ML20248B892

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Forwards Updated SG Run Time Analysis Cycle 9 & Updated Probabilistic Operational Assessment for Songs,Unit 2,Second Mid-Cycle Operating Period,Cycle 9. Assessment Updates Info Provided in 980220 Submittal & Supercedes 970925 Submittal
ML20248B892
Person / Time
Site: San Onofre 
Issue date: 05/26/1998
From: Gibson G
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20248B896 List:
References
NUDOCS 9806020013
Download: ML20248B892 (2)


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  1. } EDISON SOUIHIRN CAlllORNR An (Dih0N IN1LRNA110%Al* Canpany 4

May 26,1998

' U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 i

Gentlemen:

1

SUBJECT:

Docket No. 50-361 Updated Steam Generator Run Time Analysis for Cycle 9 San Onofre Nuclear Generating Station, Unit 2

References:

[1]

February 20,1998 Letter from Greg Gibson (SCE) to the Document Control Desk (NRC) Special Report: " Inservice inspection of Steam r.

Generator Tubes, San Onofre Nuclear Generating Station, Unit 2"

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[2]

September 25,1997 Letter from Jack Rainsberry to the Document Control Desk (NRC) " Steam Generator Run Time Analysis for i

Cycle 9, San Onofre Nuclear Generating Station, Unit 2" y

The purpose of this letter is to provide the enclosed final assessment of the results of the mid-Cycle 9 San Onofre Unit 2 steam generator inspection. The enclosed assessment updates the assessment provided to the NRC by Reference 1 and supercedes the previous run time analysis provided in Reference 2.

The enclosed arsessment provides:

The results of the mid-cycle inspection and in-situ pressure testing, and e

validates the run time conclusions in Reference 2.

The basis for operation until the end of the current fuel cycle, which is e

anticipated to occur in January 1999.

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P. O. itox 128 San Clemente. CA 92ts744128

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t In summary, safe operation of the San Onofre Unit 2 steam generators is supported by the results of the mid-Cycle 9 inspection outage, the enclosed assessments, the end of Cycle 8 and mid-Cycle 9 repairs, and operational tube leakage limits. As discussed with the NRC Staff on October 23,1997, Southern California Edison is available to discuss the analyses and the probabilistic methodologies used in the enclosed assessment.

l Very truly yours, f

Gregory T. Gibson Manager, Compliance Enclosures cc:

E. W. Merschoff, Regional Administrator, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident inspector, San Onofre Units 2 & 3 J. W. Clifford NRC Project Manager, San Onofre Units 2 and 3 bcc:

(See attached sheet) l

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