ML20133H365
| ML20133H365 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/01/1985 |
| From: | Tamlyn T COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| TKT-85-52, NUDOCS 8510170094 | |
| Download: ML20133H365 (2) | |
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@ Commonwealth Edison ouad Cities Nuctoar Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 TKT-85-52 October 1, 1985 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 experi-ments completed during the month of September, 1985, for Quad-Cities Station Units 1 and 2, DPR-29 and DPR-30.
A summary of the safety evaluation is being reported in complianca with 10 CFR 50.59.
Thirty-nine copies are provided for your use.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR P STATION T. K. Tamlyn Services Superintendent bb Enclosure cc:
J. Hojnarowski 8
8510170094 851001
,(i g PDR ADOCK 05000254 P
O Modification M-4-1-81-17 Description This modification was initiated to install additional supports on the control rod drive insert and withdrawal lines inside and outside the Drywell. These additional supports were required due to the results of a seismic review of the control rod drive lines performed by EDS Nuclear, Inc. From the results of the review, it was determined that the existing supports did not meet the FSAR criteria for support stresses; thus, additional supports were required.
Evaluatien No new systems or components were added by this modification. The existing hangers were modified to increase the hanger's loading capabilities; thus, increasing the reliability of the control rod drive insert and with-drawal lines. No new safety aspects were introduced by the installation of this modification.
Modification M-4-1-85-34 Description 10 CFR 50.49 " Environmental Qualification (EQ) of Electrical Equipment Important to Safety for Nuclear Power Plants" requires that certain equipment located in a " harsh" environment at the time of the Design Basis Accident for which that equipment is designed to mitigate, must be " qualified" to function in that accident environment. The operators on the two Core Spray Injection Valves had their motors replaced.
These replacement motors are without brakes as the original motors had.
Brakes cannot be qualified.
Evaluation The replacement items are one-for-one replacements, the function remains unchanged, and all the valve interfaces remain the same.
The level of safety will remain the same and could be seen as increased since the new motors meet the requirements of 10 CFR 50.49 and are considered Environmentally Qualified.
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