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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities 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 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments 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 ML21119A1412021-04-29029 April 2021 License Amendment Request, Revise Technical Specifications Administrative Controls Section 5.5.7 Regarding the Frequency for Performing Certain Ventilation Filter Testing RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-21-016, Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2021-01-29029 January 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML20337A3012020-12-0202 December 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML20150A0072020-05-29029 May 2020 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process ML20024G4292020-03-0404 March 2020 Record of Decision - Issuance of Subsequent Renewed Facility Operation License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3 RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions ML19193A0062019-07-12012 July 2019 Supplement No. 7 - Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML19182A1122019-07-0101 July 2019 First 10 CFR 54.21 (B) Annual Amendment to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19158A3122019-06-0707 June 2019 License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources - Operating ML19116A1962019-04-26026 April 2019 License Amendment Request to Revise Technical Specifications 3.8.1, Required Action A.3, for Temporary One-Time Extension of Completion Time ML19042A1312019-02-11011 February 2019 Supplement No. 3 - Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. ML19023A0152019-01-23023 January 2019 Supplement No. 2 - Changes to the Subsequent License Renewal Application ML18305B2702018-11-0101 November 2018 Response to Request for Additional Information - License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements ML18275A0232018-09-28028 September 2018 License Amendment Request to Reduce High Pressure Service Water System Design Pressure and Revise Technical Specifications 3.6.2.3, 3.6.2.4, 3.6.2.5, and 3.7.1 for Temporary Extension of ... ML18271A0092018-09-27027 September 2018 License Amendment Request -Technical Specifications Section 3.3.6.2 Functions 3 and 4 Applicability Changes Pertaining to Reactor Building and Refueling Floor Ventilation ML18257A1432018-09-14014 September 2018 Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML18239A3552018-08-27027 August 2018 License Amendment Request - Expanded Actions for LEFM Conditions 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. ML18193A6972018-07-10010 July 2018 Cover Letter Submitting Subsequent License Renewal Application ML18193A6992018-07-10010 July 2018 Cover Letter Submitting Paper Copies, Cds and Boundary Drawings Accompany Submittal of Subsequent License Renewal Application 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 ML18149A2992018-05-10010 May 2018 Enclosure 2 - Peach Bottom Staffing LAR - Evaluation of Proposed Changes and Attachments 2A & 2B, Emergency Plan Marked-Up Pages and Emergency Plan Clean Copy Pages ML18149A3022018-05-10010 May 2018 Enclosure 4 - Summary of Regulatory Commitments RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML17275A0692017-09-29029 September 2017 Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite-Update to TSTF-360. ML17258A1792017-09-15015 September 2017 Submittal of Measurement Uncertainty Recapture Power Uprate License Amendment Request - Supplement 5, Supplemental Reload Licensing Report ML17243A0142017-08-30030 August 2017 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. ML17241A1942017-08-29029 August 2017 License Amendment Request - Revise Technical Specifications Section 3.4.3 (Srvs/Svs) for the Remainder of the Current Operating Cycle for Unit 2 - Supplement 1 Response to Request for Additional Information ML17139D3572017-05-19019 May 2017 License Amendment Request Revise Technical Specifications Section 3.4.3 for the Remainder of the Current Operating Cycle RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process ML17080A0672017-03-20020 March 2017 Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate - Supplement 1 - Request for Non-Proprietary Version of Cameron Corporation Proprietary Documents ML17048A4442017-02-17017 February 2017 Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate ML16342C4552016-12-0707 December 2016 Supplement to License Amendment Request, Revise Turbine Condenser - Low Vacuum Scram Instrumentation Function Allowable Value ML16309A2982016-11-0404 November 2016 Request for License Amendment to Revise Turbine Condenser - Low Vacuum Scram Instrumentation Function Allowable Value ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. 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. ML16173A3712016-06-20020 June 2016 Application to Revise Technical Specifications to Adopt TSTF-501-A, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control, Revision 1, Using the Consolidated Line Item Improvement Process ML16132A4402016-05-11011 May 2016 Supplement to License Amendment Request, Revise Surveillance Requirement 3.5.1.5 Involving Recirculation Pump Discharge Valves 2023-09-08
[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
Exelon Nuclear 200 Erelon Way www exeloncorp corn Nuclear Kennett Square, PA 19348 10 CFR 50.90 September 15, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Docket Nos. 50-277 and 50-278
Subject:
License Amendment Request Revise Control Rod Scram Time Testing Frequency Consolidated Line ltem lmprovement Process (TSTF-460)
Pursuant to 10 CFR 50.90 Exelon Generation Company, LLC, (Exelon) hereby requests the following amendments to the Technical Specifications (TS), Appendix A, of Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3.
The proposed amendments would revise the TS testing frequency for the Surveillance Requirement (SR) in TS 3.1.4, "Control Rod Scram Times," from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1." These changes are based on TS Task Force (TSTF) change traveler TSTF-460, Revision 0, which has been approved generically for the Boiling Water Reactor (BWR) Standard TS, NUREG-1433 (BWW4). A notice announcing the availability of this proposed TS change using the Consolidated Line ltem lmprovement Process was published in the Federal Register on August 23,2004 (69 FR 51864).
The NRC has previously approved similar amendment requests to the TS for Browns Ferry Nuclear Plant, Units 2 and 3, Fermi 2, Brunswick Steam Electric Plant, Units 1 and 2, Columbia Generating Station, and Cooper Nuclear Station. The subject License Amendment Request proposes to adopt surveillance testing requirements similar to those discussed in the previously approved amendments.
Exelon requests approval of the proposed amendments by September 30, 2007, with the amendments being implemented within 60 days upon issuance. The requested approval date and implementation period will allow sufficient time for effective planning and scheduling of affected activities associated with scram time testing.
These proposed changes have been reviewed by the Plant Operations Review Committee, and approved by the Nuclear Safety Review Board.
U.S. Nuclear Regulatory Commission September 15,2006 Page 2 Pursuant to 10 CFR 50.91(b)(l), a copy of this License Amendment Request is being provided to the designated official of the Commonwealth of Pennsylvania.
If any additional information is needed, please contact Mr. Richard Gropp at 610-765-5557.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 15'h day of September 2006.
Respectfully,
-6 I
Pamela B. cowan Director, Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1 - Description of Proposed Changes 2- Markup of Proposed Technical Specifications Pages 3- Markup of Proposed Technical Specifications Bases Pages 4- List of Commitments cc: S. J. Collins, Administrator, Region I, USNRC F. L. Bower, USNRC Senior Resident Inspector, PBAPS J. S. Kim, Project Manager, USNRC R. R. Janati, Commonwealth of Pennsylvania
ATTACHMENT 1 Description of Proposed Changes PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Reduce Scram Time Testing Frequency
1.0 DESCRIPTION
2.0 ASSESSMENT
3.0 TECHNICAL ANALYSIS
4.0 REGULATORY ANALYSIS
4.1 No Significant Hazards Consideration Determination 4.2 Commitments 4.3 Precedence 5.0 ENVIRONMENTAL EVALUATION
6.0 REFERENCES
ATTACHMENT 1 Description of Proposed Changes
1.0 DESCRIPTION
The proposed license amendments revise the required testing frequency for Surveillance Requirement 3.1.4.2 in Technical Specification 3.1.4, "Control Rod Scram Times." A notice announcing the availability of this proposed Technical Specifications (TS) change using the Consolidated Line Item Improvement Process (CLIIP) was published in the Federal Register on August 23, 2004 (69 FR 51864).
2.0 ASSESSMENT These proposed TS changes are based on TS Task Force (TSTF) change traveler TSTF-460, Revision 0, which has been approved generically for the Boiling Water Reactor (BWR) Standard TS, NUREG-1433 (BWR/4). The required frequency, for control rod scram time testing as described in Surveillance Requirement (SR) 3.1.4.2, will be changed from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1."
The applicable regulatory requirements and guidance associated with this License Amendment Request are adequately addressed by the CLIIP Notice of Availability published on August 23, 2004 (69 FR 51864) and TSTF-460.
3.0 TECHNICAL ANALYSIS
Exelon Generation Company, LLC (Exelon) has reviewed the safety evaluation published on August 23, 2004 (69 FR 51864) as part of the CLIIP Notice of Availability.
This verification included a review of the NRC staff's safety evaluation and the supporting information provided to support TSTF-460. Exelon has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, and justify this amendment for the incorporation of the changes to the PBAPS, Units 2 and 3, TS. Exelon is not proposing variations or deviations from the TS changes described in TSTF-460 or in the content of the NRC staff's model safety evaluation published on August 23, 2004 (69 FR 51864).
As described in the CLIIP model safety evaluation, part of the justification for the change in surveillance frequency is the high reliability of the PBAPS, Units 2 and 3, Control Rod Drive System. As requested in the CLIIP Notice of Availability published on August 23, 2004 (69 FR 51864), the historical performance of the Control Rod Drive System (CRD) at PBAPS, Units 2 and 3, is described below.
PBAPS, Unit 2 Test Results PBAPS, Unit 2, has 185 control rods. Historical CRD scram time test results were reviewed for the period January 2000 through January of 2006. There were approximately 2,842 individual rod scram timing data points identified for the period. Of these, there were 14 rods that tested slow to position 46. No rods were slow to positions other than 46. Analysis of the documentation has shown that one of these slow control rods contained Buna-N Scram Solenoid Pilot Valve (SSPV) diaphragm material. All other rods identified as slow during this period contained Viton-A SSPV diaphragm material.
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ATTACHMENT 1 Description of Proposed Changes PBAPS, Unit 3 Test Results PBAPS, Unit 3, has 185 control rods. Historical CRD scram time test results were reviewed for the period January 2000 through January of 2006. There were approximately 1,428 individual rod scram timing data points identified for the period. Of these, there were 4 rods that tested slow to position 46. No rods were slow to positions other than 46. Analysis of the documentation has shown that all control rods identified as slow during this period contained Viton-A SSPV diaphragm material.
Discussion Significant operating experiences from multiple BWRs in the mid-1990s identified performance issues with the Buna-N diaphragm material originally installed in Automatic Switch Company (ASCO) "dual-type" SSPVs. Specifically, the Buna-N diaphragms experienced hardening under in-service conditions, resulting in increased times to valve actuation and start of motion following a scram initiation signal. Based on General Electric (GE) Services Information Letter (SIL) 584, Scram Solenoid Pilot Valve Diaphragm Embrittlement, PBAPS instituted a program to replace Buna-N diaphragms with Viton-A diaphragms, which were demonstrated to be less susceptible to the hardening phenomenon. Shortly after its introduction, the industry identified Viton-A diaphragm performance issues that also resulted in delayed SSPV actuation. In the case of the Viton-A diaphragms, the material would occasionally adhere to the SSPV body following extended operation of the valve in the closed position, again resulting in a delayed actuation of the valve and start of rod motion. At the recommendation of GE, PBAPS subsequently established a program to replace all remaining Buna-N and Viton-A diaphragms with Viton-515AB diaphragms. The Viton-515AB formulation, also referred to as Viton-B, has been demonstrated to be resistant to both the hardening and adhesion issues associated with Buna-N and Viton-A diaphragm materials. All Buna-N diaphragms have now been replaced with Viton-515AB material on both PBAPS units.
PBAPS is in the process of replacing all Viton-A diaphragms with Viton-515AB diaphragm material during Hydraulic Control Unit (HCU) corrective and scheduled preventative maintenance activities.
Summary Control rod insertion time test data from a 6-year period has demonstrated the high reliability of the PBAPS, Units 2 and 3, CRD systems. The combined 0.42% incidence of slow rods for both units at PBAPS is exclusively attributable to well understood SSPV diaphragm material issues which are being addressed by the systematic replacement of Viton-A diaphragms with Viton-515AB material. The high reliability of the CRD system and ongoing SSPV diaphragm replacement program, in conjunction with the more restrictive slow rod acceptance criteria of 7.5%, support extension of the SR 3.1.4.2 surveillance frequency from 120 days of cumulative operation in Mode 1 to 200 days of cumulative operation in MODE 1.
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ATTACHMENT 1 Description of Proposed Changes
4.0 REGULATORY ANALYSIS
4.1 NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Exelon has reviewed the proposed No Significant Hazards Consideration Determination published on August 23, 2004 (69 FR 51864), as part of the CLIIP. Exelon has concluded that the proposed determination presented in the notice is applicable to PBAPS, Units 2 and 3, and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
4.2 COMMITMENTS As discussed in the CLIIP model safety evaluation published in the Federal Register on August 23, 2004 (69 FR 51864) for this TS improvement, Exelon is making the following regulatory commitment with the understanding that the NRC will include it as a condition for the issuance of the requested amendments:
Exelon will incorporate the revised acceptance criterion value of 7.5 percent into the TS Bases for PBAPS, Units 2 and 3, in accordance with the Bases Control Program described in TS 5.5.10.
Exelon will make the supporting changes to the TS Bases in accordance with TS 5.5.10, "Technical Specification (TS) Bases Control Program." Attachment 3 of this letter contains markup TS Bases pages for PBAPS, Units 2 and 3. These pages are being submitted for information only and do not require issuance by the NRC.
4.3 PRECEDENCE This application is being made in accordance with the CLIIP. Exelon is not proposing variations or deviations from the TS changes described in TSTF-460 or in the content of the NRC staff's model safety evaluation published on August 23, 2004 (69 FR 51864).
The NRC has previously approved similar amendment requests to the TS for Browns Ferry Nuclear Plant, Units 2 and 3, Brunswick Steam Electric Plant, Units 1 and 2, Columbia Generating Station, Cooper Nuclear Station, and Fermi 2. The subject License Amendment Request proposes to adopt surveillance testing requirements similar to those discussed in the previously approved amendments.
5.0 ENVIRONMENTAL EVALUATION Exelon has reviewed the Environmental Evaluation included in the model safety evaluation published on August 23, 2004 (69 FR 51864) as part of the CLIIP. Exelon has concluded that the staff's findings presented in that evaluation are applicable to PBAPS, Units 2 and 3, and the evaluation is hereby incorporated by reference for this application.
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ATTACHMENT 1 Description of Proposed Changes
6.0 REFERENCES
Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specifications Improvement Regarding Revision to the Control Rod Scram Time Testing Frequency in STS 3.1.4, "Control Rod Scram Times," for General Electric Boiling Water Reactors Using the Consolidated Line Item Improvement Process, published August 23, 2004 (69 FR 51864).
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ATTACHMENT 2 PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Reduce Control Rod Scram Time Testing Frequency Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES Unit 2 Unit 3 3.1-13 3.1-13
Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 200 SR 3.1.4.2 Verify, for a representative sample, each 120 days tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam operation in dome pressure 800 psig. MODE 1 SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor steam dome pressure. control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure 800 psig. 40% RTP after work on control rod or CRD System that could affect scram time AND Prior to exceeding 40%
RTP after fuel movement within the affected core cell PBAPS UNIT 2 3.1-13 Amendment No. 259 XXX
Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 200 SR 3.1.4.2 Verify, for a representative sample, each 120 days tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam operation in dome pressure 800 psig. MODE 1 SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor steam dome pressure. control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure 800 psig. 40% RTP after work on control rod or CRD System that could affect scram time AND Prior to exceeding 40%
RTP after fuel movement within the affected core cell PBAPS UNIT 3 3.1-13 Amendment No. 262 XXX
ATTACHMENT 3 PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Reduce Control Rod Scram Time Testing Frequency Markup of Proposed Technical Specifications Bases Page Changes REVISED TS BASES PAGES Unit 2 Unit 3 B 3.1-26 B 3.1-26
Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE SR 3.1.4.2 (continued) 7.5%
REQUIREMENTS if no more than 20% of the control rods in the sample tested are determined to be "slow". With more than 20% of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 20% criterion (i.e., 20% of the active sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all Surveillances) exceeds the 7.5%
LCO limit. For planned testing, the control rods selected for the sample should be different for each test. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power, even if the control rods with 200 data may have been previously tested in a sample. The 120 day Frequency is based on operating experience that has shown control rod scram times do not significantly change over an operating cycle. This Frequency is also reasonable based on the additional Surveillances done on the CRDs at more frequent intervals in accordance with LCO 3.1.3 and LCO 3.1.5, "Control Rod Scram Accumulators."
SR 3.1.4.3 When work that could affect the scram insertion time is performed on a control rod or the CRD System, testing must be done to demonstrate that each affected control rod retains adequate scram performance over the range of applicable reactor pressures from zero to the maximum permissible pressure. This surveillance can be met by performance of either scram time testing or Diaphragm Alternative Response Time (DART) testing, when it is concluded that DART testing monitors the performance of all affected components. The testing must be performed once before declaring the control rod OPERABLE. The required testing must demonstrate the affected control rod is still within acceptable limits. The limits for reactor pressures
< 800 psig are established based on a high probability of meeting the acceptance criteria at reactor pressures 800 psig. Limits for 800 psig are found in Table 3.1.4-1. If testing demonstrates the affected control rod does not meet these limits, but is within the 7 second limit of Table 3.1.4-1, Note 2, the control rod can be declared OPERABLE and "slow."
(continued)
PBAPS UNIT 2 B 3.1-26 Revision No. 9 XX
Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE SR 3.1.4.2 (continued) 7.5%
REQUIREMENTS if no more than 20% of the control rods in the sample tested are determined to be "slow". With more than 20% of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 20% criterion (i.e., 20% of the active sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all Surveillances) exceeds the 7.5%
LCO limit. For planned testing, the control rods selected for the sample should be different for each test. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power, even if the control rods with data may have been previously tested in a sample. The 200 120 day Frequency is based on operating experience that has shown control rod scram times do not significantly change over an operating cycle. This Frequency is also reasonable based on the additional Surveillances done on the CRDs at more frequent intervals in accordance with LCO 3.1.3 and LCO 3.1.5, "Control Rod Scram Accumulators."
SR 3.1.4.3 When work that could affect the scram insertion time is performed on a control rod or the CRD System, testing must be done to demonstrate that each affected control rod retains adequate scram performance over the range of applicable reactor pressures from zero to the maximum permissible pressure. This surveillance can be met by performance of either scram time testing or Diaphragm Alternative Response Time (DART) testing, when it is concluded that DART testing monitors the performance of all affected components. The testing must be performed once before declaring the control rod OPERABLE. The required testing must demonstrate the affected control rod is still within acceptable limits. The limits for reactor pressures
< 800 psig are established based on a high probability of meeting the acceptance criteria at reactor pressures 800 psig. Limits for 800 psig are found in Table 3.1.4-1. If testing demonstrates the affected control rod does not meet these limits, but is within the 7 second limit of Table 3.1.4-1, Note 2, the control rod can be declared OPERABLE and "slow."
(continued)
PBAPS UNIT 3 B 3.1-26 Revision No. 9 XX
ATTACHMENT 4 PBAPS, Units 2 and 3 Renewed Facility Operating License Nos. DRP-44 and DPR-56 Reduce Control Rod Scram Time Testing Frequency List of Commitments
ATTACHMENT 4 LIST OF COMMITMENTS The following table identifies those actions committed to by Exelon Generation Company (Exelon), LLC, in this document. Any other statements in this submittal are provided for information purposes and are not considered to be commitments.
COMMITTED COMMITMENT TYPE COMMITMENT DATE OR ONE-TIME ACTION PROGRAMMATIC OUTAGE (Yes/No) (Yes/No)
Exelon will incorporate the revised Upon No Yes acceptance criterion value of 7.5 implementation of percent into the TS Bases for PBAPS, the Approved Units 2 and 3, in accordance with the License Bases Control Program described in Amendment TS 5.5.10.