ML14351A018

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 NRC/RGN-II/DRS/EB1
To:	Capps S Duke Energy Carolinas
References
IR 2015007
Download: ML14351A018 (8)

See also: IR 05000369/2015007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

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 NRCs 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.

S. Capps 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 teams 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

S. Capps 3

Letter to Steven D. Capps 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

S. Capps 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 teams 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

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

stations 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

Enclosure

2

11. List of equipment on the sites 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)