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Category:Inspection Plan
MONTHYEARML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information ML23335A0122023-12-0101 December 2023 FNP - IP95001 Inspection Notification and Request for Information (Email to Farley) ML23335A0112023-12-0101 December 2023 IP 95001 Inspection Notification and Request for Information (EA-23-080) IR 05000348/20220062023-03-0101 March 2023 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 Report 05000348/2022006 and 05000364/2022006 ML22347A0882022-12-13013 December 2022 Final Farley Pi_R Initial RFI (2023) IR 05000348/20220052022-08-24024 August 2022 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2022005 and 05000364/2022005 ML22229A4792022-08-15015 August 2022 HP Baseline Inspection Document Request ML22101A2862022-04-0101 April 2022 RQ Inspection Corporate Notification Letter IR 05000348/20210062022-03-0202 March 2022 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report No. 05000348/2021006 and 05000364/2021006) IR 05000348/20210052021-08-24024 August 2021 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2021005 and 05000364/2021005) ML20302A0002020-10-28028 October 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20175A1992020-06-23023 June 2020 Emergency Preparedness Program Inspection Request for Information ML20094H5182020-04-0303 April 2020 Plant Reference Simulator Inspection Request for Information IR 05000348/20190062020-03-0303 March 2020 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000348/2019006 and 05000364/2019006 ML19274D2092019-09-23023 September 2019 ISI Request for Information IR 05000348/20190052019-08-28028 August 2019 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Reports 05000348/2019005 and 05000364/2019005 IR 05000348/20190132019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 ML19100A0072019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 IR 05000364/20180062019-03-0404 March 2019 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000346 and 05000364/2018006 ML19063B8902019-03-0404 March 2019 ISI Sgisi 2019002 RFI - Bcc ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18360A2312018-12-21021 December 2018 Notification of Inspection and Request for Information for Nuclear Regulatory Commission Problem Identification and Resolution Inspection IR 05000348/20180052018-08-23023 August 2018 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 - NRC Inspection Reports 05000348/2018005 and 05000364/2018005 ML18094A7822018-04-0303 April 2018 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2018011 and 05000364/2018011 ML18059A1532018-02-28028 February 2018 EOC Assessment Letter ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML18053A0942018-02-22022 February 2018 Baseline In-Service Inspection Initial Information Request ISI 2018002 Rpc IR 05000348/20170052017-08-28028 August 2017 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2, NRC Report 05000348/2017005 and 05000364/2017005 ML17156A1032017-06-0202 June 2017 Notification of Inspection and Request for Information IR 05000348/20160062017-03-0101 March 2017 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2016006 and 05000364/2016006) IR 05000348/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 - NRC Inspection Report 05000348/2016005 and 05000364/2016005 ML16244A3102016-08-29029 August 2016 Notification of Inspection and Request for Information ML16062A1522016-03-0202 March 2016 Final Annual Assessment Letter ML15260A9022015-09-17017 September 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000348/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2015005 and 05000364/2015005) ML14245A1752014-09-0202 September 2014 Mid-cycle Ltr 2014 ML14121A5042014-05-0101 May 2014 Notification of Triennial Fire Protection Baseline Inspection and Request for Information IR 050000348-14-009 and 05000364-14-009 IR 05000348/20140012014-03-0404 March 2014 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2014001 and 05000364/2014001) ML14063A1442014-03-0404 March 2014 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 ML13354B9722013-12-20020 December 2013 Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007 ML13253A3662013-09-10010 September 2013 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML13246A1102013-09-0303 September 2013 Mid-Cycle Assessment Letter ML13070A4622013-03-0808 March 2013 Notification of Inspection and Request for Information IR 05000348/20120012013-03-0404 March 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2012001 and 364/2012001) ML13015A3652013-01-15015 January 2013 Emerg Prep Insp and RFI for 2-18-2013 ML12248A0472012-09-0404 September 2012 Mid Cycle Assessment Letter Farley 2012 ML1124401732011-09-0101 September 2011 Report 22 - Farley ML1106301482011-03-0404 March 2011 Report 22, Inspection/Activity Plan 01/01/2011 - 06/30/2012 ML1024407102010-09-0101 September 2010 Report 22 2024-01-30
[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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Text
October 28, 2020 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Company 3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT- NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION
Dear Ms. Gayheart:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a problem identification and resolution (PI&R) inspection at Joseph M. Farley Nuclear Plant during the weeks of February 8-12, 2021, and February 22-26, 2021. The inspection team will be led by Ms. Delza Mas-Penaranda, a Project Engineer from the NRCs Region II office. This inspection will be conducted in accordance with the baseline inspection procedure, 71152, Problem Identification and Resolution, issued February 26, 2015.
The biennial PI&R inspection and assessment of the licensees Corrective Action Program (CAP) complements and expands upon the resident baseline inspections of routine daily screening of all corrective action program issues, quarterly focused issue reviews, and semiannual trend PI&R reviews.
On October 26, 2020, Ms. Mas-Penaranda confirmed with Mr. Gene Surber, Licensing Manager, the details and expectations for the two weeks of the inspection.
The enclosure lists documents that will be needed prior to the inspection. Please have the referenced information available no later than January 11, 2021. Contact Ms. Mas-Penaranda with any questions concerning the requested information. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation.
If additional documents are needed, they will be requested when identified. Prior to the inspection, Ms. Mas-Penaranda will discuss, with your staff, the following inspection support administrative details: availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; method of tracking inspector requests during the inspection; and other applicable information.
C. Gayheart 2 In response to the COVID-19 coronavirus and updated Federal Government guidance on travel and social distancing, the NRC inspection team is prepared to conduct this inspection accordingly. Therefore, in support of this inspection some, or all, of the inspection team may perform their reviews with minimal onsite staff interaction or remotely as conditions permit.
The NRC inspection team requests that your staff be prepared to support these efforts. Additionally, the inspection team is open to any suggestions regarding communications and coordination such that the overall effort from both the NRC inspection team and Joseph M.
Farley Nuclear Plant support staff may be the most efficient while also prioritizing public health and safety.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Ms. Delza Mas-Penaranda at (404) 997-4504.
Sincerely,
/RA/
Alan Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket No. 05000348 and 05000364 License No. NPF-2, NPF-8
Enclosure:
Information Request for Joseph M. Farley Nuclear Plant Problem Identification and Resolution Inspections cc Distribution via ListServ
C. Gayheart 3
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT- NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION DATED: October 28, 2020 DISTRIBUTION:
RIDSNRRDRO PUBLIC RidsNrrPmFarley Resource ACCESSION NUMBER: ML20302A000 OFFICE RII/DRP RII/DRP NAME D. Mas-Penaranda A. Blamey DATE 10/26/2020 10/28/2020
INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (February 8-12, 2021 AND February 22-26, 2020)
Note: Unless otherwise noted, the information requested below corresponds to documents generated since January 1, 2019. Please provide the requested documents in electronic format. If the information is not available in electronic format, please contact the inspection team leader to coordinate other available methods to provide the information.
- 1. Copies of the corporate and site level procedures and sub-tier procedures associated with the corrective action program. This should include procedures related to:
a) Corrective action process b) Cause evaluation c) Operating experience program d) Employee concerns program e) Self-assessment program f) Maintenance rule program and implementing procedures g) Operability determination and functionality assessment process h) Degraded/non-conforming condition process (e.g., RIS 2005-20) i) System health process or equivalent equipment reliability improvement programs j) Preventive maintenance deferral process If any of the procedures requested above were revised after January 1, 2019, please provide copies of all revisions during the onsite inspection.
- 2. List of top ten risk-significant systems, top ten risk-significant components for each one of the top ten risk-significant systems, and top ten risk-significant operator manual actions.
- 3. List of all Condition Reports (CRs) initiated including the following information for each CR:
a) CR number b) Brief, but complete problem description c) Priority or level d) Affected system e) Affected component f) Responsible plant department g) CR completion status If possible, provide this list in a format compatible with spreadsheet software (i.e. Excel example shown below) and ensure the list is searchable and can be filtered by system.
AR # Problem Priority System Component Org Status CR001 A RHR Pump 2 RHR 2-RHR- ENG Open failed flow criteria PMP-A per SR 5.0.5.4 Enclosure
- 4. List of outstanding corrective actions including the following information for each action:
a) Corrective action number b) Corrective action type (e.g., corrective action to prevent recurrence, enhancement, maintenance rule evaluation, etc.)
c) Brief, but complete corrective action description d) Associated CR number e) Corrective action initiation date f) Number of extensions g) Corrective action due date h) Completion status If possible, provide this list in a format compatible with spreadsheet software (i.e. Excel, example shown below) and ensure the list is searchable and can be filtered by system.
Correctiv Type Description AR Syste Initiatio Extension Due Status e Action m n Date s Date 001 CAP Revise CR005 RHR 03/05/20 2 09/15/20 Awaitin R Procedure 8 g NGK-003- CARB 4585 review
- 5. List of control room deficiencies with a brief description and corresponding CR and/or work order (WO) number.
- 6. List of operator workarounds and operator burdens with a brief description and corresponding CR number, searchable and filtered by system.
- 7. List of all currently extended or overdue CRs, searchable and filtered by system and sorted by initiation date, with the following information:
a) CR number b) Priority or Significance c) CR title and short description
- 8. List of all CRs that have been voided, cancelled, or deleted, searchable and filtered by system. Please provide the following information for each CR:
a) CR number b) Brief, but complete problem description c) Reason voided, cancelled, or deleted
- 9. List of all structures, systems, and components (SSCs) which were classified as (a)(1) in accordance with the Maintenance Rule since January 2019. Please include the following information for each system in (a)(1):
a) Date of classification in (a)(1) b) Reason for being placed in (a)(1) c) Planned actions and their status
- 10. List of Maintenance Preventable Functional Failures (MPFF) of risk-significant systems.
Please include actions completed and current status.
- 11. List of corrective maintenance work orders and modifications for safety-related (SR) structures, systems, and components and any work considered high risk. Please include the following information for each work order:
a) WO number b) Brief, but complete work description c) Affected system and components d) Date of initiation e) Date of completion (if completed) f) Associated CR (if applicable)
If possible, provide this list in a format compatible with spreadsheet software (i.e. Excel, example shown below) and ensure the list is searchable and can be filtered by system.
Work Description System Component Initiation Due Status Order # Date Date WO01345 Replace breaker SI 2A-SI-PMP, 01/05/19 05/15/19 Closed 2A-BKR-08-BB4 BKR-08-BB4 for 2A SI Pump.
- 12. Corrective action closeout packages, including CRs with description of corrective actions, for all NRC findings and licensee-identified violations (LIVs). Please include a cross-reference linking NRC finding numbers and LIVs to appropriate CR numbers.
- 13. Corrective action closeout packages, including CRs with description of corrective actions, for all licensee event reports (LERs) issued. Please include a cross reference linking LER number to appropriate CR number.
- 14. List of all NRC generic communications (e.g., Information Notices, Generic Letters, etc.) and industry operating experience (OE) documents (e.g., Part 21 reports, vendor information letters, information from other sites, etc.) evaluated by the site for applicability to the station, regardless of the determination of applicability. Please include the reference number (e.g.,
CR number) for the documents that evaluated the aforementioned OE information.
- 15. Copies of all quality assurance audits and/or assessments issued, including the last two audits/assessments of the corrective action program.
- 16. Copies of all department self-assessments.
- 17. Copy of the most recent integrated plant trend report, departmental trend report(s), and corrective action trend reports, including any human performance and equipment reliability trends.
- 18. Copy of the latest Corrective Action Program statistics (if already compiled) such as the number of CRs initiated by department, human performance errors by department, and others as may be available.
- 19. List of routine meetings involving the CAP to be held while team is onsite.
- 20. List of CRs related to equipment aging issues in the top ten risk-significant systems since January 2019 (e.g., system erosion and/or corrosion problems; electronic component aging or obsolescence of circuit boards, power supplies, relays, etc.; environmental qualification).
Please provide the following information for each AR:
a) CR number b) Priority c) CR problem description
- 21. If performed, please provide any recent self-assessment of the site safety culture completed.
- 22. Copies of corrective action program documents related to cross-cutting issues (human performance, problem identification and resolution, and safety conscious work environment) identified via trending, self-assessments, safety review committee or other oversight methods
- 23. List of all root cause, apparent cause, common cause and related or similar equipment cause evaluations with a brief description.
- 24. Copy of Probabilistic Risk Assessment importance measures report, if available.
- 25. System health reports, system design basis documents, maintenance rule functions and status, and system description information for the top ten risk significant systems.