ML20100C747

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Final Deficiency Rept 55(e)-84-29 Re Welds in Reactor Controls,Inc CRD Support Sys.Initially Reported on 840726. Evaluation Indicated That Condition Would Not Adversely Affect Safety of Operation
ML20100C747
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 11/13/1984
From: Mangan C
NIAGARA MOHAWK POWER CORP.
To: Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
(NMP2L-0235), (NMP2L-235), 55(E)-84-29, NUDOCS 8412050574
Download: ML20100C747 (2)


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i M V NIAGARA R UMOHAWK NIAGARA MOHAWK POWER CORPORATION /300 ERIE BOULEVARD W L PHONE (315) 474-1511 November 13, 1984 (NMP2L 0235)

Mr. R. W. Starostecki, Director U. S. Nuclear Regulatory Comission Region I Division of Project and Resident Programs

'631 Park Avenue King of Prussia, PA 19406 Re: Nine Mile Point - Unit 2 Docket No. 50-410

Dear Mr. Starosteckt:

Enclosed is a final report in accordance with 10CFR50.55(e) for the problem concerning welds in the control rod drive support system.This problem was An interim report was submitted via our letter dated Augustrep 1984.

27, 1984 Very truly yours, C. V. Mangan Vice President Huclear Engineering and Licensing CVM/GG/dd Director of In'spection and Enforcenent xc:

U. S. Nuclear Regulatory Commission Washington, DC 20555 R. A. Gramm, NRC Resident Inspector Project File (2) 84 gDj2050574e41333ADOCK 05000410 PDR

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L' NIAGARA M0 HAWK POWER CORPORATION NINE MILE POINT-- UNIT 2 DOCKET.NO. 50-410 Final Report for a Problem Concerning Welds in CRD Support System (55(e)-84-29)

' Description of the Problem The problem concerns welds in'the control rod drive support system furnished by Reactor. Controls, Incorporated. - An inspection of 12 randomly selected welds indicated that four welds were 7/16 inch instead of the 1/2 inch shown on Reactor: Controls, Incorporated drawings.

Analysis of Safety Implications Reactor Controls, Incorporated has informed Stone & Webster that its evaluation shows that the minimum size weld required for the joints in

- question was 3/16 inch rather than 1/2 inch shown on the drawings.

Therefore, this condition would not adversely affect the safety of operations of the plant and the criteria for reportability have not been met.

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