ML20237L314

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Special Rept 87-08:on 870724 & 25,fire Breach Permit for Doors A-5 & A-71 to RHR & Containment Spray HX Rooms, Respectively,Exceeded Tech Spec Limiting Condition for Operation 3.7.12.Caused by Uncompleted Repair Work
ML20237L314
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 08/14/1987
From: Nobles L
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
0606Q, 606Q, 87-08, 87-8, NUDOCS 8708200168
Download: ML20237L314 (3)


Text

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bquya u ear an Post Office Box 2000 Soddy-Daisy, Tennessee 37379 f

August 14c 1987 1

U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen.

TENNESSEE VALI.EY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 1 - DOCKET NO.

50-327 - FACILITY OPERATING LICENSE DPR SPECIAL REPORT 87-08 The enclosed special report provides details concerning fire doors breached greater than seven days. This event is reported in accordance with the special report requirements of Technical Specification 3.7.12.

Very truly yours, TENNESSEE VALLEY AUTHORITY d$/f YfbYP L. M. Nobles Plant Manager i

Enclosure cc (Enclosure).

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

Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 s

Records Center Institute of Nuclear Power Operations Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 NRC Inspector, Sequoyah Nuclear Plant l

t 8708200160 070014 i

PDR ADOCK 05000327 S

PDR.

1983-TVA SOTH ANNIVERSARY I

An Equal Opportunity Employer

sa o

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 SPECIAL REPORT 87-08 DESCRIPTION OF EVENTS Event Number One On July 24, 1987, with unit 1 in mode 5 (0 percent power, 3 psig, 134 degrees F) and unit 2 in mode 5 (0 percent power, 0 psig, 132 degrees F), the fire breach permit for door A-5 to residual heat removal (RHR) room 1B exceeded the 7-day limit allowed by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.7.12.

Event Number Two On July 25, 1987, with unit 1 in mode 5 (0 percent power, 2 psig, 133 degrees F) and unit 2 in mode 5 (0 percent power, 0 psig.

134 degrees F), the fire breach permit for door A-71 to containment spray heat exchanger room 2A exceeded the 7-day limit allowed by TS LCO 3.7.12.

For both events described above, the fire breach permits were issued to keep the doors open to facilitate repair work by allowing air supply hoses and high efficiency particulate air (HEPA) filter hoses to pass through the doors.

CAUSE OF EVENTS For both events described above, the repair work was not completed within the 7-day period.

A management decision was made to keep both doors open for the duration of the repairs, to minimize removal of temporary equipment in and out of the room, and to expedite the repairs.

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ANALYSIS OF EVENTS 1

These events are being reported in accordance with the requirements of l

action statement (a) of TS LCO 3.7.12.

A roving fire watch was established for both doors as required by the action statement 3.7.12, and in the event of a fire, there is sufficient fire detection and Suppression capabilities such that there is no danger to the safety-related equipment.

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'l CORRECTIVE ACTIONS l

Event Number One

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.i Upon issue of the fire breach permit for door A-5 to RHR room 1B, a roving fire watch'was initiated at 1-hour. intervals until the repair work was completed on August 11, 1987, and the breach permit was closed. The door is now operable as a fire barrier,'and no further

, action is planned.'

l Event Number Two i

Upon issue of the fire breach permit for door A-71 to heat exchanger room 2A, a roving fire watch was initiated at 1-hour intervals until the repair work was completed on August 8, 1987, and the breach permit was-closed. The door is now operable as a fire barrier, and no further j

action is planned.

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1 0606Q l

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