ML14066A473

Notification of Shearon Harris Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 05000400-14-007

ML14066A473
Person / Time
Site:	Harris
Issue date:	03/07/2014
From:	Nease R NRC/RGN-II/DRS/EB1
To:	Kapopoulos E Carolina Power & Light Co
References
IR-14-007
Download: ML14066A473 (6)

See also: IR 05000400/2014007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

March 7, 2014

Mr. Ernie Kapopoulos

Vice President

Shearon Harris Nuclear Power Plant

Carolina Power and Light Company

P.O. Box 165, Mail Code: Zone 1

New Hill, NC 27562-0165

SUBJECT: NOTIFICATION OF SHEARON HARRIS NUCLEAR PLANT - COMPONENT

DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000400/2014007

Dear Mr. Kapopulous:

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 Harris Nuclear

Plant during the weeks of June 23 - 27, July 7 - 11, and July 21 - 25, 2014. 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 Inspection Procedure 71111.21, Component

Design Bases Inspection, issued August 14, 2012.

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 March 4, 2014, the staff confirmed with Mr. David Corlett 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 May 19 - 23, 2014

• Onsite weeks: June 23 - 27, July 7 - 11, and July 21 - 25, 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. Robert Patterson, a Reactor Inspector will be

conducting all preparation activities associated with the inspection. In addition, Mr. George

McDonald, a Region II Senior Reactor Analyst, will support Mr. Patterson 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 that will be needed prior to the information-gathering visit.

Please provide the referenced information to the Region II Office by May 5, 2014.

E. Kapopoulos 2

Additional documents may 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 will need to be available to the

team in the Region II office prior to the inspection teams preparation week of June 16, 2014.

During the information-gathering trip, Mr. Patterson 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 Mr. Patterson at 404-997-4667 or

contact me at 404-997-4530.

Sincerely,

RA

Rebecca L. Nease, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No.: 50-400

License No.: NPF-63

Enclosure:

Information Request for Shearon Harris Nuclear

Plant, Component Design Bases Inspection

cc: Distribution via Listserv

___________x SUNSI REVIEW COMPLETE FORM 665 ATTACHED

OFFICE RII:DRS RII:DRS RII DRS

SIGNATURE RA RA

NAME R. Patterson R. Nease

DATE 3/07/2014 3/07/2014 3/ /2014 3/ /2014 3/ /2014 3/ /2014 3/ /2014

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

INFORMATION REQUEST FOR SHEARON HARRIS NUCLEAR PLANT

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 May 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

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, etc.) since May 1, 2011.

8. List and brief description of safety-related structures, systems, or components (SSCs)

design modifications implemented since May 1, 2011.

9. List and brief description of common-cause component failures that have occurred

since May 1, 2011.

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

Enclosure

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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

May 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 May 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 May 19-23, 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 May 19 - 23, 2014)

27. Index and Legend for P&IDs.

28. Copy of Operability Determination procedure(s).

30. Copies of corrective action documents (i.e. PIPs) 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.

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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)