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 Engineering Manager Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC Electronic Mail Distribution

Scotty L. Bradshaw Training Manager Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC

Electronic Mail Distribution

Kenneth L. Ashe Regulatory Compliance Manager Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC Electronic Mail Distribution

R. L. Gill, Jr. Manager Nuclear Regulatory Issues & Industry Affairs Duke Power Company, LLC d/b/a Duke

Energy Carolinas, LLC Electronic Mail Distribution

Lisa F. Vaughn Associate General Counsel

Duke Energy Corporation 526 South Church Street-EC07H Charlotte, NC 28202

Kathryn B. Nolan, Senior Counsel Duke Energy Corporation 526 South Church Street-EC07H Charlotte, NC 28202

David A. Repka Winston Strawn LLP Electronic Mail Distribution

County Manager of Mecklenburg County 720 East Fourth Street Charlotte, NC 28202

SBeverly O. Hall Chief, Radiation Protection Section Department of Environmental Health

N.C. Department of Environmental Commerce & Natural Resources Electronic Mail Distribution

Dhiaa M. Jamil

Group Executive and Chief Nuclear Officer Duke Energy Carolinas, LLC Electronic Mail Distribution

Senior Resident Inspector

Duke Energy Corporation William B. McGuire Nuclear Station 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

Enclosure 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 site's 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.