ML20034B093
| ML20034B093 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/17/1990 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20033G848 | List: |
| References | |
| GL-88-01, GL-88-1, TAC-69149, NUDOCS 9004250324 | |
| Download: ML20034B093 (4) | |
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NUCLEAR REGULATORY COMMISSION'.
UNITED STATES 2
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/I WASHINGTON, D. C. 20666
\\.....l April 17; 1990 Docket No. 50-219 Mr. E. E. Fitzpatrick j
Vice President and Director Oyster Creek Nuclear Generating Station
- P. O. Box 388 :
Forked River, New Jersey 08731
Dear Mr. Fitzpatrick:
SUBJECT:
OYSTER-CREEK HUCLEAR GENERATING STATION - RESPONSE REVIEW OF.
GENERICLETTER-(GL)88-01.(TACNO.69149)-
The NRC staff with assistance from Viking Systems International'(VSI), has completed its review' of the response by GPU Nuclear Corporation (GPUN/ licensee).-
-to resolve the issues in GL-88-01:"NRC Position on IGSCC in BUR Austenitic-Stainless Steel PipinD." GPUN's response is~ documented in letters dated August 12, 1988',- January 31, 1989, November'16,'1989 and February 21, 1990.
As discussed in-the enclosed Safety Evaluation ~ (SE), the staff finds that -
GPUN's response is acceptable with the exception of the following:
1.
The licensee's position not to amend the Technical Specifications (TS) to include a statement on ISI.as required in GL;88-01..
2.
The licensee's position to reduce the-frequency of piping ' inspections based on the implementatioreof hydrogen water chemistry (HWC). The staff.1 has learned through reports >that piping weld cracking-has occurred at two nuclear power generating facilities which have-been operating with HWC.
The staff hhs some concerns-regarding the' effectiveness of'HWC in-7 mitigating IGSCC. Therefore, the staff..is not granting inspection credit-1 based on the implementation of HWC at this time until the staff's concerns are resolved.
3.
The licensee's position to reduce the frequency of inspections on SI-treated welds.
j 4
The licensee did not justify the reduction in the frequency of 1
inspections of welds classified asilGSCC Categories C, D,'E, and G.
The j
licensee should revise the inspection schedules for these welds.in l l accordance with GL-88-01-and all,1GSCC Category G welds should be inspected during the next scheduled refueling outage (13R).
j S.
The licensee's position concerning classifying five casting-to-casting welds in the Recirculation System as uninspectable. There are techniques i
available in the industry to inspect castings and the castings should be inspected in accordance with GL 88-01.
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6.
The licensee's-position concerning sample expansion based on systems rather than by IGSCC category as required.in GL 88-01.
7.
The licensee's-position of considering flaw evaluation having no.._
-constraint on plant restart. The licensee should revise its position and:
follow-the staff's position in GL 88-01 reporting requirements which requires NRC approval of flaw evaluations and/or-repairs in accordance with IWB 3640 and IWA 4130 before resumption of operation.
8.
The licensee's-position of not ultrasonically inspecting the RWCU piping welds.outboardofthesecondaryContainmentIsolation_ Valves (CIV).cfter 13R refueling outage.
The licensee should ultrasonically. inspect-at least-10% of the welds outboard of the secondary CIV during each refueling outage.
For a detail discussion of'these items see ~ sections 2.0 and 3.0 of the:
Technical Evaluatien Report (TER) prepared by Viking Systems International.
The TER is attached to' the staff's Safety Evaluation.
U 1
Based on the above, GPUN is requested to revise their inspection plans as required in GL 88-01. As requested in GL 88-01, GPUN should also incorporate:
an ISI statement per GL 88-01 in the Technical Specifications.
GPL'N is requested to submit their revised inspection plans'at least four months prior l
to the 13R refueling outage for staff review.
i We request that you respond within 30 days o' receipt of this letter indicating you intent to comply with these requirements, i
Sincerely,
/
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Alexander U. Dromerick, Senior Project Manager Project Directorate 1-4 i
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated i
cc w/ enclosure:
See next page 4
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Mr, E. E. Fitzpatrick~
-2 April 17,.1990 6.
The-licensee's positio;. concerning. sample expansion based on systems rather than by IGSCC category as required in GL 88-01, 7.
The licensee's position of considering flaw evaluation having no constraint on plant restart.
The licensee should revise its position and follow the staff's position in GL 88-01 reporting requirements which requires NRC approval of flaw evaluations and/or repairs in accordance with IWB 3640 and IWA 4130 before resumption of operation.
8.
The licensee's position of not ultrasonically inspecting the RWCU piping welds outboard of the secondary Containment Isolation Valves (CIV) af ter 13R refueling outage.
The licensee should ultrasonically inspect at I
least 10% of the welds outboard of the secondary.CIV during each refueling outage.
For a detail discussion of these items see sections 2.0 and 3.0 of the Technical Evaluation Report (TER) prepared by Viking Systems International.
The TER is attached to the staff's Safety Evaluation.
Based on the above, GPUN is requested to revise'their.-inspection plans as required in GL 88-01. As requested in GL 88-01, GPUN shculd also incorporate an ISI statement per GL 88-01 in the Technical Specifications. -GPUN is:
requested to submit their revised inspection plans at least four months prior to the 13R refueling outage for staff review.
We request that you respond within 30 days of receipt of this letter l
indicating you intent to comply with these requirements.
Sincerely,
/s/
Alexander W. Dromerick, Senior Project Manager Project Directt, rate I-4 Division of Reactor Projects -' I/II Office of Nucler.r Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION Uocket tile, Plant File B. Boger A. Dromerick 4RC"&^ Local'PDRs S. Var S. Norris OGC ACRS (ga10)
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- 04/I6/90
- 04/ /9 OFFICIAL RECORD COPY Document Name: TOM 20A l
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- lMr.i E. ' E. Fitzpatrick Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Station l
cc:
Ernest L. Blake, Jr.
Resident Inspector Shaw, Pittman, Potts and Trowbridge-c/o U.S.'NRC
.l 2300 N Street, NW Post Office Box 445 Washington -D.C.
20037 Forked River, New Jersey '08731 3
J.B. Liberman, Esquire Comissioner Bishop.-Liberman, Cook, et al.
New Jersey Department of Energy' i
/
1155 Avenue of the Americas 101 Commerce Street.
New York, New. York 10036-Newark, New Jersey 07102 Kent Tosch, Chief
.i Regional Administrator, Regien I New Jersey Department'of~ Environmental U.S. Nuclear Regulatory Comission-Protection 475 Allendale Road Bureau of Nuclear Engineering King of Prussia, Pennsylvania 19406 CN 415-i Trenton, New Jersey 08625 BWR Licensing Manager GPU Nuclear Corporation i
l' Upper-Pond Road Parsippany, New Jersey 07054 i
Mayor Lacey. Township 818 West Lacey Road Forked River, New Jersey 08731 j
Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop:
Site Emergency Bldg.
-P. O. Box 388 Forked River, New Jersey 08731 1
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