ML20012A901

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Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp
ML20012A901
Person / Time
Site: Summer, Crystal River, 05000000
Issue date: 02/27/1990
From: Vaughn H
GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT
To: Murley T
Office of Nuclear Reactor Regulation
References
REF-PT21-90 NUDOCS 9003120765
Download: ML20012A901 (1)


Text

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3 Gilbert / Commonwealth, Inc. enoinem ina consunina P.O. Box 14M, Readin0. PA 1960M498/ Telephone 215 775 2600. Cable Gitasoc/ Telex 836-431

. H. E. VAUGHN V6ce President & General Manager Quality Assurance Division United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.

20555 Attention:

T. E. Murley, Director Re:

Reportable Event Chilled Water System

Dear Mr. Murley:

This is a follow-up to my letter of February 13, 1990 which described a Reportable Event under the provisions of 10CFR21 related to the V.

C.

Summer Nuclear Station.

In ' that letter, it was mentioned that evaluation of one specific area of chilled water system operation had'not been completed for Crystal River Unit 3 (50-302).

This evaluation has - now been completed and it has been determined that a postulated high energy line break (HEIB) in the intermediate building may subject the cooling coils of the non-safety related penetration cooling system to steam loads much higher than normal loads.

This could result in chilled water temperature of the control complex chillers rising which has the potential for compromising the operability of safety related equipment.

Florida Power Corporation has been notified of these results and is evaluating this event in accordance "ith their procedures.

If you require any further information, please call me at (215) 775-2600, extension 4548.

Very truly yours.

H. E Va ghn '

HEViceo ec:

T. E. Murley (NRC) (2)

Document.' Management Branch (NRC)

E. E. Froats (FPC)

C. D. Williams W. K. Burkhart W. E. Meek R. E. Vaughn k

9003120765 900227 PDR. ADOCK 05000302:i S.

PDC l

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