ML20040C081

Forwards Safety Evaluation Re Util 770130 Steam Generator Insp Rept.Generators Should Be Reinspected 12 Months After Startup to Assess Magnitude of Inplane Expansion

ML20040C081
Person / Time
Site:	San Onofre
Issue date:	09/25/1981
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	Goller K Office of Nuclear Reactor Regulation
Shared Package
ML13319A635	List: L-79-421, Forwards Steam Generator Insp Results Re Cracking of Small Bend Radius Steam Generator Tubes at Turkey Point Unit 3. Concurrence Requested Re Proposed Corrective Actions ML13319A634 ML20040B988 ML20040B995 ML20040B998 ML20040C002 ML20040C010 ML20040C040 ML20040C045 ML20040C050 ML20040C055 ML20040C060 ML20040C061 ML20040C065 ML20040C071 ML20040C073 ML20040C075 ML20040C078 ML20040C081 ML20040C086 ML20040C090 ML20040C093 ML20040C097 ML20040C102 ML20040C105 ML20040C113 ML20040C116 ML20040C121
References
FOIA-81-313 NUDOCS 8201270245
Download: ML20040C081 (1)

Text

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Reactors, Division of Opera:in; Ra;;;;r:

FROM:

D. Eisenhut, Assistant Director for Ooerational Technology, Division of Operating Reactort SUS.!ECT:

SAN ONOFRE UNIT NO.1 SAFETY E7;LUATICG - STEAP GENERATOR INSPECTION rep 0RT (:0;KE NO. 30-205}

The Encineering Branch, Division of Operatir; React:rs, has reviewed the Southern California Edison Company report, dated January 30, 1977, on the San Onofre Unit No. 1 steam generators.

The information.

submitted by the licensee is sufficient for us to conclude that San Onofre Unit No.1 operation can be resumed withcut ccmprcmise to the

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safety or an increase in the risk associated with the operation of.the.

steam generators.

However, we do not agree with the proposed power operation without an interim shutdown for reinspection prior to the next refueling outage.

We recommend that San Onofre Unit No.1 steam generators-be reinspected 4

at the end of twelve (12) months after start up to reassess the magnitude or inplane expansion or "hourolas. sing _in the top and bottom tubs. support plates on the effect or potential continued tube denting.

Attached herewith is our safety evaluation report.

LkAU-W -

.E ennut, Assistant Director for Operational Technology Division of Operating Reactors

Enclosure:

As stated cc:

B. Rusche cc w/o enclosure:

E. Case V. Stello, Jr.

W. Mcdonald L. Shao F. Burger A. Schwencer K. Seyfrit W. Hazelton R. Stuart J. Collins t

.8'. D. Liaw F. Almeter ;

8201270245 810925 PDR FOIA Document 9 UDELL81-313 PCR a

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