ML20154D528

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Discusses Insp Rept Conducted on 710623-25.Major Areas Inspected:Qa/Qc,Methods & Procedures for Certifying Vendor Certification & Use of Safety Rept Analysis Change Procedure.Corrective Action Will Be Examined in Future Insp
ML20154D528
Person / Time
Site: Diablo Canyon, 05000000
Issue date: 07/19/1971
From: Rich Smith
US ATOMIC ENERGY COMMISSION (AEC)
To: Peterson R
PACIFIC GAS & ELECTRIC CO.
Shared Package
ML20154C370 List:
References
FOIA-88-156 NUDOCS 8805190221
Download: ML20154D528 (2)


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Jully 19,1971 Pacific Gas and Electric Ceapeny Decket No. 050 0123 245 Market street Docket as. 050-0323 San Francisco, Catitarnia % 106 Attention: Mr. Richard M. Peterson Senior Vice Freefdent Centlemes:

This refers to the inspection conducted by Messrs. A. D. Johamon and R. T. Dodds of this of fice en June 23-23, 1971, of constructica activittee authorised by AEC Construction Fermit Mos. CFFt.39 and CFFR-49, and to the discussion of our findings held by Mr. Johnson with Mr. J. D. Worthington, Mr. F. F. Heuta, and esebers of their staffs en June 30, 1971.

Areas maamland during this taspection inc1wled the QA-QC pregrame se reisted to menutocture, teattag, placement, and curtas of concrets to be usM in the l 1

construction of Unit me. 2, and the Qt-QC program epocifically relating to j

Class I components to be installed im Unit us.1. Addittoast areas enemined l tac 1Med (1) the methods and precedurse used for soeuring that vender cartifications are constatant with descriptions to be provided is the Final Safety Analysis Report for both unita, (2) the need far, and avettability of, documented disonstenal checks of tall thicknesses of sissifiaast sised i

' valves to be installed within the pressure boundary of the primary coolant system. (3) the use of your Safety Report AnalyeLa chamas procedure, and (4) the meirtenance and centret of internal records relating to cemetructies activittas which any reflect the quality characteristics of the structures.

systems and ces incorporated ta the units. Withis these areas, the l Laspection eoneisted ef eelecttve examinstisaa ef procedures and represeata-j tive records. Laterviews with reactor facility personnel, and observations i by the inspectors.

j No items of nonconformance were identified within the scope of this l j inspection.

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Pacinc Gee and Electric Company -2 July 19, 1971 It is our understancing, with respect to the following treme, that you tatend to take the actions indicated: ,

1. Review your QA system to assure that all changes made either by you  ;

or your nuclear steam supplier, which would sisatficently aller the  :

dcacription provided in the PEAR, vill be reflected in the TSAR. l

2. Collect all calibret ton procedures related to inspection and test i equipment and incorporate these procedures Lato an appropriate manual {

form as required by your recently approved QA Procedure No. PtQ-5.

3. Conduct a survey of both of ficial and unofficial loss and records at the sits to determine the scope and content of all records belas l em intain ed.
4. Determine whether dissensional checks have been sede of significant sized valves withta the pressure boundary of the primary coolant system and, where documented results are unavailable, inittate a pro 3 ras to determine the adequacy of valve call thicknesses.

These itene vill be etastnad during the next inspection.

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No reply to this letter is necessary, but should you have any questions concerntag this inspection, se will be Clad to discuss them with you. l Sincerely.

.p:

R. W. Smith Dir ec tor cc J. D. 'arthingter; F. F. Paut e -

C. V. Richards bec: J. B. Henderson, CO ($)

A. Giambusso, CO R. H.Engelken, CO L. Kornblith Jr. , CO l

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