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MONTHYEARNL-18-0039, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ...2018-07-27027 July 2018 License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ... Project stage: Request ML18243A4062018-08-31031 August 2018 Acceptance of Licensing Action Regarding Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b Project stage: Acceptance Review ML18290B0942018-10-16016 October 2018 October 16, 2018, Public Meeting Presentation Slides Related to July 27, 2018, License Amendment Request to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b. Project stage: Meeting ML18306A3132018-11-0707 November 2018 Summary of October 16, 2018, Meeting with Southern Nuclear Operating Company, Inc., to Discuss the Joseph M. Farley Unit 1 & 2, Electrical Distribution System as It Relates to the Risk-Informed Completion Times Amendment Project stage: Meeting ML18338A0052019-01-0404 January 2019 Regulatory Audit in Support of the License Amendment Request to Implement Risk-Informed Technical Specifications Initiative 4B Project stage: Acceptance Review ML19042A1082019-02-26026 February 2019 Audit Summary in Support of the License Amendment Request to Implement Risk-Informed Technical Specifications Initiative 4B Project stage: Other ML19072A0272019-03-12012 March 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4B Project stage: Acceptance Review NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)2019-05-0303 May 2019 Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI) Project stage: Response to RAI NL-19-0623, Significant Hazards Evaluation and Environmental Considerations for Farley Risk Informed Technical Specifications Response to Request for Additional Information2019-05-17017 May 2019 Significant Hazards Evaluation and Environmental Considerations for Farley Risk Informed Technical Specifications Response to Request for Additional Information Project stage: Response to RAI NL-19-0771, Risk Informed Technical Specification Information Only Bases Changes2019-06-27027 June 2019 Risk Informed Technical Specification Information Only Bases Changes Project stage: Request ML19175A2432019-08-23023 August 2019 Issuance of Amendments 225 and 222 Implementation of NEI 06-09, Risk-Informed Technical Specifications Initiative 4B, Risk-Managed Technical Specification (Rmts) Guidelines, Revision 0-A Project stage: Approval NL-22-0091, Correction of Technical Specification Typographical Omission2022-02-24024 February 2022 Correction of Technical Specification Typographical Omission Project stage: Request ML22060A1892022-03-15015 March 2022 Correction to TS Pg 3.6.6-4 During Issuance of Amendment Nos. 225 and 222 Project stage: Approval 2019-03-12
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Category:Audit Report
MONTHYEARML21260A1612021-09-24024 September 2021 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML20115E4532020-05-0101 May 2020 Audit Summary in Support of the License Amendment Request Technical Specification (TS) 3.3.7 ML19042A1082019-02-26026 February 2019 Audit Summary in Support of the License Amendment Request to Implement Risk-Informed Technical Specifications Initiative 4B ML16014A7342016-02-0808 February 2016 Report for the Audit Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 ML13337A5842014-01-17017 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML0832900802008-12-0505 December 2008 Audit of Licensee'S Management of Regulatory Commitments ML0515700752005-06-0909 June 2005 Audit of the Licensee'S Management of Regulatory Commitments ML0425402772004-09-10010 September 2004 Audit and Review Report for Plant Aging Management Reviews and Programs for the Joseph M. Farley Nuclear Plant, Units 1 and 2. 2021-09-24
[Table view] Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 2024-01-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 26, 2019 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - AUDIT
SUMMARY
IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT RISK-INFORMED TECHNICAL SPECIFICATIONS INITIATIVE 48 (EPID L-2018-LLA-0210)
Dear Ms. Gayheart:
By letter dated July 27, 2018, Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019.
The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information.
The audit summary report is provided as an enclosure to this letter.
C. Gayheart If you have any questions, please contact me at 301-415-1009 or via e-mail at Shawn.Williams@nrc.gov.
Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch II 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
- 1. Audit Summary cc: Listserv
FEBRUARY 5-7, 2019, AUDIT
SUMMARY
LICENSE AMENDMENT REQUEST TO ADOPT NEI 06-09, REVISION 0-A RISK-INFORMED COMPLETION TIMES SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364
1.0 INTRODUCTION
By letter dated July 27, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18208A619), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) to implement changes to their technical specifications program that establishes a risk-informed approach for voluntary extension of completion times for Limiting Conditions of Operations based on the Nuclear Energy Institute (NEI) 06-09 methodology, "Risk-Informed Technical Specification Initiative 4b Risk-Managed Technical Specification (RMTS) Guidelines," Revision 0-A, for Joseph M. Farley Nuclear Plant, Units 1 and 2.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the licensing review process. The NRC staff issued the regulatory audit plan on January 4, 2019 (ADAMS Accession No. ML18338A005) that included 26 questions to be discussed during the audit.
The NRC staff conducted the regulatory audit on February 5-7, 2019, at the SNC corporate office in Birmingham, Alabama. The results of the regulatory audit will be used by the NRC staff to finalize requests for additional information (RAls).
The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195).
2.0 AUDIT ACTIVITIES AND OBSERVATIONS The purpose of the audit was to understand the calculations, analyses, and bases for the LAR, and to develop requests for additional information, as needed. NRC staff discussions with SNC focused on internal events and fire probabilistic risk assessment (PRA) quality, PRA functionality, implementation of the risk informed completion time (RICT) program, TS limiting conditions for operation, and associated RICT program guidance documents. SNC provided a demonstration of how it would implement the RICT. The NRC staff reviewed applicable program documents.
The following are the specific presentation and discussion topics discussed during the audit:
- SNC Presentation of Electrical Systems Modeled in the PRA (Question 25)
- Configuration Risk Management Program (CRMP) Tool Overview Enclosure
- SNC Presentation of Responses to Questions 12, 19, 20, 21 and 24 (LAR/TS)
- Loss of Function Discussion and SNC response to Questions 13, 15, 16, and 18
- External Hazards Discussion and SNC response to Question 11
- SNC Presentation of PRA Functional Definition, Development and Use
- SNC responses to Questions 14, 17, 22, and 23 (PRA Functionality)
- Presentation of Risk Management Actions (RMAs) Determinations /Examples (plus SNC response to 026)
- Detailed CRMP Presentation
- PRA Quality Discussion and SNC responses to Questions 1, 2, 3, 6, 8, 10
- SNC responses to Questions 4 and 5 (PRA Modeling)
- SNC responses to Questions 7 and 9 (Uncertainties)
Audit Exit:
NRC staff went through each question/discussion topic in the Audit plan, and shared preliminary thoughts on any changes to the original set of questions/discussion topics. There were no regulatory decisions made regarding the final set of questions. NRC staff stated that they planned to issue a formal RAI within 30 days of the Audit.
4.0 AUDIT PARTICIPANTS NRC
Participants:
- Shawn Williams, Project Manager, Office of Nuclear Reactor Regulation (NRR), Division of Reactor Licensing (DORL)
- Candace De Messieres, NRR, APLA
- Gurcharan Matharu, NRR, Division of Engineering (DE), Electrical Engineering Operating Reactors Branch (EEOB)
- Victor Cusumano, NRR, Division of Safety Systems (DSS), Branch Chief Technical Specifications Branch (STSB)
- Garill Coles, PNNL (Contractor)
SNC
Participants:
5.0 DOCUMENTS REVIEWED The following documents were available on the Farley Portal, and reviewed by NRC and PNNL staff.
- 1. SNC Calculation PRA-BC-F-17-002, "Seismic Risk Evaluation based on IPEEE and EPRI 2014 Farley Seismic Hazard," Version 1 (Reference 6 of Enclosure 4 to NL-18-0039), and
- 2. "Joseph M. Farley Nuclear Plant Units 1 and 2, Evaluation of Other External Hazards,"
Southern Nuclear PRA Report, Revision 0, December 31, 2013 (Reference A.2-2 of Enclosure 3 to NL-18-0039).
- 3. Draft Responses to the Audit Questions.
- 4. F-RIE-FIREPRA-U00-014, Fire PRA Quantification and Summary Report, Revision 1
- 5. F-RIE-IEIF-U00-01, Internal Events and Internal Flooding and LERF Model Update" Revision 10, Version 2.0.
- 6. F-RIE-IEIF-U00-013, Characterizing the Sources of Model Uncertainty for Farley Nuclear Plant
- 7. 05058-RPT-011, Farley Fire PRA Uncertainty Analysis, Revision 2
- 8. NMP-GM-031-003, Risk Management Actions for RICT Program, Version 4.0
- 9. NMP-GM-031-002, Calculation of RMAT and RICT for the RICT Program, Version 3.1
- 10. NMP-GM-031-004, PRA Functionality Determination
- 11. FNP-O-SOP-0.13, Recording Limiting Conditions for Operation
- 12. SNCF-00358-REPT-001, Farley Internal Events F&O Closure Review (ENERCON)
- 13. F-FIE-FIREPAR U00-014, Internal Events PRA Uncertainty Analysis
- 14. FNP-O-AOP-21.0, Severe Weather Abnormal Operating Procedure
- 15. SNCF-00355-REPT-001, Farley Fire PRA Focused-Scope Peer Review, July 2018 (ENERCON)
- 16. R-401292913-255, Farley Fire PRA Focused-Scope Peer Review, January 2018 (ABS Consulting)
ML19042A108 *via E-mail OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1 /LA NRR/DE/APLA/BC* NRR/DORL/LPL2-1/BC NAME SWilliams KGoldstein MWentzel MMarkley DATE 02/22/19 02/14/19 02/22/19 02/26/19 OFFICE NRR/DORL/LPL2-1 /PM NAME SWilliams DATE 02/26/19