ML20076F136
| ML20076F136 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/16/1983 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8308250286 | |
| Download: ML20076F136 (1) | |
Text
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Northern States Power Company 414 Nicollet Mall Minneapolis. Minnesota 55401 Telephone 1612) 330-5500 August 16, 1983 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Supplemental Information Re1.ated to Reload Methodology Topical Reports - Radiological Consecuences Reference 1
" Reload Safety Evaluation Methods for Application to PI Units" NSPNAD-8102P Revision 1, December 1982.
Reference 2
" Assessment of Potential Radiological Consequences for High Exposure Fuel" XN-NF-719(P), August 1983.
Per our commitment made in our December 13, 1983 letter, we have reviewed the validity of the methodology in NSPNAD-8102P (Reference 1) for assessing the radiological consequences of accidents involving of fsite releases for exposures up to a peak pellet exposure of 55 GUD/MTU.
The design basis LOCA and the fuel handling accident have been re-analyzed by Exxon (Reference 2 submitted August 15, 1983) and have been shown not to violate 10 CFR 100 guidelines at an exposure limit of 55 GWD/MTU peak pellet.
For all other accidents involving offsite releases, the FSAR limit of 20%
failed fuel rods will be used. This limit is based on the maximum number of failed fuel rods calculated in the FSAR for transients other than the LOCA and fuel handling accident.
Specifically, the 20% limit cones from the locked rotor analysis.
Since these transients involve significantly less fuel failures than the design basis LOCA, which assumes 100% failure, they will be bounded by the LOCA calculations and will not violate 10 CFR 100 guidelines.
Therefore, the 20% failure limit stated in NSPNAD-8102P remains valid for these transients.
D M w.
David Musolf Manager - Nuclear Support Se
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cc: Regional Administrator-III Resident Inspector, URC
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