ML053540247
| ML053540247 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/20/2005 |
| From: | Ogle C NRC/RGN-II/DRS/EB1 |
| To: | Rosalyn Jones Duke Energy Corp |
| References | |
| IR-06-006 | |
| Download: ML053540247 (5) | |
See also: IR 05000269/2006006
Text
December 20, 2005
Duke Energy Corporation
ATTN: Mr. Ronald A. Jones
Vice President
Oconee Site
7800 Rochester Highway
Seneca, SC 29672
SUBJECT: NOTIFICATION OF OCONEE NUCLEAR STATION COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000269/2006006,
05000270/2006006 AND 05000287/2006006
Dear Mr. Jones:
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 Oconee Nuclear
Station during the weeks of February 13-17, 2006, February 27-March 3, 2006, and March 13-
17, 2006. The inspection team will be led by Mr. Caudle Julian, 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 November 22, 2005, Mr. R. Moore of my staff, and
Ms. J. Smith of your staff, confirmed arrangements for an information gathering site visit and
the three-week onsite inspection. The schedule is as follows:
- Information gathering visit: Week of January 30, 2006
- Onsite weeks: February 13, 2006; February 27, 2006; and March 13, 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. Walter Rogers, a Region II Senior Reactor
Analyst, will accompany Mr. Julian 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. Please contact Mr. Julian 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 inspection preparation.
DEC 2
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space; specific documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of February
6, 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 Publically Available Records (PARS) component of NRCs 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. Julian at (404) 562-4603 or me at
(404) 562-4605.
Sincerely,
/RA/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-269, 50-270, and 50-287
License Nos.: DPR - 38, DPR - 47, and DPR - 55
Enclosure
cc: w/encl: (See page 3)
DEC 3
cc w/encl: R. L. Gill, Jr., Manager
B. G. Davenport Nuclear Regulatory Issues
Compliance Manager (ONS) and Industry Affairs
Duke Energy Corporation Duke Energy Corporation
Electronic Mail Distribution 526 S. Church Street
Charlotte, NC 28201-0006
Lisa Vaughn
Associate General Counsel Peggy Force
Duke Energy Corporation Assistant Attorney General
526 South Church Street N. C. Department of Justice
Mail Code EC 07H Electronic Mail Distribution
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
Henry J. Porter, Assistant 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
County Supervisor of
Oconee County
415 S. Pine Street
Walhalla, SC 29691-2145
Lyle Graber, LIS
NUS Corporation
Electronic Mail Distribution
_________________________
OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII:DRS
SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/
NAME C. Ogle M. Ernstes R. Moore L. Mellen CJulian
DATE 12/20/2500 12/19/2005 12/19/2005 12/19/2005 12/19/2005 12/ /2005 12/ /2005
E-MAIL COPY? NO YES NO YES NO YES NO YES YES NO YES NO
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
by 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, provide component identification related to event name column
on list of Basic Event Importances by RAW list.)
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 Events 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
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.
Enclosure