ML20064N999
| ML20064N999 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/01/1982 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| NJK-82-381, NUDOCS 8209130067 | |
| Download: ML20064N999 (2) | |
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Quad Citizs Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 NJK-82-381 September 1, 1982 Mr. Edson G.
Case, Deputy Director Of fice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Case:
Enclosed please find a listing of those changes, tests, and experiments completed during the month of August, 1982, for Quad-Cities Station Units I and 2, DPR-29 and DPR-30.
A summary of the safety evaluation is being reported in compliance with 10 CFR 50.59 Thi rty-nine copies are provided for your use.
Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION
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,/ 7 N. J. Kalivianakis Station Superintendent bb Enclosure cc T. J. Rausch ol c
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SPECIAL TESTS On July 13, 1982, Special Test 1-57 was performed.
This test involved placing a sample of boraflex material in an empty cell of the spent fuel pool and collecting gas samples to determine if any gas products are given off when the sample is irradiated.
Bora flex is the absorber material used in the high density fuel racks proposed for Quad-Cities Station.
Summary of Safety Evaluation 1.
The possibility of an occurrence or the consequence of an accident, or mal function of equipnent important to safety as previously evaluated in the Final Safety Analysis Report is not increased because any novement of fuel necessitated by this test will be within the confines of the spent fuel pool and will be according to reviewed and approved procedures.
Any gases that are collected will be handled in compliance with the appropriate Rad-Protection / Chemistry Procedures currently in ef fect.
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because no activities in conjunction with this test will create accident potentials greater than the dropped fuel buadle accident considered in the FSAR.
3 The margin of safety, as defined in the basis for any Technical Specification, is not reduced because no activities in conjunction with this test would cause releases greater than those assumed for the Technical Specification basis.
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