ML092120559

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Component Design Bases Inspection - NRC Inspection Report 05000338-09-007 and 05000339-09-007
ML092120559
Person / Time
Site: North Anna  
Issue date: 07/30/2009
From: Binoy Desai
NRC/RGN-II/DRS/EB1
To: Heacock D
Virginia Electric & Power Co (VEPCO)
References
IR-09-007
Download: ML092120559 (6)


See also: IR 05000338/2009007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

SAM NUNN ATLANTA FEDERAL CENTER

61 FORSYTH STREET, SW, SUITE 23T85

ATLANTA, GEORGIA 30303-8931

July 30, 2009

Mr. David A. Heacock

President and Chief Nuclear Officer

Virginia Electric and Power Company

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060-6711

SUBJECT:

NORTH ANNA POWER STATION - COMPONENT DESIGN BASES

INSPECTION - NRC INSPECTION REPORT 05000338/2009007 AND

05000339/2009007

Dear Mr. Heacock

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 Power

Station Units 1 and 2 during the weeks of November 2-6, November 16-20, and December 7-11,

2009. The inspection team will be led by Mr. S. Rose, a Senior Operations 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

August 19, 2008.

The inspection will evaluate the capability of risk significant / low margin components to function

as designed and to support proper system operation. The inspection will also include a review

of selected operator actions, operating experience, and modifications.

During a telephone conversation on July 28, 2009, Mr. Rose 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: Week of October 19-23, 2009.

Onsite weeks: November 2-6, November 16-20, and December 7-11, 2009.

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. W. Rogers, a Region II Senior Reactor

Analyst, may accompany Mr. Rose during the information gathering visit to review probabilistic

risk assessment data and identify risk significant components which will be examined during the

inspection.

Please provide the information requested in the enclosure to the Region II office by October 13,

2009. The enclosure lists documents that will be needed prior to the information gathering visit.

The inspectors will try to minimize your administrative burden by specifically identifying only

those documents required for the inspection preparation. Contact Mr. Rose with any questions

related to the information request. 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

VEPCO

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inspection preparation week of October 26-30, 2009; 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. Rose at (404) 562-4609 or me at

(404) 562-4519.

Sincerely,

/RA/

Binoy B. Desai, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 50-338, 50-339

License Nos. NPF-4, NPF-7

Enclosure: Information Request For North Anna Power Station Units 1 and 2 Component

Design Bases Inspection

cc w/encl: (See page 3)

VEPCO

4

cc w/encl:

Daniel G. Stoddard

Site Vice President

Virginia Electric and Power Company

Electronic Mail Distribution

Eric Hendrixson

Director, Nuclear Safety and Licensing

Virginia Electric and Power Company

Electronic Mail Distribution

Chris L. Funderburk

Director, Nuclear Licensing & Operations Support

Virginia Electric and Power Company

Electronic Mail Distribution

Lillian M. Cuoco, Esq.

Senior Counsel

Dominion Resources Services, Inc.

Electronic Mail Distribution

Executive Vice President

Old Dominion Electric Cooperative

Electronic Mail Distribution

Attorney General

Supreme Court Building

900 East Main Street

Richmond, VA 23219

Senior Resident Inspector

North Anna Power Station

U.S. Nuclear Regulatory Commission

P.O. Box 490

Mineral, VA 23117

County Administrator

Louisa County

P.O. Box 160

Louisa, VA 23093

Michael M. Cline

Director

Virginia Department of Emergency Services Management

Electronic Mail Distribution

_________________________

XG SUNSI REVIEW COMPLETE

OFFICE

RII:DRS

RII:DRS

RII:DRP

RII:DRS

SIGNATURE

RA

RA

RA

RA

NAME

SROSE

WROGERS

GMCCOY

BDESAI

DATE

7/31/2009

7/31/2009

7/31/2009

7/31/2009

E-MAIL COPY?

YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO

Enclosure

INFORMATION REQUEST FOR NORTH ANNA POWER STATION UNITS 1 AND 2

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

knowledge of pressurized water reactor technology.

1.

From your most recent probabilistic safety analysis (PSA) excluding external events and

fires, please provide:

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, please provide:

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.

List of time critical operator actions with required completion times.

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 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.).

7.

A list of operability evaluations completed within the last two years, sorted by associated

component or system.

8.

A list of common-cause failures of components that have occurred at the North Anna

Power Station and have been identified within the last five years.

9.

A list of equipment currently on the sites Key Equipment Priorities List, including a

description of the reason(s) why each component (i.e. not a programmatic or system

level concern) is on that list and summaries (if available) of your plans to address those

reasons.

10.

A list of equipment currently in RIS 05-020 (formerly GL 91-18) status, or in MR (a)(1)

status.

VEPCO

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11.

Contact information for a person to discuss PRA information prior to the information

gathering trip: name, title, phone number, and e-mail address.

12.

Electronic copy of the FSAR, Technical Specifications and Bases.