ML063610280
| ML063610280 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/27/2006 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Morris J Duke Energy Carolinas, Duke Power Co |
| References | |
| IR-07-006 | |
| Download: ML063610280 (5) | |
See also: IR 05000413/2007006
Text
December 27, 2006
Duke Power Company LLC
d/b/a Duke Energy Carolinas, LLC
ATTN:
Mr. J. R. Morris
Site Vice President
Catawba Site
4800 Concord Road
York, SC 29745-9635
SUBJECT:
NOTIFICATION OF CATAWBA NUCLEAR STATION - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000413/2007006 AND
Dear Mr. Morris:
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 Catawba Nuclear
Station during the weeks of March 19-23, 2007, April 2-6, 2007, and April 16-20, 2007. The
inspection team will be led by Randy Moore, 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 June 22, 2006.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and 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 21, 2006, Mr. Moore confirmed with
Mr. G. Strickland 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 5-9, 2007
Onsite weeks: March 19-23, 2007, April 2-6, 2007, and April 16-20, 2007
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. Rudy Bernhard, a Region II Senior Reactor
Analyst, may accompany Mr. Moore 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. Moore prior to preparing copies of the materials listed in the enclosure.
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
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
March 12-16, 2007; 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. Moore at (404) 562-4628 or me at
(404) 562-4605.
Sincerely,
/RA/
Charles R. Ogle, Acting Deputy Director
Division of Reactor Safety
Docket Nos.: 50-413, 50-414
Enclosure
cc w/enc/: (See page 3)
2
cc w/encl:
Randy D. Hart
Regulatory Compliance Manager
Duke Power Company LLC
d/b/a/Duke Energy Carolinas, LLC
Electronic Mail Distribution
Lisa F. Vaughn
Associate General Counsel
and Managing Attorney
Duke Energy Carolinas, LLC
526 South Church Street-EC 07H
Charlotte, NC 28202
Kathryn B. Nolan
Senior Counsel
Duke Energy Carolinas, LLC
526 South Church Street-EC 07H
Charlotte, NC 28202
David A. Repka
Winston & Strawn LLP
Electronic Mail Distribution
North Carolina MPA-1
Electronic Mail Distribution
Henry J. Porter, Asst. Director
Div. of Radioactive Waste Mgmt.
S. C. Department of Health
and Environmental Control
Electronic Mail Distribution
R. Mike Gandy
Division of Radioactive Waste Mgmt.
S. C. Department of Health and
Environmental Control
Electronic Mail Distribution
Elizabeth McMahon
Assistant Attorney General
S. C. Attorney General's Office
Electronic Mail Distribution
Vanessa Quinn
Federal Emergency Management Agency
Electronic Mail Distribution
North Carolina Electric
Membership Corporation
Electronic Mail Distribution
Peggy Force
Assistant Attorney General
N. C. Department of Justice
Electronic Mail Distribution
County Manager of York County, SC
Electronic Mail Distribution
Piedmont Municipal Power Agency
Electronic Mail Distribution
R. L. Gill, Jr., Manager
Nuclear Regulatory Issues
and Industry Affairs
Duke Power Company LLC
d/b/a Duke Energy Carolinas, LLC
526 S. Church Street
Charlotte, NC 28201-0006
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
/RA/
/RA/
/RA/
NAME
R. Bernhard
R. Moore
J. Moorman
DATE
12/27/2006
12/27/2006
12/27/2006
12/ /2006
12/ /2006
12/ /2006
12/ /2006
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
December 21, 2006
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. Lists
should contain enough information to be easily understood to someone who has a knowledge
of pressurized water reactor technology.
1.
From your most-recent probabilistic safety analysis (PSA) excluding external events and
fires:
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:
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 operating experience evaluations completed within the last two years, sorted by
associated component and/or system. Note this includes applicability evaluations for OE
items not just those found to be applicable to Catawba.
6.
A list of safety related SSC design modifications implemented within the last two years,
sorted by affected system.
7.
This item deleted. Corrective action lists will be requested after the component sample is
determined.
8.
A list of common-cause failure of components that have occurred at Catawba and have
been identified within the last five years.
9.
A list of operability evaluations completed within the last two years, sorted by associated
component or system.
10. Contact information for a person to discuss PRA information prior to bag man trip: name,
title, phone number, and e-mail address
11. List of equipment currently 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 those reasons.
12. List of equipment currently in GL 91-18 status.
13. List of equipment currently in MR (a)(1) status.