ML072850093
| ML072850093 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/26/1992 |
| From: | Devine J GPU Nuclear Corp |
| To: | Document Control Desk, NRC/SECY |
| SECY RAS | |
| References | |
| 50-219-LR, 5000-92-3026, AmerGen-Intervenor-57, C321-92-2163, RAS 14374 NUDOCS 9206010165 | |
| Download: ML072850093 (2) | |
Text
Citizens Exhibits 57 Nuclear U.S. NUCLEAR EGIUNAD Comm"SI~
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Parsippany. New Jersey 0n 201.316-7000 TELEX 136-482 Writer's Direct Dial Number:
May 26, 1992 5000-92-3026 C321-92-2163 DOCKETED USNRC October 1,2007 (10:45am)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF U.S. Nuclear Regulatory Commission Attn: Document Control Desk
,Washington, DC 20555 Gentlemen:
Subject:
Oyster Creek.Nuclear Generating Station Docket No. 50-219 Facility Operating License No.
DPR-16 Oyster Creek Drywell Containment (OCNGS)
References:
(1)
NRC Letter dated April 24, 1992, "Evaluation Structural Integrity of the Oyster Creek Drywell (TAC No.
M79166)."
Report on f
(2)
GPUN Letter C320-92-264 dated November 26, 1990, "Oyster Creek Drywell Containment."
In response to the Reference 1 request, GPU Nuclear commits to continue taking UT drywell measurements at refueling outages and at other outages of opportunity.
The measurements will be at areas previously inspected. and also at other accessible areas not previously inspected.
Drywell thickness measurements will continue for the life of the plant.
The following is our current plan for Oyster Creek drywell UT thickness measurements.
(1)
During the 14R outage, GPU Nuclear will take UT thickness measurements in the drywell sandbed region, from the torus room side (outside the drywell), at shell locations not readily accessible from inside the drywell.
These are areas not previously inspected.
The specific locations selected for inspection will be identified once we have direct.
access to the sandbed region.
Assuming that these measurements confirm that we have bounded the corrosion problem with our current inspection locations, we currently do not plan to make repeat measurements at these specific locations.
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C321-32-2163 Page Z (2)
Now through the 15R outage, GPU Nuclear will continue taking UT thickne:s measurements in accordance with the priority method described in PRference 2, Attachment 1, "GPUN Specification IS-328227-004, FunLtional Requirements for Drywell Containment Vessel Thickness Examination".
(3)
After the 15R outage, GPU Nuclear will assess the condition of the drywell by evaluating the then current UT thickness measurements and
- will formulate an extended inspection plan.
The plan will identify measurement locations including frequency of inspection for the remaining life of the plant.
If you have any questions or comments on this submittal or the overall drywell corrosion program, please contact Mr. Michael Laggart, Manager, Corporate Nuclear Licensing at (201) 316-7968.
Very truly yours, J. C DeVine, Jr.
Vice President and Director Technical Functions JCD/RZ/amk cc:
Administrator, Region 1 Senior Resident Inspector Oyster Creek NRC Project Manager