ML20203D048
| ML20203D048 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/09/1986 |
| From: | Robey R COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| RAR-86-19, NUDOCS 8607210128 | |
| Download: ML20203D048 (3) | |
Text
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Commonwealth Edison CJad Cities Nuclear Power Station 22710 206 Avenue Nonh Cordova, Illinois 61242 Telephone 309/654-2241 RAR-86-19 July 9, 1986 Mr. Edson G. Case, Deputy Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Case:
Enclosed please find a listing of those changes, tests, and experiments completed during the month of June, 1986, 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 EDISON COMPANY QUAD-ClTIES NUCLEAR POWER STATION b-R. A. Robey Services Superintendent bb Enclosure cc J. Wojnarowski C)[
J. Leider/E. Budzichowski gp-265 0
8607210128 860709 (0
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,o SPECIAL TEST 2-57 On May 29, 1986, Special Test 2-57 was completed. The purpose of this test is to provide additional indication of the proper connection of LPRM cables by verifying proper LPRM response to control rod motion.
Safety Evaluation i
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 o
not increased because all control rod maneuvers will be performed under the direction of a Qualified Nuclear Engineer, using approved Station procedures. Therefore, there are no additional safety consequences resulting from this test.
2.
The possibility for an accident or malfunction of a different l
type than any previously evaluated in the Final Safety Analysis Report are not created because the control rod maneuvers will cause a rod to be inserted deeper into the core than its original position. Response will be measured on the adjacent LPRM string, and the control rod will be returned to its initial position before proceeding to the next stop.
3.
The margin of safety, as defined in the basis for any Technical Specification, is not reduced because all control rod maneuvers will be performed using approved Station procedures and will comply with the Technical Specifications.
4
o o
SPECIAL TEST 2-59 On June 27, 1986, Special Test 2-59 was completed. The purpose of this test was to monitor the outside Drywell stainless steel penetration welds for temperature conditions on the RHR and Core Spray pipe.
Safety Evaluation 1.
The probability of an occurrence or the consequence of an
(
accident, or calfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report, is not increased because monitoring temperatures of the stainless steel welds will not change the operating status of the unit or any system. The temperature test condition will be performed under normal operating status and normal safety system avail-ability.
2.
The possibility of an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because only normal temperature monitoring of the outside Drywell stainless steel penetration welds are being monitored at normal operating status. No systems will be affected while monitoring the temperatures of the welds.
3.
The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the monitoring of the temperature of the welds are done during the normal operation of the system and has no effect on the systems; therefore, the margin of safety is not reduced.