Letter Sequence Other |
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MONTHYEARML0910401472009-04-13013 April 2009 Proposed License Amendment Request Correction to Technical Specification Table 3.7-1 Operator Action 3.b Project stage: Request ML0923005202009-08-20020 August 2009 RAI, License Amendment Request Regarding Correction to TS Table 3.7-1 Operator Action 3.b Project stage: RAI ML1001405592010-02-26026 February 2010 License Amendment, Correction of Technical Specification Table 3.7.1 Operator Action 3.b Project stage: Other 2009-08-20
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Similar Documents at Surry |
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Category:Letter
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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] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23312A1922024-01-18018 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 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 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 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 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 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 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) - 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Request to Revise Technical Specifications Section 3.16 Emergency Power System Regarding a Temporary 21 Day Allowed Outage Time 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... 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[Table view] Category:Safety Evaluation
MONTHYEARML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure 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) 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 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes 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 ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23061A0122023-05-0909 May 2023 Issuance of Amendment Nos. 312 and 312, Regarding Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 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 ML23102A2832023-04-25025 April 2023 ASME OM 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 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 ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) 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 ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD 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 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 ML21201A1172021-08-0606 August 2021 Proposed Alternative Requests S1-I5-ISI-05 and S2-I5-ISI-06 to Eliminate Examination of Threads in Reactor Pressure Vessel Flange ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 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 ML20321A2322020-11-20020 November 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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 ML20252A0072020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI 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 ML20115E3522020-05-12012 May 2020 Alternative Request S2-I5-ISI-05 ASME Section XI Inservice Inspection Program Proposed Alternative Request to Use a Mechanical Clamping Device for a One-Inch Main Steam Line Repair 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 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 ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 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) ML19043A8242019-03-15015 March 2019 Relief Requests Examination Coverage for Pressurizer Nozzle Inner Radius Sections and Certain Stainless Steel Piping Welds (S2-15-LMT-CO1 and S2-15-LMT-P01) ML18331A0602019-02-28028 February 2019 Relief Requests Regarding Examination Coverage for Pressurizer Nozzle Inner Radius Section and Certain Stainless Steel Piping Welds (S1-I5-LMT-C01 and S1-I5-LMT-P01) ML19031B2272019-02-27027 February 2019 Issuance of Amendment Nos. 281, 264, 294, and 294 to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes ML18318A0622018-12-10010 December 2018 Review of Reactor Vessel Material Surveillance Capsule Withdrawal Schedules (CAC Nos. MG0098 and MG0099; EPID L-2017-LLL-0021) 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 ML18236A2362018-09-26026 September 2018 Relief from the Requirements of the ASME Code - Proposed Alternatives S1-I5-ISI-04 and S2-I5-ISI-04 ML18225A0202018-08-29029 August 2018 ISFSI; North Anna 1 & 2 Isfsls, and Unit 3; Surry Power 1 & 2, and Isfsls); Dominion Energy Kewaunee, Inc. (Kewaunee Power Station and Isfsi): Request for Threshold Determination Under 10 CFR 50.80 ML18166A3292018-06-29029 June 2018 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency 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) ML18019A1952018-01-24024 January 2018 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination (CAC Nos. MF9923, MF9924, MF9925, MF9926, MF9927, and MF9928; EPID L-2017-LLR-0060) ML17303A0682017-12-20020 December 2017 Nonproprietary Relief from the Requirements of the ASME Code (CAC Nos. MF8987 and MF8988; EPID L-2016-LLR-0019) ML17332A0782017-12-12012 December 2017 ISFSI; Millstone and ISFSI; North Anna and ISFSI; Surry and ISFSI - Request for Approval of Revision 24 of the Nuclear Facility Quality Assurance Program Description Topical Report, DOM-QA-1 (CAC Nos. MF9732-MF9739; EPID L-2017-LLQ-0001) ML17242A0142017-10-19019 October 2017 Clarification of Issuance of Amendments Changes to Expand Primary Grade Water Lockout Requirements in Technical Specification 3 2.E 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 2024-01-18
[Table view] Category:Technical Specifications
MONTHYEARML23136B1392023-06-29029 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 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 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 ML21277A0652021-09-30030 September 2021 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer 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 ML21106A2792021-05-0404 May 2021 Technical Specifications 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 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 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 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) ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML14169A3592014-08-12012 August 2014 Stations, Units 1 and 2, Issuance of Amendments Regarding Addition of an Analytical Methodology to the Core Operating Limits Reports and an Increase to the Surry Minimum Temperature for Criticality ML14148A2352014-07-0303 July 2014 Issuance of Amendment to Extend the Containment Type a and Type C Leak Rate Test Frequency ML13260A2502013-09-0909 September 2013 Proposed License Amendment Request Regarding Relocation of Snubber Surveillance Requirements from Technical Specifications 4.17 to Snubber Program - Supplement ML12279A2822012-09-26026 September 2012 Proposed License Amendment Request Regarding Temporary Service Water Jumper to the Component Cooling Heat Exchangers ML12222A3402012-07-31031 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 ML12109A2702012-04-17017 April 2012 Issuance of Amendments Regarding Virginia Electric and Power Company License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair ML12081A0162012-03-14014 March 2012 Supplemental Response to Request for Additional Information Related to License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair ML1106602302011-03-0404 March 2011 Supplemental Information &Typed TS Pages for Proposed License Amendment Request Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirement to Licensee Controlled Program (Adoption of TSTF-425, Rev 3) ML1035502062010-12-16016 December 2010 Proposed Technical Specification Change Temporary Alternate Repair Criteria for Steam Generator Tube Repair for Unit 2 ML1030502732010-11-0202 November 2010 Correction to Amendment Regarding Technical Specification Revisions Related to the Measurement Uncertainty Recapture (Mur) Power Uprate ML1027203442010-09-28028 September 2010 Attachment 2 to Email Regarding Typed Page 2.3-2 for Surry Dnbcolr LAR ML1013106042010-05-0606 May 2010 License Amendment Request Revised Cumulative Core Burnup Applicability Limit for Heatup and Cooldown Curves, Low Temperature Overpressure Protection System Setpoint, and Ltops Enable Temperature ML1001405592010-02-26026 February 2010 License Amendment, Correction of Technical Specification Table 3.7.1 Operator Action 3.b ML0929606162009-10-16016 October 2009 Proposed License Amendment Request Relocation of Core Operating Limits to the Core Operating Limits Report (COLR) and Addition of COLR References ML0910401472009-04-13013 April 2009 Proposed License Amendment Request Correction to Technical Specification Table 3.7-1 Operator Action 3.b ML0822500262008-09-17017 September 2008 Units, 1 and 2, Tech Spec Pages for Amendments 261 and 261 Regarding the Revision to Various Setting Limits and the Overtemperature T/Overpower T Time Constants ML0817506992008-07-0707 July 2008 Tech Spec Pages for Amendments 260 & 260 Regarding Control Room Habitability ML0814200442008-06-17017 June 2008 Tech Spec Pages for Amendments 259 and 259, Regarding the Increase of Maximum Service Water Temperature Limit from 95 F to 100 F ML0813401152008-05-16016 May 2008 Technical Specifications - Issuance of Exigent Amendment Regarding Interim Alternate Criteria for Steam Generator Tube Repair ML0810800442008-04-14014 April 2008 Proposed License Amendment Request, Interim Alternate Repair Criteria (Iarc) for Steam Generator (SG) Tube Repair ML0810211952008-04-11011 April 2008 Proposed License Amendment Request Revised Setting Limits and Overtemperature T/Overpower T Time Constants Response to Request for Additional Information (RAI) ML0809402872008-04-0202 April 2008 Proposed License Amendment Request Revision of Technical Specifications Design Features ML0802401202008-01-23023 January 2008 Tech Spec Pages for Amendments 258 and 257 Regarding Replacement of Main Control Room and Emergency Switchgear Room Air-Conditioning System Chilled Water Piping ML0735505992007-12-19019 December 2007 Units, 1 and 2, Tech Spec Pages for Amendments 257 and 256 Regarding Increase in Lead Rod Average Burnup Limit ML0733212712007-11-28028 November 2007 Proposed Additional Technical Specifications Change, Operable Definition Modification for Air Handling Units While in Temporary 45-day Allowed Outage Times to Perform Required Surveillances ML0732306102007-11-15015 November 2007 Technical Specifications for Surry, Units 1 and 2, Issuance of Amendments Use of Gothic Code for Recirculation Spray System Exigent Circumstances ML0729004772007-10-15015 October 2007 Technical Specifications, Revised Technical Specification Surveillance Requirement for the Inspection of the Containment Recirculation Sump (Tac Nos. MD3168 and MD3169) ML0724906142007-09-0606 September 2007 Technical Specifications, Issuance of Amendments Regarding Use of Westinghouse Best-Estimate Large Break Loss-of-Coolant (TAC Nos. MD3609 & MD3610) ML0723300982007-08-20020 August 2007 Proposed License Amendment Request Control Room Habitability Supplemental Response ML0719703012007-07-13013 July 2007 Proposed License Amendment Request Consolidated Line Item Improvement Process Technical Specification Improvement Control Room Habitability ML0712402632007-05-0303 May 2007 Technical Specifications, Issuance of Amendments Regarding Missed Surveillance Requirements TSTF-358 (TAC Nos. MD4206 & MD4207) ML0709200372007-03-29029 March 2007 Tech Spec Pages for Amendments 251 and 250 Regarding Steam Generator Tube Integrity ML0703201782007-01-31031 January 2007 Proposed Technical Specifications Change Missed Surveillance Requirements ML0701906552007-01-19019 January 2007 Proposed License Amendment Request Consolidated Line Item Improvement Process Technical Specification Improvement Regarding Steam Generator Tube Integrity Response to Request for Additional Information ML0630000242006-10-12012 October 2006 Tech Spec Pages for Amendments 250 and 249 Regarding Implementation of Generic Safety Issue 191 ML0627702082006-10-0303 October 2006 Proposed License Amendment Request Containment Sump Inspection Surveillance ML0622301142006-08-10010 August 2006 Technical Specifications, Issuance of Amendments Regarding Change to Exclusion Area Boundary, MC8315 & MC8316 ML0618607302006-07-0505 July 2006 Proposed Technical Specifications Change Revision of Main Control Room and Emergency Switchgear Room Air Conditioning System Requirements 2023-06-29
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 26, 2010 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENT REGARDING REQUEST TO CORRECT TECHNICAL SPECIFICATION TABLE 3.7.1 OPERATOR ACTION 3.b (TAC NOS. ME1068 AND ME1069)
Dear Mr. Heacock:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 268 to Renewed Facility Operating License No. DPR-32 and Amendment No. 267 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2 (Surry Units 1 and 2), respectively. The amendments change the Technical Specifications (TSs) in response to your application dated April 13, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091040147).
These amendments revise the TSs of Surry Units 1 and 2. The proposed change revises TS Table 3.7.1, Operator Action 3.b, and provides direction for the actions to be taken if the operating condition of fewer than the required minimum channels for the neutron flux intermediate range occurs between 7 percent and 11 percent of rated power.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
(~/1Y.( C;:ft l-C Karen Cotton, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegUlation Docket Nos. 50-280 and 50-281
Enclosures:
- 1. Amendment No. 268 to DPR-32
- 2. Amendment No. 267 to DPR-37
- 3. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 268 Renewed License No. DPR-32
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Virginia Electric and Power Company (the licensee) dated April 13, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-32 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 268 , are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Gloria J. Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. DPR-32 and the Technical Specifications Date of Issuance: February 26, 2010
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 267 Renewed License No. DPR-37
- 1. The Nuclear Regulatory Commission (the Commission) has found that A. The application for amendment by Virginia Electric and Power Company (the licensee) dated April 13, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 267 , are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Gloria J. Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes License No. DPR-37 and the Technical Specifications Date of Issuance: February 26,2010
ATTACHMENT TO LICENSE AMENDMENT NO. 268 RENEWED FACILITY OPERATING LICENSE NO. DPR-32 DOCKET NO. 50-280 AND TO LICENSE AMENDMENT NO. 267 RENEWED FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NO. 50-281 Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages License License License No. DPR-32, page 3 License No. DPR-32, page 3 License No. DPR-37, page 3 License No. DPR-37, page 3 Units 1 and 2 Units 1 and 2 TS3.7.14 TS 3.7.14
-3
- 3. This reneweellicense shall be deemed to contain an~ is sUbject to the conditions specified in the following Commission regulations: 10 CFR Part 20. Section 30:34 of 10 CFR Part 30. Section 40.41 of 10 CFR Part 40, Secttons 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 eFR Part 70; and is subject to all applicable provtslons of the Act and the rUles, regulations, and orders Of the Commission now or hereafter in effect; and is subject to the additional conditions speclfled below:
A. MaXimum Power Level The licensee is authorized to operate the faCility at steady state reactor core power levels not In excess of 2546 megawatts (thermal).
B. Technical Soeclfications The Technical SPACifications contained In Appendix A. as revised through Amendment No. 268 are hereby Incorporated in th9 rene~ license. The licensee shall oPerate the facility In accordance w~h the r.chnical Specifications.
C. Reports The licensee shall make certain reports In accordance with the requirements of the Technical Specifications. ..
D. Records The licensee shall keep facility operating records in accordance with the requrrements of the Technical Specifications.
E.. Deleted by Amendment 65 F. Deleted by Amendment 71 G. Deleted by Amendment 227 H. Deleted by Amend ment 227 I. Fire Protection The licensee shall implement and maintain in effect the provisions of the approved fire protection. program as described in the Updated Anal Safety Analysis Report* and as approved In the SER dated September 19, 1979, (and Supplements dated May 29, 19BO, October 9. 1980, December 18, 1980, February 13. 1981, December 4,1981, April 27, 1982, November 18.1982.
January 17. 1984, Februery 25, 1988, and SURRY UNIT 1 Renewed License No. DPR-32 Amendment No. 268
-3 E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess. but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
- 3. This renewed license shall be deemed to contain and is sUbject to the conditions specified in the following Commission regulations: 10 CFR Part 20. Section 30.34 of 10 CFR Part 30. Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50:59 of 10 CFR Part 50. and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and the rules. 'regulations; and orders of the CommIssion now or hereafter In effect; and is subject to the additional conditions specified below:
A. Maximum Power Level The licensee is authorizeq to operate the facility at steady state reactor core power levels not in excess of 2546 megawatts (thermal).
B. Technical SpecifICations The Technical Specifications contained 'in Appendix A, as revised through Amendment No. 267
- are hereby incorporated in this renewed license. The licensee shall operate the faciUty in accordance with the Technical 'Specifications. '
C. Reports The licensee s~all make certain reports in accordance with the reqUirements of the Technical Specifications.
D. Records The licensee shall keep facility operating records In accordance with the reqUirements of the Technical Specifications. '
E. Deleted by Amendment 54 F. Deleted by Amendment 59 and Amendment 65 G. ,Deleted by Amendment 227 H. De\eted by Amendment 227 SURRY - UNIT 2 Renewed License No. OPR-37 Amendment No. 267
TS 3.7-14 TBD TABLE 3.7-1 (Continued)
- 4. The QUADRANT POWER TILT shall be determined to be within the limit when above 75 percent of RATED POWER with one Power Range Channel inoperable by using the moveable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ACTION 3. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement and with the THERMAL POWER level:
- a. Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.
- b. Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 11 % of RATED POWER, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, decrease power below P-6 or increase THERMAL POWER above 11 % of RATED POWER.
- c. Above 11 % of RATED POWER, POWER OPERATION may continue.
Amendment Nos. 268 and 267
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281
1.0 INTRODUCTION
By letter dated April 13, 2009, Virginia Electric and Power Company (Dominion, the licensee),
submitted a license amendment request (LAR) to revise the technical specifications (TSs) of Surry Power Station, Unit Nos.1 and 2 (Surry Units 1 and 2). The proposed change revises TS Table 3.7.1, Operator Action 3.b, and provides direction for the actions to be taken if the operating condition of less than the required minimum channels for the neutron flux intermediate range occurs between 7 percent and 11 percent of rated power. The proposed change will revise TS Table 3.7.1, Operator Action 3.b, to read, "Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 11 % of RATED POWER, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decrease power below P-6 or increase THERMAL POWER above 11 % of RATED POWER." The text currently reads, "Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 7% of RATED POWER, decrease power below P-6 or, increase THERMAL POWER above 11% of RATED POWER within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."
2.0 REGULATORY EVALUATION
The following gUidance document pertains to the proposed TS change:
NRC Administrative Letter (AL) 98-10, "Dispositioning of Technical Specifications That Are Insufficient To Assure Plant Safety," dated December 29, 1998, states, "Imposing administrative controls in response to an improper or inadequate TS is considered an acceptable short-term corrective action." AL 98-10 also requires licensees to submit such a TS change with appropriate justification in a timely manner.
3.0 TECHNICAL EVALUATION
The licensee's request was based on a concern raised during a simulator training session that TS Table 3.7.1 Operator Action 3.b, as written, does not specify actions to be taken if the condition of
- 2 having less than the required minimum number of operable channels for the nuclear flux intermediate range occurs between 7 percent and 11 percent of rated power. Therefore, the actions directed by Operator Action 3.b are inadequate. As such, the licensee, consistent with the guidance of AL 98-10, imposed administrative controls by revising the Surry Units 1 and 2 Abnormal Procedures for Nuclear Instrumentation Malfunction for nuclear flux intermediate range channel inoperability for rated power levels between 7 percent and 11 percent.
The proposed TS change does not involve the installation of any new equipment or affect the design function of any structures, systems, or components (SSCs). In addition, the proposed change does not affect the condition or performance of SSCs relied upon for accident mitigation or impact any safety analysis assumptions. The licensee has taken proper actions in accordance with AL 98-10 to correct inadequate TS requirements; therefore, the NRC staff finds the proposed change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (74 FR 34049). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
Based on its review of the licensee's submittal, the staff has concluded that the licensee has taken actions in accordance with AL 98-10 and has revised the TSs to correct the inadequate TS requirements. Therefore, the NRC Staff finds the proposed change acceptable.
Principal Contributor: Hukam Garg, NRR/DE Date: February 26, 2010
February 26, 2010 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENT REGARDING REQUEST TO CORRECT TECHNICAL SPECIFICATION TABLE 3.7.1 OPERATOR ACTION 3.b (TAC NOS. ME1068 AND ME1069)
Dear Mr. Heacock:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 268 to Renewed Facility Operating License No. DPR-32 and Amendment No. 267 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2 (Surry Units 1 and 2), respectively. The amendments change the Technical Specifications (TSs) in response to your application dated April 13, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091040147).
These amendments revise the TSs of Surry Units 1 and 2. The proposed change revises TS Table 3.7.1, Operator Action 3.b, and provides direction for the actions to be taken if the operating condition of fewer than the required minimum channels for the neutron flux intermediate range occurs between 7 percent and 11 percent of rated power.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
Karen Cotton, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281
Enclosures:
- 1. Amendment No. 268 to DPR-32
- 2. Amendment No. 267 to DPR-37
- 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: Public RidsNrrLAMO'Brien Resource RidsNrrDirsltsb (TKobetz)
LPL2-1 RlF RidsOgcRp Resource RidsRgn2MailCenter Resource RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrPMSurry Resource RidsNrrDeEicb Resource GHukam, NRRlDE ADAMS Accesslon No. ML100140559 *SEtransml'ttedb)y memo dat ed 12/9/09 OFFICE NRRlLPL2-1/PM NRR/LPL2-1/LA NRRlDE/EICB NRRlDIRSIITSB OGC NRRlLPL2-1/BC NAME KCotton MOBrien WKemper* RElliott CBoote G Kulesa DATE 2/25/10 2/3/10 12/9/09 2/16/10 2/22/10 2/26/10 OFFICIAL RECORD COPY