ML090690602

William B. Mcguire Nuclear Station - Component Design Bases Inspection - NRC Inspection Report 05000369/2009-006 and 05000370/2009-006

ML090690602
Person / Time
Site:	McGuire, Mcguire
Issue date:	03/09/2009
From:	Binoy Desai NRC/RGN-II/DRS/EB1
To:	Brandi Hamilton Duke Energy Carolinas, Duke Power Co
References
IR-09-006
Download: ML090690602 (5)

See also: IR 05000370/2009006

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

SAM NUNN ATLANTA FEDERAL CENTER

61 FORSYTH STREET, SW, SUITE 23T85

ATLANTA, GEORGIA 30303-8931

March 9, 2009

Mr. Bruce H. Hamilton

Vice President

Duke Power Company, LLC

d/b/a Duke Energy Carolinas, LLC

McGuire Nuclear Station

12700 Hagers Ferry Road

Huntersville, NC 28078-8985

SUBJECT: WILLIAM B. MCGUIRE NUCLEAR STATION - COMPONENT DESIGN BASES

INSPECTION - NRC INSPECTION REPORT 05000369/2009-006 AND

05000370/2009-006

Dear Mr. Hamilton:

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 William B. McGuire

Nuclear Station during the weeks of May 18-22, June 1-5, and June 15-19, 2009. The

inspection team will be led by R. Moore, 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 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 March 3, 2009, Mr. Moore confirmed with Ms. K. Crane 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 May 4-8, 2009.

• Onsite weeks: May 18-22, June 1-5, and June 15-19, 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. R. Bernhard, a Region II Senior Reactor

Analyst, may accompany Mr. Moore 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. Moore with any questions prior to preparing materials listed in the enclosure

and provide the referenced information to the Region II office by April 20, 2009. The inspectors

will try to minimize your administrative burden by specifically identifying only those documents

required for the inspection preparation.

DPC, LLC 2

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

May 11-15, 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. Moore at (404) 562-4628 or me at

(404) 562-4519.

Sincerely,

/RA/

Binoy B. Desai, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 50-369, 50-370

License Nos. NPF-9, NPF-17

Enclosure: Information Request For William B. McGuire Nuclear Station Component Design

Bases Inspection

cc w/encl: (See page 3)

DPC, LLC 3

cc w/encl:

Steven D. Capps Kathryn B. Nolan,

Engineering Manager Senior Counsel

Duke Power Company, LLC d/b/a Duke Duke Energy Corporation

Energy Carolinas, LLC 526 South Church Street-EC07H

Electronic Mail Distribution Charlotte, NC 28202

Scotty L. Bradshaw David A. Repka

Training Manager Winston Strawn LLP

Duke Power Company, LLC d/b/a Duke Electronic Mail Distribution

Energy Carolinas, LLC

Electronic Mail Distribution County Manager of Mecklenburg County

720 East Fourth Street

Kenneth L. Ashe Charlotte, NC 28202

Regulatory Compliance Manager

Duke Power Company, LLC d/b/a Duke SBeverly O. Hall

Energy Carolinas, LLC Chief, Radiation Protection Section

Electronic Mail Distribution Department of Environmental Health

N.C. Department of Environmental

R. L. Gill, Jr. Commerce & Natural Resources

Manager Electronic Mail Distribution

Nuclear Regulatory Issues & Industry Affairs

Duke Power Company, LLC d/b/a Duke Dhiaa M. Jamil

Energy Carolinas, LLC Group Executive and Chief Nuclear Officer

Electronic Mail Distribution Duke Energy Carolinas, LLC

Electronic Mail Distribution

Lisa F. Vaughn

Associate General Counsel Senior Resident Inspector

Duke Energy Corporation Duke Energy Corporation

526 South Church Street-EC07H William B. McGuire Nuclear Station

Charlotte, NC 28202 U.S. NRC

12700 Hagers Ferry Rd

Huntersville, NC 28078

_________________________ G SUNSI REVIEW COMPLETE

OFFICE RII:DRS RII:DRS RII:DRP RII:DRS

SIGNATURE RA RA RA RA

NAME RMOORE WROGERS JBARTLEY BDESAI

DATE 3/5/2009 3/5/2009 3/5/2009 3/9/2009

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

INFORMATION REQUEST FOR WILLIAM B. McGUIRE NUCLEAR STATION

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. 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 operability evaluations completed within the last two years, sorted by associated

component or system.

7. A list of common-cause failures of components that have occurred at McGuire Nuclear

Station and have been identified within the last five years.

8. 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.

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

status.

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

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

Enclosure