ML083590110

Notification of Conduct of a Triennial Fire Protection Baseline Inspection

ML083590110
Person / Time
Site:	Peach Bottom
Issue date:	12/23/2008
From:	Rogge J Engineering Region 1 Branch 3
To:	Pardee C AmerGen Energy Co
References
Download: ML083590110 (7)

Text

December 23, 2008 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear Chief Nuclear Officer (CNO)

AmerGen Energy Company, LLC 4300 Winfield Rd.

Warrenville, IL 60555

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Pardee:

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 Peach Bottom Atomic Power Station beginning in March 2009. The inspection team will be led by Larry Scholl 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 NRCs baseline fire protection inspection procedure.

The schedule for the inspection is as follows:

• Information gathering visit - Week of March 1, 2009

• Weeks of onsite inspection - March 16-20 and March 30-April 3, 2009 The purposes of the information gathering visit are to obtain information and documentation needed 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 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 support administrative 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.

Enclosure

Mr. C. Pardee 2 We request that during the onsite inspection week you ensure that copies of analyses, evaluations, or documentation regarding the implementation and maintenance of the Peach Bottom Atomic Power Station fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest are those documents which establish that your fire protection program satisfies NRC regulatory requirements and conforms to applicable NRC and industry fire protection guidance. Also, personnel should be available as 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 Peach Bottom Atomic Power Station fire protection program and its implementation.

Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection, or the inspection teams information or logistical needs, please contact Larry Scholl, the team leader in the Region I Office at (610) 337-5144.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-277; 50-278 License Nos.: DPR-44, DPR-56

Enclosure:

List of Reactor Fire Protection Program Supporting Documents

Mr. C. Pardee 2 We request that during the onsite inspection week you ensure that copies of analyses, evaluations, or documentation regarding the implementation and maintenance of the Peach Bottom Atomic Power Station fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest are those documents which establish that your fire protection program satisfies NRC regulatory requirements and conforms to applicable NRC and industry fire protection guidance. Also, personnel should be available as 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 Peach Bottom Atomic Power Station fire protection program and its implementation.

Your cooperation and support during this inspection will be appreciated. If you have questions concerning this inspection, or the inspection teams information or logistical needs, please contact Larry Scholl, the team leader in the Region I Office at (610) 337-5144.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-277; 50-278 License Nos.: DPR-44, DPR-56

Enclosure:

List of Reactor Fire Protection Program Supporting Documents SUNSI Review Complete: JFR (Reviewers Initials) ADAMS ACC#ML083590110 DOCUMENT NAME: G:\DRS\Engineering Branch 3\Scholl\Peach Bottom Triennial Fire Protection 90 Day Letter.doc After 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 with attachment/enclosure "N" = No copy OFFICE RI/DRS RI/DRS NAME LScholl/DS/LS JRogge/JR DATE 12/19/2008 12/23/2008 OFFICIAL RECORD COPY

Mr. C. Pardee 3 cc w/encl:

C. Crane, President and Chief Operating Officer, Exelon Corporation M. Pacilio, Chief Operating Officer, Exelon Nuclear W. Maguire, Site Vice President, Peach Bottom R. DeGregorio, Senior Vice President, Mid-Atlantic R. Hovey, Senior Vice President, Nuclear Oversight G. Stathes, Acting Plant Manager, Peach Bottom J. Armstrong, Regulatory Assurance Manager, Peach Bottom J. Bardurski, Manager, Financial Control & Co-Owner Affairs B. Franssen, Acting Director, Operations P. Cowan, Director, Licensing D. Helker, Licensing K. Jury, Vice President, Licensing and Regulatory Affairs J. Bradley Fewell, Associate General Counsel, Exelon T. Wasong, Director, Training Correspondence Control Desk D. Allard, Director, Bureau of Radiation Protection, PA Department of Environmental Protection S. Gray, Power Plant and Environmental Review Division (MD)

S. Pattison, Secretary, MD Department of the Environment M. Griffen, Maryland Department of Environment A. Lauland, Director, Homeland Security Advisor Public Service Commission of Maryland, Engineering Division Board of Supervisors, Peach Bottom Township B. OConnor, Council Administrator of Harford County Council R. Ayers, Deputy Mgr, Harford County Div of Emergency Operations E. Crist, Harford County Div of Emergency Operations S. Ayers, Emergency Planner, Harford County Div of Emergency Operations R. Brooks, Cecil County Dept of Emergency Services Mr & Mrs Dennis Hiebert, Peach Bottom Alliance E. Epstein, TMI - Alert J. Johnsrud, National Energy Committee, Sierra Club Mr. & Mrs. Kip Adams R. Fletcher, Dir, MD Environmental Program Manager, Radiological Health Program J. Powers, Director, PA Office of Homeland Security R. French, Dir, PA Emergency Management Agency D. Lockbaum, Union of Concerned Scientists Enclosure

Mr. C. Pardee 4 Distribution w/encl: (via E-mail)

S. Collins, RA M. Dapas, DRA D. Roberts, DRS J. Rogge, DRS L. Scholl, DRS D. Lew, DRP J. Clifford, DRP P. Krohn, DRP R. Fuhrmeister, DRP T. Setzer, DRP F. Bower, DRP, Senior Resident Inspector M. Brown, DRP, Resident Inspector S. Schmitt, DRP, Resident OA S. Williams, RI OEDO H. Chernoff, NRR R. Nelson, NRR J. Hughey, PM NRR P. Bamford, Backup NRR Region I Docket Room (with concurrences)

Enclosure

ENCLOSURE Reactor Fire Protection Program Supporting Documentation

[Note: This is a broad list of the documents the NRC inspection team may be interested in reviewing, and possibly obtaining, during the information gathering site visit.]

1. The current version of the Fire Protection Program and Fire Hazards Analysis.

2. Electronic copy of current versions of the Updated Final Safety Analysis Report (FSAR),

Technical Specifications, and Operating License.

3. Current versions of the fire protection program implementing procedures (e.g.,

administrative controls, surveillance testing, and fire brigade.)

4. Fire brigade training program and pre-fire plans.

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

6. Post-fire alternative shutdown analysis.

7. Piping and instrumentation (flow) diagrams showing the systems and components used to 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. (Reactor Core Isolation Cooling, Residual Heat Removal, Control Rod Drive, Condensate and Feedwater, High Pressure Coolant Injection, Core Spray, Emergency Service Water, RHR Service Water, Instrument Air, Component Cooling, Main Steam, Reactor Coolant and Reactor Water Cleanup Systems)

8. Plant layout drawings which identify plant fire area delineation, areas protected by automatic fire suppression and detection, and the locations of fire protection equipment.

9. Plant layout drawings which identify the location of post-fire emergency lighting units.

10. Plant operating procedures which would be used for shutdown from the control room with 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. Copy of most recently completed maintenance and surveillance testing procedures for alternative shutdown capability components, fire barriers, fire detectors, fire pumps and suppression systems.

12. Maintenance procedures which routinely verify fuse and circuit breaker coordination in accordance with 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.

Enclosure

Mr. C. Pardee 4

14. Copies of AC and DC electrical system one line diagrams. (From offsite power grid connections down to the 120 volt level.)

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

16. A listing of the SERs which form the licensing basis for the reactor plants post-fire safe shutdown configuration.

17. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations.

18. The three most recent fire protection QA audits and/or fire protection self-assessments.

19. Recent (last 12 months) QA surveillances of fire protection activities.

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

21. A listing of fire protection and fire safe shutdown condition reports closed in the past three years.

22. Fire protection system health reports (last 2).

23. Lesson plans and related training information for licensed and non-licensed operators for post-fire safe shutdown (including alternative shutdown).

Enclosure