ML19199A685
| ML19199A685 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/10/1976 |
| From: | Arnold R Metropolitan Edison Co |
| To: | Knuth D NRC/IE |
| References | |
| GQL-0347, GQL-347, NUDOCS 7905070284 | |
| Download: ML19199A685 (2) | |
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' CST OFF'CE 30X 542 RE AOl*iG, PEN *4SYLVUJI A 19603 T E L E D w C',E 015 - 9:3-5:1 March 10,197 6 GQL 0347 Director of Nuclear Reactor Regulation Attention:
Dr. D. F. Knuth, Director Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Cc= mission Washington, D. C.
20555 Subj ect : Docket No. 50-320 Three Mile Island Nuclear Statien Unit 2 Deer Dr. Knuth:
On February 9,1976, Mr. L. Narrow of your of' ice was verbally notified of a situation which Metropolitan Edison did not consider reportable in accordance with 10CFR50.53E but which was reported for infor=ation only. This letter constitutes the thirty day follow-up letter.
Descriotion of Incident Duriag unloading of the reactor internals plenum assembly and core support shield from the shipping container, the shins and other shipping hardware were collected and stored in a site ccustruction office while awaiting a final "as shipped" inventory list. In approximately two weeks the "as shipped" inventory list arrived indicating 25 shipping shims had been packed. A count of the shipping shi=s collected from the shipping container totaled 23.
Two (2) shipping shims were missing and at the present time remain unaccounted for. These stainless steel shipping shims are approximately 2" x 4" x.002".
Analvsis of Safety Inclications Should the two missing shipping shims remain undetected in the internals, the possibility exists that they could eventually ledge against a fuel assembly, which would preclude proper heat removal flow and cculd cause hot spots to occur. The occurrence of hot spots would be detectable
- utilizing the incore nonitoring system, which constantly monitors the core conditions during operations.
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To: Jr
. F. Knuth March 10,19 76 GQL 0347 Corrective Action This condition was docu=ented by a site deviation report.
Babcock & Wilcox, the NSSS supplier and erector and United Engineers & Constructors, Inc., the construction manager, have both performed a complete visual re-exa=ination of the internal ccmponents and have verified that the shl=s are not present. Secondly, Babcock & Wilcox has been directed to submit all necessary data to assure GPUSC that the missing shi=s are not centained in the reactor coolant syste= or the reactor internals. This information will be available for your review on site by April 30, 1976.
Very truly ycurs, n
n R. C..tr old Vice President v*
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