ML13319A639

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Forwards 800520 Summary of Results of IE Inquiry Into Steam Generator Tube Support Plate Cracking at Facility.Special Team Cannot Unequivocally Establish That Licensee Intentionally Withheld Safety Info from NRC
ML13319A639
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 06/09/1980
From: Lainas G
Office of Nuclear Reactor Regulation
To: Noonan V
Office of Nuclear Reactor Regulation
Shared Package
ML13319A640 List: ... further results
References
FOIA-81-313 NUDOCS 8007010859
Download: ML13319A639 (2)


Text

JUN.0 9 1980 MEMORANDUM FOR:

Vincent S. Noonan., Assistant Director for Materials and Qualifications Engineering, Division of Engineering FROM:

G. Lainas, Assistant Director for Safety Assessment, Division of Licensing

SUBJECT:

IE INQUIRY INTO STEAM GENERATOR TUBE SUPPORT PLATE CRACKING - SOUTHERN CALIFORNIA EDISON'S SAN ONOFRE UNIT 1 In a memorandum from E.G. Case to E. Volgenau, dated April 5, 1978, NRR requested IE to make an inquiry into whether safety information had been withheld from the regulatory staff regarding steam generator: tube support plate cracking at San Onofre Unit 1. The results of the inquiry by a special team of IE inspectors were summarized in a report which was officially transmitted to NRR by the attached memorandum from V. Stello, Jr. to H.R. Denton, dated May 20, 1980. This report is being sent to the Project Manager, Tom Wambach, and will be kept in his San Onofre file.

Based on the results of inquiry the special team has concluded that they were unable to unequivocally establish that the licensee did intentionally withhold safety information from the regulatory staff. Therefore, they see no need for further action and have closed the inquiry.

%Original signed by G. Lainas, Assistant Director for Safety Assessment Division of Licensing

Attachment:

As stated cc w/attachment:

H. Denton D. Eisenhut R. Vollmer G. Lainas S. Pawlicki T. Wambach B.D. Liaw 8007010 K. Wichman C. Cheng n

OFFICE L;.-

DL:QRALDD SURNAME CChen:S a

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/80

/80 NRC FORM 318 (9-76)

NRCM 0240 U. S. GOVERNMENT PRINTING OFFICEs 1976 - 626.62A

ATTACHMENT UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MAY 2 0 1980 Docket No.:

50-206 MEMORA2DUM FOR:

Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:

Victor Stello, Jr., Director Office of Inspection and Enforcement

SUBJECT:

STEAM GENERATOR TUBE SUPPORT PLATE CRACKING SOUTHERN CALIFORNIA EDISON'S SAN ONOFRE UNIT 1 Your office requested that IE make an inquiry into whether safety infor mation had been withheld from the regulatory staff regarding steam generator tube support plate cracking at Southern California Edison's San Onofre Unit 1. This request was contained in a memorandum from E. G. Case to E. Volgenau dated April 5, 1978.

A special team of IE inspectors performed the requested inquiry which in cluded:

interviews of NRC, Westinghouse, EDS, and Southern California Edison personnel and collection and review of pertinent photographs and documents. The report of the results of the inquiry made by the team is enclosed.

Based on their review of the'results of the inquiry the team was unable to establish that the licensee did intentionally withhold safety information from-the regulatory staff. Further, the team was unable to establish that the regulatory staff did ask the licensee whether the San Onofre Unit 1 steam generators had experienced flow slot cracking similar to that ex perienced elsewhere.

As a result of the investigation findings, we had considered the issuance of a Notice of Violation to the licensee. We find, however, that the in vestication report does not clearly establish noncompliance. We see no need for further action at this time and have closed the inquiry.

Victor Ste lo, Jr.

Director Office of Inspection and Enforcement

Enclosure:

As stated