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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
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-23-0048, 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-23-0040, 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-23-0038, 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 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 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments ML21181A0572021-11-0404 November 2021 Issuance of Amendment No. 344 Adoption of TSTF-545 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-21-0069, 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-21-0053, 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-21-0051, 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 ML21144A1072021-05-17017 May 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 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 RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments JAFP-20-0080, Application to Revise Surveillance Requirement (SR) 3.5.1.62020-12-11011 December 2020 Application to Revise Surveillance Requirement (SR) 3.5.1.6 JAFP-20-0083, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule2020-12-11011 December 2020 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-20-0047, License Amendment Request: Application to Modify Technical Specifications 3.6.1.3, Primary Containment Isolation Valves2020-06-30030 June 2020 License Amendment Request: Application to Modify Technical Specifications 3.6.1.3, Primary Containment Isolation Valves JAFP-20-0046, License Amendment Request for Adoption of TSTF-478-A, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Using the Consolidated Line Item.2020-06-30030 June 2020 License Amendment Request for Adoption of TSTF-478-A, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Using the Consolidated Line Item. RS-20-025, Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2020-02-24024 February 2020 Supplement to Exelon Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls JAFP-20-0012, License Amendment Request - Application to Adopt Technical Specification Task Force Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line...2020-01-23023 January 2020 License Amendment Request - Application to Adopt Technical Specification Task Force Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line... ML19295G7832019-12-19019 December 2019 Issuance of Amendment No. 331 Regarding Change to Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters ML19277D5522019-10-0404 October 2019 Draft James A. FitzPatrick Nuclear Power Plant - Emergency License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19277G0852019-10-0404 October 2019 Emergency License Amendment Request: One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19276G3132019-10-0202 October 2019 Draft Exigent License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source JAFP-19-0092, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2019-09-26026 September 2019 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers JAFP-19-0089, License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads2019-09-12012 September 2019 License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads JAFP-19-0083, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation2019-09-0505 September 2019 License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions ML19157A2032019-07-11011 July 2019 Issuance of Amendment No. 325 Reactivity Anomalies Surveillance JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program RS-19-038, Supplement to the Application to Adopt TSTF-564, Safety Limit MCPR2019-03-0707 March 2019 Supplement to the Application to Adopt TSTF-564, Safety Limit MCPR JAFP-19-0033, License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 02019-03-0707 March 2019 License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 0 RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. JAFP-18-0106, License Amendment Request: Proposed Change to the Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters from Technical Specifications2018-11-29029 November 2018 License Amendment Request: Proposed Change to the Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters from Technical Specifications RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO JAFP-18-0093, License Amendment Request - Reactivity Anomalies Surveillance2018-10-0202 October 2018 License Amendment Request - Reactivity Anomalies Surveillance ML18292A5282018-09-25025 September 2018 Technical Evaluation Input for License Amendment Request to Remove Requirements for Deicing Heaters from Technical Specification 3.7.2 RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement JAFP-18-0048, James A. Fitzpatrick, Unit 1, License Amendment Request - Safety Limit Minimum Critical Power Ration Change2018-05-17017 May 2018 James A. Fitzpatrick, Unit 1, License Amendment Request - Safety Limit Minimum Critical Power Ration Change RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) JAFP-18-0014, James A. FitzPatrick Nuclear Power Plant - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2018-01-31031 January 2018 James A. FitzPatrick Nuclear Power Plant - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors JAFP-18-0014, Attachment 1: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2018-01-31031 January 2018 Attachment 1: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML18037A7872018-01-31031 January 2018 Attachment 1: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors 2023-08-31
[Table view] Category:Technical Specification
MONTHYEARJAFP-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 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 ML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal ML23095A3742023-04-0505 April 2023 Enclosure 2: Technical Specification (TS) Bases Revision 58 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-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-21-0053, 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 ML21095A2972021-04-0505 April 2021 Revised Technical Specifications Bases JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML19277G0852019-10-0404 October 2019 Emergency License Amendment Request: One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19276G3132019-10-0202 October 2019 Draft Exigent License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source JAFP-19-0092, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2019-09-26026 September 2019 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers JAFP-19-0089, License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads2019-09-12012 September 2019 License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-19-038, Supplement to the Application to Adopt TSTF-564, Safety Limit MCPR2019-03-0707 March 2019 Supplement to the Application to Adopt TSTF-564, Safety Limit MCPR JAFP-17-0093, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-10-0202 October 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML17104A0122017-04-10010 April 2017 Submittal of 2017 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes JAFP-17-0030, Submittal of 2017 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes2017-04-10010 April 2017 Submittal of 2017 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes JAFP-15-0047, 2015 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal2015-04-0808 April 2015 2015 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal JAFP-11-0102, Application for Change to the Current Licensing Basis, Authorizing Use of on Load Tap Changers with the Reserve Station Service Transformers2011-08-16016 August 2011 Application for Change to the Current Licensing Basis, Authorizing Use of on Load Tap Changers with the Reserve Station Service Transformers JAFP-10-0079, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Low Pressure Coolant Injection Inverter2010-06-25025 June 2010 Application for Amendment to Modify the Technical Specifications Requirements for Testing of Low Pressure Coolant Injection Inverter JAFP-10-0050, Proposed Change to the Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio2010-04-21021 April 2010 Proposed Change to the Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio JAFP-09-0086, Application for Amendment for James A. FitzPatrick Nuclear Power Plant to Modify the Technical Specifications Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure - High Function2009-07-31031 July 2009 Application for Amendment for James A. FitzPatrick Nuclear Power Plant to Modify the Technical Specifications Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure - High Function JAFP-09-0087, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves2009-07-31031 July 2009 Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions JAFP-08-0098, Supplement to the Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent...2008-09-24024 September 2008 Supplement to the Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent... ML0816900942008-08-0707 August 2008 Technical Specification JAFP-08-0011, License Amendment Request Application for Technical Specification Changes Using the Consolidated Line- Item Improvement Process (CLIIP)2008-02-0707 February 2008 License Amendment Request Application for Technical Specification Changes Using the Consolidated Line- Item Improvement Process (CLIIP) JAFP-08-0006, Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-3742008-01-22022 January 2008 Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-374 JAFP-07-0091, Application for Technical Specifications Change Based on TSTF-477, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems, Using the Consolidated Line Item Improvement Process (CLIIP)2007-07-25025 July 2007 Application for Technical Specifications Change Based on TSTF-477, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems, Using the Consolidated Line Item Improvement Process (CLIIP) JAFP-07-0088, James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 32007-07-17017 July 2007 James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3 JAFP-05-0084, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP)2005-05-31031 May 2005 Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP) JAFP-04-0083, Proposed License Amendment Re Safety Limit Minimum Critical Power Ratio2004-06-0404 June 2004 Proposed License Amendment Re Safety Limit Minimum Critical Power Ratio JAFP-03-0108, Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension2003-07-28028 July 2003 Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension ML0235000102002-12-0606 December 2002 Proposed Change to TS Regarding Local Power Range Monitor Calibration Frequency (JPTS-02-002) ML0222606432002-08-13013 August 2002 Technical Specifications for Amendment No. 275, Changes to the Technical Specification Leakage Limit for the Main Steam Isolation Valves from an Individual to an Aggregate Limit (Tac No. MB3333) JAFP-02-0146, Updated Markup and Retyped Technical Specification Pages for Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling...2002-07-17017 July 2002 Updated Markup and Retyped Technical Specification Pages for Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling... ML0219700842002-07-0303 July 2002 Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), Table of Contents ML0219700282002-07-0303 July 2002 Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), Attachment Table a - Administrative Changes Matrix ML0219700712002-07-0303 July 2002 Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), Attachment 4, Table L - Less Restrictive Changes Matrix ML0219700952002-07-0303 July 2002 Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), 3.6 Containment Systems ML0219701022002-07-0303 July 2002 Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), B 3.7 Plant Systems ML0219701382002-07-0303 July 2002 Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), Table of Contents ML0219701422002-07-0303 July 2002 Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), B 3.3 Instrumentation ML0219700922002-07-0303 July 2002 Technical Specifications, Amendment Conversion to Improved Technical Specifications (TAC No. MA5049), B. 3.4 Reactor Coolant System (RCS) JPN-02-016, Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling Dose Consequences2002-06-0707 June 2002 Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling Dose Consequences ML18031A0412000-04-14014 April 2000 Issuance of Amendment 261 Changes to the Technical Specifications Regarding the Allowed Containment Leakage Rate 2023-08-03
[Table view] Category:Bases Change
MONTHYEARJAFP-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 ML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal ML23095A3742023-04-0505 April 2023 Enclosure 2: Technical Specification (TS) Bases Revision 58 ML21095A2972021-04-0505 April 2021 Revised Technical Specifications Bases ML19276G3132019-10-0202 October 2019 Draft Exigent License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source JAFP-19-0092, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2019-09-26026 September 2019 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers JAFP-19-0089, License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads2019-09-12012 September 2019 License Amendment Request - Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability JAFP-17-0093, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-10-0202 October 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 JAFP-17-0030, Submittal of 2017 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes2017-04-10010 April 2017 Submittal of 2017 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes ML17104A0122017-04-10010 April 2017 Submittal of 2017 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes JAFP-15-0047, 2015 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal2015-04-0808 April 2015 2015 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal JAFP-11-0102, Application for Change to the Current Licensing Basis, Authorizing Use of on Load Tap Changers with the Reserve Station Service Transformers2011-08-16016 August 2011 Application for Change to the Current Licensing Basis, Authorizing Use of on Load Tap Changers with the Reserve Station Service Transformers JAFP-08-0006, Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-3742008-01-22022 January 2008 Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-374 JAFP-07-0088, James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 32007-07-17017 July 2007 James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3 JAFP-04-0083, Proposed License Amendment Re Safety Limit Minimum Critical Power Ratio2004-06-0404 June 2004 Proposed License Amendment Re Safety Limit Minimum Critical Power Ratio JAFP-02-0146, Updated Markup and Retyped Technical Specification Pages for Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling...2002-07-17017 July 2002 Updated Markup and Retyped Technical Specification Pages for Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling... 2023-08-03
[Table view] |
Text
' _ Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP
-E e Hn nthory bLycoming, RO. Box 110 NY 13093 Tel 315 349 6024 Fax 315 349 8480 TA. Sullivan Site Vice President - JAF June 4, 2004 JAFP-04-0083 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
James A. Fitzpatrick Nuclear Power Plant Docket No. 50-333 Proposed License Amendment to Safet' Limit Minimum Critical Power Ratio (SLMCPR)
Gentlemen:
Pursuant to IOCFR50.90, Entergy Nuclear Operations, Inc. (ENO) is submitting a request for amendment to the Technical Specifications (TS) for the James A. Fitzpatrick Nuclear Power Plant (JAFNPP). This proposed change provides revised values for the Safety Limit Minimum Critical Power Ratio (SLMCPR) for both single and dual recirculation loop operation.
The signed original of the Application for Amendment to the Operating License is enclosed for filing.
Attachment I contains the proposed new TS page and Attachment 2 is the Safety Evaluation for the proposed changes. Attachment 3 provides the marked-up version of the current Technical Specification page. Attachment 4 is a summary of the technical basis for the SLMCPR values and is considered proprietary information by Global Nuclear Fuel - Americas, LLC (GNF). In accordance with IOCFR2.390(bXl), an affidavit attesting to the proprietary nature of the enclosed information and requesting withholding from public disclosure is included with Attachment 4. Attachment 5 is the same GNF summary with the proprietary information removed, and is provided for public disclosure.
ENO has reviewed the proposed Technical Specification change in accordance with 10CFR50.92 and concludes that the proposed change does not involve a significant hazards consideration.
ENO has evaluated the proposed amendment against the criteria of 10CFR51.22 for environmental considerations and believes that the proposed change is eligible for categorical exclusion from the requirements for an environmental review in accordance with 10CFR5l.22(cX9). In accordance with 10CFR50.91, a copy of this application, with appropriate attachments, is being provided to the designated New York State official.
Regarding our proposed schedule for this amendment, we request your review and approval of the revised SLMCPR by September 3, 2004 with implementation prior to startup from the refueling outage.
The requested approval date and implementation period will allow sufficient time for effective planning and scheduling of affected activities associated with Refueling Outage 16, scheduled to begin on September 24, 2004.
C
If you have any questions concerning this transmittal or require additional information, please contact Mr. Andy Halliday at (315) 349-6055.
I declare under penalty of perjury that the forgoing is true and correct.
Executed on this the 4 day of " '-_ 2004.
Very truly yours, w cv- -- _ 5 ... ~
b
- Cb AL C fX T. A. Sullivan Site Vice President Attachments: 1. Revised Technical Specification Page (Retyped)
- 2. Safety Evaluation
- 3. Technical Specification Page (Mark-up)
- 4. GNF Summary of Technical Basis for SLMCPR Values (Proprietary Information)
- 5. GNF Summary of Technical Basis for SLMCPR Values (Non-Proprietary Version) cc: Regional Administrator, Region I Mr. Paul Eddy U. S. Nuclear Regulatory Commission New York State Department 475 Allendale Road of Public Service King of Prussia, PA 19406 3 Empire State Plaza, 10e Floor Albany, NY 12223 Albany, New York 12223 Office of the Resident Inspector U. S.Nuclear Regulatory Commission P. 0. Box 136 Lycoming, NY 13093 Mr. G. Vissing, Sr. Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop: 8C2 Washington, DC 20555 Mr. Peter R. Smith, President NYSERDA 17 Columbia Circle Albany, NY 12203-6399 ATTACHMENT 1 to JAFP-04-0083 REVISED TECHNICAL SPECIFICATION PAGE Safety Limit Minimum Critical Power Ratio (SLMCPR)
Entergy Nuclear Operations, Inc.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure c 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be i 251 RTP.
2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow k 10% rated core flow:
MCPR shall be k 1.06 for two recirculation loop operation or k 1.07 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be & 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
JAFNPP 2.0-1 Amendment XXX
ATTACHMENT 2 to JAFP-04-0083 SAFETY EVALUATION Safety Limit Minimum Critical Power Ratio (SLMCPR)
Entergy Nuclear Operations, Inc.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
1.0 Description of the Proposed Change Pursuant to I0CFR50.90, ENO proposes to revise Appendix A, Technical Specifications (TS) Section 2.1.1.2 of Facility Operating License DPR-59. The proposed changes to the Technical Specifications are as follows:
Page 2.0-1, Specification 2.1.1.2 - Replace the listed SLMCPR values of 1.09 (1.10 for single loop operation) with new values of 1.06 (1.07 for single loop operation).
2.0 Purpose of the Proposed Change Cycle specific calculations for JAFNPP by Global Nuclear Fuel (GNF) are summarized in Attachment 4.
The current SLMCPR values for dual and single loop operation contained in the Technical Specifications (1.09 and 1.10 respectively) are higher (more limiting) than values calculated by the fuel vendor for the next cycle (Cycle 17) using NRC-approved methods. The reduced SLMCPR values are consistent with reduced power distribution uncertainties that are supported by core monitoring methods to be used in Cycle 17 at JAFNPP. These uncertainties were reviewed and approved by the NRC as documented in . Based upon the core loading and fuel design to be used in Cycle 17, the cycle specific SLMCPR values were determined to be 1.06 for both dual loop and for single loop operation. (See additional discussion in section 3.0.)
3.0 Safety Assessment of Proposed Change The purpose of the SLMCPR is to provide high statistical probability that 99.9% of the fuel rods in the operating core would not experience transition boiling during the most limiting Abnormal Operational Transient (AOT). The criteria of transition boiling for determination of the SLMCPR is a conservative approach since this phenomena by itself does not signal the onset of fuel cladding failure. The revised SLMCPR for JAFNPP was determined using plant and cycle-specific fuel and core parameters and NRC approved methodology, as discussed in Attachment 4 (proprietary version of GNF summary of technical basis for SLMCPR values) and Attachment 5 (non-proprietary version of GNF summary). Analysis of the limiting AOT provides the allowed operating conditions, in terms of MCPR, of the core during the fuel cycle such that if the event were to occur, the transient MCPR would not be less than the SLMCPR.
No plant hardware or operational changes are required with this proposed change. supports the SLMCPR of 1.06 for single loop operation (SLO), however ENO is applying for a conservatively higher value of 1.07 for two reasons. First, the SLO SLMCPR has always been 0.01 higher than the dual loop SLMCPR for JAFNPP, and systems in place support this expected difference when operating in SLO. Second, it is expected that future cycles could show a 0.01 difference and a higher SLO SLMCPR in the Technical Specifications may avoid an amendment to support a higher value for the next or a future cycle. Actually, the single loop SLMCPR results are higher than the dual loop results by 0.008, but when rounded to two significant digits, the values are both 1.06. Both the SLO and dual loop calculation results are rounded up to the SLMCPR values submitted with this application.
4.0 No Significant Hazards Determination Pursuant to IOCFR50.92, JAFNPP has reviewed the proposed change and concludes that the change does not involve a significant hazards consideration since the proposed change satisfies the criteria in IOCFR50.92(c). These criteria require that operation of the facility in accordance with the proposed amendment will not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident Page 1 of3
previously evaluated, or (3) involve a significant reduction in a margin of safety. The discussion below addresses each of these criteria and demonstrates that the proposed amendment does not involve a significant hazards consideration.
The proposed change does not involve a significant hazards consideration because:
I. The operation of JAFNPP in accordance with the proposed amendment, will not involve a significant increase in the probability or consequences of an accident previously evaluated.
The basis of the Safety Limit Minimum Critical Power Ratio (SLMCPR) is to ensure no mechanistic fuel damage is calculated to occur if the limit is not violated. The new SLMCPR values preserve the existing margin to transition boiling and probability of fuel damage is not increased. The derivation of the revised SLMCPR for JAFNPP for incorporation into the Technical Specifications, and its use to determine plant and cycle-specific thermal limits, have been performed using NRC approved methods. These plant-specific calculations are performed each operating cycle and if necessary, will require future changes to these values based upon revised core designs. The revised SLMCPR values do not change the method of operating the plant and have no effect on the probability of an accident initiating event or transient.
Based on the above, JAFNPP has concluded that the proposed change will not result in a significant increase in the probability or consequences of an accident previously evaluated.
- 2. The operation of JAFNPP in accordance with the proposed amendment. will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes result only from a specific analysis for the JAFNPP core reload design.
These changes do not involve any new or different methods for operating the facility. No new initiating events or transients result from these changes.
Based on the above, JAFNPP has concluded that the proposed change will not create the possibility of a new or different kind of accident from those previously evaluated.
- 3. The operation of JAFNPP in accordance with the proposed amendment will not involve a significant reduction in a margin of safety.
The new SLMCPR is calculated using NRC approved methods with plant and cycle specific parameters for the current core design. The SLMCPR value remains high enough to ensure that greater than 99.9% of all fuel rods in the core will avoid transition boiling if the limit is not violated, thereby preserving the fuel cladding integrity. The operating MCPR limit is set appropriately above the safety limit value to ensure adequate margin when the cycle specific transients are evaluated. Accordingly, the margin of safety is maintained with the revised values.
As a result, JAFNPP has determined that the proposed change will not result in a significant reduction in a margin of safety.
On the basis of the above, JAFNPP has determined that operation of the facility in accordance with the proposed change does not involve a significant hazards consideration as defined in IOCFR50.92(c), in that it: (1) does not involve a significant increase in the probability or consequences of an accident Page 2 of 3
previously evaluated; (2) does not create the possibility of a new or different kind of accident from any accident previously evaluated; and (3) does not involve a significant reduction in a margin of safety.
Page 3 of 3
ATTACHMENT 3 to JAFP-04-0083 MARKED-UP TECHNICAL SPECIFICATION PAGE Safety Limit Minimum Critical Power Ratio (SLMCPR)
Entergy Nuclear Operations, Inc.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
SLs 2.0 2.0 SAFETY LIMITS (SMs) 2.1 SLs 2.1.1 Reactor Core SUs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25X RTP.
2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow 2 10X rated core f1nd:^
CPR shall be or k 44G fo fo recirculation loop operation ngle recirculation loop operation.
2.1.1.3 Reactor veifr~ater level shall be greater than the top of active irradiated fuel.
I 2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs: and 2.2.2 Insert all insertable control rods.
JAFNPP 2.0-1 Anendment .24- I
ATITACEIMENT 5 to JAFP-04-0083 GNF Summary of Technical Basis for SLMCPR Values (Non-Proprietary Version)
Entergy Nuclear Operations, Inc.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
Attachment AdditionaD Information Regarding the May 21, 2004 Cycle Specific SLMCPR for FitzPatrick Cycle 17 Proprietary Information Notice This document is the GNF non-pprietary version of the GNF propnetary report Fr=m the GNF proprietary version, the infomation denoted as GNF proprietary (enclosed in double brackets) was deleted to generate this version.
References I1 Lettr, Frank Akstulewicz (NRC to Glen A. Watford (GE), "Acceptance for Referencing of Licensing Topical Reports NEDC-32601P, Methodology and Uncertainties for Safety Limit MCPR Evaluations; NEDC-32694P, Power Distribution Uncertainties for Safety Limit MCPR Evaluation; and Amendment 23 to NEDE-2401 1-P-A on Cycle Specific Safety Limit MCPR," (TAC Nos. M97490, M99069 and M97491), March 11, 1999.
[21 Letter, Thmas EL Essig (NRC) to Glen A. Watford (GE), "Acceptance for Refrencing of Licensing Topical Report NEDC-32505P, Revision 1, R-Factor Calculation Method for GEl 1. GE12 and GE13 Fuel" (TAC Nos. M99070 and M9508 1), January 11, 1999.
[31 Genera! Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, NEDO-10958-A, January 1977.
l4J Letter, Glen A. Watford (ONF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to R. Pulsifer (NRC), "Confirmation of lOxlO Fuel Design Applicability to Improved SLMCPR, Power Distribution and R-Factor Methodologies", FLN-2001-016, September24, 2001.
[5] Letter, Glen A. Watford (GNF-A) to U. S. Nuclear Regulatory Commission Document Contol Desk with attention to J. Donoghue (NRC), "Confirmaton ofthe Applicability ofthe GEXL14 Correlation and Associated R-Factor Methodology for Calculating SLMCPR Values in Cores Containing GE14 Futr, FLN-2001-017, October 1, 2001.
[61 Ltter, Glen A. Watford (GNF-A) to U. S. Nuclear Regulatory Commission Document Control Desk with attention to J. Donoghue (NRC), 'Final Presentation Material for GEXL Presentation - Fcbnzary 11, 2002", FLN-2002-004, February 12, 2002.
page lof 7 0000-0028-9978
Attachment Additional Information Regarding the May 21,2004 Cycle Specific SLMCPR for FitzPatrick Cycle 17 Discussion Ihe Safety Limit Minimum Critcal Power Ratio (SLMCPR) evaluations for the Fitzpatrick Cycle 17 We performed using NRC approved methodology and uncertainties Ill. Table I summarizes the relevant input parameters and results of Cycle 17 and Cycle 16 cores. Additional information is provided in response to NRC questions related to smilar submittals regardmig changes in Technical Specification values of SLMCPR. NRC questions pertaining to how GE14 applications satisfyr the conditions of the NRC SERE' have been addressed in Reference [4]. Other geneically applicable questions related to application of the GEXL14 correlation, and to the applicable range for the R-factor methodology, are addressed in Reference
[5]. Items that require a plan/cycle specific response are presented below.
In general, the calculated safety limit is dominated by two key paruameters: (1) flatness of the core bundle-by-bundle MCPR distributions, and (2) flatness of the bundle pin-by-pin powerlR-factor distributions.
Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher calculated SLMCPR The impact of these parameters on the FitzPatrick Cycle 17 and Cycle 16 SLMCPR values is summarized in Table 1. The Cycle 16 column and the GETAB Bases column for Cycle 17 ae both provided for comparison to the Cycle 17 Revised Bases column. The impact of these uncertainties is discussed in more detail below.
The core loading information for FitzPatrick Cycle 16 is provided in Figure 1. For comparison the core loading information for FitzPatrick Cycle 17 is provided in Figure 2. The impact of the fiel loading pattern differences on the calculated SLMCPR is correlated to the values of 1
))
11 The uncontrolled bundle pin-by-pin power distributions were compared between the FitzPatrick Cycle 17 bundles and the Cycle 16 bundles. Pin-by-pin power distributions are characterized in terms of R-fictors using the NRC approved methodology [2. For the FitzPatrick Cycle 17 limiting case analyzed at BOC, ((
D]the FitzPatriclc Cycle 17 bundles have a more peaked power distribution than the bundles used forthe Cycle 16 SLMCPR analysis.
The SLMCPR was calculated for FitzPatrick Cycle 17 using uncertainties that have been previously reviewed and approved by the NRC. These uncertainties ae shown in Table 2a and described in Reference 11]. Wcre warntd higherplant-cle-specific uncertaindes were used, as liste in Table 2b.
These calculaions use the GEXL14 correlation for GE14 fuel.
11 page 2 of 7 0000-0028-9978
Attachment Additional Information Regarding the May 21,2004 Cycle Specific SLMCPR for FitzPatrick Cycle 17 For single loop operations (SLO) the calculated safety limit MCPR for the limiting case is 1.06 as detenmined by specific calculations for FzPatrick Cycle 17 at BOC The DLO and SLO SLMCPR values calculated for FitzPatrick Cycle 17 are dswn in Table 1.
Summary lhe calculated 1.06 SLMCPR and 1.06 SLO SLMCPR for FitzPatrick Cycle 17 are consistent with expectations 1[
DThese values are appropriate when the approved methodology and the reduced uncertainties given in NEDC-32601P-A and NEDC-32694P-A arm used.
Based on the information and discussion presented above, it is concluded that the calculated SLMCPR of 1.06 and 1.06 for SLO are appropriate for the FitzPatrick Cycle 17 corc.
page 3 of 7 0000-0028-9978
Attachment Additional Information Regarding the May 21, 2004 Cycle Specific SLMCPR for FitzPatrick Cycle 17 Table I Comparison of the FitzPatrick Cycle 17 and Cycle 16 SLMCPR ritz~atrick FitzPatrick FitzPatrick QUANTM, DESCRIElON Cytzle 16 Cycle 17 Cycde 17 Qcle 1 GETAB Bases' Revised Bases Number ofBundles in Core 560 560 560 Limiting Cvcle Exposure Point MOC MOC BOC Cycle Exposure at limiting Point M000 200 Reload Fuel Tpe GE14 GE14 GE14 Latest Rcload Batch Frwaction, % 35.0 36A 36A Latest Reload Average Batch Weight 4.05 4.05 4.05
%Enidhment Core Fuel Fraction for GE14 (fe) 35.0 71A 71A Core Fuel Fraction for GE12 (%) 65.0 28.6 28.6 Core Average Weiaht % Enrichment 4.06 4.05 4.05 Core MCPR (for limiting rod pattem) 1.46 1.38 1.37 ff f ff 11 if 1 Power disribution methodology GETAB NEDO- GETAB NEDO- Rcvised NEDC-10958-A 10958-A 32601P-A Power distribution uncertainty GETAB NEDO- GETAB NEDO. Reduced NEDC-10958-A 10958-A 32694P-A Non-powerdistribution uncertainty Revised NEDC- Rcvised NEDC- Revised NEDC-32601P-A 32601P-A 32601P-A Calculated Safety Limit MCPR 109 1.09 1.06 (DLO)
Calculated Safety Limit MCPR 110 1.09 10 (S WO
) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
lTe C17 GETAB comparison SLMCPR analysis used the Stndarduncertafiy values that we used for te C16 SLMCPR analyes.
page 4 of 7 0000-0028-9978
Attachment Additional Information Regarding the May 21,2004 Cycle Specific SLMCPR for FitzPatrick Cycle 17 Table 2a Standard Uncertainties DESCRIPTION FitzPatrick Cycle 16 FitzPatick Cycie 17 Non-power Distribution Uncertainties Revised NEDC-32601P-A Revised NEDC-32601P-A Core flow rate (derived fiom presur drop) 2.5 DLO 2.5 DLO 6.0 SLO 6.0 SLO Indialchannel fow area 11 I 11 Individual channel friction factor 5.0 5.0 Friction factormultiplier rr ir 11 Reactor pressure rr n Core inlet temperature 0.2 0.2 Feedwatertmipemture rr 11 If 11 Feedwater flow rate [f 11 If 11 Power Distribution Uncertainties GETAB NEDC-32601P-A Reduced NEDC-32694P-A GEXL R-fictor It 11 If 11 Random effective TIP reading 1.2 DLO 1.2 DLO 2.85 SLO 2.85 SWO Systematic effective TIP reading 8.6 If n Integrated effective TIP reading N/A If U Bundlepowe N/A It 11 Effective total bundle power uncertainty 4.3 Table 2b Exceptions to the Standard Uncertainties Used in FitzPatrick Cycle 17 GEXL R-factor U 2 2
TMs value was increased to accommodate increased cbanne bow uncertainty.
page 5 of 7 0000-0028-9978
A;.
Attachment Additional Information Regarding the MAy 21,2004 Cycle Specific SLMCPR for FitzPatrick Cycle 17 Figure 1 Reference Loading Pattern - FitzPatrick Cycle 16 52 BE3BE 50 9r EEl E 48 DEOWDE)E IEIDE BOM 48 ff-ERIMElYE-Off El 42 ME El E E3 f DE 40 S8 38 ID03 ffz rE lErM OE-I-YE- UErB01 Mr10 ErD f OE1 Of- s@ El 54 32 30 28 222 26 E17 xru OMsOZrEOD SEl 91- M-H-~NE ff21U-OEM~EDS SD SSD 8S 14 0
22g1 El 0 f -fE-IfErI rE1tB 921U-1f lr al UE- ffM 124 ME) OD ff@l 9M DMD9M EIUIS1 MI 102 f10 01 lBlal E]B f ELJ lWEl ff El 12 E gB C BE~~gEE x 14 3EE 17 *13 21 2325723135379443S 44 1 3567 9011 13 1517 1921 23 2527 2931 3335 3739 4143 4547 4951 Number Cycle Code Bundle Name Loaded Load d A GE12-P1ODSB412-17GZ-1QOT-150-T 2 13 B GE12-PI0DS8407-14G6.0-10OT-150-T 82 14 C GE12-P1DSB407-17GZ-1OOT-150-T 84 14 D GE12-PIODSB405-16GZ-1OOT-I50-T-2396 56 15 E GE12-PIODSB405-17GZ-IOOT-i50-T-2395 132 15 F GE12-PIODSB407-14G6.0-10OT-150-T 8 15 G GE14-PIODONAB4O5-16GZ-100T-150-T-2551 120 16 H GE14-P1ODNAB405-16GZ-IOT-150-T-2552 76 16 page 6 of 7 0000-0028-9978
i Attachment Additional Information Regarding the May 21, 2004 Cycle Specific SLMCPR for FitzPatrick Cycle 17 Figure 2 Reference Loading Pattern - FitzPatrick Cycle 17 52 __fM S0 0 F l l U0 J-EY-JE 48 48 e 46 In R]E3FIDl UEl1f =55 DE-T fl El DEl Egg E-1U E1 S 42 44 EhDDDShltDDDD 40 38 302 ff El E3 FEIl MD E-11El EDIE fEll DElDE-E E-T- @E--ff El MD WE1 28 nsF E EW hE Eh
's8 El 9 El BE-10 fE MBE-1 E-T- E-TE3 E-1UE- ETEU E-3r3O 14 "EVE ONE] EI- E21uE1^1 f MMgE 92ll fM- E~E10MQE1 M-1 32 FI~e~Ei~lEl~DkBlbEEWlESFI911Ml~
30 WE) WE3tBE- t UE-1 E 951 ff SE FM~ l 91- 5151 92-a6 BEigii~IElEh~EllktaEkEtElEh9n~EblEIEl9 14 2 ffm;} If} aElio 1 3 5 70 11 13 15 17 19 21 23 25 27 29 31 33353 739 41 43 45 47 49 61 Number Cycle Code Bundle Name Loaded Loaded A GE14-PIODNAB405-16GZ-IOOT-150-T8-2794 180 17 B GE14-PIODNAB405-15G8.0-10OT-150-T6-2793 24 17 C GE12-PIODSB405-16GZ-100T-150TB-3859 40 1S D GE12-P10DSB405-17GZ-1DOWT-150-T6-858 112 15 E GE12-PlODSB407-14G6.O-IOOT-150-T6 8 15 F GE14-PIODNAB405-16GZ-IOOT-150-T62562 120 ls G GE14-PIODNAB405-16GZ-IOOT-150-T6-2563 76 16 page 7 of 7 0000-0028-9979