Letter Sequence Response to RAI |
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EPID:L-2018-RNW-0012, Avilsbility of Peach Bottom SLR Application and Opportunity to Request a Hearing (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: CLI-22-04, Change Letter to Peach Bottom Subsequent Renewed Licenses March 17 2022 Rev 1, ML18179A457, ML18214A383, ML18282A029, ML19007A282, ML19007A326, ML19029B121, ML19142A369, ML19182A112, ML19205A206, ML19240A300, ML22096A298
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MONTHYEARML18193A6892018-07-10010 July 2018, 31 July 2018 Application for Subsequent Renewed Operating Licenses Project stage: Request ML18191B2802018-08-27027 August 2018 Avilsbility of Peach Bottom SLR Application and Opportunity to Request a Hearing Project stage: Request ML18179A4572018-08-27027 August 2018 FRN Notice of Availabity and Request for Hearing Project stage: Other ML18191B0852018-08-27027 August 2018 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Exelon Generation Company, LLC, Application for Subsequent License. Project stage: Acceptance Review ML18214A3832018-09-0505 September 2018 Subsequent License Renewal Application Online Reference Portal Project stage: Other NRC-2016-0078, Comment (1) of Alan Harris on Behalf of Entergy Louisiana, LLC and Entergy Operations, Inc. on Entergy Operations, Inc; Waterford Steam Electric Station, Unit 32018-10-0303 October 2018 Comment (1) of Alan Harris on Behalf of Entergy Louisiana, LLC and Entergy Operations, Inc. on Entergy Operations, Inc; Waterford Steam Electric Station, Unit 3 Project stage: Request ML18299A2132018-10-0909 October 2018 Comment (3) of Cheryl T. Seager on Behalf of Us Environmental Protection Agency (Epa)On the Draft Environmental Impact Statement (NUREG-1437,Supplement 59) for the License Renewal of Waterford Steam Electric Station Unit 3 ML18282A0292018-10-16016 October 2018 Plan for the In-Office Regulatory Audit Regarding the Subsequent License Renewal Application Review Project stage: Other ML18323A1032018-11-30030 November 2018 NUREG-1437, Suppl. 59, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Waterford Steam Electric Station, Unit 3 - Final Report Project stage: Acceptance Review ML19007A2822018-12-0404 December 2018 Fws to NRC, Peach Bottom Subsequent License Renewal Ipac Trust Resources List of Endangered Species, Migratory Birds, and Wetlands Project stage: Other ML18354B1132018-12-20020 December 2018 Response to NRC Request for Additional Information, Dated November 23, 2018, Regarding the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application, Environmental Requests for Additional Information Project stage: Request ML19007A3352019-01-0707 January 2019 Map of Conowingo Pond Showing Location of Stations in Trawl Zones 405, 406 and 408 - Figures Project stage: Request ML19007A3302019-01-0707 January 2019 Final Report PBAPS Thermal Study Project stage: Request ML19007A3262019-01-0707 January 2019 Response to Request Dated December 7, 2018 for Docketing of Additional Documents to Support Nrc'S Environmental Review of the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Other ML19023A0152019-01-23023 January 2019 Supplement No. 2 - Changes to the Subsequent License Renewal Application Project stage: Supplement ML19042A1312019-02-11011 February 2019 Supplement No. 3 - Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Supplement ML19029B1212019-02-26026 February 2019 and 3 - Report for the Operating Experience Review Audit Regarding the Subsequent License Renewal Application Review Project stage: Other ML19065A0082019-03-0505 March 2019 Response to Nrg Audit Review Information Request - Application for Subsequent Renewed Operating Licenses Section 4.6 Primary Containment Fatigue Analyses Project stage: Request ML19077A2532019-03-18018 March 2019 Supplement No. 4 - Changes to the Subsequent License Renewal Application Project stage: Supplement ML19114A2652019-04-0808 April 2019 Submittal of Revision 27 to Updated Final Safety Analysis Report and Revision 22 to Fire Protection Program and Reference Drawings Project stage: Request ML19108A4272019-04-10010 April 2019 Request for Additional Information for Peach Bottom 2 and 3 Subsequent License Renewal Application - Set 1 Project stage: Request ML19122A2892019-05-0202 May 2019 Response to NRC Requests for Additional Information, Set 1, Dated April 10, 2019 Related to Plant Subsequent License Renewal Application Project stage: Response to RAI ML19253D2922019-05-0707 May 2019 Request for Clarification of Information on Peach Bottom Water Chemistry Program Project stage: Request ML19150A2972019-05-30030 May 2019 Revised Responses to NRC Requests for Additional Information, Fire Water System, Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Response to RAI ML19255F7822019-06-0303 June 2019, 27 September 2019 Public Clarification Calls with Exelon to Discuss Exelon'S Response to NRC Requests for Additional Information on Environmental Fatigue, (RAI) B.2.1.25-1, and Potential License Renewal Aging Management Issues Project stage: Request ML19157A0092019-06-0606 June 2019 Response to NRC Request for Additional Information, Dated May 15, 2019 Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Response to RAI ML19142A3692019-06-0606 June 2019 Revised Report for the Operating Experience Review Audit Regarding the Subsequent License Renewal Application Review Project stage: Other ML19163A2222019-06-12012 June 2019 Revised Response to NRC Request for Additional Information, Buried Pipe, Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Response to RAI ML19163A2212019-06-12012 June 2019 Supplement No. 5 - Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Supplement ML19163A2232019-06-12012 June 2019 Revised Response to NRC Request for Additional Information, Core Shroud Support Fatigue Analysis Reevaluation, Related to the Subsequent License Renewal Application Project stage: Response to RAI 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 Project stage: Other ML19193A0062019-07-12012 July 2019 Supplement No. 7 - Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Supplement ML19205A4332019-07-24024 July 2019 NRC061 - Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants (Final Report), NUREG-2192 (July 2017) Project stage: Approval ML19206A1802019-07-25025 July 2019 Supplement No. 8 - Changes to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Supplement ML19199A1132019-07-31031 July 2019, 1 August 2019 Notice of Availability of Draft Supplement 10, Second Renewal to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Subsequent License Renewal for Peach Bottom Atomic Power Station Units 2 and 3 Project stage: Request ML19210C5712019-07-31031 July 2019 Schedule Revision for the Review of the Peach Bottom Atomic Power Station Units 2 & 3 Subsequent License Renewal Application (EPID Nos. L-2018-RNW-0012/L-2018-RNW-0013) Project stage: Approval ML19210D4532019-07-31031 July 2019 NUREG-1437, Supplement 10, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 10, Second Renewal for Peach Bottom, Units 2 and 3 Project stage: Acceptance Review ML19225B9762019-08-13013 August 2019 Response to NRC Request for Clarification of Information, Dated August 1, 2019 Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application Project stage: Request ML19268B3512019-09-12012 September 2019 Transcript of Peach Bottom Subsequent License Renewal Draft SEIS Public Meeting Held 12 Sep 2019 Project stage: Draft Approval ML19205A2062019-09-24024 September 2019 Summary Report for the In-Office Regulatory Audit Regarding the Subsequent License Renewal Application Review Project stage: Other ML19238A3032019-09-27027 September 2019 Public Clarification Call with Exelon to Discuss Exelon'S Response to NRC Requests for Additional Information on Environmental Fatigue Project stage: RAI ML19240A3002019-09-27027 September 2019 Public Clarification Call with Exelon to Discuss Questions on Their Coatings and Linings of Certain Components Aging Management Program and Their Inspection of Buried and Underground Piping and Tanks Aging Management Program for SLR Project stage: Other ML19246A1452019-09-27027 September 2019 Clarification Call to Discuss Exelon'S Response to NRC Requests for Additional Information (RAI) 3.3.2.1.1-1 Project stage: RAI ML19280B2552019-10-0707 October 2019 SLRA Revision to BWR Vessel Internals Program Enhancement 1 Project stage: Request ML19275E9682019-10-0707 October 2019 Issuance Letter - Safety Evaluation Report Related to the Subsequent License Renewal of Peach Bottom Atomic Power Station, Units 2 and 3 Project stage: Approval ML19280D8202019-10-31031 October 2019 Safety Evaluation Report Related to the Subsequent License Renewal Application of Peach Bottom Atomic Power Station, Units 2 and 3 Project stage: Approval ML20063L3242020-02-28028 February 2020 EPA Comments on NUREG-1437, Supplemental 10, Second Renewal, Final (Peach Bottom Project stage: Request 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 Project stage: Approval ML20010F2852020-03-0505 March 2020 Transmittal Letter - Issuance of Subsequent Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Station Units 2 and 3 Project stage: Approval ML22055A5572022-02-24024 February 2022 Commission Memorandum and Order (CLI-22-04) Project stage: Request 2019-04-08
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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:Response to Request for Additional Information (RAI)
MONTHYEARCCN:23-09, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML22312A3642022-11-0808 November 2022 Response to NRC Inspection Report and Preliminary White Finding ML22145A0852022-05-25025 May 2022 Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel N-16A Nozzle Repair RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting ML21035A0332021-02-0404 February 2021 Response to Request for Additional Information - 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 ML21029A1662021-01-29029 January 2021 Response to Request for Additional Information - 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 RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 ML20224A5302020-08-11011 August 2020 Response to the Order for Implementation of Additional Security Measures and Fingerprinting for Unescorted Access for Wolf Creek Operating Corporation Independent Spent Fuel Storage Installation ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML19276F2812019-10-0303 October 2019 Supplemental Response to Request for Additional Information (RAl-1) License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources-Operating ML19241A4652019-08-29029 August 2019 Response to Request for Additional Information (RAl-1) License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources-Operating ML19225B9762019-08-13013 August 2019 Response to NRC Request for Clarification of Information, Dated August 1, 2019 Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML19206A0562019-07-24024 July 2019 Stations, Units 2 and 3 - Response to Request for Additional Information - License Amendment Request to Revise Technical Specifications 3.8.1, Required Action A.3, for Temporary One-Time Extension of Completion Time ML19163A2232019-06-12012 June 2019 Revised Response to NRC Request for Additional Information, Core Shroud Support Fatigue Analysis Reevaluation, Related to the Subsequent License Renewal Application ML19157A0092019-06-0606 June 2019 Response to NRC Request for Additional Information, Dated May 15, 2019 Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 ML19150A2972019-05-30030 May 2019 Revised Responses to NRC Requests for Additional Information, Fire Water System, Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML19122A2892019-05-0202 May 2019 Response to NRC Requests for Additional Information, Set 1, Dated April 10, 2019 Related to Plant Subsequent License Renewal Application NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants ML19085A3852019-03-26026 March 2019 Response to Second Request for Additional Information - License Amendment Request to Reduce High Pressure Service Water System Design Pressure and Revise Technical Specifications ... ML19065A0082019-03-0505 March 2019 Response to Nrg Audit Review Information Request - Application for Subsequent Renewed Operating Licenses Section 4.6 Primary Containment Fatigue Analyses ML19046A1292019-02-15015 February 2019 Response to RAI - 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 Completion Times ML19028A2802019-01-28028 January 2019 Response to NRC Request for Additional Information, Dated December 13, 2018, Regarding Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Severe Accident Mitigation Alternatives Requests for Additional Information JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 ML19007A3262019-01-0707 January 2019 Response to Request Dated December 7, 2018 for Docketing of Additional Documents to Support Nrc'S Environmental Review of the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML18354B0612018-12-20020 December 2018 Response to NRC Request for Additional Information, Dated November 23, 2018, Regarding the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application, Environmental Requests for Additional Information ML18340A1852018-12-0606 December 2018 Response to Request for Additional Information License Amendment Request - Revise Technical Specifications to Allow Two Safety Relief Valves/Safety Valves to Be Out-of-Service with Increased Reactor Pressure Safety Limit RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements ML18337A2402018-11-28028 November 2018 Response to Request for Additional Information - Relief Requests Associated with the Fifth Inservice Inspection Interval ML18305B2702018-11-0101 November 2018 Response to Request for Additional Information - License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements 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 ... ML18222A3872018-08-10010 August 2018 Response to Request for Additional Information and Supplemental Information - Application to Adopt 1 O CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components ... ML18128A0092018-05-0707 May 2018 Response to Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML17354A3812017-12-20020 December 2017 Supplemental Response Concerning License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 RS-17-149, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2017-12-15015 December 2017 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. 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 ML17223A6262017-08-11011 August 2017 Response to Request for Additional Information Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML17220A2142017-08-0808 August 2017 Measurement Uncertainty Recapture License Amendment Request - Supplement 3 Response to Request for Additional Information ML17195A2852017-07-13013 July 2017 Measurement Uncertainty Recapture License Amendment Request - Supplement 2 Response to Request for Additional Information RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography 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 ML16216A0762016-08-0202 August 2016 Response to Draft Request for Additional Information Regarding the Proposed License Amendment Request Concerning Emergency Diesel Generator Fuel Oil Transfer Surveillance Requirements ML16162A1012016-06-0909 June 2016 Response to Request for Additional Information Regarding Proposed License Amendment Concerning Emergency Diesel Generator Fuel Oil Transfer Surveillance Requirements RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16083A3942016-03-23023 March 2016 Changes to High Pressure Coolant Injection and Reactor Core Isolation Cooling Surveillance Requirements - Supplement 1, Response to Request for Additional Information 2023-11-10
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Text
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10 CFR 50 10 CFR 51 10 CFR 54 May 30, 2019 U.S. Nuclear Regulatory Commission Attention: 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 NRC Docket Nos. 50-277 and 50-278
Subject:
Revised Responses to NRC Requests for Additional Information, Fire Water System, related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application
References:
- 1. Letter from Michael P. Gallagher, Exelon Generation Company LLC, to NRC Document Control Desk, dated July 10, 2018, "Application for Subsequent Renewed Operating Licenses"
- 2. E-mail from Bennett Brady, NRC to Michael P. Gallagher, Exelon Generation Company, LLC, dated April 10, 2019, "Requests for Additional Information for the Safety Review of the Peach Bottom Atomic Power Station, Units 2 and 3 Subsequent License Renewal Application - Set 1"
- 3. Letter from Michael P. Gallagher, Exelon Generation Company LLC, to NRC Document Control Desk, dated May 2, 2019, "Response to NRC Requests for Additional Information, Set 1, dated April 10, 2019 related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application" In Reference 1, Exelon Generation Company, LLC (Exelon) submitted the Subsequent License Renewal Application (SLRA) for the Peach Bottom Atomic Power Station (PBAPS),
Units 2 and 3. In Reference 2, the NRC requested additional information (RAls) to support staff review of the SLRA. In Reference 3, Exelon submitted the responses to the NRC Set 1 RAls.
In a conference call held on May 15, 2019, NRC identified that additional clarifying information was needed to support the Set 1 responses to the following Fire Water System RA ls:
B.2.1.17-2 B.2.1.17-3
May 30, 2019 U.S. Nuclear Regulatory Commission Page 2 This letter provides revised responses to the above RAls to address the additional information discussed on May 15, 2019. The enclosed revised RAI responses supersede the responses to RAls B.2.1.17-2 and B.2.1.17-3 previously submitted in Reference 3.
Enclosure A contains the revised responses to the above Fire Water System requests for additional information.
Enclosure B contains updates to sections of the SLRA (except for the Subsequent License Renewal Commitment List) affected by the revised responses.
Enclosure C provides an update to the Subsequent License Renewal Commitment List (SLRA Appendix A, Section A.5) resulting from these revised responses.
There are no other new or revised regulatory commitments contained in this letter.
If you have any questions, please contact Mr. David J. Distel, Licensing Lead, Peach Bottom Subsequent License Renewal Project, at 610-765-5517.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 301h day of May 2019.
Respectfully submitted, MichaeiP.GattaQ er Vice President - License Renewal and Decommissioning Exelon Generation Company, LLC
Enclosures:
A: Revised Responses to Set 1 Fire Water System Requests for Additional Information B: Subsequent License Renewal Application Updates C. Subsequent License Renewal Commitment List Updates cc: Regional Administrator - NRG Region I NRG Senior Project Manager (Safety Review), NRR-DMLR NRG Project Manager (Environmental Review), NRR-DMLR NRG Project Manager, NRR-DORL- Peach Bottom Atomic Power Station NRG Senior Resident Inspector, Peach Bottom Atomic Power Station R.R. Janati, Pennsylvania Bureau of Radiation Protection D.A. Tancabel, State of Maryland
Enclosure A Revised Responses to Set 1 Fire Water System Requests for Additional Information Peach Bottom Atomic Power Station, Units 2 and 3 Subsequent License Renewal Application (SLRA)
RAI B.2.1.17-2 RAI B.2.1.17-3
May 30, 2019 Enclosure A Page 1 of 5
- 4. GALL-SLR AMP Xl.M27 Fire Water System Regulatory Basis:
1O CFR 54.21 (a)(3) requires an applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the subsequent period of extended operation. One of the findings that the staff must make to issue a renewed license (10 CFR 54.29(a)) is that actions have been identified and have been or will be taken with respect to managing the effects of aging during the subsequent period of extended operation on the functionality of structures and components that have been identified to require review under 1O CFR 54.21, such that there is reasonable assurance that the activities authorized by the renewed license will continue to be conducted in accordance with the current licensing basis. In order to complete its review and enable making a finding under 1O CFR 54.29(a), the staff requires additional information in regard to the matters described below.
RAI B.2.1.17-2
Background:
GALL-SLR AMP Xl.M27, Table Xl.M27-1, recommends that hydrants be flushed in accordance with NFPA-25, "Standard for the Inspection, Testing, and Maintenance of Water-Based Fire Protection Systems," Section 7.3.2, which requires that: (a) "[e]ach hydrant shall be opened fully and water flowed until all foreign material has cleared;" and (b) "[f]low shall be maintained for not less than 1 minute." The Water-Based Fire Protection Systems Handbook, Fourth Edition, Testing Procedure for [NFPA 25 Section] 7.3.2 states, "[o]pen the hydrant fully and allow the flow to continue until all foreign material has cleared, with a minimum flow period of 1 minute." Page 196 of this document clarifies this requirement by stating, "[f]low test until all foreign material has cleared (not less than one minute)." The plant-specific procedures do not include a requirement that the hydrant flush be maintained for a minimum of one minute and the SLRA does not include an enhancement to address this, or an exception to justify the difference.
NFPA-25, Section 7.3.2, also requires that: (a) "[a]fter operation, dry barrel and wall hydrants shall be observed for proper drainage from the barrel" (b) "[f]ull drainage shall take no longer than 60 minute;" and (c) "[w]here soil conditions or other factors are such that the hydrant barrel does not drain within 60 minutes, or where the groundwater level is above that of the hydrant drain, the hydrant drain shall be plugged and the water in the barrel shall be pumped out."
During the audit, the staff's review of plant-specific operating experience revealed that multiple hydrants were found full or a water level was detected within the hydrant. In addition, the plant specific procedure for flushing hydrants states that: (a) the hydrant should be, "drained to a level approximately 3 feet below ground level;" and (b) "[i]f the hydrant is still not drained, or directed by the sign on the fire hydrant, then manually pump it down to 3 feet below the ground."
During the audit, it was conveyed to the staff that: (a) the frost line in the vicinity of Peach Bottom is 20 inches to 30 inches deep; and (b) there are some hydrants located in areas where the water table is higher and they might not remain drained following the flush. Table 7.2.2.4 of the NFPA 25 Handbook states that a barrel which contains water or ice could be indicative of a faulty drain, a leaky hydrant valve, or high groundwater table, The recommended corrective action is to "[r]epair and drain; for high groundwater it could be necessary to plug the drain and
May 30, 2019 Enclosure A Page 2 of 5 pump out the barrel after each use." The SLRA does not include an enhancement to address this, or an exception to justify the difference.
Issue:
The staff has concluded that to be consistent with GALL-SLR Report AMP Xl.M27, a hydrant must be fully open for at least one minute to ensure that an adequate flush was conducted. The staff's position is based on the fact that until the hydrant is fully open, the flow velocity might not be adequate to clear the fire water main of all debris. The SLRA lacks sufficient information to justify this staff-identified difference.
Although the plant-specific procedures require that a hydrant be drained below the frost line, the frost line is based on the soil overcharge. In the case of a hydrant, while soil surrounds the hydrant barrel, the barrel internal temperature could be below freezing for depths greater than the frost line. In addition, as conveyed to the staff during the audit, certain hydrants might refill with water due to the water table height. The SLRA lacks sufficient information to justify: (a) why hydrants are only pumped to 3 feet below the ground; and (b) why the hydrant drain is not plugged and the plant-specific procedures enhanced to state that water in the barrel shall be pumped out where the water table can result in leakage into a hydrant barrel.
Request:
a) State the basis for why an adequate hydrant flush has been conducted when the plant-specific procedures do not include a requirement to fully open the hydrant for at least one minute.
b) Respond to the following: (a) confirm the depth of the frost line; (b) state the basis for why water in the hydrant barrel will not freeze even though it is only pumped down to 3 feet below the ground level; and (c) state why the hydrant drain is not plugged and the plant-specific procedures enhanced to state that water in the barrel shall be pumped out where the water table can result in leakage into a hydrant barrel.
Exelon Response:
- a. The PBAPS fire hydrant inspection and flush test procedure requires hydrant flow until clear assuring mud and debris is flushed from the system; however, the test procedure does not specify a minimum flow duration. Enhancement 15 (Commitment 17) is added to the Fire Water System (B.2.1.17) aging management program to include a minimum flow duration of one (1) minute after the hydrant valve is fully open to assure adequate time is allowed to clear the fire water main of all foreign material.
- b. The PBAPS fire hydrant inspection and flush test procedure is performed annually in the summer months. A review of completed tests since 2004 indicate that some hydrants have been found with standing water. Water found in hydrants is the result of either ground water entering through the normally open drain port, or a leaking hydrant valve that cannot completely drain through the drain port.
After a hydrant has been flushed and given time to drain, the hydrant flush test procedure requires the hydrant to be checked for standing water. If water is found, the test requires the water be pumped down to three (3) feet below the ground surface.
Pumping down to at least three (3) feet ensures the hydrant is drained below the frost line depth of approximately thirty (30) inches.
May 30, 2019 Enclosure A Page 3 of 5 a) A maximum frost line depth between 20" - 30" is identified by the US Department of Commerce Frost Line Penetration data for the PBAPS location.
b) The basis for why the water in a fire hydrant below three (3) feet will not freeze is that the water (ground water) in the fire hydrant is below the frost line. Water in a fire hydrant that is below the established frost line for a geographical area will not freeze because of heat provided from the earth below the frost line. This is recognized and supported by national standards for the installation of fire service mains and their appurtenances including fire hydrants. National Standards such as NFPA 24, Standard for the Installation of Private Fire Service Mains and Their Appurtenances, Section 10.4.2.1, AWWA M17, Fire Hydrants: Installation Field Testing and Maintenance, Chapter 2, pg.7, NFPA 25, Standard for the Inspection, Testing, and Maintenance of Water-Based Fire Protection Systems, Section 3.3.9.1, and the 2018 National Standard Plumbing Code, Section 2.16, require the hydrant main shutoff valve to be installed below the frost line to assure there is no freezing, essentially the same as a buried pipe. There is no additional burial depth specified or required by national standards for hydrants. The hydrant barrel that extends above ground is not considered a factor in determining the hydrant main shutoff valve depth. The valve simply needs to be below the frost line even though there is no disruption in heat loss through the hydrant barrel from the top of the hydrant barrel above ground to the water below the main shutoff valve. Therefore, since heat loss conducted up through the hydrant barrel does not freeze the hydrant water supply below the shutoff valve (provided it is below the frost line), then water in the hydrant barrel above the shutoff valve will not freeze as long as it is also below the frost line.
In addition, a search of plant operating experience for freezing fire hydrants was performed since 2004. No occurrences of freezing fire hydrants at PBAPS were found. The operating experience confirms that the current fire hydrant flush and drain method that assures water in the hydrant is below the frost line is effective.
Therefore, the basis for why water in the hydrant barrel will not freeze even though it is only pumped down to three (3) feet below the ground level is that the frost line is above three (3) feet.
c) A hydrogeological study was performed for PBAPS in 2018 that determined the ground water levels at various locations around the site. The data indicated that ground water levels are below the frost line with margin. The ground water data was used to determine the ground water levels at site fire hydrants. For those fire hydrants that extend below the ground water level, ground water may enter the hydrant barrel through the normally open drain port, but will remain below the frost line and will not freeze. Therefore, plant-specific procedures do not need to be enhanced and a design change to the current hydrant configuration is not necessary.
SLRA Appendix A, Section A.2.1.17, and Appendix B, Section B.2.1.17 are revised as shown in Enclosure B. SLRA Appendix A, Section A.5, Commitment 17 is also revised as shown in Enclosure C.
May 30, 2019 Enclosure A Page 4 of 5 RAI B.2.1.17-3
Background:
SLRA Section 8.2.1.17, Enhancement No. 4 states," [r]evise procedures to improve guidance for external visual inspections of the in-scope sprinkler systems piping and sprinklers at least every two years to inspect for excessive corrosion ... "
NFPA 25 Section 5.2.1.1.2 states that, "[a]ny sprinkler that shows signs of any of the following shall be replaced: (1) leakage; (2) corrosion ..."
During its search of plant-specific operating experience, the staff noted four instances of leaking sprinklers.
GALL-SLR Report AMP Xl.M27, Table Xl.M27-1, footnote 1O states, "[w]here NFPA 25 or this table cite annual testing or inspections, testing and inspections can be conducted on a refueling outage interval if plant-specific OE has shown no loss of intended function of the in-scope SSC due to aging effects being managed for the specific component (e.g., loss of material, flow blockage due to fouling)."
Issue:
a) As recommended by GALL-SLR Report AMP Xl.M27, sprinklers exhibiting "corrosion" versus sprinklers exhibiting "excessive corrosion" are to be replaced. The SLRA does not describe the difference between "significant corrosion" and "corrosion" and as a result, the staff cannot conclude whether the changes described in Enhancement No. 4 will be consistent with GALL-SLR Report AMP Xl.M27.
b) The SLRA lacks sufficient information for the staff to conclude whether the effects of the leakage identified in the plant-specific operating experience could have adversely affected the sprinkler such that its intended function would not have been met.
Request:
a) State the criteria that differentiate between corrosion and significant corrosion and the basis for why using the criterion of significant corrosion will be effective at identifying sprinkler degradation prior to a loss of intended function.
b) State the percentage of wet pipe sprinklers that exhibited leakage in the past 10 years.
State the basis for why the effects of the observed leakage did not result in a loss of intended function of the sprinkler. If the effects could have resulted in a loss of intended function, state the basis for the effectiveness of the proposed sprinkler visual inspections.
Exelon Response:
- a. Enhancement 4 (Commitment 17) will be revised to remove the word "excessive" for consistency with GALL-SLR Report AMP Xl.M27. If corroded sprinklers are identified during the inspection, the condition will be entered into the corrective action program and the sprinklers will be replaced.
- b. The PBAPS power block fire suppression sprinkler systems consist of approximately 1900 total sprinklers. Of the 1900 sprinklers approximately 500 are dry pre-action sprinklers leaving approximately 1400 sprinklers on wet sprinkler systems. A search of
May 30, 2019 Enclosure A Page 5 of 5 plant operating experience identified five (5) sprinklers on wet pipe sprinkler systems, (0.4 percent) that were found leaking since 2004. The leaks were small (i.e. drops per minute) and found by either plant operators or maintenance personnel performing field work activities.
The basis for why the observed leakage was determined to have no effect on the intended function of the sprinkler is there was no sprinkler assembly corrosion identified or noted on the leaking sprinklers. The leaks did not adversely impact the ability of the sprinkler to perform its design function to actuate at a specific temperature and spray water in an intended spray pattern. Therefore, the intended function of the sprinklers and fire systems were maintained. The leaking sprinklers were replaced.
SLRA Appendix A, Section A.2.1.17, and Appendix 8, Section B.2.1.17 are revised as shown in Enclosure B. SLRA Appendix A, Section A.5, Commitment 17 is also revised as shown in Enclosure C.
Enclosure B Peach Bottom Atomic Power Station, Units 2 and 3 Subsequent License Renewal Application Updates Resulting from the Revised Response to the following RAls:
RAI B.2.1.17-1 RAI B.2.1.17-2 RAI B.2.1.17-3 RAI B.2.1.17-4 Notes:
- Updated SLRA Information is provided in the same order as the RAI responses contained in Enclosure A.
- To facilitate understanding, portions of the original SLRA have been repeated in this Enclosure, with revisions indicated. Previously submitted information is shown in normal font. Changes are highlighted with balded italics for inserted text and strikethro1:Jghs for deleted text.
- There are no changes from the May 2, 2019 Set 1 RAI response submittal letter (Reference 3).
May 30, 2019 Enclosure B Page 1 of 3 As a result of the responses to RAls B.2.1.17-1, B.2.1.17-2, B.2.1.17-3, and B.2.1.17-4 provided in Enclosure A of this letter, SLRA Appendix A, Section A.2.1.17 beginning on page A-25 of the SLRA, is revised to modify Enhancements 1.c and 4, and add Enhancements 15 and 16 as shown below:
A.2.1.17 Fire Water System Change to Enhancement 1.c
- 1. Revise flow test procedures to include:
- a. Inspector test flush acceptance criteria for wet pipe sprinkler systems that currently do not include the requirement to record time to flow from the opened test valve.
- b. Acceptance criteria for wet pipe main drain tests. Flowing pressures from test to test will be monitored to determine if there is a 1O percent reduction in full flow pressure when compared to previously performed tests. An issue report shall be generated in the corrective action program to determine the cause and corrective actions.
- c. If flow test acceptance criteria are not met, perform an investigation within the corrective action program that includes review for increased testing and perform at least two successful additional tests. shall be perforFRed Additional tests shall be completed within the interval in which the original test was conducted. If acceptance criteria are not met during follow-up testing, an extent of condition and extent of cause analysis shall be conducted to determine the further extent of tests which includes testing The test shall be perforFRed on the same system, on the other unit.
Change to Enhancement 4
- 4. Revise procedures to improve guidance for external visual inspections of the in scope sprinkler systems piping and sprinklers at least every two years to inspect for exoessi 1e corrosion, loss of material, leaks, and proper sprinkler orientation.
1 Corroded, leaking or damaged sprinklers shall be replaced.
Additional Enhancements 15 and 16
- 15. Revise the fire hydrant inspection and flush test procedure to include a minimum flow duration of one (1) minute after the hydrant valve is fully open to remove all foreign material.
- 16. Revise the underground fire main flow test to utilize the corrective action program to determine an increased test frequency when established test criteria is not met or when significant degraded trends that could adversely affect system intended function are identified. When test results pass the established test criteria, the test frequency may be extended to a five (5) year frequency IA W NFPA 25.
May 30, 2019 Enclosure 8 Page 2 of 3 As a result of the responses to RAls 8.2.1.17-1, 8.2.1.17-2, 8.2.1.17-3, and 8.2.1.17-4 provided in Enclosure A of this letter, SLRA Appendix 8, Section 8.2.1.17 beginning on page 8-102 of the SLRA, is revised to modify Enhancements 1.c and 4 and add Enhancements 15 and 16 as shown below:
B.2.1.17 Fire Water System Change to Enhancement 1.c
- 1. Revise flow test procedures to include:
- a. Inspector test flush acceptance criteria for wet pipe sprinkler systems that currently do not include the requirement to record time to flow from the opened test valve.
- b. Acceptance criteria for wet pipe main drain tests. Flowing pressures from test to test will be monitored to determine if there is a 10 percent reduction in full flow pressure when compared to previously performed tests. An issue report shall be generated in the corrective action program to determine the cause and corrective actions.
- c. If flow test acceptance criteria are not met, perform an investigation within the corrective action program that includes review for increased testing and perform at least two successful additional tests. shall eo performed Additional tests shall be completed within the interval in which the original test was conducted. If acceptance criteria are not met during follow-up testing, an extent of condition and extent of cause analysis shall be conducted to determine the further extent of tests which includes testing Tho test shall 90 porforrnod on the same system, on the other unit.
Program Elements Affected: Parameters Monitored or Inspected (Element 3),
Detection of Aging Effects (Element 4), Acceptance Criteria (Element 6), and Corrective Actions (Element 7)
Change to Enhancement 4
- 4. Revise procedures to improve guidance for external visual inspections of the in scope sprinkler systems piping and sprinklers at least every two years to inspect for oxoossi'lo corrosion, loss of material, leaks, and proper sprinkler orientation.
Corroded, leaking or damaged sprinklers shall be replaced. Program Elements Affected: Parameters Monitored or Inspected (Element 3) and Detection of Aging Effects (Element 4)
May 30, 2019 Enclosure B Page 3 of 3 Additional Enhancements 15 and 16
- 15. Revise the fire hydrant inspection and flush test procedure to include a minimum flow duration of one (1) minute after the hydrant valve is fully open to remove all foreign material. Program Element Affected: Preventative Actions (Element 2), Parameters Monitored or Inspected (Element 3), Detection of Aging Effects (Element 4)
- 16. Revise the underground fire main flow test to utilize the corrective action program to determine an increased test frequency when established test criteria is not met or when significant degraded trends that could adversely affect system intended function are identified. When test results pass the established test criteria, the test frequency may be extended to a five (5) year frequency IA W NFPA 25. Program Elements Affected: Parameters Monitored or Inspected (Element 3), Detection of Aging Effects (Element 4), and Acceptance Criteria (Element 6), Corrective Actions (Element 7)
Enclosure C PBAPS Subsequent License Renewal Commitment List Updates This Enclosure identifies commitments made in this document and is an update to the P8APS SLRA Appendix A, Section A.5 Subsequent License Renewal Commitment List. Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.
Changes to the P8APS SLRA Appendix A, Section A.5 Subsequent License Renewal Commitment List are as a result of the Exelon response to the following revised RAI responses:
RAI 8.2.1.17-1 RAI 8.2.1.17-2 RAI 8.2.1.17-3 RAI 8.2.1.17-4 Note: To facilitate understanding, relevant portions of the previously submitted Subsequent License Renewal Commitment List have been repeated in this Enclosure, with revisions indicated. Previously submitted information is shown in normal font. Changes due to this submittal are highlighted with balded italics for inserted text and strikethroughs for deleted text.
There are no changes from the May 2, 2019 Set 1 RAI response submittal letter (Reference 3) other than the addition of the May 30, 2019 letter in the Source column of the commitment table for Commitment 17, Item 4.
May 30, 2019 Enclosure C Page 1 of 2 As a result of the responses to RAls 8.2.1.17-1, 8.2.1.17-2, 8.2.1.17-3, and 8.2.1.17-4 provided in Enclosure A of this letter, SLRA Appendix A, Section A.5, Commitment 17, beginning on page A-95 of the SLRA, is revised as shown below:
PROGRAM OR IMPLEMENTATION NO. COMMITMENT SOURCE TOPIC SCHEDULE*
17 Fire Water System Fire Water System is an existing program that will be enhanced to: Program will be Section A.2.1. 17
- 1. Revise flow test procedures to include: enhanced no later than six months prior to the
- a. Inspector test flush acceptance criteria for wet pipe sprinkler second period of systems that currently do not include the requirement to record time extended operation.
to flow from the opened test valve.
Inspections that are to be
- b. Acceptance criteria for wet pipe main drain tests. Flowing completed prior to the pressures from test to test will be monitored to determine if there is second period of a 10 percent reduction in full flow pressure when compared to extended operation will previously performed tests. An issue report shall be generated in be completed no later the corrective action program to determine the cause and corrective than six months prior to actions. the second period of Exelon Letter
- c. If flow test acceptance criteria are not met, perform an extended operation, or PBAPSSLRA investigation within the corrective action program that no later than the last RAJ Response, includes review for increased testing and perform at least two refueling outage prior to datedMay2, successful additional tests. shall lle per:fer:mei;j Additional tests the second period of 2019 shall be completed within the interval in which the original test extended operation.
was conducted. If acceptance criteria are not met during follow-up testing, an extent of condition and extent of cause analysis shall be conducted to determine the further extent of tests which includes testing The test shall lle perferFRei;j on the same system, on the other unit.
- 4. Revise procedures to improve guidance for external visual inspections of Exelon Letter the in scope sprinkler systems piping and sprinklers at least every two years to inspect for exsessi>.1e corrosion, loss of material, leaks, and proper sprinkler PBAPSSLRA orientation. Corroded, leaking or damaged sprinklers shall be replaced. RA/ Response, dated May 30, 2019
May 30, 2019 Enclosure C Page 2 of 2 PROGRAM OR IMPLEMENTATION NO. COMMITMENT SOURCE TOPIC SCHEDULE*
- 15. Revise the fire hydrant inspection and flush test procedure to include Exelon Letter a minimum flow duration of one (1) minute after the hydrant valve is fully open to remove all foreign material. PBAPSSLRA RA/ Response, datedMay2,
- 16. Revise the underground fire main flow test to utilize the corrective 2019 action program to determine an increased test frequency when established test criteria is not met or when significant degraded trends that could adversely affect system intended function are identified. When test results pass the established test criteria, the test frequency may be extended to a five (5) year frequency IA W NFPA25.