ML13354B972

Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007

ML13354B972
Person / Time
Site:	Farley
Issue date:	12/20/2013
From:	Nease R L NRC/RGN-II/DRS/EB1
To:	Lynch T A Southern Nuclear Operating Co
References
IR-14-007
Download: ML13354B972 (6)

See also: IR 05000348/2014007

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 December 20, 2013 Mr. T. A. Lynch Vice President Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant P.O. Drawer 470, BIN B500 Ashford, AL 36312 SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1, AND 2 COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT 05000348/2014007, 05000364/2014007 Dear Mr. Lynch: The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC) Region II staff will conduct a component design bases inspection (CDBI) at your Farley Nuclear Plant, Units 1, and 2 during the weeks of May 5 - 9, May 19 - 23, and June 2 - 6, 2014. Tonya Lighty, a Project Engineer from the NRC's Region II Office, will lead the inspection team. This inspection will be conducted in accordance with the baseline inspection procedure, Procedure 71111.21, "Component Design Bases Inspection," issued November 29, 2013.

The inspection will evaluate the capability of risk-significant / low margin components to function as designed and to support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications. During a telephone conversation on December 13, 2013, Ms. Lighty confirmed with William Arens of your staff, arrangements for an information-gathering site visit and the three-week onsite inspection. The schedule is as follows: Information-gathering visit: Week of April 7 - 11, 2014 Onsite weeks: May 5 - 9, May 19 - 23, and June 2 - 6, 2014 The purpose of the information-gathering visit is to meet with members of your staff to identify risk-significant components and operator actions. Information and documentation needed to support the inspection will also be identified. Mr. George MacDonald, a Region II Senior Reactor Analyst, will support Ms. Lighty during the information-gathering visit to review probabilistic risk assessment data and identify risk-significant components, which will be examined during the inspection. The enclosure lists documents needed prior to the information-gathering visit. Please provide the referenced information to the Region II Office by March 14, 2014.

T.A. Lynch 2 Additional documents will be requested during the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information should be available to the team in the Region II Office prior to the inspection team's preparation week of April 28, 2014. Ms. Lighty will also discuss the following inspection support administrative details: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection, (2) method of tracking inspector requests during the inspection, (3) licensee computer access, (4) working space, (5) arrangements for site access, and (6) other applicable information. In accordance with 10 CFR 2.390 of the NRC's "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 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 Ms. Lighty at 404-997-4565 or contact me at 404-997-4530. Sincerely, RA Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-348, 50-364 License Nos.: NPF-2, NPF-8 Enclosure: Information Request for Farley Nuclear Plant, Units 1, and 2, Component Design Bases Inspection cc: Distribution via Listserv Additional documents will be requested during the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information should be available to the team in the Region II Office prior to the inspection team's preparation week of April 28, 2014. Ms. Lighty will also discuss the following inspection support administrative details: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection, (2) method of tracking inspector requests during the inspection, (3) licensee computer access, (4) working space, (5) arrangements for site access, and (6) other applicable information. In accordance with 10 CFR 2.390 of the NRC's "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 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 Ms. Lighty at 404-997-4565 or contact me at 404-997-4530.

Sincerely, RA Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-348, 50-364 License Nos.: NPF-2, NPF-8 Enclosure: Information Request for Farley Nuclear Plant, Units 1, and 2, Component Design Bases Inspection cc: Distribution via Listserv x PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLESENSITIVE x NON-SENSITIVE ADAMS:x Yes ACCESSION NUMBER:_ __x SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII: DRP RII: DRS RII: DRP SIGNATURE RA RA RA NAME Lighty NEASE MacDonald DATE 12/ 20/2013 12/20/2013 12/20/2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: S:\DRS\ENG BRANCH 1\BRANCH INSPECTION FILES\2014-2015-2016 CYCLE INSPECTION FOLDER FOR ALL SITES\FARLEY\FARLEY CDBI 2014007 NOTIFICATION LETTER.DOCX

Enclosure INFORMATION REQUEST FARLEY NUCLEAR PLANT, UNITS 1, AND 2 COMPONENT DESIGN BASES INSPECTION Please provide the information electronically in ".pdf" files, Excel, or other searchable format on CDROM (or FTP site, Sharepoint, etc.). The CDROM (or website) should be indexed and hyperlinked to facilitate ease of use. 1. From your most recent probabilistic safety analysis (PSA) excluding external events and fires: a. Two risk rankings of components from your site-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance b. A list of the top 500 cutsets

2. From your most recent PSA including external events and fires: a. Two risk rankings of components from your site-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance b. A list of the top 500 cutsets 3. Risk ranking of operator actions from your site-specific PSA sorted by RAW. Provide human reliability worksheets for these items. 4. List of time-critical operator actions with a brief description of each action. 5. List of Emergency and Abnormal Operating Procedures revised (significant) since September 1, 2011, with a brief description of each revision. 6. List of components with low design margins (i.e., pumps closest to the design limit for flow

or pressure, diesel generator close to design-required output, heat exchangers close to rated design heat removal, and motor-operated valve risk-margin rankings, etc.), and associated evaluations or calculations. 7. List of station operating experience evaluations/reviews performed, and documented in the station's corrective action program, for industry events and safety-related equipment failures/vulnerabilities (as communicated by NRC Generic Communications, Industry Communications, 10 CFR Part 21 Notifications, etc.) since September 1, 2011.

8. List and brief description of safety-related structures, systems, or components (SSCs) design modifications implemented since September 1, 2011. 9. List and brief description of common-cause component failures that have occurred since September 1, 2011.

10. List and brief description of operability evaluations completed since September 1, 2011.

2 11. List of equipment on the site's Station Equipment Reliability Issues List, including a description of the reason(s) why each component is on that list, and summaries (if available) of your plans to address the issue(s).

12. List and brief description of equipment currently in degraded or nonconforming status as

described in Regulatory Issue Summary 05-020.

13. List and reason for equipment classified in maintenance rule (a)(1) status from September 1, 2011, to present. 14. Copies of system descriptions (or the design basis documents) for safety-related systems. 15. Copy of Updated Final Safety Analysis Report.

16. Copy of Technical Specification(s).

17. Copy of Technical Specifications Bases. 18. Copy of Technical Requirements Manual(s). 19. List and brief description of Root Cause Evaluations performed since September 1, 2011. 20. In-service Testing Program Procedure(s).

21. Corrective Action Program Procedure(s).

22. One-line diagram of electrical plant. (Electronic and full size - hard copy week of April 7 - 11, 2014)

23. Index and legend for electrical plant one-line diagrams.

24. Primary AC calculation(s) for safety-related buses. 25. Primary DC calculation(s) for safety-related buses. 26. Piping and instrumentation diagrams (P&IDs) for safety-related systems. (Electronic and 1/2 size - hard copy week of April 7 - 11, 2014)

27. Index and Legend for P&IDs.

28. Copy of Operability Determination procedure(s). 30. Copies of corrective action documents (i.e. CRs) associated with findings from previous CDBI. (If applicable) 31. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures. 32. Copy of any self-assessments performed in preparation for this inspection.

3 33. List of any condition reports generated in preparation for this inspection. 34. Copies of condition reports generated from previous CDBI (2011).

35. Contact information for a person to discuss PSA information prior to the information-gathering trip. (Name, title, phone number, and e-mail address)