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| 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. | | 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. |
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| ML17107A260 OFFICE RII:DRP RII:DRP RII:DRP NAME SSeaton RTaylor PMcKenna DATE 4/17/2017 4/17/2017 4/17/2017 | | ML17107A260 OFFICE RII:DRP RII:DRP RII:DRP NAME SSeaton RTaylor PMcKenna DATE 4/17/2017 4/17/2017 4/17/2017 INFORMATION REQUEST FOR SEQUOYAH NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (JUNE 5 - 9 AND JUNE 19 - 23, 2017) |
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| INFORMATION REQUEST FOR SEQUOYAH NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (JUNE 5 - 9 AND JUNE 19 - 23, 2017) | |
| Note: Unless otherwise noted, the information requested below corresponds to documents generated since June 25, 2015. Please provide the requested documents in electronic format. | | Note: Unless otherwise noted, the information requested below corresponds to documents generated since June 25, 2015. 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. | | If the information is not available in electronic format, please contact the inspection team leader to coordinate other available methods to provide the information. |
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Category:Inspection Plan
MONTHYEARML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24059A4052024-02-28028 February 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-02 IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 IR 05000327/20220062023-03-0101 March 2023 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2022006 and 05000328/2022006 ML23026A0282023-01-12012 January 2023 001 Radiation Safety Baseline Inspection Information Request IR 05000327/20220052022-08-30030 August 2022 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327 2022005 and 05000328 2022005 - Final IR 05000327/20210062022-03-0202 March 2022 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - (Report No. 05000327/2021006 and 05000328/2021006) ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information IR 05000327/20200052020-08-18018 August 2020 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020005 and 05000328/2020005 ML20227A0082020-08-14014 August 2020 Requalification Program Inspection - Sequoyah Nuclear Plant ML19324E9992019-11-20020 November 2019 2020 SQN - POV Inspection Information Request - Rev. 1 ML19235A1972019-08-23023 August 2019 ISI 2019004 RFI Ajb ML19063D0842019-03-0404 March 2019 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2018006 and 05000328/2018006 IR 05000327/20180062019-03-0404 March 2019 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2018006 and 05000328/2018006 ML18283A6232018-09-25025 September 2018 04 RP Inspection Document Request ML18240A3602018-08-24024 August 2018 Requalification Program Inspection ML18172A1182018-06-21021 June 2018 Notification of Inspection and Request for Information ML18059A1432018-02-28028 February 2018 EOC Assessment Letter ML18058B1632018-02-27027 February 2018 Emailed U1 ISI 2018002 RFI - Bcc IR 05000327/20170052017-08-24024 August 2017 Updated Inspection Plan for Sequoyah Updated Inspection Plant Units 1 and 2, Report 05000327/2017005 and 05000328/2017005 ML17146A1002017-05-25025 May 2017 Notification of Inspection and Request for Documents Dated May 25, 2017 ML17107A2602017-04-17017 April 2017 Notification of Inspection and Request for Information for NRC PI&R ML17115A4452017-04-17017 April 2017 Emergency Preparedness Inspection and Request for Information ML17067A4792017-03-0707 March 2017 Notification of Inspection and Request for Documents IR 05000327/20160062017-03-0101 March 2017 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 & 2 (Report 05000327/2016006 and 05000328/2016006) ML16286A0622016-10-0606 October 2016 Notification of Inspection and Request for Information IR 05000327/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 05000327/2016005, 05000328/2016005 ML16076A0612016-03-15015 March 2016 Notification of Sequoyah Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 05000327/2016007, 05000328/2016007 ML16062A2622016-03-0202 March 2016 Annual Assessment Letter IR 05000327/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for the Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 005000327/2015005, 005000328/2015005 ML15084A4022015-03-25025 March 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000327/20140012015-03-0404 March 2015 Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 05000327/2014001, 05000328/2014001 IR 05000327/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003 ML14245A1212014-09-0202 September 2014 Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003 ML14072A0352014-03-10010 March 2014 Notification of Inspection and Request for Information ML14063A2472014-03-0404 March 2014 2013 Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2 ML13297A0732013-10-23023 October 2013 IR 05000327-14-007 & 05000328-14-007.Sequoyah Nuclear Plant, Units 1 & 2, Notification of a Triennial Fire Protection Baseline Inspection ML13246A1952013-09-0303 September 2013 Mid Cycle Assessment Letter IR 05000327/20120012013-03-0404 March 2013 Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2 (Report 05000327/2012001 and 05000328/2012001) ML12248A1042012-09-0404 September 2012 Mid Cycle Assessment Letter Sequoyah 2012 IR 05000327/20120062012-09-0404 September 2012 Mid Cycle Assessment Letter Sequoyah 2012 ML12065A3292012-03-0505 March 2012 RPT 22, Inspection/Activity Plan IR 05000382/20120012012-03-0505 March 2012 Annual Assessment Letter for Waterford Steam Electric Station-Unit 3 (Report 05000382-12-001) ML1124401842011-09-0101 September 2011 Inspection/Activity Report 22, 09/01/2011 - 12/31/2012 ML1106303542011-03-0404 March 2011 Inspection / Activity Plan, Report 22 ML1024408442010-09-0101 September 2010 Report 22 Inspection/Activity Plan 09/01/2010 - 12/31/2011 ML1006209872010-03-0303 March 2010 Inspection/Activity Plan 03/01/2010 - 06/30/2011 ML0924406512009-09-0101 September 2009 Inspection/Activity Plan 03/01/2009 - 12/31/2010 2024-05-31
[Table view] Category:Letter
MONTHYEARML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report 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 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip 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 CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems 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 ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation 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 ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report 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 ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N 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) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report 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 ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period 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 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update 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 IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 ML24100A0162024-04-11011 April 2024 Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements 2024-09-08
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 April 17, 2017 Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION
Dear Mr. Shea:
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 Sequoyah Nuclear Plant during the weeks of June 5 - 9 and June 19 - 23, 2017. The inspection team will be led by Shani Seaton, a Project Engineer from the NRCs Region II office.
This inspection will be conducted in accordance with the baseline inspection procedure, Procedure 71152, Problem Identification and Resolution, issued on 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 April 13, 2017, Mrs. Seaton confirmed with Mr. Scott Bowman of your staff, arrangements for the two-week onsite inspection and a one day pre-inspection visit.
The enclosure lists documents that will be needed prior to the inspection. Please have the referenced information available no later than May 17, 2017. Contact Mrs. Seaton 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 onsite inspection, Mrs. Seaton 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; access to licensee computers; working space; arrangements for site access; and other applicable information.
J. Shea 2 In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure 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 Mrs. Seaton at (404) 997-4461.
Sincerely,
/RA/
Philip McKenna, Acting Chief Reactor Projects Branch 7 Division of Reactor Projects Docket Nos.: 50-327, 50-328 License Nos.: DPR-77, DPR-79
Enclosure:
Information Request for Sequoyah Nuclear Plant Problem Identification and Resolution Inspection cc Distribution via Listserv 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.
ML17107A260 OFFICE RII:DRP RII:DRP RII:DRP NAME SSeaton RTaylor PMcKenna DATE 4/17/2017 4/17/2017 4/17/2017 INFORMATION REQUEST FOR SEQUOYAH NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (JUNE 5 - 9 AND JUNE 19 - 23, 2017)
Note: Unless otherwise noted, the information requested below corresponds to documents generated since June 25, 2015. 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 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 and Condition Report (PER) extension process If any of the procedures requested above were revised after June 25, 2015, please provide (or have available) copies of all revisions during the onsite inspection.
- 2. List of the top ten risk-significant systems, the top ten risk-significant components for each one of the top ten risk-significant systems, and the top ten risk-significant operator manual actions
- 3. List of all PERs initiated, including the following information for each PER:
a) PER number b) Brief, but complete problem description c) Priority or level d) Affected system e) Affected component f) Responsible plant department g) PER completion status If possible, provide this list in a format compatible with spreadsheet software (example shown below).
PER # Problem Priority System Component Org Status PERXXX A RHR Pump 2 RHR 2-RHR- ENG Open failed flow criteria PMP-A per SR 5.0.5.4 Enclosure
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- 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 PER 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 (example shown below).
Corrective Type Description PER Initiation Extensions Due Status Action # Date Date PERXXX CAPR Revise PERXX 03/05/11 2 4/15/11 Awaiting Procedure X CARB NGK-003-4585 Review
- 5. List of control room deficiencies with a brief description and corresponding PER and/or work order (WO) number
- 6. List of operator workarounds and operator burdens with a brief description and corresponding PER number
- 7. List of all currently extended or overdue PERs, sorted by initiation date, with the following information:
a) PER number b) Priority or Significance c) PER title and short description
- 8. List of all PERs that have been voided, cancelled, or deleted. Please provide the following information for each PER:
a) PER 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 June 25, 2015. 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
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- 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. 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)
If possible, provide this list in a format compatible with spreadsheet software (example shown below).
Work Description System Component Initiation Due Status Order # Date Date WO01345 Replace breaker SI 2A-SI-PMP, 01/05/11 03/15/11 Closed 2A-BKR-08-BB4 BKR-08-BB4 for 2A SI Pump.
- 12. Corrective action closeout packages, including PERs with description of corrective actions, for all NRC findings and Licensee identified violations.
- 13. Corrective action closeout packages, including PERs with description of corrective actions, for all licensee event reports (LERs) issued.
- 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., PER 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 for those programs related to the Corrective Action Program (e.g. Operating Experience, Maintenance Rule, etc.)
- 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. Copy of the latest Corrective Action Program statistics (if they exist) such as the number of PERs initiated by department, human performance errors by department, and others as may be available
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- 19. Copies of any minutes of meetings by the offsite safety review boards/groups. In addition, please provide a list of routine meetings involving the CAP to be held while team is onsite.
- 20. List of PERs related to equipment aging issues in the top ten risk significant systems since June 25, 2015 (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 PER:
a) PER number b) Priority c) PER problem description
- 21. If performed, please provide any recent self-assessment of the site safety culture.
- 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 evaluations with a brief description
- 24. Copy of Probabilistic Risk Assessment importance measures report, if available
- 25. System Health Reports, system design basis documents, and system description information for the top ten risk significant systems