ML20044A625
| 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: |
| References | |
| GL-90-05, GL-90-5, NLR-N90129, NUDOCS 9006290302 | |
| Download: ML20044A625 (3) | |
Text
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Public Service 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
. Document-Control Desk 4
- Washington, DC 20555
= Gentlemen:
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o
[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
Y. Shiraki, NRC Licensing Project Manager.
The flaw'is Mr.
C.
~ 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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' 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.
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- 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 1
I PDR ADOCK 05000354 P
PDC L'
g' 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
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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. _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
carbon steel patch coated with an epoxy sealant over the l
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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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,
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Otis 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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