ML13317A527

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Comments on NRC 820423 Final Evaluation of SEP Topic III-7.D, Containment Structural Integrity Test. Evaluation Should Be Rewritten to Reflect New Peak Pressure Re Design Basis Main Steam Line Break Accident
ML13317A527
Person / Time
Site: San Onofre 
Issue date: 03/01/1983
From: Krieger R
Southern California Edison Co
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
TASK-03-07.D, TASK-3-7.D, TASK-RR NUDOCS 8303070084
Download: ML13317A527 (1)


Text

Southern California Edison Company P.0 BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 March 1, 1983 Director, Office of Nuclear Reactor Regulation Attention: D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Gentlemen:

Subject:

Systematic Evaluation Program Topic III-7.D, Containment Structural Integrity Test San Onofre Nuclear Generating Station Unit 1

References:

A. Letter W. A. Paulson (NRC) to R. Dietch (SCE), April 23, 1982, SEP Topic III-7.D, Containment Structure Integrity Test B. Letter, K. P. Baskin (SCE) to Attention: D. M. Crutchfield (NRC), November 18, 1982, Environmental Qualification C. Letter K. P. Baskin (SCE) to Attention: D. M. Crutchfield (NRC), June 10, 1980, Automatic Initiation of Auxiliary Feedwater System, enclosed report This is in response to the NRC's final evaluation of SEP Topic III-7.D, which was transmitted to us by Reference A. We have one significant comment, as follows:

The most recent pressure, temperature values relating to the design basis main steam line break (MSLB) accident are:

53.3 psig and 391.5 0F.

These values were transmitted to the NRC with Reference B, under a different subject. The NRC's evaluation of SEP Topic III-7.0 should be rewritten to reflect the new peak pressure. It is considered that the recalculated pressure does not affect the conclusions of SEP Topic III-7.D, since the containment was successfully tested at 53.4 psig prior to operation.

Reference C provides a detailed discussion of the actual design capability of the containment sphere.

Should you have any questions, please contact the undersigned.

y trul yours, W. Krieger (Supervising En ineer g13066 09 030 San Onofre Unit 1 Licensing

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