ML20028D049
| ML20028D049 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/03/1983 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| NJK-83-2, NUDOCS 8301140442 | |
| Download: ML20028D049 (4) | |
Text
r Commonwealth Edison Quad Cities Nuclear Power St: tion 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241
{dSo 4dl NJK-83-2 January 3, 1983 Mr. Edson G. Case, Deputy Director Of fice 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 December,1982, 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.
Very truly yours, COMMONWEALTil EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION f
/
N. J. Kalivianakis Station Superintendent bb Enclosu re cc:
T. J. Rausch 8301140442 830103 DR ADOCK 05000254
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.M-4-1-80-31 Drywell Cooler, RBCCW Pump Trip Logic Change
- Description In December,1980, a Unit' Two ~ scram and Group I isolation occurred. The electromatic relief valves were used to control Reactor pressure. As a i
result, the.Drywell exceeded 2 psig due to the heating of the air from the relief valve discharge -lines. 'The high pressure initiated the Core Spray System and tripped the Drywell Coolers and RBCCW Pumps; thus, eliminating any method of cooling the Drywell and reducing the pressure.
This modification eliminates the 2 psig trip of the coolers and pumps.
The coolers and RBCCW Pumps'will only trip on a loss of. off-site power, via Bus 13 and Bus 14 undervoltage relays.
The Drywell Coolers.are designed to operate up to approximately 5 psig.- The coolers should.be manually-tripped if pressure rapidly exceeds 5-psig to prevent damage' to the Drywell ' Coolers.
Evaluation The 2 psig trip of the Drywell Coolers and RBCCW Pumps was originally installed to prevent the blower motors from overheating due to the' higher air density. Their operation will have no affect on the capability of the Core Spray System. This modification will not affect the existing automatic load shed features of the circuitry that are initiated by a loss of of f-si te power.
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. CRD Thermal! Sleeve Removal M-4-1-79-5 Description JThe control-rod drive return' line nozzle thermal sleeve was removed to j provide access for a dye penetrant test _ of the nozzle inner radius? and.
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bore, and of the vessel wall below the nozzle. This inspection is In.
accordance with NUREG-0312.
Evaluation The thermal. sleeve-provided no structural strength.' -The CRD System is operated with the. return line isolated. The operating' condition is less severe than the analyzed condition with the thermal sleeve and cold returni flow; the original stress reports are still valid.
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.M-4-1-78-33 ESS UPS Description The Unit One ESS HG Set has been removed and replaced by an uninterruptible power supply (UPS).
It has a rating of 35 KVA, and consists of a static inverter, static switch, rectifier and regulator.
Evaluation The reliability of the power supply is increased providing a more reliable ESS Bus. The new system is qualified as Class IE equipment.
It will increase the amount of protection against abnormal voltage and frequency.
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HPCI-Backup Control Power Feed Description-Cables 13926 and 23926 were rerouted 'to ensure the separation of. cable criteria. Is met.. Cables 13926 and 23926 provide--redundant control power to the Unit I and Unit 2 HPCI Systems from 125_VDC distrib' tion ' panels '
u 1A and 2A.
. Evaluation The reliability of the HPCI-ADS system.is. increased and will. operate as posutlated in the FSAR. Segregated backup power is provided for essential HPCI-ADS equipment.
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