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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000293/20240022024-08-21021 August 2024 NRC Inspection Report No. 05000293/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24129A1042024-05-26026 May 2024 Preapplication Readiness Assessment Plan for the Holtec Decommissioning International License Termination Plan ML24136A2382024-05-14014 May 2024 Annual Radiological Environmental Operating Report for 2023 ML24135A3212024-05-14014 May 2024 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2023 IR 05000293/20240012024-05-0707 May 2024 NRC Inspection Report No. 05000293/2024001 L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 L-24-010, Request for Preapplication Readiness Assessment of the Draft License Termination Plan2024-04-22022 April 2024 Request for Preapplication Readiness Assessment of the Draft License Termination Plan L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) IR 05000293/20230032024-02-29029 February 2024 NRC Inspection Report Nos. 05000293/2023003 and 05000293/2023004 L-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) 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) ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2022 ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating 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 ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 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 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) 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 2024-09-18
[Table view] Category:Safety Evaluation
MONTHYEARML21217A1752021-08-0505 August 2021 Amendment No 255 Pilgrim Independent Spent Fuel Storage Installation (ISFSI) Only Physical Security Plan - Public Version ML20328A2972020-12-0101 December 2020 Amendment No. 253 - Non-Safeguards Version ML19276C4202020-01-0202 January 2020 Issuance of Amendment No. 252, Request to Remove Cyber Security Plan Requirements for the Permanently Defueled Condition ML19274C6742020-01-0202 January 2020 Issuance of Amendment No. 251, Revise Emergency Plan and Emergency Action Level Scheme to Address Permanently Defueled Condition ML19142A0432019-12-18018 December 2019 Letter and Safety Evaluation, Exemption to Allow Reduced Emergency Planning Requirements; Revise Radiological Emergency Response Plan Consistent with Permanently Defueled Reactor ML19235A0502019-08-27027 August 2019 Issuance of Amendment No. 249 Order Approving Direct Transfer of Renewed Facility Operating License and ISFSI General License and Conforming Amendment ML19170A2502019-08-22022 August 2019 Enclosure 3, Safety Evaluation for Direct and Indirect Transfer of Renewed Facility Operating License to Holtec Pilgrim, LLC, Owner and Holtec Decommissioning International, LLC, Operator (L-2018-LLO-0003) ML19122A1992019-06-11011 June 2019 Review of Spent Fuel Management Plan ML18284A3752018-11-30030 November 2018 Issuance of Amendment No. 248, Revise Site Emergency Plan for On-Shift and Emergency Response Organization Staffing to Address Permanently Defueled Condition ML18128A0672018-06-0808 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 ML17066A1302017-07-10010 July 2017 Pilgrim Nuclear Power Station - Issuance of Amendment No. 246, Revise Administrative Controls Section of Technical Specifications to Change Staffing and Training Requirements for Permanently Defueled Condition (CAC No. MF9304) 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) ML17058A3252017-04-12012 April 2017 Approval of Certified Fuel Handler Training and Retraining Program ML16250A2232016-10-28028 October 2016 Issuance of Amendments Proposed Changes to Emergency Plan to Revise Training for the on - Shift Chemistry Technician ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16082A4602016-06-0606 June 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule 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 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16124B0872016-05-0303 May 2016 E-mail Review of Safety Evaluation for Proposed Alternative Relief Request No. PRR-51 ML16042A2912016-03-15015 March 2016 Issuance of Proposed Alternative Relief Request PRR-51, Relief from the Requirements of the ASME Code ML16008B0772016-03-0303 March 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML15338A3092016-01-0505 January 2016 Relief Request PRR-50, Relief from the Requirement of the ASME Code, Implementation of Code Case N-702 ML15166A4012015-06-19019 June 2015 Request for Alternative PRR-26 for the Fifth 10-year Inservice Inspection Interval ML15114A0212015-05-0606 May 2015 Issuance of Amendment Regarding the Minimum Critical Power Ratio License Amendment Request ML15103A0692015-04-21021 April 2015 Relief Request PRR-24 Regarding Nozzle-to-Vessel Welds and Nozzle Inner Radii Examination ML15084A0252015-03-23023 March 2015 Non-Proprietary - Safety Evaluation - Fourth 10-Year Interval Inservice Inspection - Request for Relief PRR-24 ML14272A0702015-03-12012 March 2015 Issuance of Amendment 242 Re Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open Transient ML14336A6612014-12-11011 December 2014 Issuance of Amendment Regarding Cyber Security Plan Implementation Schedule Milestone 8 (Tac No. MF3482) ML14295A6852014-10-31031 October 2014 Issuance of Amendment Regarding Heavy Loads to Facilitate Dry Storage Handling Operations ML14210A2662014-08-0808 August 2014 Arkansas, Units 1 & 2, Big Rock Point, James A. Fitzpatrick, Grand Gulf, Unit 1, Indian Point, Units 1, 2 & 3, Palisades, Pilgrim, River Bend, Unit 1, Vermont Yankee, Waterford, Safety Evaluation Quality Assurance Program Manual, Rev. 24 & ML14198A1572014-08-0101 August 2014 Relief Requests PR-03 and PR-05 Regarding the Inservice Testing Program (Tac MF0370) ML14083A6312014-03-27027 March 2014 Relief Request PRR-22 Regarding a Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds ML13149A2152013-05-29029 May 2013 Correction to Staff Assessment Letter to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13127A1792013-05-21021 May 2013 Staff Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML12261A1302012-11-13013 November 2012 Issuance of Amendments to Renewed Facility Operating License Changes in Cyber Security Plan Implementation Milestone ML1220100482012-08-0707 August 2012 Issuance of Amendment No. 237 Revision to Condensate Storage Tank Low Level Trip Setpoint 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 ML11152A0432011-07-22022 July 2011 License Amendment, Cyber Security Plan ML1106500092011-03-28028 March 2011 Issuance of Amendment No. 235 Revised Technical Specifications for Setpoint and Setpoint Tolerance Increases for Safety Relief Valves and Spring Safety Valves ML1100502982011-01-26026 January 2011 Issuance of Amendment Regarding Revised Pressure and Temperature (P-T) Limit Curves and Relocation of P-T Curves to the PTLR ML1022901632010-08-25025 August 2010 Relief Request PRR-20, Alternative Examination Requirements for Nozzle-To-Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 - Pilgrim Nuclear Power Station ML0936208072010-01-22022 January 2010 Cover Letter, (Non-Proprietary) Order Extending the Effectiveness of the Approval of the Indirect Transfer of Facility Operating Licenses for Big Rock Point, Fitzpatrick, Indian Point, Palisades, Pilgrim, and Vermont Yankee Nuclear Power St ML0936208952010-01-22022 January 2010 Safety Evaluation,(Non-Proprietary) Order Extending the Effectiveness of the Approval of the Indirect Transfer of Facility Operating Licenses for Big Rock Point, Fitzpatrick, Indian Point,Palisades,Pilgrim, and Vermont Yankee Nuclear Power ML0928706472009-10-29029 October 2009 Request for Threshold Determination Under 10 CFR 50.80-Big Rock Point, James A. FitzPatrick Nuclear Power Plant, Indian Point Nuclear Generating Nos. 1, 2 and 3, Palisades, Pilgrim, Vermont Yankee ML0927301372009-10-0909 October 2009 Safety Evaluation by the Office of Nuclear Reactor Regulation Corporate Restructuring Conversion of Companies and Stock Split-Off by Entergy Nuclear Operations, Inc and Subsidiaries 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 ML0906402242009-03-26026 March 2009 License Amendment, Revised Technical Specifications (TS) Section 2.1.2, Safety Limit Minimum Critical Power Ratio (SLMCPR) for Two-Loop and Single-Loop Operation ML0815703662008-11-20020 November 2008 License Amendment, Issuance of Amendment Adoption of TSTF-448, Revision 3, Control Room Envelope Habitability 2021-08-05
[Table view] |
Text
June 29, 2006Mr. Michael R. Kansler, PresidentEntergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PILGRIM NUCLEAR POWER STATION - RELIEF REQUEST NO. PIL-05-R-001 (TAC NO. MC8299)
Dear Mr. Kansler:
By letter dated June 29, 2005, Entergy Nuclear Operations, Inc. (the licensee), requested relieffrom the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 1998 Edition with the 2000 Addendum, Subsection IWA-4540, Pressure Testing of Class 1, 2 and 3 items. The licensee proposed an alternative to use the ASME Code,Section XI, 2001 Edition through 2003 Addendum in lieu of the Code of Record for the fourth 10-year inservice inspection (ISI) program.The Nuclear Regulatory Commission staff has concluded that the alternative proposed for thefourth 10-year ISI interval will provide an acceptable level of quality and safety. The bases ofgranting the relief are provided in the enclosed safety evaluation. Therefore, pursuant to Title10 of the Code of Federal Regulations (10CFR) 50.55a(a)(3)(i), the proposed alternative is authorized for the Pilgrim's fourth 10-year ISI interval, which ends on June 30, 2015.If you have any questions regarding this approval, please contact the Pilgrim Project Manager,James Shea, at 301-415-1388. Sincerely,/RA/Richard J. Laufer, ChiefPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-293
Enclosure:
As statedcc w/encl: See next page
ML061420470 *See SE dated 05/16/06OFFICELPL1-1/PMLPL1-1/PMLPL1-1/LACFEBOGCLPL1-1/BCNAMEBSingalJSheaSLittleKAGruss*HWedewerRLaufer DATE5/19/066/19/066/15/065/16/066/28/066/29/06 Pilgrim Nuclear Power Station cc:Regional Administrator, Region IU. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415Senior Resident InspectorU. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Post Office Box 867 Plymouth, MA 02360Chairman, Board of Selectmen11 Lincoln Street Plymouth, MA 02360ChairmanNuclear Matters Committee Town Hall 11 Lincoln Street Plymouth, MA 02360Chairman, Duxbury Board of SelectmenTown Hall 878 Tremont Street Duxbury, MA 02332Office of the CommissionerMassachusetts Department of Environmental Protection One Winter Street Boston, MA 02108Office of the Attorney GeneralOne Ashburton Place 20th Floor Boston, MA 02108Director, Radiation Control ProgramCommonwealth of Massachusetts Executive Offices of Health and Human Services 174 Portland Street Boston, MA 02114Secretary of Public SafetyExecutive Office of Public Safety One Ashburton Place Boston, MA 02108 Director, Massachusetts EmergencyManagement Agency Attn: James Muckerheide 400 Worcester Road Framingham, MA 01702-5399Mr. William D. MeinertNuclear Engineer Massachusetts Municipal Wholesale Electric Company
P.O. Box 426 Ludlow, MA 01056-0426Mr. Kevin H. BronsonGeneral Manager, Plant Operations Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill RoadPlymouth, MA 02360-5508Mr. Michael A. BalduzziSite Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill RoadPlymouth, MA 02360-5508Mr. Stephen J. BethayDirector, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill RoadPlymouth, MA 02360-5508Mr. Bryan S. FordManager, Licensing Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill RoadPlymouth, MA 02360-5508
cc:
Pilgrim Nuclear Power StationMr. Gary J. Taylor Chief Executive Officer Entergy Operations 1340 Echelon Parkway Jackson, MS 39213Mr. John T. HerronSr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. Oscar LimpiasVice President, Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. Christopher SchwarzVice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. John F. McCannDirector, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
Ms. Charlene D. FaisonManager, LicensingEntergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Mr. Michael J. ColombDirector of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Assistant General CounselEntergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601Ms. Stacey LousteauTreasury Department Entergy Services, Inc.
639 Loyola Avenue New Orleans, LA 70113Mr. James Sniezek5486 Nithsdale Drive Salisbury, MD 21801-2490Mr. Michael D. Lyster5931 Barclay Lane Naples, FL 34110-7306Mr. Garrett D. Edwards814 Waverly Road Kennett Square, PA 19348 EnclosureSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELIEF REQUEST NO. PIL-05-R-001PILGRIM NUCLEAR POWER STATIONDOCKET NO. 50-29
31.0INTRODUCTION
By letter dated June 29, 2005, Agencywide Documents Access and Management System(Accession No. ML051920157), Entergy Nuclear Operations, Inc (the licensee) submitted Relief Request No. PIL-05-R-001, related to the fourth 10-year interval inservice inspection (ISI) program for the Pilgrim Nuclear Power Station (Pilgrim). The licensee requested the Nuclear Regulatory Commission (NRC) authorization to use the American Society of MechanicalEngineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2001 Edition through the 2003 Addendum, in lieu of the 1998 Edition through the 2000 Addendum in regard to Subsection IWA-4540, "Pressure Testing of Class 1, 2, and 3 items." The licensee's proposed use of portions of subsequent edition and addenda to the ASME Code,Section XI, that is incorporated by reference in 10 CFR 50.55a(b)(2), is in accordance with Title 10 of the Code ofFederal Regulations (10 CFR) 50.55a(g)(4)(iv). The NRC staff's review focused on whether therelated requirements of the 2001 Edition ASME Code,Section XI through the 2003 Addendum are being met. The licensee's request applies to the fourth 10-year ISI interval of Pilgrim. The licensee's request would be applicable during Pilgrim's fourth 10-year ISI interval, which ends on June 30, 2015.
2.0REGULATORY EVALUATION
Section 50.55a(g) of 10 CFR requires that ISI of ASME Code Class 1, 2, and 3 components beperformed in accordance with Section XI of the ASME Code and applicable addenda, except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). According to 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph 50.55a(g) may be used, when authorized by the NRC, if an applicant demonstratesthat the proposed alternatives would provide an acceptable level of quality and safety or if the specified requirement 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 (includingsupports) 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 (ISI) 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 ISI of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition andaddenda 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 ISI Code of Record for the fourth 10-year inspection interval for Pilgrim is the 1998 Edition through the 2000 Addendum of the ASME Code,Section XI.
Pursuant to 10 CFR 50.55a(g)(4)(iv), inservice examination of component s and systempressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) of this section, subject to the limitations and modifications listed in paragraph (b) of this section, and subject to Commission approval.
Portions of editions and addenda may be used provided that all related requirements of the respective editions or addenda are met.Regulatory Issue Summary 2004-16, "Use of Later Editions and Addenda to ASME CodeSection XI for Repair/Replacement Activities," provides additional information regarding the use of editions and addenda of the ASME Code subsequent to the Code of Record.2.1Code Requirements for Which Relief is RequestedPursuant to 10 CFR 50.55a(g)(4)(iv), the licensee has proposed an alternative to the 2000Addendum for pressure testing of Class 1, 2, and 3 items by implementing the requirements of subsection IWA-4540 of the ASME Code,Section XI, 2001 Edition through the 2003 Addendum which states the following:(a)The repair/replacement activities performed by welding or brazing on a pressure-retaining boundary shall include a hydrostatic or system leakage test in accordance withIWA-5000, prior to, or as part of, return to service. The changes to the ASME Code,Section XI, subparagraph IWA-4540(a) for pressure testing of class 1, 2, and 3 items following repair/replacement activities performed by welding or brazing on a pressure-retaining boundary do not affect other parts of the ASME Code. The 2001 Edition through the 2003 Addendum of the ASME Code,Section XI requires that brazed joints and welds made in the course of a repair/replacement activity require pressurization and a VT-2 visual examination during the test. This added requirement would also be followed under the Pilgrim Repair/Replacement Program. 2.2ASME Code RequirementsFor repair/replacement activities performed by welding or brazing on pressure-retainingboundary, the ASME Code,Section XI, 1998 Edition through the 2000 Addendum, Subsection IWA-4540, "Pressure Testing of Classes 1, 2, and 3 Items" requires performance of either a system hydrostatic test in accordance with Subsection IWA-5000 or performance of thefollowing prior to, or as part of, return to service:a.Non-destructive examination (NDE) of the repair in accordance with the 1992 Edition orlater ASME Code,Section III.b.Owner's requirement prior to return to service.
c.A system leakage test in accordance with IWA-5000. 2.3Licensee's Basis for Requesting Relief The licensee's proposed alternative to use a portion of the later edition ASME Code, Section XIis in accordance with 10 CFR 50.55a(g)(4)(iv), and the NRC staff noted that the proposedASME Code has been incorporated by reference in 10 CFR 50.55a(b)(2). However, since the ISI Code of Record is the 1998 Edition through the 2000 Addendum of the ASME Code, the licensee has requested relief from a portion of its ISI Code of Record and is required to meet the related requirements of the proposed later Code. 3.0NRC STAFF EVALUATIONThe NRC staff's review focused on whether all related requirements pertaining to the portion ofthe ASME Code in regard to repair/replacement activities performed by welding or brazing on a pressure retaining boundary in the proposed edition and addenda to the Code are being met.
The staff, therefore, reviewed Subsection IWA-4540 pertaining to pressure testing of Class 1, 2, and 3 items repaired by welding or brazing in the 2001 Edition through the 2003 Addendum of the ASME Code,Section XI. The staff noted that the later Code offers more flexibility t han the1998 ASME Code,Section XI through 2000 Addendum while providing the same level of assurance of quality and safety in regard to the pressure testing of components repaired by welding or brazing as identified below. Test Requirement for Repairas stated in IWA-45401998 ASME Code Section XI through 2000 Addendum 2001 ASME Code Section XI through 2003 Addendum Required Pressure testSystem hydrostatic test perSubsection IWA-5000 or System hydrostatic orsystem l eakage test perSubsection IWA-5000 andAlternative Pressure testSystem leakage test withNDE to 1992 Edition or laterof ASME Code,Section III Pressurization and VT-2visual examination of thewelded/brazed joint only There is no other related requirement in regard to pressure testing of repaired componentsaddressed in Subsection IWA-4540 which would be applicable for the licensee in adopting to the later edition of the ASME Code and its Addenda. The licensee has stated that it wouldcomply with the related requirements of the 2001 ASME Code,Section XI through the 2003 Addendum for pressure testing of Class 1, 2, and 3 items repaired by welding or brazing. Since the 2001 Edition through 2003 Addendum of ASME Code,Section XI, was incorporated by reference in 10 CFR 50.55a(b)(2) and the licensee complies with the related requirements of this Code, the proposed alternative in Relief Request No. PIL-05-R-001 is authorized pursuant to 10 CFR 50.55a(a)(3)(i). The use of the later ASME Code and Addenda will provide anacceptable level of quality and safety.
4.0CONCLUSION
The licensee's proposed alternative in Relief Request No. PIL-05-R-001 pertains to the use ofSubsection IWA-4540 of the 2001 ASME Code,Section XI including the 2003 Addendum in lieu of the applicable 1998 ASME Code Section XI including the 2000 Addendum. The later ASME Code and its Addenda has been incorporated by reference in 10 CFR 50.55a(b)(2), and the licensee stated that it would meet the related requirements of the ASME Code in regard topressure testing components repaired by welding or brazing. The NRC staff has determinedthat the proposed alternative in Relief Request No. PIL-05-R-001 will provide an acceptablelevel of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the staff authorizes the alternative for the fourth 10-year ISI interval for Pilgrim. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including a third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: P. PatnaikDate: June 29, 2006