Letter Sequence Response to RAI |
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EPID:L-2018-LLA-0265, 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 ... (Approved, Closed) |
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MONTHYEARML18275A0232018-09-28028 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 ... Project stage: Request ML18295A2602018-10-22022 October 2018 Acceptance Review for Peach Bottom - License Amendment Request for TS Changes Related to HPSW System Project stage: Acceptance Review ML19017A0472019-01-16016 January 2019 Request for Additional Information - High Pressure Service Water One Time TS Change Project stage: RAI 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 Project stage: Response to RAI ML19058A2902019-02-27027 February 2019 Request for Additional Information - High Pressure Service Water One Time TS Change Project stage: RAI 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 ... Project stage: Request ML19232A1752019-08-20020 August 2019 Request for Additional Information - TSTF-500 Implementation LAR Project stage: RAI 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 Project stage: Approval 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 Project stage: Response to RAI 2019-02-27
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Category:Letter
MONTHYEARIR 05000277/20244012024-10-17017 October 2024 Security Baseline Inspection Report 05000277/2024401 and 05000278/2024401 (Cover Letter Only) RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24281A1012024-10-0707 October 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24221A2582024-09-0606 September 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Peach Bottom Atomic Power Station, Units 2 and 3 05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum2024-09-0505 September 2024 Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum IR 05000277/20240022024-09-0404 September 2024 Reissued Integrated Inspection Report 05000277/2024002 and 05000278/2024002 IR 05000277/20240052024-08-29029 August 2024 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2024005 and 05000278/2024005) IR 05000277/20240102024-08-23023 August 2024 Fire Protection Team Inspection Report 05000277/2024010 and 05000278/2024010 ML24235A0342024-08-23023 August 2024 U.S. Nuclear Regulatory Commission’S Analysis of Constellation Energy Generation’S Decommissioning Funding Status Report ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - 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Report 47 ML24120A2762024-04-23023 April 2024 Independent Spent Fuel Storage Installation (ISFSI) Facility - Annual Radioactive Effluent Release Report 66 January 1, 2023 Through December 31, 2023 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24107A2462024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24102A0472024-04-11011 April 2024 Operator Licensing Examination Approval 05000277/LER-2024-002, Uncoordinated DC Circuits Cause Unanalyzed Condition2024-04-0808 April 2024 Uncoordinated DC Circuits Cause Unanalyzed Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. 05000277/LER-2024-001, Submittal of LER 2024-001-00 for Peach Bottom Atomic Power Station (PBAPS) Unit 2, Automatic Reactor Scram Due to an Invalid Generator Lockout2024-03-21021 March 2024 Submittal of LER 2024-001-00 for Peach Bottom Atomic Power Station (PBAPS) Unit 2, Automatic Reactor Scram Due to an Invalid Generator Lockout IR 05000277/20244022024-03-12012 March 2024 Cybersecurity Inspection Report 05000277/2024402 and 05000278/2024402 (Cover Letter Only) 2024-09-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24214A3232024-08-0101 August 2024 Response to Request for Additional Information - Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24134A1792024-05-13013 May 2024 Supplemental Information in Support of Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations CCN: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 2024-08-09
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200 Exelon Way Exelon Generation ~ Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90 August 29, 2019 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 NRC Docket Nos. 50-277 and 50-278
Subject:
Response to Request for Additional Information (RAl-1)
License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources-Operating
References:
- 1. Exelon Letter to the NRC, "License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources-Operating,"
dated June 7, 2019 (ADAMS Accession No. ML19158A312)
- 2. NRC Email to Exelon, "Peach Bottom Units 2 and 3 - Request for Additional Information - TSTF-500 Implementation LAR (EPID L-2018-LLA-0265)," dated August 20, 2019 (ADAMS Accession No. ML19232A175)
In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (Exelon) proposed a change 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 (Reference 1). The proposed change would revise TS 3.8.4, "DC Sources - Operating," to add a Condition for the opposite Unit consistent with Technical Specifications Task Force (TSTF)-500, Revision 2, "DC [direct current] Electrical Rewrite - Update to TSTF-360," as approved by the Nuclear Regulatory Commission (NRC). Specifically, the proposed Condition would allow a 72-hour Completion Time for an opposite Unit battery charger that is required for particular plant configurations.
During their technical review of the application, the NRC staff identified the need for additional information (Reference 2).
U.S. Nuclear Regulatory Commission Response to Request for Additional Information LAR to Revise TS 3.8.4, DC Sources-Operating Docket Nos. 50-277 and 50-278 August 29, 2019 Page 2 The Attachment to this letter provides a restatement of the question cited in Reference 2 followed by Exelon's response.
Exelon has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC in Attachment 1 of the Reference 1 letter. Exelon has concluded that the information provided in this response does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92. In addition, Exelon has concluded that the information in this response does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no regulatory commitments contained in this response.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), Exelon is notifying the Commonwealth of Pennsylvania of this response by transmitting a copy of this letter to the designated State Official.
Should you have any questions concerning this response, please contact Mr. Frank J. Mascitelli at (610) 765-5512.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of August 2019.
Respectfully, David P. Helker Sr. Manager, Licensing Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information (RAl-1 },
License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources-Operating cc: Regional Administrator - NRC Region I w/ attachments II NRC Senior Resident Inspector- PBAPS II NRC Project Manager, NRR - PBAPS II R. R. Janati, Pennsylvania Bureau of Radiation Protection II D. A Tancabel , State of Maryland
ATTACHMENT License Amendment Request Peach Bottom Atomic Power Station, Units 2 and 3 Docket Nos. 50-277 and 50-278 Response to Request for Additional Information (RAl-1)
License Amendment Request to Revise Technical Specifications 3.8.4, DC Sources-Operating
Attachment Response to Request for Additional Information LAR to Revise TS 3.8.4, DC Sources-Operating Docket Nos. 50-277 and 50-278 Page 1 of 3 Response to NRC Staff's Request for Additional Information By application dated June 7, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19158A312), Exelon Generation Company, LLC (Exelon) requested an amendment to the Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The license amendment request (LAR) would revise the Technical Specifications (TS) 3.8.4, "DC Sources - Operating," to add a Condition for the opposite Unit consistent with Technical Specifications Task Force (TSTF)-500, Revision 2, "DC [direct current] Electrical Rewrite -
Update to TSTF-360," (ADAMS Accession No. ML092670242) as approved by the Nuclear Regulatory Commission (NRC).
Specifically, the proposed Condition would allow a 72-hour Completion Time (CT) for an opposite Unit battery charger that is required for particular plant configurations. Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), Section 36, "Technical Specifications," requires, in part, that the operating license of a nuclear production facility include TS. 10 CFR 50.36 (c)(2) requires that the TS include limiting conditions for operation (LCOs) which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TS until the condition can be met.
Below is a restatement of the question cited in Reference 2 of the cover letter followed by Exelon's response.
RAI -1 Question The licensee proposed a new TS 3.8.4 Condition B with associated Required Actions and Completion Times (CT) for the required opposite unit battery charger. The licensee stated that the word "required" denotes that only specific batteries from the opposite unit are required to support operation of the unit for particular plant configurations.
The proposed new Unit 2 TS 3.8.4 Condition B with associated Required Actions and CT would state:
Attachment Response to Request for Additional Information LAR to Revise TS 3.8.4, DC Sources-Operating Docket Nos. 50-277 and 50-278 Page 2 of 3
'I Resto'"'e ,_nit 3 patt~
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~ OPERAB: [ ru:.1<. I The proposed new Unit 3 TS 3.8.4 Condition B with associated Required Actions and CT would state:
fL_ Q"lf._f"PQt...1 rfd Lili:. 2 12 '1QU!"S 2d:t.e*'v ~-~ Qr Qr
~ v t:,, y s : '- m * ~ r 1P ..t rr-p r'n "'lUm "S~oQl 1snf.(L floar vc tag<:_
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The NRC staff has identified the following discrepancy:
Both the 12 hour-CT for Required Action 8.1 and the initial 12-hour CT for Required Action 8 .2 start when Condition 8 is entered. If the battery terminal voltage was restored to greater than or equal to the minimum established float voltage within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (Required Action
- 8. 1), the battery would be on the exponential charging current portion of its recharging cycle at the end of the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. It appears that there would be no time remaining for the battery charging current to decrease to less than or equal to 2 amperes (amps) within the same 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (i.e., initial 12-hour CT for Required Action 8.2) .
The staff requests the following information to address this discrepancy:
Provide a discussion to demonstrate that the required battery can be fully recharged with a charging current of less than 2 amps within the initial 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from entry into Condition B (Required Action 8.2) after the required battery terminal voltage is restored to greater than or equal to the minimum established float voltage at the end of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from entry into Condition B (Required Action 8. 1).
Attachment Response to Request for Additional Information LAR to Revise TS 3.8.4, DC Sources-Operating Docket Nos. 50-277 and 50-278 Page 3 of 3
Response
The required battery cannot be fully recharged with a charging current of less than 2 amps within the initial 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from entry into Condition B (Required Action B.2) after the required battery terminal voltage is restored to greater than or equal to the minimum established float voltage at the end of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from entry into Condition B (Required Action B.1 ). This condition had been recognized during development of the LAR. Exelon did not pursue additional calculations or analysis to provide a CT for Required Action B.2 that exceeded the analysis that had been provided in TSTF-500, Revision 2, "DC [direct current] Electrical Rewrite - Update to TSTF-360." For the above condition to occur, both the on-line and standby safety related battery chargers, as well as the permanently installed alternate non-safety related battery charger, would have had to fail. The alternate battery charger has been designed and will be operated in a manner to be available within approximately two hours to start charging the battery that may have experienced a discharging condition due to failure of the on-line and standby battery chargers. The condition of all three battery chargers failing concurrently was judged to be of such low probability that it did not justify the additional effort to support an extended CT beyond the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the battery to be fully recharged with a charging current of less than 2 amps. Exelon acknowledges that if such a condition did occur and the proposed LCO 3.8.4.B Required Action B.2 could not be met, the proposed LCO 3.8.4 Condition F would be entered and the associated Unit would be required to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.