ML062840547

Notification of Conduct of a Triennial Fire Protection Baseline Inspection While Transition to 10 CFR 50.48(c) Is in Progress

ML062840547
Person / Time
Site:	Beaver Valley
Issue date:	10/11/2006
From:	Rogge J Engineering Region 1 Branch 3
To:	Lash J FirstEnergy Nuclear Operating Co
References
Download: ML062840547 (7)

Text

October 11, 2006 Mr. James Lash Site Vice President, Beaver Valley Power Station FirstEnergy Nuclear Operating Company Post Office Box 4 Shipping Port, Pennsylvania 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION WHILE TRANSITION TO 10 CFR 50.48(c) IS IN PROGRESS

Dear Mr. Lash:

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 Beaver Valley Power Station, Units 1 and 2, beginning in January 22, 2007. The inspection team will be led by Mr. Leonard Cheung, a fire protection specialist from the NRC Region I Office. The team will be composed of personnel from NRC Region I. The inspection will be conducted in accordance with IP 71111.05TP, the NRCs baseline fire protection inspection procedure for plants in the process of implementing 10 CFR 50.48(c), NFPA 805. The inspection will focus on the fire protection program infrastructure and the evaluation of the adequacy of any compensatory measures implemented. The inspectors will not routinely inspect or evaluate circuit related issues.

The schedule for the inspection is as follows:

• Information gathering visit - January 8 - 10, 2007

• Weeks of onsite inspection - January 22 - 26, 2007, and February 5 - 9, 2007.

The purposes of the information gathering visit are to obtain information and documentation needed to support the inspection, to become familiar with the Beaver Valley Power 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 the enclosure.

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 weeks you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the Beaver Valley 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 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 Beaver Valley 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 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, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-334, 50412 License Nos. DPR-66, NPF-73

Enclosure:

List of Reactor Fire Protection Program Supporting Documents

cc w/encl:

G. Leidich, President and Chief Nuclear Officer J. Hagan, Senior Vice President of Operations and Chief Operating Officer D. Pace, Senior Vice President, Fleet Engineering J. Rinckel, Vice President, Fleet Oversight L. Myers, Executive Vice President, Special Projects R. Anderson, Vice President, FirstEnergy Nuclear Operating Company Manager, Fleet Licensing, FirstEnergy Nuclear Operating Company R. Mende, Director, Site Operations T. Cosgrove, Director, Maintenance P. Sena, Director, Engineering L. Freeland, Director, Site Performance Improvement and Manager, Regulatory Compliance D. Jenkins, Attorney, FENOC B. Sepelak, Supervisor, Nuclear Compliance M. Clancy, Mayor, Shippingport, PA D. Allard, PADEP C. OClaire, State Liaison to the NRC, State of Ohio Z. Clayton, EPA-DERR, State of Ohio Director, Utilities Department, Public Utilities Commission, State of Ohio D. Hill, Chief, Radiological Health Program, State of West Virginia J. Lewis, Commissioner, Division of Labor, State of West Virginia W. Hill, Beaver County Emergency Management Agency J. Johnsrud, National Energy Committee, Sierra Club

Distribution w/encl:

S. Collins, RA M. Dapas, DRA R. Bellamy, DRP R. Fuhrmeister, DRP A. Blough, DRS L. Cheung, DRS J. Rogge, DRS B. Sosa, OEDO R. Laufer, NRR T. Colburn, PM, NRR R. Guzman, NRR P. Cataldo - Senior Resident Inspector P. Garrett - Resident OA Region I Docket Room (with concurrences)

SUNSI Review Complete: JFR (Reviewers Initials)

DOCUMENT NAME: g:\drs\eb3\cheung\BV1&2FPletter.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 RI/DRS NAME LCheung/LSC JRogge/JFR DATE 10/06/06 10/11/06 OFFICE NAME DATE OFFICIAL RECORD COPY

ENCLOSURE Reactor 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 notify the licensee of the fire areas selected for the inspection approximately two weeks before the 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.

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

5. Post-fire alternative shutdown analysis.

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, 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 and fire barriers, detectors, pumps and suppression systems.

12. Maintenance procedures which routinely verify fuse breaker coordination in accordance with the post-fire safe shutdown coordination analysis.

13. A sample of significant fire protection and post-fire safe shutdown related design change packages and Generic Letter 86-10 evaluations.

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

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15. Temporary modification procedures.

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

17. If applicable, layout/arrangement drawings of potential reactor coolant/recirculation pump lube oil system leakage points and associated lube oil collection systems.

18. A listing of the SERs which form the licensing basis for the reactor plant's post-fire safe shutdown configuration.

19. Procedures/instructions that control the configuration of the reactor plant's fire protection program, features, and post-fire safe shutdown methodology and system design.

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

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

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

23. Recent QA surveillances of fire protection activities.

24. A listing of open and closed fire protection condition reports (problem reports/NCRs/EARs/problem identification and resolution reports) for the past three years.

25. Listing of plant fire protection licensing basis documents.

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

27. A listing of plant deviations from code commitments.

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

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

29. Latest five transient combustible permits.

30. Latest two test results of fire pump pressure and flow tests.

31. Latest two test results of main loop flow tests.

32. Latest five fire drill critiques (include fire drill(s) for the selected fire areas if applicable).

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

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34. Layout drawings and equipment listing for the Alternate Shutdown Panel(s).

35. Latest two test results of the Alternate Shutdown Panel surveillances.

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

37. Electrical one-line diagrams for 4160 Vac, 480 Vac, 120 Vac (vital buses) and 125 Vdc systems.

38. Fire fighting communication plan (if available) for fires in the selected fire areas.

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

40. Fire Protection System health reports.