ML20236M407

From kanterella
Jump to navigation Jump to search
Special Rept 87-15:on 871006,fire Breach Permit for Fire Door Exceeded 7-day Limit Allowed by Tech Spec.Caused by Failure to Complete Required Asbestos Removal Work by Due Date.Fire Door Restored to Functional Status
ML20236M407
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 11/05/1987
From: Nobles L
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
87-15, NUDOCS 8711130119
Download: ML20236M407 (2)


Text

_

G

,y.,

?

^

J

~ TENNESSEE: VALLEY AUTHORITY' i

.Sequoyah. Nuclear Plant l

r'

' Post Office Box 2000 i

Soddy-Daisy, Tennessee 37379

'I l

November 5;.1987 j

]l U.'S.

Nuclear' Regulatory Commission

]

Document Control Desk j

Washington, DC 20555 Gentlemen:

TENNESSEE VALLEY AUTHORITY,-'SEQUOYAH NUCLEAR PLANT UNIT DOCKET NO.

50-327 -~ FACILITY OPERATING LICENSE DPR-77-- SPECIAL REPORT 87 1 The enclosed special report provides. details.concerning a fire door' breached l

greater'than seven days..This event is reported in accordance with action statement (a) of Limiting Conditions for Operation 3.7.12.

t

.Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Nobles Plant Manager P

Enclosure ec (Enclosure):

J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission i

Suite 2900 101 Marietta Street, NW-Atlanta, Georgia 30323 Records-Center Institute of Nuclear Power Operations Suite 1500 i

1100 Circle 75 Parkway Atlanta, Georgia' 30339 NRC Inspector, Sequoyah' Nuclear Plant 8711130119 871105 PDR ADOCK 05000327 6

'h l

An Equal Opportunity Employer I

e

---m g

l r

.';t -

.~

v -

s

,j

' SEQUOYAH NUCLEAR PLANT.

. UNIT 1-y SPECIAL REPORT 87-15

6 DESCRIPTION OF. EVENT j

1,

l l

I I

On,0ctober 6,-1987, with unit l'in mode.5 (0 percent power, 3 psig,.and 128'

degraes F),Jthe fire breach permit issued on September 29, 1987,-for fire door A-25-(to unit l' turbine-driven auxiliary feedwater' pump room, Auxiliary-H Building: elevation 669) exceeded ~the seven-dayslimit. allowed by Technical f

Specification Limiting Condition:for Operation'(LCO) 3.7.12.

lJ The' fire breach.was issued.to facilitate the safe removal of asbestos t

insulation-from'the auxiliary feedwater piping in the turbine' driven

-auxiliary feedwater pump room to a'. low Inspection of.the piping in' accordance'with Special Maintenance Instruction (SMI)-0-317-55, "Walkdown of d

> Alternate-Analysis Piping and Supports." Door A-25 was breached open to.

construct'a temporary; air' lock thereby' ensuring a negative pressure inside

the room and, preventing a releasecof asbestosLfibers into the auxiliary building ventilation system.

3 CAUSE OF EVENT The regul' red : asbestos removal work was not completed within1the seven-day

. period due to'the complexity of the work involved.

A decision was made to maintain the breach for the duration of the asbestos removal activity to minimize the airborne asbestos hazard to employee health. As a result,.the fire' breach exceeded the seven-day limit of action statement A of LCO 3.7.12.

ANALYSIS OF EVENT This event is being reported in accordance with the requirements of action statement A of LCO 3.7.12.

A roving 1rire watch was established to inspect the turbine-driven auxiliary

'feedwater pump room on an hourly basis as required by the action statement of LCO 3.7.12.

The existing fire detection and suppression systems for the

, pump room were operable and would have actuated in the event of a fire.

.Therefore, there was no danger to redundant safety-related equipment.

' CORRECTIVE ACTION i

LA roving fire watch.at a regular interval of.one hour was established for l

door A-25-immediately and maintained until the asbestos pipe insulation removal _ work.was completed, and the fire door was restored to functional status on October 8, 1987. No further actions are required.

L 0730Q

. _ -