ML080150323: Difference between revisions

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{{Adams
#REDIRECT [[IR 05000400/2008006]]
| number = ML080150323
| issue date = 01/15/2008
| title = IR 05000400-08-006, on 04/14-182008, 04/28/2008 - 05/02/2008, Notification of Shearon Harris Nuclear Power Plant - Component Design Bases Inspection and Information Request
| author name = Desai B B
| author affiliation = NRC/RGN-II/DRS/EB1
| addressee name = Duncan R J
| addressee affiliation = Carolina Power & Light Co
| docket = 05000400
| license number = NPF-063
| contact person =
| document report number = IR-08-006
| document type = Letter
| page count = 5
}}
See also: [[followed by::IR 05000400/2008006]]
 
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GA 30303-8931
  January 15, 2008
  Carolina Power & Light Company ATTN: Mr. Robert J. Duncan, II  Vice President - Harris Plant    Shearon Harris Nuclear Power Plant
P. O. Box 165, Mail Code:  Zone 1 New Hill, North Carolina  27562-0165
SUBJECT: NOTIFICATION OF SHEARON HARRIS NUCLEAR POWER PLANT - COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000400/2008006
Dear Mr. Duncan:
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 Shearon Harris Nuclear Power Plant during the weeks of April 14 - 18, 2008, April 28 - May 2, 2008, and May 12 - 16, 2008.  The inspection team will be led by W. Russell Lewis, 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 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 January 9, 2008 and subsequent e-mail exchange on
January 10, 2008, Mr. Lewis confirmed with Mr. Wallace 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 March 31 - April 4, 2008.
* Onsite weeks:  April 14 - 18, 2008, April 28 - May 2, 2008, and May 12 - 16, 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, and Mr. Steve Rose, a Region II Senior Reactor Inspector and Team Leader, may accompany Mr. Lewis 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. Lewis with any questions prior to preparing materials listed in the enclosure, and provide the referenced information to the Region II office by March 13, 2008.  The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for the inspection preparation. 
CP&L  2During 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 April 7, 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. Lewis at (404) 562-4541 or me at (404) 562-4519.
      Sincerely,
      /RA/
Binoy B. Desai, Chief        Engineering Branch 1
      Division of Reactor Safety
  Docket Nos.:  50-400 License Nos.:  NPF-63
Enclosure: Information Request For Shearon Harris Nuclear Power Plant Component Design Bases Inspection
cc w/encl: Paul Fulford Manager
Performance Evaluation and Regulatory Affairs PEB5 Carolina Power & Light Company Electronic Mail Distribution
Chris L. Burton
Director Site Operations Carolina Power & Light Company Shearon Harris Nuclear Power Plant Electronic Mail Distribution
J. Wayne Guganious Training Manager Harris Progress Energy Carolinas, Inc. Electronic Mail Distribution
 
  (cc w/encl cont'd - See page 3) 
CP&L  3(cc w/encl cont'd) Thomas J. Natale
Manager Support Services Shearon Harris Nuclear Power Plant Electronic Mail Distribution
David H. Corlett Supervisor Licensing/Regulatory Programs Carolina Power & Light Company Electronic Mail Distribution
 
David T. Conley Associate General Counsel Legal Dept. Progress Energy Service Company, LLC
Electronic Mail Distribution
John H. O'Neill, Jr. Shaw, Pittman, Potts & Trowbridge 2300 N. Street, NW
Washingtion, DC  20037-1128
Beverly Hall Chief Radiation Protection Section N.C. Department of Environmental Commerce & Natural Resources Electronic Mail Distribution
 
Public Service Commission State of South Carolina P.O. Box 11649 Columbia, SC  29211
 
Herb Council Chair Board of County Commissioners of Wake County P.O. Box 550
Raleigh, NC  27602
Tommy Emerson Chair Board of County Commissioners of Chatham County
Electronic Mail Distribution
Distribution w/encl
: M. Vaaler, NRR RIDSNRRDIRS 
PUBLIC
 
 
OFFICE RII:DRS RII:DRS RII:DRP RII:DRS    SIGNATURE RA RA RA RA    NAME S.Rose R.Lewis R.Musser W.Rogers 
DATE 01/ 11/2008 01/11 /2008 01/14/2008 01/ 14/2008 
E-MAIL COPY YES      NO YES      NO YES      NO YES      NO   
  Enclosure INFORMATION REQUEST FOR SHEARON HARRIS NUCLEAR POWER PLANT 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 Shearon Harris Nuclear Power Plant 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.
}}

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