ML20191A223

Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection

ML20191A223
Person / Time
Site:	Browns Ferry
Issue date:	07/09/2020
From:	Tom Stephen NRC/RGN-II/DRP/RPB5
To:	Jim Barstow Tennessee Valley Authority
References
Download: ML20191A223 (7)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 July 9, 2020 Mr. James 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 UNITS 1, 2, AND 3 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION

Dear Mr. 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 August 24-28, 2020 and September 14-18, 2020. The inspection team will be led by Mr. Jeff Hamman, Resident Inspector, Watts Bar Nuclear Plant, 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 CAP issues, quarterly focused issue reviews, and semiannual trend PI&R reviews.

On July 8, 2020, Mr. Hamman confirmed, with Mr. Jamie Paul of the Tennessee Valley Authority (TVA), the arrangements for the two-week onsite inspection.

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 TVA support staff may be the most efficient while also prioritizing public health and safety.

The enclosure lists documents that will be needed prior to the inspection. Please have the referenced information available no later than July 24, 2020. Contact Mr. Hamman 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.

J. Barstow 2 If additional documents are needed, they will be requested when identified. Prior to the inspection, Mr. Hamman 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 if necessary: access to licensee computers; working space; arrangements for site access; and other applicable information.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Mr. Hamman at (404) 997-5304.

Sincerely,

/RA/

Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos.: 50-259, 50-260, and 296 License Nos.: DPR-33, DPR-52, and DPR-68

Enclosure:

Information Request for Browns Ferry PI&R 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.

ML20191A223 OFFICE RII/DRP RII/DRP RII/DRP NAME J. Hamman S. Ninh T. Stephen DATE 7/8/2020 7/8/2020 7/9/2020 1

INFORMATION REQUEST FOR THE BROWNS FERRY NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (August 24-28, 2020 AND September 14-18, 2020)

Note: Unless otherwise noted, the information requested below corresponds to documents generated since August 1, 2018. 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., IMC 0326) 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 August 1, 2018, 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.

3. List of all Condition Reports (CR) 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.

CR # Problem Priority System Component Org Status CR001 1A 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 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.

Corrective Type Description CR Initiation Extensions Due Status Action # Date Date 001 CAPR Revise CR0058 5/01/18 2 6/15/18 Awaiting Procedure MRC NGK-003-4585 review

5. List of control room deficiencies with a brief description and corresponding CR and/or work order (WO) number, searchable and can be filtered by system.

6. List of operator workarounds and operator burdens with a brief description and corresponding CR number, searchable and can be filtered by system.

7. List of all currently extended or overdue CRs, searchable and can be filtered by system, 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 can be 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 August 2018, searchable and can be filtered by system. 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 Enclosure

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10. List of Maintenance Preventable Functional Failures (MPFF) of risk-significant systems searchable and can be filtered by system. Please include actions completed and current status.

11. List of corrective maintenance work orders searchable and can be filtered by system.

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 (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, 5/01/18 7/15/18 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 report, including any human performance and equipment reliability trends.

18. Copy of the latest Corrective Action Program statistics (if any exists) such as the number of CRs initiated by department, human performance errors by department, and others as may be available.

Enclosure

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19. Please provide a list of routine meetings involving the CAP during the inspection. If those meetings will be conducted remotely please provide bridge call in numbers or any other links if available (i.e. Skype, etc.).

20. List of CRs related to equipment aging issues in the top ten risk- significant systems since May 2018 (i.e., system erosion and/or corrosion problems; electronic component aging or obsolescence of circuit boards, power supplies, relays, etc.; environmental qualification) and ensure the list is searchable and can be filtered by system. Please provide the following information for each CR:

a) CR number b) Priority c) CR problem description

21. If performed, please provide any recent completed or in progress updates regarding self-assessments of the sites 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, apparent cause, common cause and related evaluations and any safety significant equipment cause evaluations. Include a brief description, and ensure the list is searchable and can be filtered by system.

24. Copy of Probabilistic Risk Assessment importance measures report, if available.

25. System health reports, system design basis documents, and system description information upon notification of system selections.

Enclosure