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MONTHYEARML15118A7172015-04-28028 April 2015 Response to Request for Additional Information on Mellla+ License Amendment Request - Supplement 3 Project stage: Supplement ML15187A3912015-07-0606 July 2015 Supplement 4 - Response to Request for Additional Information on Mellla+ License Amendment Request, Attachments; 2, 3 and 4 Project stage: Supplement ML15247A0882015-09-0404 September 2015 Attachment 2, EPU and Mellla+ Combined Rsd Masrs (Non-Proprietary) and Attachment 3, Affidavit Project stage: Request ML15274A4672015-10-0101 October 2015 MELLLA License Amendment Request - Supplement 6 Response to Request for Additional Information Project stage: Supplement ML15299A0842015-10-26026 October 2015 PBAPS MELLLA License Amendment Request - Supplement 7 Revision Regarding Proposed Technical Specifications Project stage: Supplement ML15302A2372015-11-0909 November 2015 Transmittal of Draft Safety Evaluation for Proposed Maximum Extended Load Limit Plus Amendment Project stage: Draft Approval ML15278A0462016-02-0505 February 2016 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Units 2 and 3 Project stage: Withholding Request Acceptance ML16034A3722016-03-21021 March 2016 Issuance of Amendments Maximum Extended Load Line Limit Analysis Plus Project stage: Approval ML16099A2022016-04-0808 April 2016 Mellla+ License Amendment Issuance - Request for Corrections to Approved License Amendment Safety Evaluation Project stage: Request 2015-07-06
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Category:Letter
MONTHYEARIR 05000277/20240032024-11-0404 November 2024 Integrated Inspection Report 05000277/2024003 and 05000278/2024003 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24281A1012024-10-0707 October 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24221A2582024-09-0606 September 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Peach Bottom Atomic Power Station, Units 2 and 3 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification 05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum2024-09-0505 September 2024 Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum IR 05000277/20240052024-08-29029 August 2024 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2024005 and 05000278/2024005) ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24235A0342024-08-23023 August 2024 U.S. Nuclear Regulatory Commission’S Analysis of Constellation Energy Generation’S Decommissioning Funding Status Report IR 05000277/20240102024-08-23023 August 2024 Fire Protection Team Inspection Report 05000277/2024010 and 05000278/2024010 IR 05000277/20240022024-08-14014 August 2024 Integrated Inspection Report 05000277/2024002 and 05000278/2024002 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24225A1692024-08-12012 August 2024 10 CFR 50.46 Annual Report ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24214A3232024-08-0101 August 2024 Response to Request for Additional Information - Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) ML24191A0612024-07-0606 July 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24177A1512024-06-24024 June 2024 Post Accident Monitoring Instrumentation Report ML24166A1172024-06-20020 June 2024 Regulatory Audit Summary Regarding Proposed Alternative Schedule to Complete Decommissioning Beyond 60 Years RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000277/20243012024-06-13013 June 2024 Initial Operator Licensing Examination Report 05000277/2024301 and 05000278/2024301 RS-24-058, Regarding Subsequent License Renewal Environmental Review2024-06-0505 June 2024 Regarding Subsequent License Renewal Environmental Review ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24150A2722024-05-29029 May 2024 Annual Radiological Environmental Operating Report 81, January 1, 2023 Through December 31, 2023 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000277/20240012024-05-13013 May 2024 Integrated Inspection Report 05000277/2024001 and 05000278/2024001 ML24134A1792024-05-13013 May 2024 Supplemental Information in Support of Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations IR 05000277/20245012024-05-0808 May 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000277/2024501 and 05000278/2024501 ML24121A1832024-04-30030 April 2024 Pre-Submittal Meeting Presentation Material Peach Bottom ECCS Compensated Level System Replacement Project RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24120A2762024-04-23023 April 2024 Independent Spent Fuel Storage Installation (ISFSI) Facility - Annual Radioactive Effluent Release Report 66 January 1, 2023 Through December 31, 2023 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24107A2462024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24102A0472024-04-11011 April 2024 Operator Licensing Examination Approval 05000277/LER-2024-002, Uncoordinated DC Circuits Cause Unanalyzed Condition2024-04-0808 April 2024 Uncoordinated DC Circuits Cause Unanalyzed Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. IR 05000277/20244022024-03-12012 March 2024 Cybersecurity Inspection Report 05000277/2024402 and 05000278/2024402 (Cover Letter Only) ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners ML24060A1192024-02-29029 February 2024 Notification of Conduct of a Fire Protection Team Inspection 2024-09-06
[Table view] Category:Technical Specification
MONTHYEARML24107A2462024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition 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 ML23103A3302023-04-13013 April 2023 Submittal of Changes to 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 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 ML19158A3122019-06-0707 June 2019 License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources - Operating ML19141A1012019-05-21021 May 2019 Summary of Exelon'S Proposal for Implementation of TSTF-500-Technical Specification Changes ML18213A2712018-08-0101 August 2018 Application to Revise Technical Specifications to Adopt TSTF-500, Revision 2, DC Electrical Rewrite Update to TSTF-360, - Supplement 1, Revision of Implementation Dates. ML18172A2832018-06-21021 June 2018 Emergency License Amendment Request - One-Time Change Suspending Emergency Diesel Generator Surveillance Test Completion Requirements ML17030A3022017-01-30030 January 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML16224A3422016-08-11011 August 2016 Response to Request for Additional Information Regarding Proposed License Amendment Concerning Diesel Generator Lube Oil Inventory (TSTF-501-A) for Peach Bottom Atomic Power Station, Units 2 and 3 ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML15357A2502015-12-23023 December 2015 Application to Revise Technical Specifications to Adopt TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities, Revision 0, Using the Consolidated Line Item Improvement Process ML15349A8002015-12-15015 December 2015 License Amendment Request to Reduce Steam Dome Pressure Specified in the Reactor Core Safety Limits ML15337A4132015-12-0303 December 2015 License Amendment Request to Revise Surveillance Requirement 3.8.1.6 Involving EDG Fuel Oil Transfer ML15299A0842015-10-26026 October 2015 PBAPS MELLLA License Amendment Request - Supplement 7 Revision Regarding Proposed Technical Specifications ML15224B5722015-08-12012 August 2015 Submits Supplement to License Amendment Request Proposed Changes to the Technical Specifications to Address Administrative Control of Secondary Containment Access Openings ML15222B1712015-08-10010 August 2015 License Amendment Request to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML15133A5002015-04-14014 April 2015 Technical Specifications Bases ML15133A5032015-04-14014 April 2015 Technical Specifications Bases ML15082A2552015-03-23023 March 2015 Response to Request for Additional Information Regarding Proposed License Amendment to Revise Technical Specifications to Adopt TSTF-523 ML15041A3512015-02-0909 February 2015 Response to Request for Additional Information Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function ML14211A0192014-07-25025 July 2014 License Amendment Request Revise Technical Specifications Definition for Recently Irradiated Fuel ML14171A4092014-06-20020 June 2014 Extended Power Uprate License Amendment Request - Supplement 28 Supplemental Information ML14128A1322014-04-10010 April 2014 License No. DPR-56, Technical Specifications Bases, Page Revision Listing ML14128A1312014-04-10010 April 2014 License No. DPR-44, Technical Specifications Bases, Page Revision Listing ML13121A3792013-04-10010 April 2013 Technical Specifications Bases ML13121A3782013-04-10010 April 2013 Technical Specifications Bases ML12124A0922012-04-12012 April 2012 PBAPS Unit 3 - License No. DPR-56 Technical Specifications Bases ML12124A0912012-04-12012 April 2012 PBAPS Unit 2 - License No. DPR-44 Technical Specifications Bases ML1115401222011-06-0202 June 2011 License Amendment Request - Reactivity Anomalies Surveillance ML11126A3102011-04-15015 April 2011 Unit Unit 3 Technical Specifications Bases, Page B 3.3-66, Through Page B 3.10-36 ML11126A3092011-04-15015 April 2011 Technical Specifications Bases, Cover Page Through Unit 3 Technical Specifications Bases, Page B 3.3-65 ML1109700672011-04-0606 April 2011 License Amendment Request to Revise Operability Requirements and Actions for RCS Leakage Instrumentation ML1025004972010-04-22022 April 2010 Changes to Technical Specifications Bases ML1025004952010-04-22022 April 2010 Changes to Technical Specifications Bases ML1008407522010-03-24024 March 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. ML0924400532009-08-28028 August 2009 License Amendment Request - Type a Test Extension ML0922200452009-07-30030 July 2009 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 Improvement Process ML0912806092009-04-17017 April 2009 Changes to Technical Specifications Bases, Including Changes Through 04/08/2009 ML0912806082009-04-17017 April 2009 Changes to Technical Specifications Bases, Including Changes Through 04/08/2009 ML0824908352008-09-0505 September 2008 Amendment 273 Application of Alternative Source Term Methodology ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0819704612008-07-14014 July 2008 AST Response - Reconciliation of Technical Specifications Page Changes RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I2008-06-0909 June 2008 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item Im ML0813503632008-04-28028 April 2008 Changes to Technical Specifications Bases ML0813503662008-04-28028 April 2008 Changes to Technical Specifications Bases ML0735400492007-12-19019 December 2007 Letter to C. Pardee Correction of Administrative Error in Amendment - the Consistency of TSs to Exelon Generation Company Quality Assurance TR (Tac. MD3937 Thru MD3940 and MD3943 Thru MD3948). - Rplacement Pages 2024-04-15
[Table view] Category:Bases Change
MONTHYEARML24107A2462024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases ML23103A3302023-04-13013 April 2023 Submittal of Changes to Technical Specifications Bases 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 ML19158A3122019-06-0707 June 2019 License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources - Operating ML19141A1012019-05-21021 May 2019 Summary of Exelon'S Proposal for Implementation of TSTF-500-Technical Specification Changes ML18213A2712018-08-0101 August 2018 Application to Revise Technical Specifications to Adopt TSTF-500, Revision 2, DC Electrical Rewrite Update to TSTF-360, - Supplement 1, Revision of Implementation Dates. ML17030A3022017-01-30030 January 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML16224A3422016-08-11011 August 2016 Response to Request for Additional Information Regarding Proposed License Amendment Concerning Diesel Generator Lube Oil Inventory (TSTF-501-A) for Peach Bottom Atomic Power Station, Units 2 and 3 ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML15357A2502015-12-23023 December 2015 Application to Revise Technical Specifications to Adopt TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities, Revision 0, Using the Consolidated Line Item Improvement Process ML15349A8002015-12-15015 December 2015 License Amendment Request to Reduce Steam Dome Pressure Specified in the Reactor Core Safety Limits ML15337A4132015-12-0303 December 2015 License Amendment Request to Revise Surveillance Requirement 3.8.1.6 Involving EDG Fuel Oil Transfer ML15299A0842015-10-26026 October 2015 PBAPS MELLLA License Amendment Request - Supplement 7 Revision Regarding Proposed Technical Specifications ML15133A5002015-04-14014 April 2015 Technical Specifications Bases ML15133A5032015-04-14014 April 2015 Technical Specifications Bases ML14211A0192014-07-25025 July 2014 License Amendment Request Revise Technical Specifications Definition for Recently Irradiated Fuel ML14171A4092014-06-20020 June 2014 Extended Power Uprate License Amendment Request - Supplement 28 Supplemental Information ML14128A1322014-04-10010 April 2014 License No. DPR-56, Technical Specifications Bases, Page Revision Listing ML14128A1312014-04-10010 April 2014 License No. DPR-44, Technical Specifications Bases, Page Revision Listing ML13121A3792013-04-10010 April 2013 Technical Specifications Bases ML13121A3782013-04-10010 April 2013 Technical Specifications Bases ML12124A0922012-04-12012 April 2012 PBAPS Unit 3 - License No. DPR-56 Technical Specifications Bases ML12124A0912012-04-12012 April 2012 PBAPS Unit 2 - License No. DPR-44 Technical Specifications Bases ML1115401222011-06-0202 June 2011 License Amendment Request - Reactivity Anomalies Surveillance ML11126A3102011-04-15015 April 2011 Unit Unit 3 Technical Specifications Bases, Page B 3.3-66, Through Page B 3.10-36 ML11126A3092011-04-15015 April 2011 Technical Specifications Bases, Cover Page Through Unit 3 Technical Specifications Bases, Page B 3.3-65 ML1109700672011-04-0606 April 2011 License Amendment Request to Revise Operability Requirements and Actions for RCS Leakage Instrumentation ML1025004952010-04-22022 April 2010 Changes to Technical Specifications Bases ML1025004972010-04-22022 April 2010 Changes to Technical Specifications Bases ML0912806082009-04-17017 April 2009 Changes to Technical Specifications Bases, Including Changes Through 04/08/2009 ML0912806092009-04-17017 April 2009 Changes to Technical Specifications Bases, Including Changes Through 04/08/2009 ML0813503662008-04-28028 April 2008 Changes to Technical Specifications Bases ML0813503632008-04-28028 April 2008 Changes to Technical Specifications Bases RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program2007-08-0808 August 2007 Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program ML0713602242007-04-27027 April 2007 Technical Specifications Bases - License No DPR-44 ML0713602352007-04-27027 April 2007 Technical Specifications Bases - License No. DPR-56 RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007 Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0612804782006-04-24024 April 2006 PBAPS Unit 3 - Technical Specifications Bases Page Revision Listing ML0612805382006-04-24024 April 2006 PBAPS Unit 2 - Technical Specifications Bases Page Revision Listing ML0514004382005-05-0202 May 2005 Improved Technical Specifications (Unit 3 Bases) ML0514004362005-05-0202 May 2005 Improved Technical Specifications (Unit 2 Bases) ML0504000832005-01-21021 January 2005 Supplement to the Request for License Amendments Related to Application of Alternative Source Term, Dated July 14, 2003 ML0413800892004-04-30030 April 2004 Submittal of Changes to Technical Specifications Gases ML0211902302002-04-19019 April 2002 Part H - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40 ML0211901742002-04-19019 April 2002 Part G - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40 ML0211901312002-04-19019 April 2002 Part F - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40 ML0211901172002-04-19019 April 2002 Part E - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40 ML0211901072002-04-19019 April 2002 Part D - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40 ML0211900622002-04-19019 April 2002 Part C - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40 ML0211900242002-04-19019 April 2002 Part B - Submittal of All Peach Bottom Atomic Power Station Unit 2 & Unit 3 Technical Specifications Bases Changes Through Unit 2 Bases Revision 39 & Unit 3 Bases Revision 40 2024-04-15
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10 CFR 50.4 October 26, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Unit 2 and Unit 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
PBAPS MELLLA+ License Amendment Request - Supplement 7 Revision Regarding Proposed Technical Specifications
Reference:
- 1. Exelon letter to the NRC, "License Amendment Request - Maximum Extended Load Line Limit Analysis Plus," dated September 4, 2014 (ADAMS Accession No. ML14247A503)
In accordance with 10 CFR 50.90, Exelon Generation Company, LLC (EGC) requested amendments to Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3, respectively (Reference 1). Specifically, the proposed changes would revise the Renewed Operating Licenses to allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain and the use of the Detect and Suppress - Confirmation Density (DSS-CD) stability solution.
This letter provides an update to the proposed Technical Specifications (TS) supporting the PBAPS MELLLA+ amendment request (Reference 1). Attachment 1, Page 8, Table 1, of the EGC license amendment request (Reference 1) identifies the proposed deletion of surveillance requirement (SR) 3.3.1.1.8 to calibrate the local power range monitors (LPRM), from TS Table 3.3.1.1-1 "Reactor Protection System Instrumentation," function 2f, Average Power Range Monitors (APRM) - Operating Power Range Monitor (OPRM)
Upscale. A subsequent review of the SRs for the OPRM Upscale function, determined that SR 3.3.1.1.8 should be retained for MELLLA+ at PBAPS Units 2 and 3. Although the LPRM calibration would have been performed within its required periodicity through other APRM functions, the calibration is necessary to ensure the LPRM reading match actual core conditions for the OPRM Upscale function.
U.S. Nuclear Regulatory Commission MELLLA+ License Amendment Request - Supplement 7 October 26, 2015 Page 2 Therefore, the requested deletion of SR 3.3.1.1.8 from the OPRM Upscale function 2f is withdrawn, and the SR will be retained in the Unit 2 and Unit 3 TS following MELLLA+
implementation. Attachment 1 of this letter provides the affected markup Unit 2 and Unit 3 TS Page 3.3-7.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this letter, please call me at (610) 765-5528.
Respectfully, Kevin F. Borton Manager, Power Uprate Licensing Exelon Generation Company, LLC
Attachment:
- 1. Markup of Proposed Unit 2 and Unit 3 Technical Specifications Page 3.3-7 cc: USNRC Region I, Regional Administrator w/attachment USNRC Senior Resident Inspector, PBAPS w/attachment USNRC Project Manager, PBAPS w/attachment R. R. Janati, Commonwealth of Pennsylvania w/attachment S. T. Gray, State of Maryland w/attachment
Attachment 1 Peach Bottom Atomic Power Station Unit 2 and Unit 3 NRC Docket Nos. 50-277 and 50-278 Markup of Proposed Unit 2 and Unit 3 Technical Specifications Page 3.3-7
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 1. Wide Range Neutron Monitors
- a. Period-Short 2 3 G SR 3.3.1.1.1 13 seconds SR 3.3.1.1.5 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 5(a) 3 H SR 3.3.1.1.1 13 seconds SR 3.3.1.1.6 See Insert B for SR 3.3.1.1.12 SR 3.3.1.1.17 Note (g) SR 3.3.1.1.18
- b. Inop 2 3 G SR 3.3.1.1.5 NA SR 3.3.1.1.17 5(a) 3 H SR 3.3.1.1.6 NA SR 3.3.1.1.17
- 2. Average Power Range 0.61W + 67.1%
Monitors
- a. Neutron Flux-High 2 (c) G SR 3.3.1.1.1 15.0% RTP 3
(Setdown) SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12
- b. Simulated Thermal 1 (c) F SR 3.3.1.1.1 3 0.55 W (g)
Power-High SR 3.3.1.1.2 + 63.3% RTP(b) and 118.0%
RTP SR 3.3.1.1.8 SR 3.3.1.1.11 See Insert B for SR 3.3.1.1.12(e),(f)
(c)
- c. Note (h)
Neutron Flux-High 1 3 F SR 3.3.1.1.1 119.7% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12
- d. Inop 1,2 (c) G SR 3.3.1.1.11 NA 3
- e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.11 SR 3.3.1.1.17 18% (h)
SR 3.3.1.1.18
- f. OPRM Upscale 23% (c) I SR 3.3.1.1.1 (d) 3 NA RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.19 (continued)
(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b) 0.55 (W - W) + 61.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
(c) Each APRM channel provides inputs to both trip systems.
Deleted (d) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.
(e) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(f) The instrument channel set point shall be reset to a value that is within the Leave Alone Zone (LAZ) around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided the as-found tolerance and LAZ apply to the actual setpoint implemented in the Surveillance procedures to confirm channel performance. The NTSP methodologies used to determine the as-found tolerance and the LAZ are specified in the Bases associated with the specified function.
PBAPS UNIT 2 3.3-7 Amendment No. 273
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 1. Wide Range Neutron Monitors
- a. Period-Short 2 3 G SR 3.3.1.1.1 13 seconds SR 3.3.1.1.5 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 5(a) 3 H SR 3.3.1.1.1 13 seconds SR 3.3.1.1.6 See Insert B for SR 3.3.1.1.12 SR 3.3.1.1.17 Note (g) SR 3.3.1.1.18
- b. Inop 2 3 G SR 3.3.1.1.5 NA SR 3.3.1.1.17 5(a) 3 H SR 3.3.1.1.6 NA SR 3.3.1.1.17
- 2. Average Power Range 0.61W + 67.1%
Monitors
- a. Neutron Flux-High 2 3(c) G SR 3.3.1.1.1 15.0% RTP (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12
- b. Simulated Thermal 1 3(c) F SR 3.3.1.1.1 0.55 W Power-High SR 3.3.1.1.2 (g)
+ 63.3% RTP(b) and 118.0%
RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 (e),(f)
- c. Neutron Flux-High 1 3(c) F SR 3.3.1.1.1 119.7% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 See Inset B for SR 3.3.1.1.11 Note (h) SR 3.3.1.1.12
- d. Inop 1,2 3(c) G SR 3.3.1.1.11 NA
- e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.11 18%(h) SR 3.3.1.1.17 SR 3.3.1.1.18
- f. OPRM Upscale 23% 3(c) I SR 3.3.1.1.1 (d) NA RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.19 (continued)
(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b) 0.55 (W - W) + 61.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
(c) Each APRM channel provides inputs to both trip systems.
Deleted (d) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.
(e) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(f) The instrument channel set point shall be reset to a value that is within the Leave Alone Zone (LAZ) around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided the as-found tolerance and LAZ apply to the actual setpoint implemented in the Surveillance procedures to confirm channel performance. The NTSP methodologies used to determine the as-found tolerance and the LAZ are specified in the Bases associated with the specified function.
PBAPS UNIT 3 3.3-7 Amendment No. 277
10 CFR 50.4 October 26, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Unit 2 and Unit 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
PBAPS MELLLA+ License Amendment Request - Supplement 7 Revision Regarding Proposed Technical Specifications
Reference:
- 1. Exelon letter to the NRC, "License Amendment Request - Maximum Extended Load Line Limit Analysis Plus," dated September 4, 2014 (ADAMS Accession No. ML14247A503)
In accordance with 10 CFR 50.90, Exelon Generation Company, LLC (EGC) requested amendments to Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3, respectively (Reference 1). Specifically, the proposed changes would revise the Renewed Operating Licenses to allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain and the use of the Detect and Suppress - Confirmation Density (DSS-CD) stability solution.
This letter provides an update to the proposed Technical Specifications (TS) supporting the PBAPS MELLLA+ amendment request (Reference 1). Attachment 1, Page 8, Table 1, of the EGC license amendment request (Reference 1) identifies the proposed deletion of surveillance requirement (SR) 3.3.1.1.8 to calibrate the local power range monitors (LPRM), from TS Table 3.3.1.1-1 "Reactor Protection System Instrumentation," function 2f, Average Power Range Monitors (APRM) - Operating Power Range Monitor (OPRM)
Upscale. A subsequent review of the SRs for the OPRM Upscale function, determined that SR 3.3.1.1.8 should be retained for MELLLA+ at PBAPS Units 2 and 3. Although the LPRM calibration would have been performed within its required periodicity through other APRM functions, the calibration is necessary to ensure the LPRM reading match actual core conditions for the OPRM Upscale function.
U.S. Nuclear Regulatory Commission MELLLA+ License Amendment Request - Supplement 7 October 26, 2015 Page 2 Therefore, the requested deletion of SR 3.3.1.1.8 from the OPRM Upscale function 2f is withdrawn, and the SR will be retained in the Unit 2 and Unit 3 TS following MELLLA+
implementation. Attachment 1 of this letter provides the affected markup Unit 2 and Unit 3 TS Page 3.3-7.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this letter, please call me at (610) 765-5528.
Respectfully, Kevin F. Borton Manager, Power Uprate Licensing Exelon Generation Company, LLC
Attachment:
- 1. Markup of Proposed Unit 2 and Unit 3 Technical Specifications Page 3.3-7 cc: USNRC Region I, Regional Administrator w/attachment USNRC Senior Resident Inspector, PBAPS w/attachment USNRC Project Manager, PBAPS w/attachment R. R. Janati, Commonwealth of Pennsylvania w/attachment S. T. Gray, State of Maryland w/attachment
Attachment 1 Peach Bottom Atomic Power Station Unit 2 and Unit 3 NRC Docket Nos. 50-277 and 50-278 Markup of Proposed Unit 2 and Unit 3 Technical Specifications Page 3.3-7
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 1. Wide Range Neutron Monitors
- a. Period-Short 2 3 G SR 3.3.1.1.1 13 seconds SR 3.3.1.1.5 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 5(a) 3 H SR 3.3.1.1.1 13 seconds SR 3.3.1.1.6 See Insert B for SR 3.3.1.1.12 SR 3.3.1.1.17 Note (g) SR 3.3.1.1.18
- b. Inop 2 3 G SR 3.3.1.1.5 NA SR 3.3.1.1.17 5(a) 3 H SR 3.3.1.1.6 NA SR 3.3.1.1.17
- 2. Average Power Range 0.61W + 67.1%
Monitors
- a. Neutron Flux-High 2 (c) G SR 3.3.1.1.1 15.0% RTP 3
(Setdown) SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12
- b. Simulated Thermal 1 (c) F SR 3.3.1.1.1 3 0.55 W (g)
Power-High SR 3.3.1.1.2 + 63.3% RTP(b) and 118.0%
RTP SR 3.3.1.1.8 SR 3.3.1.1.11 See Insert B for SR 3.3.1.1.12(e),(f)
(c)
- c. Note (h)
Neutron Flux-High 1 3 F SR 3.3.1.1.1 119.7% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12
- d. Inop 1,2 (c) G SR 3.3.1.1.11 NA 3
- e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.11 SR 3.3.1.1.17 18% (h)
SR 3.3.1.1.18
- f. OPRM Upscale 23% (c) I SR 3.3.1.1.1 (d) 3 NA RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.19 (continued)
(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b) 0.55 (W - W) + 61.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
(c) Each APRM channel provides inputs to both trip systems.
Deleted (d) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.
(e) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(f) The instrument channel set point shall be reset to a value that is within the Leave Alone Zone (LAZ) around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided the as-found tolerance and LAZ apply to the actual setpoint implemented in the Surveillance procedures to confirm channel performance. The NTSP methodologies used to determine the as-found tolerance and the LAZ are specified in the Bases associated with the specified function.
PBAPS UNIT 2 3.3-7 Amendment No. 273
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 1. Wide Range Neutron Monitors
- a. Period-Short 2 3 G SR 3.3.1.1.1 13 seconds SR 3.3.1.1.5 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 5(a) 3 H SR 3.3.1.1.1 13 seconds SR 3.3.1.1.6 See Insert B for SR 3.3.1.1.12 SR 3.3.1.1.17 Note (g) SR 3.3.1.1.18
- b. Inop 2 3 G SR 3.3.1.1.5 NA SR 3.3.1.1.17 5(a) 3 H SR 3.3.1.1.6 NA SR 3.3.1.1.17
- 2. Average Power Range 0.61W + 67.1%
Monitors
- a. Neutron Flux-High 2 3(c) G SR 3.3.1.1.1 15.0% RTP (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12
- b. Simulated Thermal 1 3(c) F SR 3.3.1.1.1 0.55 W Power-High SR 3.3.1.1.2 (g)
+ 63.3% RTP(b) and 118.0%
RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 (e),(f)
- c. Neutron Flux-High 1 3(c) F SR 3.3.1.1.1 119.7% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 See Inset B for SR 3.3.1.1.11 Note (h) SR 3.3.1.1.12
- d. Inop 1,2 3(c) G SR 3.3.1.1.11 NA
- e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.11 18%(h) SR 3.3.1.1.17 SR 3.3.1.1.18
- f. OPRM Upscale 23% 3(c) I SR 3.3.1.1.1 (d) NA RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.19 (continued)
(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b) 0.55 (W - W) + 61.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
(c) Each APRM channel provides inputs to both trip systems.
Deleted (d) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.
(e) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(f) The instrument channel set point shall be reset to a value that is within the Leave Alone Zone (LAZ) around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided the as-found tolerance and LAZ apply to the actual setpoint implemented in the Surveillance procedures to confirm channel performance. The NTSP methodologies used to determine the as-found tolerance and the LAZ are specified in the Bases associated with the specified function.
PBAPS UNIT 3 3.3-7 Amendment No. 277