ML060660023

Notification of Triennial Fire Protection Baseline Inspection, NRC Inspection Report 05000280-06-009 and 05000281-06-009

ML060660023
Person / Time
Site:	Surry
Issue date:	03/06/2006
From:	Payne D NRC/RGN-II/DRS/EB2
To:	Christian D Virginia Electric & Power Co (VEPCO)
References
IR-06-009
Download: ML060660023 (7)

See also: IR 05000280/2006009

Text

March 6, 2006

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 05000280/2006009 AND 05000281/2006009)

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, Units 1 and 2, in June 2006. The inspection team will be led by Mr. McKenzie Thomas,

NRC Senior Reactor Inspector, of the Region II Office. The team will be composed of

personnel from the NRC Region II Office and a contractor. The inspection will be conducted in

accordance with the NRCs baseline fire protection inspection procedure 71111.05T.

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 on the separation of the systems and equipment

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

fire areas.

On March 2, 2006, during a telephone conversation between Mr. Barry Garber, Surry Licensing

Supervisor, and Mr. Thomas, 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 visit: May 16-18, 2006

• Week 1 of onsite inspection: June 12-16, 2006

• Week 2 of onsite inspection: June 26-30, 2006

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

needed to support the inspection, and to become familiar with the Surry Power Station fire

protection program, fire protection features, post-fire safe shutdown capabilities and plant

layout. The types of documents the team will be interested in reviewing, and possibly obtaining,

are listed in the Enclosure.

VEPCO 2

Please contact Mr. Thomas 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.

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

administrative details - office space; specific documents to be made available to the team in its

office space; 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 its 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 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 Mr. Thomas at (404) 562-4673, or me at (404) 562-4669.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its

enclosure will be available electronically for public inspection in the NRC Public Document

Room or from the Publicly Available Records (PARS) component of NRCs document system

(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

Sincerely,

\\RA\\

D. Charles Payne, Chief

Engineering Branch 2

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: (See page 3)

VEPCO 3

cc w/encl:

Chris L. Funderburk, Director

Nuclear Licensing and

Operations Support

Virginia Electric & Power Company

Electronic Mail Distribution

Donald E. Jernigan

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 Counsel

Dominion Resources Services, Inc.

Electronic Mail Distribution

Attorney General

Supreme Court Building

900 East Main Street

Richmond, VA 23219

_________________________

OFFICE RII:DRS RII:DRS RII:DRP RII:DRS

SIGNATURE MXT2 PJF KDL DCP

NAME M. Thomas P. Fillion K. Landis C. Payne

DATE 3/3/2006 3/3/2006 3/6/2006 3/6/2006 3/ /2006 3/ /2006 3/ /2006

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

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. (The preferred file format is searchable .pdf

files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of

use. Please provide 5 copies of each CDROM submitted.) Information in lists should

contain enough information to be easily understood by someone who has a knowledge

of the technology. The lead inspector will discuss specific information needs with the

licensee staff and may request additional documents.

1. The Fire Protection Program document 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 document and the pre-fire plans for the selected fire

areas/zones (to be determined during information gathering visit).

4. The post-fire safe shutdown analysis, including system and separation analyses.

5. The alternative shutdown analysis.

6. Piping and instrumentation (flow) diagrams for the fire suppression systems.

7. Piping and instrumentation (flow) diagrams for the systems and components used to

achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from

the control room.

8. Piping and instrumentation (flow) diagrams for the systems and components used to

achieve and maintain hot standby, and cold shutdown, for fires in areas requiring

alternative or dedicated shutdown capability.

9. Plant layout and equipment drawings which identify the physical plant locations of hot

standby and cold shutdown equipment.

10. Plant layout drawings which identify plant fire area and/or fire zone delineation, areas

protected by automatic fire suppression and detection, and the locations of fire

protection equipment for the selected fire areas/zones (to be determined during

information gathering visit).

11. Plant layout drawings which identify the general location of the post-fire emergency

lighting units.

12. Plant operating procedures used to, and describing, shutdown from inside the control

room with a postulated fire occurring in any plant area outside the control room.

Enclosure

2

13. Plant operating procedures used to implement the alternative shutdown capability from

outside the control room with a fire in either the control or cable spreading room (or any

other alternative shutdown area).

14. Maintenance and surveillance testing procedures for alternative shutdown capability

(including Appendix R emergency lights and communication systems) and fire barriers,

detectors, fire pumps and fire suppression systems.

15. Calculations and/or justifications that verify fuse/breaker coordination for the selected

fire areas/zones (to be determined during information gathering visit) that are fed off the

same electrical buses as components in the protected train. Also, a list of the

maintenance procedures used to routinely verify fuse/breaker coordination in

accordance with the post-fire safe shutdown coordination analysis.

16. A list of the significant fire protection and post-fire safe shutdown design change

descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter

(GL) 86-10 evaluations.

17. A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,

Section III.G) used to achieve regulatory compliance for the selected fire areas/zones

(to be determined during information gathering visit). That is, please specify whether 3-

hour rated fire barriers (Section III.G.2.a), 20-foot separation along with detection and

suppression (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression

(Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for the

selected fire areas/zones.

18. Procedures or instructions that govern the implementation of plant modifications,

temporary modifications, maintenance, and special operations, and their impact on fire

protection.

19. Organization chart(s) of site personnel down to the level of the fire protection staff.

20. Procedures or instructions that control the configuration of the fire protection program,

features, and post-fire safe shutdown methodology and system design.

21. 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 editions

committed to (Code of Record)).

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

23. 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] associated with fire protection or Appendix R safe shutdown for the

past three years.

Enclosure

3

24. A list of plant fire protection licensing basis documents (i.e., a list of the SERs and

change evaluations which form the licensing basis for the facilitys post-fire safe

shutdown configuration).

25. A list of fire protection or Appendix R calculations.

26. A list of fire impairments identified during the previous year.

27. A list of abbreviations/designators for plant systems.

End Enclosure