ML061570440

Hope Creek Nuclear Generating Station - Notification of Conduct of a Triennial Fire Protection Baseline Inspection

ML061570440
Person / Time
Site:	Hope Creek
Issue date:	06/06/2006
From:	Rogge J F Engineering Region 1 Branch 3
To:	Levis W Public Service Enterprise Group
References
Download: ML061570440 (6)

Text

June 6, 2006Mr. William LevisSenior Vice President and Chief Nuclear Officer PSEG Nuclear LCC - N09

P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK NUCLEAR GENERATING STATION - NOTIFICATION OFCONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Levis:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)Region I staff will conduct a triennial fire protection baseline inspection at your Hope CreekNuclear Generating Station beginning in March 2006. The inspection team will be led by Mr.Leonard Cheung from the NRC Region I Office. The team will be composed of personnel fromNRC Region I. The inspection will be conducted in accordance with IP 71111.05, the NRC'sbaseline fire protection inspection procedure.The schedule for the inspection is as follows:

• Information gathering visit - August 15 - 17, 2006

• Weeks of onsite inspection - August 28 - September 1, 2006, and September 11 - 15, 2006.The purposes of the information gathering visit are to obtain information and documentationneeded to support the inspection, to become familiar with the Hope Creek Nuclear GeneratingStation fire protection programs, fire protection features, and post-fire safe shutdown capabilities and plant layout, and, as necessary, obtain plant specific site access training andbadging for unescorted site access. A list of the types of documents the team is interested in reviewing, and possibly obtaining, are listed in the enclosure. Some of the listed documentsapply only to the fire areas selected for the inspection. The team leader will notify your staff ofthe selected fire areas approximately three weeks before the site visit.During the information gathering visit, the team will also discuss the following inspection supportadministrative details: office space size and location; specific documents requested to be made available to the team in their office spaces; arrangements for reactor site access (including radiation protection training, security, safety and fitness for duty requirements); and the availability of knowledgeable plant engineering and licensing organization personnel to serve aspoints of contact during the inspection. We request that during the onsite inspection weeks you ensure that copies of analyses,evaluations or documentation regarding the implementation and maintenance of the HopeCreek Nuclear Generating Station fire protection program including post-fire safe shutdown Mr. Christopher M. Crane2capability, be readily accessible to the team for their review. Of specific interest, are thosedocuments which establish that your fire protection program satisfies NRC regulatoryrequirements and conforms to applicable NRC and industry fire protection guidance. Also,personnel should be available at the site during the inspection who are knowledgeable regarding those plant systems required to achieve and maintain safe shutdown conditions frominside 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 HopeCreek Nuclear Generating Station 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 Leonard Cheung, the team leader, in the Region I Office at (610) 337-5296.Sincerely,/RA/

John F. Rogge, ChiefEngineering Branch 3 Division of Reactor SafetyDocket No.50-354License No.NPF-57

Enclosure:

List of Reactor Fire Protection Program Supporting Documents cc w/encl:G. Barnes, Site Vice President D. Winchester, Vice President - Nuclear Assessments W. F. Sperry, Director - Business Support D. Benyak, Director - Regulatory Assurance M. Massaro, Hope Creek Plant Manager J. J. Keenan, Esquire M. Wetterhahn, Esquire Consumer Advocate, Office of Consumer Advocate F. Pompper, Chief of Police and Emergency Management Coordinator P. Baldauf, Assistant Director of Radiation Protection and Release Prevention, State of New Jersey K. Tosch, Chief, Bureau of Nuclear Engineering, NJ Dept. of Environmental Protection H. Otto, Ph.D., DNREC Division of Water Resources, State of Delaware N. Cohen, Coordinator - Unplug Salem Campaign W. Costanzo, Technical Advisor - Jersey Shore Nuclear Watch E. Zobian, Coordinator - Jersey Shore Anti Nuclear Alliance Mr. Christopher M. Crane3Distribution w/encl:S. Collins, RA M. Dapas, DRA A. Blough, DRS M. Gray, DRP B. Welling, DRP G. Malone, DRP, Senior Resident Inspector T. Wingfield, DRP, Resident Inspector K. Venuto, DRP, Resident OA B. Sosa, RI OEDO D. Roberts, NRR D. Collins, NRR S. Bailey, PM, NRR Region I Docket Room (with concurrences)SUNSI Review Complete: JFR (Reviewer's Initials

)DOCUMENT NAME: E:\Filenet\ML061570440.wpdAfter declaring this document "An Official Agency Record" it will/will not be released to the Public.To receive a copy of this document, indicate in the box:

" C" = Copy without attachment/enclosure " E" = Copy with attachment/enclosure " N" = No copyOFFICERI/DRSRI/DRSNAMELSCheung/LSCJFRogge/JFRDATE06/02/0606/02/06OFFICENAMEDATEOFFICIAL RECORD COPY ENCLOSUREReactor Fire Protection Program Supporting Documentation[Note: This is a broad list of the documents the NRC inspection team is interested in reviewing,and possibly obtaining, during the information gathering site visit. The team leader will notifythe licensee of the fire areas selected for the inspection approximately three weeks before the site visit.]1.The current version of the Fire Protection Program and Fire Hazards Analysis for theselected fire areas.2.Current versions of the fire protection program implementing procedures (e.g.,administrative controls, surveillance testing, fire brigade). 3.Fire brigade training program.

4.Pre-fire plans for the selected fire areas.

5.Post-fire safe shutdown systems and separation analysis for the selected fire areas. 6.Post-fire alternative shutdown analysis for the selected fire areas.

7.Piping and instrumentation (flow) diagrams showing the components used to achieveand maintain hot standby and cold shutdown for fires outside the control room and thosecomponents used for those areas requiring alternative shutdown capability. 8.Plant layout and equipment drawings which identify the physical plant locations of hotstandby and cold shutdown equipment for a fire in the selected fire areas. 9.Plant layout drawings which identify plant fire area delineation, areas protected byautomatic fire suppression and detection, and the locations of fire protection equipment. 10.Plant layout drawings which identify the general location of the post-fire emergencylighting units.11.Plant operating procedures which would be used and describe shutdown from inside thecontrol room with a postulated fire occurring in any plant area outside the control room,procedures which would be used to implement alternative shutdown capability in theevent of a fire in either the control or cable spreading room. 12.Maintenance and surveillance testing procedures for alternative shutdown capability andfire barriers, detectors, pumps and suppression systems.13.Latest two test results of the Alternate Shutdown Panel surveillances (Note: this itemmay be combined with item 12 if the procedure is included in the test results).14.Latest two test results of fire pump pressure and flow tests (Note: this item may becombined with item 12 if the procedure is included in the test results).

215.Maintenance procedures which routinely verify fuse/breaker coordination in accordancewith the post-fire safe shutdown coordination analysis. 16.A sample of significant fire protection and post-fire safe shutdown related design changepackages and Generic Letter 86-10 evaluations.17.The reactor plant's IPEEE, results of any post-IPEEE reviews, and listings of actionstaken/plant modifications conducted in response to IPEEE information.18.Temporary modification procedures.

19. Organization charts of site personnel down to the level of fire protection staff personnel.

20.If applicable, layout/arrangement drawings of potential reactor coolant/recirculationpump lube oil system leakage points and associated lube oil collection systems.21.A listing of the SERs which form the licensing basis for the reactor plant's post-fire safeshutdown configuration.22.Procedures/instructions that control the configuration of the reactor plant's fire protectionprogram, features, and post-fire safe shutdown methodology and system design.23.A list of applicable codes and standards related to the design of plant fire protectionfeatures and evaluations of code deviations.24.Procedures/instructions that govern the implementation of plant modifications,maintenance, and special operations, and their impact on fire protection.25.The three most recent fire protection Quality Assurance (QA) audits and/or fireprotection self-assessments.26.Recent QA surveillances of fire protection activities.

27.A listing of open and closed fire protection condition reports (problemreports/NCRs/EARs/problem identification and resolution reports) for the past threeyears.28.Listing of plant fire protection licensing basis documents.

29.A listing of the NFPA code versions committed to (NFPA codes of record).

30.A listing of plant deviations from code commitments.

31.Actual copies of Generic Letter 86-10 evaluations.

32.Latest five hot work permits completed during power operation.

33.Latest five transient combustible permits.

334.Latest two test results of main loop flow tests.35.Latest five fire drill critiques (include fire drill(s) for the selected fire areas if applicable).36.Layout drawings and equipment listing of the Alternate Shutdown Panel(s).

37.Appendix R circuit breaker coordination analysis (if dedicated analysis is available).

38.Electrical one-line diagrams for 4160 Vac, 480 Vac, 120 Vac (vital buses) and 125 Vdcsystems.39.Fire fighting communication plan (if available) for fires in the selected fire areas.

40.Latest two inventory results of post-fire cold shutdown equipment.

41.Fire Protection System health reports.