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MONTHYEARML15253A1962015-09-0101 September 2015 Request for Approval of Relief Request (PRR)-53, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) to ASME Section XI, Appendix Viii, Supplement 11 for Qualification Requirements for Full Structural Overlaid Wrought Austenitic. Project stage: Supplement ML15286A0042015-10-0909 October 2015 NRR E-mail Capture - Acceptance Review: Pilgrim Relief Request (PRR)-53, Proposed Alternative to ASME for Full Structural Overlaid Austenitic Piping Welds Project stage: Acceptance Review ML16194A3262016-08-0404 August 2016 Issuance of Relief Request No. PRR-53 - Relief from ASME Code, Section XI Requirements for Ultrasonic Inspection Qualifications of Weld Overlays Project stage: Approval 2015-09-01
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Category:Code Relief or Alternative
MONTHYEARML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 ML17093A8942017-05-12012 May 2017 Pilgrim Nuclear Power Station - Relief Requests PNPS-ISI-001 and PNPS-ISI-002, Relief from ASME Code Volumetric Examination Requirements for the Fourth 10-Year Inservice Inspection Interval (CAC Nos. MF8092 and MF8093) ML16257A5732016-09-15015 September 2016 Issuance of Relief Request No. PRR-52-Relief from ASME Code, Section XI Requirements for Pressure Testing of Class 1 Pressure Retaining Components as a Result of Repair/Replacement Activity and Use of Code Case N-795 ML16194A3262016-08-0404 August 2016 Issuance of Relief Request No. PRR-53 - Relief from ASME Code, Section XI Requirements for Ultrasonic Inspection Qualifications of Weld Overlays ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16042A2912016-03-15015 March 2016 Issuance of Proposed Alternative Relief Request PRR-51, Relief from the Requirements of the ASME Code ML16057A1772016-02-16016 February 2016 Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of ML15338A3092016-01-0505 January 2016 Relief Request PRR-50, Relief from the Requirement of the ASME Code, Implementation of Code Case N-702 CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division ML15103A0692015-04-21021 April 2015 Relief Request PRR-24 Regarding Nozzle-to-Vessel Welds and Nozzle Inner Radii Examination ML14198A1572014-08-0101 August 2014 Relief Requests PR-03 and PR-05 Regarding the Inservice Testing Program (Tac MF0370) ML12174A1472012-07-10010 July 2012 Safety Evaluation for Relief Request PRR-21, Rev 4, to Install a Weld Overlay on RPV-n14-1 Standby Liquid Control Safe-End Nozzle Weld at Pilgrim JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP2011-10-0303 October 2011 Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP ML0923705492009-09-11011 September 2009 Relief Request (PRR)19, Install a Weld Overlay on Jet Pump Instrumentation Nozzle Weld RPV-N9A-1- Pilgrim Nuclear Power Station ML0911304562009-04-30030 April 2009 Relief Request ISI-2008-1, Use of Later ASME Section XI Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Destructive Testing Activities-Pilgrim Nuclear Power Station CNRO-2009-00003, Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activ2009-03-17017 March 2009 Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activities ML0813004082008-05-27027 May 2008 Relief Request No. RV-07, Alternate to the ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves - Pilgrim Nuclear Power Station ML0805801992008-02-14014 February 2008 Request for Approval of Relief Request No. PRR-16, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection ML0724201612007-09-27027 September 2007 Relief for the Reactor Core Shroud Stabilizer Assemblies ML0618701632006-06-28028 June 2006 Request for Approval of ASME Code, Section XI, Third Ten-Year Relief Request, PRR-42, Examinations of Component Welds with Less than Essentially 100% Examination Coverage ML0606601322006-04-0505 April 2006 Relief Request No. PIL-05-R-002, ML0602400552006-03-22022 March 2006 Relief Request No. PRR-9, ML0601201272006-02-17017 February 2006 Relief Request No. PPR-05 ML0519902762005-08-29029 August 2005 Entergy Relief Request PR-03 High-Pressure Coolant Injection Pump ML0519201572005-06-29029 June 2005 Fourth Ten-Year Inservice Inspection Program Plan and the Associated Relief Requests for NRC Approval ML0429203582005-02-25025 February 2005 Request - Alternative Repair Plan for Generic Letter 88-01, Reactor Pressure Vessel Nozzle-To Cap Weld in the Control Rod Drive Return Line ML0423100082005-01-0606 January 2005 Relief Request No. PRR-29, Relief from System Hydrostatic Test Requirements for Small Bore ASME Code Class 1 Reactor Coolant Pressure Boundary Vent, Drain and Branch Lines and Connections ML0427406642004-10-14014 October 2004 Relief Request Nos. R-33, R-71, R 3-40(A) and R-41, James A. FitzPatrick Nuclear Power Plant, Indian Point Nuclear Generating Unit Nos. 2 and No. 3 and Pilgrim Nuclear Power Station ML0429505512004-10-12012 October 2004 Response to NRC Request for Additional Information and Revised Relief Request, PRR-39, Rev. 1 ML0417401842004-07-0606 July 2004 Relief Request, Nos. RR-34 and PRR for the Third 10-Year Inservice Inspection (ISI) Interval, MC1999 and MC2006 ML0410700882004-07-0606 July 2004 Relief Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-600 ML0407807052004-04-30030 April 2004 Relief Request, Fourth 10-Year Inservice Testing (IST) Program and Request for Approval of IST Relief Requests ML0408205162004-03-22022 March 2004 Relief Request Nos. RR-68, RR3-37, and PRR-34 (TAC MC1559, MC1560, & MC1561) ML0402600132004-02-26026 February 2004 Pilgrim Relief Request Review, Relief Request No. 38, Relief from ASME Code, Section XI, Appendix Viii, Supplement 11, Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds. JPN-03-020, Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-6002003-08-11011 August 2003 Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600 ML0312701492003-05-0808 May 2003 Relief Request, Relief from ASME Code, Section XI, Appendix Viii, Supplement 10, Performance Demonstration for Ultrasonic Examination Systems ML0306402042003-04-11011 April 2003 Relief Request, Examinations of Reactor Pressure Vessel Circumferential Shell Welds ML0224002392002-09-17017 September 2002 Relief, Code Relief Request from Section XI, the Pump and Valve Inservice Testing Program Regarding Inclusion of Additional Excess Flow Check Valves ML0216800622002-06-0505 June 2002 Code Relief, Pilgrim Relief Request (PRR)-27 Relief from 1989 ASME Code Section XI Requirements for Certification of VT-2 Visual Examination Personnel 2018-06-08
[Table view] Category:Letter
MONTHYEARL-24-002, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2024-02-0202 February 2024 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML23342A1182024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23334A1822023-11-30030 November 2023 Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary November 2021 Through October 2023 L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) L-23-011, 10 CFR 72.48 Biennial Change Summary Report2023-10-27027 October 2023 10 CFR 72.48 Biennial Change Summary Report IR 05000293/20234012023-08-31031 August 2023 NRC Inspection Report No. 05000293/2023401 & 2023001 (Cover Letter Only) IR 05000293/20230022023-08-0404 August 2023 NRC Inspection Report No. 05000293/2023002 L-23-008, Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI)2023-05-23023 May 2023 Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI) ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating Report, January 1 Through December 31, 2022 ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML23069A2782023-03-13013 March 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1 Subsequent License Renewal Application ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000293/20220042023-02-15015 February 2023 NRC Inspection Report No. 05000293/2022004 ML22356A0712023-01-31031 January 2023 Issuance of Exemption for Pilgrim Nuclear Power Station ISFSI Regarding Annual Radioactive Effluent Release Report - Cover Letter ML22347A2782022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 L-22-041, Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension2022-12-0909 December 2022 Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension IR 05000293/20220032022-11-18018 November 2022 NRC Inspection Report No. 05000293/2022003 L-22-036, Decommissioning Trust Fund Agreement2022-11-0808 November 2022 Decommissioning Trust Fund Agreement ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22266A1922022-09-23023 September 2022 and Pilgrim Nuclear Power Station - Request to Withdraw Prior Submissions from NRC Consideration ML22272A0352022-09-22022 September 2022 S. Lynch-Benttinen Letter Regarding U.S. Citizen Intent to Sue U.S. Fish and Wildlife and NOAA Fisheries Representing the Endangered Species (Na Right Whale) Which Will Be Adversely Affected by Holtec International Potential Actions ML22269A4202022-09-22022 September 2022 Citizen Lawsuit ML22241A1122022-08-29029 August 2022 Request for Exemption from 10 CFR 72.212(a)(2), (b)(2), (b)(3), (b)(4), (B)(5)(i), (b)(11), and 72.214 for Pilgrim ISFSI Annual Radioactive Effluent Release Report IR 05000293/20220022022-08-12012 August 2022 NRC Inspection Report No. 05000293/2022002 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22193A1662022-07-28028 July 2022 LTR-22-0154-1 - Heather Govern, VP, Clean Air and Water Program, Et Al., Letter Regarding Radioactive Wastewater Disposal from the Pilgrim Nuclear Power Station (Docket No. 05000293) ML22175A1732022-07-28028 July 2022 LTR-22-0153-1 - Response Letter to D. Turco, Cape Downwinders, from A. Roberts, NRC, Regarding Holtec-Pilgrim Plans to Dump One Million Gallons of Radioactive Waste Into Cape Cod Bay ML22154A4882022-06-0101 June 2022 Letter from Conservation Law Foundation Regarding Irradiated Water Release from Pilgrim ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22136A2602022-05-16016 May 2022 Submittal of Annual Radiological Environmental Operating Report for January 1 Through December 31, 2021 ML22136A2572022-05-16016 May 2022 Submittal of Annual Radioactive Effluent Release Report for January 1 Through December 31, 2021 ML22102A0932022-05-12012 May 2022 LTR-22-0067 Response to Matthew P. Levesque, President, Barnstable Town Council Regarding Irradiated Water Release from Pilgrim IR 05000293/20220012022-05-11011 May 2022 NRC Inspection Report No. 05000293/2022001 ML22104A0542022-04-30030 April 2022 LTR-22-0093 Response to Sheila Lynch-Benttinen, Regarding Irradiated Water Release from Pilgrim L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22152A2592022-04-25025 April 2022 Zaccagnini Letter Dated 04/25/22 ML22152A2642022-04-19019 April 2022 Flynn Letter Dated 04/19/22 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22130A6762022-03-14014 March 2022 Decola Ltr Dtd 03/14/22 Re Potential Discharge of Radioactive Water from Pilgrim Nuclear Power Station ML22041B0762022-03-0707 March 2022 03-07-22 - Letter to the Honorable William R. Keating, Responds to Letter Regarding Proposed Release of Irradiated Water at Pilgrim Nuclear Power Station Into Cape Cod Bay ML22054A2962022-02-23023 February 2022 Annual ISFSI Radioactive Effluent Release Report for 2021 2024-02-02
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 4, 2016 Vice President, Operations Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508
SUBJECT:
PILGRIM NUCLEAR POWER STATION - ISSUANCE OF RELIEF REQUEST NO. PRR RELIEF FROM ASME CODE, SECTION XI REQUIREMENTS FOR ULTRASONIC INSPECTION QUALIFICATIONS OF WELD OVERLAYS (CAC NO. MF6697)
Dear Sir or Madam:
By letter dated September 1, 2015 (Agencywide Documents Access and Management System Accession No. ML15253A196), Entergy Nuclear Operations, Inc. (the licensee) submitted Relief Request No. PRR-53 to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for ultrasonic inspection qualifications of weld overlays at the Pilgrim Nuclear Power Station (Pilgrim).
Specifically, pursuant to Title 1O of the Code of Federal Regulations (10 CFR),
Section 50.55a(z)(1 ), the licensee requested to use the proposed a.lternative in Relief Request No. PRR-53 on the basis that the alternative provides an acceptable level of quality and safety.
The licensee proposed to use the Performance Demonstration Initiative (POI) Program as an alternative to the requirements in the ASME Code,Section XI, 2001 Edition, Appendix VIII, Supplement 11, "Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds," at Pilgrim for its Fifth 10-year inservice inspection (ISi) interval.
The NRC staff determined that using the POI inspection qualification program in lieu of ASME Code,Section XI, Appendix VIII, Supplement 11, provides an adequate level of rigor to provide reasonable assurance that the procedures, equipment, and personnel qualified under this program would be able to find fabrication flaws and service-induced flaws in the weld-overlaid piping. As set forth in the enclosed Safety Evaluation, the NRC staff concludes that the alternatives proposed in Relief Request No. PRR-53 provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore, pursuant to 10 CFR 50.55a(z)(1 ), PRR-53 is authorized for use during the Fifth 10-year ISi interval for Pilgrim, until December 31, 2017.
If you have any questions, please contact the project manager, Booma Venkataraman, at (301) 415-2934 or Booma.Venkataraman@nrc.gov.
Sincerely, Travis L. Tate, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
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 PROPOSED ALTERNATIVE RELIEF REQUEST NO. PRR-53 ENTERGY NUCLEAR OPERATIONS, INC.
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated September 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15253A196), Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted Relief Request No. PRR-53 to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for ultrasonic inspection qualifications of weld overlays at the Pilgrim Nuclear Power Station (Pilgrim).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.55a(z)(1 ), the licensee requested to use the proposed alternative in Relief Request No. PRR-53 on the basis that it provides an acceptable level of quality and safety. The licensee proposed to use the Performance Demonstration Initiative (POI) Program as an alternative to the requirements in the ASME Code,Section XI, 2001 Edition, Appendix VIII, Supplement 11, "Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds," at Pilgrim for its Fifth 10-year inservice inspection (ISi) interval.
2.0 REGULATORY REQUIREMENTS Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," to the extent practical, within the limitations of design, geometry, and materials of construction of the components.
However, 10 CFR 50.55a(z) states, in part, that alternatives to the requirements of 10 CFR 50.55a(g) may be used, when authorized by the NRC, if the licensee demonstrates that (1) the proposed alternatives would provide an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Enclosure
Based on analysis of the regulatory requirements, the NRC staff concludes that regulatory authority exists to authorize the proposed alternative pursuant to 10 CFR 50.55a(z)(1).
3.0 TECHNICAL EVALUATION
3.1 ASME Code Component Affected The components covered in this relief request are various Class 1 Pressure Retaining Piping Welds subject to ultrasonic examination using procedures, personnel, and equipment qualified by demonstration to ASME Section XI, Appendix VIII, Supplement 11.
3.2 ASME Code Requirements The code of record for the Fifth 10-year ISi interval is the 2007 Edition with 2008 Addenda of ASME Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components."
ASME Code,Section XI repair/replacement, pressure testing and nondestructive testing activities at Pilgrim are being maintained to the 2001 Edition through the 2003 Addenda for the Fifth 10-Year Interval until December 31, 2017, using Alternative Request PRR-26, which was NRC approved on June 19, 2015 (ADAMS Accession No. ML15166A401 ).
The requirements for qualifying ultrasonic procedures, personnel, and equipment for weld overlay examinations are described in ASME Code,Section XI, Appendix VIII, Supplement 11, "Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds."
3.3 Licensee's Proposed Alternative to the ASME Code The licensee requests approval to use the POI Program for weld overlay inspection qualifications as an alternative to the requirements within the 2001 Edition ASME Section XI, Appendix VIII, Supplement 11.
3.4 Reason for Request The licensee stated, in part, in its application that this alternative request is being submitted for authorization because the ASME Section XI at Pilgrim will not be updated from the 2001 Edition through the 2003 Addenda until after December 31, 2017. Implementation of Appendix VIII, Supplement 11 requirements of the 2001 Edition using the alternatives based on the use of the POI Program requirements in this request are still needed at Pilgrim when using the 2001 Edition through the 2003 Addenda of Section XI.
Further, the licensee stated that the alternative qualification requirements are based on the POI Program requirements. The U.S. nuclear industry utilizes the POI program for the qualification of equipment, procedures and personnel. The POI Program does not meet the letter of the Code requirements identified in ASME Section XI, Appendix VIII, Supplement 11 of the 2001 Edition or the latest edition and addenda. As a result, other alternative requests have been authorized throughout the industry for the implementation of the POI program in lieu of Supplement 11, and Pilgrim needs the authorization of this request to use the POI program.
3.5 Licensee's Basis for Use Compliance with the proposed alternatives in this request, versus those in the 2001 Edition of ASME Section XI, Appendix VIII, Supplement 11, are needed to support qualification requirements for the examination of weld overlays. The proposed alternative qualification requirements are very similar to the 2001 Edition of ASME Section XI, Appendix VIII, Supplement 11 requirements.
The primary differences between the ASME Code,Section XI, Appendix VIII requirements and the POI program are listed below:
- 1) A scope statement has been added to reflect the applicability of Supplement 11.
- 2) The use of 3-inch minimum grading unit length in Appendix VIII vs. an 1-inch minimum grading unit size in the POI program.
- 3) The names of the grading units were changed from "base metal" and "overlay fabrication" to "inservice" and "preservice," respectively.
- 4) The term "base metal flaws" was changed to "service-induced flaws" and the term "overlay fabrication flaws" was changed to "fabrication-induced flaws."
- 5) Provisions have been added for qualification of "Optimized" weld overlays.
- 6) Qualification for width sizing of laminar flaws is now addressed.
3.6 Duration of the Alternative The licensee stated this request will apply to a portion of the Fifth 10-Year Interval, which starts on July 1, 2015 and will continue to December 31, 2017.
- 3. 7 NRC Staff Evaluation of the Alternative The licensee proposed to use the POI qualification program for weld overlay inspections in lieu of the requirements of ASME Code,Section XI, Appendix VIII, Supplement 11, on the basis that the POI Program provides an acceptable level of quality and safety.
The NRC staff performed a comparison of the POI qualification program and the ASME Code,Section XI, Appendix VIII, Supplement 11 requirements. Based on the review of the two programs, the NRC staff determined that the POI Program for qualifying procedures, equipment, and personnel, as described in the proposed alternative, is technically very similar to ASME Code,Section XI, Appendix VIII, Supplement 11. For the qualification of full structural weld overlays, the differences between the Appendix VIII requirements and the POI Program are largely administrative or semantic in nature, such as changing "base metal flaws" to "service-induced flaws." The major technical difference between the 2001 Edition of the Code and the POI program is the use of 3-inch long minimum grading units in ASME Code,Section XI, Appendix VIII, versus 1-inch long minimum grading units in the POI program. This
difference was reviewed by the NRC staff to determine the effects on the qualification program and found the use of 1-inch grading units was acceptable. The change in grading unit size is incorporated into the 2007 Edition of ASME Code,Section XI, Appendix VIII, which is incorporated by reference in 10 CFR 50.55a.
Based upon the NRC comparison of the POI weld overlay inspection qualification program and ASME Code Section XI, Appendix VIII, Supplement 11, the NRC determined that using the POI inspection qualification program in lieu of ASME Code,Section XI, Appendix VIII, Supplement 11 requirements provides an adequate level of rigor to provide reasonable assurance that the procedures, equipment, and personnel qualified under this program would be able to find fabrication flaws and service-induced flaws in weld overlays.
4.0 CONCLUSION
As set forth above, the NRC staff concludes that the proposed alternative to use the POI Program to qualify procedures, equipment, and personnel for ultrasonic inspections of weld overlays at Pilgrim for the Fifth 10-year ISi interval provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore, the NRC staff authorizes relief request PRR 53 pursuant to 10 CFR 50.55a(z)(1) during the Fifth 10-year ISi interval at Pilgrim until December 31, 2017.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: Stephen Cumblidge D~e: August 4, 2016
If you have any questions, please contact the project manager, Booma Venkataraman, at (301) 415-2934 or Booma.Venkataraman@nrc.gov.
Sincerely, IRA/
Travis L. Tate, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosure:
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