ML053010217

IR 05000280-05-005, IR 05000281-05-005, Notification of Surry Nuclear Station Integrated Designs and Component Capability Inspection - NRC Inspection Report

ML053010217
Person / Time
Site:	Surry
Issue date:	10/28/2005
From:	Ogle C NRC/RGN-II/DRS/EB1
To:	Christian D Virginia Electric & Power Co (VEPCO)
References
IR-05-005
Download: ML053010217 (4)

See also: IR 05000280/2005005

Text

October 28, 2005

Virginia Electric and Power Company

ATTN: Mr. David A. Christian

Senior Vice President and

Chief Nuclear Officer

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060

SUBJECT: NOTIFICATION OF SURRY NUCLEAR STATION INTEGRATED DESIGN AND

COMPONENT CAPABILITY INSPECTION - NRC INSPECTION REPORT

05000280/2005005 AND 05000281/2005005

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 an integrated design and component capability inspection at your

Surry Nuclear Station during the weeks of January 9-13, 2006, January 23-27, 2006, and

February 6-10, 2006. The inspection team will be led by Mr. Caswell Smith, a Senior Reactor

Inspector from the NRC's Region II Office. This inspection will be conducted in accordance

with the soon to be issued baseline inspection Procedure 71111.21, Integrated Design and

Component Capability Inspection. (This inspection procedure has not been issued yet.)

As currently planned, 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 October 18, 2005, Mr. Smith of my staff, and Mr. Barry

Garber 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 December 12, 2005

• Onsite weeks: January 9, 2006; January 23, 2006; and February 6, 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. Smith 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. Smith 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.

VEPCO 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 their office space and prior to the inspection preparation week of

January 2, 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. Smith at (404) 562-4630 or me at

(404) 562-4605.

Sincerely,

/RA/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-280, and 50-281

License Nos.: DPR - 32 and DPR - 37

cc: w/o encl: (See page 3)

VEPCO 3

cc w/encl:

Chris L. Funderburk, Director

Nuclear Licensing and

Operations Support

Virginia Electric & Power Company

Electronic Mail Distribution

Donald E. Jernigan

Site Vice President

Surry Power Station

Virginia Electric & Power Company

Electronic Mail Distribution

Virginia State Corporation Commission

Division of Energy Regulation

P. O. Box 1197

Richmond, VA 23209

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:DRP RII:DRS

SIGNATURE /RA/ /RA/ /RA/ /RA/

NAME C. Ogle KLandis C. Smith L.Mellen

DATE 10/28/2005 10/27/2005 10/19/2005 10/19/2005 10/ /2005 10/ /2005 10/ /2005

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

INFORMATION REQUEST FOR SURRY NUCLEAR STATION -- INTEGRATED DESIGN AND

COMPONENT CAPABILITY 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.

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. 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