Letter Sequence Approval |
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MONTHYEARML13162A4032013-06-11011 June 2013 E-mail from R. Guzman to J. Lynch Acceptance Review Determination for Pilgrim Revision to TS Safety Limits to Resolve Pressure Regulator Fail Open Transient Project stage: Acceptance Review ML14042A0432014-02-18018 February 2014 Request for Additional Information Regarding Safety Limits to Resolve Pressure Regulator Fail-Open Transient License Amendment Request Project stage: RAI 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 Project stage: Approval 2014-02-18
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Category:Letter
MONTHYEARML24151A6482024-06-0303 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) 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) 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 ML22269A4202022-09-22022 September 2022 Citizen Lawsuit 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 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 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 2024-06-03
[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] Category:Technical Specifications
MONTHYEARML20328A2972020-12-0101 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 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 ML17163A1812017-05-25025 May 2017 Supplemental to Technical Specifications Proposed Change - Administrative Controls for Permanently Defueled Condition ML17053A4682017-02-14014 February 2017 Technical Specifications Proposed Change - Administrative Controls for Permanently Defueled Condition ML16363A2662017-01-10010 January 2017 Correction to Amendment No. 234 Change in Technical Specification Measurement Frequency from 18 Months to 24 Months ML16250A2232016-10-28028 October 2016 Issuance of Amendments Proposed Changes to Emergency Plan to Revise Training for the on - Shift Chemistry Technician 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 ML14295A6852014-10-31031 October 2014 Issuance of Amendment Regarding Heavy Loads to Facilitate Dry Storage Handling Operations ML14259A3812014-09-11011 September 2014 Supplement to Proposed License Amendment Request to Modify Technical Specification 4.3.4, Heavy Loads to Facilitate Dry Storage Handling Operations ML13108A2172013-04-0505 April 2013 Proposed License Amendment: Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open (PRFO) Transient Reported by General Electric Nuclear Energy in Accordance with 10 CFR 21.21(d) CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications ML12005A1982011-12-29029 December 2011 Cycle-Specific License Amendment Request for Rod Worth Minimizer (RWM) Bypass Allowance to Allow Reactor Startup ML0731004782007-11-0505 November 2007 Technical Specifications, Issuance of Amendment Control Rod Operability, Scram Insertion Time, and Control Rod Accumulator Requirements ML0726101972007-09-18018 September 2007 Technical Specifications, 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 ML0726102002007-05-17017 May 2007 Technical Specifications, Corrected Page II (Fixed Administrative Error) ML0715605422007-04-25025 April 2007 Tech Spec Pages for Amendment 228 Single Control Rod Withdrawal Allowances ML0714303052007-04-25025 April 2007 Technical Specifications, Limiting Conditions for Operation ML0708603592007-03-26026 March 2007 Technical Specifications, 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. ML0708603392007-02-22022 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 ML0702302932007-01-15015 January 2007 Proposed Change to Applicability of Pilgrim'S Pressure - Temperature Curves as Described in Technical Specification Figures 3.6.1, 3.6.2, and 3.6.3, Revision 1 ML0631303512006-11-0202 November 2006 Application for Technical Specification (TS) Change to Add LCO 3.0.8 on the Inoperability of Snubbers (and Adoption of TS Bases for LCO 3.0.8) Using the Consolidated Line Item Improvement Process (CLIIP) ML0626405822006-09-20020 September 2006 Tech Spec Pages for Amendment 225 Regarding Revised Reactor Coolant System Leakage Detection Instrumentation Requirements and Actions ML0626202402006-09-14014 September 2006 Technical Specification Pages Re Relocation of Technical Specifications Structural Integrity Requirements to Final Safety Analysis Report ML0624904892006-08-30030 August 2006 Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), Revision 1, ML0622800132006-08-0909 August 2006 Tech Spec Pages for Amendment 223 Regarding Administrative Changes and Relocation of Certain Technical Specification Responsibilities ML0622301672006-08-0404 August 2006 Tech Spec Pages for Amendment 222 Deletion of Requirement Related to NRC Approval of Engineering Evaluation for Elevated Relief Valve Discharge Pipe Temperature ML0618704692006-06-30030 June 2006 Technical Specifications Amendment Request to Revise the Surveillance Requirements for the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems ML0613000952006-05-0505 May 2006 Correction to Amendment No. 221 Revised Rod Worth Minimizer Bypass Allowances - Technical Specifications ML0610702152006-04-13013 April 2006 Technical Specification Page, Deletes the Main Steam Isolation Valve Twice Per Week Partial Stroke Testing Surveillance Specified in Technical Specification 4.7.A.2.b.1.c ML0610702042006-04-13013 April 2006 Technical Specification Page Re Revised Rod Worth Minimizer Bypass Allowances ML0610908322006-04-12012 April 2006 Proposed License Amendment to Change Technical Specification 3.6.A.2, Pressure-Temperature Limit Curves ML0610701672006-04-12012 April 2006 Tech Spec Pages for Amendment 219 Regarding Single Recirculation Loop Operation ML0611402652006-04-10010 April 2006 Technical Specification Pages Re Revised Applicability for Containment Oxygen and Differential Pressure Limits ML0524301522005-08-29029 August 2005 Technical Specification Pages Re Surveillance Frequency Improvements ML0521400792005-07-29029 July 2005 Technical Specifications, Revised Action for Scram Discharge Volume Vent and Drain Valves ML0515204742005-05-24024 May 2005 Technical Specifications Amendment Request to Revise Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Applicability Requirements ML0515204582005-05-24024 May 2005 Technical Specifications Amendment Request for Rod Worth Minimizer (RWM) Bypass Allowances ML0515204732005-05-24024 May 2005 Request for Amendment to the Technical Specifications to Delete Requirement Related to NRC Approval of Engineering Evaluation for Elevated Safety Relief Valve Discharge Pipe Temperature ML0512200952005-04-28028 April 2005 Technical Specifications, Eliminates Secondary Containment Operability Requirements When Handling Sufficiently Decayed Irradiated Fuel or Performing Core Alterations ML0510400322005-04-12012 April 2005 Technical Specifications, Revision to Surveillance Requirement Frequency for Containment and Suppression Pool Spray Headers and Nozzles ML0509004102005-03-30030 March 2005 Technical Specifications, Allows One-time Extension of Appendix J Type a Integrated Leakage Rate Test Interval ML0507601772005-03-16016 March 2005 Tech Spec Pages for Amendment No. 211, Revise Reactor Vessel Hydrostatic and Leak Testing Requirements ML0503800052005-02-0202 February 2005 Tech Spec Page for Amendment 210 Changes to Technical Specifications Table 3.2.C-1 ML0500701552005-01-0505 January 2005 Technical Specification Pages for Amendment No. 209 to License No. DPR-35 ML0423206092004-08-17017 August 2004 Technical Specifications, Issuance of Amendment Re.: Multiple Control Rod Removal, Limiting Condition for Operation 3/4.10.D ML0420502772004-07-22022 July 2004 Tech Spec Pages for Amendment 206 Elimination of Requirements for Hydrogen Analyzers ML0403307902004-01-30030 January 2004 License Amendment, Tech Spec Pages ML0332100752003-11-14014 November 2003 Revised TS Page 5.0-7, Eliminating Requirements for Post-Accident Sampling System 2020-12-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 12, 2015 Mr. John A. Dent, Jr.
Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508
SUBJECT:
PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT REGARDING SAFETY LIMITS TO RESOLVE PRESSURE REGULATOR FAIL-OPEN TRANSIENT LICENSE AMENDMENT REQUEST (TAC NO. MF1382)
Dear Mr. Dent:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 242 to Renewed Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. This amendment consists of changes to the Technical Specification (TS) in response to your application transmitted by letter dated April 5, 2013, as supplemented by letter dated March 20, 2014.
This amendment change reduces the reactor steam dome pressure from 785 pounds per square inch gauge (psig) to 685 psig in TS 2.1.1 and 2.1.2, "Safety Limits," to resolve the Pressure Regulator Failure-Open transient.
A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/I Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
- 1. Amendment No. 242 to License No. DPR-35
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR GENERATION COMPANY AND ENTERGY NUCLEAR OPERATIONS, INC.
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 242 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 April 5, 2013, as supplemented by letter dated March 20, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations; 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.
Enclosure 1
- 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 Renewed 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. 242, are hereby incorporated in the renewed operating 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 Benjamin G. Beasley, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: March 12, 2015
ATTACHMENT TO LICENSE AMENDMENT N0.242 RENEWED FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas 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 2-1 2-1
provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A. Maximum Power Level ENO is authorized to operate the facility at steady state power levels not to exceed 2028 megawatts thennal.
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 242, are hereby incorporated in the renewed operating license.
The licensee shall operate the facility in accordance with the Technical Specifications.
C. Records ENO shall keep facility operating records in accordance with the requirements of the Technical Specifications.
D. Eaualizer Valve Restriction - DELETED E. Recirculation Loop Inoperable - DELETED F. Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated December 21, 1978 as supplemented subject to the following provision:
ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (50 FR27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards lnfonnation protected under 1O CFR 73.21, is entitled: "Pilgrim Nuclear Power Station Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision O" submitted by letter dated October 13, 2004, as supplemented by letter dated May 15, 2006.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 236, as supplemented by changes approved by License Amendment Nos. 238 and 241.
Amendment 242 Renewed License No. DPR-35
2.0 SAFETY LIMITS
- 2. 1 Safety Limits 2.1.1 With the reactor steam dome pressure < 685 psig or core flow < 10% of rated core flow:
THERMAL POWER shall be~ 25% of RATED THERMAL POWER.
2.1.2 With the reactor steam dome pressure ~ 685 psig and core flow ?. 10% of rated core flow:
MINIMUM CRITICAL POWER RATIO shall be?. 1.08 for two recirculation loop operation or?. 1.11 for single recirculation loop operation.
2.1.3 Whenever the reactor is in the cold shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be less than 12 inches above the top of the normal active fuel zone.
2.1.4 Reactor steam dome pressure shall be ~ 1340 psig at any time when irradiated fuel is present in the reactor vessel.
2.2 Safety Limit Violation With any Safety Limit not met within two hours the following actions shall be met:
2.2.1 Restore compliance with all Safety Limits, and 2.2.2 Insert all insertable control rods.
Amendment No. 15,27, 42,72, 133, 146, 171, 191, 219.~.232,235,242 2-1
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.242 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-35 ENTERGY NUCLEAR GENERATION COMPANY AND ENTERGY NUCLEAR OPERATIONS. INC.
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated April 5, 2013 (Agencywide Document Access and Management System (ADAMS) Accession No. ML13108A217), as supplemented by letter dated March 20, 2014 (ADAMS Accession No. ML14087A128), Entergy Nuclear Operations, Inc., the licensee, submitted a request to the Nuclear Regulatory Commission (NRC) for changes to the Pilgrim Nuclear Power Station (Pilgrim) Technical Specification (TS). The supplement dated March 20, 2014, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register on August 6, 2013 (78 FR 47788).
The proposed changes would revise the TS associated with the reactor steam dome pressure to resolve a Title 10 of the Code of Federal Regulations (10 CFR) Part 21 condition concerning a potential violation of the reactor core safety limits during a Pressure Regulator Failure-Open (PRFO) transient.
2.0 BACKGROUND
In accordance with 10 CFR 21.21 (d), on March 29, 2005, GE Nuclear Energy (GE) issued Safety Communication, SC 05-03, "Potential to Exceed Low Pressure Technical Specification Safety Limit" to Entergy (Reference 3). An unanalyzed condition was identified where a PRFO -
Maximum Demand Abnormal Operation Occurrence (AOO) could result in a condition where the reactor steam dome pressure could potentially and momentarily decrease below the reactor core safety limit of 785 pounds per square inch gauge (psig), while reactor power is above 25 percent of rated thermal power. On July 18, 2006, the Technical Specifications Task Force (TSTF) and the Boiling Water Reactor Owners' Group (BWROG) submitted Revision 0 of Enclosure 2
TSTF-495, "Bases Change to Address GE Part 21 SC05-03" (Reference 4), proposing a modification to the "Applicable Safety Analysis" portion of the TS Bases 2.1.1. This change proposed to clarify that the safety limit was considered not to apply to momentary depressurization transients. In the NRC staff's safety evaluation (SE) input for TSTF-495, dated August 14, 2007 (Reference 5), it was stated that although the technical arguments presented in TSTF-495 had some merit, the NRC staff found the proposed change unacceptable because it would set a precedent which could lead to erosion of safety margins protected by safety limits.
The NRC staff further stated in the SE that from a regulatory standpoint, the proposed change to the TS Bases was not acceptable. Consequently, the BWROG discontinued the effort to resolve the issue generically and recommended that plants lower their Low Pressure Safety Limit to meet the lower range of their critical power correlation on plant-specific basis.
Some advanced fuel designs have an NRC-approved critical power correlation with a lower-bound pressure significantly below the 785 psig reactor steam dome pressure, as specified in TS 2.1.1 and 2.1.2. The licensee proposed to utilize this fact and reduce the reactor steam dome pressure consistent with the approved lower-bound pressures for the critical power correlations for the GE14 and Global Nuclear Fuels 2 (GNF2) fuels comprising the core. The GE14 and GNF2 fuels utilize the General Electric Critical Quality (X) - Boiling Length (L) (GEXL) 14 and GEXL 17 critical power correlations with approved pressure range from 700 per square inch absolute (psia) to 1400 psia.
3.0 REGULATORY EVALUATION
3.1 Description of System The licensee stated that the "pressure regulator failure open event involves the failure of the pressure regulator in the open direction causing the turbine control valves to fully open, including the bypass valves. This causes the reactor to depressurize rapidly.
When the Main Steam Line low pressure setpoint is reached, the Main Steam Isolation Valves (MSIVs) start to close and a reactor scram occurs. As the MSIVs approach full closure, reactor depressurization terminates and pressure commences to rise to the safety-relief valve setpoint."
The purpose of the safety limit is to ensure that specified acceptable fuel design limits (SAFDLs) are not exceeded during steady state operation and analyzed transients. The fuel cladding is one of the physical barriers that separate the radioactive materials from the environment. The integrity of this cladding barrier is related to its relative freedom from perforations or cracking.
Fuel cladding perforations can result from thermal stresses, which can occur from reactor operation significantly above design conditions. Since the parameters that result in fuel damage are not directly observable during reactor operation, the thermal and hydraulic conditions that result in the onset of transition boiling (OTB) have been used to mark the beginning of the region in which fuel cladding damage could occur. The reactor core safety limits are set such that fuel cladding integrity is maintained and no significant fuel damage is calculated to occur due to OTB if the safety limits are not exceeded.
3.2 Proposed TS Change The reactor steam dome pressure is reduced from 785 psig to 685 psig in TS 2.1.1 and 2.1.2, "Safety Limits."
The NRC is not required to review and approve changes to the TS bases pages. For information purposes only, the licensee provided the following TS bases changes:
- The current reactor steam dome pressure value of 785 psig is revised to 685 psig in the TS Bases Pages B2-1, 82-2, and B3/4.2-2.
- The Bases on B3/4.1-5 is revised to describe the role of the MSIV closure in preventing power operation with reactor pressure below 685 psig and core thermal power greater than 25% of rated thermal power.
- NEDC-33270P, Rev. 4, "GNF2 Advantage Generic Compliance with NEDE-2401 1-P-A (GESTAR II)", dated October 2011 is deleted and the following three references are added on TS Bases Page B2-4:
NEDC-32851P-A, Rev. 4, "GEXL 14 Correlation for GE 14 Fuel," dated September 15, 2008 NEDC-33292P, Rev. 3, "GEXL 17 Correlation for GNF2 Fuel," dated June 2009 NEDC-33270P, Rev. 4, "GNF2 Advantage Generic Compliance with NEDE-24011-PA (GESTAR II)," dated October 2011 3.3 Regulatory Requirements and Guidance The construction permit for Pilgrim was issued by the Atomic Energy Commission (AEC) on August 26, 1968, a low-power license was issued on June 8, 1972, and a full-power license was issued on September 15, 1972. The plant design approval for the construction phase was based on the proposed General Design Criteria (GDC) published by the AEC in the Federal Register (32 FR 10213) on July 11, 1967. The AEC published the final rule that added Appendix A to 10 CFR Part 50, "General Design criteria for Nuclear Power Plants," in the Federal Register (36 FR 3255) on February 20, 1971.
Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license application. The Commission's regulatory requirements related to the content of the TS are contained in 1O CFR 50.36(c). Section 50.36(c) of 10 CFR requires that the TSs include, among other things, items in the following categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
The regulation at 10 CFR 50.36(c)(1 )(i)(A) states, in part, that if any safety limit is exceeded, the reactor must be shut down.
Criterion 10, "Reactor Design," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 states, in part, that "the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that [SAFDLs] are not exceeded."
NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," provides guidance on the acceptability of the reactivity control systems, the
reactor core, and fuel system design. Specifically, Section 4.2, "Fuel System Design," specifies all fuel damage criteria for evaluation and whether fuel designs meet the SAFDLs. Section 4.4, "Thermal Hydraulic Design," provides guidance on the review of thermal-hydraulic design in meeting the requirement of GDC-10 and the fuel design criteria established in Section 4.2.
4.0 TECHNICAL EVALUATION
During the PRFO described in GE's 10 CFR Part 21 notification, the critical power ratio (CPR) increases during depressurization, so GE concluded that the initial CPR is the limiting condition during the entire transient, the conditions that exceed the low pressure TS safety limit exist for only a few seconds, and fuel cladding integrity is not threatened. Nevertheless, GE considers the PRFO to be a known anticipated operational occurrence (AOO) that could contribute to the exceeding of a safety limit. While this condition had been determined to not involve an actual safety hazard, the potential for violation of a reactor core safety limit had been identified, and restoration to comply with the safety limit is required for the PRFO event.
At Pilgrim during the PRFO transient, both pressure regulators fail open and the turbine control valves open wider, which causes rapid depressurization. When reactor pressure reaches 810 psig, the low pressure isolation set point is reached and MSIVs begin to close. When MSIVs are approximately 10 percent closed (90 percent open), a position driven reactor scram occurs, which terminates the event. The proposed changes to lower the low pressure to 685 psig offer a greater range for pressure to reduce further while MSIVs are closing. The MSIVs close in 3 to 5 seconds, leading to the termination of pressure reduction. As a result, the licensee is revising the reactor steam dome pressure in TS 2.1.1 and 2.1.2, consistent with the NRG-approved pressure range of critical power correlations for the current fuel designs. Reducing the reactor steam dome pressure specification in this fashion provides margin to ensure that TS 2.1.1 and 2.1.2 are not violated and resolves the 10 CFR Part 21 issue involving a potential to violate the low pressure TS safety limit during a PRFO transient.
The current Pilgrim core has both GE14 and GNF2 fuel. The NRC staff notes that a SE (Reference 6) was issued approving the GEXL 14 critical power correlation, which applies to GE14 fuel. As described in the associated licensing topical report and the NRC staff SE, the GEXL 14 correlation is approved for the performance of critical power calculations with a pressure range of 700 psia to 1400 psia. The reactor steam dome pressure of 685 psig is established from the lower bound pressure (700.0 psia - 14.7 psia = 685.3 psig - 685 psig). As a result, the proposed change to TS 2.1.1 and 2.1.2 continues to ensure that a valid CPR calculation is performed for the AOOs described in the updated final safety analysis report, and that the proposed reactor steam dome pressure of 685 psig would not result in a violation of the TSs during a PRFO transient. In addition, the GEXL 17 correlation for GNF2 fuel was approved for use per NEDE-24011-PA "General Electric Standard Application for Reactor Fuel (GESTAR II)." Since this approach is consistent with the methodology used to establish the reactor steam dome pressure and valid CPR calculations will continue to be performed, the NRC finds the GEXL 17 correlation for GNF2 an acceptable method to address the 10 CFR Part 21 condition.
The NRC staff notes that the data used for development and verification of the GEXL critical power correlation for GE14 fuel and GNF2 fuels has an extended pressure range from 700 psia to 1400 psia using Stern Laboratory test data, as documented in References 7 and 8. The GEXL correlation also provides the validity of Minimum Critical Power Ratio (MCPR) calculations due to the fact that the PRFO event causes the MCPR to increase due to the
pressure reduction effect on the greater latent heat of vaporization, and the large voids causing negative reactivity and lower power as compared to the higher pressure condition. Therefore, the NRC staff has determined that as long as the core pressure and flow are within the range of validity of the specified CPR correlation (GEXL 14 and GEXL 17), the proposed reactor steam dome pressure change to TS 2.1.1 and 2.1.2 will continue to ensure that 99.9 percent of the fuel rods in the core are not expected to experience OTB. This satisfies the regulatory requirements regarding acceptable fuel design limits and continues to assure that the underlying criteria of the safety limit is met, and therefore, reducing the reactor steam dome pressure to 685 psig is acceptable. The NRC staff has also determined that reducing the reactor steam dome pressure from 785 psig to 685 psig resolves the reported 10 CFR Part 21 condition.
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 previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on August 6, 2013 (78 FR 47788). 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
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) there is reasonable assurance that 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.
8.0 REFERENCES
- 1. Entergy Nuclear Operations, Inc., "Proposed License Amendment: Revision to Technical Specification (TS) 2.1, Safety Limits To Resolve Pressure Regulator Fail-Open (PRFO) Transient Reported by General Electric Nuclear in Accordance with 10 CFR 21.21 (d)," Pilgrim Nuclear Power Station, Docket No. 50-293, License No. DPR-35 April 5, 2013, ADAMS Accession No. ML13108A217.
- 2. Entergy Nuclear Operations, Inc., "Entergy Response to NRC Request for Additional Information in Support of Proposed License Amendment: Revision to Technical
Specification (TS) 2.1, Safety Limits To Resolve Pressure Regulator Fail-Open (PRFO)
Transient Reported by General Electric Nuclear in Accordance with 10 CFR 21.21 (d),"
Pilgrim Nuclear Power Station, Docket No. 50-293, License No. DPR-35 March 20, 2014, ADAMS Accession No. ML14087A128.
- 3. General Electric, GENE SC05-03, "Potential to Exceed Low Pressure Technical Specification Safety Limit," Reportable condition pursuant to 1O CFR 21, March 29, 2005.
- 4. Technical Specifications Task Force, (TSTF-06-20) transmitting TSTF-495, Revision 0, "Bases Change to Address GE Part 21 SC05-03," dated July 18, 2006, ADAMS Accession No. ML061990227.
- 5. Kobetz, Timothy, NRC Technical Specification Branch memo to Gregory Cranston, U.S.
Nuclear Regulatory Commission, "Safety Evaluation Input for TSTF-495, Revision 0, Bases Change to Address GE Part 21 SC05-03" August 14, 2007, ADAMS Accession No. ML072280007.
- 6. Nieh, Ho K., U.S. Nuclear Regulatory Commission, letter to Andrew A. Lingenfelter, GNF Engineering, "Final Safety Evaluation for Global Nuclear Fuel (GNF) Topical Report (TR)
NEDC-32851 P, Revision 2, "GEXL 14 Correlation for GE14 Fuel," August 3, 2007, ADAMS Accession No. ML072080365.
- 7. Global Nuclear Fuel, "Acceptance Version of Global Nuclear Fuel (GNF) Topical Report NEDC-32851 P, Revision 2, 'GEXL 14 Correlation for GEXL Fuel 14,"' (Table 2, Page 6),
September 14, 2007, ADAMS Accession Nos. ML072620193.
- 8. Global Nuclear Fuel, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33270P, Revision 2, June 2009 and GEXL Correlation for GNF2 Fuel, NEDC-33292P, Revison 3, June 2009 (MFN 09-436), ADAMS Accession Nos.
ML091830614 and ML091830618, Table 3-1, Pg 3-4.
Principal Contributors: T. Huang C. Tilton Date: March 12, 2015
ML14272A070 *See dated memo OFFICE LPLl-1/PM LPLl-1/PM LPLl-1/LA DSS/SRXB/BC NAME DRender NMorqan KGoldstein CJackson DATE 2/05/2015 2/04/2015 1/21/2015 7/8/2014*
OFFICE DSS/SNPB/BC DSS/STSB/BC OGC LPLl-1/BC NAME JDean RElliott SUttal BBeasley DATE 2/11/2015 2/05/2015 2/23/2015 3/12/2015