Letter Sequence Other |
---|
|
|
MONTHYEARML16189A3282016-07-12012 July 2016 NRC Plan for the Audit of Exelon Generation'S Mitigation Strategies Assessment Submittals Relating to Order EA-12-049 for Braidwood Station, Dresden Nuclear Power Station, Peach Bottom Units 2 and 3, and Three Mile Island, Unit 1 Project stage: Other ML16302A4592016-11-28028 November 2016 Flood Hazard Mitigation Strategies Assessment Project stage: Other ML16300A1992016-12-0808 December 2016 Flood Hazard Mitigating Strategies Assessment Project stage: Other L-2016-226, NEI 12-06, Revision 2, Appendix G, G.4.2 Mitigating Strategies Assessment Flex Strategies Report for the New Flood Hazard Information2016-12-20020 December 2016 NEI 12-06, Revision 2, Appendix G, G.4.2 Mitigating Strategies Assessment Flex Strategies Report for the New Flood Hazard Information Project stage: Request ML16362A2082017-01-11011 January 2017 Flood Hazard Mitigation Strategies Assessment Project stage: Other ML17076A1982017-03-29029 March 2017 Correction to Flood Hazard Mitigation Strategies Assessment Project stage: Other ML17143A0342017-06-27027 June 2017 Flood Hazard Mitigation Strategies Assessment Project stage: Other 2016-07-12
[Table View] |
NRC Plan for the Audit of Exelon Generation'S Mitigation Strategies Assessment Submittals Relating to Order EA-12-049 for Braidwood Station, Dresden Nuclear Power Station, Peach Bottom Units 2 and 3, and Three Mile Island, Unit 1ML16189A328 |
Person / Time |
---|
Site: |
Dresden, Peach Bottom, Three Mile Island, Braidwood ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
---|
Issue date: |
07/12/2016 |
---|
From: |
Govan T V Japan Lessons-Learned Division |
---|
To: |
Bryan Hanson Exelon Generation Co |
---|
References |
---|
CAC MF7898, CAC MF7899, CAC MF7921, CAC MF7922, CAC MF7958, CAC MF7959, CAC MF7984 |
Download: ML16189A328 (6) |
|
|
---|
Category:Audit Plan
MONTHYEARML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) ML24088A3202024-03-28028 March 2024 Beyond 60 Years - Audit Plan ML22335A5652022-12-14014 December 2022 Audit Plan to Support the Review of Licensee'S Information Related to Equipment Qualification License Amendment Request for Transition to GNF3 Fuel ML22265A0132022-09-28028 September 2022 Steam Generator License Renewal Response to Commitment 10 - Audit Plan ML22214A0042022-08-0202 August 2022 Audit Plan to Support the Review of Amendments to Revise Criticality Safety Analysis Methodologies (Epids L-2022-LLA-0085, L-2021-LLA-0124, and L-2021-LLA-0159) ML21314A2182022-01-18018 January 2022 Audit Plan in Support of Review of License Amendment Request Regarding the Ultimate Heat Sink ML20290A5242020-10-21021 October 2020 Regulatory Virtual Audit Plan Regarding License Amendment Request to Adopt TSTF-505, Revision 2 ML19133A0862019-05-20020 May 2019 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 ML19031C8452019-01-25025 January 2019 Audit Plan for Exelon Generation Company, Llc. License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies at Braidwood Station, Units 1 and 2 - Renewed Facility Operating License Nos. NPF-72 and NPF-77 ML18304A2002018-11-0606 November 2018 License Renewal Severe Accident Mitigation Alternatives Audit Plan Regarding the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML18289A3792018-10-25025 October 2018 License Renewal Environmental Site Audit Plan Regarding the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application ML18282A0292018-10-16016 October 2018 Plan for the In-Office Regulatory Audit Regarding the Subsequent License Renewal Application Review ML18249A2802018-09-13013 September 2018 Plan for the Operating Experience Audit Regarding the Subsequent License Renewal Application 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) ML17220A3282017-08-10010 August 2017 Nuclear Regulatory Commission Audits of Licensee Responses to Phase 2 of Order EA-13-109 to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML17177A4462017-07-0606 July 2017 Audit Plan for Licensee Responses Concerning Seismic Hazard Reevaluations Related to Request for Information -(50.54(F) Letter) Regarding Recommendation 2.1 of the Near-Term Task Force ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16189A3282016-07-12012 July 2016 NRC Plan for the Audit of Exelon Generation'S Mitigation Strategies Assessment Submittals Relating to Order EA-12-049 for Braidwood Station, Dresden Nuclear Power Station, Peach Bottom Units 2 and 3, and Three Mile Island, Unit 1 ML15230A2732015-08-26026 August 2015 Nuclear Regulatory Commission Plan for Audit of Exelon Generation Company Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 Flooding for Three Mile Island Nuclear Station, Unit 1 ML15230A2352015-08-26026 August 2015 Nuclear Regulatory Commission Plan for the Audit of Exelon Generation Company Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 Flooding for Peach Bottom Atomic Power Station ML15183A4342015-07-0909 July 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML15161A4132015-06-11011 June 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML15119A2922015-05-0606 May 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14356A0032015-02-10010 February 2015 Audit of Licensee Responses to the Expedited Seismic Evaluation Process to Support Implementation of Near-Term Task Force Recommendation 2.1, Seismic ML14356A0042014-12-30030 December 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14183A0132014-07-0202 July 2014 Plan to Audit the Regional Response Center Proof of Concept Demonstration with Three Mile Island Nuclear Station, Unit 1 Regarding Implementation of Phase 3 Related to Order EA-12-049 (Mitigating Strategies) ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 ML13182A0482013-07-10010 July 2013 Audit Plan for Braidwood and Byron Licensee Action Taken to Resolve Turbine Building High Energy Line Break Non-Conformance 2024-07-24
[Table view] Category:Letter
MONTHYEARIR 05000277/20240022024-08-14014 August 2024 Integrated Inspection Report 05000277/2024002 and 05000278/2024002 IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24225A1692024-08-12012 August 2024 10 CFR 50.46 Annual Report 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 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter 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 RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24191A0612024-07-0606 July 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, “Safety Limit Mcpr” ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter ML24177A1512024-06-24024 June 2024 Post Accident Monitoring Instrumentation Report ML24166A1172024-06-20020 June 2024 Regulatory Audit Summary Regarding Proposed Alternative Schedule to Complete Decommissioning Beyond 60 Years IR 07200077/20240012024-06-18018 June 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 07200077/2024001 ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant ML24157A3672024-06-13013 June 2024 Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter ML24135A1972024-06-13013 June 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0091 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000277/20243012024-06-13013 June 2024 Initial Operator Licensing Examination Report 05000277/2024301 and 05000278/2024301 ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations RS-24-058, Regarding Subsequent License Renewal Environmental Review2024-06-0505 June 2024 Regarding Subsequent License Renewal Environmental Review RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel ML24150A2722024-05-29029 May 2024 Annual Radiological Environmental Operating Report 81, January 1, 2023 Through December 31, 2023 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24120A3242024-05-24024 May 2024 TMI-2 Email to Fws RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications 2024-08-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville
, IL 60555 July 12, 2016
SUBJECT:
NUCLEAR REGULA TORY COMMISSION PLAN FOR THE AUDIT OF EXELON GENERATION COMPANY, LLC'S MITIGATION STRATEGIES ASSESSMENT SUBMITTALS RELATING TO ORDER EA-12-049, "ORDER TO MODIFY LICENSES WITH REGARD TO REQUIREMENTS FOR MITIGATION STRATEGIES FOR BEYOND-DESIGN-BASIS EXTERNAL EVENTS," FOR BRAIDWOOD STATION, UNITS 1 AND 2 (CAC NOS. MF7898 AND MF7899); DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 (CAC NOS. MF7921 AND MF7922); PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 (CAC NOS. MF7958 AND MF7959); AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (CAC NO. MF7984).
Dear Mr. Hanson:
This letter documents the U.S. Nuclear Regulatory Commission (NRC) staff's plan to perform regulatory audits of Exelon Generation Company, LLC's (the licensee)
Mitigation Strategies Assessment (MSA) submittals related to Order EA-12-049
, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12054A735) for the following plants:
- Braidwood Station, Units 1 and 2 (Braidwood)
- Dresden Nuclear Power Station, Units 2 and 3 (Dresden)
- Peach Bottom Atomic Power Station, Units 2 and 3 (Peach Bottom)
- Three Mile Island Nuclear Station, Unit 1 (Three Mile Island).
These technical audits will be performed consistent with NRC Office of Nuclear Reactor Regulation Office Instruction LIC-111, "Regulatory Audits," dated December 29, 2008 (ADAMS Accession No. ML082900195)
. The audits will be conducted over multiple sessions, as needed, and the NRC staff will develop an audit summary report to document its observations and conclusions within 90 days of the final audit session.
The audits will provide the NRC staff with a better understanding of the MSAs. Specifically, the audits will be used to confirm that the MSA submitted by the licensee has adequately addressed the reevaluated hazards within its mitigation strategies for beyond-design-basis external events.
B. Hanson The enclosed audit plan outlines the process that will allow the NRC staff to identify additional information potentially necessary for licensees to supplement their MSAs, and resolve any potential technical concerns. The details of this audit have been discussed with Mr. Dave Distel of your staff. If you have any questions
, please contact me at (301) 415-6197 or by e-mail at Tekia.Govan@nrc
.gov. Docket Nos.: Sincerely
, Juu °'-
Tekia V. Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Braidwood:
STN 50-456 and STN 50-457 Dresden: 50-237 and 50-249 Peach Bottom: 50-277 and 50-278 Three Mile Island: 50-289 Enclosure
- Audit Plan cc w/encl: Distribution via Listserv NRC PLAN FOR THE AUDIT OF EXELON GENERATION
- COMPANY, LLC'S MITIGATION STRATEGIES ASSESSMENT SUBMITTALS RELATING TO ORDER EA-12-049 FOR MULTIPLE PLANTS BACKGROUND AND AUDIT BASIS: By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No ML 12053A340),
the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(f)
(hereafter referred to as the 50.54(f) letter). The 50.54(f) letter was issued as part of the lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested that licensees reevaluate flood-causing mechanisms using present-day methodologies and guidance. Concurrent with the reevaluation of flood hazards, licensees were required to develop and implement mitigating strategies using the most recent external hazard information in accordance with NRC Order EA-12-049
, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML 12054A735)
. That order requires holders of operating reactor licenses and construction permits issued under 10 CFR Part 50 to modify the plants to provide additional capabilities and defense-in-depth for responding to beyond-design-basis external events, and to submit to the NRC for review a final integrated plan that describes how compliance with the requirements of Attachment 2 of the order was achieved. In order to proceed with implementation of Order EA-12-049
, licensees used the current licensing basis flood hazard or the most recent flood hazard information
, which may not be based on present day-methodologies and guidance, in the development of their mitigating strategies
. The NRC staff and industry recognized the difficulty in developing and implementing mitigating strategies before completing the reevaluation of flood hazards.
The NRC staff described this issue and provided recommendations to the Commission on integrating these related activities in COMSECY-14-0037
, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flood Hazards," dated November 21, 2014 (ADAMS Accession No. ML 14309A256)
. The Commission issued a staff requirements memorandum on March 30, 2015 (ADAMS Accession No. ML 15089A236)
, affirming that the Commission expects licensees for operating nuclear power plants to address the reevaluated flood hazards, which are considered beyond-design-basis external events, within their mitigating strategies
. Exelon Generation Company, LLC (Exelon, the licensee) submitted its Mitigation Strategies Assessment (MSA) for the following plants: Braidwood Station, Units 1 and 2, by letter dated June 30, 2016 (ADAMS Accession No ML 16182A378)
Dresden Nuclear Power Station, Units 2 and 3, by letter dated June 30, 2016 (ADAMS Accession No. ML 16182A388)
Peach Bottom Atomic Power Station, Units 2 and 3, by letter dated June 30, 2016 (ADAMS Accession No. ML 16182A009)
Three Mile Island Nuclear Station, Unit 1, by letter dated June 29, 2016 (ADAMS Accession No. ML 16181A202)
Enclosure The NRC staff has begun its review of the aforementioned submittals and plans to conduct regulatory audits of Exelon to aid in its review of the licensee's MSAs. REGULA TORY AUDIT SCOPE AND METHODOLOGY Nuclear Energy Institute (NEI) 12-06, Revision 2, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" (ADAMS Accession No. ML 16005A625),
has been endorsed by the NRC as an appropriate methodology for licensees to perform assessments of the mitigating strategies against the reevaluated flood hazards developed in response to the March 12, 2012, 50.54(f) letter. The guidance in NEI 12-06, Revision 2, and Appendix G in particular, supports the proposed Mitigation of Beyond-Design-Basis Events rulemaking.
The endorsement, including exceptions, clarifications, and additions, is described in NRC Japan Lessons-Learned Division (JLD) interim staff guidance (ISG) JLD-ISG-2012-01, Revision 1, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML 15357A163)
. Therefore, Appendix G of NEI 12-06, Revision 2, describes acceptable methods for demonstrating that the reevaluated flooding hazard is addressed within the assessments of mitigating strategies for beyond-design-basis external events. INFORMATION AND OTHER MATERIAL NECESSARY FOR THE REGULATORY AUDIT: The areas of focus for the regulatory audit is the information contained in the MSA submittals, and all associated and relevant supporting documentation used in the development of the aforementioned document including, but not limited to, methodology, process information, calculations
, computer models, etc. NRC AUDIT TEAM: Title Team Member Affiliation Team Leader, NRR/JLD Tekia Govan NRC Branch Chief, NRR/JLD/JHMB Gregory Bowman NRC Branch Chief, NRR/JLD/JOMB Mandy Halter NRC Branch Chief, NRR/JLD/JERB Stewart Bailey NRC Branch Chief, NRR/JLD/JCBB Jessie Quichocho NRC Technical Staff, NRR/JLD Various Staff Members NRC LOGISTICS:
The audit meetings will be coordinated with Exelon staff. DELIVERABLES:
The NRC team will develop an audit summary report to convey the audit results.
The report will be placed in ADAMS within 90 days of the completion of the final audit session, and will be publicly available.
B. Hanson The information discussed in the audit may be included, fully or in part, in the development of the NRC staff's evaluation of the MSA review.
B. Hanson The enclosed audit plan outlines the process that will allow the NRC staff to identify additional information potentially necessary for licensees to supplement their MSAs, and resolve any potential technical concerns. The details of this audit have been discussed with Mr. Dave Distel of your staff. If you have any questions
, please contact me at (301) 415-6197 or by e-mail at Tekia.Govan@nrc
.gov. Sincerely
, IRA/ Tekia V. Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos.: Braidwood
- STN 50-456 and STN 50-457 Dresden: 50-237 and 50-249 Peach Bottom: 50-277 and 50-278 Three Mile Island: 50-289 Enclosure
- Audit Plan cc w/encl: Distribut ion via Listserv DISTRIBUTION
- PUBLIC JLD R/F RidsNRRJLD Resource MShams, NRR MHalter, NRR TGovan, NRR JQuichocho
, NRR RidsNrrDorlLPL 1-2 RidsNrrDorlLPL3-2 RidsNrrPMBra idwoodResou rce RidsNrrPMDresdenResource RidsNrrPMPeachBottomResource RidsNrrPMThreeMilelslandResource ADAMS Accession No.: ML16189A328 OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NAME TGovan Slent GBowman DATE 07/08/2016 07/08/2016 07/10/2016 OFFICAL RECORD COPY GBowman, NRR SBailey, NRR *via email NRR/JLD/JHMB/PM TGovan 07/12/2016