ML20236M880

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Responds to I Mckenna 870716 Telcon Re Leakage of Spray Water Behind Crane Wall Following Postulated Dba.Vol of Water Inside Containment Was Determined Using Min Actual Ice Weights Taken from Surveillance Testing
ML20236M880
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 08/04/1987
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8708110288
Download: ML20236M880 (2)


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. TENNESSEE VALLEY AUTHORITY I

SN 157B Lookout Place AUG 041987

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

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'Gentiemen:

i In:the Matter of

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Docket Nos. 50-327 Tennessee Valley Authority

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50-328 g.,

lSEvC0YAH NUCLEAR PLANT (SQN) - LEAKAGE OF SPRAY WATER BEHIND THE CRANE

, WALL FOLLOWING A POSTULATED DESIGN BASIS ACCIDENT (DBA)

Reference:

TVA letter from me to NRC dated July 8, 1987 This'information'is being provided in accordance with a request from Ilene McKenna during a July 16, 1987 telephone call.

As discussed in.the referenced letter, the volume of water inside containment was determined using the minimum actual ice weights taken from surveillance testing. These weights were used to reflect the condition of the plant at the time the problem was identified for deportability considerations.

The addition of curbs and drains wiu ensure-that a water'1evel of 13.2 feet, calculated using the minimum ice weights allowed by technical specifications, will be available in the sump at the time of switchover from the refueling water storage tank to recirculation from the sump.

The referenced letter also. stated that an. evaluation would be performed to determine the adequacy of the electrical system for the containment air return fans to handle the increased loading as a result of spray water entrained in the containment atmosphero. The evaluation concluded that the electrical system is adequate to handle the increased load.

The evaluation determined that the maximum current induced by the fan's motor is within.the cable ampacity allowed. Also, the diesel generator inading is..within the generator rating. The breaker settings were evaluated and found to be' satisfactory. Thus, no physical modifications are necessary because of the increased electrical load.

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Very truly yours.

TENNESSEE VA LEY AUTHORITY R.Gridley,Ifirector i

Nuclear Safety and Licensing l

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see page 2 l

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8708110288 870804 3

PDR ADOCK 05000327 i

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An Equal Opportunity Employer

... i U.S. Nuclear Regulatory Commission lil 3 041987 cc:

Mr. G. G. Zech, Assistant Director for Inspection Programs Office of Special Projects U.S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant Director fo.* Projects Divisiva of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission 4350 East West Highway EWW 322 Bethesda, Maryland 20814 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2000 Igou Ferry Road Soddy Daisy, Tennessee 37379 i

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