Letter Sequence Acceptance Review |
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EPID:L-2017-LLA-0281, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B (Approved, Closed) CAC:MG0181, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B (Approved, Closed) CAC:MG0182, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B (Approved, Closed) EPID:L-2017-LLA-0281, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B (Approved, Closed) |
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MONTHYEARML17086A4512017-02-21021 February 2017 02-21-17 NRC Final Revision of Appendix X to NEI 05-04, 07-12, 12-16, Close-Out of Facts and Observations (F&Os) Project stage: Request ML17243A0142017-08-30030 August 2017 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. Project stage: Request ML17272B0162017-10-10010 October 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Adoption of Title 10 of the Code of Federal Regulations Section 50.69 (CAC Nos. MG0181-82; EPID L-2017-LLA-0281) Project stage: Acceptance Review ML17297B5212017-10-24024 October 2017 Supplement to Application to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Supplement ML17300A2762017-10-27027 October 2017 Acceptance Review - Peach Bottom Units 2 and 3 - License Amendment Request to Adopt 10 CFR 50.69 (CAC Nos. MG0181 and MG0182; EPID L-2017-LLA-0281) Project stage: Acceptance Review ML18005A0772018-01-0909 January 2018 Regulatory Audit Plan Regarding License Amendment Request to Adopt 10 CFR 50.69 (CAC Nos. MG0181 and MG0182; EPID L-2017-LLA-0281) Project stage: Other 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 Project stage: RAI ML18072A3722018-04-10010 April 2018 Regulatory Audit Summary Regarding License Amendment Request to Adopt Title 10 of the Code of Federal Regulations Section 50.69 Project stage: Other 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. Project stage: Response to RAI ML18157A2602018-06-0606 June 2018 Supplemental Information to Support Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants. Project stage: Supplement ML18178A4772018-06-27027 June 2018 Request for Additional Information 2nd Round - Adopt 50.69 License Amendment Project stage: RAI ML18192A1192018-07-10010 July 2018 Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment Project stage: RAI ML18200A2742018-07-17017 July 2018 Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment Project stage: RAI 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 ... Project stage: Supplement ML18234A1872018-08-22022 August 2018 Supplemental Information - Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants Project stage: Supplement ML18263A2322018-10-25025 October 2018 Issuance of Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69 (CAC Nos. MG0181 and MG0181; EPID L-2017-LLA-0281) Project stage: Approval ML18302A2572018-11-0101 November 2018 Correction to Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems and Components (CAC Nos. MG0181 and MGO182; EPID L-2017-LLA-0281) Project stage: Other 2018-04-10
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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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 October 10, 2017 SUBJECT: PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3-SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: ADOPTION OF TITLE 10 OF THE CODE OF FEDERAL REGULATIONS SECTION 50.69 (CAC NOS. MG0181 AND MG0182; EPID L-2017-LLA-0281) Dear Mr. Hanson: By letter dated August 30, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17243A014), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for the Peach Bottom Atomic Power Station, Units 2 and 3. The proposed amendments would revise the licensing basis by adding a license condition to allow for the implementation of the provisions of Title 10 of the Code of Federal Regulations (1 O CFR) Section 50.69. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with 1 O CFR 50.69, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following, as far as applicable, the form prescribed for original applications. Section 50.34 of 1 O CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application and concluded that the information listed in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendments in terms of regulatory requirements and the protection of public health and safety and the environment. In order to make the application complete, the NRC staff requests that Exelon supplement the application to address the information requested in the enclosure by October 27, 2017. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by this date, the application will not be accepted for review pursuant to 1 O CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
B. Hanson -2 -The information requested and associated timeframe in this letter were discussed with Mr. Richard Gropp and other members of your staff, in a conference call with the NRC staff, on October 10, 2017. If you have any questions, please contact me at (301) 415-1420 or Rick.Ennis@nrc.gov. Docket Nos. 50-277 and 50-278 Enclosure: Supplemental Information Needed cc w/Enclosure: Distribution via Listserv Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST RE: ADOPTION OF TITLE 10 OF THE CODE OF FEDERAL REGULATIONS SECTION 50.69 EXELON GENERATION COMPANY. LLC PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 By letter dated August 30, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17243A014), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request (LAR) for the Peach Bottom Atomic Power Station, Units 2 and 3 (Peach Bottom). The proposed amendments would revise the licensing basis by adding a license condition to allow for the implementation of the provisions of Title 10 of the Code of Federal Regulations (1 O CFR) Section 50.69. The regulations in 10 CFR 50.69(c)(1 )(i) require that the probabilistic risk assessment (PRA) must be: (1) of sufficient quality and level of detail to support the categorization process; and (2) subjected to a peer review process assessed against a standard or set of acceptance criteria endorsed by the U.S. Nuclear Regulatory Commission (NRC). Section 50.69(b)(2)(iii) of 1 O CFR requires that the results of the peer review process conducted to meet 10 CFR 50.69 (c)(1)(i) criteria be submitted as part of the application. Regulatory Guide (RG) 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities" (ADAMS Accession No. ML090410014), endorses, with certain clarifications and qualification, the industry PRA standard contained in the American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) Standard ASME/ANS RA-Sa-2009 and provides guidance to licensees for determining the acceptability of their PRA by reviewing it against relevant parts of the standard using a peer review process. During a peer review, the documentation of differences or deficiencies between the licensee's PRA model and the NRG-endorsed industry PRA standards are generally labeled as facts and observations (F&Os). Nuclear Energy Institute (NEI) 05-04/07-12/12-06, Appendix X: "Close Out of Facts and Observations (F&Os)" (ADAMS Accession No. ML 17086A451 ), as accepted by the NRC in a letter dated May 3, 2017 (ADAMS Accession No. ML 17079A427), provides guidance to licensees for closing F&Os that were opened during the peer review process. In its LAR, the licensee stated that it reviewed and closed findings using the process documented in Appendix X to NEI 05-04, NEI 07-12, and NEI 12-13, and that the NRC staff observed the closure review of open PRA F&Os in November 2016. However, NEI provided the draft version of Appendix X to the NRC on February 8, 2016, and the final version on February 21, 2017. The final version of Appendix X included two substantive changes not addressed in the draft version. These changes included provisions for:
- A documented licensee justification and an F&O closure team assessment that supports the classification of each F&O finding resolution as either a PRA upgrade or PRA maintenance update, as defined in the ASME/ANS RA-Sa-2009 PRA Standard endorsed by RG 1.200, Revision 2; and Enclosure
-2 -* The independent assessment (IA) team's confirmation that the aspects of the underlying supporting requirements (SRs) that were previously not met, or met at Capability Category I (CC-I), are now met or met at CC-II. Because the F&O closure process described in Appendix X relies on an onsite review, there are no provisions for a "gap assessment" in order to update the results of a review performed before February 21, 2017, to the final guidance. The May 3, 2017, NRC letter that accepted the F&O closure process references an NRC Staff Memorandum (ADAMS Accession No. ML 17095A252), which includes the NRC staff observations of the Peach Bottom F&O closure process, including the observation of the F&O closure final report after it was completed. As indicated in the NRC memorandum, neither the licensee nor the IA team conducted a systematic evaluation or provided a documented justification that supported the classification of each F&O resolution as either a PRA upgrade or PRA maintenance update. In addition, the NRC memorandum noted that in most cases, the IA team did not revisit the original text of the SRs in ASME/ANS RA-Sa-2009, but instead only addressed the text provided by the licensee that described the F&O and the reported resolution. The NRC staff has determined that the following information is required in order for the licensee's LAR to be accepted as a risk-informed LAR: a. A description of the evaluation performed that led to the conclusion in the LAR that the "closed findings were reviewed and closed using the process documented in Appendix X ... as accepted by NRC in the staff memorandum dated May 3, 2017." b. The licensee's documented justification and the IA team's documented assessment supporting the classification of each F&O finding resolution for closed F&Os as either a PRA upgrade or PRA maintenance update, as defined in the ASME/ANS RA-Sa-2009 PRA Standard endorsed by RG 1.200, Revision 2. c. The IA team's confirmation that for the closed F&Os, the aspects of the underlying SRs in ASME/ANS RA-Sa-2009 that were previously not met, or met at CC-I, are now met or met at CC-II. The information requested above was discussed in a conference call, between the Exelon staff and the NRC staff, on October 10, 2017. During this call, for item "b" above, it was agreed that the licensee would document this information and make it available for NRC staff audit after it is completed. Exelon's response to this supplemental information request should acknowledge this path forward and state the date when the information will be available.
B. Hanson -3 -SUBJECT: PEACH BOTIOM ATOMIC POWER STATION, UNITS 2 AND 3 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: ADOPTION OF TITLE 10 OF THE CODE OF FEDERAL REGULATIONS SECTION 50.69 (CAC NOS. MG0181 AND MG0182; EPID L-2017-LLA-0281) DATED OCTOBER 10, 2017 DISTRIBUTION: PUBLIC RidsNrrDorl Resource RidsNrrDorlLpl1 Resource RidsNrrPMPeachBottom Resource RidsACRS_MailCTR Resource RidsRgn1 MailCenter Resource RidsNrrLALRonewicz Resource RidsNrrDraApla Resource JTobin, NRR ADAMS Accession No.: ML 172728016 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NAME REnnis LRonewicz DATE 10/10/2017 10/02/2017 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/PM NAME Joanna REnnis DATE 10/10/2017 10/10/2017 OFFICIAL RECORD COPY NRR/DRA/APLA/BC SRosenberg (JRobins for) 10/10/2017