ML022770153

Notification of Conduct of a Triennial Fire Protection Baseline Inspection

ML022770153
Person / Time
Site:	Oyster Creek
Issue date:	10/04/2002
From:	Linville J Division of Nuclear Materials Safety I
To:	Skolds J Exelon Generation Co
References
Download: ML022770153 (6)

Text

October 4, 2002 Mr. Jack Skolds President and CNO Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road 5th Floor Warrenville, IL 60555

SUBJECT:

OYSTER CREEK - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Skolds:

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 the Oyster Creek Generating Station in December, 2002. The inspection team will be led by Mr. Chris Cahill, a senior reactor inspector from the NRC Region I Office. The team will be composed of NRC personnel. The inspection will be conducted in accordance with IP 71111.05, the NRCs baseline fire protection inspection procedure.

The schedule for the inspection is as follows:

• Information gathering visit - Week of November 24, 2002

• Onsite inspection - Weeks of December 15, 2002 and January 5, 2003 The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the Oyster Creek Generating 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. The types of documents the team may be interested in reviewing, and possibly obtaining, are listed in Enclosure 1. The inspection team leader will contact you with specific document requests and inform you of plant areas for inspection focus.

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 and safety); and the availability of knowledgeable plant engineering and licensing organization personnel to serve as points of contact during the inspection.

Mr. J. Skolds 2 We request that during the onsite inspection you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the Oyster Creek Generating 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 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 Oyster Creek Generating 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 Mr. Chris Cahill, the team leader, in the Region I Office at (610) 337-5108 or by e-mail at CGC@nrc.gov.

Sincerely,

/RA/

James C. Linville, Chief Electrical Branch Division of Reactor Safety Docket Nos. 50-219 Licensee Nos. DPR-16

Enclosure:

List of Reactor Fire Protection Program Supporting Documents

Mr. J. Skolds 3 cc w/encl:

Amergen Energy Company - Correspondence Control Deck President and CNO, Exelon Nuclear Vice President - Oyster Creek Licensing and Regulatory Affairs- Vice President, Exelon Corporation Director-Licensing Regulatory Assurance Manager R. Shadis, New England Coalition Staff State of New Jersey N. Cohen, Coordinator - Unplug Salem Campaign E. Gbur, Coordinator - Jersey Shore Nuclear Watch E. Zobian, Coordinator - Jersey Shore Anti Nuclear Alliance

Mr. J. Skolds 4 Distribution w/encl:

Region I Docket Room (with concurrences)

R. Summers, DRP - NRC Resident Inspector H. Miller, RA J. Wiggins, DRA J. Rogge, DRP S. Shaffer, DRP C. Bixler, DRP W. Lanning, DRS H. Nein, OEDO S. Richards, NRR P. Tam, PM, NRR T. Colburn, PM, NRR DOCUMENT NAME: C:\ORPCheckout\FileNET\ML022770153.wpd 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 E RI/DRS NAME CCahill JLinville DATE 10/03/02 10/03/02 OFFICIAL RECORD COPY

ENCLOSURE 1 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. Current versions of the fire protection program implementing procedures (e.g.,

administrative controls, surveillance testing, fire brigade, technical requirements manual).

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

4. Post-fire safe shutdown analysis, including systems and separation analysis, as well as alternative shutdown analysis.

5. Piping and instrumentation (flow) diagrams for fire protection suppression systems.

6. Piping and instrumentation (flow) diagrams showing the 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.

7. Plant layout and equipment drawings which identify the physical plant locations of hot standby and cold shutdown equipment.

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 general location of the post-fire emergency lighting units.

10. Plant operating procedures which would be used and describe shutdown from inside 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 (or any other alternative shutdown area).

11. Maintenance and surveillance testing procedures for alternative shutdown capability and fire barriers, detectors, 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. Significant fire protection and post-fire safe shutdown related design change packages (including the associated 10 CFR 50.59 evaluations) and Generic Letter 86-10 evaluations.

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14. The reactor plants IPEEE, results of any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in response to IPEEE information associated with fires.

15. Procedures/instructions that govern the implementation of plant modifications, temporary modifications, maintenance, and special operations, and their impact on fire protection.

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

17. Listing of plant fire protection licensing basis documents (i.e., a listing of the SERs and change evaluations which form the licensing basis for the reactor plants post-fire safe shutdown configuration).

18. Procedures/instructions that control the configuration of the reactor plants fire protection program, features, and post-fire safe shutdown methodology and system design.

19. A list of applicable codes and standards related to the design of plant fire protection features and evaluations of code deviations (i.e, a listing of the NFPA code versions committed to (NFPA codes of record)).

20. A listing of all open condition reports associated with fire protection or Appendix R safe shutdown issues (problem reports/NCRs/EARs/problem identification and resolution reports).

21. A listing of condition reports associated with fire protection or Appendix R safe shutdown issues (problem reports/NCRs/EARs/problem identification and resolution reports) that have been closed within the last three years.

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

23. Copies of QA surveillances of fire protection activities performed in the last three years.

24. Electrical one-line drawings showing the power supplies (normal and emergency) for hot standby and cold shutdown equipment (including instrumentation and control circuits necessary for safe shutdown).