ML20133H839

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Interim Significant Const Deficiency Rept Re Oxidized Jumper Clips in Type Rz Push Button Modules Supplied by Bailey Controls.Initially Reported on 850612.Clips Will Be Replaced.Final Rept Will Be Submitted by 850828
ML20133H839
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 07/17/1985
From: Martin T
Public Service Enterprise Group
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8508090535
Download: ML20133H839 (2)


Text

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-M Thomas J. Martin Public Service Electric and Gas Company f.0 Park Plaza Newark, N.J. 07101 201/430B316 Vice President Engineering and Construction July 17, 1985 Dr. Thomas E.

Murley, Administrator U.

S.

Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

SIGNIFICANT CONSTRUCTION DEFICIENCY BAILEY CONTROLS - RZ MODULES HOPE CREEK GENERATING STATION On June 12, 1985, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr.

E.

Kelly, advising of a significant construction deficiency concerning oxidized jumper clips in type RZ push button modules supplied by Bailey Controls.

The following interim report is provided in accordance with 10CFR50.55(e).

Description of the Deficiency During contact resistance testing of twelve (12) RZ modules, two (2) of the 72 push button switch units showed high resistance values (112K ohms and 125K ohms).

These values are high enough to prevent the 862 digital and 7000 analog systems from performing as required by the depression of the RZ push button.

Inspection of the push button switch units revealed oxidation of the spring steel jumper clip used to connect the normally open contacts in series.

Bechtel is preparing to issue a Field Change Package to replace the jumper clips with soldered connections using

  1. 22 AWG bare solid wire.

Approximately 700 RZ modules are affected, including spares.

There are six (6) switches per module with one (1) jumper clip in each switch.

8508090535 850717 PDR ADOCK G5000354 i

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.t Dr.

T.

E. Murley 2

7/17/85 We anticipate providing you with a final report on this issue by August 28, 1985, to include the status of our corrective action and the requisite safety analysis.

Very truly yours, s

C Office of Inspection and Enforcement l

Division of Reactor Construction Inspection Washington, D. C.

20555 NRC Resident Inspector - Hope Creek i

P.

O.

Box 241 Hancocks Bridge, NJ 08038 l

Records Center i

Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 4

l Atlanta, GA 30339 1

I

.