ML20058A638
| ML20058A638 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/18/1990 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20058A641 | List: |
| References | |
| GL-88-01, GL-88-1, TAC-67183, NUDOCS 9010290044 | |
| Download: ML20058A638 (3) | |
Text
_
October 18, 1990 Docket No.- 50-219 Mr.-E. E. Fitzpatrick Vice President and Director Oyster Creek-Nuclear Generating Station
-P.C. Box 388 Forked River, New Jersey 08731
Dear Mr. Fitzpatrick:
SUBJECT:
INTERGRANGLAR STRESS CORROSION CRACKING (IGSCC) - INSPECTION AND REPAIRSFOROYSTERCREEKNUCLEARGENERATINGSTATION(OCNGS)
The NRC staff has completed its review of GPU Nuclear Corporation's (licensee) submittals dated January 20, 23, and 31,1989, October 30, 1989, and February 21, 1990 regarding the IGSCC inspection and repairs, additional information and future inspection plans for the Reactor Water Cleanup System (RWCU) during the
-13R refueling outage at OCNGS. The licensee reported that a total of 150 welds susceptible to IGSCC in various stainless steel piping systems were inspected during this outage and that six welds were found to contain IGSCC indications.
Five flawed welds were repaired with standard weld overlays and one was evaluated by fracture mechanics as acceptable without repair for one fuel cycle.
In addition, IHSI was effectively applied to forty-two welds, and six structural weld. overlays were inspected for IGSCC and no indications of IGSCC were found.
Furthermore, the licensee submitted its 13R IGSCC inspection plan to inspect 10% of the RWCU weld population outboard of the containment isolation valves.
Based on the review of the information provided by the licensee, M e staff finds the inspection and overlay repairs that were performed meet the gufdo-lines for GL-68-Ci acceptable with the exception of the inspection scope of l
Category G welds (welds not yet being properly inspected) and the proposed RWCU IGSCC inspection plan subsequent to 13R. Because of the timing of GL-88-01 issuance, the reduced inspection scope of Category G welds for 12R refueling outage.was accepted. The staff's review, and conclusions are contained in the enclosed Safety Evaluation, i
Sincerely, original signed by Alexander W. Dromerick, Senior Project Manager Pro,iact Directorate I-4 Div1; ion of Reactor Project - I/II 1
Office of. Nuclear Reactor Regulation j
Enclosure:
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October 18, 1990
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1 Mr. E. E. Fitzpatrick Vice President and Director Oyster Creek Nuclear Generating Statian P,0. Box 388 Forked River, New Jersey 08731
Dear Mr. Fitzpatrick:
1
SUBJECT:
INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) - INSPECTION AND REPAIRSFOROYSTERCREEKNUCLEARGENERATINGSTATION(OCNGS)
(TAC HO. 67183)
-The NRC staff has completed its review of GPU Nuclear Corporation's (licensee) submittals dated January 20, 23, and 31,1989, October 30, 1989, and February 21, 1990 regarding the IGSCC inspection and repairs, additional information and future inspection plans for the Reactor Water Cleanup System (RWCU) during the 13R refueling outage at OCNGS. The licensee reported that a total of 150 welds i
susceptible to IGSCC in various stainless steel piping systems were inspected l
during this outage and that six welds were found to contain IGSCC indications, f
Five flawed welds were repaired with standard weld overlays and one was evaluated by fracture mechanics as acceptable without repair for one fuel cycle.
In addition, IHSI was effectively applied to forty-two welds, and six structural weld overlays were inspected for IGSCC and no indications of IGSCC were found.
Furthermore, the licensee submitted its 13R IGSCC inspection plan to inspect 10% of the RWCU weld p oulation outboard of the containment isolation valves.
Based on the review of the information provided by the licensee, the staff finds the inspection and overlay repairs that were performed meet the guide-lines for GL-88-01 acceptable with-the exception of the inspection scope of Category G welds (welds not yet being properly inspected) and the proposed RWCU l
IGSCC ins issuance,pection plan subsequent to 13R.
Because of the timing of GL-88-01 the reduced inspection scope of Category G welds for 12R refueling-outage was accepted. The staff's review, and conclusions are contained in the j
enclosed Safety Evaluation.
Sincere 1,
/
M4h A-Y Alexander W. Dromerick, Senior Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page l
Mr.' E.- E. Fitzpatrick Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Station cc:
Ernest L. Blake, Jr.
Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C.
20037 Forktd River, New Jersey 08731 Comissioner I. H. Jolles, Executive Vice President New Jersey Department of Energy GPU Service Corporation 101 Commerce Street 100 Interpace Parkway Ne'sark, New Jersey 07102 Parsipanny, New Jersey 07054 Kent Tosch, Chief Regional Administrator, Region I New Jersey Department of Environmental l-U.S. Nuclear Regulatory Commission Protection 475 Allendale Road Bureau of Nuclear Engineering l
King of Prussia, Pennsylvania 19406 CN 415 i
Trenton, New Jersey 08625 l
BWR Licensing Manager l
GPU Nuclear Corporation 1 Upper Pond Road
(
Parsippany, New Jersey 07054 Mayor Lacey Township i
L 818 West Lacey Road Forked River, New Jersey 08731 l
Licensing Manager i
Oyster Creek Nuclear Generating Station l
Mail Stop:
Site Emergency Bldg.
P.-0. Box 388 Forked River, New Jersey 08731 1
1.