ML19319E005

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Forwards Insp Rept 50-312/70-06 on 700917-18.Nonconformance Noted
ML19319E005
Person / Time
Site: Rancho Seco
Issue date: 10/20/1970
From: Spencer G
US ATOMIC ENERGY COMMISSION (AEC)
To: James O'Reilly
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19319D996 List:
References
02277, 2277, NUDOCS 8003270722
Download: ML19319E005 (2)


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DIVISION OF COMPLIANCE T

REGION V 443 2111 BANCROFT WAY i

BERKELEY, CAI.!FORNIA 94704 Tm.rmw. e43-stas sn. si October 20, 1970 J. P. O 'Reilly, Chief Reactor Inspection and Enforcement Branch Division of Compliance, Headquarters SACRAMENTO MUNICIPAL UTILITY DISTRICT (RANCHO SECO)

DOCKET No. 50-312 The Chicago Bridge and Iron Company Western Area office in Fremont, California and the Rancho Seco construction site were visited on September 17-18, 1970.

I The principal purpose of the routine construction inspection was to have W. Kelley (CO:II) review spot radiographs that were used as an aid to the quality of welder's work on the containment liner, and to review welding of the liner plate. One item of nonconformance involving the failure to meet film density code requirements was observed. A proposed CDN covering this item is being submitted to Headquarters for review and concurrence.

Regarding the item of nonconformance, the licensee (John Jackson) has informed us that Bechtel (San Francisco) has independently reviewed all of the spot radiographs of liner plate welds and admits that they do not meet the density requirements of W-51 of Section VIII of the ASME Code. However, it is their contention f.nat the quality and technique used for the radiographs are satisfactory enough to permit an experienced and qualified reader to evaluate the quality of work and determine the existence of undesirable defects.

According to the licensee, none of the final radiographs of the welds were rejected by Bechtel. Nevertheless, all future radiographs will be required to meet the code.

Comparative. test results of concrete samples taken at the point of placement have thus far shown the strength to exceed the specified value. However, these are preliminary results since better h ndling techniques were being developed for the samples and additional testing has been planned.

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G.S.Shencer Senior Reactor Inspector

Attachment:

CO Rpt. No. 50-312/70-6 by R. T. Dodds p) dtd 10-20-70 g7g37 4

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October 20, 1970 DISTRIBUTION:

E. G. Case, DRS (3)

P. A. Morris, DRL R. S. Boyd, DEL (2)

R. C. DeYoung, DRL (2)

D. J. Skovholt. DRL (3)

P. W. Howe, DRL (2) l L. Kornblith, Jr., CO:HQ l

Regional Directors, CO i

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