ML20032E256
| ML20032E256 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 12/15/1970 |
| From: | Kirkman R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | William Cahill CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| References | |
| NUDOCS 8111200116 | |
| Download: ML20032E256 (3) | |
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UNITED STATES m, <,,
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970 BROAD STREET 4
srsrn p NEWARK. NEW JERSEY o7to2 DEC 151970 Consolidated Edison Company of New York 4 Irving Place New York, New York I
Attention:
Mr. William J. Cahill, Jr., Vice President Gentlemen:
This letter relates to the di.:ussion Messrs. Whitesell and Varela of this office held with Mr. E. J. Dadson of your staff during the inspec.
tion of November 16 and 17, 1970, regarding the construction activities 4i authorized by AEC Construction Permit No. CPPR-62.
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Mi As noted during the discussion, apparent deficiencies were identified in.
i volving items not in conformance with Appendix B to Title 10, Code of Federal Regulations, Part 50, entitled, " Quality Assurance Criteria for Nuclear Power Plants", or which may otherwise raise questions concerning I{
adequacy of construction.
These items are as follows:
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Criterion V, Appendix B, 10 CFR 50, entitled, " Instruction and Drawings", states in part:
" Activities affecting quality shall be prescribed by docu-l mented instructions, procedures, or drawings, or a type 7,
appropriate to the circumstances and shall be accomplished
'rf 4 in accordance with these instructions, procedures, or
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drawings.
'7 Yl Contrary to the above, the inspectors found:
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Procedures or instructions relevant to heating the reactor vessel lifting beam and means of determining the surface temperature
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of this beam were not prepared, although the procedure for " Hand-l ling and Setting of IP-3 Reactor Vessel" stipulates that the W
lifting beam must not be used when its surface temperature falls
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below 70 F based on NDTT considerations.
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The log, showing gas pressures, condition of covers, and visitors jf to the area, is not being maintained as required by the Wedco procedure, " Reactor Vessel and Reactor Vessel Head Receipt In-
$gi spection 'and Security During Storage."
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The Wedeo " Procedure for llandling the Reactor Vessel Skid" refer-ences, among others, a " Procedure for Installing the Lifting Beam" and a " Procedure for Setting the Reactor Vessel."
There was no evidence that either' of these procedures' vere being developed.
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Wedco's procedure WQA-4.0, part 2.3.3-a, states in part:
"All records and documentation from the supplier must be on site and acceptable before the item is fully accepted."
Contrary to this procedure, the reactor vessel has been released for installation prior to receipt of the N-1, " Data Report Form."
Please provide us, within 30 days, with your comments concerning these items and any steps which have been or will be taken to correct them and to mini-
- I mize recurrence, including any appropriate changes that have been or will be made to your quality assurance program.
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Should you have any questions concerning the matters discussed in this 1
letter, you may communicate directly with this office.
'j Very truly yours,
/I 2 444 N.
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.t....s J. P. O'Reilly CONSOLIDATED EDISON COMPANY a\\
j Chief, RI6EB, CO: LIQ
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A. Giambusso, CO Forwarded herewith is a copy of a CDN, issued I,
L. Kornblith, C0 cars to the licensee 12/15/70, resulting from in-formation contained in CO Report No. 286/70-6.
TO (Name sad utilt) imriats
.twanns Report is presently in reproduction and will R. Engelken, CO
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be forwarded for information.
cart F rom (Name and umt)
.twah5 E. M. Iloward f r. Reactor Inspector
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CO:I g)).f U PHOht na CAft i
3942 12/17/70 j ust er o s at mi.oario.t
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