ML20035B732

From kanterella
Jump to navigation Jump to search
Special Rept 1-93-004:on 930212,latch Arm Gasket Failed on Deluge Valve 20 Causing Leak in Valve Pit.Caused by Design Deficiency.Continuous Firewatches Have Been Placed in Five Areas of Reactor Bldg
ML20035B732
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 03/29/1993
From: Morgan R
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1-93-004, 1-93-4, BSEP-93-0033, BSEP-93-33, NUDOCS 9304050047
Download: ML20035B732 (2)


Text

I' CP&L x. 7,;

Carolina Power & Light Company Brunswick Nuclear Plant P.

O.

Box 10429 Southport, NC 28461-0429 MAR 2 91993 FILE:

BO9-13510C SERIAL:

BSEP-93-0033 U.S.

Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 SPECIAL REPORT PER TECHNICAL SPECIFICATION 3.7.8 AND PURSUANT TO TECHNICAL SPECIFICATION 6.9.2 (SR 1-93-0041-.

Gentlemen:

Unit I was in Cold Shutdown for the outage started on April 21, 1992.

The following summarizes fire protection Limiting Condition for Operation (LCO) Al-93-F0172:

On February 12, 1993, the latch arm gasket failed on Deluge Valve 20 causing a leak in the valve pit.

Deluge valve 20 is the supply valve for the Unit 1 Reactor Building sprinkler system. Failure of the gasket causes a system leakage problem but does not of itself render the fire protection. system inoperable.

This is an original design problem with the deluge valves. At 0635, the deluge valve was isolated to allow investigation into the cause of the gaskist failure.

A Limiting Condition of Operation was initiated and compensatory actions were placed in ef fect. The gasket is scheduled to be replaced and the system declared operable by April 15, 1993.

Brunswick Nuclear Plant believes that gasket failure in these valves is due to a design deficiency.

An investigation is in progress to identify methods-for permanent repair. An updated status report will be provided by July 1, 1993.

Continuous firewatches have'been placed in five areas of the Reactor Building (north and south.-17'0" elevation, north and south 20'0" elevation and north' 50'0" elevation). ' Backup fire suppression is the Reactor Building Standpipe System. Compensatory measures will remain in effect until the Deluge Valve can 93o4o5oo47 930329

1 0 ADOCK 050 5

gDR g

.r;...

9 I

'b'e returned to service. 'The special report is required due to the system being-~

l

' inoperable longer than the 14 days required by Technical Specifications.

l

'f Very truly yours,

-l 114W M

R.

E. Morgan, Plant Manager Unit-1 Brunswick Nuclear Plant cc:

Mr.

S. D.

Ebneter Mr.

P.

D.

Milano BSEP NRC Resident Office l

'l l

t

'E h

1 i

+

4

'I

-i t

i i

.i r

I r

.i I

i

[])'

i t

.f

~