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Category:Letter
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report ML23228A1342023-08-16016 August 2023 Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance ML23208A1622023-07-27027 July 2023 Operator Licensing Examination Approval IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML23152A0042023-06-0101 June 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000333/2023401 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 ML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 2024-02-07
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23261C3982023-09-0808 September 2023 Acceptance Review of Amendment to Update the Fuel Handling Accident Analysis ML22223A1412022-09-0101 September 2022 Issuance of Amendment No. 353 Adoption of TSTF - 505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22196A0612022-08-23023 August 2022 Issuance of Amendment No. 352 Adoption of 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22166A4302022-07-15015 July 2022 Issuance of Amendment No. 351 Removal of Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation ML22126A1962022-05-27027 May 2022 Issuance of Amendment No. 350 Adoption of TSTF-264, Revision 0 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML21364A0432022-02-28028 February 2022 Issuance of Amendment No. 348 Revising Surveillance Requirement 3.5.1.6 Involving Recirculation Pump Discharge Valves ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21300A3552021-11-16016 November 2021 Issuance of Amendment No. 345 Adoption of TSTF-582 ML21131A1272021-08-0909 August 2021 Issuance of Amendment No. 343 Modifications to Technical Specification 3.6.1.3, Primary Containment Isolation Valves (Pcivs) ML21162A0422021-06-14014 June 2021 Issuance of Amendment No. 342, One Time Extension of Completion Times to Support Residual Heat Removal Pump Motor Replacement (Emergency Circumstances) JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement ML21049A3552021-04-28028 April 2021 Issuance of Amendment No. 341 Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20169A5102020-08-20020 August 2020 Issuance of Amendment No. 339 Changes to Technical Specifications Related to Primary Containment Hydrodynamic Loads ML20140A0702020-07-21021 July 2020 Issuance of Amendment No. 338 Application of Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20094G9032020-06-0202 June 2020 Issuance of Amendment No. 335 Adoption of TSTF-372, Addition of LCO 3.0.8, 'Inoperability of Snubbers' ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML20024C6612020-03-0202 March 2020 Issuance of Amendment No. 332 Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line Item Improvement Process ML19266A5272019-10-0808 October 2019 Issuance of Amendments to Eliminate Second Completion Times from Technical Specifications ML19204A0632019-09-13013 September 2019 Independent Spent Fuel Storage Installation, James A. FitzPatrick, and Nine Mile Point - Issuance of Amendments to Revise the Emergency Response Organization Staff ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19189A0842019-08-19019 August 2019 Issuance of Amendment No. 326 Adoption of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18289A4322018-11-28028 November 2018 Issuance of Amendment No. 323 Revision to the Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 ML18324A6852018-11-26026 November 2018 Correction to Amendment No. 321 Revising Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ML18214A7062018-09-19019 September 2018 Issuance of Amendment No. 322, Revise Technical Specification 2.1.1, Reactor Core Sls, to Change Cycle 24 Safety Limit Minimum Critical Power Ratio Numeric Values ML18194A8822018-08-24024 August 2018 Issuance of Amendment No. 321 Re: Revision to Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control (EPID L-2017-LLA-0311) ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18180A3722018-07-19019 July 2018 Issuance of Amendment No. 319, Revise Technical Specification Surveillance Requirement 3.6.4.1.3 to Allow Opening of Inner and Outer Secondary Containment Access Openings (CAC MG0239; EPID L-2017-LLA-0298) ML17289A1752018-03-26026 March 2018 Issuance of Amendment No. 318, Revise Emergency Plan for Emergency Response Organization Requalification Training Frequency Consistent with Exelon Fleet (CAC MG0026; EPID L-2017-LLA-0273) ML17313A0772017-11-30030 November 2017 Issuance of Amendment Application for Order Approving Direct Transfer of Renewed Facility Operating License & Independent Spent Fuel Storage Installation General License & Conforming Amendment (CAC No. MG0014; EPID L-2017-LLM-0004) ML17240A0692017-11-0707 November 2017 Nonproprietary LTR with Order Approving Direct Transfer of Renewed Facility Operating License & Independent Spent Fuel Storage Installation General License & Conforming Amendment (CAC MG0014; EPID L-2017-LLM-0004) ML17235A5402017-09-29029 September 2017 Issuance of Amendment Cyber Security Plan Implementation Schedule ML17153A0182017-06-30030 June 2017 Issuance of Amendment Emergency Plan Emergency Action Level HU1.5 ML17082A2832017-03-31031 March 2017 Issuance of Amendment Application for Order to Transfer Renewed Facility Operating License, Independent Spent Fuel Storage Installation General License, and Conforming Amendment from Entergy Nuclear to Exelon Generation CAC No. MF8293) ML17025A2882017-01-30030 January 2017 Issuance of Amendments Application for Order to Transfer Master Decommissioning Trust from PASNY to Entergy ML16336A4922017-01-27027 January 2017 Transmittal Letter: Order Approving Transfer of Master Decommissioning Trust Funds for Indian Point, No. 3 & FitzPatrick Nuclear Plant from the Power Authority of the State of New York to Entergy Nuclear Operations, Inc. ML17009A3722017-01-24024 January 2017 Issuance of Amendment Regarding Revision of Technical Specification 5.5.6 for Extension of Type a and Type C Leak Rate Frequencies ML16062A3882016-04-0606 April 2016 Issuance of Amendment No. 311 Cyber Security Plan Implementation Schedule ML15014A2772015-02-0909 February 2015 Issuance of Amendment Application to Revise Technical Specifications for Technical Specification Low Pressure Safety Limit ML14202A3722014-12-0101 December 2014 Issuance of Amendment 308 License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 8 2023-09-08
[Table view] Category:Safety Evaluation
MONTHYEARML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML22223A1412022-09-0101 September 2022 Issuance of Amendment No. 353 Adoption of TSTF - 505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22196A0612022-08-23023 August 2022 Issuance of Amendment No. 352 Adoption of 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22166A4302022-07-15015 July 2022 Issuance of Amendment No. 351 Removal of Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation ML22126A1962022-05-27027 May 2022 Issuance of Amendment No. 350 Adoption of TSTF-264, Revision 0 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML21364A0432022-02-28028 February 2022 Issuance of Amendment No. 348 Revising Surveillance Requirement 3.5.1.6 Involving Recirculation Pump Discharge Valves ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21300A3552021-11-16016 November 2021 Issuance of Amendment No. 345 Adoption of TSTF-582 ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21131A1272021-08-0909 August 2021 Issuance of Amendment No. 343 Modifications to Technical Specification 3.6.1.3, Primary Containment Isolation Valves (Pcivs) ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21162A0422021-06-14014 June 2021 Issuance of Amendment No. 342, One Time Extension of Completion Times to Support Residual Heat Removal Pump Motor Replacement (Emergency Circumstances) ML21049A3552021-04-28028 April 2021 Issuance of Amendment No. 341 Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20169A5102020-08-20020 August 2020 Issuance of Amendment No. 339 Changes to Technical Specifications Related to Primary Containment Hydrodynamic Loads ML20140A0702020-07-21021 July 2020 Issuance of Amendment No. 338 Application of Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20094G9032020-06-0202 June 2020 Issuance of Amendment No. 335 Adoption of TSTF-372, Addition of LCO 3.0.8, 'Inoperability of Snubbers' ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20024C6612020-03-0202 March 2020 Issuance of Amendment No. 332 Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line Item Improvement Process ML19295G7832019-12-19019 December 2019 Issuance of Amendment No. 331 Regarding Change to Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19189A0842019-08-19019 August 2019 Issuance of Amendment No. 326 Adoption of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19157A2032019-07-11011 July 2019 Issuance of Amendment No. 325 Reactivity Anomalies Surveillance ML19135A4442019-06-21021 June 2019 Issuance of Relief Request I4R-22 Relief from the Requirements of the ASME Code ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML18360A6352019-02-25025 February 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4464; EPID No. L-2014-JLD-0049) ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18289A4322018-11-28028 November 2018 Issuance of Amendment No. 323 Revision to the Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 ML18214A7062018-09-19019 September 2018 Issuance of Amendment No. 322, Revise Technical Specification 2.1.1, Reactor Core Sls, to Change Cycle 24 Safety Limit Minimum Critical Power Ratio Numeric Values ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18180A3722018-07-19019 July 2018 Issuance of Amendment No. 319, Revise Technical Specification Surveillance Requirement 3.6.4.1.3 to Allow Opening of Inner and Outer Secondary Containment Access Openings (CAC MG0239; EPID L-2017-LLA-0298) ML18039A8542018-05-30030 May 2018 Relief Requests I5R-02, I5R-03, I5R-04 from ASME Code Requirements for Reactor Vessel Internals, Ferretic Piping Repair/Replacement, and RPV Flange Welds, 5th 10-Year Inservice Inspection Interval (MG0116-MG0118; L-2017-LLR-0083 to 0085) ML18044A9932018-04-13013 April 2018 Request for Alternatives PRR-01, PRR-02, PRR-04, VRR-02, VRR-03, and VRR-04 from ASME OM Code Requirements for Various Pumps and Valves, Fifth 10-Year Inservice Testing Interval (CAC MG0052-MG0061; EPID L-2017-LLR-0067 to L-2017-LLR-0074) ML17289A1752018-03-26026 March 2018 Issuance of Amendment No. 318, Revise Emergency Plan for Emergency Response Organization Requalification Training Frequency Consistent with Exelon Fleet (CAC MG0026; EPID L-2017-LLA-0273) ML18003B3822018-01-0303 January 2018 Correction to the Safety Evaluation to James A. Fitzpatrick Nuclear Power Plant Issuance of Relief Request for Proposed Alternative to Use ASME Code Case N-789-1 (CAC No. MF9692; EPID L-2017-LLR-0027) (Original Safety Evaluation: ML17289A07 ML17342A0062017-12-18018 December 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17289A0752017-12-12012 December 2017 Issuance of Relief Request for Proposed Alternative to Use ASME Code Case N-789-1 (CAC No. MF9692; EPID L-2017-LLR-0027) Note Correction Safety Evaluation See ML18003B382 2023-05-01
[Table view] Category:Technical Specifications
MONTHYEARML23095A3762023-04-0505 April 2023 Enclosure 4: Technical Requirements Manual (TRM) Revision 109 ML22196A0612022-08-23023 August 2022 Issuance of Amendment No. 352 Adoption of 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22166A4302022-07-15015 July 2022 Issuance of Amendment No. 351 Removal of Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V JAFP-21-0022, Technical Requirements Manual Specifications - Redacted2022-03-29029 March 2022 Technical Requirements Manual Specifications - Redacted ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21131A1272021-08-0909 August 2021 Issuance of Amendment No. 343 Modifications to Technical Specification 3.6.1.3, Primary Containment Isolation Valves (Pcivs) ML21166A3662021-06-17017 June 2021 Correction to Amendment No. 342 Issued June 14, 2021, One Time Extension to Technical Specifications 3.5.1, 3.6.1.9, and 3.6.4.1 Completion Times to Support Residual Heat Removal Pump Motor Replacement (Emergency Circumstances) ML21162A0422021-06-14014 June 2021 Issuance of Amendment No. 342, One Time Extension of Completion Times to Support Residual Heat Removal Pump Motor Replacement (Emergency Circumstances) ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20140A0702020-07-21021 July 2020 Issuance of Amendment No. 338 Application of Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML20094G9032020-06-0202 June 2020 Issuance of Amendment No. 335 Adoption of TSTF-372, Addition of LCO 3.0.8, 'Inoperability of Snubbers' RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML20024C6612020-03-0202 March 2020 Issuance of Amendment No. 332 Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line Item Improvement Process ML19301C5552019-10-28028 October 2019 Technical Specification Bases B.3.3.5.2 and B3.3.6.1 Provided by Licensee to Support a 10/28/2019 Public Meeting to Discuss Draft Response to Request for Supplemental Information to Revise Allowable Value for RWCU System Primary Containment ML19277D5522019-10-0404 October 2019 Draft James A. FitzPatrick Nuclear Power Plant - Emergency License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML18214A7062018-09-19019 September 2018 Issuance of Amendment No. 322, Revise Technical Specification 2.1.1, Reactor Core Sls, to Change Cycle 24 Safety Limit Minimum Critical Power Ratio Numeric Values RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement JAFP-16-0142, Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 22016-09-19019 September 2016 Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 2 JAFP-16-0077, Response to Request for Additional Information (RAI) Regarding Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 12016-06-0303 June 2016 Response to Request for Additional Information (RAI) Regarding Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 1 ML16062A3882016-04-0606 April 2016 Issuance of Amendment No. 311 Cyber Security Plan Implementation Schedule ML15014A2772015-02-0909 February 2015 Issuance of Amendment Application to Revise Technical Specifications for Technical Specification Low Pressure Safety Limit ML14202A3722014-12-0101 December 2014 Issuance of Amendment 308 License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 8 ML14086A1522014-07-16016 July 2014 Issuance of Amendment Change to Renewed Facility Operating License Condition 2.T JAFP-14-0047, Proposed Change to Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio2014-05-0101 May 2014 Proposed Change to Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio ML14085A4462014-04-14014 April 2014 Issuance of Amendment Revision to the Definition of Shut Down Margin, by Adopting the Nuclear Regulatory Commission Approved Technical Specification Task Force (TSTF) Standard Technical Specification (STS) 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 ML1134308512012-02-14014 February 2012 License Amendment, Issuance of Amendment Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal2011-04-0606 April 2011 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal ML1024604012010-09-27027 September 2010 ME3786, Letter - Issuance of Amendment to Renewed FOL SLMCPR JAFP-09-0132, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves2009-11-23023 November 2009 Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves JAFP-09-0131, Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record2009-11-23023 November 2009 Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record JAFP-09-0070, Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time2009-06-0404 June 2009 Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time ML0915507232009-06-0303 June 2009 Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time - (Draft) ML0828203902008-10-0303 October 2008 Technical Specification Relocation of Pressure and Temperature Curves to the Pressure and Temperature Limits Report Consistent with TSTF-419-A ML0810102422008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix a - Technical Specifications JAFP-08-0034, Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A2008-04-22022 April 2008 Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A JAFP-08-0006, Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-3742008-01-22022 January 2008 Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-374 ML0800804572008-01-0303 January 2008 Technical Specifications, Issuance of Amendment Technical Specifications Regarding Control Room Envelope Habitability, Consistent with Technical Specification Task Force-448 JAFP-07-0124, Revision to Application for Technical Specifications (TS) Change Based on TSTF-477, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems, Using the Consolidated Line Item Improvement Process (CLIIP)2007-11-0101 November 2007 Revision to Application for Technical Specifications (TS) Change Based on TSTF-477, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems, Using the Consolidated Line Item Improvement Process (CLIIP) JAFP-07-0098, Supplement to Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 32007-08-13013 August 2007 Supplement to Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3 JAFP-07-0088, James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 32007-07-17017 July 2007 James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3 ML0717601272007-06-21021 June 2007 Technical Specifications (Ts), Revised TS 3.10.1, Inservice Leak and Hydrostatic Testing Operation, Consistent with Technical Specification Task Force-484 ML0714303022007-05-17017 May 2007 Technical Specifications, Allow Additional Startup and Operating Flexibility and an Expanded Operating Domain JAFP-07-0023, Application for Amendment to Technical Specifications 3.10.1. Re Inservice Leak and Hydrostatic Testing Operation, Consistent with TSTF-4842007-02-15015 February 2007 Application for Amendment to Technical Specifications 3.10.1. Re Inservice Leak and Hydrostatic Testing Operation, Consistent with TSTF-484 ML0625802332006-09-14014 September 2006 Tech Spec Pages for Amendment 286 Technical Specifications on DC Electrical System Requirements 2023-04-05
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 9, 2015
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT- ISSUANCE OF AMENDMENT RE: APPLICATION TO REVISE TECHNICAL SPECIFICATIONS FOR TECHNICAL SPECIFICATION LOW PRESSURE SAFETY LIMIT (TAC NO. MF2897)
Dear Sir or Madam:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 309 to Renewed Facility Operating License No. DPR-59 for the James A.
FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 8, 2013, as supplemented by a letter dated November 18, 2014.
The amendment modifies the TSs to reduce the reactor pressure associated with the Reactor Core Safety Limit from 785 psig to 685 psig in TS 2.1.1.1 and TS 2.1.1.2. This change addresses the potential to not meet the pressure/thermal power/minimum critical power ratio TS safety limit during a pressure regulator failure-maximum demand (open) (PRFO) transient. The PRFO transient was reported by General Electric Nuclear Energy as a notification pursuant to Title 10 of the Code of Federal Regulations, Part 21, "Reporting of Defects and Noncompliance."
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosures:
- 1. Amendment No. 309 to DPR-59
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR FITZPATRICK. LLC ENTERGY NUCLEAR OPERATIONS. INC.
DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 309 Renewed Facility Operating License No. DPR-59
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the James A. FitzPatrick Nuclear Power Plant (the facility) Renewed Facility Operating License No. DPR-59 filed by Entergy Nuclear Operations, Inc. (the licensee) dated October 8, 2013, as supplemented on November 18, 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 set forth in 10 CFR Chapter I; 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 2.C.(2) of Renewed Facility Operating License No. DPR-59 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 309, 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 its issuance and shall be implemented within 30 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 Renewed Facility Operating License and Technical Specifications Date of Issuance: February 9, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 309 RENEWED FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 3 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 2.0-1 2.0-1
(4) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.
(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable 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 or incorporated below:
(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 309, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to the following provision:
Amendment 309 Renewed License No. DPR-59
Sls 2.0 2.0 SAFETY LIMITS {Sls) 2.1 Sls 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure< 685 psig or core flow
< 10% rated core flow:
THERMAL POWER shall be~ 25% RTP.
2.1.1.2 With the reactor steam dome pressure~ 685 psig and core flow
~ 10% rated core flow:
MCPR shall be~ 1.10 for two recirculation loop operation or
~ 1.13 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be~ 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all Sls; and 2.2.2 Insert all insertable control rods.
JAFNPP 2.0-1 Amendment 309
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 309 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-59 ENTERGY NUCLEAR FITZPATRICK, LLC AND ENTERGY NUCLEAR OPERATIONS. INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated October 8, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13282A559) [Reference 1], as supplemented by a letter dated November 18, 2014 (ADAMS Accession No. ML14322B022) [Reference 2], Entergy Nuclear Operations, Inc. (Entergy, the licensee) requested an amendment to revise the Technical Specifications (TSs) for the James A. FitzPatrick Nuclear Power Plant (JAFNPP). The proposed change would reduce the reactor steam dome pressure specified within Reactor Core Safety Limits Specification 2.1.1, in the TS. This change would resolve a concern reported by General Electric Nuclear Energy as a notification pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) Part 21, "Reporting of Defects and Noncompliance," regarding the potential to momentarily violate Reactor Core Safety Limit 2.1.1.1 and 2.1.1.2 during a pressure regulator failure maximum demand (open) (PRFO) transient.
The supplemental letter dated November 18, 2014, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on July 8, 2014 (79 FR 38589).
2.0 REGULATORY EVALUATION
The following explains the use of general design criteria (GDC) for JAFNPP. The construction permit for JAFNPP was issued by the Atomic Energy Commission (AEC) on May 20, 1970, and the operating license was issued on October 17, 1974. The plant design criteria for the construction phase are listed in the Updated Final Safety Analysis Report (UFSAR)
Chapter 1.5, "Principal Design Criteria." The AEC published the final rule that added Appendix A to Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50, "General Design Criteria for Nuclear Power Plants," in the Federal Register on February 20, 1971 (36 FR 3255),
with the rule effective on May 21, 1971. In accordance with an NRC staff requirements memorandum from S. J. Chilk to J. M. Taylor, "SECY-92-223- Resolution of Deviations Identified During the Systematic Evaluation Program," dated September 18, 1992 (ADAMS Accession No. ML003763736), the Commission decided not to apply the final GDC to plants with construction permits issued prior to May 21, 1971, which includes JAFNPP. However, the JAFNPP UFSAR, Chapter 16.6, "Conformance to AEC Design Criteria," evaluates JAFNPP against the 10 CFR Part 50, Appendix A GDC. Also, the initial AEC safety evaluation of JAFNPP, dated November 20, 1972, Chapter 14.0, stated, "Based on our evaluation of the design and design criteria for the James A. FitzPatrick Nuclear Power Plant, we conclude that there is reasonable assurance that the intent of the General Design Criteria for Nuclear Power Plants, published in the Federal Register on May 21, 1971 as Appendix A to 10 CFR part 50, will be met." Therefore, the NRC staff reviews amendments to the JAFNPP license using the 10 CFR Part 50, Appendix A GDC unless there are specific criteria identified in the UFSAR.
The regulatory requirements and guidance documents that the staff considered in its review of the proposed amendment included the following items.
Section 50.36 of 10 CFR, "Technical specifications," [Reference 6] provides the regulatory requirements for the content required in the TSs. As stated in 10 CFR 50.36(c)(1 )(i)(A):
Safety limits for nuclear reactors are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity. If any safety limit is exceeded, the reactor must be shut down. The licensee shall notify the Commission, review the matter, and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude recurrence. Operation must not be resumed until authorized by the Commission.
Compliance with the fuel licensing criteria of 10 CFR Part 50 Appendix A, GDC 10, "Reactor design," [Reference 7] is achieved by preventing the violation of fuel design limits. GDC 10 states:
The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits [SAFDLs] are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition," (SRP) [Reference 8] provides guidance on, among other things, 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 and 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 SRP Section 4.2. It states that the critical power ratio (CPR) is to be established such that at least 99.9 percent of fuel rods
in the core would not be expected to experience departure from nucleate boiling or onset of transition boiling (OTB) during normal operation or anticipated operational occurrences (AOOs).
3.0 TECHNICAL EVALUATION
In 2005, General Electric (GE) submitted a 10 CFR Part 21 notification, SC05-03, "Potential to Exceed Low Pressure Technical Specification Safety Limit" to the NRC [Reference 3]. The Part 21 notification discussed how applying newer computer analysis codes to a PRFO transient could result in a condition where the reactor steam dome pressure could momentarily decrease below 785 pounds per square inch gauge (psig), while rated thermal power (RTP) was above the plant-specific thermal power limit specified in TS 2.1.1.1, which would result in a violation of the Reactor Core Safety Limit. Initially, the Boiling Water Reactor Owners' Group (BWROG) attempted to resolve the Part 21 issue. On July 18, 2006, the Technical Specifications Task Force (TSTF) and the BWROG submitted an Improved Standard Technical Specifications Change Traveler TSTF-495, Revision 0, "Bases Change to Address GE Part 21 SC05-03"
[Reference 4], proposing a modification to the "Applicable Safety Analysis" portion of the Reactor Core Safety Limit TS Bases (B 2.1.1 ). This change proposed to clarify that the safety limit was considered not to apply to momentary depressurization transients. In the NRC safety evaluation (SE) input for TSTF-495, dated August 14, 2007 [Reference 5], the staff stated that although the technical arguments presented in TSTF-495 had merit, the proposed change was not acceptable because it would set a precedent that could lead to erosion of safety margins protected by Safety Limits. The staff further stated that from a regulatory standpoint, the proposed change to the TS Bases was also not acceptable. Consequently, in April 2012, 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 a plant-specific basis. As a result, the licensee submitted this license amendment request to lower the lower-bound pressure limit for JAFNPP from 785 psig to 685 psig.
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 specified in TS Reactor Core Safety Limits 2.1.1.1 and 2.1.1.2. The licensee proposes to utilize this fact and reduce the reactor steam dome pressure consistent with the approved lower-bound pressure for the critical power correlation for the GNF2 (Global Nuclear Fuel) fuel currently comprising the JAFNPP core. The GNF2 fuel utilizes the GEXL 17 critical power correlations with an approved pressure range that encompasses the licensee's proposed lower-bound pressure limit of 685 psig. Revising the reactor steam dome pressure specified in Reactor Core Safety Limits (SLs) 2.1.1.1 and 2.1.1.2 from 785 psig to 685 psig would resolve the 10 CFR Part 21 condition concerning the potential to violate a safety limit during a PRFO transient.
PROPOSED TS CHANGES The following change is proposed to TS SL 2.1.1, "Reactor Core SLs":
Current TS 2.1.1.1:
With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
Proposed TS 2.1. 1.1:
With the reactor steam dome pressure < 685 psig or core flow < 10% rated core flow:
THERMAL POWER shall be ~ 25% RTP.
Current TS 2.1.1.2:
With the reactor steam dome pressure =::: 785 psig and core flow =::: 10% rated core flow:
MCPR [minimum critical power ratio] shall be =::: 1.10 for two recirculation loop operation or =::: 1.13 for single recirculation loop operation.
Proposed TS 2.1.1.2:
With the reactor steam dome pressure =::: 685 psig and core flow =::: 10% rated core flow:
MCPR shall be =::: 1.10 for two recirculation loop operation or =::: 1.13 for single recirculation loop operation.
In its October 8, 2013 submittal [Reference 1], the licensee stated that the GNF2 fuel type is currently in use in the JAFNPP reactor core. As stated earlier, GNF2 fuel type has an approved pressure range for its critical power correlations that encompass the licensee's proposed lower-bound pressure limit of 685 psig.
Each fuel vendor has developed critical power correlations valid over specified pressure and flow ranges (mass flow rates) that are approved by the NRC. These critical power correlations have become increasingly fuel design dependent as advanced fuel designs have evolved. This has resulted in an extension of the NRC approved pressure range to lower pressures as additional test data became available to demonstrate the validity of revised or new correlations for performance of critical power calculations. The critical power correlations for some advanced fuel designs have received NRC approval down to a lower pressure than those approved previously. The lower-bound of the extended pressure ranges for these advanced fuel designs can be used to establish a lower reactor steam dome pressure than the 785 psig value currently specified in JAFNPP Reactor Core Safety Limits 2.1.1.1 and 2.1.1.2. The licensee proposes to utilize the fact that the GNF2 fuel comprising the JAFNPP core utilizes critical power correlation that have an approved pressure range including the proposed lower safety limit of 685 psig. Therefore, a wider pressure range is available for transients to demonstrate compliance with MCPR limits. Thus, the proposed change offers a greater pressure margin for a PRFO transient than what is currently available.
In the 10 CFR Part 21 notification [Reference 3], GE concluded that fuel cladding integrity is not threatened during the PRFO because the CPR increases during depressurization such that the initial CPR is the limiting CPR condition during the entire transient, and the conditions that exceed the low pressure TS safety limit exist for only a few seconds. Nonetheless, GE considered the PRFO to be a known AOO that could contribute to exceeding a safety limit.
While this condition was not considered to involve an actual safety hazard, the potential for violating a Reactor Core Safety Limit had been identified, and restoration to comply with the safety limit is required for the PRFO event. As a result, the licensee proposes to revise the
reactor steam dome pressure TS Safety Limit consistent with the NRC approved pressure range of critical power correlations for the current JAFNPP fuel design. Lowering the reactor steam dome pressure specification in this fashion would provide margin to ensure that Reactor Core Safety Limit 2.1.1.1 is not violated and would resolve the 10 CFR Part 21 issue.
The licensee confirmed [Reference 2] that the JAFNPP Cycle 22 core consists of one fuel type, namely 560 GNF2 fuel assemblies, and that there is no lead test assembly (LTA) in the core.
The NRC staff reviewed the licensee's submittal [Reference 1], supplemental information provided by the licensee in response to the staff's questions [Reference 2], and related documentation (e.g., the JAFNPP TS and Updated Final Safety Analysis Report (UFSAR), the GE 10 CFR Part 21 notification, the proposed TSTF-495, and related staff SEs). The staff concluded that reactor depressurization transients, such as PRFOs, are non-limiting for fuel cladding integrity and that the proposed change in TS 2.1.1.2 will have no negative impact on the MCPR core operating limits. Although this condition does not involve an actual safety hazard, the potential for violating a TS Reactor Core Safety Limit was identified by the 10 CFR Part 21 notification and restoration to comply with the safety limit was required; hence, the licensee proposed this amendment in order to address this issue.
The NRC staff determined that revising the Reactor Core Safety Limits 2.1.1.1 and 2.1.1.2 reactor steam dome pressures from 785 to 685 psig resolves the 10 CFR Part 21 notification issue. TS Safety Limits are specified to ensure that SAFDLs are not exceeded during steady state operation, normal operational transients, and AOOs. 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.
The NRC staff confirmed that the GEXL 17 correlation for GNF2 fuel was approved for use per NEDE-24011-PA, "General Electric Standard Application for Reactor Fuel (GESTAR II)"
[Reference 9]. The pressure range over which the GEXL 17 correlation is valid for performance of critical power calculations includes the proposed lower safety limit. The reactor steam dome pressure of 685 psig is established from the lower bound pressure (700.0 pounds per square inch absolute (psia)- 14.7 psia =685.3 psig;;:;; 685 psig). As a result, the staff concluded that the proposed change to the Reactor Core Safety Limits continues to ensure that a valid CPR is maintained for the AOOs described in the UFSAR, including the PRFO transient, and that the proposed value of 685 psig for the reactor steam dome pressure would not result in a violation of Reactor Core Safety Limit 2.1.1.1 during a PRFO transient. Furthermore, the proposed change will continue to provide protection during startup conditions to ensure that operation at less than 685 psig or less than 10% core flow, while greater than 25 percent RTP, would not occur. Since this approach follows, and is consistent with, the way the reactor steam dome pressure has been established and valid CPR values will be maintained, it is a safe and appropriate method to address the 10 CFR Part 21 notification and, therefore, is acceptable. If JAFNPP transitions to different fuel designs, the licensee will need to reevaluate the GE 10 CFR Part 21 notification to determine whether NRC approval is required to change the TS Safety Limits.
The NRC staff evaluated the proposed changes against the applicable regulatory requirements and acceptance criteria. The NRC staff concludes that as long as the core pressure and flow are within the range of validity of the specified CPR correlation (i.e., GEXL 17 correlations for JAFNPP), the proposed reactor steam dome pressure changes to Reactor Core Safety Limits
2.1.1.1 and 2.1.1.2 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 are met consistent with GDC 10 and 10 CFR 50.36(c)(1)(i)(A). Therefore, the proposed amendment is acceptable. The NRC staff further concludes that there is reasonable assurance that the health and safety of the public, following approval of this TS change, will be unaffected.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the 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 as published in the Federal Register on July 8, 2014 (79 FR 38589). 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.
6.0 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.
7.0 REFERENCES
- 1) Letter from L.M. Coyle (Entergy) to USNRC, "Application to Revise Technical Specifications for Technical Specification Low Pressure Safety Limit, James A FitzPatrick Nuclear Power Plant," October 8, 2013, ADAMS Accession No. ML13282A559.
- 2) Letter from L.M. Coyle (Entergy) to USNRC, "Response to Request for Additional Information (RAI) for Low Pressure Safety Limit License Amendment (TAC No.
MF2897), James A FitzPatrick Nuclear Power Plant," November 18, 2014, ADAMS Accession No. ML143228022.
- 3) GE letter to the NRC, GENE SC05-03, "Potential to Exceed Low Pressure Technical Specification Safety Limit," Reportable condition pursuant to 10 CFR Part 21, dated March 29, 2005.
- 4) Technical Specifications Task Force letter (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) Safety Evaluation Input For TSTF-495, Revision 0, "Bases Change To Address GE Part 21 SC05-03," (TAC No. MD2672), dated August 14, 2007, ADAMS Accession No. ML072280007.
- 6) U.S. Code of Federal Regulations, "Domestic Licensing of Production and Utilization Facilities -Technical specifications," Title 10 of the Code of Federal Regulations," Part 50, Section 36 (1 0 CFR 50.36).
- 7) U.S. Code of Federal Regulations, "Domestic Licensing of Production and Utilization Facilities - General Design Criteria for Nuclear Power Plants," Title 10 of the Code of Federal Regulations," Part 50, Appendix A (1 0 CFR 50, Appendix A).
- 8) U.S. Nuclear Regulatory Commission, i*standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," (NUREG-0800, Formerly issued as NUREG-75/087).
- 9) Memorandum from A J. Mendiola (NRC) to S. L. Rosenberg (NRC), "Staff Findings Regarding Supplemental Information Pertaining to the Compliance of the GNF2 Fuel Design to the General Electric Standard Application for Reactor Fuel (GESTAR II),"
August 4, 2009, ADAMS Accession No. ML092080499.
- 10) U.S. Nuclear Regulatory Commission, "Report to Congress on Abnormal Occurrences, Fiscal Year 2006," NUREG-0090, Vol. 29, April2007, ADAMS Accession No. ML071080195.
Principal Contributor: M. M. Razzaque, DSS/SRXB Date: February 9, 2015
ML15014A277 *b>Y memo OFFICE LPLI-1\PM LPLI-1\PM LPLI-1\LA DSS\SRXB DSS\STSB OGC LPLI-1\BC NAME DRender DPickett KGoldstein CJackson* REIIiot JWachutka BBeasley DATE 01/20/2015 1/22/2015 01/20/2015 12/19/2014 2/02/2015 1/26/2015 2/09/2015