IR 05000369/2015007

IR 05000369/2015007 and 05000370/2015007, Notification of McGuire, Units 1 and 2, Component Design Bases Inspection

ML14351A018
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/12/2014
From:	Nease R L NRC/RGN-II/DRS/EB1
To:	Capps S D Duke Energy Carolinas
References
IR 2015007
Download: ML14351A018 (8)

Text

December 12, 2014

Steven D. Capps, Vice President Duke Energy Carolinas, LLC McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-8985

SUBJECT: NOTIFICATION OF MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 COMPONENT DESIGN BASES INSPECTION - U. S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000369/2015007 AND 05000370/2015007

Dear Mr. Capps:

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 McGuire Nuclear Station during the weeks of April 27 - May 1, May 11 - 15, and June 1 - 5, 2015. Mr. Jason Eargle, a Senior Reactor Inspector from the NRC's Region II office, will lead the inspection team. This inspection will be conducted in accordance with the baseline inspection procedure (IP) 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 10, 2014, Mr. Eargle confirmed with Mrs. Kay Crane of your staff, arrangements for an information-gathering site visit and the 3-week onsite inspection. The schedule is as follows: * Information-gathering visit: Week of April 6 - 10, 2015 * Onsite inspection: Weeks April 27 - May 1, May 11 - 15, and June 1 - 5, 2015 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. John Hanna, a Region II Senior Reactor Analyst, will support Mr. Eargle 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 20, 2015. 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 20, 2015. Mr. Eargle 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 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, its enclosure, and your response (if any) 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 Document Access and Management 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 Mr. Eargle at 404-997-4632 or contact me at 404-997-4530.

Sincerely,/RA: Geoffrey K. Ottenberg for Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17

Enclosure:

Information Request for McGuire Nuclear Station Component Design Bases Inspection cc: Distribution via Listserv Letter to Steven from Rebecca L. Nease dated December 12, 2014

SUBJECT: NOTIFICATION OF MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 COMPONENT DESIGN BASES INSPECTION - U. S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000369/2015007 AND 05000370/2015007 Distribution RIDSNRRDIRS PUBLIC RidsNrrPMMcGuire Resource 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 20, 2015. Mr. Eargle 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 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, its enclosure, and your response (if any) 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 Document Access and Management 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 Mr. Eargle at 404-997-4632 or contact me at 404-997-4530.

Sincerely,/RA: Geoffrey K. Ottenberg for Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17

Enclosure:

Information Request for McGuire Nuclear Station Component Design Bases Inspection cc: Distribution via Listserv

ML_14351A018____ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DRS SIGNATURE JAE1 JAE1 for RLN1 NAME J. Eargle R. Nease DATE 12/12/2014 12/12/2014 E-MAIL COPY YES NO YES NO Enclosure INFORMATION REQUEST FOR MCGUIRE NUCLEAR STATION 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 Web site) 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, including 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 March 1, 2012, 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) since March 1, 2012 8. List and brief description of safety-related structures, systems, or components (SSCs) design modifications implemented since March 1, 2012 9. List and brief description of common-cause component failures that have occurred since March 1, 2012 10. List and brief description of operability evaluations completed since March 1, 2012

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 March 1, 2012, 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 Selected Licensee Commitment Manual(s)

19. List and brief description of Root Cause Evaluations performed since March 1, 2012 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 6, 2015)

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 6, 2015)

27. Index and Legend for P&IDs 28. Copy of Operability Determination procedure(s)

29. Copies of corrective action documents (i.e. problem identification program reports (PIPs)) associated with findings from previous CDBI, if applicable 30. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures 31. Copy of any self-assessments performed in preparation for this inspection 3 32. List of any PIPs generated in preparation for this inspection 33. Copies of PIPs generated from previous CDBI (2012) 34. Contact information for a person to discuss PSA information prior to the information-gathering trip (name, title, phone number, and e-mail address)