ML091670141

Notification of Conduct of a Triennial Fire Protection Baseline Inspection

ML091670141
Person / Time
Site:	Pilgrim
Issue date:	06/15/2009
From:	Rogge J Engineering Region 1 Branch 2
To:	Bronson K Entergy Nuclear Operations
References
Download: ML091670141 (7)

Text

June 15, 2009 Mr. Kevin Bronson Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508

SUBJECT:

PILGRIM NUCLEAR POWER STATION - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Bronson:

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 Pilgrim Nuclear Power Station beginning in September 2009. The inspection team will be led by Jennifer Tifft 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 August 31, 2009

• Weeks of onsite inspection - September 14-18 and September 28-October 2, 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.

We request that during the onsite inspection week you ensure that copies of analyses, evaluations, or documentation regarding the implementation and maintenance of the Pilgrim Nuclear Power Station fire protection program, including post-fire safe shutdown capability, be Enclosure

Mr. K. Bronson 2 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 Pilgrim Nuclear 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 Jennifer Tifft, the team leader in the Region I Office at (610) 337-5273.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-293 License No. DPR-35

Enclosure:

List of Reactor Fire Protection Program Supporting Documents

Mr. K. Bronson 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 Pilgrim Nuclear 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 Jennifer Tifft, the team leader in the Region I Office at (610) 337-5273.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-293 License No. DPR-35

Enclosure:

List of Reactor Fire Protection Program Supporting Documents SUNSI Review Complete: JFR (Reviewers Initials) ADAMS ACC#ML091670141 DOCUMENT NAME: G:\DRS\Engineering Branch 3\JTifft\Pilgrim 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 JTifft/DS/LScholl for JRogge/JFR DATE 06/12/09 06/15/09 OFFICIAL RECORD COPY

3 cc w/encl:

Vice President, Operations, Entergy Nuclear Operations Vice President, Oversight, Entergy Nuclear Operations Senior Manager, Nuclear Safety & Licensing, Entergy Nuclear Operations Senior Vice President and COO, Entergy Nuclear Operations Assistant General Counsel, Entergy Nuclear Operations R. Walker, Director, Radiation Control Program, Commonwealth of Massachusetts The Honorable Therese Murray The Honorable Vincent deMacedo Chairman, Plymouth Board of Selectmen Chairman, Duxbury Board of Selectmen Chairman, Nuclear Matters Committee Plymouth Civil Defense Director D. OConnor, Massachusetts Secretary of Energy Resources J. Miller, Senior Issues Manager Office of the Commissioner, Massachusetts Department of Environmental Protection Office of the Attorney General, Commonwealth of Massachusetts Electric Power Division, Commonwealth of Massachusetts R. Shadis, New England Coalition Staff D. Katz, Citizens Awareness Network W. Meinert, Nuclear Engineer J. Giarrusso, MEMA, SLO Commonwealth of Massachusetts, Secretary of Public Safety Enclosure

Mr. K. Bronson 4 Distribution w/encl: (via E-mail)

S. Collins, RA M. Dapas, DRA D. Lew, DRP J. Clifford, DRP L. Trocine, RI OEDO M. Gray, DRP B. Bickett, DRP A. Rosebrook, DRP S. McCarver, DRP M. Kowal, NRR J. Kim, PM, NRR J. Boska, NRR R. Nelson, NRR M. Schneider, DRP, Senior Resident Inspector B. Smith, DRP, Resident Inspector A. Ford, DRP, Resident OA Region I Docket Room (with concurrences)

J. Rogge, DRS J. Tifft, DRS L. Scholl, DRS 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, Operating License and Technical Requirements Manual (TRM).

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 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, Feedwater, High Pressure Coolant Injection, Core Spray, Emergency Service Water, RHR Service Water, Instrument Air, Component Cooling, Main Steam, Reactor Coolant, Reactor Water Cleanup, Nuclear Boiler, and Nuclear Boiler Vessel Instrumentation 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.

Enclosure

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. 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 safety evaluation reports (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