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MONTHYEARML18029A1182018-01-22022 January 2018 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Project stage: Request ML18067A0042018-03-0808 March 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action TSTF-522, Revision to Ventilation System Testing Requirements Project stage: Acceptance Review ML18092A0812018-03-26026 March 2018 Supplement to Proposed License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Project stage: Supplement ML18290A8522018-11-27027 November 2018 Issuance of Amendments 280, 263 to Revise Technical Specifications Regarding Ventilation System Surveillance Requirements in Accordance with TSTF-522 Project stage: Approval 2018-11-27
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Category:Letter
MONTHYEARML24283A0392024-10-0909 October 2024 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.D ML24281A1372024-10-0707 October 2024 ISFSI - Submittal of Cask Registration for Spent Fuel Storage 05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-24024 September 2024 Automatic Reactor Trip Due to Prni High Negative Rate IR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter ML24243A0872024-09-20020 September 2024 Response to EPA Comments Regarding the Final Site Specific Supplement to the Generic Eist for License Renewal North Anna Power Station, Units 1 and 2 IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma 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 ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York 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) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant ML24206A0902024-07-24024 July 2024 Owners Activity Report 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 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 ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 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 ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24082A2742024-03-22022 March 2024 Request for Approval of Alternative Request N1-I5-NDE-007 to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24086A4682024-03-21021 March 2024 Summary of Facility Changes, Tests and Experiments ML24005A0042024-03-18018 March 2024 Issuance of Amendment Nos. 296 and 279, Regarding Revised Emergency Plan for Relocation of the Technical Support Center 2024-09-24
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24054A0142024-04-22022 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 ML24005A0042024-03-18018 March 2024 Issuance of Amendment Nos. 296 and 279, Regarding Revised Emergency Plan for Relocation of the Technical Support Center ML22312A5502022-11-0707 November 2022 Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML22307A3172022-11-0303 November 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump ML22223A1452022-08-11011 August 2022 (Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Second 10 CFR 54.21(b) Annual Amendment ML22146A0272022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant. ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML21252A5142021-09-0909 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Rev 1, Using the Consolidated Line Item Improvement Process ML21238A2972021-08-26026 August 2021 Subsequent License Renewal Application Supplement 4 ML21126A3142021-05-0606 May 2021 Proposed License Amendment Request - Revise Primary Grade Water Isolation Time from 15 Minutes to 1 Hour Following Reactor Shutdown ML21076B0252021-03-17017 March 2021 Update to Subsequent License Renewal Application, Supplement 2 ML21035A3032021-02-0404 February 2021 (Naps), Units 1 and 2 - Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML21007A2642021-01-0707 January 2021 Proposed License Amendment Request Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A, Revision 1 ML20352A3942020-12-17017 December 2020 Proposed License Amendment Request to Change Battery Surveillance Requirements ML20090B3972020-03-26026 March 2020 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency 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 ML19086A1132019-03-18018 March 2019 Proposed License Amendment Request to Reduce Maximum EDG Steady State Voltage from 4580V to 4400V ML18334A1062018-11-19019 November 2018 Amendment for Flood Protection Dike Modification ML18092A0812018-03-26026 March 2018 Supplement to Proposed License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML18029A1182018-01-22022 January 2018 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML18025B4932018-01-16016 January 2018 Attachments 7 & 8: Surry - Proposed Changed SPS Emergency Plan Pages and Offsite Response Agency Letters of Concurrence ML18025B4912018-01-16016 January 2018 Attachments 5 and 6: North Anna - Proposed Changed to Emergency Plan Pages and Marked-Up SPS Emergency Plan Page Changes ML18025B4882018-01-16016 January 2018 Attachments 1 to 4: Proposed Consolidated Emergency Operations Facility ML18025B4852018-01-16016 January 2018 Isfsis, Surry, Units 1 and 2, and ISFSIs - Submittal of Proposed Consolidated Emergency Operations Facility ML17207A1702017-07-19019 July 2017 Proposed License Amendment Request for Spent Fuel Storage and New Fuel Storage ML17129A4512017-05-0202 May 2017 Submittal of Proposed License Amendment Request for Spent Fuel Storage and New Fuel Storage ML17129A4522016-11-30030 November 2016 Criticality Safety Evaluation Report ML15352A1082015-12-10010 December 2015 License Amendment Request to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev. 1 and NSAL-15-1 ML15147A0292015-05-22022 May 2015 Proposed License Amendment Request (Lar), TS 3.8.1 - AC Sources - Operating, Revised Surveillance Requirement ML15041A6672015-02-0404 February 2015 Proposed License Amendment Request Re Alternate Control Rod Position Monitoring ML14246A1902014-08-27027 August 2014 Proposed License Amendment Request, Clarification of Reactor Coolant System Heatup and Cooldown Technical Specification Figures ML13179A0142013-06-26026 June 2013 Proposed License Amendment Request Addition of an Analytical Methodology to Core Operating Limits Reports and an Increase to Minimum Temperature for Criticality ML13179A0152013-05-31031 May 2013 Units I and 2, Qualification of the ABB-NV and Wlop CHF Correlations in the Dominion VIPRE-D Computer Code ML13064A3522013-02-22022 February 2013 Proposed License Amendment Request (LAR) Control Bank Sequence and Overlap Limit Action ML12356A2982012-12-13013 December 2012 Supplemental Information for Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process. ML12283A0692012-09-27027 September 2012 ISFSIs and Surry, Units 1 and 2 and ISFSIs Proposed Emergency Action Level Revisions ML12219A0722012-07-30030 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12136A4512012-05-11011 May 2012 Proposed License Amendment Request - Temporary Change to Allow Two Inoperable Demand Position Indicators Per Control Bank ML1111900932011-04-27027 April 2011 License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation. ML1029804472010-10-21021 October 2010 Proposed License Amendment Request (LAR) Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA) ML1012605172010-05-0606 May 2010 Proposed License Amendments and Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding ML1009001632010-03-30030 March 2010 Proposed License Amendment Request Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) ML1009001672010-03-30030 March 2010 Marked-Up Technical Specification Bases Page Changes ML0933602472009-11-20020 November 2009 Request for Approval of Cyber Security Plan ML0927304682009-09-28028 September 2009 Proposed License Amendment Request, TS 3.7.12 - ECCS Pump Room Exhaust Air Cleanup System (Preacs) Addition of Conditions/Action Statements ML0920503812009-07-23023 July 2009 License Amendment Request, One Time Extension of the Completion Time for 1 J - 480 Volt AC Distribution Subsystem ML0909000552009-03-26026 March 2009 License Amendment Request, Measurement Uncertainty Recapture Power Uprate ML0909102652009-03-26026 March 2009 License Amendment Request on Measurement Uncertainty Recapture Power Uprate ML0904004652009-02-0606 February 2009 License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Work Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0902102792009-01-15015 January 2009 Proposed License Amendment Request TS 3.7.12 - ECCS Pump Room Exhaust Air Cleanup System (Preacs) Addition of Conditions/Action Statements 2024-04-22
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection ML23346A0972023-12-11011 December 2023 License Amendment Request to Revise the Emergency Plan Relocation of the Technical Support Center - Response to NRC Request for Additional Information 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 ML23136A8832023-05-16016 May 2023 Responses to Request for Additional Information and Request for Confirmation of Information Regarding Environmental Review of Subsequent License Renewal Application L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23103A2752023-04-13013 April 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request for Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML23089A3542023-03-30030 March 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI ML22115A1752022-04-25025 April 2022 ASME Section XI Inservice Inspection Program - Relief Request N2-14-LMT-004 - Fourth Interval Third Period Limited Examinations - Response to Request for Additional Information ML21350A4082021-12-16016 December 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Genera Tor Tube Inspections, Rev 1, Using the Consolidated Line-Item Improvement Process Response to RAI ML21341B4372021-12-0606 December 2021 (Naps), Units 1 and 2 - Subsequent License Renewal Application Responses to NRC Request for Additional Information Safety Review - Set 5 ML21258A3542021-09-15015 September 2021 (Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Confirmation of Information Set 2 Safety Review ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21210A3962021-07-29029 July 2021 (Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 4 and Supplement 3 ML21147A2932021-05-27027 May 2021 (Naps), Units 1 and 2 Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 3 and Administrative Change to SLRA Table A4.0-1, Item 25 ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21126A3152021-05-0606 May 2021 Proposed License Amendment Request to Battery Surveillance Requirements - Response to Request for Additional Information ML21119A2872021-04-29029 April 2021 (Naps), Unit 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 2 and Flow Accelerated Corrosion Program Enhancement Completion ML21091A1872021-04-0101 April 2021 Response to NRC Request for Additional Information Regarding Safety Review - Set 1 & Clarification to Aging Management of Fire Protection System Lined Ductile Iron Valves ML21084A1822021-03-24024 March 2021 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information for the Safety Review - Set 1 ML21056A5572021-02-25025 February 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Final Supplemental Response ML21053A4332021-02-22022 February 2021 (Naps), Units 1 and 2 - Subssequent License Renewal Application (SLRA) Environmental Review - Response to NRC Request for Additional Information ML21042B9042021-02-11011 February 2021 Subsequent License Renewal Application, Response to NRC Requests for Confirmation of Information for the Environmental Review ML21033A3022021-01-25025 January 2021 (NAPS) Units 1 and 2 - Subsequent License Renewal Application (SLRA) - Provides Requested Documents in Response to Environmental Audit. Part 1 of 2 ML21022A1752020-12-16016 December 2020 Steam Generator Tube Inspection Report RAI Response ML20296A6672020-10-22022 October 2020 ASME Section XI Inservice Inspection Program Proposed Inservice Inspection Relief Request N1-I4-LMT-003 Response to Request for Additional Information ML20296A7272020-10-22022 October 2020 Stations Units 1 & 2 - Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break LOCA Supplement to the Response to Request for Additional Information ML20268B1872020-09-24024 September 2020 ASME Section XI Inservice Inspection Program, Proposed Inservice Inspection Alternative N1-I5-NDE-002, Response to Request for Additional Information ML20156A2872020-06-0404 June 2020 Inservice Testing Program Plan for Pumps, Valves, and Snubbers Fifth 10-Year Interval Update for Units 1 & 2 Request for Alternatives to Requirements of ASME OM Code - Response to RAI ML20149K6942020-05-28028 May 2020 Response to Request for Additional Information, to Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident ML20140A3362020-05-18018 May 2020 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules - Response to Request for Additional Information ML20021A0052020-01-17017 January 2020 Inservice Testing Program Request for Alternative to Requirements of ASME OM Code Relief Request P-9, Response to Request for Additional Information ML19249B7672019-08-29029 August 2019 Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs ML19248B7622019-08-22022 August 2019 Supplement to Proposed License Amendment Request - Flood Protection Dike Modification - Response to Onsite Audit Questions ML19225D1302019-08-0808 August 2019 Response to Request for Additional Information (Follow-Up) Regarding Open Phase Protection Per NRC Bulletin 2012-01 - Proposed License Amendment Request ML19196A1102019-07-0909 July 2019 Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages ML19156A2072019-05-24024 May 2019 Response to Request for Additional Information on Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01 ML19071A1142019-03-0707 March 2019 Response to 03/12/2012 Information Request, Seismic Probabilistic Risk Assessment Supplement for Recommendation 2.1 ML18267A0682018-09-18018 September 2018 Attachment - Response to Request for Clarification on Proposed Consolidated Emergency Operations Facility License Amendment Requests ML18257A2272018-09-14014 September 2018 SPRA (Fukushima 50.54f) Audit (Clarification) Questions - Plant Response ML18169A2262018-06-13013 June 2018 Attachment 1 - Response to Request for Additional Information ML18169A2272018-06-13013 June 2018 Attachment 3 - Proposed NAPS Emergency Plan Changes ML18093A4452018-03-28028 March 2018 Ad 2, Response to 03/12/2012 Information Request Seismic Probabilistic Risk Assessment for Recommendation 2.1 ML18092A0812018-03-26026 March 2018 Supplement to Proposed License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML18037A7042018-01-31031 January 2018 Response to Request for Additional Information Regarding Proposed License Amendment Request for Spent Fuel Storage and New Fuel Storage ML17354A1602017-12-14014 December 2017 Response to March 12, 2012 Information Request Spent Fuel Pool Seismic Evaluation for Recommendation 2.1 ML17241A0452017-08-24024 August 2017 Proposed ISI Alternatives NI-14-NDE-010 and N2-14-NDE-005 Reactor Pressure Vessel Nozzle Weld Inspections Response to Request for Additional Information ML17171A2302017-06-14014 June 2017 Response to Request for Additional Information ASME Section XI Inservice Inspection Program Request for Proposed Alternative N1-I4-009 and N2-I4-NDE-004 ML17065A2502017-02-28028 February 2017 & Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Response to Request for Referenced Information Related to RAIs 2-2, 3-5, and 3-8 2024-03-25
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10 CFR 50.90 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 26, 2018 United States Nuclear Regulatory Commission Serial No.18-123 Attention: Document Control Desk NRNDEA R1 Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 VIRGINIJ!l ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SUPPLEiVIENT TO PROPOSED LICENSE AMENDMENT REQUEST TO REVl:SE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-522, REVISE \/ENTILATION SYSTEM SURVEILLANCE REQUIREMENTS TO OPERATrE FOR 10 HOURS PER MONTH By letter dated January 22, 2018 (ADAMS Accession No. ML18029A118), Virginia Electric and Powar Company (Dominion Energy Virginia) submitted a proposed license amendment request (LAR) to modify the Technical Specifications (TS) for North Anna Power Station (NAPS) Units 1 and 2, to operate ventilation systems with charcoal filters for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> each month in accordance with Technical Specifications Task Force traveler 522 (TSTF-522),
Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Month." The NRC staff determined that the information provided in the LAR is not of sufficient detail to enable the NRC staff to proceed with its detailed technical review regarding the acceptability of the proposed LAR.
On March 7, 2018, a telecom was held between the NRC and Dominion to discuss the Acceptamce Review Findings and a LAR Supplement schedule related to the proposed LAR.
As discussed during the telecom, a change to the Ventilation Filter Testing Program (VFTP) was not proposed in TSTF-522, nor evaluated by the staff in making TSTF-522 available for adoption. Therefore, the NRC staff requested justification be provided in the LAR supplement for the proposed increase in relative humidity from 70% to 95% for the testing of the Main Control Room I Emergency Switch Gear Room Emergency Ventilation System in TS 5.5.1 O.c., and the corresponding removal of the requirement to have the ventilation system heaters operating in SR 3.7.10.1. In addition, the NRC staff requested the LAR supplement include a revision, as necessary, to the proposed no significant hazards consideration evaluation that fully addresses the proposed changes to the VFTP, in addition to the changes endorsed in TSTF-522. A submittal date of March 26, 2018 was agreed upon for the LAR supplement.
By letter dated March 8, 2018, the NRC formally provided Dominion an opportunity to supplement the proposed LAR identified above. provides Dominion Energy Virginia's response to NRC's request for supplemental Information.
Serial No.18-123 Docket Nos. 50-338/339 Supplemental Response Proposed Amendment to Adopt TSTF-522 Page 2 of 3 If you have any questions or require additional information, please contact Ms. Diane E.
Aitken at (804) 273-2694.
Sincerely, Mark Sartain Vice President Nuclear Engineering and Fleet Support Attachments
- 1. Supplemental Response, Proposed License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 This letter contains no NRC commitments.
COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by M. D. Sartain who is Vice President - Nuclear Engineering and Fleet Support of Virginia Electric and Power Company. 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.
Acknowled!Jed before me this ~ a y of &Cb , 2018.
My Commi,ssion Expires: &, 31 ZO/R. 1
~-t~ Notary Public
Serial No.18-123 Docket Nos. 50-338/339 Supplemental Response Proposed Amendment to Adopt TSTF-522 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission Re.gion II Marquis One Tower 24fi Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glem Allen, Virginia 23060 NRC Senior Resident Inspector North Anna Power Station Mr. James R. Hall NRC Senior Project Manager-North Anna U. S. Nuclear Regulatory Commission One White Flint North Maiil Stop 0-8 G9A 11555 Rockville Pike Ro.ckville, Maryland 20852-2738 Ms. K. R. Cotton-Gross NRC Project Manager-Surry U. S. Nuclear Regulatory Commission One White Flint North Madi Stop 0-8 G9A 11 :555 Rockville Pike Rockville, Maryland 20852
Serial No.18-123 Docket Nos. 50-338/339 Supplemental Response Proposed Amendment to Adopt TSTF-522 Page 1 of 6 ATTACHMENT 1 SUPPLEMENTAL RESPONSE PROPOSED LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-522 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
NORTH ANNA POWER STATION UNITS 1 AND 2
Serial No.18-123 Docket Nos. 50-338/339 Supplemental Response Proposed Amendment to Adopt TSTF-522 Attachment 1 - Page 2 of 6 Supplemental Response Pro1posed License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 By letter dated January 22, 2018 (ADAMS Accession No. ML18029A118), Virginia ElectriG and Power Company (Dominion Energy Virginia) submitted a proposed license amendlment request (LAR) to modify the Technical Specifications (TS) for North Anna Power Station (NAPS) Units 1 and 2, requirement to operate ventilation systems with charcoal filters for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> each month in accordance with Technical Specifications Task Force traveler 522 (TSTF-522), Revision 0, "Revise Ventilation System Surveilllance Requirements to Operate for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Month." The NRG staff determined that the information provided in the LAR is not of sufficient detail to enable the NRG staff to proceed with its detailed technical review regarding the acceptability of the proposed LAR.
By letter dated March 8 2018, the NRG provided Dominion an opportunity to supplement the proposed LAR as follows:
NRC INFORMATION REQUEST NO. 1 Dominion should supplement the application to provide a detailed discussion and justification of the proposed VFTP changes because the LAR does not provide this level of detail and a change to the VFTP was not proposed by the TSTF in TSTF-522, nor evaluated by the staff in making TSTF-522 available for adoption. Specifically, the increase in relative humidity from 70% to 95% for the testing of the MCR/ESGR EVS in TS 55.1 O.c., and the corresponding removal of the requirement to have the heaters operaUng in SR 3.7.10.1, should be explicitly addressed and justified.
DOMINION RESPONSE The Main Control Room (MGR) / Emergency Switchgear Room (ESGR) Emergency Ventilation System (EVS) provides a protected environment from which occupants can control the unit following an uncontrolled release of radioactivity, hazardous chemicals, or smoke. The MCR/ESGR EVS consists of four 100% capacity redundant trains (2 per unit) that can filter and recirculate air inside the MCR/ESGR envelope or supply filtered makeup air to the MCR/ESGR envelope, and a MCR/ESGR boundary that limits the in-leakage of unfiltered air. Each train consists of a heater, demister filter, a high efficiency particulate air (HEPA) filter, an activated charcoal adsorber section for removal of gaseous activity (principally iodines), and a fan. The sole purpose of the heaters, powere~d from the emergency buses, is to maintain the relative humidity below 70%.
Domini:on Energy Virginia proposes to increase the relative humidity specified in Technical Specification (TS) 5.5.10.c for the MCR/ESGR EVS from 70% to 95% and
Serial No.18-123 Docket Nos. 50-338/339 Supplemental Response Proposed Amendment to Adopt TSTF-522 Attachment 1 - Page 3 of 6 remov1~ the operability and surveillance requirements for the associated heaters from Technical Specifications 3.7.10.1 and TS 5.5.10.e, respectively.
Technical Specification (TS) 5.5.1 O.c, Ventilation Filter Testing Program (VFTP) for the MCR/ESGR EVS, is currently performed in accordance with ASTM 03803-1989, "Standard Test Method for Nuclear Grade Activated Carbon," at a relative humidity of 70%, as specified. Based on guidance provided in ASTM 03803-1989, an increase in the relative humidity (RH) from 70% to 95% increases the amount of methyl iodide penetration. Specifically, at 70% RH, the average penetration is 0.10% +/- NA and at 95% relative humidity; the average penetration is 0.56% +/- 11 %. Although removal of the heaters and subsequent escalation in RH increases the charcoal methyl iodide penetration, the acceptance criterion for methyl iodide penetration of 2.5% specified in TS 5.5.10.c will continue to be met. The North Anna radiological accident analysis of record (AOR) assumes MCR/ESGR EVS methyl iodide filter efficiency of 95%.
Therefore, the North Anna radiological AOR filter efficiency assumptions, without crediting the heaters, is not affected and a safety factor of at least 2 is maintained in the Technical Specification acceptance criterion.
Additionally, removal of the heaters will reduce the electrical loading on the emergency diesel generators, thereby increasing the margin to the design load limit for each diesel genera1tor.
NRC /JVFORMATION REQUEST NO. 2 Similarly, Dominion should review and revise, as necessary, the proposed no significant hazards consideration evaluation provided in the LAR, to ensure that the evaluation fully addresses the proposed changes to the VFTP, in addition to the changes endorsed in TSTF-1522.
DOMIMION RESPONSE No SigJnificant Hazards Consideration By letter dated January 22, 2018 (ADAMS Accession No. ML18029A118), Virginia Electric and Power Company (Dominion Energy Virginia) requests adoption of an approved change to the standard technical specifications {STS) and plant specific Technical Specifications (TS), to revise TS 3.7.10, "Control Room Emergency Filtration System (MCR/ESGR EVS)," and TS 3.7.12, "Emergency Core Cooling System (ECCS)
Pump Room Exhaust Air Cleanup System (PREACS)," in the STS for Westinghouse plants (NUREG-1431) from operating the MCR/ESGR EVS and ECCS PREACS with the electric heaters for a continuous 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> period every 31 days to require operation of the systems for 15 continuous minutes every 31 days. The proposed amendment is consist,ent with Technical Specifications Task Force traveler 522 (TSTF-522), Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Month." In addition, Dominion Energy Virginia requests an increase to the relative
Serial No.18-123 Docket Nos. 50-338/339 Supplemental Response Proposed Amendment to Adopt TSTF-522 Attachment 1 - Page 4 of 6 humidity specified in Technical Specification (TS) 5.5.1 O.c for the MCR/ESGR EVS from 70% to 95% and removal of the operability and surveillance requirements for the associated heaters from Technical Specifications 3.7.10.1 and TS 5.5.10.e, respectively. An administrative change is also being made to the Environmental Protection Plan (EPP) as part of this change to reflect current code numbering. As discussed below, the TSTF has evaluated whether or not a significant hazards consideration is involved with the proposed generic change by focusing on the three standa.rds set forth in 10 CFR 50.92, "Issuance of amendment." Likewise, Dominion Energy Virginia has evaluated whether or not a significant hazards consideration is involved with the proposed increase in RH specified in TS 5.5.1 O.c.:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No These systems are not accident initiators. The proposed changes do not change any of the previously evaluated accidents in the Updated Final Safety Analysis Report (UFSAR) and therefore, these changes do not involve a significant increase in the probability of an accident. The proposed system and filter testing changes are consistent with ASTM 03803-1989 for these systems and will continue to assure that these systems perform their design function of mitigating accidents via filtration. The proposed change does not change the conclusions of the NAPS radiological accident analysis of record (AOR) and the safety factor of at least 2 is maintained in the TS acceptance criterion for methyl iodide penetration. Thus the change does not involve a significant increase in the consequences of an accident.
The proposed change modifies existing SRs to operate the ECCS PREACS Systems equipped with electric heaters and the MCR/ESGR EVS for a continuous 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> period every 31 days with a requirement to operate the systems for 15 continuous minutes every 31 days with heaters operating, if needed. In addition, it is proposed to remove the electrical heater output test in the VFTP (TS 5.5.1 O.e) and make a corresponding change to the charcoal filter testing (TS 5.5.10.c) to require testing be conducted at a humidity of at least 95%
RH. The proposed change does not increase the likelihood of a malfunction of an SSC. The result of this change will be the eventual removal of un-needed equipment. Since the equipment is not needed and the removal will make the system less complex, the probability of a malfunction of the MCR/ESGR EVS is not significantly increased .
.Additionally, the removal of the post-accident electrical load associated with the MCR/ESGR EVS heaters reduces the electrical load on the emergency diesel
Serial No.18-123 Docket Nos. 50-338/339 Supplemental Response Proposed Amendment to Adopt TSTF-522 Attachment 1 - Page 5 of 6 generators. This will provide additional margin regarding the capability of emergency power.
The change to the EPP is administrative in nature to reflect approved NRG references (codes).
Therefore, it is concluded that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The MCR/ESGR EVS and ECCS PREACS are accident response systems and as such, do not cause or initiate accidents. The proposed change for these ventilation systems does not functionally change the design or operation of these systems. The deletion of the heater operability and surveillance requirements for the MCR/ESGR EVS is based on the heaters not being needed for mitigation of any accident condition and does not significantly affect the operation of these systems. These systems will continue to meet the functional requirements in the current radiological accident analysis of record (AOR) for NAPS and maintain calculated dose consequences within acceptable limits. Testing requirements will be revised and will continue to demonstrate that the Limiting Conditions for Operation are met and the system components are capable of performing their intended safety functions. The proposed change does not create new failure modes or mechanisms and no new accident precursors are generated.
The change to the EPP is administrative in nature to reflect approved NRG references (codes).
Therefore, it is concluded that this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The removal of the MCR/ESGR EVS heaters will result in a reduction in the efficiency of the charcoal absorber due to the removal of the humidity reduction affect. The proposed increase to 95% RH during the required testing of the MCR/ESGR EVS charcoal filters compensates for the function of the heaters, which was to reduce the humidity of the incoming air to below the currently-
- specified value of 70% RH for the charcoal. These changes are bounded within
Serial No.18-123 Docket Nos. 50-338/339
.. Supplemental Response Proposed Amendment to Adopt TSTF-522 Attachment 1 - Page 6 of 6 the assumptions of the AOR. The removal of the heaters does not alter the safety margins contained in the radiological accident analysis. The charcoal absorber sample laboratory testing protocol accurately demonstrates the required performance of the absorbers in the MCR/ESGR EVS and ECCS PREACS following a design basis accident. These testing standards ensure adequate margin exists and that the charcoal will perform its design basis function. The offsite and control room dose analyses of record are not affected by this change.
Furthermore, deletion of the heater op~rability and surveillance requirements for the MCR/ESGR EVS will allow the MCR/ESGR EVS heaters to be permanently de-energized. This will result in an increase in the margin between the post-accident calculated load and the load limitation on the emergency diesel generators.
The change to the EPP is administrative in nature to reflect approved NRC references (codes).
Therefore, it is concluded that this change does not involve a significant reduction in a margin of safety.
Based on the above, Dominion Energy Virginia concludes that the proposed change presents no significant hazards considerations under the standards set forth in 10 CFR 50.92(G), and, accordingly, a finding of "no significant hazards consideration" is justified.