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MONTHYEARML0911304562009-04-30030 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 Project stage: Other 2009-04-30
[Table View] |
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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
[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
~...~ REGUl UNITED STATES
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- -i' Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508
SUBJECT:
RELIEF REQUEST ISI-2008-1, USE OF LATER EDITION AND ADDENDA OF ASME CODE, SECTION XI FOR REPAIR AND REPLACEMENT, PRESSURE TESTING, AND DESTRUCTIVE TESTING ACTIVITIES - PILGRIM NUCLEAR POWER STATION (TAC NO. ME0238)
Dear Sir or Madam:
By letter dated December 1, 2008 (Agencywide Document and Management System (ADAMS)
Accession No. ML083500367), as supplemented by letter dated March 17,2009 (ML090900519),
Entergy Nuclear Operations, Inc. (the licensee) requested permission to use: (a) the 2001 Edition through 2003 Addenda of the American Society of Mechanical Engineers (ASIVIE) Boiler and Pressure Vessel Code (Code)Section XI for inservice inspection (lSI) related activities associated with repairs, replacements, pressure testing, and nondestructive examination (NDE),
and (b) the 2001 Edition of the ASME Code,Section XI for performance demonstration of ultrasonic examinations, in its Pilgrim Nuclear Power Station. The licensee's request relates to the ASME Code Class 1, 2, 3 and metal containment components, component supports, and welds in the ASME Code,Section XI pressure boundary. The duration of this request is for remainder of the fourth 1O-year lSI interval which ends on July 30, 2015. The results of the Nuclear Regulatory Commission staff's review are provided in the enclosed safety evaluation.
If you have any questions regarding this approval, please contact the Pilgrim Project Manager, James Kim, at 301-415-4125.
Sincerely, Richard V. Guzman, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket 1\10. 50-293
Enclosure:
As stated cc w/encl: Distribution via ListServ
...~p.l\ REGilt _ UNITED STATES
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/}J .L WASHINGTON, D.C. 20555-0001
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- i' SAFETY EVALUATION BYTHE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF ISI-2008-1 ENTERGY NUCLEAR OPERATIONS. INC.
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated December 1. 2008, as supplemented by letter dated March 17, 2009, Entergy Nuclear Operations, Inc. (the licensee) submitted Request ISI-2008-1 for Nuclear Regulatory Commission (NRC) review and approval. In the letter, the licensee requested permission to use the 2001 Edition through 2003 Addenda of the American Society of Mechanical Engineers (AS ME)
Boiler and Pressure Vessel Code (Code)Section XI for inservice inspection (lSI) related activities associated with repairs, replacements, pressure testing, and nondestructive examination (NDE),
as specified in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(gX4 )(iv). In addition, the licensee requested to use the 200'1 Edition of the ASME Code,Section XI for performance demonstration of ultrasonic examinations, as specified in 10 CFR 50.55a(b)(2)(xxiv). This request is applicable to Pilgrim Nuclear Power Station (PNPS) and relates to the ASME Code Class 1, 2, 3 and metal containment (MC) components, component supports, and welds in the ASME Code,Section XI pressure boundary. This request is submitted in accordance with Regulatory Issue Summary (RIS) 2004-16, dated October 19, 2004. The duration of this request is for the remainder of the fourth 1O-year lSI interval which ends on July 30, 2015.
2.0 REGULATORY REQUIREMENTS Pursuant to 10 CFR 50.55a(b)(2), the use of ASME Code,Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components" 1970 Edition through 1976 Winter Addenda and 1977 Edition (Division 1) through 2004 Edition (Division 1) are approved, subjected to limitations and modifications.
Pursuant to 10 CFR 50.55a(g), the ISlof components including supports that are classified as ASME Code Class 1, 2, and 3 is to be performed in accordance with the ASME Code,Section XI of applicable editions and addenda, except where specific written relief has been granted by the NRC.
Pursuant to 10 CFR 50.55a(g)(4), throughout the service life of a boiling or pressurized nuclear power facility, components (including supports) which are classified as the ASME Code Class 1, 2, and 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of the ASME Code and Addenda that become effective subsequent to editions specified in paragraphs (g)(2) and (g)(3) of this section and that are incorporated by reference in 10 CFR 50.55a(b), to the extent practical within the limitations of design. geometry and materials of construction of the components.
Enclosure
-2 Pursuant to 10 CFR 50.55a(g)(4), the lSI of Class MC pressure retaining components and their integral attachments must meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI and its Addenda incorporated by reference in paragraph (b)(2) and subject to the limitations listed in paragraph (b)(2)(vi) and the modifications listed in paragraphs (b)(2)(viii) and (b)(2)(ix) of 10 CFR 50.55a. These requirements shall be met to the extent practical within the limitations of design, geometry, and materials of construction of the components.
According to the 10 CFR 50.55a(g)(4)(ii), the lSI examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements of the latest Edition and Addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month inspection interval, subject to the limitations and modifications listed therein.
10 CFR 50.55a(g)(4)(iv) states that lSI examination of components of system pressure tests may meet the requirements set forth in subsequent Editions and Addenda of the ASME Code,Section XI provided that they are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modiHcations listed in 10 CFR 50.55a(b), and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective Editions or Addenda are met.
Regulatory Issue Summary (RIS) 2004-16, dated October 19,2004, maintains that although the repair, replacement, and modification of plant components activities in the ASME Code,Section XI are not explicitly mentioned in 10 CFR 50.55a(g)(4) and associated subparagraphs, these activities are not separate and distinct and are included under in-service examinations requirements of the 10 CFR 50.55a(g)(4)(iv).
3.0 PROPOSED REQUEST ISI-2008-1
3.1 ASME Code Components Affected
The licensee has stated that its request relates to the ASME Code Class 1, 2, and 3 components and MC components, component supports, and welds in the ASME Code,Section XI pressure boundary at PNPS.
3.2 Applicable Code Edition and Addenda The licensee has stated that the lSI related activities such as repairs, replacements, pressure testing, and NDE at PNPS are currently performed in accordance with the 1998 Edition through 2000 Addenda of the ASME Code,Section XI with various NRC approved alternatives which are specified in the PNPS lSI programs.
3.3 Proposed Alternative The licensee has proposed to use, at its PNPS, the 2001 Edition through 2003 Addenda of the ASME Code,Section XI for lSI related activities associated with repairs, replacements, pressure testing, and NDE, as specified in 10 CFR 50.55a(g)(4)(iv). In addition, the licensee has proposed to use, at its PNPS. the 2001 Edition of the ASME Code,Section XI for performance demonstration of ultrasonic examinations, as specified in 10 CFR 50.55a(b)(2)(xxiv).
-3 The licensee has proposed to utilize all "Articles" (e.g. IWA-4000, IWA-5000) from every "Subsection" (e.g. IWA, IWB, etc.) of the 2001 Edition through 2003 Addenda of the ASME Code,Section XI that could be used or referenced for the performance of repair, replacement, pressure testing, and NDE activities. The licensee has also proposed to comply with all "Mandatory Appendices" of the 2001 Edition through 2003 Addenda of the ASME Code,Section XI.
The licensee stated that it will comply with all applicable 10 CFR 50.55a conditions and limitations including:
- With regard to the performance of lSI examinations and tests, the licensee will continue to select, plan, and schedule these lSI inspection activities as specified in IWA-IWB-IWC-,
IWD-, IWE-, and IWF-2500 or NRC approved lSI alternatives in accordance with the PNPS current lSI Program Plan.
- Performance demonstration of ultrasonic examinations will be conducted in accordance with the 2001 Edition, No Addenda, of Appendix VIII of the ASME Code,Section XI to comply with 10 CFR 50.55a(b )(2)(xxiv).
- The f\lDE provision in IWA-4540(a)(2) of the 2001 Edition through 2002 Addenda of the ASME Code,Section XI are applied when performing system leakage tests after repair and replacement activities involving welding or brazing to comply with 10 CFR 50.55a(b)(2)(xx)(B).
- Pressure testing of mechanical joints of Class 1, 2, and 3 items are performed in accordance with IWA-4540(c) of the 1998 Edition, No Addenda, of the ASME Code,Section XI to comply with 10 CFR 50.55a(b)(2)(xxvi).
- All NRC conditions, limitations, and restrictions in 10 CFR 50.55a that are applicable to the 2001 Edition through 2003 Addenda of the ASME Code,Section XI will be met.
4.0 STAFF EVALUATION The NRC staff has evaluated the licensee's Request ISI-2008-1, dated December 1, 2008, with a supplement dated March 17,2009, pursuant to 10 CFR 50.55a(g)(4)(iv). In response to the NRC staff's request for additional information, the licensee has provided in its supplement, (a) correction to two inadvertent typographical errors in its Request ISI-2008-1 regarding the citation of paragraphs 10 CFR 50.55a(b)(2)(xxiv) and 10 CFR 50.55a(b)(2)(xxvi), and (b) response to the NRC staff's question regarding Article IWA-2000, for which the licensee has requested to use certain subarticles of both the 1998 Edition through 2000 Addenda and the 2001 Edition through 2003 Addenda of the ASME Code,Section XI.
The NRC staff finds acceptable that the licensee will follow the requirements of system leakage tests in 10 CFR 50.55a(b)(2)(xx)(B) which states that the NDE provision in IWA-4540(a)(2) of the 2002 Addenda of the ASME Code,Section XI must be applied when performing system leakage tests after repair and replacement activities performed by welding or brazing on a pressure retaining boundary using the 2003 Addenda through the latest edition and addenda incorporated by reference in paragraph 10 CFR 50.55a(b)(2).
-4 The NRC staff finds acceptable that the licensee will follow the incorporation of the performance demonstration initiative and addition of ultrasonic examination criteria in 10 CFR 50.55a(b)(2)(xxiv) which prohibits the use of Appendix VIII and its supplements and Article 1-3000 of Section XI of the ASME Code, 2002 Addenda through the latest Edition and Addenda incorporated by reference in paragraph 10 CFR 50.55a(b)(2).
The NRC staff finds acceptable that the licensee will follow the requirements in 10 CFR 50.55a(b)(2)(xxvi). This paragraph states that the repair and replacement activity provisions in IWA-4540(c) of the 1998 Edition of the ASIVIE Code,Section XI for pressure testing Class 1, 2, and 3 mechanical joints must be applied when using the 2001 Edition through the latest Edition and Addenda of the ASME Code,Section XI incorporated by reference in paragraph 10 CFR 50.55a(b)(2).
The NRC staff finds acceptable that Articles IWE-3000 and IWE-5000 will be used for the lSI activities associated with the performance of repair/replacement and pressure testing of Class MC components. The licensee stated that it will comply with all related requirements in ASME Code,Section XI, by utilizing all articles from every applicable subsection, including all mandatory appendices, of the 2001 Edition through the 2003 Addenda of ASME Code,Section XI, that could be used or referenced for the performance of repair/replacement and pressure testing activities of Class MC components.
The NRC staff finds acceptable that lSI of snubbers are performed in accordance with IWF-5000 except that the preservice and lSI examinations and tests are performed in accordance with Subsection ISTD of the OM Code, 1998 Edition/2000 Addenda as required by IWF-5200 and IWF-5300. The alternative 'use of Subsection ISTD of the OM Code is acceptable pursuant to 10 CFR 50.55a(b)(3)(v).
In its letter dated March 17,2009, the licensee stated that Request ISI-2008-1 does not apply to the selection, planning, or scheduling of lSI examinations and tests at PNPS. The licensee intends to continue to perform activities related to the selection, planning, or scheduling of lSI examinations and tests at PNPS in accordance with the 1998 Edition through 2000 Addenda of the ASME Code,Section XI which is the present Code of Record for PNPS. Request ISI-2008-1 applies only to the performance of lSI related activities such as repairs, replacements, pressure testing, and NDE using the 2001 Edition through 2003 Addenda of the ASME Code,Section XI at PNPS.
The NRC staff is satisfied that the licensee has listed all related requirements in the 2001 Edition through 2003 Addenda of the ASME Code,Section XI, that are relevant to repairs, replacements, pressure testing, and NDE activities. The NRC staff is satisfied that the licensee has satisfactorily identified the conditions specified in 10 CFR 50.55a(b) on the use of 2001 Edition through 2003 Addenda of the ASME Code,Section XI in Request ISI-2008-1. The NRC staff has already determined the acceptability of using the 2001 Edition through 2003 Addenda of the ASME Code,Section XI as reflected in 10 CFR 50.55a(b). In addition, the licensee has agreed to all of the conditions in 10 CFR 50.55a(b)(2) related to the use of the 2001 Edition through 2003 Addenda of the ASME Code,Section XI. Therefore, the NRC staff finds the use of Request ISI-2008-1 to be acceptable.
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5.0 CONCLUSION
The NRC staff concludes that the proposed Request ISI-2008-1 for the ASME Code Class 1,2, and 3 piping, MC components, component supports, and welds provides an acceptable level of quality and safety at PNPS. Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), the use of Request ISI-2008-1 for the ASME Code Class 1,2, and 3 piping, MC components, component supports, and welds at PNPS for the remainder of the fourth 10-year lSI interval which ends on July 30, 2015, is approved.
Principal Contributors: Ali Rezai Farhad Farzam Date: April 30, 2009
April 30, 2009 Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 SUB..IECT: RELIEF REQUEST ISI-2008-1, USE OF LATER EDITION AND ADDENDA OF ASME CODE, SECTION XI FOR REPAIR AND REPLACEMENT, PRESSURE TESTING, AND DESTRUCTIVE TESTING ACTIVITIES - PILGRIM NUCLEAR POWER STATION (TAC NO. ME0238)
Dear Sir or Madam:
By letter dated December 1, 2008 (Agencywide Document and Management System (ADAMS)
Accession No. ML083500367), as supplemented by letter dated March 17, 2009 (ML090900519),
Entergy Nuclear Operations, Inc. (the licensee) requested permission to use: (a) the 2001 Edition through 2003 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code)Section XI for inservice inspection (lSI) related activities associated with repairs, replacements, pressure testing, and nondestructive examination (NDE),
and (b) the 2001 Edition of the ASME Code,Section XI for performance demonstration of ultrasonic examinations, in its Pilgrim Nuclear Power Station. The licensee's request relatesto the ASME Code Class 1, 2, 3 and metal containment components, component supports, and welds in the ASME Code,Section XI pressure boundary. The duration of this request is for remainder of the fourth 10-year lSI interval which ends on July 30, 2015. The results of the Nuclear Regulatory Commission staff's review are provided in the enclosed safety evaluation.
If you have any questions regarding this approval, please contact the Pilgrim Project Manager, James Kim, at 301-415-4125.
Sincerely,
/RA!
Richard V. Guzman, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosure:
As stated cc w/encls: Distribution via ListServ DISTRIBUTION:
PUBLIC A. Rezai, Nrr RidsNrrDciCpnb Resource RidsAcrsAcnw_MailCTR Resource RidsNrrLASLittle F. Farzam, Nrr RidsNrrDeEmcb Resource RidsNrrDorlDpr Resource M. Gray, RI RidsNrrPMJKim Rids NrrDorl Lp11-1 Resou rce Rids Rg n1MaiICenter Accession No ... ML091130456 *See memos dated OFFICE LPLI-1/PM LPLI-1/LA CPNB/BC EI\I1CB/BC LPL 1-1 /BC(A)
NAME JKim SLittie TChen* MKhanna* RGuzman DATE 4/30/09 4/30/09 3/30/2009 4/15/2009 4/30/09 OFFICIAL RECORD COPY