ML18046B419

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Forwards Listing of Changes,Tests & Experiments Completed During Oct 1981.Summary of Safety Evaluation Also Encl
ML18046B419
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 11/02/1981
From: Kalivianakis N
COMMONWEALTH EDISON CO.
To: Case E
Office of Nuclear Reactor Regulation
References
NJK-81-415, NUDOCS 8111160097
Download: ML18046B419 (2)


Text

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e Commonwealth9ison Quad Cities Nuclear Power Station 2271 O 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 NJK-81-415 November 2, 1981 Mr. Edson G. Case, Deputy Director Off ice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20S55

Dear Mr. Case:

Enclosed please find a listing of those changes, tests, and experi-ments completed during the month of October, 1981, for Quad-Cities Station Units 1 and 2, DPR-29 and DPR-30. A summary of the safety evaluation is being reported in compliance with 10 CFR 50.59.

Thirty-nine copies are provided for your use.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-~I~~~~JOWER s:~)J.ON

//~~

N. J. Ka~~is Station Superintendent bb Enclosure cc: T. J. Rausch

( R~aRi 1160097

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011 102 ADOCK 05000254 "

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SPECIAL TEST 1-56 Special Test 1-56 was completed on October 16, 1981.

This test was performed to evaluate the temperature rise in the Fuel Pools when Reactor Building Closed Cooling Water is isolated from the Fuel Pool Cooling Heat Exchangers.

SUMMARY

OF THE SAFETY EVALUATION The probability of an occurrence or the consequences of an accident or malfunction previously evaluated in the FSAR was not increased, because the probability of a dropped fuel bundle was not increased.

The increase in Fuel Pool temperature allowed was small, and did not decrease the ability of the Fuel Pool Cooling System to maintain the Fuel Pools at the proper temperature.

The probability of an accident or malfunction of a different type than evaluated in the FSAR was not created, because cooling water to the Fuel Pool Heat Exchangers was available for service if needed to restore normal Fuel Pool Cooling.

The margin of safety as defined in the basis for any Technical Specificaiion was not reduced because isolation of cooling water to the Heat Exchanger has no effect on Fuel Pool level, nor the ability to control Fuel Pool level. The small temperature rise of the Fuel Pool has no effect on Keff of the Fuel Pool. Therefore, the margin of safety was not reduced.