Letter Sequence RAI |
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TAC:ME9631, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (Approved, Closed) TAC:ME9632, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting
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MONTHYEARML12286A0122012-09-28028 September 2012 License Amendment Request - Extended Power Uprate Project stage: Request ML12286A0112012-09-30030 September 2012 License Amendment Request - Extended Power Uprate, Attachment 4, NEDO-33566, Rev. 0, Safety Analysis Report, Constant Pressure Power Uprate, Page 2-488 Through End, and Attachments 5 and 7 Through 9 Project stage: Request ML12279A2852012-10-22022 October 2012 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML12279A2902012-10-22022 October 2012 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit 2 Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13042A0962013-02-0808 February 2013 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Error in Main Steam Line High Flow Calculational Methodology Project stage: Request ML13051A0322013-02-15015 February 2013 Supplemental Information & Corrections Supporting Request for License Amendment Request - Extended Power Uprate - Supplement No. 1 Project stage: Supplement ML13056A4822013-03-0808 March 2013 Acceptance Review Regarding Proposed Extended Power Uprate Project stage: Acceptance Review ML13052A8532013-03-11011 March 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13052A8562013-03-11011 March 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13081A7052013-03-28028 March 2013 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML13106A1262013-04-26026 April 2013 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML13129A1432013-05-0707 May 2013 Extended Power Uprate, Supplement 2 - Response to Request for Additional Information Project stage: Supplement ML13149A1452013-05-24024 May 2013 Extended Power Uprate License Amendment Request - Supplement 3 Response to Request for Additional Information - Extended Power Uprate Project stage: Supplement ML13156A3682013-06-0404 June 2013 Extended Power Uprate License Amendment Request Supplement 4 Response to Request for Additional Information - Extended Power Uprate Project stage: Supplement ML13134A3842013-06-10010 June 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13161A3972013-06-26026 June 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13182A0252013-06-27027 June 2013 Supplemental Information Supporting Request for License Amendment Request - Extended Power Uprate - Supplement No. 5 Project stage: Supplement ML13178A3312013-07-0101 July 2013 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML13183A1992013-07-0303 July 2013 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML13203A1142013-07-23023 July 2013 Non-Proprietary - Request for Additional Information Regarding Proposed License Amendment Extended Power Uprate Project stage: RAI ML13203A1002013-07-23023 July 2013 Request for Additional Information Regarding License Amendment Request for Extended Uprate Project stage: RAI ML13211A4032013-07-30030 July 2013 EPU LAR Supplement 6 Attachment 2 - Response to Request for Additional Information - Snpb Project stage: Supplement ML13211A4022013-07-30030 July 2013 Extended Power Uprate License Amendment Request - Supplement 6 Response to Request for Additional Information - Extended Power Uprate Project stage: Supplement ML13213A2852013-07-31031 July 2013 Extended Power Uprate License Amendment Request - Supplement 7, Response to Request for Additional Information - Extended Power Uprate Project stage: Supplement ML13217A4312013-08-0505 August 2013 Extended Power Uprate License Amendment Request - Supplement 8 Response to Request for Additional Information - Extended Power Uprate Project stage: Supplement ML13221A0642013-08-15015 August 2013 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML13240A0022013-08-22022 August 2013 Extended Power Uprate License Amendment Request - Supplement 9 Response to Request for Additional Information Project stage: Supplement ML13232A2772013-08-26026 August 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13232A2902013-08-26026 August 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13241A4182013-08-29029 August 2013 Extended Power Uprate License Amendment Request - Supplement 10 Response to Request for Additional Information Project stage: Supplement ML13253A4162013-09-11011 September 2013 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML13260A0762013-09-13013 September 2013 Extended Power Uprate License Amendment Request - Supplement 11 Response to Request for Additional Information Project stage: Supplement ML13247A7692013-09-18018 September 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13261A0432013-09-18018 September 2013 Requesty for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: Other ML13242A0902013-10-0101 October 2013 Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Draft Other ML13242A1082013-10-0101 October 2013 Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Draft Other ML13268A4002013-10-0101 October 2013 Enclosure 2 - Peach Bottom Atomic Power Station, Units 2 and 3 - Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML13268A2632013-10-0101 October 2013 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML13289A1912013-10-11011 October 2013 Extended Power Uprate License Amendment Request - Supplement 12, Response to Request for Additional Information Project stage: Supplement ML13289A3002013-10-15015 October 2013 Extended Power Uprate License Amendment Request - Supplement 13 Response to Request for Additional Information Project stage: Supplement ML13308A3312013-10-31031 October 2013 Extended Power Uprate License Amendment Request - Supplement 14, Response to Request for Additional Information Project stage: Supplement ML13291A1222013-11-0606 November 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13339A8072013-11-22022 November 2013 Comment (1) of Kevin Borton on Behalf of Exelon Generation Co. LLC, on Proposed License Amendment to Increase the Maximum Reactor Power Level Project stage: Other ML13338A2502013-12-0404 December 2013 Notice of Forthcoming Closed Meeting with Exelon Generation Company, LLC (Exelon) to Discuss Steam Dryer Analysis Related to Proposed Extended Power Uprate (EPU) for Peach Bottom Atomic Power Station (Pbaps), Units 2 and 3 Project stage: Request ML13345A6872013-12-0606 December 2013 Supplement 15 Response to Request for Additional Information Extended Power Uprate License Amendment Request Project stage: Supplement ML13308C4412013-12-11011 December 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13351A3902013-12-19019 December 2013 Summary of Closed Meeting with Exelon Generation Company, LLC, to Discuss Steam Dryer Analysis Related to Proposed Extended Power Uprate for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Meeting ML13358A0832013-12-20020 December 2013 Extended Power Uprate License Amendment Request- Supplement 16 Corrections, Clarifications and Additional Information - Extended Power Uprate Project stage: Supplement ML13345B3102014-01-0808 January 2014 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML14002A1762014-01-15015 January 2014 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI 2013-05-24
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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:Request for Additional Information (RAI)
MONTHYEARIR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML22118A3312022-04-28028 April 2022 NRR E-mail Capture - Peach Bottom - Formal RAI for Proposed Alternative I5R-14, Revision 1 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22021A5692022-01-21021 January 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000277/2022403 and 05000278/2022403 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21035A2222021-02-0404 February 2021 Notification of Conduct of a Fire Protection Team Inspection ML21091A1782021-02-0202 February 2021 Ti 2515/194 Inspection Documentation Request ML21012A1302021-01-12012 January 2021 Request for Additional Information - TSTF-505 ML20357A0972020-12-21021 December 2020 Request for Additional Information - TSTF-505 ML20296A3342020-10-21021 October 2020 ISI Remote Inspection - Supplemental Request for Information ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20070R2282020-03-10010 March 2020 Request for Additional Information - RR ML19303D1662019-10-31031 October 2019 Requests for Additional Information for the Environmental Review of the Peach Bottom Subsequent License Renewal Application - Set 2 (EPID No. L-2018-RNW-0013)- RAIs ML19232A1752019-08-20020 August 2019 Request for Additional Information - TSTF-500 Implementation LAR ML19140A2832019-05-15015 May 2019 Email - Peach Bottom Atomic Power Station, Units 2 and 3 Second Round RAI Request - Set 1 ML19140A2822019-05-15015 May 2019 027 Pb FU RAI Subsequent to Clarification Call - Cu Greater than 15 Zn Holston (Jg) ML19253D2932019-05-0707 May 2019 002 Attachment 4D Confirmation Water Chemistry Chereskin Revised (002) ML19249C7252019-05-0303 May 2019 SLRA Requests for Additional Information - Set 2 May 3, 2019 ML19108A4282019-04-10010 April 2019 RAIs SLRA Set 1_ERO(Rev 1) ML19079A0232019-03-19019 March 2019 Licensed Operator Positive Fitness-For-Duty Test ML19058A2902019-02-27027 February 2019 Request for Additional Information - High Pressure Service Water One Time TS Change ML19037A4832019-02-0606 February 2019 NRR E-mail Capture - Clarification Questions Associated with Staff Assessment of Peach Bottom Seismic Probabilistic Risk Assessment Report Dated August 28, 2018 ML19028A0062019-01-25025 January 2019 Secondary Containment LAR Requests for Additional Information ML19017A0472019-01-16016 January 2019 Request for Additional Information - High Pressure Service Water One Time TS Change ML18348B0292018-12-13013 December 2018 Subsequent License Renewal Severe Accident Mitigation Alternatives Requests for Additional Information ML19010A3832018-12-0707 December 2018 Additional Documents Needed for Peach Bottom SLR Environmental Review ML18324A6742018-11-15015 November 2018 Request for Additional Information (FINAL)- LAR to Allow 2SRV/SVs OOS at High Pressure ML18312A4072018-11-0808 November 2018 Request for Additional Information (Public) - LAR to Allow 2SRV/SVs OOS at High Pressure ML18276A0202018-10-0202 October 2018 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan for Limerick and Peach Bottom ML18240A1742018-08-28028 August 2018 Request for Additional Information (Final) - Adopt TSTF-500 Battery TS Changes LAR ML18239A1322018-08-27027 August 2018 Request for Additional Information Final - Relief Request I5R-04 ML18228A6762018-08-14014 August 2018 Request for Additional Information - Adopt TSTF-500 Battery TS Changes LAR ML18226A2012018-08-14014 August 2018 Request for Additional Information - Relief Request I5R-05 ML18214A2812018-08-0202 August 2018 Request for Additional Information Draft - Relief Request I5R-02 ML18200A2742018-07-17017 July 2018 Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment ML18192A1192018-07-10010 July 2018 Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment ML18178A4772018-06-27027 June 2018 Request for Additional Information 2nd Round - Adopt 50.69 License Amendment ML18096B5062018-04-0606 April 2018 Request for Additional Information Exelon Generation Company, LLC Requested Amendment to Adopt 10 CFR 50.69 for Risk-informed Categorization and Treatment of Structures, Systems and Components ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17317B5502017-11-0909 November 2017 Licensed Operator Positive Fitness-For-Duty Test ML17240A0062017-08-24024 August 2017 Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML17222A0962017-08-10010 August 2017 Request for Additional Information - Amendment Request Regarding Safety Relief Valve and Safety Valce Operability for Cycle 22 2023-09-21
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{{#Wiki_filter:OFFICIAL USE ONLY PROPRIETARY INFORMATION (" UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 July 23, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE (TAC NOS. ME9631 AND ME9632)
Dear Mr. Pacilio:
By letter dated September 28, 2012, as supplemented by letters dated February 15, 2013, May 7,2013, May 24,2013, June 4,2013, and June 27,2013, (Agencywide Documents Access and Management System Accession Nos. ML 122860201, ML 13051A032, ML 13129A143, ML13149A145, ML13156A368, and ML13182A025, respectively), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for Peach Bottom Atomic Power Station, Units 2 and 3. The proposed amendment would authorize an increase in the maximum power level from 3514 megawatts thermal (MWt) to 3951 MWt. The requested change, referred to as an extended power uprate, represents an increase of approximately 12.4 percent above the current licensed thermal power level. The Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The Reactor Systems Branch RAI questions were provided in draft form to Mr. Kevin Borton of your staff on June 17, 2013. The Accident Dose Branch RAI question was provided in draft form to Mr. Borton on July 2, 2013. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
On July 23, 2013, Mr. Borton stated that a response to the RAls would be provided within 30 days of the date of this letter. Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. The NRC staff has determined that Enclosure 1 contains proprietary information pursuant to 10 CFR 2.390. Accordingly, the staff has prepared a redacted, publicly available, proprietary version (Le., Enclosure 2). Enclosure 1 transmitted herewith contains sensitive unclassified non-safeguards information.
When separated from Enclosure 1, this document is decontrol/ed.
OFFICIAL USE ONLY PROPRIETARY INFORMATION 1E L OFFICIAL USE ONLY PROPRIETARY M. Pacilio -2 If you have any questions, please contact me at (301) 415-1420.
Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278
Enclosures:
- 1. Request for Additional Information (non-publicly available)
- 2. Request for Additional Information (publicly available) cc w/encl 2: Distribution via Listserv OFFICIAL USE ONLY PROPRIETARY REQUEST FOR ADDITIONAL REGARDING PROPOSED LICENSE EXTENDED POWER PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND DOCKET NOS. 50-277 AND Proprietary information pursuant Title 10 of the Code of Federal Regulations (10 CFR) Section has been redacted from this Redacted information is identified by blank space enclosed within double as shown here [[ Enclosure 2
REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT EXTENDED POWER UPRATE EXELON GENERATION COMPANY, LLC PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 By letter dated September 28, 2012, as supplemented by letters dated February 15, 2013, May 7,2013, May 24,2013, June 4,2013, and June 27, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 122860201, ML 13051A032, ML 13129A143, ML 13149A145, ML 13156A368, and ML 13182A025, respectively), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed amendment would authorize an increase in the maximum power level from 3514 megawatts thermal (Mwt) to 3951 MWt. The requested change, referred to as an extended power uprate (EPU), represents an increase of approximately 12.4 percent above the current licensed thermal power level. The Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific request for additional information (RAI) is addressed below. Reactor Systems Branch (SRXB) Reviewer:
Diana Woodyatt Fuel and Core Design SRXB RAI-2 Section 2.8.2.1 of the Power Uprate Safety Analysis Report (PUSAR1) indicates that the average bundle power would increase from the current licensed thermal power (CL TP) value of 4.60 Megawatts (MW)/bundle to a value of 5.17 MW/bundle under EPU conditions.
This 12.4% change in average bundle power level corresponds to the same percent increase of total core power from CL TP to EPU conditions.
For constant pressure power uprate (CPPU) for water reactors (BWRs), it is assumed that the additional core power is obtained by flattening the core power profile (Le., raising the average bundle power, but keeping the peak bundle power the same). However, past BWR EPU operations have demonstrated that peak bundle power can increase by a limited amount. Please provide the current peak bundle power level and the expected value of peak bundle power for EPU operation at PBAPS. 1 A proprietary (i.e., non-publicly available) version of the PUSAR is contained in Attachment 6 to the application dated September 28, 2012. A non-proprietary (i.e., publicly available) version of the PUSAR is contained in Attachment 4 to the application dated September 28,2012.
-2 SRXB As stated in the PUSAR, PBAPS EPU analyses assumed a representative "equilibrium" core comprised of GNF2 fuel only. Describe the PBAPS core design for the first EPU cycle. If the actual EPU core will be comprised of other GE fuel designs, for example GE14, in addition to GNF2, then justify why using a GNF2 equilibrium core for EPU calculations provides bounding results for EPU transient and accident analyses, in particular the safety limits (minimum critical power ratio (MCPR), linear heat generation rate, maximum average planar linear heat rate, peak cladding temperature (PCT), etc.). SRXB RAI-4 Pellet clad interaction (PCI) and stress corrosion cracking (SCC) phenomena can cause clad perforation resulting in leaking fuel bundles and resultant increased reactor coolant activity.
Therefore, the NRC staff requests the licensee to provide the following additional information regarding PCI/SCC for PBAPS at EPU conditions: Describe any differences in operating procedures associated with PCI/SCC at EPU conditions versus pre-EPU operations. From the standpoint of PCI/SCC, discuss which of the Anticipated Operational Occurrences (AOOs), if not mitigated, would most affect operational limitations associated with PCI/SCC. For the AOOs in part (b), discuss the differences between the type of required operator actions, if any, and the time to take mitigating actions between pre-EPU and EPU operations. If the EPU core will include fuel designs with non-barrier cladding which have less built-in PCI resistance, then demonstrate by plant-specific analyses that the peak clad stresses at EPU conditions will be comparable to those calculated for the current operating conditions. Describe operator training on PCI/SCC operating guidelines.
Thermal-Hydraulic Design and Anticipated Transients Without SCRAM SRXB RAI-5 Characterize the expected amount of bypass voiding under CPPU conditions.
Provide the expected bypass void level at points C, D, and E of Figure 1-1 of the PUSAR, using a methodology equivalent to that used by ISCOR for both hot and average channel. SRXB RAI-6 Reliability of the local power range monitor (LPRM) instrumentation and accurate prediction of in-bundle pin powers typically requires operation with bypass voids lower than 5% at nominal conditions (e.g., point E of Figure 1-1 of the PUSAR). If the expected bypass void conditions at CPPU are greater than 5%, evaluate the impact on: (1) reliability of LPRM instrumentation, (2) accuracy of LPRM instrumentation, and (3) in-bundle pin powers.
-3 SRXB The presence of bypass voids affects the LPRM calibration.
Evaluate the expected calibration error on Oscillation Power Range Monitor (OPRM) and Average Power Range Monitor cells induced by the expected level of bypass voids. Document the impact of this error on the and-suppress Option III scram setpoint.
SRXB RAI-8 PUSAR Table 2.8-2 only shows the Option III Setpoints Demonstration.
Please provide an example setpoint calculation for the EPU cycle including an uncertainty term reflecting the possible LPRM miscalibration under bypass void conditions.
SRXB RAI-9 The Delta Critical Power Ratio (CPR) over Initial CPR Versus Oscillation Magnitude (DIVOM) slope is not included in PUSAR Table 2.8-2 under CPPU conditions.
Please document which DIVOM slope will be used for future CPPU cycles and which methodology will be used to: (1) calculate it, or (2) evaluate the adequacy of an older slope. SRXB RAI-10 Assuming a conservative OPRM setpoint of 1.15, provide the hot-spot fuel temperature as a function of time before the scram. Evaluate this fuel temperature oscillation against PCI limits. Assume that the steady-state fuel conditions before the oscillations are those of point A 1 of PUSAR Figure 2.8-21 (the highest power point in the backup stability protection (SSP) scram region). SRXB RAI-11 Describe any effects or impacts of EPU on the long-term stability implementation.
SRXB RAI-12 For the SSP calculations, describe how the stability curves for the scram region and the controlled entry region shown in PUSAR Figure 2.8-21 are calculated for EPU conditions.
Specifically, provide the associated feedwater temperature assumptions that allow the use of the same decay ratio criteria shown in Table 2.8-3 for the Scram and Controlled Entry boundary.
SRXS RAI-13 Provide plant-specific information relevant to an anticipated transient without scram (A lWS) event under EPU conditions.
Specifically, provide the location of the boron injection, a description of the standby liquid control system actuation logic and its operability requirements, boron enrichment level, turbine bypass capacity, and location of the steam extraction points for the feedwater heaters.
-SRXB Provide a short summary of the Solution III hardware currently installed in PBAPS. Provide justification that the hot channel oscillation magnitude portion of the Option III calculation is not affected by EPU because the OPRM hardware does not change. SRXB RAI-15 Provide a summary of the A TWS emergency operating procedure (EOP) actions. What version of emergency operating guidelines is currently implemented in PBAPS? Provide a short description of the process used to ensure that the emergency procedure guideline variables (e.g., hot shutdown boron weight, heat capacity temperature limit, etc.) are adequate under CPPU conditions.
SRXB RAI-16 Provide a short description of how the Stability Mitigation Actions (e.g., immediate water level reduction and early boron injection) are implemented in PBAPS. Does operation at CPPU conditions require modification of any operator instructions?
SRXB RAI-17 PBAPS currently operates under the Option III solution.
Please provide clarification for the following areas: Describe the process that was followed by PBAPS to implement Option III Long-Term Stability Solution and to verify that Option III is still applicable under CPPU operation. Describe the expected effects of CPPU operation on Option III. Describe any alternative method to provide detection and suppression of any mode of instability other than through the current OPRM scram. Provide a summary of the PBAPS Technical Specifications affected by the Option III implementation and future CPPU operation. List the approved methodologies used to calculate the OPRM setpoint by the current operation and future PBAPS CPPU operation.
SRXB RAI-18 Provide a table of hot channel and core-wide decay ratios at the most limiting state point for the last cycles and the proposed CPPU condition.
The purpose is to evaluate the impact of CPPU on relative stability of the plant, and the applicability of Option III to PBAPS under these new conditions.
-5 SRXB RAI-19 Describe the effects or impacts, if any, of EPU on suppression pool cooling during isolation ATWS events and/or EOPs. SRXB RAI-20 Please provide a short description of the simulator neutronic core model. Also, provide the schedule to show when the PBAPS simulator will be upgraded for EPU conditions.
SRXB RAI-21 PUSAR Section 2.8.5.7.3 states that the highest calculated PCT for ATWS events is 1342 of, during the Pressure Regulator Failure Open event. The submittal states that: Local cladding oxidation is not explicitly analyzed because, with PCT less than 1600 of, cladding oxidation has been demonstrated to be insignificant compared to the acceptance criteria of 17% of cladding thickness.
Therefore, the local cladding oxidation for the PBAPS A TWS events is qualitatively evaluated to show compliance with the acceptance criteria of 10 CFR 50.46. Please provide a reference to show where cladding oxidation has been demonstrated to be insignificant when the PCT is less than 1600 of during A TWS events. Emergency Systems SRXB RAI-22 With respect to overpressure protection (i.e., Section 2.8.4.2 of the PUSAR), if an analysis was performed for the Turbine Trip with Bypass Failure and Scram on High Flux (TTNBPF) event, as it is required in Table E-1 of EL TR-1, please provide a plot comparing the pressure transients for the Main Steam Isolation Valve Closure with Scram on High Flux and the TTNBPF events. If a TTNBPF analysis was not performed for EPU, then justify why not. SRXB RAI-23 Do the decay heat removal requirements change between current and EPU power levels due to any changes in decay heat load or suppression pool temperature?
If so, what are the new requirements and how does the reactor core isolation cooling (RCIC) system meet the new criteria without updating the system performance?
SRXB RAI-24 Table 4.7.1 in the PBAPS Updated Final Safety Analysis Report (UFSAR) shows that the RCIC system pump has a design temperature range of 40 of to 140 of. Are there any instances under EPU conditions where the pump would be operating outside of this temperature range? If so, what are the conditions and how are they addressed for this EPU?
-6 SRXB What is the effect on net positive suction head for the reactor recirculation system for EPU? The PUSAR stated this result is based on past uprate analyses.
Explain the past analyses and their relevance.
Accident and Transient Analyses SRXB RAI-26 Section 2.8.5.6.2.5 of the PUSAR states that the licensing basis PCT is 1925 of based on the most limiting Appendix K case, including a variable plant uncertainty term. Please provide further explanation regarding the "plant variable uncertainty term." SRXB RAI-27 Page 2-396 of the PUSAR states that, independent of the EPU, the licensee will be replacing the recirculation system pump motor power supplies from motor/generator set power supplies to adjustable speed drives (ASDs). Section 2.8.5.2.1 of the PUSAR discusses Loss of External Load and Turbine Trip events with specific evaluations for the Generator Load Rejection with Steam Bypass Failure (LRNBP) event and the Trip with Steam Bypass Failure event. Results of the transient analysis, shown in PUSAR Table 2.8-12, indicates that LRNBP is the limiting event with a delta CPR of 0.27. Section 2.8.5.2.1 indicates that, [[ ]] Please specify the resulting delta CPR [[ II Operating Experience SRXB RAI-28 Recent operating experience has shown that, at a similar BWR/4, the events that follow a loss of stator cooling (LOSC) could cause a situation that is limiting with respect to the MCPR. Please explain whether the LOSC has a potential to be CPR-limiting at PBAPS. If the LOSC is non-CPR limiting, explain what design features exist to provide protection from a LOSC. If the LOSC is a CPR-limiting event, please explain what affect the EPU could have on the severity of the event, and how the EPU safety analyses address the event.
-7 Accident Dose Branch (AADB) Reviewers:
John Parillo and Jason White AADB-RAI-2 In Section 2.1.5 of Attachment 1 to Exelon's letter dated May 24, 2013, the licensee stated that: The EPU Main Steam Line Break (MSLB) Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) atmospheric dispersion factors are updated using a site-specific X/Q calculation.
This differs from the CLB [current licensing basis] MSLB evaluation which used X/Q values calculated using guidance from RG [Regulatory Guide] 1.5. Please provide a description of the calculation used for the updated MSLB XlQ values. Include a discussion of how it differs from the CLB MSLB evaluation, a justification for its use, and all inputs and assumptions used to make the calculation.
OFFICIAL USE! ONLY PROPRIE!TARY M. Pacilio -If you have any questions, please contact me at (301) 415-1420.
Sincerely, /ra! Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278
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