ML20211F392
| ML20211F392 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/11/1987 |
| From: | Robey R COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| RAR-87-10, NUDOCS 8702250078 | |
| Download: ML20211F392 (4) | |
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O Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 RAR-87-10 February 11, 1987 Mr. Edson G. Case, Deputy Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Case:
Enclosed please find a listing of those changes, tests, and experiments completed during the month of January, 1987, 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 NUCLEAR POWER STATION k-R.A.Robeyl Services Superintendent bb Enclosure cc I. Johnson J. Leider / E. Budzichowski G702250078 870211 PDR ADOCK 05000254 R
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SPECIAL TEST 2-51 Special Test 2-51 was completed June 9, 1985. The purpose of this test was to provide added indication of the proper connection of the Traversing incore Probe (TlP) tubes by using the TIP System in conjunction with Special Control Rod Maneuvers.
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 increased because all rod movements will be performed using Station approved procedures under the direction of a Qualified Nuclear Engineer.
Power will be maintained at approximately 50% of rated thermal power, thus there are no additional safety implications from a rod drop accident.
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because the rod maneuvers will be performed at normal operating conditions but at reduced power. All rod movements will begin with insertions deeper into the core from their target pattern position. Response will be noted on the adjacent TIP and the control rods returned to their initial position before proceeding to the next step.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because all rod movements will be performed using approved operating procedures and within Technical Specifications. Thus, no Technical Specification safety margins are reduced.
c SPECIAL TEST 2-55 Special Test 2-55 was completed on April 21, 1986. The purpose of this test was to perform General Electric Field Disposition Instruction RB6R on one Log Radiation Monitor to evaluate new firmware changes for process signal smoothing and self-testing.
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 increased because the overal1Ffunction of the Log Radiation Monitor is not changed. Any faults in the system will result in either an up-scale or downscale trip that will be immediately apparent. Also, this test will be done on a single LRM unit, therefore, the remaining three units will be unchanged. The functional response timing test performed prior to placing the LRM in service will assure the criteria specified in the FSAR is met by the monitor.
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because the system function is not changed.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because the firmware filtering to reduce process signal variations will result in a somewhat higher reading due to the higher discrimination of the downward going noise signals.
The response time to increasing radiation levels will remain the same. The self-test firmware is not part of the normal signal processing circuit.
SPECIAL TEST 2-65 Special Test 2-65 was completed October 12, 1986.
The purpose of this test was to verify that temperature sensor locations, as specified in QTS 150-S17, produce an indication representative of the mean temperature of their respective subvolume.
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 increased because this test will serve only to demonstrate that the specified instrument locations provide representative indications from the temperature detectors used exclusively for the Integrated Primary Containment Leak Rate Test (IPCLRT). All instruments installed for this purpose will be removed prior to unit startup.
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because all testing will be done in a shutdown mode.
No ties into present systems are required. Therefore, this test has no affect upon systems needed for Reactor safety.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because no systems in the Techneial Specifications are affected by this test.
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