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Category:Annual Operating Report
MONTHYEARJAFP-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 2023-07-31
[Table view] Category:Letter type:JAFP
MONTHYEARJAFP-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-23-0057, 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-23-0048, 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-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 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 JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021 Notification of Readiness for NRC 95001 Inspection JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021 Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement 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 JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, 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 Replacement2021-06-12012 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 JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021 Reply to a Notice of Violation; EA-20-138 JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021 Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 2023-08-31
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Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.46 JAFP-17-0076 August 1, 2017 U.S. 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:
10 CFR 50.46 Annual Report
References:
- 1) Letter from William C. Drews (Entergy Nuclear Operations, Inc.) to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Report,"
dated August 1, 2016 (JAFP-16-0121)
- 2) Letterfrom GE Hitachi Nuclear Energy (GEH) to Exelon, "10 CFR 50.46 Notification Letter 2017-01, Fitzpatrick Nuclear Power Plant",
dated June 12, 2017 The purpose of this letter is to submit the 10 CFR 50.46 reporting information for James A.
FitzPatrick Nuclear Power Plant (JAF). The most recent 10 CFR 50.46 Annual Report for JAF (Reference 1), was provided by Entergy Nuclear Operations, Inc.
Two attachments are included in this letter that provide the current JAF 10 CFR 50.46 status. Attachment 1, "Peak Cladding Temperature (PCT) Rack-Up Sheets", provides updated information regarding the PCT for the limiting analysis and Attachment 2, "Assessment Notes", contains a detailed description of each change or error reported.
This is the first annual report from JAF being submitted by Exelon Generation, LLC (EGC).
Subsequently, the prior 10 CFR 50.46 Annual Reports have been reformatted to match the current EGC format.
Since the Reference 1 annual report was submitted, one (1) new error, 2017-01, was reported. This new error is included in the current LOCA model assessments with a zero PCT impact.
U.S. Nuclear Regulatory Commission 10 CFR 50.46 Annual Report August 1, 2017 Page 2 No new regulatory commitments are established in this submittal.
If any additional information is needed, please contact Christian Williams at (610) 765-5729.
Jam Direct - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1) Peak Cladding Temperature Rack-Up Sheets
- 2) Assessment Notes cc: USNRC Administrator, Region I USNRC Project Manager, JAF, Unit 1 USNRC Senior Resident Inspector, JAF, Unit 1
ATTACHMENT 1 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments Assessments as of August 1, 2017 Peak Cladding Temperature Rack-Up Sheets James A. FitzPatrick Nuclear Power Plant
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of August 1, 2017 Attachment 1 Peak Cladding Temperature Rack-Up Sheets Page 1of2 PLANT NAME: James A. FitzPatrick ECCS EVALUATION MODEL: SAFER/G ESTR(PRI ME)-LOCA REPORT REVISION DATE: 08/01/2017 CURRENT OPERATING CYCLE: 23 ANALYSIS OF RECORD Evaluation Model:
- 1. B. S. Shiralkar et al, The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident: Volume Ill - SAFER/GESTR Application Methodology, February 1985 (NEDE-23785-1-P-A and NED0-23785-1-A)
- 2. Compilation of Improvements to GEN E's SAFER ECCS-LOCA Evaluation Model, NEDC-32950P, January 2000 as reviewed by letter from S. A. Richards (NRC) to J.
F. Klapproth (GE), General Electric Nuclear Energy (GENE) Topical Reports NEDC-32950P and NEDC-32084P Acceptability Review, May 24, 2000
- 3. GESTR-LOCA and SAFER Models for Evaluation of Loss-of-Coolant Accident Volume Ill, Supplement 1, Additional Information for Upper Bound PCT Calculation, NEDE-23785P-A, Supplement 1, Revision 1, March 2002
- 4. Implementation of PRIME Models and Data in Downstream Methods, NED0-33173 Supplement 4-A, Revision 1, November 2012 Calculations:
- 1. 0000-0076-4111-RO Rev 0, James A. Fitzpatrick Nuclear Power Plant GNF2 ECCS-LOCA Evaluation, August 2008 (JAF-RPT-08-00014 Rev 0)
Fuel: GNF2 Limiting Single Failure: Battery Failure Limiting Break Size and Location: Double-Ended Guillotine in a Recirculation Suction Pipe Reference Peak Cladding Temperature (PCT): GNF2 = 1800 °F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated December 22, 2008 (Note 1) GNF2: tiPCT =0 10 CFR 50.46 Report dated July 31, 2009 (Note 2) GNF2: tiPCT =0 10 CFR 50.46 Report dated July 31, 2010 (Note 3) GNF2: tiPCT =0 10 CFR 50.46 Report dated August 1, 2011 (Note 4) GNF2: tiPCT =50 10 CFR 50.46 Report dated August 1, 2012 (Note 5) GNF2: tiPCT =0 10 CFR 50.46 Report dated August 1, 2013 (Note 6) GNF2: tiPCT =40
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of August 1, 2017 Attachment 1 Peak Cladding Temperature Rack-Up Sheets Page 2 of 2 10 CFR 50.46 Report dated August 1, 2014 (Note 7) GNF2: ~PCT= 35 10 CFR 50.46 Report dated August 3, 2015 (Note 8) GNF2: ~PCT= -25 10 CFR 50.46 Report dated August 1, 2016 (Note 9) GNF2: ~PCT= 0 NET PCT GNF2: 1900 °F B. CURRENT LOCA MODEL ASSESSMENTS Total PCT change from current assessments (Note 10) GNF2: I~PCT =0 Cumulative PCT change from current assessments GNF2: Il~PCTI = O NET PCT GNF2: 1900 °F
ATTACHMENT 2 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments Assessments as of August 1, 2017 Peak Cladding Temperature Rack-Up Sheets James A. FitzPatrick Nuclear Power Plant Assessment Notes
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of August 1, 2017 Attachment 2 Assessment Notes Page 1of2
- 1) Prior LOCA Model Assessment GNF2 fuel was first installed during Refueling Outage 18, October 2008.
No changes or errors were reported against GNF2 during this reporting period.
[
Reference:
Letter from E. Dorman (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-08-0133, "1 O CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models," dated December 22, 2008.]
- 2) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.
[
Reference:
Letter from E. Dorman (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-09-0091, "10 CFR 50.46 Annual Report- Errors in Emergency Core Cooling System (ECCS) Evaluation Models," dated July 31, 2009.]
- 3) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.
[
Reference:
Letter from J. Pechacek (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-10-0084, "10 CFR 50.46 Annual Report- Errors in Emergency Core Cooling System (ECCS) Evaluation Models," dated July 31, 2010.]
- 4) Prior LOCA Model Assessment Two errors were reported against GNF2 fuel during this reporting period.
Error 2011-02 described the database error for heat deposition on peak cladding temperature (PCT) for 10x10 fuel bundles. The error was estimated to increase the GNF2 PCT by +45 °F.
Error 2011-03 described the updated formulation for gamma heat deposition to the channel wall for 10x10 fuel bundles. The error was estimated to increase the GNF2 PCT by +5 °F.
[
Reference:
Letter from Eugene W. Dorman (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-11-0097, "10 CFR 50.46 Annual Report-Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models," dated August 1, 2011.]
- 5) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.
[
Reference:
Letter from Jorge O'Farrill (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-12-0089, "10 CFR 50.46 Annual Report- Changes and Errors in Emergency Core Cooling System Evaluation Models," dated August 1, 2012.]
- 6) Prior LOCA Model Assessment One change was reported against GNF2 during this reporting period.
Change 2012-01 described the impact from PRIME implementation to compute fuel properties.
The error was estimated to increase the GNF2 PCT by +40 °F.
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of August 1, 2017 Attachment 2 Assessment Notes Page 2 of 2
[
Reference:
Letter from Chris M. Adner (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-13-0096, "10 CFR 50.46 Annual Report-Changes and Errors in Emergency Core Cooling System Evaluation Models," dated August 1, 2013.]
- 7) Prior LOCA Model Assessment Four changes and errors were reported against GNF2 fuel during this reporting period.
Change 2014-01 described code maintenance changes. These changes were estimated to have no impact upon the GNF2 PCT.
Error 2014-02 described a mass non-conservatism. The error was estimated to increase the GNF2 PCT by +10 °F.
Error 2014-03 described an error in the minimum core differential pressure model. The error was estimated to increase the GNF2 PCT by +20 °F.
Error 2014-04 Rev O described an error in the bundle I lower plenum counter-current flow-limited head model. The error was estimated to increase the GNF2 PCT by +5 °F.
[
Reference:
Letter from Chris M. Adner (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-14-0094, "10 CFR 50.46 Annual Report-Changes and Errors in Emergency Core Cooling System Evaluation Models," dated August 1, 2014.]
- 8) Prior LOCA Model Assessment One error was reported against GNF2 fuel during this reporting period.
Error 2014-04 Rev 1 was issued as a revision to error notification 2014-04 Rev 0 (Note 7). The revision identified a change to the hot bundle pressure head used as input to the counter-current flow-limited head model that resulted in a benefit (PCT reduction) . With this revised notice, the prior PCT change of +5 °F was replaced by a PCT change of-20 °F. Consequently, the error was estimated to have a net change upon GNF2 PCT of -25 °F.
[
Reference:
Letter from Chris M. Adner (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-15-0092, "1 O CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models," dated August 3, 2015.]
- 9) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.
[
Reference:
Letter from William C. Drews (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-16-0121, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models," dated August 1, 2016.]
- 10) Current LOCA Model Assessment One error was reported against GNF2 during this reporting period.
Error 2017-01 identifies that the GNF2 leakage paths between the bundle and the bypass (lower tie plate flow hole and channel to lower tie plate interface) were incorrectly modeled. The error was estimated to have no impact upon the GNF2 PCT.