ML061530239

Notification of Triennial Fire Protection Baseline Inspection (NRC IR 05000260-06-014 and 05000296-06-014) and Unit 1 Recovery Inspection

ML061530239
Person / Time
Site:	Browns Ferry
Issue date:	06/02/2006
From:	Edwin Lea NRC/RGN-II/DRS/EB2
To:	Singer K Tennessee Valley Authority
References
IR-06-014
Download: ML061530239 (8)

See also: IR 05000260/2006014

Text

June 2, 2006Tennessee Valley AuthorityATTN:Mr. Karl W. SingerChief Nuclear Officer and

Executive Vice President6A Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801SUBJECT:NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION(NRC INSPECTION REPORT 05000260/2006014 AND 05000296/2006014)AND UNIT 1 RECOVERY INSPECTION Dear Mr. Singer:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)Region II staff will conduct a triennial fire protection baseline inspection at the Browns Ferryreactor facilities, Units 2 and 3, in August and September 2006. Mr. George MacDonald, NRCSenior Reactor Inspector, will lead the inspection team, which will be composed of pers

onnelfrom the NRC Region II Office. The inspection will be conducted in accordance with the

NRC'sbaseline fire protection inspection procedure 71111.05T.The inspection objective will be to evaluate your fire protection program implementation withemphasis on post-fire safe shutdown capability and the fire protection features provided toensure at least one post-fire safe shutdown success path is maintained free of fire damage.

The inspection team will focus their review on the separation of the systems and equipmentnecessary to achieve and maintain safe shutdown and the fire protection features of selected

fire areas.On May 31, 2006, during a telephone conversation between Mr. Jim Davenport, LicensingEngineer, and Mr. Paul Fillion, Fire protection Team Leader Region II, our respective staffsconfirmed arrangements for a three-day information gathering onsite visit and a two-week

onsite inspection. The schedule for the inspection is as follows:*Information gathering onsite visit - August 1 - 3, 2006*Week 1 of onsite inspection - August 28 - September 1, 2006

• Week 2 of onsite inspection - September 11 - 15, 2006

TVA2The purposes of the information gathering visit are to obtain information and documentationneeded to support the inspection, and to become familiar with the Browns Ferry fire protectionprogram, fire protection features, post-fire safe shutdown capabilities and plant layout. Thetypes of documents the team will be interested in reviewing, and possibly obtaining, are listed inthe Enclosure.Please contact Mr. MacDonald prior to preparing copies of the materials listed in the Enclosure. The inspection team will try to minimize your administrative burden by specifically identifyingthose documents required for inspection preparation.During the information gathering visit, the team will also discuss the following inspection supportadministrative details - office space, specific documents to be made available to the team in its

office space, arrangements for reactor site access (including radiation protection training,

security, safety and fitness for duty requirements), and the availability of knowledgeable plantengineering and licensing organization personnel to serve as points of contact during the

inspection.Also discussed during the May 31, 2006 telephone conversation, the inspection team

willconduct a Unit 1 recovery inspection in the area of fire protection during September 25 - 29,

2006. At present, the concept of this inspection will be to review the post-fire safe shutdownprocedures that you are preparing in anticipation of Unit 1 restart and any other issues that mayarise from the baseline inspection on Units 2 and 3 that apply to Unit 1. The report number for

the Unit 1 portion of the inspection has not yet been selected.We request that during the inspection weeks you ensure that copies of analyses, evaluations ordocumentation regarding the implementation and maintenance of the Browns Ferry fireprotection program, including post-fire safe shutdown capability, be readily accessible to theteam for its review. Of specific interest are those documents which establish that your fire

protection program satisfies NRC regulatory requirements and conforms to applicable NRC andindustry fire protection guidance. Also, personnel should be available at the site during the

inspection who are knowledgeable regarding those plant systems required to achieve andmaintain safe shutdown conditions from inside and outside the control room (including the

electrical aspects of the relevant post-fire safe shutdown analyses), reactor plant fire protection

systems and features, and the Browns Ferry fire protection program and its implementation.Your cooperation and support during this inspection will be appreciated. If you have questionsconcerning this inspection, or the inspection team's information or logistical needs, please

contact Mr. MacDonald at (404) 562-4543, or me at (404) 562-4567.

TVA3In 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).Sincerely,/RA Paul Fillion for/Edwin Lea., Acting ChiefEngineering Branch 2

Division of Reactor SafetyDocket Nos. 50-259, 50-260, 50-296License Nos. DPR-33, DPR-52, DPR-68Enclosure: Triennial Fire Protection Inspection Support Documentation

TVA4cc w/encl:Ashok S. Bhatnagar

Senior Vice President

Nuclear Operations

Tennessee Valley Authority

Electronic Mail DistributionLarry S. Bryant, Vice PresidentNuclear Engineering & Technical Services

Tennessee Valley Authority

Electronic Mail DistributionBrian O'GradySite Vice President

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail DistributionPreston D. SwaffordSenior Vice President

Nuclear Support

Tennessee Valley Authority

Electronic Mail DistributionGeneral CounselTennessee Valley Authority

Electronic Mail DistributionJohn C. Fornicola, ManagerNuclear Assurance and Licensing

Tennessee Valley Authority

Electronic Mail DistributionBruce M. Aukland, Plant ManagerBrowns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail DistributionGlenn W. Morris, ManagerCorporate Nuclear Licensing

and Industry Affairs

Tennessee Valley Authority

Electronic Mail DistributionWilliam D. Crouch, M

anagerLicensing and Industry Affairs

Browns Ferry Nuclear Plant

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 35611Masoud Bajestani, Vice PresidentBrowns Ferry Unit 1 Restart

Browns Ferry Nuclear Plant

Tennessee Valley Authority

P. O. Box 2000

Decatur, AL 35609Robert G. Jones, General ManagerBrowns Ferry Site Operations

Browns Ferry Nuclear Plant

Tennessee Valley Authority

P. O. Box 2000

Decatur, AL 35609

__ML061530239_

__________OFFICERII:DRSRII:DRPSIGNATURE/RA//RA H. Gepford for/NAMEP. FillionM. WidmannDATE6/ /20067/ /2006E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO

EnclosureNote: This is a broad list of the documents the NRC inspection team may be interestedin reviewing, and possibly obtaining, during the information gathering site visit. The

current version of these documents is expected unless specified otherwise. Electronic

media is preferred, if readily available. (The preferred file format is searchable ".pdf"

files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease ofuse. Please provide 5 copies of each CDROM submitted.) Information in "lists" shouldcontain enough information to be easily understood by someone who has a knowledge

of the technology. The lead inspector will discuss specific information needs with thelicensee staff and may request additional documents.1.The Fire Protection Program document and the Fire Hazards Analysis.

2.The fire protection program implementing procedures (e.g., administrative controls,surveillance testing, fire brigade).3.The fire brigade training program document and the pre-fire plans for the selected fireareas/zones (to be determined during information gathering visit).4.The post-fire safe shutdown analysis, including system and separation analyses.5.The alternative shutdown analysis.

6.Piping and instrumentation (flow) diagrams for the fire suppression systems.7.Piping and instrumentation (flow) diagrams for the systems and components used toachieve and maintain hot shutdown, and cold shutdown, for fires outside the controlroom.8.Piping and instrumentation (flow) diagrams for the systems and components used toachieve and maintain hot shutdown, and cold shutdown, in areas requiring alternative

shutdown capability.9.Plant layout and equipment drawings which identify the physical plant locations of hotshutdown and cold shutdown equipment.10.Plant layout drawings which identify plant fire area and/or fire zone delineation, areasprotected by automatic fire suppression and detection, and the locations of fireprotection equipment for the selected fire areas/zones (to be determined during

information gathering visit).11.Plant layout drawings which identify the general location of the post-fire emergencylighting units.12.Plant operating procedures used to, and describing, shutdown from inside the controlroom with a postulated fire occurring in any plant area outside the control room.

3Enclosure13.Plant operating procedures used to implement the alternative shutdown capability fromoutside the control room with a fire in either the control or cable spreading room (or anyother alternative shutdown area).14.Maintenance and surveillance testing procedures for alternative shutdown capability(including Appendix R emergency lights and communication systems) and fire barriers,detectors, fire pumps and fire suppression systems.15.Calculations and/or justifications that verify fuse/breaker coordination for the selectedfire areas/zones (to be determined during information gathering visit) that are fed off the

same electrical buses as components in the protected train. Also, a list of the

maintenance procedures used to routinely verify fuse/breaker coordination in

accordance with the post-fire safe shutdown coordination analysis.16.A list of the significant fire protection and post-fire safe shutdown design changedescriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter (GL) 86-10 evaluations.17.A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,Section III.G) used to achieve regulatory compliance for the selected fire areas/zones

(to be determined during information gathering visit). That is, please specify whether 3-

hour rated fire barriers (Section III.G.2.a), 20-foot separation along with detection andsuppression (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression(Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for theselected fire areas/zones.18.Procedures or instructions that govern the implementation of plant modifications,temporary modifications, maintenance, and special operations, and their impact on fire

protection.19.Organization chart(s) of site personnel down to the level of the fire protection staff.

20.Procedures or instructions that control the configuration of the fire protection program,features, and post-fire safe shutdown methodology

and system design.21.A list of applicable codes and standards related to the design of plant fire protectionfeatures and evaluations of code deviations (i.e., a listing of the NFPA code editions

committed to (Code of Record)).22.The three most recent fire protection QA audits and/or fire protection self-assessments.

23.A list of open and closed fire protection problem identification and resolution reports[also known as action reports/condition reports/problem reports/problem investigation

reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for thepast three years.

4EnclosureEnclosure24.A list of plant fire protection licensing basis documents (i.e., a list of the SERs andchange evaluations which form the licensing basis for the facility's post-fire safeshutdown configuration).25.A list of fire protection or Appendix R calculations.

26.A list of fire impairments identified during the previous year.

27.A list of abbreviations/designators for plant systems.