ML20044A625

Requests Approval of Temporary Noncode Repair of ASME Code Class III Piping Flaw.Flaw Located in 30-inch Diameter Moderate Energy Svc Water Line.Svc Water Sys Will Be Evaluated for Other Flaws,Per Generic Ltr 90-05

ML20044A625
Person / Time
Site:	Hope Creek
Issue date:	06/21/1990
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20044A626	List: ML20044A625 ML20044A627
References
GL-90-05, GL-90-5, NLR-N90129, NUDOCS 9006290302
Download: ML20044A625 (3)

Text

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Public Service

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Electric and Gas 1 Cornpany -r

Steven E. Mittenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1100 Vk:e President and Chief Nucbar Officer F

June 21, 1990 .

m NLR-N90129  !

I United States Nuclear Regulatory Commission '

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. Document-Control Desk

Washington, DC 20555

= Gentlemen: l i

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[1 REQUEST FOR APPROVAL OF TEMPORARY

'NON-CODE REPAIR OF CODE CLASS III PIPING- -

HOPE CREEK GENERATING STATION DOCKET NO.-50-354 ,

Public Service Electric and Gas Company (PSE&G) hereby requests

. approval-to perform a non-code temporary repair of an ASME Code  ;

Class'3 pipe-flaw. This issue was discussed with i Mr.

C. Y. Shiraki, NRC Licensing Project Manager. The flaw'is

~ located in1the~ thirty inch diameter moderate' energy service water

'line which supplies the non-safety related Reactor Auxiliary

.I Cooling System (RACS) heat exchanger down stream of1the Safety

-Auxiliary? Cooling System (SACS) heat exchangers isolation valves.- i The flaw-is a pin hole size through wall' leak in'a' degraded area J(below'ainimum wall) approximately 2 1/2"'long. .PSE&G has followed the provisions;of Generic: Letter 90-05 and has determined the following:

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1. ' Flaw Detection During Plant Operation and Impracticality.

Determination.

H As described above, the leak is in a thirty-inch service ,

water line which supplies the RACS heat exchanger. i

'* Isolation of the leak by closing the two SACS' heat 4 exchangers discharge valves to perform:a code repair would remove the ultimate heat sink for the RACS heat exchanger.

This action would force a plant shutdown. This is despite the fact'that no safety related heat loads are affected, and no-Technical Specification Limiting condition for Operation applies.

L :2. Root Cause Determination and Flaw Characterization

'The-flaw is a localized pit with a pinhole size through wall ,

leak. The affected area measures approximately 2 1/2 inches at its maximum diameter. This was determined utilizing a 0

0 9006290302 900621 I PDR ADOCK 05000354 1 P PDC L'

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Document Control Desk 2 June 21,1990 i NLR-N90129 1 it suitable ultrasonic testing method. The SA155,_ Grade KC70, i Class 2 carbon steel piping is internally coated with an l l epoxy to prevent corrosion. It is suspected that a flaw in

? the coating allowed service water to directly contact the  !

piping and initiate a localized corrosion pit.

3. Flaw Evaluation PSE&G has utilized thi "through wall flaw" approach described in Generic Letter 90-05 to determine the structural integrity of the piping. Attachment 1_is a copy of these calculations. Based on these calculations  !

structural integrity of the piping is assured.

PSE&G proposes to utilize a 5 inch square by 3/8 inch thick l' l carbon steel patch coated with an epoxy sealant over the L leak. The patch will be secured utilizing an appropriate l . size fillet weld completely around the perimeter of the  ;

L patch. Pursuant to the Generic Letter, the flaw will be-l- code repaired at the next scheduled outage of 30 days or l more.

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, 4. Augmented Inspection y

PSE&G will evaluate the service water system for other flaw  ;

susceptible locations and inspect them as described in

. Generic Letter 90-05. NRC will be notified if other flaws  ;

requiring evaluation according to the rules of.Section XI l are detected.

In addition, PSE&G will monitor the non code repair section of'the affected piping on a regular frequency. The area will_be ultrasonically tested at 3 month intervals until code repaired.

L If you have any questions regarding this transmittal, please do not hesitate to call. Your expeditious processing of this waiver is requested.

Sincerely, Otis

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Attachment

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4 Document Control Desk 3 June 21, 1990 NLR-N90129 C Mr. C. Y. Shiraki Licensing Project Manager Mr. T. P. Johnson Senior Resident Inspector Mr. T. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering 4

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