ML20236P139
| ML20236P139 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/04/1987 |
| From: | Robey R COMMONWEALTH EDISON CO. |
| To: | Lieberman J NRC |
| References | |
| RAR-87-52, NUDOCS 8711170166 | |
| Download: ML20236P139 (2) | |
Text
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..p 6 22710 206 Avenue North Commonwealth Edison
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ouad Cities Nuclear Power Station 1
Cordova, Illinals 61242 Telephone 309/654-2241 i
f' RAR-87-52 November 4, 1987 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attn:
J. Lieberman M/S MNBB-4100 Enclosed please find a listing of those changes,' tests, and experiments completed during the month of October, 1987, 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.
Respectfully, COMMONWEALTH EDIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION i
RAPAw R. A Robey
Services. Superintendent h
vk Enclosure cc:
I. Johnson
.i T. Watts /J. Gali!gan
/[
8711170166 871104 PDR ADOCK 05000254 0027H/0061Z R
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SPECIAL TEST 2-78 i
Special test 2-78 was completed on October 21, 1987. The purpose of this test was to simulate a Reactor Low Water Level initiation of the High Pressure Coolant Injection (HPCI) system using the manual initial pushbuttons in order to verify that HPCI valves and equipment actuations perform as designed.
Safety Evaluation 1.
The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not increased because this test was performed with the reactor in a cold shutdown l
and.therefore could not cause any actual water injection into the l
reactor vessel.
Actuations of valves and turbine auxiliary equipment do not affect plant operation, therefore this test does not increase l
the probability of occurrence, or consequences of an accident.
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'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 this test is similar to the HPCI logic test (QMS 700-4) which is performed every refueling outage and has been previously evaluated.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because this test was performed during a cold shutdown condition when the HPCI system does not affect the margin of safety.
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