ML080150323
| ML080150323 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/15/2008 |
| From: | Binoy Desai NRC/RGN-II/DRS/EB1 |
| To: | Duncan R Carolina Power & Light Co |
| References | |
| IR-08-006 | |
| Download: ML080150323 (5) | |
See also: IR 05000400/2008006
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER
61 FORSYTH STREET, SW, SUITE 23T85
ATLANTA, GA 30303-8931
January 15, 2008
Carolina Power & Light Company
ATTN: Mr. Robert J. Duncan, II
Vice President - Harris Plant
Shearon Harris Nuclear Power Plant
P. O. Box 165, Mail Code: Zone 1
New Hill, North Carolina 27562-0165
SUBJECT: NOTIFICATION OF SHEARON HARRIS NUCLEAR POWER PLANT -
COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT
Dear Mr. Duncan:
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 at your Shearon Harris
Nuclear Power Plant during the weeks of April 14 - 18, 2008, April 28 - May 2, 2008, and May
12 - 16, 2008. The inspection team will be led by W. Russell Lewis, a Senior Reactor Inspector
from the NRC's Region II Office. This inspection will be conducted in accordance with the
baseline inspection procedure, Procedure 71111.21, Component Design Bases Inspection,
issued September 20, 2007.
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 January 9, 2008 and subsequent e-mail exchange on
January 10, 2008, Mr. Lewis confirmed with Mr. Wallace 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 March 31 - April 4, 2008.
- Onsite weeks: April 14 - 18, 2008, April 28 - May 2, 2008, and May 12 - 16, 2008.
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. Walt Rogers, a Region II Senior Reactor
Analyst, and Mr. Steve Rose, a Region II Senior Reactor Inspector and Team Leader, may
accompany Mr. Lewis 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
contact Mr. Lewis with any questions prior to preparing materials listed in the enclosure, and
provide the referenced information to the Region II office by March 13, 2008. The inspectors
will try to minimize your administrative burden by specifically identifying only those documents
required for the inspection preparation.
CP&L 2
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space; supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of April 7,
2008; arrangements for site access; and the availability of knowledgeable plant engineering and
licensing personnel to serve as points of contact during the inspection.
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 document 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. Lewis at (404) 562-4541 or me at
(404) 562-4519.
Sincerely,
/RA/
Binoy B. Desai, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-400
License Nos.: NPF-63
Enclosure: Information Request For Shearon Harris Nuclear Power Plant Component Design
Bases Inspection
cc w/encl:
Paul Fulford
Manager
Performance Evaluation and Regulatory Affairs PEB5
Carolina Power & Light Company
Electronic Mail Distribution
Chris L. Burton
Director Site Operations
Carolina Power & Light Company
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
J. Wayne Guganious
Training Manager
Harris
Progress Energy Carolinas, Inc.
Electronic Mail Distribution
(cc w/encl contd - See page 3)
CP&L 3
(cc w/encl contd)
Thomas J. Natale
Manager
Support Services
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
David H. Corlett
Supervisor
Licensing/Regulatory Programs
Carolina Power & Light Company
Electronic Mail Distribution
David T. Conley
Associate General Counsel
Legal Dept.
Progress Energy Service Company, LLC
Electronic Mail Distribution
John H. O'Neill, Jr.
Shaw, Pittman, Potts & Trowbridge
2300 N. Street, NW
Washingtion, DC 20037-1128
Beverly Hall
Chief
Radiation Protection Section
N.C. Department of Environmental Commerce & Natural Resources
Electronic Mail Distribution
Public Service Commission
State of South Carolina
P.O. Box 11649
Columbia, SC 29211
Herb Council
Chair
Board of County Commissioners of Wake County
P.O. Box 550
Raleigh, NC 27602
Tommy Emerson
Chair
Board of County Commissioners of Chatham County
Electronic Mail Distribution
Distribution w/encl:
M. Vaaler, NRR
RIDSNRRDIRS
PUBLIC
OFFICE RII:DRS RII:DRS RII:DRP RII:DRS
NAME S.Rose R.Lewis R.Musser W.Rogers
DATE 01/ 11/2008 01/11 /2008 01/14/2008 01/ 14/2008
E-MAIL COPY YES NO YES NO YES NO YES NO
INFORMATION REQUEST FOR SHEARON HARRIS NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Information
in lists should contain enough information to be easily understood to someone who has
knowledge of pressurized water reactor technology.
1. From your most recent probabilistic safety analysis (PSA) excluding external events and
fires, please provide:
a. Two risk rankings of components from your site-specific probabilistic safety
analysis (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 probabilistic safety analysis (PSA) including external events and
fires, please provide:
a. Two risk rankings of components from your site-specific probabilistic safety
analysis (PSA) - one sorted by Risk Achievement Worth (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
copies of your human reliability worksheets for these items.
4. Any pre-existing evaluation or list of components and calculations 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,
MOV risk-margin rankings, etc.).
5. A list of station applicability evaluations/reviews performed and documented in the station
corrective action program in the past two years for industry events, critical equipment
failures, and safety related equipment vulnerabilities (as communicated by NRC generic
communications, industry communications, 10 CFR Part 21 notifications, etc.).
6. A list of operability evaluations completed within the last two years, sorted by associated
component or system.
7. A list of common-cause failures of components that have occurred at Shearon Harris
Nuclear Power Plant and have been identified within the last five years.
8. A list of equipment currently on the sites Key Equipment Priorities List, including a
description of the reason(s) why each component (i.e. not a programmatic or system
level concern) is on that list and summaries (if available) of your plans to address those
reasons.
9. A list of equipment currently in RIS 05-020 (formerly GL 91-18) status, or in MR (a)(1)
status.
10. Contact information for a person to discuss PRA information prior to the information
gathering trip: name, title, phone number, and e-mail address.
Enclosure