IR 05000259/2007007
| ML072260413 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/14/2007 |
| From: | Cain L M NRC/RGN-II/DRS/EB1 |
| To: | Campbell W R Tennessee Valley Authority |
| References | |
| IR-07-007 | |
| Download: ML072260413 (7) | |
Text
August 14, 2007
Tennessee Valley AuthorityATTN:Mr. William R. CampbellChief Nuclear Officer and Senior Vice President6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT COMPONENTDESIGN BASES INSPECTION - NRC INSPECTION REPORT NOS.
05000259/2007007, 05000260/2007007, AND 05000296/2007007
Dear Mr. Campbell:
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 Browns Ferry Nuclear Plant during the weeks of November 13 - 16, 2007, November 26 - 30, 2007, and December 10 -
14, 2007. The inspection team will be led by Mr. David A. Jones, 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 June 22, 2006.The inspection will evaluate the capability of risk significant / low margin components to functionas designed and support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications. During a telephone conversation on August 7, 2007, Mr. Jones confirmed with Mr. T. Langley ofyour 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 29 - November 2, 2007*Onsite weeks: November 13 - 16, November 26 - 30, and December 10 - 14, 2007 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. Jones 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. Pleasecontact Mr. Jones prior to preparing copies of the materials listed in the enclosure and provide this information to the Region II office by October 15, 2007.
TVA 2The inspectors will try to minimize your administrative burden by specifically identifying onlythose documents required for the inspection preparation. During the information gathering visit, the team leader will also discuss the following inspectionsupport 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 November 5 - November 9, 2007; 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 itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom 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 theinformation requested or the inspection, please contact Mr. Jones at (404) 562-4631 or me at (404) 562-4876.
Sincerely,/RA/
Loyd M. Cain, Acting Branch ChiefEngineering Branch 1 Division of Reactor SafetyDocket Nos.:50-259, 50-260, 50-296License Nos.:DPR-33, DPR-52, DPR-68
Enclosure:
Information Request for Browns Ferry Plant Component Design Basis Inspection cc w/encl:Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority Electronic Mail DistributionPreston D. SwaffordSenior Vice President Nuclear Support Tennessee Valley Authority Electronic Mail Distribution(cc w/encl cont'd - See page 3)
TVA 3(cc w/encl cont'd)Walter M. Justice, II Interim Vice President Nuclear Engineering &
Technical Services Tennessee Valley Authority Electronic Mail DistributionBrian J. O'GradySite Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail DistributionGeneral CounselTennessee Valley Authority Electronic Mail DistributionRobert G. Jones, General ManagerBrowns Ferry Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35609Beth A. Wetzel, ManagerCorporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801D. T. Langley, ManagerLicensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail DistributionJohn C. Fornicola, General ManagerNuclear Assurance Tennessee Valley Authority Electronic Mail Distribution(cc w/encl cont'd - See page 4)
TVA 4(cc w/encl cont'd)Robert H. Bryan, Jr., General Manager Licensing & Industry Affairs Tennessee Valley Authority Electronic Mail DistributionState Health OfficerAlabama Dept. of Public Health RSA Tower - Administration Suite 1552 P. O. Box 303017 Montgomery, AL 36130-3017ChairmanLimestone County Commission 310 West Washington Street Athens, AL 35611Distribution w/encl
_________________________OFFICERII:DRSRII:DRSRII:DRPSIGNATURERANAMEBERNHARDJONESTLIUDATE8/ /20078/ /20078/14/20078/ /20078/ /20078/ /20078/ /2007 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO EnclosureBrowns Ferry Information Request for CDBIPlease provide the information electronically in ".pdf" files, Excel, or other searchable format onCDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists should contain enough information to be easily understood to someone who has a knowledge of boiling water reactor technology.1.From your most-recent probabilistic safety analysis (PSA) excluding external events andfires:
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 andfires:
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. Providecopies 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 stationcorrective 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 safety related SSC design modifications implemented within the last two years,sorted by affected system.7.This item deleted. Corrective action lists will be requested after the component sample isdetermined
.8.A list of common-cause failure of components that have occurred at Browns Ferry andhave been identified within the last five years. 9.A list of operability evaluations completed within the last two years, sorted by associatedcomponent or system.10.Contact information for a person to discuss PRA information prior to the informationgathering trip: name, title, phone number, and e-mail address.
2Enclosure11.List of equipment currently on the site's Station Equipment Reliability Issues List, includinga description of the reason(s) why each component is on that list and summaries (if available) of your plans to address those reasons.12.List of equipment currently in RIS 05-020 (formerly GL 91-18) status.
13.List of equipment currently in MR (a)(1) status.