|
---|
Category:Advisory Report
[Table view] Category:Annual Operating Report
MONTHYEARJAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0035, Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments as Required by 10 CFR 50.59 and 10 CFR 72.48, and Summary of Commitment Changes, for 2019 and 20202021-05-0707 May 2021 Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments as Required by 10 CFR 50.59 and 10 CFR 72.48, and Summary of Commitment Changes, for 2019 and 2020 JAFP-20-0063, Submittal of 10 CFR 50.46 Annual Report2020-07-28028 July 2020 Submittal of 10 CFR 50.46 Annual Report JAFP-19-0072, 10 CFR 50.46 Annual Report2019-08-0101 August 2019 10 CFR 50.46 Annual Report JAFP-18-0069, Submittal of 10 CFR 50.46 Annual Report2018-08-0101 August 2018 Submittal of 10 CFR 50.46 Annual Report JAFP-17-0076, Submittal of 10 CFR 50.46 Annual Report2017-08-0101 August 2017 Submittal of 10 CFR 50.46 Annual Report JAFP-17-0046, 2016 Annual Radiological Environmental Operating Report2017-05-11011 May 2017 2016 Annual Radiological Environmental Operating Report JAFP-16-0121, James a FitzPatrick - Transmittal of 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2016-08-0101 August 2016 James a FitzPatrick - Transmittal of 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models JAFP-15-0092, James a FitzPatrick, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2015-08-0303 August 2015 James a FitzPatrick, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models JAFP-14-0061, 2013 Annual Radiological Environmental Operating Report2014-05-13013 May 2014 2013 Annual Radiological Environmental Operating Report CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G JAFP-13-0067, Annual Radiological Environmental Operating Report2013-05-15015 May 2013 Annual Radiological Environmental Operating Report CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012 Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G JAFP-11-0097, James a FitzPatrick - 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models2011-08-0101 August 2011 James a FitzPatrick - 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models JAFP-11-0056, 2010 Annual Radiological Environmental Operating Report2011-05-13013 May 2011 2010 Annual Radiological Environmental Operating Report JAFP-11-0055, 2010 Annual Radioactive Effluent Release Report, for the Period of January 1, 2010 Through December 31, 20102011-04-29029 April 2011 2010 Annual Radioactive Effluent Release Report, for the Period of January 1, 2010 Through December 31, 2010 JAFP-10-0084, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models2010-07-31031 July 2010 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models JAFP-10-0055, Annual Radioactive Effluent Release Report2010-04-30030 April 2010 Annual Radioactive Effluent Release Report JAFP-10-0056, 2009 Annual Radiological Environmental Operating Report2009-12-31031 December 2009 2009 Annual Radiological Environmental Operating Report CNRO-2009-00006, Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2009-04-13013 April 2009 Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G JAFP-07-0066, Transmittal of Annual Radiological Environmental Operating Report for the Period of January 1, 2006 Through December 31, 20062007-05-15015 May 2007 Transmittal of Annual Radiological Environmental Operating Report for the Period of January 1, 2006 Through December 31, 2006 ML0729605892007-05-15015 May 2007 Annual Radiological Environmental Operating Report; January 1, 2006 - December 31, 2006 JAFP-05-0069, Summary of Plant Changes, Tests, and Experiments for 2003 and 2004 as Required by 10 CFR 50.59 and 10 CFR 72.48, and Summary of Commitment Changes for 2003 and 20042005-05-0505 May 2005 Summary of Plant Changes, Tests, and Experiments for 2003 and 2004 as Required by 10 CFR 50.59 and 10 CFR 72.48, and Summary of Commitment Changes for 2003 and 2004 ML0534202162004-12-31031 December 2004 Annual Radiological Environmental Operating Report - 2004 ML0534202132003-12-31031 December 2003 Annual Radiological Environmental Operating Report. - 2003 JAFP-03-0124, CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models2003-08-28028 August 2003 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models JAFP-03-0065, Summary of Plant Changes, Tests, & Experiments for 2001/2002 as Required by 10 CFR 50.59 & 10 CFR 72.48, & Summary of Commitment Changes for 2001/20022003-05-12012 May 2003 Summary of Plant Changes, Tests, & Experiments for 2001/2002 as Required by 10 CFR 50.59 & 10 CFR 72.48, & Summary of Commitment Changes for 2001/2002 ML0534202102002-12-31031 December 2002 Annual Radiological Environmental Operating Report - 2002 ML18018B0491977-02-25025 February 1977 Letter Enclosing the Annual Environmental Operating Report January 1, 1976 - December 31, 1976 2024-07-31
[Table view] Category:Letter type:JAFP
MONTHYEARJAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for 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 JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 JAFP-24-0014, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-03-25025 March 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis 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 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-23-0066, for James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem2023-12-0101 December 2023 for James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem 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 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use 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 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 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 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 JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022 Core Operating Limits Report Cycle 26 JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022 Core Operating Limits Report Mid-Cycle 25 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.. JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022 Oswego County and New York State Participation in the Emergency Plan JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022 2021 REIRS Transmittal of NRC Form 5 JAFP-22-2020, Supplemental Information No. 1 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. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022 Supplemental Information No. 1 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. and 10CFR 50.69, Risk-Informed JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022 Amendments to Indemnity Agreements JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation 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 JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments 2024-09-25
[Table view] |
Text
Exelon Generation(, James A FitzPatrick NPP PO Box 110 Lycoming , NY 13093 Tel 315-342-3840 Richard M. Sullivan Regulatory Assurance Manager - JAF JAFP-21-0035 May 7, 2021 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333
Subject:
Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments as required by 10 CFR 50.59 and 10 CFR 72.48, and Summary of Commitment Changes, for 2019 and 2020
Dear Sir or Madam:
This letter transmits the summary of changes, tests and experiments implemented at the James A. FitzPatrick Nuclear Power Plant (JAF) that required performance of a 10 CFR 50.59 or 10 CFR 72.48 Evaluation, for the years 2019 and 2020, as required by 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2). Attachment 1 provides the summary of each 10 CFR 50.59 Evaluation. During this period there were no changes to the Independent Spent fuel Storage Installation requiring a 10 CFR 72.48 Evaluation.
Included is the summary of revised regulatory commitments for the years 2019 and 2020 as required by Nuclear Energy Institute Guideline NEI 99-04, "Guidelines For Managing NRC Commitment Changes," revision 0. During this period there were no changes to regulatory commitments which require NRC notification.
There are no new regulatory commitments made in this letter. Should you have any questions concerning this report, please direct them to Mr. Richard M. Sullivan, Regulatory Assurance Manager, at (315) 349-6562.
Very truly yours,
~
Richard M. Sullivan Regulatory Assurance Manager RMS/mh Attachments: 1. Summary of 10 CFR 50.59 Reports for 2019 and 2020 cc: NRC Regional Administrator, Region 1 NRC Resident Inspector NRC Project Manager New York State Department of Public Service NYSERDA President
JAFP-21-0035 Attachment 1 Summary of 10 CFR 50.59 Reports for 2019 and 2020 (5 Pages)
JAFP-21-0035 Attachment 1 Summary of 10 CFR 50.59 Reports for 2019 and 2020 Below are a brief description and a summary of the safety evaluation of each of those changes, tests, and experiments which were carried out at James A. FitzPatrick Nuclear Power Plant (JAF) without prior Nuclear Regulatory Commission (NRC) approval, pursuant to the requirements of 10 CFR 50.59.
JAF-SE-2019-001, Rev. 0: Tornado Missile Project ACTIVITY TYPE: Design Change Description of Change:
As part of the U.S. Nuclear Regulatory Commission (NRC) issued Regulatory Issue Summary (RIS) 2015-06 and Enforcement Guidance Memorandum (EGM) 15-002, all licensees of operating plants are reminded of their obligations to comply with their licensing basis and regulatory commitments to protect safe shutdown equipment from tornado generated missiles.
This activity evaluates non-conformities in Control and Relay Room HVAC systems and Concrete walls less than 24 thick, using the Tornado Missile Risk Evaluator (TMRE) method provided in NEI 17-02, Tornado Missile Risk Evaluator (TMRE) Industry Guidance Document.
This activity does not make any physical changes to any structures, systems, or components (SSC). Existing design analyses are not changed by this activity and continue to ensure equipment meet the current licensing basis. The Final Safety Analysis Report (FSAR) will be updated to clearly identify the Tornado Missile Protection licensing basis which includes the use of the TMRE methodology to address non-conformances.
Summary of Evaluation:
A 50.59 evaluation was performed due to a departure from a method of evaluation described in the FSAR. The new methodology will qualify components with non-conformities due to Tornado Missile. The calculation (JAF-CALC-19-00022) uses the TMRE probability risk assessment (PRA) methodology which was not included in the current FSAR. The TMRE methodology used to evaluate and qualify the non-conformities is done per the methodology provided in NEI 17-02 Rev. 1A which has been approved by the NRC in support of a license amendment for the Vogtle Electric Generating Plant. The TMRE methodology presented in Rev. 1A was approved, with restrictions, as an acceptable method to address non-conformances due to Tornado Missile.
Jensen Hughes Report No. JF-ASM-002, Rev. 0, JAF TMRE Model Development and Quantification qualified FitzPatricks Tornado Missile Protection non-conformances.
Page 1 of 5
JAFP-21-0035 Attachment 1 Summary of 10 CFR 50.59 Reports for 2019 and 2020 JAF-SE-2020-001, Rev. 0: Lifting Leads to Turbine Intercept Valve Fast Acting Solenoids and Extension of Steam Turbine Intercept Valve Testing Frequency ACTIVITY TYPE: Temporary Change Description of Change:
This activity is a Temporary Configuration Change to lift leads for the four Intercept Valve Operator Fast Acting Solenoid Valves (94SOV-IV1-1, 94SOV-IV2-1, 94SOV-IV3-1 and 94SOV-IV4-1) (FASV) to the respective Turbine Intercept Valves. Due to the leads being lifted, ST-21C, "Main Turbine Combined Intermediate Valve Test" which has a normal performance frequency of 6 months will be extended to 11 months (the remaining operating cycle). A spurious increased speed signal to the Intercept Valves FASVs has resulted in movement of the Intercept Valves when not required. The lifting of the leads prevents movement of the Turbine Intercept Valves.
The FSAR requires the steam turbine valves to be tested within every 225 days (approximately 7.4 months). To support the lifting of the leads, the steam turbine combined intermediate valve testing interval requires extension to 11 months.
Summary of Evaluation:
This activity lifts the leads to the Intercept Valves for FASVs, along with extending the turbine valve testing interval from 7.4 months to 11 months. This impacts the turbine missile probability.
A turbine missile is considered an "accident" for the purposes of 10 CFR 50.59 in accordance with NEI 96-07 Section 3.2. FSAR section 10.2.4 requires a missile generation probability of less than 1.0E-04 events per year. This limit is based upon Regulatory Guide 1.115 for a favorable turbine orientation and a resultant failure probability. By maintaining the turbine missile generation below 1.0E-04, the resultant accident probability is maintained less than 1.0E-07. Turbine missiles are postulated to occur due to two potential events: a low speed rotor failure (design overspeed) and a failure at speeds well greater than rated turbine speed (destructive overspeed).
Due to this activity, the calculated turbine missile generation probability is increased from 4.35E-05 events per year to 1.78E-04 events per year. The new value does not meet the applicable requirement given in the FSAR Section 10.2.4, however, the activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated.
JAF-SE-2020-002, Rev. 0: Digital Reactor Water Level Controls Upgrade ACTIVITY TYPE: Design Change Description of Change:
This activity upgrades the JAF Reactor Water Level Control System (RWLCS). The physical scope of this Activity includes replacing the existing RWLCS controller system, including the Level 8 turbine trip logic relays in Control Room back panel 09-18. The upgrade is based on the Ovation OCC-100. The digital control system was developed by Westinghouse Electric Company (WEC). This new system provides improved reliability, more precise system control, greater flexibility for future upgrades and reduced Operator burden during/following a SCRAM.
The new control scheme is designed to remove almost all Operational Critical Components (OPCCs) presently in the previous control system equipment.
Page 2 of 5
JAFP-21-0035 Attachment 1 Summary of 10 CFR 50.59 Reports for 2019 and 2020 Summary of Evaluation:
This does not adversely impact any safety analyses described in the FSAR and maintains the present design bases. The feedwater controller failures analyzed in the FSAR bound those of the new control system. The results of the accident and transient evaluations in the FSAR have not identified any transient requiring further review.
Based on the 10 CFR 50.59 Screening and Evaluation the activity may be implemented per plant procedures without obtaining a License Amendment; because no increased transient, accident, or malfunctions, consequences, and increased probabilities or likelihood of an accident or malfunction have been identified as more than minimally adverse in the 50.59 Evaluations review process.
JAF-SE-2020-003, Rev. 0: Revised Core Decay Heat Evaluation ACTIVITY TYPE: Design Change Description of Change:
This activity replaces the existing GE12-based decay heat with a bounding GNF2-based decay heat. This activity changes the facilitys underlying analytical basis because the decay heat is an input into multiple evaluations that demonstrate how intended design functions are accomplished. This activity revises those evaluations, as appropriate, for the GNF2-based decay heat change. This activity is a document-only change. There are no physical changes to the facility.
The existing 1999 GE12-based decay heat curve is replaced by a bounding GNF2-based decay heat curve. Both the 1999 curve and the GNF2 curve apply the ANSI/ANS-5.1-1979 decay heat standard. These new core design limits allow the core designer to greater flexibility and permit increased fuel economy via fewer bundles purchased. Correspondingly, there is also a reduction in the number of spent bundles discharged, reducing the demand for spent fuel pool and dry storage space.
The containment licensing basis is directly impacted by the new GNF2 curve. Short-term effects, such as containment loads and peak pressure, are unaffected. Long-term effects, such as peak suppression pool and peak drywell temperature, are affected, and the impact of this change is quantified. Additionally, the impact upon the containment pressure / temperature profiles for downstream evaluations such as equipment qualification and netpositive suction head are also quantified.
The existing station blackout, and Appendix R fire protection, calculations are revised to address the long-term impact from the bounding GNF2 decay heat.
Impacts upon the ECCS-LOCA evaluation, the loss-of-feedwater transient, and anticipated transient without scram are also evaluated.
Summary of Evaluation:
The 50.59 review finds that the activity increases the peak drywell temperature and peak suppression pool temperatures above the values shown in UFSAR Sections 4.7, 6.5, and 8.11.
Consequently, this review concludes that a 10 CFR 50.59 Evaluation is required because the effect of the change is such that existing safety analyses are no longer bounding, and FSAR safety analyses are re-run to demonstrate that all required safety functions and design requirements are met.
Page 3 of 5
JAFP-21-0035 Attachment 1 Summary of 10 CFR 50.59 Reports for 2019 and 2020 Because the decay heat is produced by an accident, this activity cannot alter any accident frequency or malfunction likelihood. Similarly, the decay heat change cannot introduce a new failure mode, or initiate a new accident or malfunction; therefore, this activity cannot create a new accident type or change a malfunction result. All design basis limits remain satisfied; therefore, there is no change in the radiological consequences of any accident or malfunction.
This activity does not exceed or alter any design basis limit for a fission product barrier, and this activity does not depart from a method of evaluation described by the FSAR. The 10 CFR 50.59 Evaluation concludes that the proposed activity may be implemented without prior NRC approval because there is no change to the Technical Specifications, no change to the Facility Operating License, and none of the eight 10 CFR 50.59 criterion are satisfied.
JAF-SE-2020-004, Rev. 0: Main Turbine Thrust Bearing Wear Detector ACTIVITY TYPE: Design Change Description of Change:
This activity is a design change that removes the excessive thrust bearing wear trip of the main turbine by the Thrust Bearing Wear Detector (TBWD). A control room annunciator alarm and a computer point will still be actuated on excessive thrust bearing wear. The automatic turbine trip is replaced with manual operator action based on the alarm response to trip the main turbine on excessive thrust bearing wear.
The resultant automatic trip removal requires that the operator be informed in order to respond and trip the turbine manually. The operating procedure OP-9 listed in FSAR Section 13.8.2 revision to remove the TBWD trip discussion and include this new manual trip action in response to the TBWD alarm.
Summary of Evaluation:
Per JAF's procedure AP-16.01 Attachment 4 Section 3.2, an annunciator alarm requiring immediate attention is required to have a yellow coloration, so the main control room annunciator point being revised from a trip alarm to alarm only for this thrust wear condition will be provided with the yellow heightened awareness for immediate operator response to trip the turbine, as provided in this Activity.
Thus, the proposed Activity involves a change to a procedure that adversely affects how a FSAR described SSC design function is performed and controlled, requiring a 50.59 Evaluation.
The 50.59 Evaluation determined that the proposed activity will not change the expected frequency of a turbine trip due to excessive thrust bearing wear. Therefore, proposed activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the FSAR. The proposed activity will not increase the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the FSAR.
Page 4 of 5
JAFP-21-0035 Attachment 1 Summary of 10 CFR 50.59 Reports for 2019 and 2020 JAF-SE-2020-005, Rev. 0: Lifting Leads to Turbine Intercept Valve Fast Acting Solenoids and Extension of Steam Turbine Intercept Valve Testing Frequency ACTIVITY TYPE: Temporary Change Description of Change:
This activity is a Temporary Configuration Change to lift the leads for the four Intercept Valve Operator Fast Acting Solenoid Valves (94SOV-IV1-1, 94SOV-IV2-1, 94SOV-IV3-1 and 94SOV-IV4-1) (FASV) to the respective Turbine Intercept Valves. Due to the leads being lifted, ST-21C, "Main Turbine Combined Intermediate Valve Test" which has a normal performance frequency of 6 months is extended indefinitely until the FASV function is restored. A spurious increased speed signal to the Intercept Valves FASVs has resulted in movement of the Intercept Valves when not required. The lifting of the leads prevents movement of the Turbine Intercept Valves. Work was performed in J1R24 to address the issue, but the leads will remain lifted for the duration of the next cycle to prevent undesired movement of the Intercept valves. This will allow the site to monitor the circuit to determine if troubleshooting was successful, without the risk.
The FSAR requires the steam turbine valves to be tested within every 225 days (approximately 7.4 months). Extending the test interval is an adverse change to how the FSAR described SSC design functions are performed or controlled, requiring evaluation under 10 CFR 50.59.
Summary of Evaluation:
Lifting of the leads for the FASVs of the Turbine Intercept Valves and extending the turbine valve testing interval will have an impact on the turbine missile probability. A turbine missile is considered an "accident" for the purposes of 10 CFR 50.59 in accordance with NEI 96-07 Section 3.2. FSAR section 10.2.4 requires a missile generation probability of less than 1.0E-04 events per year.
The methodology used to determine the probability remains the same as when it was previously calculated as discussed in JAF-SE-17-001 and JAF-CALC-20-00005 and documented in UFSAR section 10.2.4. This limit is based upon Regulatory Guide 1.115 for a favorable turbine orientation and a resultant failure probability. By maintaining the turbine missile generation below 1.0E-04, the resultant accident probability is maintained less than 1.0E-07. Turbine missiles are postulated to occur due to two potential events: a low speed rotor failure (design overspeed) and a failure at speeds well greater than rated turbine speed (destructive overspeed). The lifting of the leads affects the design of the control signal and prevents the function of the Intercept Valves to fast close but does not affect the design of the valves or prevent them from slow closing.
The calculation has been modified to assess the activity and the revised probability is below the NRC limit of 1.0E-4 as specified in FSAR section 10.2.4.
Page 5 of 5