Letter Sequence Supplement |
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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
[Table View] |
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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:Technical Specification
MONTHYEARRS-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 ML15133A5032015-04-14014 April 2015 Technical Specifications Bases ML15133A5002015-04-14014 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 ML13121A3782013-04-10010 April 2013 Technical Specifications Bases ML13121A3792013-04-10010 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 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 ML0719701642007-07-12012 July 2007 Tech Spec Pages for Amendment 265 Risk-Informed Modification to Selected Required End States 2023-05-25
[Table view] Category:Bases Change
MONTHYEARML23103A3302023-04-13013 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 ML13121A3782013-04-10010 April 2013 Technical Specifications Bases ML13121A3792013-04-10010 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 ML11126A3092011-04-15015 April 2011 Technical Specifications Bases, Cover Page Through Unit 3 Technical Specifications Bases, Page B 3.3-65 ML11126A3102011-04-15015 April 2011 Unit Unit 3 Technical Specifications Bases, Page B 3.3-66, Through Page B 3.10-36 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 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 ML0713602352007-04-27027 April 2007 Technical Specifications Bases - License No. DPR-56 ML0713602242007-04-27027 April 2007 Technical Specifications Bases - License No DPR-44 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 ML0211900092002-04-19019 April 2002 Part a - 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 2023-04-13
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Text
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