ML072950106

Notification of Surry Power Station - Component Design Bases Inspection NRC Inspection Report 05000280-08-006 & 05000281-08-006

ML072950106
Person / Time
Site:	Surry
Issue date:	10/19/2007
From:	Binoy Desai NRC/RGN-II/DRS/EB1
To:	Christian D Virginia Electric & Power Co (VEPCO)
References
IR-08-006
Download: ML072950106 (6)

See also: IR 05000280/2008006

Text

October 19, 2007

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 SURRY POWER STATION - COMPONENT DESIGN

BASES INSPECTION NRC INSPECTION REPORT 05000280/2008006 AND

05000281/2008006

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 Surry Power Station

during the weeks of January 28-February 1, 2008, February 11-15, 2008, and February 25-29,

2008. The inspection team will be led by Mr. Robert Berryman, 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 September 20, 2007.

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 15, 2007, Mr. Berryman confirmed with Mr. Paul

Kershner 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 January 14-18, 2008.

• Onsite weeks: January 28-February 1, 2008, February 11-15, 2008, and

February 25-29, 2008.

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. Walt Rogers, a Region II Senior Reactor

Analyst, may accompany Mr. Berryman 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.

VEPCO 2

The enclosure lists documents that will be needed prior to the information gathering visit.

Please contact Mr. Berryman 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.

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 21, 2008; 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. Berryman at (404) 562-4817 or me

at (404) 562-4519.

Sincerely,

/RA/

Binoy B. Desai, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-280, 50-281

License Nos.: DPR-32, DPR-37

Enclosure: Information Request for Surry Power Station Component Design Bases Inspection

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

(cc w/encl contd - See page 3)

VEPCO 3

(cc w/encl contd)

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

Distribution w/encl:

S. P. Lingam, NRR

Richard Jervey, NRR

RIDSNRRDIRS

PUBLIC

_________________________

OFFICE RII:DRS

SIGNATURE RA

NAME RBERRYMAN

DATE 10/18/2007 10/ /2007 10/ /2007 10/ /2007 10/ /2007 10/ /2007 10/ /2007

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO 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. 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 station applicability evaluations/reviews performed and documented in the

station corrective action program in the past two years for industry events, critical

equipment failures, and safety related equipment vulnerabilities [as communicated by

NRC generic communications, industry communications, 10 CFR part 21 notifications,

etc.]

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 Surry Power Station

and have been identified within the last five years.

Enclosure

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 the information

gathering 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 RIS 05-020 (formerly GL 91-18) status.

13. List of equipment currently in MR (a)(1) status.

Enclosure