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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] |
Text
May 16, 2003 Mr. Michael Kansler Sr. Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - AMENDMENT RE:
ELIMINATION OF REQUIREMENTS FOR POST ACCIDENT SAMPLING (TAC NO. MB8030)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 278 to 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 transmitted by letter dated February 27, 2003.
The amendment deletes TS 5.5.3, "Post Accident Sampling," and thereby eliminates the requirements to have and maintain the post accident sampling system for the James A.
FitzPatrick Nuclear Power Plant.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.
Sincerely,
/RA/
Guy S. Vissing, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosures:
- 1. Amendment No. 278 to DPR-59
- 2. Safety Evaluation cc w/encls: See next page
FitzPatrick Nuclear Power Plant cc:
Mr. Jerry Yelverton Ms. Charlene D. Faison Chief Executive Officer Licensing Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. Theodore H. Sullivan Supervisor Vice President Operations Town of Scriba Entergy Nuclear Operations, Inc. Route 8, Box 382 James A. FitzPatrick Nuclear Power Plant Oswego, NY 13126 P.O. Box 110 Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General Mr. Dan Pace New York Department of Law Vice President, Engineering 120 Broadway Entergy Nuclear Operations, Inc. New York, NY 10271 440 Hamilton Avenue White Plains, NY 10601 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. John Kelly 475 Allendale Road Director - Licensing King of Prussia, PA 19406 Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Oswego County Administrator White Plains, NY 10601 Jack Tierney 46 East Bridge Street Mr. George Tasick Oswego, New York 13126 Licensing Manager Entergy Nuclear Operations, Inc. Mr. William M. Flynn, President James A. FitzPatrick Nuclear Power Plant New York State Energy, Research, P.O. Box 110 and Development Authority Lycoming, NY 13093 17 Columbia Circle Albany, NY 12203-6399 Resident Inspectors Office U. S. Nuclear Regulatory Commission Mr. Arthur Zaremba, Licensing Manager P.O. Box 136 Director, Safety Assurance Lycoming, NY 13093 Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant Mr. Harry P. Salmon, Jr. P.O. Box 110 Director of Oversight Lycoming, NY 13093 Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Mr. Paul Eddy White Plains, NY 10601 Electric Division New York State Dept. of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
M FitzPatrick Nuclear Power Plant Mr. Tim Judson Organizer cc: Citizens Awareness Network 140 Bassett St.
Michael J. Colomb Syracuse, NY 13210 General Manager Entergy Nuclear Operations, Inc. Deborah Katz James A. FitzPatrick Nuclear Power Plant Executive Director P.O. Box 110 Citizens Awareness Network Lycoming, NY 13093 P.O. Box 83 Shelburne Falls, MA 01370
- r. James Knubel Vice President, Operations Support Shawn McConnell Entergy Nuclear Operations, Inc. NYPIRG Project Coordinator 440 Hamilton Avenue 13 Hewitt Union White Plains, NY 10601 SUNY Oswego Oswego, NY 13126 Mr. John M. Fulton Assistant General Counsel Tom Dellwo Entergy Nuclear Generation Co. Oswego NYPIRG Environmental Pilgrim Station Project Leader 600 Rocky Hill Road 13 Hewitt Union Plymouth, MA 02360 SUNY Owego Oswego, NY 13126 Mr. J. Spath, Program Director New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Ronald Schwartz SRC Consultant 64 Walnut Drive Spring Lake Heights, NJ 07762 Mr. Ronald J. Toole SRC Consultant Toole Insight 605 West Horner Street Ebensburg, PA 15931 Mr. Charles W. Hehl SRC Consultant Charles Hehl, Inc.
1486 Matthew Lane Pottstown, PA 19465
May 16, 2003 Mr. Michael Kansler Sr. Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - AMENDMENT RE:
ELIMINATION OF REQUIREMENTS FOR POST ACCIDENT SAMPLING (TAC NO. MB8030)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 278 to 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 transmitted by letter dated February 27, 2003.
The amendment deletes TS 5.5.3, "Post Accident Sampling," and thereby eliminates the requirements to have and maintain the post accident sampling system for the James A.
FitzPatrick Nuclear Power Plant.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.
Sincerely,
/RA/
Guy S. Vissing, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosures:
- 1. Amendment No. 278 to DPR-59
- 2. Safety Evaluation cc w/encls: See next page Accession Number: ML030910011 *See Previous Concurrence OFFICE CLIIP LPM PDI-1\PM PDI-1\LA PDI-1\SC NAME WReckley* GVissing SLittle RLaufer DATE 3/26/03 Official Record Copy
DATED: May 16, 2003 AMENDMENT NO. 278 TO FACILITY OPERATING LICENSE NO. DPR-59 FITZPATRICK PUBLIC PDI-1 R/F RLaufer OGC GHill (2)
WBeckner ACRS BPlatchek, RI SRichards GVissing SLittle cc: Plant Service list
ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 278 License No. DPR-59
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated February 27, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions 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 Facility Operating License No. DPR-59 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 278, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 16, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 278 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 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 Pages Insert Pages 5.5-2 5.5-2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 278 TO FACILITY OPERATING LICENSE NO. DPR-59 ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated February 27, 2003, Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the James A. FitzPatrick Nuclear Power Plant Technical Specifications (TSs). The requested changes would delete TS 5.5.3, "Post Accident Sampling," and thereby eliminate the requirements to have and maintain the post accident sampling system (PASS) for the James A. FitzPatrick Nuclear Power Plant.
In the aftermath of the accident at Three Mile Island (TMI), Unit 2, the Nuclear Regulatory Commission (NRC) imposed requirements on licensees for commercial nuclear power plants to install and maintain the capability to obtain and analyze post-accident samples of the reactor coolant and containment atmosphere. The desired capabilities of the PASS [or Station] were described in NUREG-0737, "Clarification of TMI Action Plan Requirements." The NRC issued Orders to licensees with plants operating at the time of the TMI accident to confirm the installation of PASS capabilities (generally as they had been described in NUREG-0737). A requirement for PASS and related administrative controls was added to the TS of the operating plants and was included in the initial TS for plants licensed during the 1980s and 90s.
Additional expectations regarding PASS capabilities were included in Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following an Accident."
Significant improvements have been achieved since the TMI accident in the areas of understanding risks associated with nuclear plant operations and developing better strategies for managing the response to potentially severe accidents at nuclear power plants. Recent insights about plant risks and alternate severe accident assessment tools have led the NRC staff to conclude that some TMI Action Plan items can be revised without reducing the ability of licensees to respond to severe accidents. The NRCs efforts to oversee the risks associated with nuclear technology more effectively and to eliminate undue regulatory costs to licensees and the public have prompted the NRC to consider eliminating the requirements for PASS in TS and other parts of the licensing bases of operating reactors.
The staff has completed its review of the topical report submitted by the Boiling Water Reactor (BWR) Owners Group (BWROG) that proposed the elimination of PASS. The justifications for the proposed elimination of PASS requirements center on evaluations of the various radiological and chemical sampling and their potential usefulness in responding to a severe
reactor accident or making decisions regarding actions to protect the public from possible releases of radioactive materials. As explained in more detail in the staffs safety evaluation (SE) for the topical report, the staff has reviewed the available sources of information for use by decision makers in developing protective action recommendations and assessing core damage.
Based on this review, the NRC staff found that the information provided by PASS is either unnecessary or is effectively provided by other indications of process parameters or measurement of radiation levels. The staff agrees with the owners group that licensees can remove the TS requirements for PASS, revise (as necessary) other elements of the licensing bases, and pursue possible design changes to alter or remove existing PASS equipment.
2.0 BACKGROUND
In its letter dated November 30, 2000, the BWROG submitted for the NRC staff's review Topical Report NEDO-32991, "Regulatory Relaxation for BWR Post Accident Sampling Stations (PASS)," for eliminating PASS requirements from BWRs. The NRC staff's SE for the BWROG Topical Report is dated June 12, 2001 (ADAMS Accession Number ML011630016). The BWROG proposed that relaxation of the PASS requirements be incorporated into the standard technical specifications by submitting TSTF-413.
The NRC staff prepared this SE relating to the elimination of requirements on post accident sampling for BWRs and solicited public comment (66 FR 66949, dated December 27, 2001) in accordance with the Consolidated Line Item Improvement Program (CLIIP). The use of the CLIIP in this matter is intended to help the NRC to efficiently process amendments that propose to remove the PASS requirements from TSs. Licensees of nuclear power reactors to which this SE apply were informed (67 FR 13027, dated March 20, 2002) that they could request amendments conforming to the SE, and, in such requests, should confirm the applicability of the SE to their reactors and provide the requested plant-specific verifications and commitments.
3.0 EVALUATION The ways in which the requirements and recommendations for PASS were incorporated into the licensing bases of commercial nuclear power plants varied as a function of when the plants were licensed. Plants that were operating at the time of the TMI accident are likely to have been the subject of Confirmatory Orders that imposed the PASS functions described in NUREG-0737 as obligations. The issuance of plant-specific amendments to adopt this change, which would remove PASS and related administrative controls from TSs, would also supercede the PASS specific requirements imposed by post-TMI Confirmatory Orders.
The technical evaluations for the elimination of PASS sampling requirements are provided in the SE dated June 12, 2001, for BWROG Topical Report NEDO-32991. As described in its SE for the topical report, the staff finds that the post-accident sampling requirements for the following may be eliminated for BWR plants:
- 1. Reactor coolant dissolved gases.
- 2. Reactor coolant hydrogen.
- 3. Reactor coolant oxygen.
- 4. Reactor coolant chlorides.
- 5. Reactor coolant pH.
- 6. Reactor coolant boron.
- 7. Reactor coolant conductivity.
- 8. Radioisotopes in the reactor coolant.
- 9. Containment hydrogen.
- 10. Containment oxygen.
- 11. Radioisotopes in the containment atmosphere.
- 12. Suppression pool pH.
- 13. Chlorides in the suppression pool.
- 14. Boron in the suppression pool.
- 15. Radioisotopes in the suppression pool.
The staff agrees that the sampling of radioisotopes is not required to support emergency response decision making during the initial phases of an accident because the information provided by PASS is either unnecessary or is effectively provided by other indications of process parameters or measurement of radiation levels. Therefore, it is not necessary to have dedicated equipment to obtain this sample in a prompt manner.
The staff does, however, believe that there could be significant benefits to having information about the radioisotopes existing post-accident in order to address public concerns and plan for long-term recovery operations. As stated in the SE for the topical report, the staff has found that licensees could satisfy this function by developing contingency plans to describe existing sampling capabilities and what actions (e.g., assembling temporary shielding) may be necessary to obtain and analyze highly radioactive samples from the reactor coolant system (RCS), suppression pool, and containment atmosphere. (See item 4.1 under Verifications and Commitments.) The contingency plans for obtaining samples from the RCS, suppression pool, and containment atmosphere may also enable a licensee to derive information on parameters such as hydrogen concentrations in containment and the pH of water in the suppression pool.
The staff considers the sampling of the suppression pool to be potentially useful in confirming calculations of pH and confirming that potentially unaccounted for acid sources have been sufficiently neutralized. The use of the contingency plans for obtaining samples would depend on the plant conditions and the need for information by the decision makers responsible for responding to the accident.
In addition, the staff considers radioisotope sampling information to be useful in classifying certain types of events (such as a reactivity excursion or mechanical damage) that could cause fuel damage without having an indication of a loss of reactor coolant inventory. However, the staff agrees with the topical reports contentions that other indicators of failed fuel, such as radiation monitors, can be correlated to the degree of failed fuel. (See item 4.2 under Verifications and Commitments.)
In lieu of the information that would have been obtained from PASS, the staff believes that licensees should maintain or develop the capability to monitor radioactive iodines that have been released to offsite environs. This information would be useful for decision makers trying to assess a release of and limit the publics exposure to radioactive materials. (See item 4.3 under Verifications and Commitments.)
The staff believes that the changes related to the elimination of PASS that are described in the topical report, related SE, and this proposed change to TS are unlikely to result in a decrease in the effectiveness of a licensees emergency plan. Each licensee, however, must evaluate
possible changes to its emergency plan in accordance with 10 CFR 50.54(q) to determine if the change decreases the effectiveness of its site-specific plan. Evaluations and reporting of changes to emergency plans should be performed in accordance with applicable regulations and procedures.
The staff notes that containment hydrogen concentration monitors are required by 10 CFR 50.44 and are relied upon to meet the data reporting requirements of 10 CFR Part 50, Appendix E, Section VI.2.a.(ii)(3). The staff concludes that these hydrogen monitors provide an adequate capability for monitoring containment hydrogen concentration during the early phases of an accident. The staff sees value in maintaining the capability to obtain grab samples for complementing the information from the hydrogen monitors in the long term (i.e., by confirming the indications from the monitors and providing hydrogen measurements for concentrations outside the range of the monitors). As previously mentioned, the licensees contingency plan (see item 4.1 under Verifications and Commitments) for obtaining highly radioactive samples will include sampling of the containment atmosphere and may, if deemed necessary and practical by the appropriate decision makers, be used to supplement the hydrogen monitors.
4.0 VERIFICATIONS AND COMMITMENTS As requested by the staff in the notice of availability for this TS improvement, the licensee has addressed the following plant-specific verifications and commitments.
4.1 Each licensee should verify that it has, and make a regulatory commitment to maintain (or make a regulatory commitment to develop and maintain),
contingency plans for obtaining and analyzing highly radioactive samples of reactor coolant, suppression pool, and containment atmosphere.
The licensee has committed to develop and maintain contingency plans for obtaining and analyzing highly radioactive samples of the reactor coolant, suppression pool, and containment atmosphere. The contingency plans will be contained within plant procedures. The licensee will implement this commitment within 6 months after the implementation of this license amendment.
4.2 Each licensee should verify that it has, and make a regulatory commitment to maintain (or make a regulatory commitment to develop and maintain), a capability for classifying fuel damage events at the Alert level threshold (typically this is 300 FCi/ml dose equivalent iodine). This capability may utilize the normal sampling system and/or correlations of radiation readings to radioisotope concentrations in the reactor coolant.
The licensee has committed to establish and maintain the capability for classifying fuel damage events at the Alert level threshold. This capability will be described in plant procedures. The licensee will implement this commitment within 6 months after the implementation of this license amendment.
4.3 Each licensee should verify that it has, and make a regulatory commitment to maintain (or make a regulatory commitment to develop and maintain), an I-131 site survey detection capability, including an ability to assess radioactive iodines
released to offsite environs, by using effluent monitoring systems or portable sampling equipment.
The licensee has committed to establish and maintain an I-131 site survey detection capability, including an ability to assess radioactive iodines released to offsite environs. This capability will be described in plant procedures. The licensee will implement this commitment within 6 months after the implementation of this license amendment.
The NRC staff finds that reasonable controls for the implementation and for subsequent evaluation of proposed changes pertaining to the above regulatory commitments are provided by the licensees administrative processes, including its commitment management program.
Should the licensee choose to incorporate a regulatory commitment into the emergency plan, final safety analysis report, or other documents with established regulatory controls, the associated regulations would define the appropriate change-control and reporting requirements.
The staff has determined that the commitments do not warrant the creation of regulatory requirements, which would require prior NRC approval of subsequent changes. The NRC staff has agreed that Nuclear Energy Institute 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes," provides reasonable guidance for the control of regulatory commitments made to the NRC staff. (See Regulatory Issue Summary 2000-17, Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC staff, dated September 21, 2000, ADAMS Accession Number ML003741774.) The commitments should be controlled in accordance with the industry guidance or comparable criteria employed by a specific licensee. The staff may choose to verify the implementation and maintenance of these commitments in a future inspection or audit.
5.0 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.
6.0 ENVIRONMENTAL CONSIDERATION
This 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 or changes a surveillance requirement. 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 (68 FR 18276). 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) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: W. Reckley Date: May 16, 2003