ML16341D943

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Safety Evaluation Supporting Resolution of Unresolved Item 50-275/85-36-04 Re Fire Damper Installation
ML16341D943
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 10/26/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML16341D944 List:
References
TAC-59802, TAC-59803, NUDOCS 8611050015
Download: ML16341D943 (8)


See also: IR 05000275/1985036

Text

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UNITED STATES

NUCLEAR REGULATORY COMMIS ION

WASHINGTON, D. C. 20555

SAFETY EVALUATION BY THE OFFICE

OF NUCLEAR REACTOR

REGULATION

RELATED TO FIRE

DAMPER INSTALLATION

PACIFIC GAS AND ELECTRIC COMPANY

DIABLO CANYON NUCLEAR POWER PLANT, UNITS I AND 2

DOCKET NOS.

50-275

AND 50-323

I.

INTRODUCTION

In November

1985,

an Appendix

R team inspection

was conducted

by the

NRC

staff at the Diablo Canyon Nuclear

Power Plant, Units

1 and

2 (Ref. I).

During the inspection,

the team observed that in a number of plant locations

fire damper assemblies

were not installed in accordance

with the manufacturer's

installation requirements.

This finding was

documented

in Region

V Inspection

Report Nos.

50-275/85-36

and 50-323/85-04

as

Unresolved

Item 50-275/85-36-04

(Ref. I).

The

NRC staff met with representatives

of Pacific

Gas

and Electric Company

(PG&E), the licensee for the Diablo Canyon Plant,

on March 20,

1986 to discuss

the fire damper installations in further detail

and requested

additional

information (Ref. 2).

By letter dated

May 13,

1986, the licensee

provided its

response

to this issue

(Ref. 3).

An industry-wide concern that many fire rated

damper assemblies

had not been

installed in accordance

with manufacturer's

recommendations

had

been identified

in Bechtel

Problem Alert M-82-06 and

NRC IE Information Notice 83-69.

To

determine if such situation existed at the Diablo Canyon Plant, the licensee

conducted

an examination of all as-built installation details.

This examination

indicated that the manufacturer's

installation instructions

were not explicitly

adhered to for certain fire damper assemblies.

In its response

to the above

examination,

the licensee

categori'zed

these installation discrepancies

into

the following four groups:

1.

Damper assemblies

installed within ducts protected

by a fire rated

barrier material.

2.

Damper assemblies

installed in concrete walls with less

than the

manufacturer's

specified

gap between the damper

assembly

sleeve

and wall.

3.

Damper assemblies

installed in stud walls and suspended

ceilings with

less that the manufacturer's

specified

gap between the damper assembly

sleeve

and wall or ceiling opening.

4.

Damper assemblies

in areas without safe

shutdown

components

installed

at variance with the manufacturer's

recommendations.

8611050015

861026

PDR

ADOCK 05000275

PDR

In accordance

with its procedures

for evaluating potential

nonconformances,

the licensee

stated that two nonconformance

reports

were generated

to address

the cause

and safety significance of the identified discrepancies.

On the

basis of its review, the licensee

determined that the variances

from the

manufacturer's

recommendations

would not prevent the safe

shutdown of the

plant.

II.

EVALUATION

GROUP I:

Fire Dampers in Fire Protected

Ducts/Sleeves

In Attachment

A to the

May 13,

1986 letter, the licensee identified 42 fire

damper

assemblies

installed outside the plane of the wall.

The ductwork and

sleeves

containing these

damper assemblies

are protected

by an approved material

that affords

a I-hour fire resistance

to the ducts

and damper

assembly

sleeves.

By letter dated

November

13,

1978 (Ref. 4), the licensee

committed to protect

the ducts in several

rooms in this manner.

In Supplement

8 to the Diablo

Canyon, Units I and

2 Safety Evaluation Report,

the staff found these fire

damper installations

acceptable

(Ref. 5).

As stated

in Generic Letter 86-10

(Ref.

6 ), if a fire area

boundary

was described

in the fire hazards

analysis

and

was evaluated

and accepted

in a published Safety Evaluation,

then the

boundary

remains

acceptable,

and it need not be reviewed

as part of the

licensee's

reanalysis for compliance with Appendix R.

On this basis,

those

fire damper assemblies

that are installed in this manner

and that are

explicitly identified in the licensee's

November

13,

1978 letter, are

acceptable.

However, this approval applies only to those fire damper assemblies

that were

explicitly identified and not to any other assembly.

The staff could not

establish,

on the basis of the licensee's

May 13,

1986 letter, whether or not

each of the

42 damper assemblies

identified in the letter was subject to this

previous staff approval.

Therefore,

the licensee

should review the fire

damper assemblies

and evaluate

those that were not subject to this previous

staff approval in accordance

with Interpretation

4, "Fire Area Boundaries," of

the interpretations

document attached

to Generic Letter 86-10.

In accordance

with the Generic Letter,

an additional

licensee

submittal

on these fire damper

assemblies

is not required.

Therefore,

the staff considers

the concerns with

Group I dampers

resolved.

GROUPS

2 and 3:

Fire Dampers in the Plane of the Wall or Ceiling

Fire damper assemblies

in Groups

2 and

3 are installed in the plane of the

wall or ceiling, but with less

than the manufacturer's

specified expansion

gap

between

the damper

assembly

sleeves

and the wall or ceiling.

In Attachments

B

and

C to the

May 13,

1986 letter (Ref. 3), the licensee identified 43 such

fire damper assemblies.

The licensee

also provided

a summary engineering

A

IP

evaluation for each of the individual dampers.

On the basis of these

evaluations,

the licensee

concluded that the

43 fire damper assemblies

are

acceptable.

In summary,

the licensee

has justified these

damper assemblies

on

one or more of the following basis:

A.

The fire load in each of the fire areas

separated

by the damper

assemblies

yields

an equivalent fire severity less

than the

ASTM E-119

standard

time-temperature fire used to test the fire damper assemblies.

B.

Failure of the dampers

would not adversely affect safe

shutdown

capability because

the dampers

do not- separate

redundant

safe

shutdown

components.

C.

An automatic fire suppression

system

has

been installed

on one or both

sides of the damper assembly.

GROUP 4:

Fire Dampers without Safe Shutdown

Components

The fire damper assemblies

identified above

as

Group

4 dampers

were not

installed to protect the safe

shutdown capability, but to minimize property

damage in the event of fire.

Therefore,

the staff has not evaluated

these

fire damper assemblies.

CONCLUSION:

The staff has

reviewed the licensee's

summary engineering evaluation

and finds

them acceptable.

The staff concurs with the licensee's

assessment

that the

subject fire damper assemblies

provide an adequate

level of fire safety for

the areas

in which they are installed.

In the staff's judgement, modification

of the damper assemblies

would not significantly increase

the level of plant

fire safety.

Use of the fire damper assemblies

identified in the licensee's

May 13,

1986 letter is, therefore,

acceptable.

PRINCIPAL CONTRIBUTOR:

S.

West

1

4

REFERENCES:

1.

U.S. Nuclear Regulatory

Commission,

Region

V Inspection

Report

Nos.

50-275/85-36

and 50-323/85-34,

dated

December

24,

1985, transmitted

by

letter from D. Kirsch

(NRC) to J.

D. Shiffer (PGSE)

by letter dated

December

30,

1985.

2.

3.

U.S. Nuclear Regulatory

Commission,

"Meeting Summary - Fire Protection",

by H. Schierling,

dated April 30,

1986.

Letter from J.

D. Shiffer

(PGSE) to S.

A. Varga

(NRC), "Fire Dampers",

DCL 86-133,

dated

May 13,

1986.

4.

Letter from P.

H. Crane

(PGSE) to J.

F. Stolz

(NRC), dated

November

13,

1978.

5.

6.

U.S. Nuclear Regulatory

Commission,

"Safety Evaluation of the Diablo

Canyon Nuclear

Power Station,

Units

1 and 2", NUREG-0675,

Supplement

8

(SSER-8),

November,

1978.

4

U.S Nuclear Regulatory

Commission,

"Generic Letter 86-10:

Implementation

of Fire Protection

Requirements",

Letter from D.

G. Eisenhut

(NRC) to

Licensees

and Applicants, dated April 24,

1986.

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