B10584, Final Deficiency Rept Re Missing Westinghouse Design Thermal Sleeves in 2-inch Chemical & Vol Control Sys (SD-24). Initially Reported on 820712.Affected Thermal Sleeves Will Be Eliminated

Final Deficiency Rept Re Missing Westinghouse Design Thermal Sleeves in 2-inch Chemical & Vol Control Sys (SD-24). Initially Reported on 820712.Affected Thermal Sleeves Will Be Eliminated

ML20069J865
Person / Time
Site:	Millstone
Issue date:	10/13/1982
From:	Counsil W, Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
10CFR-050.55E, 10CFR-50.55E, B10584, NUDOCS 8210250290
Download: ML20069J865 (2)

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October 13,1982 Docket No. 50-423 AEC-MP3-294 B10584 Mr. Ronald C. Haynes Region I Of fice Of Inspection and Enforcement U. S. Nuclear Regulatory 631 Park Avenue King of Prussia, PA 19406

Dear Sir:

Millstone Nuclear Power Station, Unit No. 3, Reporting of Significant Deficiencies in Design and Construction: Westinghouse Design Thermal Sleeves in two-inch CVCS Lines (SD-24)

As required by Title 10, Code of Federal Regulations Part 50, Paragraph 55(e),

Northeast Nuclear Energy Company (NNECO), reported a potential significant deficiency on July 12, 1982 in a telephone conversation between our Mr. R.

Lefebure and your Mr. E. 3. Brunner.

The reported potential significant deficiency was a result of information forwarded by Westinghouse. One of their operating plant customers, Duke Power, discovered though radiography examination and underwater camera inspection, that a thermal sleeve in one of the four Si accumulator piping nozzles to the RCS cold leg piping in McGuire Unit I was missing. This prompted Westinghouse to initiate investigations and subsequently inform any of their customers who have plants with similarly designed thermal sleeves. Thus, we were informed because it was determined that the thermal sleeves used in connecting the two-inch CVCS fill lines to the 31-inch inside diameter reactor coolant loop crossover pipes of Millstone Unit No. 3 utilized the affected thermal sleeve design. In turn, we then notified the NRC of a potential significant deficiency.

As a follow-up to a growing generic NRC concern, the NRC issued IE Information Notice No. 82-30, " Loss of Thermal Sleeves in Reactor Coolant System Piping at Certain Westinghouse PWR Power Plants." This has acted as a reinforcement to our concern with this matter.

After performing a safety and engineering evaluation, Westinghouse has recommended to us to eliminate the affected thermal sleeves. As such, we consider this reported potential significant deficiency resolved.

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Per a September 29, 1982 telephone conversation between our Mr. 3. M. Powers and your Mr. T. Elsasser, this final disposition is being forwarded on or before October 13,1982.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY M E. M W. G. Counsil Senior Vice President 5Wu By: 3.Y. Opeka Vice President Nuclear Operations cc: E. 3. Brunner l

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