ML20154N560
| ML20154N560 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/03/1986 |
| From: | Tomlyn T COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| TKT-86-25, NUDOCS 8603170352 | |
| Download: ML20154N560 (3) | |
Text
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f Commonwealth Edison ound Cities Nuclear Power Station 22710 206 Avenue North Corcova, ll!!nois 61242 Telephone 309/654-2241 TKT-86-25 March 3, 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 February, 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-CITIES NUCLEA HER STATION T. K. Tamlyn Services Superintendent bb Enclosure cc:
J. Wojnarowski j!
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8603170352 060303 DR ADOCK 050 4
I SPECIAL TEST 1-81 On February 14, 1986, Special Test 1-81 was completed. This was the completion of the End of Cycle 8 Testing Program for barrier fuel and the segmented barrier test program.
It prepared two barrier assemblies for a fifth cycle of irradiation.
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 incrcased because all fuel handling will be performed within the confines of the spent fuel storage pool using standard, reviewed, and approved fuel handling procedures. Generic procedures will also be used by General Electric personnel that have been reviewed under the Special Test review and are found acceptable.
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 fuel maneuvers will be standard operations, such as bundle transfers between racks, dechanneling, and channeling fuel are within the assumption of the FSAR evaluation.
The other activities do not create accident potentials greater than the dropped fuel bundle accident considered in the FSAR.
3.
The margin of safety as defined in the basis for any Technical Specification will not be reduced because no activities during this test would cause release rates greater than those assumed for the Technical Specification basis.
l
9 O
Modification M-4-1-85-37 Description This modification was to install a new RHR pump motor for the IB RHR Pump. This was initiated due to the inoperability of a badly damaged IB RHR Pump motor and no exact motor replacement could be found.
A similar environmentally qualified motor was obtained from Northern States Power, Monticello Station, and was adapted to the Station'a motor stand and coupling pieces.
Evaluation The motor is identical in horsepower, KV rating, and RPM. Thus, it met the basic requirements for the IB RHR Pump. All flows remained the same and met the Technical Specification requirements. The motor met or exceeded all of the environmental qualification requirements.
No safety concerno have been created due to this modification.