Letter Sequence Approval |
---|
|
|
MONTHYEARML14342A2292014-12-0505 December 2014 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change Project stage: Request ML15120A2872015-04-30030 April 2015 Safety Limit Minimum Critical Power Ratio Change - Supplement 1 Response to Request for Additional Information Project stage: Supplement ML15120A2902015-04-30030 April 2015 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change Project stage: Request ML15218A5612015-08-0606 August 2015 Safety Limit Minimum Critical Power Ratio Change - Supplement 1 Response to Request for Additional Information Project stage: Supplement ML16008A2542016-01-13013 January 2016 Transmittal of Draft Safety Evaluations for Proposed Amendments Safety Limit Minimum Critical Power Ratio Change Project stage: Draft Approval ML15343A1652016-02-0808 February 2016 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change Project stage: Approval ML15343A1772016-02-0808 February 2016 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change Project stage: Approval 2015-08-06
[Table View] |
|
---|
Category:Letter
MONTHYEARML24022A2262024-01-22022 January 2024 (PBAPS) Unit 3 - Submittal of the Inservice Inspection (ISI) Owner'S Activity Report (OAR) for the 24th Refueling Outage for Unit 3 ML23346A2412024-01-17017 January 2024 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information (EPID L-2019-PMP-0061) - Letter IR 05000277/20234022024-01-11011 January 2024 Security Baseline Inspection Report 05000277/2023402 and 05000278/2023402 and Independent Spent Fuel Storage Installation Security Inspection 07200029/2023401 ML23354A1922024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23355A0622023-12-18018 December 2023 Independent Spent Fuel Storage Installation (Isfsi), Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan 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 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) IR 05000277/20230032023-10-30030 October 2023 Integrated Inspection Report 05000277/2023003 and 05000278/2023003 and Exercise of Enforcement Discretion ML23286A0012023-10-13013 October 2023 Reply to a Notice of Violation (NOV) - NOV 05000277, 05000278/2023010-01 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 ML23271A1342023-10-11011 October 2023 Dtf Analysis Letter IR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 ML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L IR 05000277/20230102023-09-15015 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000277/2023010 and 05000278/2023010 and Notice of Violation ML23251A2022023-09-11011 September 2023 Cover Letter W/Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement IR 05000277/20230052023-08-31031 August 2023 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2023005 and 05000278/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 IR 05000277/20230112023-08-15015 August 2023 Comprehensive Engineering Team Inspection Report 05000277/2023011 and 05000278/2023011 ML23226A1112023-08-14014 August 2023 10 CFR 50.46 Annual Report IR 05000277/20230022023-08-0808 August 2023 Integrated Inspection Report 05000277/2023002 and 05000278/2023002 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 IR 05000277/20230402023-07-17017 July 2023 95001 Inspection Supplemental Report 05000277/2023040 and Follow-Up Assessment Letter ML23188A0532023-07-0707 July 2023 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML23186A1272023-07-0606 July 2023 Response to Disputed Non-Cited Violation Documented in Peach Bottom Atomic Power Station, Units 2 and 3, Inspection Report 05000277/2022004 and 05000278/2022004 ML23178A0352023-06-27027 June 2023 Senior Reactor and Reactor Operator Initial License Examinations 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 ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ML23150A2052023-05-30030 May 2023 Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report 80 January 1, 2022 Through December 31, 2022 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 ML23142A1602023-05-23023 May 2023 Summary of April 11, 2023, Public Observation Meeting with Constellation Energy Generation, LLC Re Proposed Exemption Request from Work Hour Requirements ML23132A1582023-05-18018 May 2023 Correction to Technical Specification 3.4.7 (Page 3.4-16) Issued in Amendment No. 337 ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) IR 05000277/20230012023-05-0808 May 2023 Integrated Inspection Report 05000277/2023001 and 05000278/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI 2024-01-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23132A1582023-05-18018 May 2023 Correction to Technical Specification 3.4.7 (Page 3.4-16) Issued in Amendment No. 337 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22096A2982022-04-0808 April 2022 Correction Letter to Modification to Subsequent Renewed Facility Operating License Nos. DPR-44 and DPR-56 in Conjunction with Commission Memorandum and Order CLI-22-04 ML22054A1782022-03-0202 March 2022 Correction to Amendment Nos. 341 and 344 Changes to Technical Specification 5.5.7, Ventilation Filter Testing Program ML22004A2582022-02-14014 February 2022 Issuance of Amendment Nos. 341 and 344 Change to Technical Specification 5.5.7, Ventilation Filter Testing Program ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21074A4112021-05-14014 May 2021 Issuance of Amendment Nos. 338 and 341, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4B ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML20024G4262020-03-0505 March 2020 Issuance of Subsequent Renewed Facility Operating License No. DPR-56 for Peach Bottom Atomic Power Station Unit 3 ML20024G4232020-03-0505 March 2020 Issuance of Subsequent Renewed Facility Operating License No. DPR-44 for Peach Bottom Atomic Power Station Unit 2 ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19289B9312019-12-17017 December 2019 Issuance of Amendment Nos. 329 and 332 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML19266A6222019-10-29029 October 2019 Issuance of Amendment Nos. 328 and 331 Revising Technical Specifications 3.81, AC Sources - Operating, for a One-Time Extension of Completion Time ML19182A0062019-08-28028 August 2019 Issuance of Amendment Nos. 327 and 330 Reduce High Pressure Service Water System Design Pressure and Temporarily Extend Completion Times ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML19039A2232019-02-26026 February 2019 Issuance of Amendment Nos. 324 and 327 Expanded Actions for Leading Edge Flow Meter Conditions ML19011A3252019-02-26026 February 2019 Issuance of Amendment Nos. 323 and 326 to Revise Technical Specifications to Allow Continued Operation with Two Safety Relief Valves/Safety Valves Out of Service ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18302A2572018-11-0101 November 2018 Correction to Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems and Components (CAC Nos. MG0181 and MGO182; EPID L-2017-LLA-0281) ML18263A2322018-10-25025 October 2018 Issuance of Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69 (CAC Nos. MG0181 and MG0181; EPID L-2017-LLA-0281) ML18249A2402018-09-28028 September 2018 Issuance of Amendment Nos. 320 and 323 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18173A0422018-06-23023 June 2018 Issuance of Amendment Nos. 318 & 321 to Revise Technical Specifications 3.8.1 and 3.8.3, One-Time Change Suspending EDG Surveillance Test Completion Requirements (Emergency Situation) ML17325B7082017-12-27027 December 2017 Issuance of Amendments Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-542 (CAC Nos. MF9138 and MF9139; EPID L-2017-LLA-0174) ML17286A0132017-11-15015 November 2017 Issuance of Amendments Measurement Uncertainty Recapture Power Uprate (CAC Nos. MF9289 and MF9290; EPID L-2017-LLS-0001) ML17249A1512017-10-25025 October 2017 Issuance of Amendment Safety Relief Valve and Safety Valve Operability for Cycle 22 (CAC No. MF9705; EPID L-2017-LLA-0229) ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) ML16292A1882016-11-16016 November 2016 Issuance of Amendments Diesel Generator Fuel Oil Transfer Surveillance Requirements ML16235A4052016-10-14014 October 2016 Issuance of Amendments Diesel Generator Lube Oil Inventory Requirements ML16165A0022016-08-10010 August 2016 Issuance of Amendments Surveillance Requirements for Recirculation Pump Discharge Valves ML16159A1482016-07-0505 July 2016 Issuance of Amendments Surveillance Requirements for High Pressure Coolant Injection System and Reactor Core Isolation Cooling System ML16084A9682016-05-0909 May 2016 Issuance of Amendments Inservice Leak and Hydrostatic Testing Operation ML16064A1502016-04-27027 April 2016 Issuance of Amendments Reduce Steam Dome Pressure Specified in Reactor Core Safety Limits ML16034A3722016-03-21021 March 2016 Issuance of Amendments Maximum Extended Load Line Limit Analysis Plus ML15343A1652016-02-0808 February 2016 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change ML15343A1772016-02-0808 February 2016 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change ML15350A1792016-02-0101 February 2016 Issuance of Amendments Secondary Containment Access Openings 2023-08-30
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22236A6702022-08-30030 August 2022 Authorization and Safety Evaluation for Alternative Request I5R-14, Revision 1, ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22039A0752022-02-22022 February 2022 Site Walkdown for the Review of Plant Information to Perform a Risk Analysis in Accordance with LIC-504, Integrated Risk-Informed Decisionmaking for Emergent Issues,Regarding High Energy Arcing Faults ML22004A2582022-02-14014 February 2022 Issuance of Amendment Nos. 341 and 344 Change to Technical Specification 5.5.7, Ventilation Filter Testing Program ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21074A4112021-05-14014 May 2021 Issuance of Amendment Nos. 338 and 341, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4B ML21110A6802021-04-23023 April 2021 Approval of One-Time Alternative to Flaw Characterization and Removal Requirements for N-16A Nozzle ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20097D6442020-04-14014 April 2020 Issuance of Relief Request Limited Examination Coverage During Fourth 10-Year Inservice Inspection Interval ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19350A0152019-12-19019 December 2019 Correction to Relief Request I5R-10 Dated December 2, 2019, Errors Introduced During the Issuance of Relief from the ASME Code Dated December 2, 2019 ML19330C6442019-12-0202 December 2019 Issuance of Relief Request Examination of Standby Liquid Control Nozzle Inside Radius Section in Lieu of Specific ASME Code Requirements ML19266A6222019-10-29029 October 2019 Issuance of Amendment Nos. 328 and 331 Revising Technical Specifications 3.81, AC Sources - Operating, for a One-Time Extension of Completion Time ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19182A0062019-08-28028 August 2019 Issuance of Amendment Nos. 327 and 330 Reduce High Pressure Service Water System Design Pressure and Temporarily Extend Completion Times ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19149A2392019-06-11011 June 2019 Issuance of Relief Request Examination of Standby Liquid Control Nozzle Inside Radius Section in Lieu of Specific ASME Code Requirements ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19015A4222019-03-11011 March 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19039A2232019-02-26026 February 2019 Issuance of Amendment Nos. 324 and 327 Expanded Actions for Leading Edge Flow Meter Conditions ML19011A3252019-02-26026 February 2019 Issuance of Amendment Nos. 323 and 326 to Revise Technical Specifications to Allow Continued Operation with Two Safety Relief Valves/Safety Valves Out of Service ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18346A5002018-12-21021 December 2018 Issuance of Relief Request Use of ASME Code Case N-513-3 in Lieu of Specific ASME Code Requirements ML18331A2162018-12-21021 December 2018 Issuance of Alternative Requests Related to the Fifth Inservice Inspection Interval ML18263A2322018-10-25025 October 2018 Issuance of Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69 (CAC Nos. MG0181 and MG0181; EPID L-2017-LLA-0281) ML18249A2402018-09-28028 September 2018 Issuance of Amendment Nos. 320 and 323 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18179A3942018-07-18018 July 2018 Safety Evaluation of Relief Request I5R-03Regarding the Fifth 10-Year Interval of the Inservice Inspection Program ML18173A0422018-06-23023 June 2018 Issuance of Amendment Nos. 318 & 321 to Revise Technical Specifications 3.8.1 and 3.8.3, One-Time Change Suspending EDG Surveillance Test Completion Requirements (Emergency Situation) ML18141A6002018-05-30030 May 2018 Safety Evaluation of Relief Request GVRR-2 Regarding the Fifth 10-Year Interval of the Inservice Testing Program 2023-08-30
[Table view] Category:Technical Specifications
MONTHYEARML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements 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 ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML19266A6222019-10-29029 October 2019 Issuance of Amendment Nos. 328 and 331 Revising Technical Specifications 3.81, AC Sources - Operating, for a One-Time Extension of Completion Time ML19182A0062019-08-28028 August 2019 Issuance of Amendment Nos. 327 and 330 Reduce High Pressure Service Water System Design Pressure and Temporarily Extend Completion Times ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML18263A2322018-10-25025 October 2018 Issuance of Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69 (CAC Nos. MG0181 and MG0181; EPID L-2017-LLA-0281) ML18249A2402018-09-28028 September 2018 Issuance of Amendment Nos. 320 and 323 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML18257A0172018-09-14014 September 2018 Response to Request for Additional Information Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite Update to ... ML18173A0422018-06-23023 June 2018 Issuance of Amendment Nos. 318 & 321 to Revise Technical Specifications 3.8.1 and 3.8.3, One-Time Change Suspending EDG Surveillance Test Completion Requirements (Emergency Situation) 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 ML16217A0082016-08-11011 August 2016 Correction to Amendment Nos. 308 and 312 Regarding Surveillance Requirements for High Pressure Coolant Injection System and Reactor Core Isolation Cooling System ML16162A1012016-06-0909 June 2016 Response to Request for Additional Information Regarding Proposed License Amendment Concerning Emergency Diesel Generator Fuel Oil Transfer Surveillance Requirements ML16084A9682016-05-0909 May 2016 Issuance of Amendments Inservice Leak and Hydrostatic Testing Operation ML16034A3722016-03-21021 March 2016 Issuance of Amendments Maximum Extended Load Line Limit Analysis Plus ML15343A1772016-02-0808 February 2016 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change ML15350A1792016-02-0101 February 2016 Issuance of Amendments Secondary Containment Access Openings ML15275A2652015-10-0202 October 2015 License Amendment Request, Proposed Changes to the Technical Specifications for High Pressure Coolant Injection and Reactor Core Isolation Cooling Surveillance Test Pressure and Clarification of Surveillance Requirements ML15196A5592015-09-0808 September 2015 Issuance of Amendments Extension of Type a and Type C Leak Rate Test Frequencies ML15189A1852015-08-11011 August 2015 Issuance of Amendment No. 305 Change to Replacement Steam Dryer License Condition ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15167A4562015-07-28028 July 2015 Issuance of Amendments Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function ML15162A1392015-07-17017 July 2015 Issuance of Amendments Revise Technical Specification Definition for Recently Irradiated Fuel ML15154A6142015-06-30030 June 2015 Issuance of Amendments Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15093A0532015-03-27027 March 2015 (PBAPS) Unit 1 Decommissioning Status Report - 2014 ML14363A2272015-03-11011 March 2015 Issuance of Amendments Revise Facility Operating License and the Technical Specifications to Incorporate Administrative Changes ML15055A5062015-02-23023 February 2015 License Amendment Request - Proposed Changes to the Technical Specifications to Address Administrative Control of Secondary Containment Access Openings ML15041A6302015-02-19019 February 2015 Correction to Amendments Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs ML14247A5242014-09-0303 September 2014 License Amendment Request Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function ML14163A5892014-07-28028 July 2014 Issuance of Amendments Delete Non-Conservative Note from Limiting Condition for Operation 3.5.1 ML14192B1432014-07-11011 July 2014 License Amendment Request to Revise Facility Operating License and the Technical Specifications to Incorporate Administrative Changes ML14136A4852014-06-0505 June 2014 Issuance of Amendments Revise Normal Heat Sink Operability Requirements ML14160A6992014-06-0505 June 2014 Extended Power Uprate License Amendment Request - Supplement 27 Supplemental Information ML14079A1022014-05-0505 May 2014 Issuance of Amendments Safety Relief Valve and Safety Valve Lift Setpoint Tolerance ML14099A5372014-04-0808 April 2014 Response to Request for Additional Information - Revision of Normal Heat Sink Technical Specification to Remove the 24-Hour Average Temperature Limit with No Change to the Peak Maximum Temperature ML14092A3152014-03-28028 March 2014 Decommissioning Status Report for 2013 ML13109A4632013-06-18018 June 2013 Issuance of Amendments Revise Technical Specifications to Add Residual Heat Removal System Drywell Spray Function Requirements ML13018A2252013-01-17017 January 2013 Response to Request for Additional Information - Revision of Normal Heat Sink Technical Specification to Remove the 24-Hour Average Temperature Limit with No Change to the Peak Maximum Temperature ML12286A0122012-09-28028 September 2012 License Amendment Request - Extended Power Uprate ML12243A2862012-08-29029 August 2012 License Amendment Request to Add LCO 3.0.8 on the Lnoperability of Snubbers Using the Consolidated Line Item Improvement Process ML12200A3882012-07-18018 July 2012 Revision of Normal Heat Sink Technical Specification to Remove the 24-Hour Average Temperature Limit with No Change to the Peak Maximum Temperature ML1130814412011-11-0303 November 2011 License Amendment Request - Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks ML1116001802011-06-0808 June 2011 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change ML1109700672011-04-0606 April 2011 License Amendment Request to Revise Operability Requirements and Actions for RCS Leakage Instrumentation ML0824703052008-08-28028 August 2008 Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497 2023-08-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 8, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 - ISSUANCE OF AMENDMENT RE: SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGE (CAC NO. MF6169)
Dear Mr. Hanson:
The Commission has issued the enclosed Amendment No. 308 to Renewed Facility Operating License No. DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Unit 3. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated April 30, 2015, as supplemented by letter dated August 6, 2015.
The amendment revises the TSs related to the Safety Limit Minimum Critical Power Ratios. The proposed changes result from a cycle-specific analysis performed to support the operation of PBAPS, Unit 3, in the current Cycle 21. The re-analysis was performed to accommodate operation in the Maximum Extended Load Line Limit Analysis Plus operating domain based on a separate license amendment request dated September 4, 2014.
A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-278
Enclosures:
- 1. Amendment No. 308 to Renewed DPR-56
- 2. Safety Evaluation cc w/enclosures: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY. LLC PSEG NUCLEAR LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 308 Renewed License No. DPR-56
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (Exelon Generation Company) and PSEG Nuclear LLC (the licensees), dated April 30, 2015, as supplemented by letter dated August 6, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, the license is amended as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Renewed Facility Operating License No. DPR-56 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 308, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented prior to operation in the Maximum Extended Load Line Limit Analysis Plus operating domain.
FOR THE NUCLEAR REGULATORY COMMISSION Moo~d~i::~
Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: February 8, 2016
ATTACHMENT TO LICENSE AMENDMENT NO. 308 RENEWED FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove 3
Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 2.0-1 2.0-1
(5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1) Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3951 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 308, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1 , submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.
Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP),
including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 283 and modified by Amendment No. 304.
1
Renewed License No. DPR-56 Revised by letter dated October 28, 2004 Revised by letter dated November 5, 2004 Revised by letter dated May 29, 2007 Amendment No. 308 Page 3
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< 785 psig or core flow< 10% rated core flow:
THERMAL POWER shall be$ 23% RTP.
2.1.1.2 With the reactor steam dome pressure~ 785 psig and core flow~ 10% rated core flow:
MCPR shall be~ 1.15 for two recirculation loop operation or~ 1.15 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.
continued PBAPS UNIT 3 2.0-1 Amendment No. 308
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 308 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-56 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 DOCKET NO. 50-278
1.0 INTRODUCTION
By application dated April 30, 2015, as supplemented by letter dated August 6, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML15120A290 and ML15218A561, respectively), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request (LAR) for the Peach Bottom Atomic Power Station (PBAPS), Unit 3. The proposed amendment would revise the Technical Specifications {TSs) related to the Safety Limit Minimum Critical Power Ratios (SLMCPRs).
The proposed changes result from a cycle-specific analysis performed to support the operation of PBAPS, Unit 3, in the current operating cycle, Cycle 21. The re-analysis was performed to accommodate operation in the Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
operating domain based on a separate LAR dated September 4, 2014 (ADAMS Accession No. ML14247A503).
The supplement dated August 6, 2015, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC or the Commission) staff's original proposed no significant hazards consideration determination as published in the Federal Register on July 7, 2015 (80 FR 38773).
2.0 REGULATORY EVALUATION
=
Background===
Fuel design limits can be exceeded if the core exceeds critical power. Critical power is a term used for the power at which the fuel departs from nucleate boiling and enters a transition to Enclosure 2
film boiling. For boiling-water reactors (BWRs), the critical power is predicted using a correlation known as the General Electric (GE) critical quality boiling length correlation, better known as the GEXL correlation. Due to core-wide and operational variations, the margin to boiling transition is most easily described in terms of a critical power ratio (CPR), which is defined as the rod critical power, as calculated by GEXL, divided by the actual rod power. The greater a CPR value exceeds 1.0, the greater the margin to boiling transition is. The SLMCPR is calculated using a statistical process that takes into account operating parameters and uncertainties. The Operating Limit Minimum Critical Power Ratio (OLMCPR) is equal to the SLMCPR plus a CPR margin for transients. At the OLMCPR, at least 99.9 percent of the rods avoid boiling transition during steady state-operation and transients caused by a single operator error or equipment malfunction.
General Design Criteria The construction permit for PBAPS, Units 2 and 3, was issued by the Atomic Energy Commission (AEC) on January 31, 1968. As discussed in Appendix H to the PBAPS Updated Final Safety Analysis Report (UFSAR), during the construction/licensing process, both units were evaluated against the then-current AEC draft of the 27 General Design Criteria (GDC) issued in November 1965. On July 11, 1967, the AEC published, for public comment in the Federal Register (32 FR 10213), a revised and expanded set of 70 draft GDC (hereinafter referred to as the "draft GDC"). Appendix Hof the PBAPS UFSAR contains an evaluation of the design basis of PBAPS, Units 2 and 3, against the draft GDC. The licensee concluded that PBAPS, Units 2 and 3, conform to the intent of the draft GDC.
On February 20, 1971, the AEC published in the Federal Register (36 FR 3255) a final rule that added Appendix A to Title 1O of the Code of Federal Regulations (10 CFR) Part 50, "General Design Criteria for Nuclear Power Plants" (hereinafter referred to as the final GDC").
Differences between the draft GDC and final GDC included a consolidation from 70 to 64 criteria. As discussed in the NRC's Staff Requirements Memorandum for SECY-92-223, dated September 18, 1992 (ADAMS Accession No. ML003763736), the Commission decided not to apply the final GDC to plants with construction permits issued prior to May 21, 1971. At the time of promulgation of Appendix A to 10 CFR Part 50, the Commission stressed that the final GDC were not new requirements and were promulgated to more clearly articulate the licensing requirements and practice in effect at that time. Each plant licensed before the final GDC were formally adopted was evaluated on a plant-specific basis determined to be safe and licensed by the Commission.
The licensee has made changes to the facility over the life of the plant that may have invoked the final GDC. The extent to which the final GDC have been invoked can be found in specific sections of the UFSAR and in other plant-specific design and licensing basis documentation.
The NRC staff identified that final GDC-10, "Reactor design," is applicable to this LAR. Final GDC-1 O requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
Technical Specification Requirements In 10 CFR 50.36, "Technical specifications," the NRC established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plant's TSs.
As discussed in 10 CFR 50.36(c)(1 ), safety limits for nuclear reactors are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity. If a safety limit is exceeded, the reactor must be shut down. TS 2.1.1 specifies the reactor core safety limits for PBAPS, Unit 3. The LAR would change the SLMCPR values in TS 2.1.1.2 as follows:
Parameter Current Proposed SLMCPR SLM CPR Value Value Two Recirculation Loop Operation ~ 1.09 ~ 1.15 Single Recirculation Loop Operation ~ 1.12 ~ 1.15
3.0 TECHNICAL EVALUATION
3.1 Cycle 21 Core As discussed above in safety evaluation (SE) Section 1.0, the proposed SLMCPR changes result from a cycle-specific analysis performed to support the operation of PBAPS, Unit 3, in the current operating cycle, Cycle 21. Unit 3 entered Cycle 21 following the completion of the fall 2015 refueling outage. The Cycle 21 core loading consists of 344 fresh GNF2 fuel bundles, 272 once-burnt GNF2 fuel bundles, and 148 twice-burnt GNF2 fuel bundles.
The SLMCPR changes would be implemented to support operation in the MELLLA+ operating domain. PBAPS, Units 2 and 3, operation in the MELLLA+ operating domain is being evaluated under a separate LAR dated September 4, 2014.
3.2 Major Contributors to SLMCPR Change In general, the calculated safety limit is dominated by two key parameters: (1) flatness of the core bundle-by-bundle MCPR distribution; and (2) flatness of the bundle pin-by-pin power/A-Factor distribution. Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher calculated SLMCPR. The MCPR Importance Parameter (MIP) measures the core bundle-by-bundle. The MCPR distribution and A-Factor Importance Parameter (RIP) measures the bundle pin-by-pin power/A-Factor distribution. The impact of the fuel loading pattern on the calculated two-loop-operation (TLO) SLMCPR has been correlated to the parameter MIPRIP, which combines the MIP and RIP values. Another factor besides core MCPR distribution or bundle A-factor distribution that significantly impacts the SLMCPR is the expansion of the analysis domain that comes with the initial application of MELLLA+ (Reference 2). The rated power/minimum core flow point is analyzed at a lower core
flow (than without MELLLA+), using increased uncertainties (see Section 2.2.1.1 of Reference 2) that tend to increase the SLMCPR.
3.3 Methodology Global Nuclear Fuel (GNF) developed the PBAPS, Unit 3, Cycle 21 SLMCPR values using the following NRG-approved methodologies and uncertainties:
- NEDC-32601 P-A, Revision 0, "Methodology and Uncertainties for Safety Limit MCPR Evaluations" (Reference 3)
- NEDC-32694P-A, Revision 0, "Power Distribution Uncertainties for Safety Limit MCPR Evaluations" (Reference 4)
- NEDE-24011-P-A, Revision 20, "General Electric Standard Application for Reactor Fuel" (referred to as GESTAR-11) (Reference 5)
- NEDC-32505P-A, Revision 1, "A-Factor Calculation Method for GE11, GE12 and GE13 Fuel" (Reference 6)
- NEDC-33173P-A, Revision 4, "Applicability of GE Methods to Expanded Operating Domains" (Reference 7)
Plant-specific use of these methodologies must adhere to certain restrictions as discussed below.
3.3.1 Methodology Restrictions Based on the review of Licensing Topical Reports NEDC-32601 P-A, NEDC-32694P-A, and Amendment 25 to NEDE-24011-P-A, the NRC staff identified the following restrictions for the use of these Topical Reports:
- 1. The TGBLA (lattice physics code) fuel rod power calculational uncertainty should be verified when applied to fuel designs not included in the benchmark comparisons of Table 3.1 of NEDC-32601 P-A, since changes in fuel design can have a significant effect on calculation accuracy.
- 2. The effect of the correlation of rod power calculation uncertainties should be reevaluated to ensure the accuracy of the A-Factor uncertainty when the methodology is applied to a new fuel lattice.
- 3. In view of the importance of MIP (MCPR Importance Parameter) criterion and its potential sensitivity to changes in fuel bundle designs, core loading, and operating strategies, the MIP criterion should be reviewed periodically as part of the procedural review process to ensure that the specific value recommended in NEDC-32601 P-A is applicable to future designs and operating strategies.
Restrictions (1) and (2)
With respect to restrictions (1) and (2), GNF stated in Reference 8 that the rod power calculational uncertainties are dominated by geometrical considerations and that the uncertainty for GE14 fuel is identical to GE12 fuel. GNF stated in Reference 9 that GNF2 fuel is designed for mechanical, nuclear, and thermal-hydraulic compatibility with the other 1Ox10 GNF fuel designs. The design has features of the currently operating GE10, GE11/13, and GE12/14 fuel, including pellet-cladding interaction resistant barrier cladding, high performance spacers, part length rods, interactive thick corner/thin wall channel, and axial enrichment loading. The GNF2 design is a 1Ox1 O array with 92 fuel rods, 2 large central water rods, and 14 part length fuel rods. The part length rod configuration improves efficiency and reactivity margins. Tables 2.1 and 3.1 of NEDC-32601 P-A provide a summary of SLMCPR uncertainties and a summary of pin power comparisons for a typical GNF fuel design. The values given in these tables are representative of the values being calculated for GE14 and GNF2 fuel.
In a request for additional information (RAI), the NRC staff asked the licensee to explain the differences in design and geometrical considerations between GNF2 and GE14 fuel. In response to the staff's question (Reference 10), the licensee stated that GNF2 is an evolutionary fuel product based on GE14 and that it is not considered a new fuel design, as it maintains the previously established 1Ox1 O array.
Based on the above discussion, the NRC staff concludes that the SLMCPR and the rod power calculational uncertainties used by GNF to develop the PBAPS, Unit 3, Cycle 21 SLMCPR values are valid for GNF2 fuel and that the response to the RAI addresses the staff's concern and is acceptable.
Restriction (3)
The limiting control rod patterns used to calculate the SLMCPR reasonably assure that at least 99.9 percent of the fuel rods in the core would not be expected to experience boiling transition during normal operation or anticipated operational occurrences during the operation of PBAPS, Unit 3, Cycle 21. The NRC staff determined that the rod patterns used produce a limiting MCPR distribution that reasonably bounds the MCPR distributions that would be expected during the operation of the PBAPS, Unit 3, core throughout Cycle 21 in conjunction with the MELLLA+
LAA. In accordance with NEDC-33173P-A, Revision 4 (Reference 7), a 0.02 SLMCPR penalty was added for operation in the MELLLA+ region.
In summary, the NRC staff concludes that the licensee has adequately addressed the restrictions of Licensing Topical Reports NEDC-32601 P-A, NEDC-32694P-A, Amendment 25 to NEDE-24011-P-A, NEDC-33173P-A, and NEDC-32505P-A, and that the use of these reports to evaluate the PBAPS, Unit 3, Cycle 21 SLMCPR is acceptable.
3.4 Departures from NRG-Approved Methodology No departures from NRG-approved methodologies were identified by the NRC staff's review.
3.5 Deviations from the NRG-Approved Calculational Uncertainties 3.5.1 A-Factor The A-factor is an input into the GEXL correlation used to describe the local pin-by-pin power distribution and the fuel assembly and channel geometry on the fuel assembly critical power.
The R-f actor uncertainty analysis includes an allowance for power peaking modeling uncertainty, manufacturing uncertainty, and channel bow uncertainty. GNF has increased this uncertainty for all SLMCPR calculations to account for the potential impact of control blade shadow corrosion induced bow. GNF has generically increased the GEXL A-Factor uncertainty (Reference 6) to account for an increase in channel bow due to the emerging unforeseen phenomenon called control blade shadow corrosion-induced channel bow, which is not accounted for in the channel bow uncertainty component of the approved A-Factor uncertainty.
The PBAPS, Unit 3, Cycle 21 analysis shows that the expected channel bow uncertainty is bounded by the GEXL A-Factor uncertainty. Thus, the NRC staff finds that the use of a GEXL A-Factor uncertainty (Reference 6) adequately accounts for the expected control blade shadow corrosion-induced channel bow for PBAPS, Unit 3, Cycle 21.
3.5.2 Core Flow Rate and Random Effective Traversing In-Core Probe {TIP) Reading As a result of issues reported to the NRC pursuant to 10 CFR Part 21 (Reference 11 ), GNF has expanded the state points previously used in the determination of the SLMCPR. Consistent with the discussion in Reference 11, GNF now performs analyses at the rated core power and minimum licensed core flow point, in addition to analyses at the rated core power and rated core flow point. The NRG-approved SLMCPR methodology is applied at each statepoint that is analyzed. For the TLO calculations performed in the MELLLA+ domain at rated power/minimum core flow and off-rated power/off-rated core flow, the approved uncertainty values for the core flow rate (2 .5 percent) and the random effective Tl P reading ( 1.2 percent) are conservatively adjusted by using the single-loop-operation (SLO) uncertainty values of 6.0 percent and 2.85 percent for the core flow rate and random effective TIP reading respectively. The treatment of the core flow and random effective TIP reading uncertainties is based on a conservative assumption that the signal-to-noise ratio deteriorates as core flow is reduced.
In accordance to the limitation and conditions of NEDC-33006P-A, Revision 3 (Reference 12),
SLO uncertainties are applied to TLO conditions for operation in the MELLLA+ region.
For PBAPS, Unit 3, Cycle 21, the most limiting SLMCPR calculation occurred at the 78.8 percent rated power/55 percent rated flow point. At low core flows, the search spaces for the limiting rod pattern and the nominal rod pattern are essentially the same. Hence, the rod pattern used to calculate the SLMCPR at 78.8 percent rated power/55 percent rated flow reasonably assures that at least 99.9 percent of the fuel rods in the core would not be expected to experience boiling transition during normal operation or anticipated operational occurrences during the operation of PBAPS, Unit 3, Cycle 21. Consequently, the SLMCPR value calculated from the 78.8 percent rated power/55 percent rated core flow condition limiting MCPR distribution reasonably bounds this mode of operation for PBAPS, Unit 3, Cycle 21. The NRC staff finds that the uncertainty used in the analysis should bound the original non-flow
dependent uncertainties and, therefore, the staff finds it acceptable for PBAPS, Unit 3, Cycle 21.
3.6 Core Monitoring System For PBAPS, Unit 3 Cycle 21, the GNF 30 MONICORE system will be used as the core monitoring system. The 30 MONICORE system is in widespread use throughout the GNF fueled fleet of BWRs similar to PBAPS. Use of a current version of 30 MONICORE provides the plant capability to perform the reactivity anomaly surveillance. Use of 30 MONICORE has been previously evaluated and accepted by the NRC in a letter dated March 11, 1999 (Reference 4). Therefore, the NRC staff finds the use of the GNF 30 MONICORE system for PBAPS, Unit 3, Cycle 21 to be acceptable.
3.7 Technical Evaluation Conclusion Based on the discussion in SE Sections 3.1 through 3.6, the NRC staff concludes that the proposed amendment is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (80 FR 38773). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. Exelon letter to the NRC, "License Amendment Request - Maximum Extended Load Line Limit Analysis Plus," dated September 4, 2014 (ADAMS Accession No. ML14247A503).
- 2. Safety Evaluation of GE Licensing Topical Report NEDC-33006P, "General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus," Revision 2, dated October 2008 (ADAMS Accession No. ML081130008).
- 3. General Electric Nuclear Energy Licensing Topical Report NEDC-32601 P-A, Revision 0, "Methodology and Uncertainties for Safety Limit MCPR Evaluations," dated August 1999 (ADAMS Accession Nos. ML003740145 (non-public) and ML14093A216 (public)).
- 4. NRC letter to General Electric, "Acceptance for Referencing of Licensing Topical Reports NEDC-32601 P, Methodology and Uncertainties for Safety Limit MCPR Evaluations; NEDC-32694P, Power Distribution Uncertainties for Safety Limit MCPR Evaluations; and Amendment 25 to NEDE-24011-P-A on Cycle-Specific Safety Limit MCPR," dated March 11 , 1999 (ADAMS Accession No. ML993140059).
- 5. Global Nuclear Fuel, Licensing Topical Report NEDE-24011-P-A, Revision 20, "General Electric Standard Application for Reactor Fuel," dated December 2013 (ADAMS Accession No. ML13352A474).
- 6. GE Nuclear Energy, Licensing Topical Report NEDC-32505P-A, Revision 1, "A-Factor Calculation Method for GE11, GE12 and GE13 Fuel," dated July 1999 (ADAMS Accession No. ML060520634).
- 7. GE Hitachi Nuclear Energy, Licensing Topical Report NEDC-33173P-A, Revision 4, "Applicability of GE Methods to Expanded Operating Domains," dated November 2012 (ADAMS Accession No. ML123130130}.
- 8. Global Nuclear Fuel letter to NRC, "Confirmation of 1Ox10 Fuel Design Applicability to Improved SLMCPR, Power Distribution and A-Factor Methodologies," dated September 24, 2001 (ADAMS Accession No. ML012710272).
- 9. Global Nuclear Fuel, Licensing Topical Report NEDE-31152P, Revision 9, "Global Nuclear Fuels Fuel Bundle Designs," dated May 2007 (ADAMS Accession No. ML071510276).
- 10. Letter from Exelon to NRC, "Safety Limit Minimum Critical Power Ratio Change -
Supplement 1, Response to Request for Additional Information," dated August 6, 2015 (ADAMS Accession No. ML15218A561 ).
- 11. GE Nuclear Energy letter MFN 04-081 to NRC, "Part 21 Reportable Condition and 60-Day Interim Report; Notification: Non-conservative SLMCPR," dated August 24, 2004 (ADAMS Accession No. ML042720293).
- 12. GE Hitachi Nuclear Energy, Licensing Topical Report NEDC-33006P-A, "General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus," Revision 3, dated June 2009 (ADAMS Accession No. ML091800530).
- 13. Letter from Exelon to NRC, "License Amendment Request, Safety Limit Minimum Critical Power Ratio Change," dated April 30, 2015 (ADAMS Accession No. ML15120A290).
Principal Contributors: W. MacFee R. Ennis Date: February 8, 2016
ML15343A177 bFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/LA DSS/SRXB/BC DSS/STSB/BC OGC- NLO NAME REnnis LRonewicz CJackson RElliott DRoth (MHamm for)
DATE 12/14/15 12/10/15 12/21/15 12/22/15 12/29/15 OFFICE DORL/LPL 1-2/BC DORL/LPL 1-2/PM NAME DBroaddus REnnis (TLamb for)
DATE 12/30/15 2/8/16