ML071570377

Notification of Conduct of a Triennial Fire Protection Baseline Inspection

ML071570377
Person / Time
Site:	Millstone
Issue date:	06/05/2007
From:	Rogge J F Engineering Region 1 Branch 3
To:	Christian D A Dominion Resources Services
References
Download: ML071570377 (7)

Text

June 5, 2007Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT 3 - NOTIFICATION OF CONDUCT OFA TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Christian:

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 Millstone Power Station, Unit 3 beginning in September 2007. The inspection team will be led by Dan Orr from the NRC Region I office. The team will be composed of personnel from the NRC Region I. The inspection will be conducted in accordance with NRC inspection procedure 71111.05T, the NRC's baseline fire protection inspection procedure.The schedule for the inspection is as follows:

Information gathering visit - Week of September 4, 2007 Weeks of onsite inspection - September 17 - 21 and October 1 - 5, 2007The purposes of the information gathering visit are to obtain information and documentationneeded to support the inspection, to become familiar with the station fire protection programs, fire protection features, and post-fire safe shutdown capabilities and plant layout, and, as necessary, obtain plant specific site access training and badging for unescorted site access. A list of the types of documents the team may be interested in reviewing and possibly obtaining, are listed in Enclosure 1. The team leader will contact you with specific document requests prior to the information gathering 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 as points of contact during the inspection. We request that during the onsite inspection week you ensure that copies of analyses,evaluations, or documentation regarding the implementation and maintenance of the Millstone Power Station, Unit 3 fire protection program, including post-fire safe shutdown capability, be 2Mr. David A. Christianreadily accessible to the team for their review. Of specific interest are those documents whichestablish that your fire protection program satisfies NRC regulatory requirements 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 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 Millstone Power Station, Unit 3 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 Dan Orr, the team leader in the Region I Office at (610) 337-5048.Sincerely,/RA/John F. Rogge, ChiefEngineering Branch 3 Division of Reactor SafetyDocket Nos. 50-423License No. NPF 49

Enclosure:

List of Reactor Fire Protection Program Supporting Documents 2Mr. David A. Christianestablish that your fire protection program satisfies NRC regulatory requirements and conformsto 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 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 Millstone Power Station, Unit 3 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 Dan Orr, the team leader in the Region I Office at (610) 337-5048.Sincerely,John F. Rogge, ChiefEngineering Branch 3 Division of Reactor SafetyDocket Nos. 50-423License No. NPF 49

Enclosure:

List of Reactor Fire Protection Program Supporting Documents SUNSI Review Complete: JFR (Reviewer's Initials

)ML071570377DOCUMENT NAME: C:\FileNet\ML071570377.wpdAfter declaring this document "An Official Agency Record" it will be released to the Public.To receive a copy of this document, indicate in the box:

" C" = Copy without attachment/enclosure " E" = Copy withattachment/enclosure " N" = No copyOFFICERI/DRSRI/DRSNAMEJDOrr/JDOJFRogge/JFRDATE06/05/0706/05/07OFFICENAMEDATEOFFICIAL RECORD COPY 3Mr. David A. Christiancc w/encl:

J. A. Price, Site Vice President, Millstone Station C. L. Funderburk, Director, Nuclear Licensing and Operations Support D. W. Dodson, Supervisor, Station Licensing L. M. Cuoco, Senior Counsel C. Brinkman, Manager, Washington Nuclear Operations J. Roy, Director of Operations, Massachusetts Municipal Wholesale Electric Company First Selectmen, Town of Waterford B. Sheehan, Co-Chair, NEAC E. Woollacott, Co-Chair, NEAC E. Wilds, Director, State of Connecticut SLO Designee J. Buckingham, Department of Public Utility Control G. Proios, Suffolk County Planning Dept.

R. Shadis, New England Coalition Staff G. Winslow, Citizens Regulatory Commission (CRC)

S. Comley, We The People D. Katz, Citizens Awareness Network (CAN)

R. Bassilakis, CAN J. M. Block, Attorney, CAN P. Eddy, Electric Division, Department of Public Service, State of New York M. Balboni, Deputy Secy, New York State Energy Research and Development Authority J. Spath, SLO Designee, New York State Energy Research and Development Authority 4Mr. David A. ChristianDistribution w/encl:(via E-mail)S. Collins, RA M. Dapas, DRA J. Lamb, RI OEDO H. Chernoff, NRR J. Lubinski, NRR J. Hughley NRR, PM E. Miller, NRR R. Treadway, Acting Senior Resident Inspector J. Benjamin, Resident Inspector R. Powell, DRP B. Norris, DRP M. Gamberoni, DRS J. Rogge, DRS J. Orr, DRS Region I Docket Room (with concurrences)

ENCLOSURE Reactor Fire Protection Program Supporting Documentation[Note: This is a broad list of the documents the NRC inspection team may be interested inreviewing, and possibly obtaining, during the information gathering site visit.]1.The current version of the Fire Protection Program and Fire Hazards Analysis.

2.Current versions of the fire protection program implementing procedures (e.g.,administrative controls, surveillance testing, fire brigade). 3.Fire brigade training program and pre-fire plans.

4.Post-fire safe shutdown systems and separation analysis.

5.Post-fire alternative shutdown analysis.

6.Piping and instrumentation (flow) diagrams showing the systems and components usedto achieve and maintain hot standby and cold shutdown for fires outside the control room and those components used for those areas requiring alternative shutdown capability. 7.Plant layout and equipment drawings which identify the physical plant locations of hotstandby and cold shutdown equipment. 8.Plant layout drawings which identify plant fire area delineation, areas protected byautomatic fire suppression and detection, and the locations of fire protection equipment. 9.Plant layout drawings which identify the location of the post-fire emergency lightingunits.10.Plant operating procedures which would be used for shutdown from the control roomwith a postulated fire occurring in any plant area outside the control room, and procedures which would be used to implement alternative shutdown capability in the event of a fire in either the control or cable spreading room. 11.Maintenance and surveillance testing procedures for alternative shutdown capability andfire barriers, detectors, pumps and suppression systems. (Last completed copy.)12.Maintenance procedures which routinely verify fuse breaker coordination in accordancewith the post-fire safe shutdown coordination analysis. 13.A list of fire protection and post-fire safe shutdown related design change packages(including their associated 10 CFR 50.59 evaluations) and Generic Letter 86-10 evaluations.14.The reactor plant's IPEEE, results of any post-IPEEE reviews, and listings of actionstaken/plant modifications conducted in response to IPEEE information.

215.Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.)16. Organization charts of site personnel down to the level of fire protection staff personnel.

17.A listing of the SERs which form the licensing basis for the reactor plant's post-fire safeshutdown configuration.18.A list of applicable codes and standards related to the design of plant fire protectionfeatures and evaluations of code deviations.19.Procedures/instructions that govern the implementation of plant modifications,temporary modifications, maintenance, and special operations, and their impact on fire protection.20.The three most recent fire protection QA audits and/or fire protection self-assessments.

21.Recent QA surveillances of fire protection activities.

22.A listing of open fire protection and fire safe shutdown related condition reports.

23.A listing of fire protection and fire safe shutdown condition reports closed in the pastthree years.24.Fire protection system health reports (last 2).

25.Lesson Plans and related training information for licensed and non-licensed operatorsfor post-fire safe shutdown (including alternative shutdown).