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
November 1, 2005 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711
SUBJECT:
SURRY POWER STATION, UNIT 2 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS FOURTH 10-YEAR INSERVICE INSPECTION (ISI) INTERVAL, RELIEF REQUEST SPT-008 (TAC NO. MC7013)
Dear Mr. Christian:
By letter dated May 20, 2005, as supplemented by letter dated August 4, 2005, Virginia Electric and Power Company (VEPCO) submitted Relief Request SPT-008 to use certain requirements of the American Society of Mechanical Engineers (ASME),Section XI Boiler and Pressure Vessel Code (Code) at Surry Power Station, Unit 2. Specifically, VEPCO proposed to examine selected welds using ultrasonic and surface testing requirements specified in ASME,Section III, instead of performing radiography testing. The Nuclear Regulatory Commission (NRC) staff has completed its review of this relief request and our evaluation and conclusion is contained in the enclosed Safety Evaluation.
The NRC staff has reviewed Relief Request SPT-008 and concludes that VEPCOs proposed alternative provides reasonable assurance of structural integrity. In addition, the NRC staff has determined that the ASME Code-required examination would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, Relief Request SPT-008 is authorized pursuant to Title 10 of the Code of Federal Regulations Section 50.55a(a)(3)(ii) for the fourth 10-year ISI interval at Surry, Unit 2.
Sincerely,
/RA/
Evangelos Marinos, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-281
Enclosure:
As stated cc w/ encl: See next page
ML053040203 NRR-028 OFFICE PM/PDII-1 LA/PDII-2 SC/EMEB OGC SC/PDII-1 NAME SMonarque CHawes TChan GLongo EMarinos DATE 10/17/2005 10/14/2005 09/12/2005 10/27/2005 11/ 01 /05 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE FOURTH 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM SURRY POWER STATION, UNIT 2 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO.50-281
1.0 INTRODUCTION
By letter dated May 20, 2005, as supplemented by letter dated August 4, 2005, Virginia Electric and Power Company (the licensee) submitted relief request SPT-008 to use certain requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) at Surry Power Station, Unit 2. Specifically, the licensee proposed to examine selected welds using ASME,Section III, ultrasonic testing (UT) and surface testing requirements in lieu of radiography testing (RT) requirements. The request is for the fourth 10-year inservice inspection (ISI) interval, which started on May 16, 2004, and is scheduled to end May 17, 2014.
2.0 REGULATORY REQUIREMENTS The ISI of the ASME Code Class 1, 2, and 3 components is to be performed in accordance with Section XI of the ASME Code and applicable edition and addenda as required by Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). As stated, in part, in 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if the licensee demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The Code of Record for Surry, Unit 2 for the fourth 10-year ISI interval is the 1998 Edition through 2000 Addenda of Section XI of the ASME Code. The components (including supports) may meet the requirements set forth in Enclosure
subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to commission approval.
3.0 SAFETY EVALUATION - Relief Request SPT-008 3.1 Identification of Components The components affected by this request for relief are the branch connection welds:
Component Drawing Number Weld Number 30"-SHP-101-601/ 6"SHP-145-601 11548-WMKS-103A2-1 2-01BC 30"-SHP-102-601/ 6"SHP-146-601 11548-WMKS-103A2-2 2-01BC 30"-SHP-103-601/ 6"SHP-147-601 11548-WMKS-103A2-3 2-01BC 3.2 Code Requirements The licensee is using the 1998 Edition through the 2000 Addenda of the ASME Code,Section XI for the fourth 10-year ISI interval.
IWA-4540(a)(2)(a) states, The nondestructrive examination methodology and acceptance criteria of the 1992 Edition or later of Section III shall be met prior to return to service.
3.3 Licensees Proposed Alternative In lieu of the 1998 Edition with 2000 Addenda, ASME Code,Section III required RT examination, the licensee proposed the following for the three subject welds:
- 1) Perform a surface examination of the root pass, mid-wall pass, and final pass.
- 2) Perform an UT examination to the maximum extent achievable to the requirements of ASME,Section V with the acceptance criteria to ASME Section III, NC-5330.
The procedures and examiners are qualified in accordance with ASME Section XI, Appendix VIII, Supplement 3, and the recording and acceptance criteria of ASME Section XI are also utilized.
These welds were scanned to the extent possible in four directions with 45E and 60E transducers. Coverage was limited in all four directions due to the joint configuration resulting in a combined coverage for the 45E transducer of 48 percent with coverage of the weld root in only one direction. For the 60E scans the combined total of 58.7 percent coverage was attained, and the root was examined from one direction.
For scans searching for circumferentially oriented flaws using the 45E transducer, coverage of 5.3 percent was achieved in one direction and 84 percent coverage was achieved in the other direction.
For scans searching for circumferentially oriented flaws using the 60E transducer coverage of 41 percent was achieved in one direction and 91 percent coverage was achieved in the other direction. Coverage of the root and lower 1/3 of the weld was excellent for both the 45E and 60E transducers from one direction. For scans searching for axially oriented flaws, coverage was 51.3 percent with both the 45E and 60E transducers in both directions and was predominantly in the upper one-half of the weld.
- 3) A system leakage test will be performed in accordance with IWA-5000.
- 4) These welds are ASME Section XI, IWC-2500-1, Examination Category C-F-2, Item C5.81.
The licensee will include one of the three welds in an Augmented Inspection Plan and will perform a surface and best effort volumetric examination once per period for the next three periods.
3.4 Licensees Basis for the Alternative The licensee replaced the 6-inch main steam trip valve bypass lines at Surry, Unit 2. Under IWA-4540, any ASME Section XI repair/replacement activity that involves welding requires either 1) a system hydrostatic test or 2) a system leakage test along with all nondestructive examination requirements of the 1992 or later Edition of ASME,Section III and all Owners requirements prior to return-to-service.
The original Construction Code for Surry, Unit 2 is the 1967 Edition of American National Standards Institute B31.1. ASME,Section III requires an RT examination of these welds; however, neither the original Construction Code nor present Owners specifications would require an RT.
The system hydrostatic test required by IWA-4540(a)(1) is not practical, as no isolation valve exists between the subject components and the steam generator. The alternative to the system hydrostatic test, permitted by IWA-4540(a)(2), requires the use of nondestructive examination methodology and acceptance criteria of the 1992 Edition of ASME,Section III.
ASME Section III requires RT examination to be performed on the welds. RT of the three weldolets would require approximately 48 exposures for each weld and installation of gamma ports into the 30-inch piping to facilitate the RT process. Furthermore, a double wall RT is not feasible with the weldolet configuration, and even with the large number of exposures, 100 percent coverage would not be attained. The RT would result in unusual difficulty without a compensating increase in the level of quality and safety.
The following discussion explains the anticipated weld quality. The low hydrogen controls on filler metal, 400 EF preheat, and continuous preheat maintenance leading directly into postweld heat treatment (PWHT) ensures that hydrogen assisted cracking cannot occur. Welding using stringer beads produces the smallest possible weld puddle. This reduces the risk of incomplete fusion fabrication defects usually caused by carrying too large a weld puddle. Stringer beads additionally reduce the risk of trapped slag. Also, weld heat inputs per pass are lower than for weave beads and the greater number of beads may give a more uniform tempered metallurgical structure to the weld deposit. Final PWHT ensures that the resulting weld will have a microstructure free from untempered martensite. The principal flaws that might be reasonably postulated will be circumferential in nature. These flaws would be expected to be either incomplete fusion or trapped slag. The maximum through thickness dimension of a
fabrication flaw occurring while welding would be associated with the weld deposit thickness per pass (approximately 1/8-inch). The larger number of weld beads needed to fill the groove when using stringer beads decreases the risk that postulated flaws through thickness would become larger aligned interbeads flaws. The probable location for large aligned postulated flaws to occur is at the base metal fusion lines. Since magnetic particle testing (MT) inspection was performed on the root pass, at mid thickness, and final weld surfaces, the maximum through thickness flaw resulting from postulated aligned lack of fusion (LOF) or slag inclusions would be less than 1/2-inch measured from the root surface outward to just below the midwall MT surface. Similarly, the maximum through thickness flaw resulting from postulated aligned LOF or slag inclusions measured from the midwall thickness MT surface to the face of the reinforcing fillet weld would be under 1/2-inch to 1-inch. It would be unreasonable to expect that a through wall construction flaw would exist. Flaws of the magnitude described above are extremely unlikely to occur.
The weld location was evaluated with a through-wall flaw and with a flaw depth equal to half the wall thickness. The flaws were subjected separately to operating basis earthquake (OBE) and design basis earthquake (DBE) loadings in addition to pressure, dead weight, and thermal expansion loadings. A 5.75-inch long flaw with a depth equal to half of the component wall thickness will remain stable in the normal operating plus OBE condition with a factor of safety of 2.77, and in the normal operating plus DBE condition with a factor of safety of 1.39. A limit load analysis was also performed for both kinds of flaws with flow stress in the material equal to 36,000 pounds per square inch, and the results show there is significant margin against ductile rupture.
3.5 NRC Staff Evaluation The licensee performed the repair using the 1998 Edition with 2000 Addenda of ASME Code,Section XI, IWA-4540, Pressure Testing of Class 1, 2, and 3, Items.
IWA-4540(a) states Unless exempt by (b) below, repair/replacement activities performed by welding or brazing on a pressure-retaining boundary shall include (a)(1) or (a)(2) below.
(1) A system hydro test shall be performed in accordance with IWA-5000 prior to, or as part of, returning to service.
(2) The following requirements shall be met.
(a) The nondestructive examination methodology and acceptance criteria of the 1992 Edition or later of Section III shall be met prior to return to service.
(b) The Owners Requirements shall be met prior to return to service.
(c) A system leakage test shall be performed in accordance with IWA-5000.
The construction welds attaching the nozzles to the steam generator were originally installed and examined to the requirements of the 1967 Edition of ANSI B31.1, which only required a system hydrostatic test. The licensee supplemented the original requirements with a surface examination. For the repair, the licensee had the option of performing the original examination requirements or using the 1992 Edition of ASME,Section III or later editions of the ASME Code plus any additional owner requirements and a system leakage test.
The licensee stated that the ASME Class 2 nozzle to main steam line pipe weld is not easily isolated for a system hydrostatic test. In its letter dated August 4, 2005, the licensee stated that the system hydrostatic test would require filling the steam generator with water to the main
steam isolation valves outside containment, as well as blanking or gagging the five main steam safety valves. The main steam lines would need additional supports to carry the added weight of the water.
Because of the difficulties in performing a hydrostatic pressure test, the licensee chose to use the pressure test requirements of IWA-4540(a)(2) from the 1992 Edition or later endorsed editions of ASME,Section III. Besides the remaining requirements of IWA-4540(a)(2), the 1992 Edition and later endorsed editions of Section III also requires an RT examination. The licensee believes that RT would result in unusual difficulty without a compensating increase in the level of quality and safety. The weld design creates varying through-wall dimensions which necessitates approximately 48 film exposures for each weld and the installation of ports into the 30-inch steam line for inserting the radioactive source. Even with all these film exposures, the RT would not be able to completely examine the welds. In lieu of RT, the licensee proposed volumetrically examining the welds with UT.
UT and RT examinations are complementary though not directly comparable or equivalent.
Depending on the flaw type (i.e., volumetric or planar) and orientation, UT examinations may be superior to RT or vice versa. RT is most effective in detection of volumetric type flaws (i.e., slag and porosity) and detection of planar type flaws (i.e., lack of fusion and cracks) that are oriented in a plane parallel to the x-ray beam. However, RT is limited in detecting planar flaws not oriented parallel to the beam. In contrast, UT is very effective in detecting planar type flaws that are not oriented in a plane parallel to the sound beam. Finally, UT is capable of detecting volumetric type flaws such as slag and porosity, but is limited, compared to RT, in ability to characterize volumetric flaws.
In the licensees proposed alternative, the examination coverage consists of scanning with angle beam transducers in two opposite directions perpendicular to the weld axis and two opposite directions parallel to the weld axis to the extent permitted by the nozzle-to-pipe configuration. Where the scan perpendicular to the weld is limited on one side, a full V-path will be used for the second direction. The scans provide assurance that planar flaws, regardless of orientation, will be detected and non-planar, construction flaws will be easier to discern from second phase precipitates and grain boundaries.
The qualification process assures that the UT procedure contains sufficient detail and that the personnel have the necessary skills for detecting various types of flaws. The procedure was demonstrated capable of detecting and characterizing flaws in Section XI, Appendix VIII, Supplement 3 mockups. Flaws that are detected with UT will be evaluated in accordance with the acceptance criteria of NC-5330, ASME Code,Section III, which is the same criteria for crack-type flaws detected by RT.
In addition to the UT and the system pressure leakage test, the licensee performed MT on the weld root pass, weld mid-wall pass and the finished outside surface of the weld region. The MT verified that at these three locations, there were no unacceptable flaws. Any flaws that may exist would most likely be no greater than the thickness of one weld bead (one weld pass),
which is approximately 1/8-inch through-wall that should be detectable with the UT.
However, the licensee performed crack growth calculation using a postulated 1/2-inch through-wall crack and concluded that such a flaw would not affect the structural integrity of the weld.
The UT and MT examinations and the crack propagation calculations along with the followup augmented examinations will provide reasonable assurance of the structural integrity of the subject welds.
4.0 CONCLUSION
Based on the above evaluation, the NRC staff concludes that the licensees proposed alternative SPT-008 to use UT and MT in lieu of RT for the main steam trip valve bypass lines will provide reasonable assurance of structural integrity, and that compliance with the ASME Code RT requirement would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the NRC staff authorizes request number SPT-008 for examination of the subject welds for the fourth 10-year ISI interval at Surry, Unit 2.
All other requirements of the ASME Code requirements for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: D. Nauock Date: November 1, 2005
Surry Power Station, Units 1 & 2 cc:
Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
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 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711