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| ==Subject:== | | ==Subject:== |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| James A FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059 Entergy letter, 1 O CFR 50.46 Annual Report -Changes and Errors in Emergency Core Cooling System Evaluation Models, JAFP-14-0094, dated August 1, 2014 The attached report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2014 to July 31, 2015 for Entergy's James A. FitzPatrick Nuclear Power Plant (JAF). This letter contains no new commitments. Should you have any questions, please contact me at (315) 349-6766. Chris M. Adner Regulatory Assurance Manager CMA/mh cc: next page | | James A FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059 Entergy letter, 1 O CFR 50.46 Annual Report -Changes and Errors in Emergency Core Cooling System Evaluation Models, JAFP-14-0094, dated August 1, 2014 The attached report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2014 to July 31, 2015 for Entergy's James A. FitzPatrick Nuclear Power Plant (JAF). This letter contains no new commitments. |
| | Should you have any questions, please contact me at (315) 349-6766. Chris M. Adner Regulatory Assurance Manager CMA/mh cc: next page |
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| ==Attachment:== | | ==Attachment:== |
| 1 O CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 cc: NRC Regional Administrator, Region I NRC Resident Inspector Senior Project Manager
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| JAFP-15-0092 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 (3 Pages) | | 1 O CFR 50.46(a)(3)(ii) |
| JAFP-15-0092 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 1 of 3 INTRODUCTION This report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2014 to July 31, 2015 for Entergy's James A. FitzPatrick Nuclear Power Plant. Since the last reporting update (Reference 4), FitzPatrick has been subject to one notification of changes and errors in the Evaluation Model used for ECCS-LOCA calculation (Reference 9). Notification Letter 2014-04, Rev. 1 reported an Evaluation Model error related to bundle and reactor vessel lower plenum counter current flow limited (CCFL) head that results in a small (non-significant) change in PCT. Revision 1 replaces the change previously reported Notification Letter 2014-04, Rev. 0. | | Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 cc: NRC Regional Administrator, Region I NRC Resident Inspector Senior Project Manager |
| JAFP-15-0092 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 2 of 3 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK Report Period Notification Nature of PCT Change in ECCS Evaluation GNF2 Fuel(1) Estimated PCT Impact Licensing Basis PCT Prior Reporting Periods (Ref. 1, 2, 3, & 4) Cycle 19 Core Load Using GNF2 Type Fuel (Ref. 10, 11) n/a 1800°F 2011-02, Impact of Database Error for Heat Deposition on the Peak Cladding Temperature (PCT) for 10x10 Fuel Bundles (Ref. 5) 45°F 1845°F 2011-03, Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and 10x10 Fuel Bundles (Ref. 6) 5°F 1850°F 2012-01, Change in an acceptable evaluation model or application of such model due to PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (Ref. 7) 40°F 1890°F 2014-01, Maintenance Update Changes (Ref. 8) 0°F 1890F 2014-02, Mass Non-conservatism (Ref. 8) 10°F 1900°F 2014-03, Minimum Core Differential Pressure Model (Ref. 8) 20°F 1920°F 2014-04, Bundle/Lower Plenum Counter Current Flow Limited Head (Ref. 8) 5°F 1925°F Cumulative Licensing Basis PCT as of previous reporting period 1925°F August 1, 2014 - July 31, 2015 (Remove) 2014-04, Rev 0 -5°F 1920°F 2014-04, Rev. 1, Bundle/Lower Plenum Counter Current Flow Limited Head (Ref. 9) -20°F 1900°F Cumulative sum of absolute magnitude of changes and errors in this reporting period 25°F NOTE: (1) GNF2 fuel was first installed during Refueling Outage 18, October 2008 JAFP-15-0092 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 3 of 3 REFERENCES1. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-11-0097, dated August 1, 2011, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 2. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-12-0089, dated August 1, 2012, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 3. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-13-0096, dated August 1, 2013, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 4. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-14-0094, dated August 1, 2014, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 5. General Electric 10 CFR 50.46 Notification Letter 2011-02, dated July 20, 2011 regarding "Impact of Database Error for Heat Deposition on the Peak Cladding Temperature (PCT) for 10x10 Fuel Bundles" (Proprietary) 6. General Electric 10 CFR 50.46 Notification Letter 2011-03, dated July 20, 2011 regarding "Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and 10x10 Fuel Bundles" (Proprietary) 7. General Electric 10 CFR 50.46 Notification Letter 2012-01, dated November 29, 2012 regarding "PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties" (Proprietary) (Letter LRW-ENO-GEN-12-131) 8. Entergy Nuclear Operations, Inc. Memorandum to File, CEXI-2014-00002, dated May 23, 2014 regarding "Entergy Plant 10 CFR 50.46 Notification Letters 2014-01, 2014-02, 2014-03, and 2014-04" 9. General Electric Hitachi 10 CFR 50.46 Notification Letter 2014-04, Rev. 1, dated December 5, 2014 (Proprietary) 10. General Electric Nuclear Energy, "James A. FitzPatrick Nuclear Power Plant SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31317P, Class III (Proprietary), Revision 2, April 1993 11. GE Report, "James A. FitzPatrick Nuclear Power Plant GNF2 ECCS-LOCA Evaluation," 0000-0076-4111-R0, August 2008 (Proprietary) (Internal Report JAF-RPT-08-00014 R0)}} | | |
| | JAFP-15-0092 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 (3 Pages) |
| | JAFP-15-0092 0 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 1 of 3 INTRODUCTION This report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2014 to July 31, 2015 for Entergy's James A. FitzPatrick Nuclear Power Plant. Since the last reporting update (Reference 4), FitzPatrick has been subject to one notification of changes and errors in the Evaluation Model used for ECCS-LOCA calculation (Reference 9). Notification Letter 2014-04, Rev. 1 reported an Evaluation Model error related to bundle and reactor vessel lower plenum counter current flow limited (CCFL) head that results in a small (non-significant) change in PCT. Revision 1 replaces the change previously reported Notification Letter 2014-04, Rev. 0. |
| | JAFP-15-0092 0 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 2 of 3 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK Report Period Notification Nature of PCT Change in ECCS Evaluation GNF2 Fuel (1) Estimated PCT Impact Licensing Basis PCT Prior Reporting Periods (Ref. 1, 2, 3, & 4) Cycle 19 Core Load Using GNF2 Type Fuel (Ref. 10, 11) n/a 1800°F 2011-02, Impact of Database Error for Heat Deposition on the |
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| | Peak Cladding Temperature |
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| | (PCT) for 10x10 Fuel Bundles |
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| | (Ref. 5) 45°F 1845°F 2011-03, Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and 10x10 Fuel Bundles (Ref. 6) 5°F 1850°F 2012-01, Change in an acceptable evaluation model or application of such model due to |
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| | PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (Ref. 7) 40°F 1890°F 2014-01, Maintenance Update Changes (Ref. 8) 0°F 1890F 2014-02, Mass Non-conservatism (Ref. 8) 10°F 1900°F 2014-03, Minimum Core Differential Pressure Model |
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| | (Ref. 8) 20°F 1920°F 2014-04, Bundle/Lower Plenum Counter Current Flow Limited |
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| | Head (Ref. 8) 5°F 1925°F Cumulative Licensing Basis PCT as of previous reporting period 1925°F August 1, 2014 - |
| | July 31, 2015 (Remove) 2014-04, Rev 0 -5°F 1920°F 2014-04, Rev. 1, Bundle/Lower Plenum Counter Current Flow |
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| | Limited Head (Ref. 9) |
| | -20°F 1900°F Cumulative sum of absolute magnitude of changes and errors in this reporting period 25°F NOTE: (1) GNF2 fuel was first installed during Refueling Outage 18, October 2008 JAFP-15-0092 0 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 3 of 3 REFERENCES1. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-11-0097, dated August 1, 2011, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 2. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-12-0089, dated August 1, 2012, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 3. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-13-0096, dated August 1, 2013, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 4. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-14-0094, dated August 1, 2014, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 5. General Electric 10 CFR 50.46 Notification Letter 2011-02, dated July 20, 2011 regarding "Impact of Database Error for Heat Deposition on the Peak Cladding Temperature (PCT) for 10x10 Fuel Bundles" (Proprietary) 6. General Electric 10 CFR 50.46 Notification Letter 2011-03, dated July 20, 2011 regarding "Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and |
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| | 10x10 Fuel Bundles" (Proprietary) 7. General Electric 10 CFR 50.46 Notification Letter 2012-01, dated November 29, 2012 regarding "PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties" (Proprietary) (Letter LRW-ENO-GEN-12-131) 8. Entergy Nuclear Operations, Inc. Memorandum to File, CEXI-2014-00002, dated May 23, 2014 regarding "Entergy Plant 10 CFR 50.46 Notification Letters 2014-01, 2014-02, |
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| | 2014-03, and 2014-04" 9. General Electric Hitachi 10 CFR 50.46 Notification Letter 2014-04, Rev. 1, dated December 5, 2014 (Proprietary) 10. General Electric Nuclear Energy, "James A. FitzPatrick Nuclear Power Plant SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31317P, Class III (Proprietary), Revision 2, April 1993 11. GE Report, "James A. FitzPatrick Nuclear Power Plant GNF2 ECCS-LOCA Evaluation," 0000-0076-4111-R0, August 2008 (Proprietary) (Internal Report JAF-RPT-08-00014 R0)}} |
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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
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
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- -=-Entergy JAFP-15-0092 August 3, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. James A. FitzPatrick NPP P.0.Box110 Lycoming, NY 13093 Tel 315-342-3840 Chris M. Adner Regulatory Assurance Manager
Subject:
1 O CFR 50.46 Annual Report -Changes and Errors in Emergency Core Cooling System Evaluation Models
Reference:
Dear Sir or Madam:
James A FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059 Entergy letter, 1 O CFR 50.46 Annual Report -Changes and Errors in Emergency Core Cooling System Evaluation Models, JAFP-14-0094, dated August 1, 2014 The attached report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2014 to July 31, 2015 for Entergy's James A. FitzPatrick Nuclear Power Plant (JAF). This letter contains no new commitments.
Should you have any questions, please contact me at (315) 349-6766. Chris M. Adner Regulatory Assurance Manager CMA/mh cc: next page
Attachment:
1 O CFR 50.46(a)(3)(ii)
Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 cc: NRC Regional Administrator, Region I NRC Resident Inspector Senior Project Manager
JAFP-15-0092 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 (3 Pages)
JAFP-15-0092 0 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 1 of 3 INTRODUCTION This report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2014 to July 31, 2015 for Entergy's James A. FitzPatrick Nuclear Power Plant. Since the last reporting update (Reference 4), FitzPatrick has been subject to one notification of changes and errors in the Evaluation Model used for ECCS-LOCA calculation (Reference 9). Notification Letter 2014-04, Rev. 1 reported an Evaluation Model error related to bundle and reactor vessel lower plenum counter current flow limited (CCFL) head that results in a small (non-significant) change in PCT. Revision 1 replaces the change previously reported Notification Letter 2014-04, Rev. 0.
JAFP-15-0092 0 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 2 of 3 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK Report Period Notification Nature of PCT Change in ECCS Evaluation GNF2 Fuel (1) Estimated PCT Impact Licensing Basis PCT Prior Reporting Periods (Ref. 1, 2, 3, & 4) Cycle 19 Core Load Using GNF2 Type Fuel (Ref. 10, 11) n/a 1800°F 2011-02, Impact of Database Error for Heat Deposition on the
Peak Cladding Temperature
(PCT) for 10x10 Fuel Bundles
(Ref. 5) 45°F 1845°F 2011-03, Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and 10x10 Fuel Bundles (Ref. 6) 5°F 1850°F 2012-01, Change in an acceptable evaluation model or application of such model due to
PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (Ref. 7) 40°F 1890°F 2014-01, Maintenance Update Changes (Ref. 8) 0°F 1890F 2014-02, Mass Non-conservatism (Ref. 8) 10°F 1900°F 2014-03, Minimum Core Differential Pressure Model
(Ref. 8) 20°F 1920°F 2014-04, Bundle/Lower Plenum Counter Current Flow Limited
Head (Ref. 8) 5°F 1925°F Cumulative Licensing Basis PCT as of previous reporting period 1925°F August 1, 2014 -
July 31, 2015 (Remove) 2014-04, Rev 0 -5°F 1920°F 2014-04, Rev. 1, Bundle/Lower Plenum Counter Current Flow
Limited Head (Ref. 9)
-20°F 1900°F Cumulative sum of absolute magnitude of changes and errors in this reporting period 25°F NOTE: (1) GNF2 fuel was first installed during Refueling Outage 18, October 2008 JAFP-15-0092 0 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2014 to July 31, 2015 Page 3 of 3 REFERENCES1. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-11-0097, dated August 1, 2011, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 2. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-12-0089, dated August 1, 2012, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 3. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-13-0096, dated August 1, 2013, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 4. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-14-0094, dated August 1, 2014, "10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models" 5. General Electric 10 CFR 50.46 Notification Letter 2011-02, dated July 20, 2011 regarding "Impact of Database Error for Heat Deposition on the Peak Cladding Temperature (PCT) for 10x10 Fuel Bundles" (Proprietary) 6. General Electric 10 CFR 50.46 Notification Letter 2011-03, dated July 20, 2011 regarding "Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and
10x10 Fuel Bundles" (Proprietary) 7. General Electric 10 CFR 50.46 Notification Letter 2012-01, dated November 29, 2012 regarding "PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties" (Proprietary) (Letter LRW-ENO-GEN-12-131) 8. Entergy Nuclear Operations, Inc. Memorandum to File, CEXI-2014-00002, dated May 23, 2014 regarding "Entergy Plant 10 CFR 50.46 Notification Letters 2014-01, 2014-02,
2014-03, and 2014-04" 9. General Electric Hitachi 10 CFR 50.46 Notification Letter 2014-04, Rev. 1, dated December 5, 2014 (Proprietary) 10. General Electric Nuclear Energy, "James A. FitzPatrick Nuclear Power Plant SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," NEDC-31317P, Class III (Proprietary), Revision 2, April 1993 11. GE Report, "James A. FitzPatrick Nuclear Power Plant GNF2 ECCS-LOCA Evaluation," 0000-0076-4111-R0, August 2008 (Proprietary) (Internal Report JAF-RPT-08-00014 R0)