Information Notice 1989-52, Potential Fire Damper Operational Problems

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Potential Fire Damper Operational Problems
ML031180663
Person / Time
Issue date: 06/08/1989
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-89-052, NUDOCS 8506050146
Download: ML031180663 (9)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C.

20555

June 8, 1989

NRC INFORMATION NOTICE NO. 89-52: POTENTIAL FIRE DAMPER OPERATIONAL PROBLEMS

Addressees

e

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

This information notice is being provided to alert addressees to potential

problems affecting the closing reliability of curtain-type fire dampers under

ventilation system operational air flow.conditions.

It is expected that

recipients will review the information for applicability to their facilities

and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice do not constitute NRC require- ments; therefore, no specific action or written response is required.

Description of Circumstances

On November 6, 1984, Ruskin Manufacturing transmitted a 10 CFR Part 21 notifi-

-- cation-to the NRC regarding seven of Its curtain-type fire dampers that failed

to close during ventilation duct air flow tests. The tests were performed at

the Palo Verde nuclear plant and were conducted to determine the ability of the

curtain-type fire dampers to close under operational air flow conditions, as

designed.

On January 18, 1985, Northern States Power Company (NSP) notified the NRC of

several curtain-type fire dampers that failed to fully close under ventilation

system air flow conditions during ventilation duct system operability tests

performed by NSP. The fire damper testing method used remote trip wires in

place of the thermal links and the ventilation ducts were fully closed with

no open duct access panels, thus representing the actual air flow and pressures

that would be present during operating conditions.

On May 14, 1986, Wisconsin Public Service Corporation (WPSC) notified the NRC

of two curtain-type fire dampers manufactured by Action Air that were tested

and that failed to close completely under normal air flow conditions.

On December 27, 1987, Alabama Power Company notified the NRC that control room

fire dampers at Farley Unit 1 were inoperable because of failure to close

during testing under air flow conditions.

IN 89-52 June 8, 1989 On February 23, 1988, Alabama Power Company reported to NRC that a number of

fire dampers at Farley Unit 2 failed to close when tested under air flow.

Until quite recently, the only Industry standard governing the design, fabri- cation, and testing of fire dampers was Underwriters Laboratories, Inc. (UL)

Standard 555, "Fire Dampers and Ceiling Dampers."

The 1979 edition states in

part that "the closing reliability of fire dampers...is evaluated on the basis

that...ventilating systems are automatically shut down when a fire occurs...

therefore, the UL ratings are applicable to fire dampers...installed in systems

where air movement is effectively stopped at the start of a fire...." The

standard does not evaluate whether or not fire dampers will close under air

flow conditions. Therefore, the UL fire damper rating only indicates whether a

fire damper in the closed position will maintain its integrity under fire

conditions for a specific time period, typically rated for 1i or 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Discussion:

NRC requirements and guidelines for fire damper configurations are contained in

various documents, including Appendix A to the Branch Technical Position (BTP)

APCSB 9.5-1, "Guidelines for Fire Protection for Nuclear Power Plants Docketed

Prior to July 1, 1976," (NUREG-75/087; NUREG-0800) and Standard Review Plan

(SRP) 9.5.1, "Fire Protection Program' (NUREG-0800). The extent to which these

guidelines apply to a specific plant depends on licensee commitments and license

requirements that are applicable to the fire protection program.

The objective

of these guidelines is to provide a fire damper that will close and latch as

required-to ensure-that-those-systems and-components i mjprtant to safe shutdown

will be capable of performing their intended functions.

-

-

Licensees should be aware that fire damper testing methods that do not simulate

the actual total differential pressure at the damper (i.e., visual inspection

or drop testing with duct access panels open) may not show operability under

'air flow conditions. If licensees depend on the UL product listing and do not

sufficiently model air flow during surveillance testing, they cannot be sure

that the dampers will close fully when called upon to do so unless air flow

is stopped first.

Licensees who have adequately addressed this issue have either (1) type tested

"1worse-case" air flow conditions of plant-specific fire damper configurations;

(2) tested all dampers installed in required fire barriers; or (3) administra- tively shut down the ventilation systems to an area upon confirmation of a

fire. The last approach has been incorporated into plant emergency procedures.

Because all curtain-type fire dampers currently installed at nuclear power

stations are of a similar design, all stations having these fire dampers should

consider the 10 CFR Part 21 report, which specifically references Ruskin dampers, to be applicable to curtain-type fire dampers manufactured by other companies.

This type of fire damper, as installed in nuclear power stations, is typically

used to protect redundant trains of safe shutdown systems and should be capable

of closing and latching under anticipated air flow conditions.

IN 89-52 June 8, 1989 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate

regional office.

Charles E. Rossi, Di rtor

(

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Dennis J. Kub1cki, NRR

(301) 492-0825

Joseph J. Petrosino, NRR

(301) 492-0979

Joseph M. Ulie, Region III

(312) 790-5712 Attachment: List of Recently Issued NRC Information Notices

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hIN 8R-52

June 8, 19SS

Pipe I of I

LIST oF RECENTLY

ISSUED

NRC INFORNATIO.

NFTICES

snformetior.

Usti of

Notice ho.

89-51

88-88 Supp. 1

89-50

89-49 Subject

Potential Loss of Required

Shutdown Margin During

Refueling

Operations

D

dation of Westinghouse

Inaodeuete Emergency

Diesel Generator Fuel

Supply

Failune to Close Service

Water Cross-Connect

Isolation

Valves

Design Deficiency

i1 the

Turbine-Driven

Auxiliary

Foedwater Pupp Cooling

Water System

Potential Probluns With

Worm or Distorted Hse

clamps on Self-Containe

Breathing

Apparatus

Confidentiality of

Exercise Scenarios

Issuance

Issued

to

5/31/89

All holders of OLs

or CPs for nuclear

power reactors.

5/31/89 All holders

of OLs

or CPs for nuclar

power reactors.

5/30/89

All holders of OLs

or CPs for nuclear

power reactors.

5/22/89 All holders o' CLS

or CPs for nuclear

power reactors.

5/22/it

All holders of OLs

or COs for nuclear

power reactors.

89-i.

89-4e

S/18/89 All holdtrs of' Ohs

or ;s

for nuclear

power reactors and

full facilities.

5/11/89 All holders *! licenses

for fuel cycle facilities

and byproduct material

licensees

havinr an

approved

eergency

response plan.

5/8/89 All holders

of OLs

or CPs for nuclear

power reactors.

4/27/es

All holders of OLs

or Cps for nuclear

power reactors.

89-45 Hetalclad. Low-Voltage

Power Circuit breakers

Refurbished with Sub- standard Parts

89-44 hydrogen Storage on the

Roof of the Control Rooam

OL

  • Operatin, License

C'

  • Construction Permit

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, 6300

FIRST CLASS MAIL

POSTAGE b FEES PAID

USNPRC

PERMIT Ne. 0-t7

IN 89-52 June 8, 1989 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate

regional office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts:

Dennis J. Kubicki, NRR

(301) 492-0825

Joseph J. Petrosino, NRR

(301) 492-0979 Joseph M. Ulie,

(312) 790-5712 Region III

Attachment:

List of Recently Issued NRC Information Notices

-

  • SEE PREVIOUS (
  • ECEB:DEST:NRR

DKubicki:gr

02/28/89 CONC

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D/

CERossi

06/g'/89

  • VIB:DRIS:NRR

JPetrosino

03/01/89

  • C/OGCB:DOEA:NRR

CHBerlinger

03/09/89

  • C/ECEB:DEST:NRR

CMcCracken

03/03/89

  • RPB:ARM
  • D/DRIS:NRR

TechEd

BKGrimes

06/02/89

03/01/89

  • SC/VIB:DRIS:NRR*C/VIB:DRIS:NRR

EBaker

EWBrach

03/01/89

03/01/89

IN 89-XX

June XX,

1989 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate

regional office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts:

Dennis J. Kubicki, NRR

(301) 492-0825

Joseph J. Petrosino, NRR

(301) 492-0979 Joseph M. Ulie,

(312) 790-5712 Region III

Attachment:

List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

D/DOEA:NRR

CERossi

03/ /89

  • VIB:DRIS:NRR

JPetrosino

03/01/89

  • C/OGCB: DOEA:NRR

CHBerlinger

03/09/89

  • C/ECEB:DEST:NRR

CMcCracken

03/03/89 AM VA

  • D/DRIS:NRR

chEd

BKGrimes

"%ft

f

ohvf

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  • SC/VIB:DRIS:NRR*C/VIB:DRIS:NRR

EBaker

EWBrach

03/01/89

03/01/89

  • ECEB:DEST:NRR

DKubicki:gr

02/28/89

IN 89-XX

March XX, 1989 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate

regional office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts:

Dennis J. Kubicki, NRR

(301) 492-0825

Joseph J. Petrosino, NRR

t301) 492-0979 Joseph M. Ulie,

(312) 790-5712 Region III

Attachment:

List of Recently Issued NRC Information Notices

  • SEE PREVIOUS I
  • ECEB:DEST:NRR

DKubicki:gr

02/28/89

CONCURRENCES

D/DOEA:NRR

CERossi

03/ /89

  • VIB:DRIS:NRR

JPetrosino

03/01/89 RPB:ARM

  • D/DRIS:NRR

TechEd

BKGrimes

03/

/89

03/01/89

  • SC/VIB:DRIS:NRR*C/VIB:DRIS:NRR

EBaker

EBrach

03/01/89

03/01/89

IN 89-XX

March XX, 1989 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact one of the technical

contacts listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Dennis J. Kubicki, NRR

(301) 492-0825

Joseph J. Petrosino, NRR

(301) 492-0979

Joseph M. Ulie, Region III

(312) 790-5712 Attachment:

List of Recently Issued NRC Information Notices

DISTRIBUTION:

Central Files

ECEB R/F

ECEB S/F

B. Grimes

E. W. Brach

E. Baker

D. Notley

R. Wescott

J. Ulie, Region III

DIR:DOEA

ERossi

03/

/89

  • SEE PREVIOUS CONCURRENCE

OFC :ECEB:DEST*

VIB:DRIS*

n____.___________-_____________

NAME :DKubicki:gr :JPetrosino

n____-_____ _____

-_____ _____

DATE :02/28/89

03/01/89

OFFICIAL RECORD COPY

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03/3S /89
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03/01/89
03/01/89-
03/ _/89

IN 89-XX

February XX, 1989 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact one of the technical

contacts listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: Dennis J. Kubicki, NRR

(301) 492-0825

Joseph J. Petrosino, NRR

(301) 492-0979

Joseph M. Ulie, Region III

(312) 790-5712

1*

Attachment:

List of Recently Issued NRC Information Notices

DISTRIBUTION:

entral Fles

ECEB R/F

ECEB S/F

B. Grimes

E. W. Brach

E. Baker

D. Notley

R. Wescott

J. Ulie, Region III

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OFFICIAL REC D COPY

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