ML19326A028

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Forwards Vendor Insp Rept 999-042/72-01 on 720104-06.Code Nonconformance Noted
ML19326A028
Person / Time
Site: Davis Besse, Oconee, Rancho Seco  Duke Energy icon.png
Issue date: 03/02/1972
From: Vetter W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Henderson J
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19326A024 List:
References
REF-QA-99900042 NUDOCS 8001310604
Download: ML19326A028 (2)


Text

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DIVISION OF COMPLIANCE 0

REGION til ting,, og 799 ROOSEVELT ROAD mpag GLEN ELLYN, ILLINOIS 60137 (si:n ass.zeso March 2, 1972 J. B. Henderson, Chief, Reactor Construction Branch Division of Compliance, Headquarters VENDOR INSPECTION REPORT BABCOCK & WILCOX COMPANY, BARBERTON, OHIO STEAM GENERATORS FOR:

TOLEDO EDISON COMPANY (DAVIS-BESSE) 50-346 DUKE POWER COMPANY (OCONEE 2) 50-270 l

SACRAMENTO MUNICIPAL UTILITY DISTRICT (RANCHO SECO) 50-312 The attached report of a vendor inspection at the subject vendor's p

manufa.cturing plant on January 4 - 6, 1972, is transmitted for

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information. Areas of code nonconformance (materials of construc-

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tion) were identified with respect to the manufacture of both the Oconee 2 and Rancho Seco steam generators.

According to inforna-tion supplied by CO:I, the licensee (SMUD) involved is to be informed of apparent code nonconformance through CO:HQ corres-pondence.

In this regard, we have provided the standard communica-tion to our licensee (Davis-Besse).

Concerning the exchange of steam generator plate material between the Midlands and Davis-Besse projects, the results of this inspec-tion indicate that all of the records (traceability) are in order and that both the 4 1/16-inch thick and 7-inch thick plate used for the Davis-Besse steam generators has been correctly qualified to SA 516, Grade 70, material. The only difference between the two categories of plate is that the 4 1/16-inch thick plate was l

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J. B. Henderson March 2, 1972.

qualified on the basis of a Charpy-V impact test temperature of 700F whereas the 7-inch. thick plate was qualified at 400F during i

the Charpy-V impact tests.

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o W. E. Vetter Senior Reactor Inspector

Attachment:

CO Rpt No. 999-042/72-01 by R. E. 011er 1

cc:

E. G. Case, DRS (3)

R. S. Boyd, DRL (2)

R. C. DeYoung, DRL (2)

D. J. Skovholt, DRL (3)

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H. R. Denton, DRL (2) l L. Kornblith, CO R. H. Engelken, CO CO Files 1

DR Central Files i

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