ML021970190

IR 05000400-02-011 for Shearon Harris Nuclear Power Plant. Notification of Triennial Fire Protection Baseline Inspection in September, October & November 2002

ML021970190
Person / Time
Site:	Harris
Issue date:	07/15/2002
From:	Payne D NRC/RGN-II
To:	Scarola J Carolina Power & Light Co
References
FOIA/PA-2003-0358 IR-02-011
Download: ML021970190 (6)

See also: IR 05000400/2002011

Text

Carolina Power & Light Company

ATTN: Mr. James Scarola

Vice President - Harris Plant

Shearon Harris Nuclear Power Plant

P. O. Box 165, Mail Code: Zone 1

New Hill, NC 27562-0165

SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION,

(NRC INSPECTION REPORT NO. 50-400/02-011)

Dear Mr. Scarola:

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 Shearon Harris

Nuclear Plant in September, October, and November 2002. The inspection team will be led by

Mr. R. Schin, Senior Reactor Inspector, 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 systems and equipment

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

areas.

On July 10, 2002, during a telephone conversation with Mr. John Caves, Supervisor of

Licensing, 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 - September 30 - October 2, 2002.

 Week 1 of onsite inspection - October 21 - 25, 2002.

 Week 2 of onsite inspection - November 4 - 8, 2002

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

needed to support the inspection; to become familiar with the Shearon Harris fire protection

program, fire protection features, 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 will be interested in reviewing, and possibly obtaining, are

listed in the Enclosure. Please contact Mr. Schin 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.

CP&L 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 Shearon Harris Nuclear

Plant 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 Shearon Harris 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. Schin at (404) 562-4629, or me at (404) 562-4669.

Sincerely,

/RA/

D. Charles Payne, Acting Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-400

License Nos.: NPF-63

Enclosure: Triennial Fire Protection Inspection

Support Documentation

cc w/encl:

Terry C. Morton, Manager

Performance Evaluation and

Regulatory Affairs CPB 9

Carolina Power & Light Company

Electronic Mail Distribution

(cc w/encl contd - See page 3)

CP&L 3

(cc w/encl contd)

Robert J. Duncan II

Director of Site Operations

Carolina Power & Light Company

Shearon Harris Nuclear Power Plant

Electronic Mail Distribution

Benjamin C. Waldrep

Plant General Manager--Harris Plant

Carolina Power & Light Company

Shearon Harris Nuclear Power Plant

Electronic Mail Distribution

James W. Holt, Manager

Support Services

Carolina Power & Light Company

Shearon Harris Nuclear Power Plant

Electronic Mail Distribution

John R. Caves, Supervisor

Licensing/Regulatory Programs

Carolina Power & Light Company

Shearon Harris Nuclear Power Plant

Electronic Mail Distribution

William D. Johnson

Vice President & Corporate Secretary

Carolina Power & Light Company

Electronic Mail Distribution

John H. O'Neill, Jr.

Shaw, Pittman, Potts & Trowbridge

2300 N. Street, NW

Washington, DC 20037-1128

Beverly Hall, Acting Director

Division of Radiation Protection

N. C. Department of Environmental

Commerce & Natural Resources

Electronic Mail Distribution

Peggy Force

Assistant Attorney General

State of North Carolina

Electronic Mail Distribution

(cc w/encl contd - See page 4)

CP&L 4

(cc w/encl contd)

Public Service Commission

State of South Carolina

P. O. Box 11649

Columbia, SC 29211

Chairman of the North Carolina

Utilities Commission

P. O. Box 29510

Raleigh, NC 27626-0510

Robert P. Gruber

Executive Director

Public Staff NCUC

4326 Mail Service Center

Raleigh, NC 27699-4326

Linda Coleman, Chairman

Board of County Commissioners

of Wake County

P. O. Box 550

Raleigh, NC 27602

Gary Phillips, Chairman

Board of County Commissioners

of Chatham County

Electronic Mail Distribution

Distribution w/encl:

J. Goshen, NRR

RIDSNRRDIPMLIPB

PUBLIC

OFFICE RII:DRS RII:DRP RII:DRS

SIGNATURE SCHIN BONSER PAYNE

NAME SCHIN BONSER PAYNE

DATE 7/11/2002 7/11/2002 7/15/2002 7/ /2002 7/ /2002 7/ /2002 7/ /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\ML021970190.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,

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.

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