ML18130A474

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IE Insp Repts 50-280/79-29 & 50-281/79-46 on 790605-08. No Noncompliance Noted.Major Areas Inspected:Fire Protection & Prevention
ML18130A474
Person / Time
Site: Surry  
Issue date: 06/22/1979
From: Miller W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Conlon T
Shared Package
ML18130A475 List:
References
50-280-79-29, 50-281-79-46, NUDOCS 7908230674
Download: ML18130A474 (7)


See also: IR 05000280/1979029

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTA ST., N.W., SUITE 3100

ATLANTA, GEORGIA 30303

Report Nos. 50-280/79-29 and 50-281/79-46

Licensee:

Virginia Electric and Power Company

P. 0. Box 26666

Richmond, Virginia 23261

Facility Name:

Surry Power Station, Units 1 and 2

Docket Nos.

50-280 and 50-281

Licensee Nos.

DPR-32 and DPR-37

Inspection at Sur~ Site near Williamsburg,

Inspector, (A/~~

W. H. Miller, J.

Approved b~ /? _.,g,f:P~

Virginia

T. E. Conlon, Section Chief, RCES Branch

SUMMARY

Inspection on June 5-8, 1979

Areas Inspected

Date Signed

e..(z "Z.-h 1

Date Signed

This routine, unannounced inspection involved 24 inspector-hours onsite in the

areas of fire protection/prevention.

Results

Of the area inspected, no apparent items of noncompliance or deviations were

identified .

'

DETAILS

1.

Persons Contacted

Licensee Employees

  • W. L. Steward, Station Manager
  • J. L. Wilson, Superintendent Operations
  • R. F. Saunders, Superintendent Maintenance
  • T. A. Peebles, Superintendent Technical Services
  • F. L. Rentz, Resident QC Engineer
  • R. L. Baldwin, Supervisor Administrative Services
  • E. P. Dewandel, Staff Assistant
  • W. R. Skelley, Jr., Staff Assistant - SGRP
  • A. L. Parrish, III, Project Manager - SGRP
  • J. Goodson, Resident QC Engineer - SGRP

Y. P. Mangum, Resident Engineer Project Control - SGRP

  • C. Gillette, Administrative Supervisor - SGRP
  • T. J. Kenny, Engineering Supervisor

M. Terrier, System Fire Protection Engineer

  • J. S. Fisher, Fire Marshal

K. Barnett, SGRP Fire Marshal

Other Organizations

Stone and Webster

  • L.A. Budlong
  • L. B. Reynolds

M. Randolph

NRC Resident Inspector

  • D. J. Burke
  • Attended exit interview.

2.

Exit Interview

The inspection scope and findings were summarized on June 8, 1979 with

those persons indicated in Paragraph 1 above.

3.

Licensee Action on Previous Inspection Findings

a.

(Open) Deviation Item (50-281/79-08-0l), "Failure to Implement the

Fire Protection Commitments of Document, entitled Steam

Generator Repair Program for Surry Units 1 and 2".

The required

temporary fire protection equipment for the steam generator replace-

ment project had been provided for the Unit 2 containment.

Also,

the fire brigade for the construction site which will augment the

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existing plant fire brigade organization, had been organized and

trained.

However, the installation of the containment standpipe

system had not been completed due to the following:

(1)

One check valve and two control valves in the supply piping had

not been installed.

(2)

One hose station at the (-) 27' - 7" elevation had not been

installed.

(3)

Only 50 feet of 1 1/2-inch hose was installed on each hose rack

in lieu of the 100 feet required by the system design (Work

Procedure DC-78-0SJ).

(4) Entire system had not been hydrostatically tested to 200 psi as

required by Section 7-1.1 of National Fire Protection Association

Standard No. 14 (NFPA-14), "Standpipe and Hose Systems".

A

hydrostatic test was conducted on June 5, 1979 with 200 psi

placed on the system at the (-) 27' - 7" elevation.

This

resulted in the piping located on the 47' - 4" elevation being

tested to approximately 175 psi.

b.

(Closed) Unresolved Item (50-281/79-08-02), "Inadequate Fire Protection

Procedures for Construction Site".

VEPCO Administrative Instruction

No. 2.9.3, "Fire Plan" has been revised to incorporate the procedure

entitled "Surry Steam Generator Replacement Project Fire Protection

and Prevention Plan" dated April 1, 1979.

This procedure has been

implemented and should provide adequate administrative control for

the fire protection/prevention feature during the steam generator

replacement project.

4.

Unresolved Items

Unresolved items are matters about which more information is required to

determine whether they are acceptable or may involve noncompliance or

deviations.

New unresolved items identified during this inspection are

discussed in paragraphs 5.b and 6.a.

5.

Fire Protection/Prevention - Steam Generator Repair Program

An inspection was made of the following areas:

a.

Steam Generator Component Storage Warehouses

The sprinkler system installation discrepancies previously identified

as Inspector Followup Item (50-281/79-08-03) were revi~wed and found

corrected, except the dry pipe valve enclosure in Warehouse 7 had

not been provided with heat to prevent the system from freezing

during cold weather and the sprinkler heads adjacent to the unit

heaters in Warehouse 9 had not been changed to high degree type

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heads as required by Section 3-15.6.4 of NFPA-13, "Sprinkler Systems".

Pending correction of the above discrepancies this item will remain

open.

b.

Temporary Ventilation System For Unit 2 Containment

Section 4.5.4 of the document entitled "Steam Generator Repair

Program for Surry Power Station Units 1 and 211 states that the

temporary containment ventilation systems will be equipped with fire

protection devices similar to those installed for permanent systems.

A review of the temporary ventilation system for Unit 2 indicated

that fire protection devices are not provided for this system.

This

item is identified as Unresolved Item (50-281/79-46-0I), "Fire

Protection Requirements for Temporary Ventilation System for Unit 2

Containment", pending further evaluation by the NRC.

Within the areas examined, no i:tems of' noncom!)liance or deviations

were identified.

6.

Fire Protection/Prevention Program - Operating Plant

The following items of the fire protection/prevention program for the

operating plant were reviewed:

a.

Procedures

All of the licensee's fire protection/prevention procedures have

been consolidated into a manual entitled "Fire Protection Plan for

Surry Power Station" which contains the following:

(1)

(2)

(3)

(4)

(5)

(6)

(7)

Designates the station manager and/or superintendent of station

operations as being responsible for the fire protection/prevention

activities.

Requires a yearly audit of the fire protection/prevention

program by the Quality Assurance Department.

Requires all contractor personnel and other offsite personnel

to receive training in the station's fire protection plan.

Lists the qualifications of fire brigade members.

Indicates the action to be taken upon discovery of fire.

Provides administrative procedures for the control of combus-

tible materials, flammable or combustible liquids, housekeeping,

and hazards associated with open flame ignition sources such as

welding and cutting.

Provides fire fighting procedures for various areas of the

plant.

I

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(8) Lists the training requirements for the fire brigade.

These procedures appear to provide acceptable administrative control

over the fire protection/prevention program.

A review of the fire

brigade roster and training records indicated that adequate personnel

were assigned to the brigade. However most members of one brigade

shift and several members on other brigade shifts had not attended

all of the designated quarterly drills during 1978 and 1979 as

required by the fire protecti!mplan.

The licensee agreed to evaluate the current fire brigade training

program and to take the necessary action to assure that all brigade

members receive the required training.

This item is identified as

Unresolved Item 50-280/79-29-01 and 50-281/79-46-02, "Fire Brigade

Training."

b.

Fire Protection Inspections

C.

The most recent fire protection inspection report on the plant which

was conducted by American Nuclear Insurers and dated March 5-8, 1979

was reviewed.

This report contained 8 recommendations.

The licensee

stated that 2 of these items had been corrected.

Three items are

currently being reviewed by NRC/NRR, to determine the necessary

requirements.

Two items are scheduled for correction in 1979 and

another item is being reviewed within the station design change

program.

The action taken by the licensee appears adequate at this

time.

A review was made of the "Annual Fire Protection Audit of Surry

Power Station" dated January 9, 1979.

This audit was conducted by

the licensee's corporate staff and contained 7 recommendations.

Correspondence indicating the action to be taken on the recommenda-

tions had apparently not been filed at the site and was not available

for review.

This item will be reviewed on a subsequent inspection

by the NRC and is identified as Inspector Followup Item (50-280/

79-29-02 and 50-281/79-46-03), "Licensee's Corrective Action Taken

on RecoJIDDendations in Fire Protection Audit".

Emergemcy Fire Drills

On June 7, 1979 at 8:10 a.m.

a fire occured outside the plant

structures adjacent to the fuel building.

The fire originated in a

portable toilet and spread to another portable toilet and then to a

small all-metal building which was used for the storage of protective

clothing.

The two portable toilets were completely destroyed by the

fire and the metal storage building experienced minor fire damage .

The cause of this fire was incendiarism.

An investigation is being

conducted by the licensee.

The fire was discovered by a worker in

the area who reported and attempted to extinguish the fire with a

fire extinguisher.

The fire brigade responsed and extinguished the

fire using hose streams supplied from adjacent fire hydrants.

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Salvage operations were conducted by the brigade which mainimized

the fire damage.

The inspector witness the fire fighting operations

by the brigade and considered the response and performance of the

brigade satisfactory.

The licensee has attempted to involve the local offsite fire depart-

ments in fire training/drills and inspection of the fire protection

features of the plant.

On October 4, 1978 an invitation was sent to

the Surry and Smithfield Volunteer Fire Departments to participate

in a training session, however only representatives from the Surry

Volunteer Fire Department participated in this training.

In May,

1979 another invitation was sent to these same two departments but a

response was not received.

d.

Fire Protection Systems

The following periodic test procedures and recorded tests on the

fire protection systems were reviewed and found to be satisfactory:

(1)

PT 24.1, Fire Pumps

(2)

PT 24.2, Carbon Dioxide System for Fuel Oil Pump House

(3)

PT 24.2A, Carbon Dioxide System for Emergency Service Water

Pump House

(4)

PT 24.4H, Hose Houses-Fire Equipment

(5)

PT 24.5, Smoke Detector Systems

e.

Facility Tour

An inspection was made of the fire pumps, ten control valves in the

fire protection water system, three hose houses, and the carbon-

dioxide system for the fuel oil pump house.

The fire protection

systems were found operational, valves properly aligned, and hose

houses properly equipped.

However, the control valves in the fire

protection water system were neither sealed nor locked in the correct

position as required by Section 3-6 of NFPA-24, "Outside Protection"

and Section 6-1 of NFPA-26, "Supervision of Water Supply Valves".

Currently these valves are checked monthly, but to meet the NFPA

criterion they are required to be locked in the correct position.

This is one of the fire protection items currently being evaluated

by NRC(NRR).

Pending the result of this evaluation this item is

identified as Inspector Followup Item (S0-280/79-29-03 and 50-281/

79-46-04), "Supervision of Fire Protection Control Valves" .

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£.

Emergency Breathing Apparatus

A total of 22 self-contained breathing apparatus units with 11 spare

cylinders are available at the plant.

An air compressor, cascade

type, refilling system is also provided.

The adequacy of the

breathing apparatus and refilling system is currently being

evaluated by NRC(NRR).

Within the areas examined, no items of noncompliance or deviations were

identified .

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