Letter Sequence Approval |
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MONTHYEARML0708603392007-02-22022 February 2007 Technical Specifications, Modify the TSs to Extend the Use of the Current Pressure-Temperature Limits as Specified in TS Figures 3.6.1, 3.6.2, and 3.6.3 Through the End of Operating Cycle 18 Project stage: Other ML0705303842007-03-26026 March 2007 License Amendment, Issuance of Amendment Extension of Pressure-Temperature Limits Specified in Technical Specifications Project stage: Approval 2007-02-22
[Table View] |
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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:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML21251A1732021-10-21021 October 2021 Enclosure 1 - Pilgrim Amendment No. 257 ISFSI Only Emergency Plan ML21203A0482021-08-24024 August 2021 License Amendment No. 256 ML21217A1752021-08-0505 August 2021 Amendment No 255 Pilgrim Independent Spent Fuel Storage Installation (ISFSI) Only Physical Security Plan - Public Version ML21103A0562021-05-12012 May 2021 Amendment Pilgrim Ps -Alternative Measures Rev 20 ML20335A1832020-12-0101 December 2020 Amendment Pilgrim Ps ISFSI to Incorporate ISFSI II ML20328A2972020-12-0101 December 2020 Amendment No. 253 - Non-Safeguards Version ML19274C6742020-01-0202 January 2020 Issuance of Amendment No. 251, Revise Emergency Plan and Emergency Action Level Scheme to Address Permanently Defueled Condition ML19276C4202020-01-0202 January 2020 Issuance of Amendment No. 252, Request to Remove Cyber Security Plan Requirements for the Permanently Defueled Condition ML19275E4252019-10-28028 October 2019 Issuance of Amendment No. 250, Revise Technical Specifications to Permanently Defueled TS and Revise Facility License for Permanently Defueled Condition 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 ML19170A1012019-08-22022 August 2019 Letter, Order Approving Direct and Indirect Transfer of Renewed Facility Operating License to Holtec Pilgrim, LLC, Owner and Holtec Decommissioning International, LLC, Operator 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 ML18295A0252018-11-16016 November 2018 Correction to Remove Technical Specification Pages from Authority File Related to Amendment Nos. 169 and 177 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) ML16250A2232016-10-28028 October 2016 Issuance of Amendments Proposed Changes to Emergency Plan to Revise Training for the on - Shift Chemistry Technician ML16082A4602016-06-0606 June 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule ML15114A0212015-05-0606 May 2015 Issuance of Amendment Regarding the Minimum Critical Power Ratio License Amendment Request 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 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 ML0910404232012-05-29029 May 2012 Issuance of Renewed License for Pilgrim Nuclear Generating Station 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 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 ML0727503942007-11-0505 November 2007 License Amendment, Issuance of Amendment Control Rod Operability, Scram Insertion Time, and Control Rod Accumulator Requirements ML0723400092007-08-23023 August 2007 Revised License Pages of Facility Operating License DPR-35 B.5.b ML0708711652007-05-14014 May 2007 Issuance of Amendment Adoption of Technical Specification Task Force (TSTF) Change TSTF-372, the Addition of Limiting Condition for Operation (LCO) 3.0.8 on the Inoperability of Snubbers ML0707404192007-04-25025 April 2007 License Amendment, Issuance of Amendment Single Control Rod Withdrawal Allowances ML0705303842007-03-26026 March 2007 License Amendment, Issuance of Amendment Extension of Pressure-Temperature Limits Specified in Technical Specifications ML0705306462007-03-26026 March 2007 Issuance of License Amendment 226 Adoption of Technical Specification Task Force (TSTF) Change TSTF-484 Use of TS 3.10.1 for Scram Time Testing Activities. ML0624303372006-09-20020 September 2006 License Amendment 225 Regarding Revised Reactor Coolant System Leakage Detection Instrumentation Requirements and Actions ML0622803042006-09-14014 September 2006 Issuance of Amendment Relocation of Technical Specifications ML0617200682006-08-0909 August 2006 Issuance of License Amendment 223 Regarding Administrative Changes and Relocation of Certain Technical Specification Responsibilities ML0618400322006-08-0404 August 2006 Issuance of License Amendment 222 Deletion of Requirement Related to NRC Approval of Engineering Evaluation for Elevated Relief Valve Discharge Pipe Temperature ML0606000402006-04-13013 April 2006 Issuance of Amendment Removal of Main Steam Isolation Valve Twice Per Week Testing Surveillance Requirement ML0607402142006-04-13013 April 2006 License Amendment 221 Regarding Revised Rod Worth Minmizer Bypass Allowances ML0601701192006-04-12012 April 2006 Issuance of Amendment Single Recirculation Loop Operation ML0531404332006-04-10010 April 2006 Issuance of Amendment Revised Applicability for Containment Oxygen and Differential Pressure Limits ML0518700032005-08-29029 August 2005 Issuance of License Amendment 217, Surveillance Frequency Improvements ML0518702572005-07-29029 July 2005 License Amendment 216 Revised Action for Scram Discharge Volume Vent and Drain Valves ML0501804932005-03-16016 March 2005 License Amendment No. 211, Revise Reactor Vessel Hydrostatic and Leak Testing Requirements ML0500504862005-02-0202 February 2005 Issuance of Amendment Changes to Technical Specifications Table 3.2.C-1 ML0423001372005-01-0505 January 2005 License Amendment, Revision to the Reactor Pressure Vessel Material Surveillance Program ML0434902432004-12-27027 December 2004 Issuance of Amendment Engineering Evaluation Submitted Pursuant to Technical Specifications Section 3.6.D.3 and 3.6.D.4 ML0419704502004-08-17017 August 2004 License Amendment, Issuance of Amendment Re.: Multiple Control Rod Removal, Limiting Condition for Operation 3/4.10.D ML0411000092004-07-22022 July 2004 License Amendment, Eliminate Requirements for Hydrogen Analyzers 2021-08-05
[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
March 26, 2007 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: EXTENSION OF PRESSURE-TEMPERATURE LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS (TAC NO. MD4093)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 227 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated January 15, 2007.
The proposed changes modify the TSs to extend the use of the current pressure-temperature limits as specified in TS Figures 3.6.1, 3.6.2, and 3.6.3 through the end of operating cycle 18.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register Notice.
Sincerely,
/RA/
James Kim, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
- 1. Amendment No. 227 to License No. DPR-35
- 2. Safety Evaluation cc w/encls: See next page
March 26, 2007 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: EXTENSION OF PRESSURE-TEMPERATURE LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS (TAC NO. MD4093)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 227 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated January 15, 2007.
The proposed changes modify the TSs to extend the use of the current pressure-temperature limits as specified in TS Figures 3.6.1, 3.6.2, and 3.6.3 through the end of operating cycle 18.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register Notice.
Sincerely,
/RA/
James Kim, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
- 1. Amendment No. 227 to License No. DPR-35
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1-1 RPowell, RI RidsOGC RP PDI-I R/F RidsNrrLASLittle RidsNrrPMJKim GHill (2)
RidsAcrsAcnwMail LLois Accession Number: ML070530384 OFFICE LPL1-1/PM LPL1-1/LA SBWB/BC OGC LPL1-1/BC NAME JKim SLittle GCranston SUttal DPickett DATE 3/01/07 3/01/07 3/05/07 3/22/07 2/23/07 OFFICIAL RECORD COPY
ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 227 License No. DPR-35
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by Entergy Nuclear Operations, Inc. (the licensee) dated January 15, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 227, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Douglas V. Pickett, Chief (Acting)
Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: March 26, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 227 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 3 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3/4.6-9 -
3/4.6-10 -
3/4.6-11 -
3/4.6-12 -
3/4.6-13 -
3/4.6-14 3/4.6-9 3/4.6-15 3/4.6-10 3/4.6-16 3/4.6-11
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 227 TO FACILITY OPERATING LICENSE NO. DPR-35 ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated January 15, 2007 (ADAMS Accession No. ML070230293), Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the Pilgrim Nuclear Power Station (Pilgrim) Technical Specifications (TSs). Specifically, the proposed changes would extend the use of the current pressure-temperature (PT) limits as specified in TS Figures 3.6.1, 3.6.2, and 3.6.3 through the end of operating cycle 18. The licensee has chosen the RAMA code to calculate the vessel fluence. The extension time is needed by Entergy to design, submit, and execute an action plan to improve the reactor vessel dosimetry. The dosimetry is needed to benchmark the RAMA code in order to satisfy a RAMA limitation.
The licensee is requesting a two fuel cycles extension of the current PT limits in order to submit and execute a plan to improve plant dosimetry and use the RAMA calculated fluence values to the end of the extended license. The NRC staff finds the request reasonable based on the estimated margin for 48 effective full-power years (EFPYs) of operation. The 48 EFPY peak vessel fluence value is lower than the value used for the current PT curves calculated for 32 EFPYs. In addition, the license amendment request includes two commitments, i.e., (1) to
[s]ubmit to the NRC an action plan to improve benchmarking data to support approval of new P-T curves for Pilgrim using R.G. 1.190 guidance by September 15, 2007, and (2) [s]ubmit updated P-T curves for Pilgrim to the NRC for approval by June 8, 2010.
2.0 REGULATORY EVALUATION
Fast neutron irradiation (E > 1.0 MeV) modifies the material properties of the reactor vessel.
The level of irradiation determines material properties, therefore, it is subject to the requirements of General Design Criteria (GDC) 30, Quality of Reactor Coolant Pressure Boundary, GDC 31, Fracture Prevention of Reactor Coolant Pressure Boundary, and GDC 14, Reactor Coolant Pressure Boundary. GDC 30 requires that the vessel ...shall be designed, fabricated, erected and tested to the highest quality standards possible. GDC 31, requires that the vessel be designed with sufficient margin to assure that when the vessel is stressed under operating, maintenance testing and postulated accident conditions the boundary behaves in a non brittle manner. Finally, GDC 14, requires that the pressure vessel be
designed, fabricated, erected and tested so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and gross rupture.
The NRC staff issued RG 1.190 that describes acceptable calculational methods for the determination of the vessel fluence that satisfies the requirements of the above GDCs, therefore, the review is subject to the guidance in RG 1.190.
3.0 TECHNICAL EVALUATION
3.1 Staff Evaluation The licensee has chosen the RAMA code to calculate the vessel fluence. However, the RAMA code has a limitation requiring that plants (other than boiling-water reactors 4s) have a minimum of one plant-specific surveillance capsule successfully analyzed using the RAMA code. Pilgrim could not satisfy this requirement. In addition, the proposed calculated fluence value to the end of the extended license is smaller than the existing value to the end of the current license. The smaller calculated fluence value is possible at the end of extended license because the original values were overly conservative and the plant-specific benchmark value will be more realistic due to use of RAMA code.
The licensee is requesting extension of the current PT limit curves for two fuel cycles to enable collection of data to establish acceptable plant dosimetry to satisfy the RAMA limitation. The request is based on the fact that the current limit curves are based on a fluence value calculated for 48 EFPYs of operation and there exists sufficient margin to assure safe operation. Pilgrim will be at the end of cycle 16 in the spring of 2007. The requested extension of applicability is to the end of cycle 18 when the estimated operation will be 26.3 EFPYs.
Therefore, the margin is 48/26.3 = 1.83. Based on bounding fluence value uncertainties to
+/- 10%, the NRC staff finds that there is sufficient margin to assure safe operation for cycles 17 and 18.
Another fact supporting the conservatism of the current fluence value is that the source term for the calculation of cycles 4, 5, 6, and 7 was based on a composite model derived from cycle 4, which had an unusually high number of fuel assemblies in the periphery, thus, overestimating the contribution of the source. The projections of fluence based on this model would be conservatively high and the conservatism would be compounded when extrapolated out to end-of-life.
Another fluence conservatism was identified in the justification of previously approved Pilgrim licensing amendment (LA) 197 where the staff observed that the General Electric (GE) report MDE-277-1285 provided conservative projections that were 25% higher than predicted peak vessel fluence values.
In summary, the NRC staff finds that the requested extension of the applicability of the current PT limit curves for two more cycles is acceptable because there is sufficient margin to assure safe operation for cycles 17 and 18.
3.2 Technical Specification Changes The only change required to indicate the change of the period of applicability is the number of the cycle number on the title of Figures 3.6.1, 3.6.2, and 3.6.3 from 16 to 18. The PT limit curves remain the same. In addition, the licensee proposes to eliminate five blank TS pages which is an editorial change.
3.3 Licensee Commitments The licensee made the following commitments: (1) Submit to the NRC an action plan to improve benchmarking data to support approval of new P-T curves for Pilgrim using R.G 1.190 guidance by September 15, 2007, and (2) Submit updated P-T curves for Pilgrim to the NRC for approval by June 8, 2010.
4.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
DETERMINATION The Commission's regulations in 10 CFR 50.92 state that the Commission may make a final determination that a license amendment involves no significant hazards consideration if operation of facility, in accordance with the amendment, would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Because this amendment is being issued before the expiration of 60 days, pursuant to 10 CFR 2.309(b), the NRC staff has made a final no significant hazards consideration determination.
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The current pressure-temperature curves were generated in accordance with the fracture toughness requirements of 10 CFR Part 50, Appendix G, and American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)
Code, Section Xl, Appendix G and NRC Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials." The current pressure-temperature curves were established in compliance with the methodology used to calculate and predict effects of radiation on embrittlement of reactor vessel beltline materials. The use of the proposed pressure-temperature curves through operating cycle 18 is acceptable because sufficient margin exists between the actual Effective Full Power Years (EFPYs) and the Effective Full Power Years used to establish the 48 EFPY curve. This proposed license amendment does not modify the reactor coolant pressure boundary, (i.e., there are no changes in operating pressure, materials, or seismic loading) and there are no physical changes to the plant being introduced. In addition, the proposed change does not adversely affect the integrity of the reactor coolant pressure boundary such that its function in the control of radiological consequences is affected.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the [proposed] change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed license amendment does not create the possibility of new or different kind of accident from any accident previously evaluated. The pressure-temperature curves were generated in accordance with the fracture toughness requirements of 10 CFR Part 50, Appendix G, and ASME B&PV Code, Section Xl, Appendix G. Compliance with the proposed pressure-temperature curves will ensure the avoidance of conditions in which brittle fracture of primary coolant pressure boundary materials is possible because such compliance with the current pressure-temperature curves provides sufficient protection against a non-ductile-type fracture of the reactor pressure vessel. No new modes of operation are introduced by the proposed change. The proposed change will not create any failure mode not bounded by previously evaluated accidents. Further, the proposed change does not affect any activities or equipment and is not assumed in any safety analysis to initiate any accident sequence. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The current curves are based on established NRC and ASME methodologies in force when LA 197 was approved. The proposed license amendment requests the use of the proposed curves for two additional operating cycles. This is acceptable because sufficient margin exists between actual EFPYs and the EFPYs used in the development of the existing curves to yield a conservatism factor slightly in excess of 1.8.
Operation within the current limits ensures that the reactor vessel materials will continue to behave in a non-brittle manner, thereby preserving the original safety design bases. No plant safety limits, set points, or design parameters are adversely affected by the proposed changes. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Massachusetts State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has made a final finding that the amendment involves no significant hazards consideration. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
7.0 CONCLUSION
Based on the above, the NRC staff finds that the requested extension of the applicability of the current PT limit curves for two more cycles is acceptable.
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Lambros Lois Date: March 26, 2007
Pilgrim Nuclear Power Station cc:
Regional Administrator, Region I Secretary of Public Safety U. S. Nuclear Regulatory Commission Executive Office of Public Safety 475 Allendale Road One Ashburton Place King of Prussia, PA 19406-1415 Boston, MA 02108 Senior Resident Inspector Director, Massachusetts Emergency U. S. Nuclear Regulatory Commission Management Agency Pilgrim Nuclear Power Station Attn: James Muckerheide Post Office Box 867 400 Worcester Road Plymouth, MA 02360 Framingham, MA 01702-5399 Chairman, Board of Selectmen Mr. William D. Meinert 11 Lincoln Street Nuclear Engineer Plymouth, MA 02360 Massachusetts Municipal Wholesale Electric Company Chairman P.O. Box 426 Nuclear Matters Committee Ludlow, MA 01056-0426 Town Hall 11 Lincoln Street Mr. Kevin H. Bronson Plymouth, MA 02360 General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Chairman, Duxbury Board of Selectmen Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 878 Tremont Street Plymouth, MA 02360-5508 Duxbury, MA 02332 Mr. Michael A. Balduzzi Office of the Commissioner Site Vice President Massachusetts Department of Entergy Nuclear Operations, Inc.
Environmental Protection Pilgrim Nuclear Power Station One Winter Street 600 Rocky Hill Road Boston, MA 02108 Plymouth, MA 02360-5508 Office of the Attorney General Mr. Stephen J. Bethay One Ashburton Place Director, Nuclear Safety Assurance 20th Floor Entergy Nuclear Operations, Inc.
Boston, MA 02108 Pilgrim Nuclear Power Station 600 Rocky Hill Road Director, Radiation Control Program Plymouth, MA 02360-5508 Commonwealth of Massachusetts Executive Offices of Health and Mr. Bryan S. Ford Human Services Manager, Licensing 174 Portland Street Entergy Nuclear Operations, Inc.
Boston, MA 02114 Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508
Pilgrim Nuclear Power Station cc:
Mr. Gary J. Taylor Mr. Michael J. Colomb Chief Executive Officer Director of Oversight Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. John T. Herron Assistant General Counsel Sr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. 440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Ms. Stacey Lousteau Mr. Oscar Limpias Treasury Department Vice President, Engineering Entergy Services, Inc.
Entergy Nuclear Operations, Inc. 639 Loyola Avenue 440 Hamilton Avenue New Orleans, LA 70113 White Plains, NY 10601 Mr. James Sniezek Mr. Christopher Schwarz 5486 Nithsdale Drive Vice President, Operations Support Salisbury, MD 21801-2490 Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Mr. Michael D. Lyster White Plains, NY 10601 5931 Barclay Lane Naples, FL 34110-7306 Mr. John F. McCann Director, Nuclear Safety Assurance Mr. Garrett D. Edwards Entergy Nuclear Operations, Inc. 814 Waverly Road 440 Hamilton Avenue Kennett Square, PA 19348 White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601