ML090690602: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 1: Line 1:
{{Adams
#REDIRECT [[IR 05000369/2009006]]
| number = ML090690602
| issue date = 03/09/2009
| title = William B. Mcguire Nuclear Station - Component Design Bases Inspection - NRC Inspection Report 05000369/2009-006 and 05000370/2009-006
| author name = Desai B
| author affiliation = NRC/RGN-II/DRS/EB1
| addressee name = Hamilton B
| addressee affiliation = Duke Energy Carolinas, LLC, Duke Power Co
| docket = 05000369, 05000370
| license number = NPF-009, NPF-017
| contact person =
| case reference number = IR-09-006
| document type = Letter, Request for Additional Information (RAI)
| page count = 5
}}
See also: [[see also::IR 05000370/2009006]]
 
=Text=
{{#Wiki_filter: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
}}

Latest revision as of 12:54, 14 January 2025

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML090690602&oldid=5319231"