ML20084J284

Followup of 730424 AO Rept Re Failure of Electromatic Relief Valve NR-108-B During Operability Test.Addl Investigation Revealed Failure Due to Solenoid Core Guide Pin.New 304SS Guide Pins Machined to Proper Dimensions

ML20084J284
Person / Time
Site:	Oyster Creek
Issue date:	06/22/1973
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084J282	List: ML20084J279 ML20084J284
References
NUDOCS 8305120388
Download: ML20084J284 (2)

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! Jersey Central Powcr & Light Company M ADISON AVENUE AT PUNCH BOWL RO AD e MoRRISTOWN, N.J. 07360 e 539-6111 y ;--~~

, June 22, 1973 / $ Q M b

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,@j' g Mr. A. Giambusso / W di Deputy Director for Reactor Projects f. gip 3 p.;g Directorate of Licensing ,s

.' 3 United States Atoaic Energy Commission 7 4

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4 Washington, D. C. 20545 .

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Dear Mr. Giambusso- ,

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Subject:

Oyster Creek Station 4

Docket No. 50-219 i Electromatic Relief Valve Failure This letter is intended to follow up our April 24, 1973 letter re-

, porting one electromatic relief valve NR-108-B failed an operability test. As a result of additional investigation into this problem, the reason for the fail-ure of the "B" electronatic relief valve to open during the test was traced to the failure of the solenoid core guide pin as previously reported. The solenoid 4

core is guided by two 1/2" pins silver soldered to their m pport plates. The soldered joinc failed parcially because of marginal soldering. The guido pins

] were cocked to one side and prevented the solenoid core-fron moving in the trip

direction as required.

4 To prevent this type failure from reoccurring, the following repair was made to the pins support plate assembly of all five electromatic relief vsives at Oyster Creek. (Please refer to the attached drawing.) New 304SS guide pins were machined to the dimensions shown en the attached drawing. The new pins-were welded to the underside of the support plates using 308L wire. New-1/8" spacers were installed between the solenoid core frame.and the guide support to

. . clear the underside weld.

Upon completion of the repair, the valves were tested satisfactorily with the reactor at rated pressure during our restart following our recent re-fueling outage.

4 Enclosed are forty (40) copics of this report. ,>

Very truly yours,._ f QI.L ' 4 ' './[ 'jI 830512030s 740207 PDR ADOCK 05000219

' g/ f c' W P '

S PDR Donald A. Ross  ;

Manager, Nucicar Generating Stations .

DAR:cs. . .JV Enclosures ~ /'f cc: . Mr. J. P. O'Reilly, Director

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- Directorate of Regulatory Operations,' Region I f

COPY SENT REGION 7%

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