ML20203D232
| ML20203D232 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/07/1986 |
| From: | Tamlyn T COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| TKT-86-32, NUDOCS 8604220064 | |
| Download: ML20203D232 (3) | |
Text
f sa-xY 4-ur e Commonwealth Edison Ouad Cities Nuclear Power Station 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654-2241 TKT-86-32 April 7, 1986 Mr. Edson G. Case, Deputy Director Office of Nuclear Reactor Regulation l
U. S. Nuclear Regulatory Commission l
Washington, DC 20555
Dear Mr. Case:
Enclosed please find a listing of those changes, tests, and experiments completed during the month of March, 1986, for Quad-Cities Station Units 1 and 2, DPR-29 and DPR-30.
A summary of the safety evaluation is being repot, 1 in compliance with 10 CFR 50.59.
Thirty-nine copies are provided for your use.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEA OW R STATION j
y rr T. K. Tamlyn Services Superintendent bb Enclosure cc J. Wojnarowski
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SPECIAL TEST l-87 On March 21, 1986, Special Test 1-87 was completed. This test performed a Unit One Drywell temperature profile to verify that the temperature sensor locations, as specified by the Integrated Primary Containment Leak Rate Test procedures (QTS 150-S17), represent the mean representative temperature for the various subvolumes.
SAFETY EVALUATION l
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 will verify instrument location for the Integrated Primary Containment Leak Rate Test. All instruments will be removed prior to startup of the unit.
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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 are not created because all testing will be done in a shutdown mode.
No ties into the present system are required.
Therefore, this test has no affect upon systems needed for Reactor safety.
3.
The margin of safety as defined in the basis for any Technical Specifications will not be reduced because systems in Technical Specifications are not affected by this test.
SPECIAL TEST l-88 On March 21, 1986, Special Test 1-88 was completed. This test performed a Unit One Drywell humidity profile to verify that the dewcell sensor locations, as specified by the Integrated Primary Containment Leak Rate Test procedures (QTS 150-S17), are representative of the mean dewpoint temperature for the various subvolumes.
t 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 no operating systems are affected by this test.
Only a humidity profile of the Drywell will be obtained.
1 O
SPECIAL TEST l-88 (cont.)
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report are not created because no operating systems are affected and no addition'l operating equipment is utilized.
3.
The margin of safety as defined in tha basis for any Technical Specifications will not be reduced because the humidity profile of the Drywell will be obtained using a wet and dry bulb which does not affect safety related equipment.