Letter Sequence Other |
---|
|
|
MONTHYEARML0820600342008-07-25025 July 2008 Acceptance Review Regarding Third Ten-Year Interval Inservice Inspection Program Relief Request Numbers I3R-03 and I3R-04 Project stage: Acceptance Review ML0832600992009-01-15015 January 2009 Request for Relief No. 13R-03 for the Third 10-Year Inservice Inspection Interval Regarding the System Pressure Test Project stage: Other 2008-07-25
[Table View] |
|
---|
Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RA-20-0312, Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval2020-11-0404 November 2020 Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval ML20080G9502020-04-0505 April 2020 Relief from the Requirements of the ASME Code ML19018A0252019-02-26026 February 2019 Relief Request I3R-18, Regarding Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Inservice Inspection Program for Containment, Third Ten-Year Interval RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) ML18283B5442018-11-20020 November 2018 Relief from the Requirements of the ASME Code, Section XI, Reactor Vessel Closure Head Penetration Nozzle Repair Technique RA-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 22018-11-12012 November 2018 Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML15342A0432016-01-0606 January 2016 Supplemental Safety Evaluation to Relief Request I3R-15 for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Inspection Program - Third 10-Year Interval ML15203A7022015-09-18018 September 2015 Relief Request 13R-15 for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Inspection Program - Third 10 - Year Interval ML14093A0752014-04-11011 April 2014 Relief Request I3R-13 for Reactor Vessel Closure Head Penetration Nozzle 37 Repair Inservice Inspection Program - Third 10-Year Interval ML13238A1542013-09-13013 September 2013 Relief Request I3R-11 for Reactor Vessel Closure Head Penetration Nozzles Repair Inservice Inspection Program - Third 10-Year Interval ML13017A3492013-01-28028 January 2013 Relief Request I3R-10 for Spent Fuel Pool Cooling Piping Inservice Inspection Program - Third 10-Year Interval HNP-12-133, Relief Request I3R-10 Spent Fuel Pool Cooling Piping, Request for Additional Information Response2012-12-17017 December 2012 Relief Request I3R-10 Spent Fuel Pool Cooling Piping, Request for Additional Information Response ML12270A2582012-10-0202 October 2012 Relief Request 13R-09 for Reactor Vessel Closure Head Penetration Nozzles Repair Inservice Inspection Program Third 10-Year Interval HNP-12-060, Relief Request I3R-09 Reactor Vessel Closure Head Nozzle Repairs Inservice Inspection Program - Third Interval, Request for Additional Information Response2012-05-18018 May 2012 Relief Request I3R-09 Reactor Vessel Closure Head Nozzle Repairs Inservice Inspection Program - Third Interval, Request for Additional Information Response HNP-12-054, Relief Request I3R-09 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval2012-05-0303 May 2012 Relief Request I3R-09 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval ML1014800292010-06-17017 June 2010 Acceptance Review Regarding a Relief Request to Defer an American Society of Mechanical Engineers Code-Required Repair of a Service Water System Weld Unit the Refueling Outage ML1008204632010-04-0808 April 2010 Request for Relief 2R1-018 for the Second 10-Year Interval Inservice Inspection Program Plant ML0912701882009-05-19019 May 2009 Acceptance Review Regarding Relief Requests on Final Documentation for the Second 10-Year Inservice Inspection Program for Limited Coverage of Welds in Multiple Exam Categories HNP-08-045, Second Ten-Year Interval Inservice Inspection Program-Final Documentation Including Requests for Relief in Accordance with 10 CFR 50.55a2009-02-0505 February 2009 Second Ten-Year Interval Inservice Inspection Program-Final Documentation Including Requests for Relief in Accordance with 10 CFR 50.55a ML0832601362009-01-21021 January 2009 Request for Relief No. 13R-04 for the Third 10-Year Inservice Inspection Interval Regarding System Pressure Testing of Class 1 Systems (Tac MD8744) ML0832600992009-01-15015 January 2009 Request for Relief No. 13R-03 for the Third 10-Year Inservice Inspection Interval Regarding the System Pressure Test ML0727607372007-10-10010 October 2007 Relief Request No. 1 Regarding Proposed Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements for Pressurizer Nozzle Weld Overlay Repairs HNP-07-073, Withdrawal of the Relief Request from ASME Code Inservice Testing Requirements for the Second 10-Year Interval2007-05-15015 May 2007 Withdrawal of the Relief Request from ASME Code Inservice Testing Requirements for the Second 10-Year Interval ML0608703872006-04-17017 April 2006 Relief Request No. 2R1-015 for the Second 10-Year Inservice Inspection Interval ML0608700432006-04-0707 April 2006 Relief, Relief Request 2R1-016 and 2R1-017 for the Second 10 Yr Inservice Inspection Interval HNP-05-128, Relief Request from Inservice Inspection Program No. 2R1-015 Alternative to ASME Code Section XI, IWA-4000 Requirements2005-11-18018 November 2005 Relief Request from Inservice Inspection Program No. 2R1-015 Alternative to ASME Code Section XI, IWA-4000 Requirements ML0412900022004-05-0303 May 2004 Relief, ASME Code, Section XI, Appendix Viii, Supplement 10 2023-09-25
[Table view] Category:Letter
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 ML22138A4012022-05-26026 May 2022 Project Manager Reassignment ML22101A2822022-05-0606 May 2022 Regulatory Audit Summary Related to the Review of License Amendment Regarding Revising the Flood Hazard Protection Scheme IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 ML22034A5352022-02-0202 February 2022 Notification of Licensed Operator Initial Examination 05000400/2022301 2024-01-30
[Table view] Category:Safety Evaluation
MONTHYEARML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation ML22083A0272022-03-23023 March 2022 Safety Evaluation -Harris Safety Evaluation -EPID L-2021-LLA-0149 - Revise TS Related to Reactor Protection System ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency ML21320A0012022-01-20020 January 2022 Issuance of Amendment No. 189 to Regarding Administrative Change to Reflect Development of a Technical Requirements Manual ML21316A2482022-01-19019 January 2022 Issuance of Amendment No. 188, Regarding Revision of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML21155A2132021-08-26026 August 2021 Plant ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21047A4702021-04-0808 April 2021 Issuance of Amendment No. 185 Regarding Reduction of Reactor Coolant System Minimum Flow Rate and Update to the Core Operating Limits Report References ML21047A3142021-04-0202 April 2021 Issuance of Amendment No. 184 Regarding Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times RITSTF Initiative 4B ML21033B0072021-03-22022 March 2021 Issuance of Amendment No, 183 to Correct Non-Conservative Technical Specification Related to Reactor Coolant System Pressure/Temperature Limits ML21069A0642021-03-18018 March 2021 Alternative to ASME Section XI Code Requirements to Defer Repair of Emergency Service Water System Socket Weld ML21035A1322021-03-16016 March 2021 Issuance of Amendment No. 182 Regarding Technical Specifications Related to Accident Monitoring Instrumentation, and Refueling Operations Instrumentation ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20259A5122020-12-0808 December 2020 Issuance of Amendment No. 181 Regarding Adoption of 10 CFR Part 50, Appendix J, Option B, for Type B and C Testing and for Permanent Extension of Type a, B, and C Leak Rate Testing Frequencies(L-2019-LLA-0256) ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20281A2792020-10-13013 October 2020 Correction Letter to Amendment No. 179 Regarding Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML20212L5942020-09-29029 September 2020 Issuance of Amendment No. 179 Regarding Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20099F5052020-06-29029 June 2020 Issuance of Amendment No. 177 Regarding Elimination of Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications ML19225C0692019-09-19019 September 2019 Issuance of Amendment No. 175 Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints ML19192A0122019-09-17017 September 2019 Issuance of Amendment No. 174 Adopt Title 10 of the Code of Federal Regulations 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19108A1732019-07-18018 July 2019 Issuance of Amendment No. 173 Regarding Emergency Plan Emergency Action Level Scheme Change ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML18288A1392019-04-29029 April 2019 Issuance of Amendments 171, 263 Revising Technical Specifications to Support Self Performance of Core Reload Design and Safety Analyses ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18347A3852019-03-29029 March 2019 Issuance of Amendment No. 169, Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML19018A0252019-02-26026 February 2019 Relief Request I3R-18, Regarding Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Inservice Inspection Program for Containment, Third Ten-Year Interval ML18303A0482018-12-0404 December 2018 Extension of Reactor Pressure Vessel Surveillance Report for Capsule Z ML18283B5442018-11-20020 November 2018 Relief from the Requirements of the ASME Code, Section XI, Reactor Vessel Closure Head Penetration Nozzle Repair Technique ML18262A3032018-11-19019 November 2018 Issuance of Amendment No. 168 Regarding License Amendment Request for Rod Control Movable Assemblies Technical Specifications Changes ML18204A2862018-10-22022 October 2018 Issuance of Amendment No. 167 Regarding (CAC MF9996; EPID 2017-LLA-0303) ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18060A4012018-04-10010 April 2018 Redacted Issuance of Amendments Revising TSs for Methodology Reports DPC-NE-3008-P, Revision 0, and DPC-NE-3009-P, Revision 0) (CAC Nos. MF8439 and MF8440; EPID L-2016-LLA-0012) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads 2023-09-25
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 15, 2009 Chris L. Burton, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - RELIEF REQUEST 3R-03 FOR THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL REGARDING THE SYSTEM PRESSURE TEST (TAC NO. MD8743)
Dear Mr. Burton:
By letter dated April 29, 2008, Carolina Power and Light Company (the licensee), now doing business as Progress Energy Carolinas, Inc., submitted Relief Request (RR) 13R-03, pertaining to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirement on system pressure testing for the third 1O-year inservice inspection (lSI) interval at the Shearon Harris Nuclear Power Plant, Unit 1.
In RR 13R-03, the licensee requested relief from performing the system pressure test of the Reactor Vessel Head Flange Seal Leak Detection Piping at the ASME Code-required test pressure corresponding to nominal operating pressure during system operation.
Based on the information provided in RR 13R-03, the U.S. Nuclear Regulatory Commission (NRC) staff concluded that compliance with the ASME Code requirement in regard to the test pressure is impractical.
Therefore, pursuant to Title 10 of the Code of Federal Regulations, Part 50.55a(g)(6)(i), the NRC authorizes the lSI program alternatives proposed in RR 13R-03 for the third 10-year lSI interval at the Shearon Harris Nuclear Power Plant, Unit 1.
The NRC staff's safety evaluation is enclosed. If you have any questions regarding this matter, please contact Marlayna Vaaler at (301) 415-3178.
Sincerely,
.//17 i ' 7(,."':V~
'1 v
l'2
... (/
I Thomas H. Boyce,', hief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION THIRD 10-YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUEST 13R-03 REGARDING SYSTEM PRESSURE TESTING SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-400
1.0 INTRODUCTION
By letter dated April 29, 2008, Carolina Power and Light Company (the licensee), now doing business as Progress Energy Carolinas, Inc., submitted Relief Request (RR) 13R-03, pertaining to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirement on system pressure testing for the third 1O-year inservice inspection (lSI) interval at the Shearon Harris Nuclear Power Plant, Unit 1.
In RR 13R-03, the licensee requested relief from performing the system pressure test of the Reactor Vessel Head Flange Seal Leak Detection Piping at the ASME Code-required test pressure corresponding to nominal operating pressure during system operation. The licensee stated that the configuration of the leak detection piping precludes implementing the ASME Code-required pressure test either with the vessel head installed or while removed.
The U.S. Nuclear Regulatory Commission (NRC) staff evaluated the licensee's proposed alternative pursuant to Title 10 of the Code of Federal Regulations (10 CFR)
Part 50.55a(g)(6)(i), in order to determine that compliance with the ASME Code requirement in regard to the test pressure for system pressure testing of the Reactor Vessel Head Flange Seal Leak Detection Piping is impractical.
2.0 REGULATORY REQUIREMENTS The requirements of 10 CFR 50.55a(g) specify that inservice inspection of ASME Code Class 1, 2, and 3 components be performed in accordance with Section XI of the ASME Code and applicable addenda, except where specific written relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i). 10 CFR 50.55a(g)(5)(iii) states that "if the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in 10 CFR 50.4, information to support the determination." The requirements of 10 CFR 50.55a(g)(6)(i) allow the Commission to evaluate determinations that code requirements are impractical. 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 that could result if the requirements were imposed on the facility.
Enclosure
-2 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 preservice 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 lSI of components and system pressure tests conducted during the first 1O-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 lSI Code of Record for the third 1O-year inservice inspection interval at the Shearon Harris Nuclear Power Plant, Unit 1 is the 2001 Edition of the ASME Code,Section XI through the 2003 Addenda.
3.0 TECHNICAL EVALUATION
3.1 System/Component(s) for Which Relief is Requested Reactor Vessel Head Flange Seal Leak Detection Piping 3.2 ASME Code Requirements Table IWC-2500-1, Examination Category C-H, Item Number C7.1 0, requires that all Class 2 pressure retaining components be subject to a system leakage test with a VT-2 visual examination once per inspection period (40 months) in accordance with IWC-5220. The system leakage test shall be conducted at the system pressure obtained while the system, or portion of the system, is in service performing its normal operating function.
3.3 Licensee's Request for Relief Relief is requested from performing the system leakage test at a pressure corresponding to the nominal operating pressure during system operation. The licensee proposed an alternative pressure testing requirement in lieu of the system leakage test required under IWC-5221 for the Reactor Vessel Head Flange Seal Leak Detection Piping.
3.4 Licensee's Basis for Requesting Relief According to the licensee's application, the Reactor Vessel Head Flange Seal Leak Detection Piping is separated from the reactor pressure boundary by one passive membrane that is an O-ring located on the vessel flange. A second O-ring is located on the opposite side of the tap in the vessel flange. This piping is required during plant operation in order to indicate failure of the inner flange seal O-ring. Failure of the inner O-ring would result in annunciation of a high pressure alarm in the control room. Failure of the inner O-ring is the only condition under which this line would be pressurized.
The configuration of this piping precludes system pressure testing while the vessel head is removed because the configuration of the vessel tap, coupled with the high test pressure requirement (approximately 1045 pounds per square inch gauge), prevents the tap in the flange from being temporarily plugged or connected to other piping. The opening in the flange is
-3 smooth walled, making the effectiveness of a temporary seal very limited. Failure of this seal could possibly cause ejection of the device used for plugging or connection to the vessel.
The configuration also precludes pressure testing with the vessel head installed because the seal prevents complete filling of the piping, which has no vent available. The top head of the vessel contains two grooves that hold the O-rings. The O-rings are held in place by a series of retainer clips that are housed in recessed cavities in the flange face. If a pressure test were performed with the head on, the inner O-ring would be pressurized in a direction opposite to what it would experience in normal operation. This test pressure would result in a net inward force on the inner O-ring that would tend to push it into the recessed cavities that house the retainer clips. The thin O-ring material would very likely be damaged by this inward force.
3.5 Licensee's Proposed Alternative A VT-2 visual examination will be performed on the Reactor Vessel Head Flange Seal Leak Detection Piping during flood-up of the refueling pool with the vessel head off during each refueling outage. The hydrostatic head developed due to the water above the vessel flange with the leak detection line filled during flood-up will allow for the detection of any gross indications in the piping. This examination will be performed during each refueling outage to meet the ASME Code requirement on the frequency of examination as specified in Table IWC-2500-1.
4.0 STAFF EVALUATION The ASME Code,Section XI, requires that all Class 2 pressure retaining components be subject to a system leakage test with a VT-2 visual examination once per inspection period. The test pressure for the system leakage test shall correspond to the nominal operating pressure of the system. In RR 13R-03, the licensee requested relief from performing a system leakage test of the Reactor Vessel Head Flange Seal Leak Detection Piping at the ASME Code-required test pressure corresponding to the nominal operating pressure during system operation.
The piping is located between the inner and outer O-ring seals of the vessel flange and is required during plant operation in order to detect failure of the inner flange seal O-ring. The design of this line makes the ASME Code-required system leakage test impractical either with the vessel head in place or removed. During a system leakage test, the subject piping cannot be filled completely with water since, due to its configuration, there is no vent mechanism to remove entrapped air from the line either with the vessel head in place or removed.
If a pressure test was to be performed with the head in place, the space between the inner and outer O-ring seals would be pressurized. The test pressure would exert a net inward force on the inner O-ring that would tend to push it into the recessed cavities that house the retainer with the possibility of damaging the inner O-ring seal. The configuration of this piping also precludes system leakage testing while the vessel head is removed because the odd configuration of the vessel tap, coupled with the high test pressure requirement, prevents the tap in the flange from being temporarily plugged or connected to other piping. In addition, the opening in the flange is smooth walled, making the effectiveness of a temporary seal very limited. Failure of this seal could cause ejection of the device used for plugging or connection to the vessel.
In order to perform the system leakage test in accordance with the ASME Code requirements, the Reactor Vessel Head Flange Seal Leak Detection Piping would have to be redesigned,
- 4 fabricated, and installed. This would represent an impractical means of complying with the ASME standard. As an alternative to the ASME Code requirements, the licensee has proposed to perform a VT-2 visual examination of the Reactor Vessel Head Flange Seal Leak Detection Piping when the reactor cavity is flooded with water during each refueling outage. The NRC staff believes that the hydrostatic head developed due to the water above the vessel flange with the leak detection line filled during flood-up will allow for detection of any gross inservice flaws present in the subject piping, and hence, the proposed alternative testing method would continue to provide a reasonable assurance of structural integrity. Therefore, the NRC authorizes the licensee's proposed alternative in RR 13R-03.
5.0 CONCLUSION
Based on the NRC staff's evaluation, a system leakage test of the Reactor Vessel Head Flange Seal Leak Detection Piping at the ASME Code-required test pressure corresponding to the nominal operating pressure during system operation is impractical and would cause a burden on the licensee if the requirement were to be imposed. In addition, the licensee's proposed alternative continues to provide reasonable assurance of structural integrity.
Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), the proposed alternative in RR 13R-03 is authorized for the third 10-year lSI interval at the Shearon Harris Nuclear Power Plant, Unit 1.
The relief granted is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. All other requirements of the ASME Code,Section XI, for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Prakash Patnaik Date: January 15, 2009
January 15, 2009 Chris L. Burton, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - RELIEF REQUEST 3R-03 FOR THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL REGARDING THE SYSTEM PRESSURE TEST (TAC NO. MD8743)
Dear Mr. Burton:
By letter dated April 29, 2008, Carolina Power and Light Company (the licensee), now doing business as Progress Energy Carolinas, Inc., submitted Relief Request (RR) 13R-03, pertaining to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirement on system pressure testing for the third 1O-year inservice inspection (lSI) interval at the Shearon Harris Nuclear Power Plant, Unit 1.
In RR 13R-03, the licensee requested relief from performing the system pressure test of the Reactor Vessel Head Flange Seal Leak Detection Piping at the ASME Code-required test pressure corresponding to nominal operating pressure during system operation.
Based on the information provided in RR 13R-03, the U.S. Nuclear Regulatory Commission (NRC) staff concluded that compliance with the ASME Code requirement in regard to the test pressure is impractical.
Therefore, pursuant to Title 10 of the Code of Federal Regulations, Part 50.55a(g)(6)(i), the NRC authorizes the lSI program alternatives proposed in RR 13R-03 for the third 1O-year lSI interval at the Shearon Harris Nuclear Power Plant, Unit 1.
The NRC staff's safety evaluation is enclosed. If you have any questions regarding this matter, please contact Marlayna Vaaler at (301) 415-3178.
Sincerely, Ira!
Thomas H. Boyce, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrPMMVaaler RidsNrrLACSola RidsNrrDorlLpl2-2 RidsOgcRp RidsAcrsAcnw_MailCTR Prakash Patnaik, NRR RidsRgn2MailCenter (RMusser) RidsNrrDciCsgb ADAMS Accession Number' ML083260099 NRR-028 OFFICE LPL2-2/PM LPL2-2/LA CSGB/BC OGC LPL2-2/BC NAME MVaaler CSoia AHiser* DRoth NLO** TBoyce DATE 12/2/2008 11/26/2008 9/26/2008 12/12/2008 1/15/09
- by memo **wlth comments OFFICIAL RECORD COPY