ML060050554
| ML060050554 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/05/2006 |
| From: | Ogle C NRC/RGN-II/DRS/EB1 |
| To: | Gordon Peterson Duke Energy Corp |
| References | |
| IR-06-007 | |
| Download: ML060050554 (5) | |
See also: IR 05000369/2006007
Text
January 5, 2006
Duke Energy Corporation
ATTN:
Mr. G. R. Peterson
Vice President
McGuire Nuclear Station
12700 Hagers Ferry Road
Huntersville, NC 28078-8985
SUBJECT:
NOTIFICATION OF MCGUIRE NUCLEAR STATION COMPONENT DESIGN
BASES INSPECTION-NRC INSPECTION REPORT 05000369/2006007 AND
Dear Mr. Peterson:
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 McGuire Nuclear
Station during the weeks of March 20-24, 2006, April 3-7, 2006, and April 17-21, 2006. The
inspection team will be led by Larry Mellen, 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 December 2,
2005.
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 January 4, 2006, I confirmed with Ms. K. Crane 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 6, 2006.
Onsite weeks: March 20, 2006; April 3, 2006; and April 17, 2006.
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. Mellen and the inspection team 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. Mellen prior to preparing copies of the materials listed in the enclosure.
2
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space, suplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of March
13, 2006; 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. Mellen at (404) 562-4531 or me at
(404) 562-4605.
Sincerely,
/RA/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-369, 50-370
Enclosure
cc w/enc/: (See page 3)
3
cc w/encl:
C. J. Thomas
Regulatory Compliance Manager (MNS)
Duke Energy Corporation
Electronic Mail Distribution
R. L. Gill, Jr., Manager
Nuclear Regulatory Issues
and Industry Affairs
Duke Energy Corporation
526 S. Church Street
Charlotte, NC 28201-0006
Lisa Vaughn
Associate General Counsel
Duke Energy Corporation
526 South Church Street
Mail Code EC 07H
Charlotte, NC 28201-1244
Anne Cottingham
Winston & Strawn LLP
Electronic Mail Distribution
Beverly Hall, Acting Director
Division of Radiation Protection
N. C. Department of Environmental
Health & Natural Resources
Electronic Mail Distribution
County Manager of Mecklenburg County
720 East Fourth Street
Charlotte, NC 28202
Peggy Force
Assistant Attorney General
N. C. Department of Justice
Electronic Mail Distribution
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRS
SIGNATURE
NAME
C. Ogle
M. Ernstes
R. Moore
DATE
1/ /2006
1/ /2006
1/ /2006
1/ /2006
1/ /2006
1/ /2006
1/ /2006
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
INFORMATION REQUEST FOR MC GUIRE NUCLEAR STATION
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 a knowledge of pressurized water reactor technology.
1.
Risk ranking of components from your site specific probabilistic safety analysis (PSA)
sorted by Risk Achievement Worth (RAW) and sorted separately by Birnbaum
Importance. If possible, please provide a correlation between actual plant components
in plain language, and RAW values.
2.
Provide a list of the top 500 cutsets from your PSA.
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.
If you have an External Event or Fire PSA Model, provide the information requested in
Items 1 and 2 for external events and fire.
5.
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.).
6.
A list of the last two years of operating experience evaluations, modifications, and
corrective actions sorted by component or system.
7.
Information of any common cause failure of components experienced in the last 5 years
at your facility.