ML20082B934
| ML20082B934 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/15/1983 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NED-83-566, TAC-52448, NUDOCS 8311210376 | |
| Download: ML20082B934 (2) | |
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Georg;a Power Company 333 Predrront Avenue Attarta. Geora.a 30338 Telephone 404 5266S26 Venq Address:
Prxt Off ce Box 4545 Attanta, Gogia 30302 Georgia Power 4
L T. Cucwa the soufre "Wrm enom Manager fiuctoar En7neer ng NED-83-566 and Chet fLclear Ernneer November 15, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 i
Division of Licensing U. S. Nuclear Regulatory Comunission Washington, D. C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EIWIN I. HATCH NUCLEAR PLANT UNIT 1 CORE RECONSTI'IUTION OUTAGE Gentlemen:
In response to inquiries by members of your staff and for further amplification of our plans for the ' current Plant Hatch Unit I core reconstitution outage (see details' presented in our October 5,
- 1983, letter), GPC provides the following infomation:
As stated in that letter, the unit experienced an increase in offgas activity in early September, 1983, indicative of a small number of leaking fuel rods.
Due to operational considerations, including outage scheduling for Plant Hatch Unit 2
recirculation pipe replacement, GPC decided to shut down Unit 1 and replace the leaking fuel prior to the beginning of the Unit 2 piping replacement outage.
Plant Hatch Unit 1 is currently shut down and the core has been unloaded, but because fuel sipping and inspection are only just beginning, the extent and cause of the failures are not yet known.
All fuel in the core will be sipped and the leaking fuel assemblies ' identified.
Visual examination and non-destructive testing techniques will be used on selected fuel assemblies to identify the failure mechanism and assess the condition of some non-failed rods.
If the failure mechanism is other than crud induced localized corrosion (CILC), we will inform you of our findings.
To provide reasonable assurance that offgas levels will be low during operation, our plans are that no identified leaking fuel rods will be reloaded. Also, to the extent feasible and consistent with the revised core design, other material judged to be most susceptible to CILC will not be included in the portions of the batches for reinsertion.
'Ihe core design for continued operation has been based on removing a large part of several l
reload batches, with utilization of some fresh and available previously l
irradiated fuel from the pool as replacements.
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- PDR ADOCK 05000321
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Georgia Power A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Oilef Operating Reactors Branch No. 4 November 15, 1983 Page 1ko To minimize the probability of future CILC failures, General Electric has developed a program to address the zircaloy material variability, and fresh fuel loaded during this and future outages will have received the benefit of that program.
Fresh fuel loaded during two previous outages at Hatch 1 received at least partial benefit from that program.
In addition, GPC has employed General Electric to assist us in a water chemistry improvement program to f ner reduce the likelihood of future CILC failures.
Very truly yours, W $"
L. T. Gucwa LDf/RDB/mb xc:
J. T. Beckham, Jr.
II. C. Nix, Jr.
J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector T00775 m