ML20073E223
| ML20073E223 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/31/1983 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 6371, NUDOCS 8304140384 | |
| Download: ML20073E223 (2) | |
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AM NIAGARA MOHAWK POWER CORPORATION /300 ER!E DoVLEVARD WEST. SYRACUSE. N Y.13202/ TELEPHONE (315) 474-1511 March 31,1983 (6371)
Mr. R. W. Starostecki, Director U.S. Nuclear Regulatory Commission Region I Division of Project and Resident Programs 631 Park Avenue King of Prussia, PA 19406 Re: Nine Mile Point Unit 2 Docket No. 50-410 4
Dear Mr. Starostecki:
Enclosed is a 30 day final report in accordance with 10CFR50.55(e) for the problem concerning radiation source term data supplied by General Electric Company. This condition was reported via telecon to Mr. H. Kister of your staff on February 24, 1983.
Very truly yours, (JfD%%fSw C. V. Mangan Vice President Nuclear Engineering & Licensing xc: Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. R. D. Schulz, Resident Inspector 8304140384 830331 h
PDR ADOCK 05000410 S
NIAGARA M0 HAWK POWER CORPORATION NINE MILE POINT UNIT 2 DOCKET NO. 50-410 Final Report for a Problem Concerning Radiation Source Term Data Description of the Problem A review of our calculations indicated that there were significant differences between the Nine Mile Point Unit 2 fission products inventory list and another boiling water reactor fission products inventory list.
Consequently, General Electric Company was requested to review the source term data supplied by them for Unit 2.
On February 4, 1983, General Electric provided a revised fission product inventory list for Unit 2.
Analysis of Safety Implications The increase in fission product inventory may affect environmental qualification of equipment and may require revision to accident analyses results reported in the Final Safety Analysis Report and the' Environmental Report. Therefore, there is a possibility that if this problem were to have remained uncorrected, it could have adversely affected the safe operation of the plant. A detailed analysis of safety implications was not performed because the corrective action as outlined below will be taken.
Corrective Actions The effect of revised source term data will be evaluated and the following corrective actions will be taken:
1.
The revised integrated radiation doses for equipment qualification will be incorporsted into the appropriate specifications unless the values in a specification are more conservative.
2.
.The accident analyses results in the Final Safety Analysis Report and Environmental Report will be revised.
This corrective actions will be completed by April 30, 1984.