ML021840019

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Operating Corporation - Notification of an NRC Triennial Fire Protection Baseline Inspection 50-482/2002-08
ML021840019
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 07/03/2002
From: Marschall C
NRC Region 4
To: Maynard O
Wolf Creek
References
IR-02-008
Download: ML021840019 (6)


See also: IR 05000482/2002008

Text

July 3, 2002

Otto L. Maynard, President and

Chief Executive Officer

Wolf Creek Nuclear Operating Corporation

P.O. Box 411

Burlington, Kansas 66839

SUBJECT: WOLF CREEK NUCLEAR OPERATING CORPORATION - NOTIFICATION OF

AN NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

50-482/2002-08

Dear Mr. Maynard:

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

Region IV staff, will conduct a triennial fire protection baseline inspection at the Wolf Creek

Nuclear Operating Corporation in September and October of 2002. The inspection team will be

comprised of a team of reactor inspectors from the NRC Region IV office. The inspection will

be conducted in accordance with Inspection Procedure 71111.05, Fire Protection, the NRCs

baseline fire protection inspection procedure.

The schedule for the inspection is as follows:

  • Information gathering visit - September 9 - 13, 2002
  • 1st Week of onsite inspection - September 23 - 27, 2002
  • 2d Week of onsite inspection - October 7 - 11, 2002

In advance of the onsite inspections, some members of the inspection team will visit the Wolf

Creek Nuclear Operating Company the week of September 9 -13, 2002, to obtain information

and documentation needed to support the inspection, become familiar with your fire protection

program and, as necessary, obtain plant-specific site-access training and badging for

unescorted site access. A nonexhaustive list of the types of documents the team will be

interested in reviewing, and possibly obtaining, are listed in the Enclosure. The team leader will

determine at that time the documents necessary for examination in our regional office in

preparation for the onsite portion of this inspection. We would appreciate it if you could send

this information to our office in Arlington, Texas, so that it will arrive no later than noon on

September 16, 2002.

During the week prior to the inspection, the team leader will 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 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.

Wolf Creek Nuclear Operating Corp. -2-

We request that during the onsite inspection weeks, you ensure that copies of analyses,

evaluations, or documentation regarding the implementation and maintenance of the fire

protection program, including post-fire safe shutdown capability, be readily accessible to the

team for their review. Of specific interest are those documents that establish that your fire

protection program satisfies NRC regulatory requirements and conforms to applicable NRC

and industry fire protection guidance. Also, appropriate personnel knowledgeable of: (1) those

plant systems required to achieve and maintain safe shutdown conditions from inside and

outside the control room, (2) the electrical aspects of the post-fire safe shutdown analyses,

(3) reactor plant fire protection systems, and (4) the fire protection program and its

implementation should be available at the site during the inspection.

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 Rebecca Nease at 817-860-8154.

Sincerely,

/RA/

Charles S. Marschall, Chief

Engineering and Maintenance Branch

Division of Reactor Safety

Docket: 50-482

License: NPF-42

Enclosure:

Reactor Fire Protection Program Supporting Documentation

cc w/enclosure:

Vice President Operations

Wolf Creek Nuclear Operating Corp.

P.O. Box 411

Burlington, Kansas 66839

Jay Silberg, Esq.

Shaw, Pittman, Potts & Trowbridge

2300 N Street, NW

Washington, DC 20037

Supervisor Licensing

Wolf Creek Nuclear Operating Corp.

P.O. Box 411

Burlington, Kansas 66839

Wolf Creek Nuclear Operating Corp. -3-

Chief Engineer

Utilities Division

Kansas Corporation Commission

1500 SW Arrowhead Rd.

Topeka, Kansas 66604-4027

Office of the Governor

State of Kansas

Topeka, Kansas 66612

Attorney General

Judicial Center

301 S.W. 10th

2nd Floor

Topeka, Kansas 66612-1597

County Clerk

Coffey County Courthouse

110 South 6th Street

Burlington, Kansas 66839-1798

Vick L. Cooper, Chief

Radiation Control Program, RCP

Kansas Department of Health

and Environment

Bureau of Air and Radiation

1000 SW Jackson, Suite 310

Topeka, Kansas 66612-1366

Frank Moussa

Division of Emergency Preparedness

2800 SW Topeka Blvd

Topeka, Kansas 66611-1287

Wolf Creek Nuclear Operating Corp. -4-

Electronic distribution by RIV:

Regional Administrator (EWM)

DRP Director (KEB)

DRS Director (EEC)

Branch Chief, DRS/EMB (CSM)

Senior Resident Inspector (FLB2)

SRI, Callaway (JDH1)

Branch Chief, DRP/B (DNG)

Senior Project Engineer, DRP/B (RAK1)

Staff Chief, DRP/TSS (PHH)

Inspector, (RLN1)

RITS Coordinator (NBH)

Only inspection reports to the following:

Scott Morris (SAM1)

WC Site Secretary (SLA2)

DOCUMENT NAME: R:\_CPSES\CP2002-03-LTR-RLN.WPD

RIV:DRS\SRI\EMB C:EMB

RLNease:nlh CSMarschall

WMcNeill for /RA/

07/01/02 07/01/02

OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

ENCLOSURE

Reactor Fire Protection Program Supporting Documentation

1. The current version of the fire protection program and fire hazards analysis.

2. A listing of the fire protection program implementing procedures (e.g., administrative

controls, maintenance, surveillance testing, fire brigade).

3. Pre-fire plans.

4. Post-fire safe shutdown analysis.

5. Piping and instrumentation (flow) diagrams highlighting the system 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.

6. Plant layout and equipment drawings that identify the physical plant locations of major hot

standby and cold shutdown equipment.

7. Plant layout drawings that identify plant fire area and/or fire zone delineation, areas

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

equipment.

8. Plant layout drawings that identify the general location of the post-fire emergency lighting

units.

9. A listing of plant operating procedures that would be used and which describe shutdown

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

control room, and procedures that would be used to implement alternative shutdown

capability in the event of a fire in either the control or cable spreading room.

10. A listing of maintenance procedures that routinely verify fuse breaker coordination in

accordance with the post-fire safe shutdown coordination analysis.

11. A listing of fire protection and post-fire safe shutdown related design change packages

(including their associated 10 CFR 50.59 evaluations) performed in the last three years.

12. A listing of Generic Letter 86-10 evaluations performed in the last three years.

13. The plants individual plant examination external event report, results of any post-individual

plant examination external event reviews, and listings of actions taken or plant modifications

conducted in response to individual plant examination external event information.

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

15. A listing of procedures/instructions that govern the implementation of plant modifications,

maintenance, and special operations, and their impact on fire protection.

-2-

16. A listing of applicable codes and standards related to the design of plant fire protection

features and evaluations of code deviations.

17. Listing of open and closed fire protection ONE forms and/or SMART forms (problem

reports, nonconformance reports, problem identification and resolution reports) initiated

within the last three years.

18. Listing of plant fire protection licensing basis documents.

19. Design basis document for fire protection.