ML19317G042
| ML19317G042 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/14/1972 |
| From: | Rich Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| Shared Package | |
| ML19317G034 | List: |
| References | |
| NUDOCS 8002210743 | |
| Download: ML19317G042 (2) | |
See also: IR 05000312/1971005
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UNITED STATES
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ATOMIC ENERGY COMMIS:',10N
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DIVISION OF COMPLIANr4
REGION V
2181 BANCROFT . AY
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BERKEI.EY, CALIFORNIA 94704
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January 14, 1972
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Sacramento Municipal Utility District
Docket No. 050-0312
P. O. Box 15830
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Sacramento, California 95813
Attentions- Mr. John'J. Mattimoe
Chief Engineer
Gentlemen
This refers to the inspection conducted by Mr. Dodds and Mr. Johnson of this
office on December 13-17, 1971, of construction activities authorized by AEC
Construction Permit No. CPPR-56, and to the discussion held by Mr. Dodds with.
Mr. D. Raasch and other members of your staff, and Bechtel project representa-
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tives, at the conclusion of the inspection and at a-subsequent meeting with
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Messrs. K. Davis and J. Mattimoe on January 7, 1972.
Areas examined during this inspection included (1) documentation of Class I
carbon steel pipe, (2) SMUD review of material design change for steam
generator No. 2, (3) weld repair on steam generator No. 1, (4) results of
measurements of valves, (5) instructions to welders, (6) continuation of
previous review of QC system for instrumentation, (7) vendor and construction
recor,ds for electrical components, (8) vendor and construction records for
cables, (9) QC program and construction of on-site fabricated Class I vessels,
-(10).QC program for handling the reactor pressure vessel and stcom generators,
and (11) records relating to materials used in the post tensioning system for
the containment vessel. Within these areas, the inspection consisted of
selective examinations of procedures and: representative records, interviews
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During this. inspection it was found that several of your activities appeared to
be in noncompliance with AEC requirements. The items and references to
pertinent requirements are listed in the enclosure to this letter.
Please
provide us within 30 days, in writing, with your comments concerning these items,
any steps which have been or will be taken to correct them, any steps which have
been or'will be taken to prevent recurrence, and the date all corrective nctions
or preventive measures were or will be completed.
Your reply should emphasize,
in particular, any appropriate changes that have been or will be made to improve
the effectiveness of your quality assurance program.
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It- is our understanding, .with respect to the' following items, that you intend
to take the actions indicated.
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- 1.: ~ Review the need for'odditional testing and/or obtain additional
documentation to show the acceptability of.the use of unnormalized SA 516
steel- for one of the shell' rings in- s team generator No. 2.
To clarify
the documentation,f the cause of the design contract variation will be
-included in the nonconformance report.
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A manufacturing data report will be 'obtained for circuit breaker No.
52-4A01-1200A. .Further, the electrical equipment records will be examined
to assure that'all applicable manufacturing data reports have been
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received.
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A Nonconformance Report will be prepared for station battery charger,No.
633-1-H4BD requesting Engineering disposition because of the excessive
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time required to trip the output breaker for pole N' .1.
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The manufacturer's tests of the battery chargers will be reviewed to assure
independent. inspection of performance tests and that the records adequately
identify the inspector in accordance with AEC Criteria X and XVII
respectively.
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5.
The procedures provided by Babcock and Wilcox Company for receipt, inspection,
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handling, storage and installation of the reactor vessel and the steam
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generators will .be implemented by Construction Management as applicabic.
'6~." -The quality control program governing the construction of Class I field
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f,j erected tanks will be evaluated to determine if the implemented non-
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'e destructive test program'is adequate to assure quality consistent with the
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safety importance pf the tanks.
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7. , ;The procedure controlling weld filler material for Class I field erected
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, tanks will be changed to limit the duration of time that low hydrogen
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Jfiller. material may be used.after disbursal from the holding ov
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We will1 examine your actions on the above items at the time of our next inspection.
Should you have any questions concerning1this inspection, we-will be glad to
, discuss them with you.
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bec: LJ. B..Henderson, CO
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Sincerely,
A. Giambusso,.CO
L. Kornblith, CO
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R. H. Engelken, CO
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T - R. W. Smith -
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CO Files-
Director
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V. P. McMahon.
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Local PDR
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T. Laughlin
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