ML20197G886
| ML20197G886 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/07/1984 |
| From: | Counsil W NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| F0342A, F342A, SD-30, NUDOCS 8406180194 | |
| Download: ML20197G886 (2) | |
Text
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General Offices
- Seiden Street, Berlin. Connecticut
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HARTFORD, CONNECTICUT 06141-0270 g
oen.Ast uruves seaaca cow-(203) 666-6911 NOA44 A5e IRJCLE AA EeERGT COWM June 7,1984 Docket No. 50-423 F0342A Dr. Thomas E. Murley Regional Administrator Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Reference:
(1)
W. G. Counsil to R. C. Haynes, B10644, dated December 30, 1982.
Dear Dr. Murley:
Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Design and Construction:
Cable Tray Offset Reducers (SD-30)
In a November 22, 1982 telephone conversation between your Mr. L. Briggs and our Mr. R. E. Lefebvre, Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency in the construction of Millstone Unit No. 3 as required by 10CFR50.55(e). The potential significant deficiency involved cracks found in the side rails of several cable tray offset reducers manufactured by T.3. Cope Co.
The cracks occurred in the side rails where the flanges were notched by T. 3. Cope to allow inward bending to form a narrower width for the cable tray. Examination of the manufacturer's drawings indicated that there should have been a seam weld made where the side rails were notched and bent to allow the reduced width.
A preliminary analysis by our architect engineer, Stone & Webster Engineering Corporation, indicated that the structural integrity of the cable trays could be challenged during a seismic event due to this potential significant deficiency.
However, subsequent analyses were performed by Stone & Webster and T.3. Cope using calculations assuming actual cable tray and reducer configurations,100 percent cable fill tray weights, and the specific seismic design "g" values at the affected locations. These analyses have shown that the
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subject cable tray reducers are structurally adequate and will perform their intended function. Based on this, we have determined that no corrective action is necessary and do not consider this to be a significant deficiency.
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We consider this to be our final report regarding SD-30. We trust that the above information satisfactorily responds to your concerns.
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Very truly yours, s
NORTHEAST NUCLEAR ENERGY COMPANY
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. ]Al424 W. G. Counsil
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l Senior Vice President i
cc:
Mr. R.'C. DeYoung, Director Division of Inspection and Enforcement U. S. Nuclear Re Phillips Building'gulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014
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