ML19319C993

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Deficiency Rept Re Excessive Pressure Drop in Spring Loaded Stop Check Valves BSV-9,10,67 & 68.Caused by Inadequate Design.Valves to Be Replaced W/Conventional Swing Check Valves,Supplementing
ML19319C993
Person / Time
Site: Crystal River 
Issue date: 02/16/1976
From: Rodgers J
FLORIDA POWER CORP.
To:
Shared Package
ML19319C975 List:
References
NUDOCS 8003040923
Download: ML19319C993 (2)


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.,p' Florida Power February 16, 1976 Mr. John Davis, Acting Director Directorate of Regulatory Operations U. 5. Nuclear Regulatory Comission Washington, D.C.

20545

Subject:

Docket No. 50-302

Dear Mr. Davis:

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As a follow-up to our letter of June 17, 1975, regarding the "possible" significant deficiency in the hydraulic performance of the reactor building spray system, we wish to provide you with this update.

We performed a series of performance tests on the subject system and a transient enalysis was run of the borated water storage tank draw down. This analysis has confimed that a design deficiency in the reactor building spray system did exist and that the deficiency was, in fact, a reportable deficiency pursuent to 10 CFR 50.55(e).

It was determined that four valves; BSV-9,10, 67 & 58, which are sp.'ir1 loaded stop check valves, have excessive pressure drop relative to the required system operation. These valves will be replaced with conventional swing check valves with a lesser design pressure drop. An analysis has been performed which indicates the system, with the soecified redification, will perform as designed in accordance with Crystal River Unit 3 FSAR.

The corrective action, although significant to the system performance, is considered a minor change because of the predictability of valve properties by industry standards.

As in previous cases, the analysis is available at the Crystal River Unit 3 plant site for further I&E review.

Very truly yours, JTR:1dh

. T. Rodgers Assistant Vice P msident j

cc: Mr. Norman C. Moseley Director, Region II dM i

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