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Category:Inspection Plan
MONTHYEARML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24087A1822024-03-28028 March 2024 Notification of Target Set Inspection and Request for Information NRC Inspection Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24052A1472024-02-28028 February 2024 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 IR 05000259/20220062023-03-0101 March 2023 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006 ML23020A0602023-01-20020 January 2023 Long Term Steam Dryer Inspection Plan IR 05000259/20220052022-08-30030 August 2022 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022005, 05000260/2022005 and 05000296/2022005 ML22210A1342022-07-20020 July 2022 Requalification Inspection Notification Letter ML22174A2722022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000259/20224012022-03-0808 March 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000259/2022401; 05000260/2022401; 05000296/2022401 ML22091A1942022-03-0808 March 2022 2022 BFN POV Inspection Information Request IR 05000259/20210062022-03-0202 March 2022 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 (Report No. 05000259/2021006, 05000260/2021006 and 05000296/2021006 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections ML21343A4232021-12-0909 December 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI) IR 05000259/20210052021-08-23023 August 2021 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3- Report Nos. 05000259/2021005, 05000260/2021005 and 5000296/2021005 IR 05000259/20200062021-03-0303 March 2021 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020006, 05000260/2020006 and 05000296/2020006 ML21047A4732021-02-16016 February 2021 Notification of Browns Ferry Nuclear Power Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2021010, 05000260/2021010, and 05000296/2021010 ML20338A3682020-12-0303 December 2020 Notification of Inspection and Request for Information ML20266G4472020-09-22022 September 2020 Notification of Inspection and Request for Information IR 05000259/20200052020-08-18018 August 2020 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020005, 05000260/2020005, and 05000296/2020005 ML20191A2232020-07-0909 July 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000259/20190062020-03-0303 March 2020 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1,2,and 3 - NRC Report 05000259/2019006, 05000260/2019006, and 05000296/2019006 ML19108A1682019-04-18018 April 2019 EP Exercise Inspection RFI IR 05000259/20180062019-03-0404 March 2019 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2018006, 05000260/2018006 and 05000328/2018006 ML19030A6712019-01-25025 January 2019 U2 ISI RFI ML19024A4112019-01-24024 January 2019 Transmittal of RP Baseline Inspection Document Request 2019 ML18264A2052018-09-21021 September 2018 U1 ISI Emailed RFI Notification ML18059A1052018-02-28028 February 2018 EOC Assessment Letter ML18029A4672018-01-29029 January 2018 Notification of Browns Ferry Nuclear Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2018010, 05000260/2018010, and 05000296/2018010 ML18029A2552018-01-29029 January 2018 U3 RFI Email Request ML17236A1972017-08-24024 August 2017 Updated Inspection Plan ML17156A1612017-06-0202 June 2017 Notification of Inspection and Request for Information IR 05000259/20160062017-03-0101 March 2017 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Report 05000259/2016006, 05000260/2016006 and 05000296/2016006) IR 05000259/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3, NRC Inspection Reports 05000259/2016005, 05000260/2016005 and 05000296/2016005 ML16243A2242016-08-30030 August 2016 Notification of Inspection and Request for Information ML16120A1182016-04-27027 April 2016 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000259/2016011, 05000260/2016011 and 05000296/2016011 IR 05000259/20150062016-03-0202 March 2016 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 NRC Inspection Reports 05000259/2015006, 05000260/2015006 and 05000296/2015006 ML16013A0812016-01-12012 January 2016 Browns Ferry Nuclear Plant, Unit 3 - Notification of Inspection and Request for Information ML15348A1802015-12-14014 December 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000259/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for the Browns Ferry Nuclear Plant Units 1, 2 and 3, NRC Inspection Report 005000259/2015005, 005000260/2015005, and 005000296/2015005 IR 05000259/20140012015-03-0404 March 2015 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 - NRC Inspection Reports 05000259/2014001, 05000260/2014001 and 05000296/2014001 IR 05000259/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 (NRC Inspection Reports 05000259/2014006, 05000260/2014006 and 05000296/2014006) ML14063A1092014-03-0404 March 2014 2013 Annual Assessment Letter for Browns Ferry ML14031A4122014-01-31031 January 2014 U3 2014002 ISI RFI Final - Copy ML13353A5852013-12-19019 December 2013 PIR Notification Letter 2014 ML13246A1842013-09-0303 September 2013 Mid Cycle Assessment Letter ML13084A0052013-03-25025 March 2013 Emergency Preparedness Inspection Notification and Request for Information 2024-09-24
[Table view] Category:Letter
MONTHYEARML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision 05000296/LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator2024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-03
[Table view] |
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Jim Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION
Dear Jim Barstow:
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 your Browns Ferry Nuclear Plant, Units 1,2, and 3 during the weeks of November 4 - 8, and November 18 - 22, 2024. The inspection team will be led by Kevin Pfeil, Resident Inspect at Browns Ferry Nuclear Plant. This inspection will be conducted in accordance with the baseline inspection procedure, Procedure 71152, Problem Identification and Resolution, issued on October 31, 2023.
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 August 8, 2024, Kevin Pfeil confirmed with member of your staff, William Webster, Browns Ferry team lead, arrangements for the two-week onsite inspection and the one-day pre-inspection visit.
The enclosure lists documents that will be needed prior to the inspection. Please, provide the referenced information no later than October 7, 2024; and contact Kevin Pfeil with any questions concerning the requested information. The inspectors have worked to minimize your administrative burden by specifically identifying documents necessary for inspection preparation.
If additional documents are required, they will be requested as needed. Prior to the onsite inspection, Kevin Pfeil will discuss with your staff inspection support administrative details including 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; access to licensee computers; working space; arrangements for site access; and other applicable information.August 16, 2024 J. Barstow 2 In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website 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 Kevin Pfeil at (518) 229-8021.
Sincerely, Louis J. McKown, II, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos.: 05000259, 05000260, and 05000296 License Nos.: DPR-33, DPR-52, and DPR-68
Enclosure:
Information Request for Browns Ferry Nuclear Plant Problem Identification & Resolution Inspection cc: w/ Encl: via Listserv Signed by McKown, Louis on 08/16/24
J. Barstow 3
PAPERWORK REDUCTION ACT STATEMENT
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011.
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
ML24225A168 X SUNSI Review X Non-Sensitive X Publicly Available Sensitive Non-Publicly Available
OFFICE RII/DRP RII/DRP NAME K. Pfeil L. McKown DATE 8/16/2024 8/16/2024 INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION November 4th-8th and November 18th-22nd
Note: Unless otherwise noted, the information requested below corresponds to documents generated since July 11, 2022. 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) Operability determination process d) Operating experience program e) 10 CFR Part 21 and programs for reporting defects and non-compliance f) Employee concerns program g) Self-assessment program h) Maintenance rule program and implementing procedures i) System health process or equivalent equipment reliability improvement programs j) Quality assurance program
If any of the procedures requested above were revised after August 8, please provide (or have available) 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; and a copy of the probabilistic risk assessment importance measures report, if available. Please provide by September 16, 2024.
- 3. List of all Condition Reports (CRs) initiated including the following information or each CR:
a) CR number b) Brief, but complete problem description c) Affected system d) Affected component e) Responsible plant department f) CR completion status g) CAQ characterization
Provide this list in a format compatible with spreadsheet software (example shown below) and ensure the list is searchable and can be filtered by system and organization.
CR # Subject Description System Component Org CAP/ Status Not CAP 02351551 A RHR Pump Should include initial description RHR 2-RHR-PMP-A ENG CAP APPROVED failed flow criteria section from NCR entry per SR 5.0.5.4
- 4. List of outstanding corrective actions including the following information for each action:
Enclosure 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
Provide this list in a format compatible with spreadsheet software (example shown below) and ensure the list is searchable and can be filtered by system and organization.
Corrective Type Description CR Initiation Extensions Due Status Action # Date Date AR0034 CAPR Revise CR0058 01/05/12 2 06/15/12 Awaiting Procedure CARB NGK-003-4585 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
- 7. List of all prompt operability determinations or other engineering evaluations to provide reasonable assurance of operability; if fewer than approximately 20, provide full CR package.
- 8. List of all CRs that have been voided, cancelled, or deleted. Please provide the following information for each CR:
a) CR number b) Brief, but complete problem description c) Affected system d) Responsible organization e) CAP characterization f) 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. 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 d) Copy of evaluations
- 10. List of Maintenance Preventable Functional Failures (MPFF) of risk significant systems with actions completed and current status, and associated CR(s).
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- 11. List of corrective and deficient maintenance WOs and WRs for safety-related (SR) structures, systems, and components and any condition considered a condition adverse to quality. Please include the following information for each:
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) g) Priority h) Status (e.g., open/closed) i) CAQ characterization
Provide this list in a format compatible with spreadsheet software (example shown below) and ensure the list is searchable and can be filtered by system.
WR/WO # Description System Component Initiation Due Date CAQ Priority Status Date
WO01345 Replace breaker 2A-SI 2A-SI-PMP, 01/05/11 03/15/22 Yes 3 Closed 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). Include a cross reference linking NRC finding tracking 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. 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. Include the reference number (e.g., CR number) for the documents that evaluated the associated 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 report, including any human performance and equipment reliability trends.
- 18. If performed, provide all self-assessments of the site safety culture completed within the last two years.
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- 19. 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.
- 20. Contact information and availability during inspection period for Employee Concerns Program representative on site.
- 21. Copy of the latest CAP statistics (if exists) such as the number of CRs initiated by department, human performance errors by department, and others as may be available.
- 22. List of routine meetings and agendas involving the CAP (including but not limited to CAP screening, maintenance rule, operating experience, new work screening team, operations focus, management review, challenge, etc.,) to be held during the inspection period.
- 23. Five-year Review: List of CRs related to equipment aging issues in the top ten risk significant systems since November 2019 (e.g., system erosion and/or corrosion problems; electronic component aging or obsolescence of circuit boards, power supplies, relays, etc.;
environmental qualification). Provide the following information for each CR, in a format compatible with spreadsheet software and ensure the list is sortable and searchable:
a) CR number b) CR problem description c) Affected system d) Affected component e) Responsible organization f) CAP characterization g) Status
- 24. List of all root cause, apparent cause, common cause and related or similar equipment cause evaluations with a brief description.
- 25. System health reports, system design basis documents, maintenance rule functions and status, and system description information for top ten risk significant systems OR upon notification of system selections.
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