Letter Sequence Approval |
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TAC:MD2097, Steam Generator Tube Integrity (Approved, Closed) TAC:MD2098, Steam Generator Tube Integrity (Approved, Closed) |
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MONTHYEARML0631101952006-11-0606 November 2006 Request for Additional Information (RAI) Regarding the Steam Generator Tube Integrity Technical Specification Amendment Project stage: RAI ML0708806242007-03-29029 March 2007 Issuance of License Amendments 251 and 250 Regarding Steam Generator Tube Integrity Project stage: Approval ML0709200372007-03-29029 March 2007 Tech Spec Pages for Amendments 251 and 250 Regarding Steam Generator Tube Integrity Project stage: Acceptance Review 2006-11-06
[Table View] |
Similar Documents at Surry |
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Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23285A0922023-10-12012 October 2023 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests ML23277A1172023-10-0303 October 2023 Operator Licensing Examination Approval 05000280/2023301 and 05000281/2023301 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - 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[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 - 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Slides ML20085G9642020-05-19019 May 2020 Issuance of Amendments Nos. 298 and 298 to Revise Technical Specifications Table 3.7-1, Reactor Trip Instrument Operating Conditions, for an Addition of 24-Hour Completion Time for an Inoperable Rector Trip Breaker ML20115E2372020-05-0707 May 2020 Issuance of Exigent Amendments Nos. 299 and 299, to Revise TS 6.4.Q, Steam Generator (SG) Program, to Allow a One-Time Deferral of the Inspection of Surry Unit 2 Sg B Spring 2020 Refueling Outage ML20099F8732020-04-17017 April 2020 Audit Proposed License Amendment Request for the Addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1 (EPID L-2019-LLA-0243 and EPID L-2019-LLA-0236 ML20058F9662020-03-16016 March 2020 Issuance of Amendment Nos. 297 and 297 to Revise Technical Specifications 3.16, Emergency Power System, to Allow a One Time 14-Day Allowed Outage Time for Replacement of 5-KV Cables Associated with Reserve Station 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) ML19031B2272019-02-27027 February 2019 Issuance of Amendment Nos. 281, 264, 294, and 294 to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes 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 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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MF7716 and MF7717). 08/10/2017 ML16202A0682016-07-14014 July 2016 Proposed Licensed Amendment Request Emergency Service Water Pump Allowed Outage Time Extension ML16042A1732016-02-29029 February 2016 Issuance of Amendments for Generic Letter 2008-01 (Gas Accumulation) ML15314A0782015-11-0505 November 2015 Virginia Electric and Power Company, Surry Power Station, Units 1 and 2 - Intent to Pursue Second License Renewal 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 ML15173A1022015-06-26026 June 2015 Issuance of Amendments Regarding Clarification of Reactor Coolant System Heatup and Cooldown Limitation Technical Specification Figures ML15099A6792015-04-28028 April 2015 Issuance of Amendments Regarding Relocation of Augmented Inspection Requirements 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 ML14073A4052014-04-24024 April 2014 Issuance of Amendment for the Technical Specifications Changes Related to Snubber Surveillance Requirements ML13186A1972013-09-25025 September 2013 Independent Spent Fuel Storage Installations - Issuance of Amendments for Changes to the Emergency Action Level Revisions ML13018A0862013-01-28028 January 2013 Issuance of License Amendment Request to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection 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 ML1207303042012-04-17017 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 ML11192A2492011-08-31031 August 2011 Issuance of Amendment Regarding Cyber Security to Dominion Plants ML11194A2902011-07-28028 July 2011 License Amendment, Issuance of Amendments Regarding Administrative Changes to Technical Specifications 3.12 and 6.2 ML11110A1112011-05-31031 May 2011 Issuance of Amendments Regarding Reactor Vessel Heatup and Cooldown Curves for 48 Effective Full-Power Years 2024-01-18
[Table view] Category:Safety Evaluation
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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] |
Text
March 29, 2007 Mr. David A. Christian Senior Vice 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 AMENDMENTS REGARDING STEAM GENERATOR TUBE INTEGRITY (TAC NOS. MD2097 AND MD2098)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 251 to Renewed Facility Operating License No. DPR-32 and Amendment No. 250 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively.
The amendments change the Technical Specifications (TSs) in response to your application dated May 26, 2006, as supplemented by letter dated January 19, 2007.
These amendments revise the Technical Specification (TS) requirements related to steam generator tube integrity and Reactor Coolant System (RCS) leakage definitions and requirements. The TSs have been revised to implement TS Task Force (TSTF) Standard TS Change Traveler, TSTF-449, Steam Generator Tube Integrity, (TSTF-449, Rev. 4) with minor deviations to be consistent with Surrys custom TSs.
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,
/RA/
Siva P. Lingam, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281
Enclosures:
- 1. Amendment No. 251 to DPR-32
- 2. Amendment No. 250 to DPR-37
- 3. Safety Evaluation cc w/encls: See next page
March 29, 2007 Mr. David A. Christian Senior Vice 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 AMENDMENTS REGARDING STEAM GENERATOR TUBE INTEGRITY (TAC NOS. MD2097 AND MD2098)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 251 to Renewed Facility Operating License No. DPR-32 and Amendment No. 250 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively.
The amendments change the Technical Specifications (TSs) in response to your application dated May 26, 2006, as supplemented by letter dated January 19, 2007.
These amendments revise the Technical Specification (TS) requirements related to steam generator tube integrity and Reactor Coolant System (RCS) leakage definitions and requirements. The TSs have been revised to implement TS Task Force (TSTF) Standard TS Change Traveler, TSTF-449, Steam Generator Tube Integrity, (TSTF-449, Rev. 4) with minor deviations to be consistent with Surrys custom TSs.
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,
/RA/
Siva P. Lingam, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281
Enclosures:
- 1. Amendment No. 251 to DPR-32
- 2. Amendment No. 250 to DPR-37
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public RidsNrrLAMOBrien (hard copy) RidsNrrDirsItsb (TKobetz)
LPL2-1 R/F RidsOgcRp RidsRgn2MailCenter (EGuthrie)
RidsNrrDorlLpl2-1 (EMarinos) RidsAcrsAcnwMailCenter RidsNrrDorlDpr(BSingal)
RidsNrrPMSLingam (hard copy) GHill (4 hard copies) RidsNrrDciCsgb (AHiser)
RidsNrrDirsItsb (TWertz) RidsNrrDciCsgb (LMiller)
Package No.: ML070880618 Amendment No.: ML Tech Spec No.: ML070880624 *transmitted by memo dated.
OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA DCI/CSGB/BC DIRS/ITSB/BC NRR/LPL2-1/BC NAME SLingam MOBrien AHiser TKobetz EMarinos DATE 3/26 /07 3/26 /07 9/26/06* 3/19/07* 3/27/07 OFFICIAL RECORD COPY
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 251 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 May 26, 2006, as supplemented by letter dated January 19, 2007, 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. 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. 251, 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 180 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Evangelos C. Marinos, Chief Plant Licensing Branch II-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: March 29, 2007
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 250 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 May 26, 2006, as supplemented by letter dated January 19, 2007, 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. 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. 250, 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 180 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes License No. DPR-37 and the Technical Specifications Date of Issuance: March 29, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 251 RENEWED FACILITY OPERATING LICENSE NO. DPR-32 DOCKET NO. 50-280 AND TO LICENSE AMENDMENT NO. 250 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.
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 251 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO. 250 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 May 26, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML061510096), as supplemented by letter dated January 19, 2007 (ADAMS Accession No. ML070190655), Virginia Electric and Power Company (the licensee) submitted a request for changes to the Surry Power Station, Unit Nos. 1 and 2 (Surry 1 and 2),
Technical Specifications (TSs).
The proposed changes would revise the existing steam generator (SG) tube surveillance program. The changes are modeled after TS Task Force (TSTF) Standard Technical Specification (STS) Change Traveler TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation prepared by the Nuclear Regulatory Commission (NRC) and published in the Federal Register on March 2, 2005 (70 FR 10298). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), changes to the SG reporting requirements, and associated changes to the TS Bases.
The supplement dated January 19, 2007, provided clarifying information that did not change the scope of the original application and the initial proposed no significant hazards consideration determination.
2.0 REGULATORY EVALUATION
The background, description, and applicability of the proposed changes associated with the SG tube integrity issue and the applicable regulatory requirements were included in the NRC staffs model safety evaluation (SE) published in the Federal Register on March 2, 2005 (70 FR 10298). The Notice of Availability of Model Application Concerning Technical Specification Improvement To Modify Requirements Regarding Steam Generator Tube Integrity
Using the Consolidated Line Item Improvement Process was published in the Federal Register on May 6, 2005 (70 FR 24126), and made the model SE available for licensees to reference.
3.0 TECHNICAL EVALUATION
In the licensees May 26, 2006, application, as supplemented by letter dated January 19, 2007, the licensee proposed changes to the TSs that are modeled after TSTF STS Change Traveler, TSTF-449, Steam Generator Tube Integrity. There were minor differences between TSTF-449 and the licensee's application. These included differences in the facility licensing basis (than that discussed in TSTF-449) and differences in TS format and numbering. These differences are discussed below.
With respect to the differences in the facility licensing basis, the differences did not invalidate the technical evaluation on TSTF-449; rather they resulted in the licensee having to slightly deviate from some of the modifications discussed in TSTF-449. For example, TSTF-449 has specific definitions of the modes of operation whereas for Surry the modes of operation are termed reactor operation conditions. There are slight differences between the operating conditions (e.g., temperature) associated with these reactor operation conditions when compared to the modes in TSTF-449. These differences resulted in the licensee having slightly different requirements (associated with the reactor operation conditions) than that discussed in TSTF-449 (although in some instances the licensee would specify the temperature corresponding to the TSTF-449 mode of operation in their TS rather than referencing the reactor operation condition to make their submittal more consistent with TSTF-449). Another example is that the licensee indicated that the dose consequences are within the limits of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.67, (rather than Part 100 as indicated in TSTF-449) since the licensees current licensing basis is based on 10 CFR 50.67.
Another example is that the licensee indicated in their Bases that the accident analyses for a SG tube rupture assumes the contaminated secondary fluid is released to the atmosphere via power operated relief valves or safety valves (rather than only being briefly released to the atmosphere via safety valves with the majority being discharged to the main condenser as indicated in TSTF-449). Since the licensees accident analysis differs from that assumed in TSTF-449, they did not incorporate the text from TSTF-449 rather they incorporated a sentence that reflects their accident analysis. Since these differences in the licensing basis were minor in nature, they were consistent with the plants licensing basis, or they were consistent with the intent of TSTF-449, the NRC staff determined they were acceptable.
With respect to the differences in the numbering of the TSs, these differences were administrative in nature and did not affect the technical adequacy of the submittal. As a result, the NRC staff determined they were acceptable. As a result of the differences in the format of their TSs, the licensee relocated many of the TSTF-449 requirements into the appropriate sections of its TSs (e.g., the limiting conditions for operation and action statements are in different sections than the surveillance requirements). In addition, there were some changes in the Bases section of TSTF-449 that were not incorporated into the licensees submittal, since the licensee did not have the corresponding paragraphs in their Bases. For example, the licensee did not have several references to their SG tube surveillance program in their existing Bases so it did not need to delete these changes in order to adopt TSTF-449. These differences in TS format also resulted in listing the requirements in sentence format rather than
tabular format and using slightly different terminology. Since these differences were administrative in nature and did not affect the technical adequacy of the submittal, the NRC staff determined they were acceptable.
In addition to the above, the licensee also proposed a few changes that went beyond TSTF-449. For example, the licensee also proposed changes to the requirements pertaining to reactor coolant system operational leakage that went beyond TSTF-449 (e.g., adding definitions to TS 1.X, and modifying the action statements in TS 3.1.C). Since these proposed TS changes, including the changes to the Bases, were generally consistent with the standard TSs as modified to reflect the plants licensing basis, the NRC staff determined that the proposed changes were acceptable. The licensee also had minor wording changes to preclude confusion. For example, the licensee replaced performed with completed to avoid confusion regarding when the verification that primary-to-secondary leakage was within limits was to be performed/completed. Another example is that the licensee proposed, in part, to limit accident-induced leakage to 1 gallon per minute for all SGs. Since this proposal was more restrictive than that required by TSTF-449 (which limited accident-induced leakage, in part, to 1 gallon per minute per SG), the NRC staff found it acceptable.
The remainder of the application was consistent with, or more limiting than, TSTF-449.
In summary, the NRC staff determined that the model safety evaluation is applicable to this review and finds the proposed changes acceptable.
Consistent with TSTF-449, the proposed TS changes include: (1) a revised definition of LEAKAGE, (2) a revised TS Section 3.1.C, "RCS [Reactor Coolant System] Operational Leakage," (3) a new TS Section 3.1.H, "Steam Generator (SG) Tube Integrity," (4) a new TS Section 4.13, RCS Operational Leakage, (5) a revised TS Section 4.19, Steam Generator Tube Integirty, (6) a new TS Section 6.4.Q, "Steam Generator (SG) Program," (7) a new TS Section 6.6.A.3, "Steam Generator Tube Inspection Report," and (8) revised Table of Content pages to reflect the proposed changes.
The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provides reasonable assurance that the SGs can be operated safely without increase in risk.
The revised TSs will contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective. However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained.
Failure to meet the performance criteria will be reportable pursuant to the requirements in 10 CFR Parts 50.72 and 50.73. The NRC reactor oversight process provides a process by
which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented.
In conclusion, the NRC staff finds that the TS changes proposed by the licensee in its May 26, 2006, application and January 19, 2007, supplement conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety.
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 requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. 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 (71 FR 46941, published August 15, 2006). The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusions set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10). 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
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Trent Wertz Leslie Miller Date: March 29, 2007
Surry Power Station, Units 1 & 2 cc:
Mr. David A. Christian Office of the Attorney General Senior Vice President Commonwealth of Virginia and Chief Nuclear Officer 900 East Main Street Virginia Electrical and Power Company Richmond, Virginia 23219 Innsbrook Technical Center 5000 Dominion Boulevard Mr. Chris L. Funderburk, Director Glen Allen, VA 23060-6711 Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Ms. Lillian M. Cuoco, Esq. Innsbrook Technical Center Senior Counsel 5000 Dominion Blvd.
Dominion Resources Services, Inc. Glen Allen, Virginia 23060-6711 Building 475, 5th Floor Rope Ferry Road Waterford, Connecticut 06385 Mr. Donald E. Jernigan Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218