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Category:Letter
MONTHYEARML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20244032024-10-0303 October 2024 Cyber Security Inspection Report 05000280-2024403 and 05000281-2024403 Cover Letter (Public) IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection 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) 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 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 ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign 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 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 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report 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 ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24115A1952024-04-24024 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 ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 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 ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 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 2024-09-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information 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 ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to 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 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 ML23096A1972023-04-0606 April 2023 License Amendment Request - Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure - Response to Request for Additional Information 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 ML23044A0392023-02-11011 February 2023 Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request for Additional Information ML23025A1252023-01-25025 January 2023 Response to Request for Additional Information License Amendment Request, NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure ML22343A0002022-12-0909 December 2022 Response to Request for RAI on ASME Operation & Maintenance Code Inservice Testing Program - Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML22342A4242022-12-0707 December 2022 Response to 3/12/2012 Request for Information Enclosure 2, Recommendation 2.0, Flooding Focused Evaluation Integrated Assessment Submittal Revised Commitment Completion Date 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 ML22300A1882022-10-27027 October 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information ML22220A2162022-08-0808 August 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability Supplemental Information ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit 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 ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis 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 ML21098A2612021-04-0808 April 2021 Subsequent License Renewal Application, Response to Request for Additional Information Re Environmental Review ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification ML21056A5412021-02-25025 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 ML21042B9262021-02-11011 February 2021 ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative Requests S1-I5-ISl-05 and S2-I5-ISl-06 - Response to Request for Additional Information ML22040A1012021-02-0909 February 2021 Response to Request for Additional Information 2021 Steam Generator Inservice Report 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 ML20247J6352020-09-0303 September 2020 Virginia Electric & Power Co - Subsequent License Renewal Application (SLRA) Environmental Review, Response to Request for Additional Information Concerning Aquatic Resources ML20181A4222020-06-29029 June 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Response to Request for Additional Information ML20181A3082020-06-23023 June 2020 Response to Request for Additional Information on 2019 Steam Generator Inservice Inspection Report ML20269A4072020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 2 of 3 ML20269A4062020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 3 of 3 ML20269A4082020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 1 of 3 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 ML20034F0532020-01-31031 January 2020 Proposed License Amendment Request: Allowed Outage Time Extension for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Response to Request for Clarification and Additional Information 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 ML19283B6222019-10-10010 October 2019 Subsequent License Renewal Application Safety Review - Documentation of Draft Third Round Requests for Additional Information ML19291B0342019-10-0101 October 2019 Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal ML19269B7342019-09-19019 September 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Sets 3 and 4 Revised SLRA Mark-Ups ML19267A0422019-09-16016 September 2019 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information Set 2 ML19253B3302019-09-0303 September 2019 Response to Requests for Additional Information - Sets 3 and 4 - Subsequent License Renewal Application 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 ML19204A3572019-07-17017 July 2019 Subsequent License Renewal Application Response to Request for Additional Information - Set 2 ML19198A0592019-07-11011 July 2019 Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information 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 ML19183A3862019-06-27027 June 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Set 1 ML19148A4212019-05-10010 May 2019 All Enclosures with Coversheets ML18304A3302018-10-25025 October 2018 Proposed License Amendment Request TSTF-490 & Update of Alternative Source Term Analyses Response to Request for Additional Information & Revised Proposed Technical Specifications ML18302A1212018-10-18018 October 2018 Response to Request for Additional Information, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML18303A2882018-10-18018 October 2018 Response to Request for Additional Information Regarding Relief Request S2-I5-LMT-P01 Examination Category R-A, Preservice Weld Examinations 2024-05-07
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e Vreo1NIA ELECTRIC AND PowER CoMPANY RICHMOND, VIRGIN IA 23261 April 14, 1978,
- Mr. Edson G. Case, Acting Director Serial No. 614A/121577 Office of Nuclear Reactor Regulation PO&M/DLB:das U. S. Nuclear Regulatory Conunission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 DPR-37
Dear Sir:
In response to your request of December 15,.1977, completed questionnaires on Standby Diesel Generators were forwarded in our letter of January 23, 1978.
Two completed questionnaires *were forwarded; one for Surry Unit Nos. 1 and 2 and one for North Anna Unit No. 1. In the questionnaire for Surry Unit Nos. 1 and 2, seven items were not filled in due to unavailability of data. The missing information has been obtained and is included in the attachment to this letter.
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e e Attachment QUESTIONNAIRE FOR NUCLEAR REGULATORY co~~IISSION RELIABILITY STUDY OF STANDBY DIESEL GENERATOR UNITS SURRY POWER STATION UNIT NOS. 1 AND 2 The following information was not available at the time of our January 23, 1978 submittal. Item numbers used are from the original questionnaire.
Item B.2 (p2): "Minii.'Illilil air tank pressure for cranking: 90 psig ItemB.2 (p3): "What is air pressure drop from air tank to engine during cranking?" 28 psi 11 Item B.2 (p4): What is the time required to recharge one air tank?"
35 minutes from 50 psig to 210 psig.
NOTE: Where questionnair~! refers to air "tank" we have interpreted this to mean "bank". Each engine has two independent "banks" consisting of three "tanks" ..
Item D .4a (p7): "Normal operating (oil) pressure: 75 psi.
Item L.3.a (pl4): "Equilibrium (lube oil pressure): 75 psi.
Item 0.3.a.b (pl7): " ... maximum speed surge when starting;" 965. rpm.
NOTE: Frequency meter is not functional on starting and tachometer is not normally observed during start. The figure reported is the result of observation of one start.
Item Q.5 (p18): Inside switch gear hottest (Temperature): 85°F with ambient temperature 72.
NOTE: Switchgear, voltage regulator and exciter are in the same cabinet.