ML20138Q916
| ML20138Q916 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 11/01/1985 |
| From: | Tamlyn T COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| TKT-85-58, NUDOCS 8511180329 | |
| Download: ML20138Q916 (3) | |
Text
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Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 TKT-85-58 November 1, 1985 Mr. Edson G. Case, Deputy Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Cotamission Washington, D. C.
20555
Dear Mr. Case:
Enclosed please find a listing of those changes, tests, and experiments completed during the month of October, 1985, for Quad-Cities Station t' nits 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 NUCLEAR POWER STATION
/ p Y11 s
T. K. Tamlyn Services Superintendent bb Enclosure
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cc:
J. Wojnarowski
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8511180329 B51101 PDR ADOCK 05000254 R
PDR l1
Modification M-4-1-84-10 Description This modification involved installing a dual train system of three RTD's each to sense a leak in the piping of the Reactor Water Cleanup System.
It was installed as part of the Electrical Equipment Qualifica-tion Program (10 CFR 50.49) Bulletin 79-OlB to detect a leak so an Operator may take steps to isolate before an area becomes a harsh environment.
Evaluation This modification was non-safety related.
It provides only an alarm indication and is designed to operate in a harsh environment.
This system, therefore, is a reliable source of information and will not mislead the Operator.
Modification M-4-1-82-16 Description The Pressure Suppression Chamber Wide Range Level Monitoring System was inrtalled as a result of AIR 4-82-6 to provide the main Control Room with level indication outside the normal range of operation.
The system is comprised of two independent channels and uses differential pressure, between the top and the bottom of the Pressure Suppression Chamber, to sense the level.
Each channel has a gauge readout on the 901-3 Panel and a strip chart recorder on the 901-2 Panel. Pressure indication is provided alongside level readout on all four indicators.
Evaluation The existing Pressure Suppression Chamber level monitoring system will remain intact and will be used during normal operation.
In the event that Suppression Chamber level rises / falls outside the range of the existing level monitoring system, the wide range level monitoring system will provide the necessary information.
Since this system only supplies additional information, the margin of safety is increased.
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Modification M-4-2-84-30 Description On October 27, 1983, the core Spray Inlet Bellows X-16B was Local Leak Rete Tested and found to leak 19.0 SCFH. This bellows van a double-ply, testable bellows. During the End of Cycle 6 Refueling Outage, the bellows was replaced with a single-ply bellows (reference Modification M-4-2-84-1).
The single-ply bellows was tested during the Integrated Leak Rate Test.
In order to make the bellows testable using Local Leak Rate Test methcds, a second bellows will be installed outside the primary bellows to form a test boundary. The second bellows was installed during the End of Cycle 7 Refueling Outage.
Evaluation This second bellows merely makes the inner bellows testable using Local Leak Rate Test techniques. The inner bellows is the containment boundary and will not be altered.
Modification M-4-2-85-27 Description This modification was initiated to replace the existing Unit Two High Pressure Coolant Injection (HPCI) Steam Exhaust Check Valve. This valve was replaced due to excessive leakage observed during a Local Leak Rate Test (LLRT). The new valve is nearly an exact replacement for this valve. The difference (and reason for this modification) being a change of material used in the spring bearing. That material was changed to stainless steel.
Evaluation The replacement valve is of equal or better construction and materials when compared to the existing valve.
The reliability of the HPCI Steam Exhaust Check Valve will not be affected by this modification.
The basic design of the valve and system remain unchanged since only a single component has had a change of materials.