ML20138C198

Insp Repts 50-324/86-04 & 50-325/86-03 on 860121-24. Violation Noted:Inadequate Fire Brigade Drills & Training & Failure to Implement Fire Protection Procedure FPP-013

ML20138C198
Person / Time
Site:	Brunswick
Issue date:	02/26/1986
From:	Conlon T, Wiseman G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20138C162	List: ML20138C159 ML20138C169 ML20138C198
References
50-324-86-04, 50-324-86-4, 50-325-86-03, 50-325-86-3, NUDOCS 8604020392
Download: ML20138C198 (6)

See also: IR 05000324/1986004

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMisslON

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REGION 11

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101 MARIETTA STREET N.W.

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ATLANTA, GEORGI A 30323

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Report Nos.: 50-325/86-03 and 50-324/86-04

Licensee:

Carolina Power and Light Company

P. O. Box 1551

Raleigh, NC 27602

Docket Nos.: 50-325 and 50-324

License Nos.: DPR-71 and DPR-62

Facility Name: Brunswick 1 and 2

Inspection Conducted: January 21-24, 1986

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Inspector:

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G. R. Wi s ema n' '

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Approved by:

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T. Ef Eoniori, Sectionfhief-

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Plant Systems Section, Engineering Branch

Division of Reactor Safety

SUMMARY

Scope:

This routine, unannounced inspection entailed 26 inspector-hours on site

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in the areas of Fire Protection / Prevention and followup on previously identified

inspection items.

-Results:

Two apparent violations were identified - Inadequate Fire Brigade

Drills and Training - paragraph 5.b. and Failure to Implement Fire Protection

Procedures FPP-013 - paragraph 6.a.

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REPORT DETAILS

1.

' Persons Contacted

Licensee Employees

• E. A. Bishop, Manager Operations

• J. W. Chase, Assistant to General Manager

• C. R. Dietz, Plant General Manager

• C. E. Enzor, Director Regulatory Compliance

• R. J. Groover, Manager, Brunswick Construction Unit

• J. R. Holder, Outage Manager

• B. L. Parks, Engineering Supervisor

• R. E. Porterfield, Senior Engineer - Fire Protection

• R. M. Poulk, Jr., Senior Specialist - Regulatory Compliance

A. Spencer, Training Specialist

• J. D. Wilcox, Principal Engineer-0perations

• T. H. Wyllie, Manager, Engineering and Construction

Other licensee employees contacted included construction craf tsinen,

engineers, technicians, operators, mechanics, security force members, and

office personnel.

Other Organizations

R. E. Deacy, Fire Protection Engineer, Impell Corporation

NRC Resident Inspectors

'*W. H. Ruland

• L. Garner

• Attended exit interview

2.

Exit Interview

The inspection scope and findings were summarized on January 24, 1986, with

those persons indicated in paragraph 1 above.

The inspector described the

areas inspected and discussed in detail the inspection findings.

No

dissenting comments were received from the licensee.

a.

ViolationItem(324/86-04-01and325/86-03-01), Inadequate Fire Brigade

Drills and Training - parag' .2ph 5.b.

b.

Violation Item (324/86-04-02 and 325/86-03-01), Failure to Implement

Fire Protection Procedures FPP-013,' paragraph 6.

The licensee did not identify-as proprietary any of the materials provided

to or reviewed by the inspector during this inspection.

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3.

Licensee' Action on Previous Enforcement Matters

(Closed) Unresolved Item -(324/84-37-02 and 325/84-37-02), Surveillance

Requirements of the Fire / Flame Impingement Barrier for Fire Pumps. Section

7.8 of Surveillance Procedure PT-34.6.7.2, Revision 1, has been revised to

include an' inspection of the fire / flame impingement barrier for the fire

pumps on a 18-month frequency.

4.

Unresolved Items

Unresolved items were not identified during the inspection.

5.

Fire Protection Prevention Program (64703)

a.

Fire Prevention / Administrative Controls Procedures

The inspector ' reviewed the following Fire Prevention / Administrative

Proced res:

Procedure No.

Title

FPP-003

Fire Brigade Training

FPP-004

Fire Brigade Personnel Medical

-and Physical Qualifications

FPP-007

Control

and Use of Fire

Fighting Equipment

FPP-013

Weekly Fire Inspection and

Plant Housekeeping

FPP-014

Control of . Combustibles - and

Transient Loads

FPP-017

Control of Cutting, Welding and

Grinding

PFP-001

Pre-Fire Control Procedure

PFP-013

General Fire Plan

Based on this review, it appears that the above procedures meet the NRC

Guidelines of:

(1) The docurnent entitled " Nuclear Plant Fire Protection functional

Responsibilities, Administrative Controls, and Quality Assurance"

dated June 1977.

(2) 10 CFR 50 Appendix R - Fire Protection Programs for Nuclear Power

Facilities.

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b.

Fire Brigade

(1) Organizations-

The plant fire brigade is composed of six shifts of fully dedi-

cated fire brigade personnel. The fire brigade leader is normally

a Senior Reactor Operator and the remaining fire brigade members

are composed of Auxiliary Operators and a radwaste representative.

The inspector reviewed the on-shift " fire brigade roster" for the

dates January 8,1986 through January 22, 1986, and verified that a

sufficient number of fire brigade personnel were on duty to meet

the provisions of Technical Specification 6.2.2 for fire brigade

operations and for plant operation.

(2) Training

The inspector reviewed the training records for six brigade Fire

Chiefs and 13 fire brigade members assigned duty during the above

period and found that four of the fire brigade members had not

completed all quarterly fire brigade training and one brigade.

member had not participated in the number of fire drills required

by procedure FPP-003.

This is identified as Violation Item

(324/86-04-01 and 325/86-03-01), Inadequate Fire Brigade Drills

and Training.

A sample of the records of the annual physical

examinations and respirator training for the brigade members

required by procedure FPP-004 were reviewed and found satisfac-

tory.

(3) Fire Brigade Equipment

The inspector performed an inspection of the fire brigade equip-

ment, consisting of fire hose, nozzles, tools, and miscellaneous

equipment, stored at the fire brigade equipment response location

located at the south fire equipment house.

A total of 17 sets of turnout gear (coats, boots, helmets etc.),

17 sets of self contained breathing apparatus, and 38 spare air

cylinders are available.

Ten sets are located adjacent .to the

main centrol room; two sets are in the radwaste control room; and

five_ sets are at the south fire equipment house.

Based on this inspection, the designated fire brigade equipment

stored at the fire brigade equipment response locations appeared

to be properly maintained and stored in a ready condition.

Except as noted above, no additional violations or deviations were identi-

fied within the areas inspected.

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Fire Protection / Prevention Program Implementation (64704)

Plant Tours

Plant tours were made by the inspector on both day and night shifts. At the

time of the inspections Unit I was in full operation.and Unit 2 was in an

extended outage.

During the plant tours portions of the following plant

areas.and .their related fire protection features were inspected:

Diesel Generator Building - 2',

23', and 50' elevations

Service Water Building - 4',

20' elevations

Reactor Building Unit 2 - (-)17', 20' and 50' elevations

Reactor Building Unit 1 - 20' - 50' Elevations and Refueling Floor Control

Building - 23' and 49' elevations

The inspector visually inspected the fire / smoke detection capabilities, and

the manual firefighting equipment (i.e., portable extinguishers, hose

stations, etc.) and the fire barrier walls associated with the above plant

areas.

Based on the visual inspection, it appears that the fire protection features

associated with the above plant areas were properly maintained and fully

functional, except that a number of fire doors in the diesel generator

building were not in service. However, the licensee had established the LCO

requirements of the Technical Specifications for these areas.

The plant tours also reviewed the licensee's implementation of the fire

protection administrative procedures.

On January 22, 1986, the inspector

and the Brunswick plant Fire Protection Engineer accompanied members of the

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Fire Protection Support group during their conduction of a weekly fire

inspection per the criteria of procedures FPP-013 and .FPP-014 of the Service

Water Building and Diesel Generator Building.

During this walkthrough the

inspector observed a non fire-retardant wood crate, combustible cardboard

and rubber gasketing material associated with Unit 2 maintenance work which

had obstructed fire protection equipment in the Unit 1 area of the Service

Water Building.

Also identified was flammable oil accumulations on the

floor, conduits and cable trays within the 2' elevation of the diesel

generator building.

These conditions were reported to the licensee.

The

licensee's fire protection support group inspector during this walkthrough

did not identify or note any of these conditions on the FPP-013 checklist.

FPP-013 requires the inspectors to note any identified condition which could

adversely affect the fire protection status of the area.

Failure to

identify, and not correct the above mentioned conditions which are adverse

to the fire protection of the area is considered a faihre to implement

FPP-013.

This constitutes a violation of Technical Specification 6.8.1.f,

which requires that written procedures for the fire protection program be

implemented and is identified as Violation Item (324/86-04-02 and

325/86-03-02), Failure to Implement Fire Protection Procedure FPP-013.

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Several _ welding operations were observed in the Unit-2 reactor building

during outage maintenance activities.

An approved " Hot Work" permit had

been issued for the welding sites and the operations and fire prevention /

protection practices generally met the licensee's fire prevention procedure

requirements.

The general housekeeping as a whole had deteriorated somewhat since the last

NRC fire protection . inspection.

This can be contributed to the Unit 2

outage activities and the licensee's failure to identify and correct adverse

housekeeping practices as identified _ by above Violation Item 324/86-04-02

and 325/86-03-02.

Except as noted above, no additional violations or deviations were identi-

fied within the areas inspected.

7.

Inspector Followup Items

(Closed) Inspector Followup Item, (324/84-37-01 and 325/84-37-01), Surveil-

lance Testing for Eight Hour Battery Powered Emergency Lighting Units.

Procedure PT-34.15.9.1 Revision 0, was issued on November 13, 1985, to

provide semiannual physical inspection and lighting head positioning for all

Appendix R Emergency Lighting . Units.

In addition, this procedure provides

for an 18-month battery capacity 8-hour discharge test for a 10% sample of

the emergency lighting units. The scope of testing and schedule provided in

the procedure appear acceptable.

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