Similar Documents at Surry |
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Category:Code Relief or Alternative
MONTHYEARML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI 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 ML23073A1912023-04-21021 April 2023 Alternative for Inservice Inspections of Pressurizer and Steam Generator Weld Examinations ML22342A1002022-12-0707 December 2022 Relief Request Acceptance Review Results; Surry ISI Alternative, Prz and SG Welds and Nozzles 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) ML18236A2362018-09-26026 September 2018 Relief from the Requirements of the ASME Code - Proposed Alternatives S1-I5-ISI-04 and S2-I5-ISI-04 ML18068A0642018-03-26026 March 2018 Relief from the Requirements of the ASME Code Repair/Replacement of Buried Circulating and Service Water Class 3 Piping with Carbon Fiber Reinforced Polymer (CAC Nos. MF8987 and MF8988; EPID L-2016-LLR-0019) ML17303A0682017-12-20020 December 2017 Nonproprietary Relief from the Requirements of the ASME Code (CAC Nos. MF8987 and MF8988; EPID L-2016-LLR-0019) ML16365A1182017-02-17017 February 2017 Requests for Relief LMT-R01, LMT-SS01, LMT-CS01, LMT-P01, LMT-C01, LMT-C02, LMT-C03, and LMT-C04 - for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval ML16208A0092016-08-24024 August 2016 Requests for Relief LMT-R01, LMT-R02, LMT-R03, LMT-P01, and LMT-C01, Alternatives to ASME Code Requirements for Limited Coverage from the Requirements of the ASME Code ML15023A4412015-03-16016 March 2015 Alternatives to the Requirements of the ASME Code and Use of a Subsequent Edition and Addenda of the ASME B&PV Code, Section XI ML15029A4242015-02-10010 February 2015 Fifth 10-Year Inservice Inspection Interval Request for Subsequent Edition/Addenda ML14309A6662014-11-25025 November 2014 Relief from the Requirements of the ASME Code ML14125A4712014-05-0909 May 2014 Relief from the Requirements of the ASME Code ML14115A1992014-04-30030 April 2014 Relief from the Requirements of the ASME OM Code ML14113A3462014-04-25025 April 2014 Relief from the Requirements of the ASME Code ML13204A2972013-08-0101 August 2013 Relief from the Requirements of the ASME Code (Tacs. MF0329 and MF0330) ML13106A1402013-04-30030 April 2013 Relief from the Requirements of the ASME Code Section XI for the Fourth Ten-Year Inservice Inspection Program Interval ML12348A0082012-11-0909 November 2012 ASME Section XI Inservice Inspection (Isl) Program Request for Alternative - Reactor Vessel Nozzle to Safe End Butt Welds Examination Relief Requests CMP-008 and CMP-010 ML12130A2172012-04-25025 April 2012 ASME Section XI Inservice Inspection (ISI) Program Request for Alternative - Implementation of Extended Reactor Vessel Inservice Inspection Interval Relief Requests CMP-007 and CMP-009 ML0930003522009-10-27027 October 2009 Submittal of Relief Request SPT-004, Revision 2, SPT-003, Revision 2 and Elimination of NRC Bulletin 2003-02 Commitment ML0714403422007-08-0303 August 2007 Relief Request to Use Portion of 2001 Edition of American Society of Mechanical Engineers Code ML0712700162007-06-0505 June 2007 Relief, Forth 10-Year Inservice Inspection Interval Relief Request CMP-001, Revision 1 ML0633402942006-11-29029 November 2006 Surrry, Unit No. 2, Reply to Fourth 10-Year Inservice Inspection Interval Relief Request CMP-007, TAC MD2673 ML0615103652006-05-31031 May 2006 Relief, Third 10-Year ISI Interval ML0611706232006-04-27027 April 2006 Relief, Section XI Inservice Inspection Program Relief Requests PRT-07 and PRT-08 NRC Safety Evaluation Report Discrepancy ML0608701372006-04-14014 April 2006 Third 10-Year Inservice Inspection Interval Relief Requests PRT-01 and PRT-02 ML0607304682006-03-28028 March 2006 Relief, Third 10-Year Inservice Inspection Interval PRT-07 ML0605402842006-03-28028 March 2006 Third 10-Year Inservice Inspection Interval Relief Request PRT-08 ML0604405462006-02-0202 February 2006 Relief, Containment Relief Request IWL1 ML0530402032005-11-0101 November 2005 Relief Request, Fourth 10-Year Inservice Inspection SPT-008 ML0529300322005-11-0101 November 2005 Relief, Fourth 10-Year Inservice Inspection Program, MC5586, MC5587, MC5596, MC5597, MC5598, and MC5600 ML0526903172005-09-28028 September 2005 Relief Request, ASME Section XI ISI on Partial Examination (Tac No. MC4633, MC4634, MC4635, MC4636, MC4637) ML0520800062005-08-0808 August 2005 Relief, Safety Significant Socket Weld Examinations, TAC MC3134 ML0515302482005-05-20020 May 2005 ASME Section XI Inservice Inspection Relief Request Main Steam Line Branch Connection Weldolets ML0514604312005-05-20020 May 2005 RR, Correction Letter for SR-36 ML0510101962005-04-11011 April 2005 ASME Section XI Relief Request Alternative Acceptance Criteria for Surface Examinations ML0510204862005-04-0808 April 2005 RR-8, ASME IST Requirements on Spray Pumps for Revised Relief P-8 (Tac No. MC6258) ML0504806682005-02-17017 February 2005 SE, Correction for ASME ISI (Tac No. MC3142, MC3143) ML0503406172005-02-0101 February 2005 Ltr, Authorization of RR SR-036 & SR-037 ML0501804952005-01-10010 January 2005 ASME Section XI Inservice Inspection Program, End of Intervals System Pressure Testing ML0500400542005-01-0404 January 2005 Relief, Interval Request for Relief SR-004, Rev. 2, TAC MC3693 ML0429504442004-10-16016 October 2004 Relief Request, American Society of Mechanical Engineers Inservice Inspection Program Third 10-Year Interval ML0429402892004-10-11011 October 2004 ASME Section Xl Inservice Inspection Program Partial Examination Relief Request ML0427304532004-09-28028 September 2004 American Society of Mechanical Engineers Inservice Testing Program, Revised Relief Requests P-2 ML0425900412004-09-13013 September 2004 Relief, Risk-Informed Inservice Inspection Relief Request R-1 ML0424606322004-09-0101 September 2004 Fourth Interval Inservice Testing Program Revised Relief Requests P-2 ML0419101182004-07-0202 July 2004 7/2/04, Surry, Units 1 & 2, Relief, Certain American Society of Mechanical Engineers (ASME) Inservice Testing (IST) Requirements. Proposed Alternatives in Relief Requests P-1, P3, P-4, P-5, P-6, P-7, V-2, V-3, V-4, V-5 & V-6 Acceptable ML0412700022004-05-0404 May 2004 Request to Use Code Case N-663 as an Alternative for Surface Examination of ASME Code Class 2 Piping Welds(Tac MC2489, MC2490, MC2491, MC2523 & MC2524) 2023-09-18
[Table view] Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23285A0922023-10-12012 October 2023 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests ML23277A1172023-10-0303 October 2023 Operator Licensing Examination Approval 05000280/2023301 and 05000281/2023301 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23256A2672023-09-21021 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations IR 05000280/20220042023-09-0101 September 2023 Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004 ML23244A0142023-08-30030 August 2023 Inservice Inspection Owner'S Activity Report IR 05000280/20230052023-08-23023 August 2023 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005) ML23226A1862023-08-10010 August 2023 Proposed License Amendment Request - Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML23220A1492023-08-0707 August 2023 Independent Spent Fuel Storage Installation - Submittal of Cask Registrations for Spent Fuel Storage ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information IR 05000280/20230022023-08-0404 August 2023 Integrated Inspection Report 05000280/2023002 and 05000281/2023002 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations ML23198A0322023-07-18018 July 2023 Regulatory Audit Report Regarding Review of License Amendment to Modify Emergency Plan Staff Augmentation Times ML23193A9382023-07-18018 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23173A0602023-07-11011 July 2023 Audit Summary for License Amendment Request Revision of the Emergency Plan to Support Relocation of the Technical Support Center ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23152A0432023-06-22022 June 2023 Audit Plan License Amendment Requests to Change Emergency Plan Staff Augmentation Times ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23151A6612023-05-31031 May 2023 ES-2.1-1, Surry 2023-301 Corporate Notification Letter (Revised) ML23167B0072023-05-31031 May 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary ML23117A0952023-05-10010 May 2023 Audit Plan License Amendment Request to Support Relocation of the Technical Support Center ML23130A3742023-05-10010 May 2023 Request to Delay NRC Intial Licensing Examination 2024-02-06
[Table view] 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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 August 1, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glenn Allen, VA 23060
SUBJECT:
SURRY POWER STATION, UNIT NOS 1 AND 2 - RELIEF FROM THE REQUIREMENTS OF THE ASME CODE (TAC NOS. MF0329 AND MF0330)
Dear Mr. Heacock:
By letter dated November 9, 2012, as supplemented by letter dated January 14, 2013, the Virginia Electric and Power Company, Dominion (the licensee), submitted Relief Requests CMP-008 and CMP-010. Relief Requests CMP-008 and CMP-010 propose the use of alternate root mean square (RMS) error criteria for sizing flaws that are greater than the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," (N-695) at Surry Power Station, Units 1 and 2.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g)(5)(iii), the licensee requested approval to use alternative requirements for the reactor vessel nozzle to safe end dissimilar metal butt end welds examination. The proposed alternative uses an alternate depth-sizing qualification for volumetric examinations of these welds from the inside surface and uses a RMS error criterion for sizing flaws that is greater than that allowed by ASME Code. Pursuant to 10 CFR 50.55a(g)(6)(i), the staff has evaluated the licensee's determination that the Code Case requirements are impractical.
The NRC staff determines that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(5)(iii). Therefore, the NRC grants relief as described in relief requests CMP-008 and CMP-010, as supplemented by the letter dated January 14, 2013, for Surry Power Station, Units 1 and 2, until the end of their fourth 10-year lSI intervals which are scheduled to end on December 13, 2013 and May 9, 2014, respectively.
D. Heacock -2 If you have any questions, please contact the Project Manager, Karen Cotton at 301-415-1438 or via e-mail at karen.cotton@nrc.gov.
bert Pascarelli, Ch f lant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos: 50-280 and 50-281
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NUMBERS CMP-OOB AND CMP-01 0 REGARDING THE FOURTH TEN YEAR INSPECTION INTERVAL VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION. UNITS 1 AND 2 DOCKET NUMBER 50-2BO AND 50-2B1
1.0 INTRODUCTION
By letter dated November 9, 2012 (Agency Wide Documents Access and Management System (ADAMS) Accession Number ML12341A213) as supplemented January 14,2013 (ADAMS Accession No. ML 13025AOB4), the Virginia Electric and Power Company, Dominion (the licensee). submitted Relief Requests CMP-OOB and CMP-010. Relief Requests CMP-OOB and CMP-010 propose the use of alternate root mean square (RMS) error criteria for sizing flaws that are greater than the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," (N-695) at Surry Power Station Units 1 and 2. Relief Request CMP-OOB covers the examination of welds in Unit 1 and Relief Request CMP-01 0 covers the examination of welds in Unit 2.
2.0 REGULATORY EVALUATION
In its letter dated November 9,2012, the licensee requested relief from the 0.125 inch RMS error depth sizing acceptance criteria contained in ASME Code Case N-695 pursuant to 10 CFR 50.55a(g)(5)(iii).
ASME Code Case N-695 is accepted for use in Nuclear Regulatory Commission (NRC)
Regulatory Guide (RG) 1.147, Revision 16, "Inservice Inspection Code Case Acceptability ASME Section XI, Division 1," and incorporated by reference in 10 CFR 50.55a(b).
10 CFR 50.55a(g)(4)(ii) states, in part. that inservice examination of components conducted during 120-month intervals must comply with the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) 12 months before the start of the 120-month inspection interval or the optional ASME Code cases listed in NRC RG 1.147.
10 CFR 50.55a(g)(5)(iii) states, in part, that if the licensee has determined that conformance with a code requirement is impractical, the licensee shall notify the NRC and submit information to support the determinations.
Enclosure
-2 10 CFR 50.55a(g){6){i) states, in part that the Commission will evaluate determinations under paragraph (g){5) of this section that code requirements are impractical and that the Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee if the requirements were imposed upon the licensee.
8ased on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to grant the relief requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 The Licensee's Relief Request The components covered by Relief Requests CMP-OOB and CMP-010 are large-bore reactor inlet and outlet dissimilar metal welds. The welds are all ASME Code Class 1 and are Inspection Category 8-F, Item 85.10 "Reactor Vessel Nozzle to Safe-End 8utt Welds". The welds are covered by the licensee's risk informed lSI program as Category R-A, Item R1.11, "Elements Subject to Thermal Fatigue".
The vessel material in both cases is SA50B Class 2 ferritic steel. The weld metal is described as austenitic stainless steel and not a nickel alloy weld metal such as alloy 1B2 or B2.
Table 1 WeIdCovere d 8Iy -
RR CMP OOB for Surry P ower St al'Ion U'tnI 1 Component Designation Location ID Thickness Safe End Material 29"-RC-1-2501 R-1-010M Loop A Hot Leg 29" 2.70" ASTM A-376 TP 316 i 27.5"-RC-3-2501 R-1-170M Loop A Cold Leg 27.5" 2.56" SA351 CFBM
- 29"-RC-4-2501 R-1-01 OM Loop 8 Hot Leg 29" 2.70" ~STM A-376 TP 316
- 27.5"-RC-6-2501 R-1-170M Loop 8 Cold Leg 27.5" 2.56" A351 CFBM 29"-RC-7-2501 R-1-01 OM Loop C Hot Leg 29" 2.70" ASTM A-376 TP 316 27.5"-RC-9-2501 R-1-170M Loop C Cold Leg 27.5" 2.56" SA351 CFBM Table 2 WeIdCovered 8Iy RR CMP-010 for Surry Power StarIon U't nI 2 Component Designation Location 10 Thickness Safe End Material 29"-RC-301-2S01 R-1-01 OM Loop A Hot Leg 29" 2.70" ASTM A-376 TP 316 27.5"-RC-303-2501 R-1-170M Loop A Cold Leg 27.5" 2.56" SA351 CFBM
- 29"-RC-304-2501 R-1-01 OM Loop 8 Hot Leg 29" 2.70" ASTM A-376 TP 316 27.5"-RC-306-2501 R-1-170M Loop 8 Cold Leg 127.5" 2.56" SA351 CFBM 29"-RC-307-2501 R-1-01 OM Loop C Hot Leg 29" 2.70" ASTM A-376 TP 316
! 27.5"-RC-309-2501 R-1-170M Loop C Cold Leg 27.5" 2.56" SA351 CFBM Surry, Unit 1 and Surry, Unit 2, are both currently in their fourth 10-year Inservice Inspection (lSI) intervals. The ASME 80iler and Pressure Vessel Code (ASME Code) of record for both units is the 199B Edition of Section XI through the 2000 addenda.Section XI Code Case N-695
-3 (Qualification Requirements for Dissimilar Metal Piping Welds) is referenced in the lSI program.
This Code Case is listed in Regulatory Guide 1.147, Rev. 16, Table 1 - "Acceptable Section XI Code Cases". In addition, as required by 10 CFR 50.55a, the ASME Section XI, 2001 Edition is used for Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems:"
The volumetric examination specified by Examination Category B-F, Item B5.1 0, "RPV nozzle to safe-end dissimilar metal (DSM) butt welds" will be performed using the ultrasonic (UT) examination method as described in IWA-2232 and Appendix I. Appendix I, 1-2220 requires that ultrasonic examination procedures, equipment, and personnel be qualified by performance demonstration in accordance with Appendix VIII. Dominion will be using NRC-approved Code Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds" which provides an alternative to Appendix VIII. Code Case N-695 provides an alternative to the Appendix VIII, Supplement 10 requirements for the qualification requirements of OM welds. Paragraph 3.3(c) indicates that examination procedures, equipment, and personnel are qualified for depth-sizing when the RMS error of the flaw depth measurements, as compared to the true depths, do not exceed 0.125 inch.
To date, no inspection vendor has been able to achieve the Appendix VIII-required 0.125 inch RMS error for depth sizing of large bore OM welds from the 10. The Performance Demonstration Initiative (POI), who administers Appendix VIII testing, has given out partial certifications to procedures and personnel capable of detecting and length sizing cracks. The partial certifications include the achieved RMS error for the inspections. While these partial certifications show that the inspections can be very effective at detecting cracks, these partial certifications do not meet Appendix VIII requirements.
To demonstrate the impracticality of achieving an RMS error of 0.125 inches, the licensee stated:
The most recent attempt at achieving 0.125 inch RMS error was in early 2008. This attempt, as well as previous attempts, did not achieve the required RMS error value.
The qualification attempts have been substantial. The attempts have involved multiple vendors, ultrasonic instruments, personnel, and flaw depth-sizing methodologies, all of which have been incapable of achieving the 0.125 inch RMS error value.
The licensee proposes using an alternative depth-sizing RMS error value greater than the 0.125 inch RMS error value stated in ASME Code Case N-695 for the examination of the welds listed above. The licensee proposes to use an RMS error of 0.224 inches (based on the results achieved by the examination vendor) instead of the 0.125 inches required for Code Case N-695.
In the event an indication is detected that requires depth-sizing, the difference between the required RMS error and the demonstrated RMS error will be added to the measured through wall extent for comparison with the applicable ASME Section XI acceptance criteria. As indicated in the supplemental letter dated January 14, 2013, the licensee provided the following:
- 1. The welds under consideration will be examined using an ultrasonic technique (UT) which is qualified for flaw detection and length sizing.
- 2. Indications connected to the inside surface with measured depths of less than 50 percent of the wall thickness will be dispositioned in accordance with an indication the
- 4 depth of which is the measured depth plus the root mean square error minus 0.125 inches.
- 3. For indications connected to the inside surface with measured depths of 50 percent of the wall thickness or greater, the indication will be repaired or a flaw evaluation of the observed indication will be performed. In addition to the information normally contained in flaw evaluations, the evaluation will include:
- a. Information concerning the mechanism which caused the crack,
- b. Information concerning the surface roughness/profile in the area of the pipe/weld required to perform the inspection (i.e., for the area in which the examination is required to be performed, the inner surface profile will be provided), and
- c. Information concerning areas in which the UT probe may "lift off' from the surface of the pipe/weld, This flaw evaluation shall be submitted to the NRC for review and approval prior to reactor startup.
The NRC staff considers the three items listed above, including the sentence on submitting the subject flaw evaluation to the NRC for review and approval prior to reactor startup to be part of the alternative as proposed by the licensee. Accordingly, this granting of relief is subject to those items and any departure from them would require a further relief request for NRC review and approval.
Relief Requests CMP-008 and CMP-010 would be applicable to the Surry Power Station, Units 1 and 2, until the end of their fourth ten-year lSI interval. The fourth 10-year lSI interval at Surry, Unit 1, is scheduled to end on December 13, 2013 and the fourth 10-year lSI interval at Surry, Unit 2, is scheduled to end on May 9,2014.
3.2 NRC Staff Evaluation As described above, the licensee has requested relief from the requirements of ASME Code Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds". This code case requires that procedures used to inspect welds from the inside diameter (ID) be qualified by performance demonstration. The acceptance criterion established by the code case is an RMS error of not greater than 0.125 inches.
The staff has confirmed that attempts have been made to qualify ID UT inspection procedures since 2002 and that, to date, no inspection vendor has been able to meet the acceptance criteria established by the code case despite the fact that numerous individuals from several companies have attempted to do so. The staff finds that this repeated inability to qualify ID UT inspection techniques in accordance with ASME Code Case N-695 constitutes an impracticality as described in 10 CFR 50.55a(g)(5)(iii).
- 5 While no procedures or personnel are qualified to depth size flaws from the 10 of the welds, the probability of detection and length sizing capabilities of the partially-certified procedures and personnel from the 10 has been demonstrated to be acceptable.
In July 2012, the NRC staff reviewed the proprietary POI program (administered by Electric Power Research Institute (EPRI)) data used in blind tests. This review of the POI data was conducted to verify the information and analysis contained in MRP-2012-11 (provided as attachment 1 of ADAMS Accession No. ML120730196). Based on this review, the NRC staff was able to determine that the addition of the industry-proposed correction factor prior to flaw evaluation for flaws less than 50 percent thro~gh-wall satisfactorily reduces the effect of the increased sizing error associated with not meeting the 0.125 RMS error required by Supplement 10 of ASME Section XI and ASME Code Case N-695. The licensee has agreed that if any cracks are detected and measured as 50 percent through-wall depth or greater, and to remain in-service without mitigation or repair, the licensee shall submit flaw evaluations to the NRC for review and approval prior to reactor startup. This evaluation will include the inner profile of the weld, pipe, and nozzle in the region at and surrounding the flaw, and an estimate of the percentage of potential surface areas with UT probe lift-off. Requiring NRC approval for restart when a flaw greater than 50 percent through-wall is discovered and is to be left in service without mitigation or repair addresses the staff concerns with the possibilities of large undersizing errors in deep flaws.
The NRC staff finds that for flaws measured at 50 percent or less through-wall depth adding the industry-proposed correction factor (procedure RMS error - 0.125 inch) to the depths of any flaw found by the inspections and obtaining NRC review and approval prior to startup for any flaws measured as greater than 50 percent through-wall depth provides adequate assurance of structural integrity and leak tightness.
Based on the concerted efforts by the industry to meet the acceptance criteria contained in ASME Code,Section XI, Supplement 10 and ASME Code Case N-695 and the difficulties associated with other inspection methods, the NRC staff finds that meeting the 0.125 inch acceptance criterion is impractical and represents a burden to the licensee.
Based on the above evaluation, the NRC staff finds that this alternative provides reasonable assurance of structural integrity and leak tightness of the subject components.
4.0 CONCLUSION
As set forth above, the NRC staff determines that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(5)(iii). Therefore, the NRC staff grants relief as described in relief requests CMP-008 and CMP-01 0, as supplemented by the letter dated January 14, 2013, for Surry Power Station, Units 1 and 2, until the end of their fourth 10-year lSI intervals which are scheduled to end on December 13, 2013 and May 9,2014 respectively.
- 6 All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Stephen Comblidge Date: August 1, 2013
D. Heacock - 2 If you have any questions, please contact the Project Manager, Karen Cotton at 301-415-1438 or via e-mail at karen.cotton@nrc.gov.
Sincerely, IRA by JPaige fori Robert Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos: 50-280 and 50-281
Enclosure:
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