Test Interval Extensions for Components of the Reactor Protection System (WCAP-15376-P), August 7, 2002 (ADAMS Accession No. ML022470164).
- 4. U. S. Nuclear Regulatory Commission, NRR Office Instruction, LIC 101, Revision 5, License Amendment Review Procedures, January 9, 2017 (ADAMS Accession No. ML16061A451).
- 5. U.S. NRC Office Instruction, LIC 111 Regulatory Audits, dated December 16, 2008 (ADAMS Accession No. ML082900195).
ML19220A555 OFFICE NRR/DORL/LSPB/PM NRR/DORL/LPL2-1 LAit NRR/DORL/LPL2-1/LA NAME VThomas KEntz KGoldstein DATE 8/13/19 08/09/19 08/13/19 OFFICE NRR/DRA/APLA/BC NRR/DORL/LPL2-1/BC NRR/DORL/LSPB/PM NAME SRosenberg MMarkley GEMiller DATE 8/13/19 8/13/19 8/13/19
