ML19260C452

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Confirms 790720 Telcon Re Containment Response to Main Steam Line Break Assuming Steam Generator Tube Failures.Lower Value of 1.5 Times Containment Design Pressure Should Be Used Based on Preliminary Analysis W/Simplified Assumptions
ML19260C452
Person / Time
Issue date: 07/23/1979
From: Tan C
Office of Nuclear Reactor Regulation
To: Zwolinski J
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-03, REF-GTECI-A-04, REF-GTECI-A-05, REF-GTECI-SG, TASK-A-03, TASK-A-04, TASK-A-05, TASK-A-3, TASK-A-4, TASK-A-5, TASK-OR NUDOCS 8001030461
Download: ML19260C452 (1)


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. t JUL 2 31979 MEMORANDUM FOR:

J. Zwolinski Containment Systems Branch Division of Systems Safety FROM:

C. P. Tan Structural Engineering Branch Division of Systems Safety

SUBJECT:

CONTAINMENT RESPONSE TO MSLB ASSUMING STEAM GENERATOR TUBE FAILURES This is to confirm our telephone conversation on July 20, 1979, with respect to the maximum allowable containment pressure mentioned in your July 11, 1979, memo to J. Strosnider of DOR. In the above telephone conversation, I commented on your statement that the maximum allowable containment pressure for either a steel vessel or a reinforced concrete vessel based on the ultimate strength of steel is approximately 2.75 times the containment design pressure, may not be appropriate. Although maintenance of containment structural integrity is a necessary condition for containment integrity, it is not a sufficient condition by itself. This is due to the fact that the function of the containment structure is to limit the release of radioactive material, which depends more on the leaktight integrity of a containment than on its structural integrity. The leaktight integrity is more reliably assured at yield limit of steel rather than at its ultimate strength. Therefore, instead of the.2.75 times the containment design pressure mentioned in your meacrandum lower value of say 1.5 times the containment design pressure should be used.

It should be noted that the above suggested factor of 1.5 was based on prelim-inary analysis using several simplified assumptions.

k0 C. P. Tan Structural Engineering Branch Division of Systems Safety cc:

S. Hanauer /

D. Pickett L. Soffer R. Denise J. Kudrick K. Parczewski D. Eisenhut V. Noonan F. Odar M. Aycock J. Strosnider F. Almeter F. Schauer Z. Rosztoczy E. Adensan W. Butler P. Check D. Jeng d

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