ML19242D841

Forwards Addl Info Re Containment Isolation Valve Operability.Differential Pressure Across BWR Containment Isolation Valves Calculated for Three Different Fluids.Valve Response Differences Are Insignificant

ML19242D841
Person / Time
Issue date:	07/30/1979
From:	Lainas G Office of Nuclear Reactor Regulation
To:	Grimes B Office of Nuclear Reactor Regulation
References
NUDOCS 7908210554
Download: ML19242D841 (4)

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UNITED STATES y ()(D NUCLEAR REGULATORY COMMISSION 3

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JUL 3 01979 f1EMORAflDUit FOR:

B. Grimes, Acting Assistant Director for Systems Engineering, Division of Operating Reactor:

FROM:

G. Lainas, Chief, Plant Systems Branch, Division of Operating Reactors

SUBJECT:

C0flTAINMENT ISOLATI0fl VALVE OPERABILITY Enclosed is the additional information on containment isolation valve operability which you requested.

PSB has calculated the total differential pressure across a BWR contain-ment isolation valve for systems with an initial upstream pressure of 60 psia.

Comparisons were made with systems composed of three different fl ui ds :

air, natural gas and a post-LOCA mixture.

Figure 1 summarizes the results of these calculations.

As can be seen from this figure, the differences in the valve response are insignificant.

The total differential pressure across the 2" valve in the bypass line was compared with the total differential pressure across the 18" contain-

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ment isolation valve in a BWR.

The results are summarized in Figure 2.

The 18" containment isolation valve is subjected to a slightly higher

(~4 psid) differential pressure than the valve in the 2" byp. ass line.

/ diu-G.

'ainas, Chief Plant Systems Branch Division of Operating Reactors

Contact:

J. Kerrigan, X27110 Enclos ure :

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