ML062620025

Notification of North Anna Nuclear Power Plant - Component Design Bases Inspection - NRC Inspection Report Nos. 05000338/2007006, 05000339/2007006

ML062620025
Person / Time
Site:	North Anna
Issue date:	09/18/2006
From:	Ogle C NRC/RGN-II/DRS/EB1
To:	Christian D Virginia Electric & Power Co (VEPCO)
References
IR-07-006
Download: ML062620025 (6)

See also: IR 05000338/2007006

Text

September 18, 2006

Virginia Electric and Power Company

ATTN.: Mr. David A. Christian

Sr. Vice President and

Chief Nuclear Officer

Innsbrook Technical Center - 2SW

5000 Dominion Boulevard

Glen Allen, VA 23060-6711

SUBJECT: NOTIFICATION OF NORTH ANNA NUCLEAR POWER PLANT - COMPONENT

DESIGN BASES INSPECTION - NRC INSPECTION REPORT NOS.

05000338/2007006, 05000339/2007006

Dear Mr Christian:

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 North Anna Nuclear

Power Plant during the weeks of January 8 - 12, 2007; January 22 - 26, 2007; and

February 5 - 9, 2007. The inspection team will be led by Mr. Bob Hagar, a Senior Resident

Inspector in Region II. 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 September 13, 2006, Mr. Hagar confirmed with Mr. J.

Leberstien of your staff, arrangements for an information-gathering site visit and the three-week

onsite inspection. The schedule is as follows:

• Information-gathering visit: December 12-14, 2006

• Onsite inspection: January 8 - 12, January 22 - 26, and February 5 - 9, 2007

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

risk-significant components and operator actions, and to identify information and documentation

needed to support the inspection. Mr. Walt Rogers, a Region II Senior Reactor Analyst, may

accompany Mr. Hagar 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. Hagar prior to preparing copies of the materials listed in the enclosure.

VEPCO 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, supplemental documents requested to be made

available to the team in the Region II office prior to the inspection preparation week of January

2, 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. Hagar at (843) 339-2822 or me at

(404) 562-4605.

Sincerely,

/RA/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-338, 50-339

License Nos.: NPF-4, NPF-7

Enclosure

cc w/enc/: (See page 3)

VEPCO 3

cc w/encl:

Chris L. Funderburk, Director

Nuclear Licensing and

Operations Support

Virginia Electric and Power Company

Electronic Mail Distribution

Jack M. Davis

Site Vice President

North Anna Power Station

Electronic Mail Distribution

Executive Vice President

Old Dominion Electric Cooperative

Electronic Mail Distribution

County Administrator

Louisa County

P. O. Box 160

Louisa, VA 23093

Lillian M. Cuoco, Esq.

Senior Counsel

Dominion Resources Services, Inc.

Electronic Mail Distribution

Attorney General

Supreme Court Building

900 East Main Street

Richmond, VA 23219

_________________________

OFFICE RII:DRS RII:DRSP

SIGNATURE /RA/ by email

NAME E. Guthrie R. Hagar

DATE 9/18/2006 9/18/2006 6/ /2006 6/ /2006 6/ /2006 6/ /2006

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

INFORMATION REQUEST FOR NORTH ANNA 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. 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.

c. A risk ranking of all operator actions, sorted by RAW.

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.

c. A risk ranking of all operator actions, sorted by RAW.

3. Human reliability worksheets for the operator actions included in your PSA model.

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.

6. A list of design modifications implemented within the last two years, sorted by affected

system.

7. A list of corrective-action evaluations that involved plant equipment and were completed

within the last two years, sorted by involved component or system.

8. A list of common-cause failure of components that have occurred at North Anna and have

been identified within the last five years.

Enclosure

VEPCO 2

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.

Enclosure