ML16363A011

Notification of Shearon Harris Nuclear Power Plant Design Basis Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2017007

ML16363A011
Person / Time
Site:	Harris
Issue date:	12/27/2016
From:	Bartley J NRC/RGN-II/DRS/EB1
To:	Hamilton T Progress Energy Carolinas
References
IR 2017007
Download: ML16363A011 (5)

See also: IR 05000400/2017007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

December 27, 2016

Mrs. Tanya M. Hamilton

Site Vice President

Shearon Harris Nuclear Power Plant

5413 Shearon Harris Road

M/C HNP01

New Hill, North Carolina 27562-0165

SUBJECT: NOTIFICATION OF SHEARON HARRIS NUCLEAR POWER PLANT DESIGN

BASIS ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY

COMMISSION INSPECTION REPORT 05000400/2017007

Dear Mrs. Hamilton:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a Design Basis Assurance Inspection (DBAI) at your Harris Nuclear

Plant during the weeks of March 20 - 24 and April 3 - 7, 2017. Mr. Wesley Deschaine, the

Resident Inspector from the NRCs Sequoyah office, will lead the inspection team. The

inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design

Bases Assurance Inspection (Teams), dated January 1, 2017 (ADAMS ML16238A320).

The inspection will evaluate the capability of components that have been modified and 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 November 8, 2016, with Tasha Stephens, we confirmed

arrangements for an information-gathering site visit and the two-week onsite inspection. The

schedule is as follows:

• Information-gathering visit: Week of February 27 - March 3, 2017

• Onsite weeks: Weeks of March 20 - 24 and April 3 - 7, 2017

The purpose of the information-gathering visit is to meet with members of your staff to identify

components that have been modified, risk-significant components and operator actions.

Information and documentation needed to support the inspection will also be identified. Mr.

George McDonald, a Region II Senior Risk Analyst, will support Mr. Deschaine during the

information-gathering visit to review probabilistic risk assessment data and identify components

to be examined during the inspection. Additionally, during the onsite weeks, time will be needed

on the plant-referenced simulator in order to facilitate the development of operator action-based

scenarios.

T. Hamilton 2

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 February 13, 2017.

Additional documents will be requested following 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 be needed in the Region II

office by March 13, 2017, to support the inspection teams preparation week. During the

information-gathering trip, Mr. Deschaine 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

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. Deschaine at 423-842-8001 or

contact me at 404-997-4607.

Sincerely,

/RA/

Jonathan H. Bartley, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-400

License Nos.: NPF-63

Enclosure:

Information Request for Shearon Harris Nuclear

Plant, Design Basis Assurance Inspection

cc: Distribution via Listserv

_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED

OFFICE RII:DRP RII:DRS

SIGNATURE WXD1 VIA EMAIL JHB1

NAME WDESCHAINE JBARTLEY

DATE 12/27/2016 12/27/2016

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

INFORMATION REQUEST FOR SHEARON HARRIS NUCLEAR PLANT

DESIGN BASIS ASSURANCE 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. The requested items below, identified with an asterisk (*),

should have a date range from January 1, 2014, until present.

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

design modifications implemented

2. 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 cut-sets

c. A list of the top 500 LERF contributors

3. 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 cut-sets

4. Risk ranking of operator actions from your site-specific PSA sorted by RAW and human

reliability worksheets for these items

5. List of time-critical operator actions with a brief description of each action

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 and brief description of Root Cause Evaluations performed

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

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

described in NRC Inspection Manual Chapter 0326, issued December 3, 2015

10. *List and brief description of Operability Determinations and Functionality Assessments

11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status

Enclosure

2

12. *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) along with dates added or removed from

the issues list

13. List of current operator work arounds/burdens

14. Copy of Updated Final Safety Analysis Report

15. Copy of Technical Specification(s)

16. Copy of Technical Specifications Bases

17. Copy of Technical Requirements Manual(s)

18. Copy of the Quality Assurance Program Manual

19. Copy of Corrective Action Program Procedure(s)

20. Copy of Operability Determination Procedure(s)

21. List of motor operated valves and air operated valves in the valve program, and their

associated design margin and risk ranking

22. Primary AC and DC calculations for safety-related buses

23. One-line diagram of electrical plant (Electronic only)

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

25. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)

26. Index and Legend for P&IDs

27. Index (procedure number, title, and current revision) of station Emergency Operating

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

28. Copies of corrective action documents generated from previous CDBI

29. Copy of any self-assessments performed, and corrective action documents generated, in

preparation for current DBAI

30. Contact information for a person to discuss PSA information prior to and during the

information-gathering trip (Name, title, phone number, and e-mail address)