ML20206L731
| ML20206L731 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/01/1987 |
| From: | Robey R COMMONWEALTH EDISON CO. |
| To: | Vollmer R Office of Nuclear Reactor Regulation |
| References | |
| RAR-87-16, NUDOCS 8704170216 | |
| Download: ML20206L731 (3) | |
Text
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Commonwealth Edison ouad Cities Nuclear Power Station 22710 206 Avenue North Cordova. Illinois 61242 Telephone 309/654-2241 RAR-87-16 April 1, 1987 Hi. R. H. Vollmer, Deputy Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commtssion Washington, D. C.
20555
Dear Mr. Vollmer:
Enclosed please find a listing of those changes, tests, and experiments completed during the month of March, 1987, 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, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION
$.b-Q R. A. Robey Services Superintendent bb Enclosure cc:
- 1. Johnson J. Leider/E, Budzichowski 0704170216 070401 PDR ADOCK 05000254 P
PDR q
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Modifications M-4-1(2)-85-22 & M-4-1/2-85-6 IIFA Coil Spool Replacement Doncription Failures of General Electric type liFA Relays have been reported industry-wide since 1973. The principle cause of the failures has been cracking of the nylon or lexan bobbins of the magnetic coil assemblies (detailed in NRC I.E.
Bulletin 84-02). The Station committed to the NRC to replace the coil assemblies on all Safety Related HFA Relays with a Tefzel bobbin (G.E.
Century Series Coils). After the coils were replaced, relays were bench tested for contact wipe and gap, proper mating of contacts, pick-up voltages, and smoothness of motion.
Once the relays were returned to their locations, de-energized and energized tests were done to ensure correct contact con-figuration. No logic circuitry was altered by the coil replacement.
Evaluation The new coils with a Tefzel bobbin are more resistant to cracking and have made the relays more reliable.
The margin of safety, therefore, has increased due to the replacement.
I o
Modification M-4-1/2-85-12 Description This modification consists of removing two 7 inch long sections of the support plate along the west side of the fuel pool transfer canal.
The support plates run the entire length of the transfer canal and serve as the supporting members for the transfer canal cover plating.
The purpose of this modification is to provide space for the in-sta11ation of an LPRM cutting tool. This LPRM cutting tool will allow the fission chambers in the LPRM to be separated from the string. The remaining parts of the assembly then can be disposed of as low level or non-contaminated materials.
The removal of the support plate sections will be done using approved cutting and welding practices.
t Evaluation This modification dealo only with the removal of two sections of the fuel transfer canal cover support plate. The cover plate is used only as a personnel convenience and does not affect the normal operation or design of any plant facilities. The cover support plate is not analyzed in the Final Safety Analysis Report and is not defined in the basis of any Technical Specification. The structural changes in the plant due to this modification are insignificant; the capability of the cover support plate to perform its intended function is essentially unchanged.
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