ML023260353

Notification of Triennial Fire Protection Baseline Inspection (NRC Inspection Report Nos. 50-280, 281/2003-005) at Surry Power Station in January & February 2003

ML023260353
Person / Time
Site:	Surry
Issue date:	11/21/2002
From:	Ogle C Division of Reactor Safety II
To:	Christian D Virginia Electric & Power Co (VEPCO)
References
IR-03-005
Download: ML023260353 (6)

See also: IR 05000280/2003005

Text

NOVEMBER 21, 2002

Virginia Electric and Power Company

ATTN: Mr. David A. Christian

Senior Vice President and

Chief Nuclear Officer

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060

SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION,

(NRC INSPECTION REPORT NOS. 50-280, 281/2003-005)

Dear Mr. Christian:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a triennial fire protection baseline inspection at the Surry Power

Station in January and February 2003. The inspection team will be led by Mr. Charles Payne,

Fire Protection Team Leader, of the Region II Office. The team will be composed of personnel

from the NRC Region II Office and conducted in accordance with the NRCs baseline fire

protection inspection procedure 71111.05.

The inspection objective will be to evaluate your fire protection program implementation with

emphasis on post-fire safe shutdown capability and the fire protection features provided to

ensure at least one post-fire safe shutdown success path is maintained free of fire damage.

The inspection team will focus their review of the separation of the systems and equipment

necessary to achieve and maintain safe shutdown and fire protection features of selected fire

areas.

On November 21, 2002, during a telephone conversation with Mr. Barry Garber, Licensing

Engineer, our respective staffs confirmed arrangements for a three-day information gathering

onsite visit and a two-week onsite inspection. The schedule for the inspection is as follows:

 Information gathering onsite visit - January 7 - 9, 2003

 Week 1 of onsite inspection - January 27 - 31, 2003

 Week 2 of onsite inspection - February 10 - 14, 2003

The purposes of the information gathering visit are to obtain information and documentation

needed to support the inspection; to become familiar with the Surry fire protection program, fire

protection features, post-fire safe shutdown capabilities and plant layout; and, as necessary, to

obtain plant specific site access training and badging for unescorted site access. The types of

documents the team will be interested in reviewing, and possibly obtaining, are listed in the

Enclosure. Please contact Mr. Payne prior to preparing copies of the materials listed in the

Enclosure. The inspection team will try to minimize your administrative burden by specifically

identifying those documents required for inspection preparation.

VEPCO 2

During the information gathering visit, the team will also discuss the following inspection support

administrative details: office space; 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 inspection weeks you ensure that copies of analyses, evaluations or

documentation regarding the implementation and maintenance of the Surry 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 Surry 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. Payne at (404) 562-4669, or me at (404) 562-4605.

Sincerely,

/RA/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-280, 50-281

License Nos.: DPR-32, DPR-37

Enclosure: Triennial Fire Protection Inspection

Support Documentation

cc w/encl:

Stephen P. Sarver, Director

Nuclear Licensing and

Operations Support

Virginia Electric & Power Company

Electronic Mail Distribution

(cc w/encl contd - See page 3)

VEPCO 3

(cc w/encl contd)

Richard H. Blount, II

Site Vice President

Surry Power Station

Virginia Electric & Power Company

Electronic Mail Distribution

Virginia State Corporation Commission

Division of Energy Regulation

P. O. Box 1197

Richmond, VA 23209

Lillian M. Cuoco, Esq.

Senior Nuclear Counsel

Dominion Nuclear Connecticut, Inc.

Electronic Mail Distribution

Attorney General

Supreme Court Building

900 East Main Street

Richmond, VA 23219

Distribution w/encl:

G. Edison, NRR

RIDSNRRDIPMLIPB

PUBLIC

OFFICE RII:DRS RII:DRP RII:DRS

SIGNATURE PAYNE LANDIS OGLE

NAME PAYNE LANDIS OGLE

DATE 11/ 21/2002 11/21/2002 11/21/2002 11/ /2002 11/ /2002 11/ /2002 11/ /2002

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

OFFICIAL RECORD COPY DOCUMENT NAME: C:\ORPCheckout\FileNET\ML023260353.wpd

Triennial Fire Protection Inspection Support 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. The

current version of these documents is expected unless specified otherwise. Electronic

media is preferred if readily available (i.e., on CD-ROM or computer disc). If electronic

media is offered, we request that an index of files or a simple menu be provided.]

1. The Fire Protection Program and the Fire Hazards Analysis.

2. The fire protection program implementing procedures (e.g., administrative controls,

surveillance testing, fire brigade).

3. The 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 those 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.

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 the control, the cable spreading room or any other Appendix R, Section

III.G.3 designated fire 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 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.

Enclosure

2

14. The reactor plants IPEEE, results of any post-IPEEE reviews, and a list of actions taken

or plant modifications conducted in response to IPEEE information.

15. Temporary modification procedure(s).

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 pump lube oil

system leakage points and associated lube oil collection systems.

18. A list of the SERs which form the licensing basis for the post-fire safe shutdown

configuration.

19. Procedures/instructions that control the configuration of the 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 QA audits and/or fire protection self-assessments.

23. Recent QA surveillances of fire protection activities.

24. A list of open and closed fire protection problem identification and resolution reports

[also known as action reports/condition reports/problem reports/problem investigation

reports/NCRs/EARs].

25. A list of plant fire protection licensing basis documents.

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

27. A list of plant deviations from code commitments.

Enclosure