ML20214A170
| ML20214A170 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/29/1986 |
| From: | Robey R COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| RAR-86-36, NUDOCS 8611190276 | |
| Download: ML20214A170 (3) | |
Text
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Commonwealth Edison Quad Cit:es Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 RAR-86-36 October 29, 1986 Mr. Edson G. Case, Deputy Director Office 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 October, 1986, 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.
Thirty-nine copies are provided for your use.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION
(
f 4)%Gfear R. A. Robey Services Superintendent bb Enclosure cc:
J. Hojnarowski J. Leider/E. Budzichowski 8611190276 861029
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PDR ADOCK 05000254 00 R
PDR 0027H/0061Z
Modification M-4-1-81-24 Description This modification provides a more extensive suppression pool tempera-ture monitoring system from which an average " bulk" temperature is derived.
This was accomplished by installing 16 thermocouples symmetrically around the suppression chamber, at the normal center of gravity of the water mass.
These 16 thermocouples are divided into 2 channels, 8 thermocouples apiece.
These signals are sent to a strip chart recorder in the main Control Room along with the average temperature value for that channel.
Each channel has an individucl high temperature (200*F) alarm and a bulk high temperature (110*F) alarm associated with it.
Evaluation By installing this modification more reliable local and average sup-pression pool temperature values can be obtained.
Failure of this equipment would create the same conditions as existed prior to this modification.
The margin of safety is increased by installing this modification.
e SPECIAL TEST l-96 Special Test 1-96 was completed on October 9, 1986. The purpose of 1-96 is to verify the accuracy of a minimum performance test pump curve prepared by Nutech.
Safety Evaluation 1
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 the test is based on QOS 1000-1, Quarterly LPCI Flow Rate Test, and all procedural steps, precautions, and limitations remain the same.
The system will not be placed in any unsafe configurations.
The test will be run concurrently with the Quarterly LPCI Flow Rate Test, QOS 1000-1.
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 the system configuration and operation is the same as for the normal LPCl three pump operation. Therefore, no new or different safety hazards are created.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because the Nutech pump curve is designed around Technical Specification, as discussed under 3.5.A.-
4/5 and 4.5.4/5, and gives a minimum pump performance boundary.
This test is to verify that all combinations of pumps will deliver sufficient pressures over a wide flow range within the specified boundary.
I