ML20092P333
| ML20092P333 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 02/01/1984 |
| From: | STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | |
| Shared Package | |
| ML20092P332 | List: |
| References | |
| NUDOCS 8407060176 | |
| Download: ML20092P333 (1) | |
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.sr the application of credible fcult voltages on the ' isolated output portions of W circuit (nonprotective side) will not affect the protection system circuits. The signals obtained from the isolation amplifiers are not returned to the protective system cabinets.
The reactor trip system is the standard Westinghouse system used on plants H
previously reviewed and approved by the staff, such as the W. B. McGuire Station (Docket No. 50-369).
-l 7.2.2 Resolution of Issues 7.2.2.1 Sensor Time Response Testing l
The applicant intends to use a computer-based system which utilizes process noise with the plant at power for sensor time response testing. Although i
staff review during meetings with the applicant indicates that the method is satisfactory, there is only limited experience to date with this method on operating plants.
i The applicant will be required to submit a summary of the results from and
,i experience with this method of time response testing within three months j
following the testing done at the time of initial plant startup. A similar i
summary will be required within 3 months following the testing done at each of the first three plant refuelings.
Each summary will contain conclusions on the adequacy of the test method and the adequacy of the sensor time response values measured. This will allow a confirmatory review of the adequacy of the time respor.se testing method to be obtained and applies only to the first of the SNUPPS units going into operation (either Callaway Unit 1 or Wolf Creek s
Generating Staion Unit 1).
The license will be conditioned to require the submittal of the above infor-mation on response time testing and evaluation for the first $NUPPS unit to go into operation.
7.2.2.2 Protection System Temperature Detector Flow Bypass Loops i
The reactor coolant system hot-and cold-les resist'ance temperature detectors used for reactor protection are located in reactor coolant bypass loops. A bypass loop from upstream of the steam generator to downstream of the steam generator is used for the hot-leg resistance-temperature detector, and a hvoass 1000 from downstream of the reactor coolant pump to upstream of the pump is used for the cold-leg resistance-tamperature detector. The flowrate affects the overall time response of the temperature signals provided for reactor protection, and thus should be monitored at. appropriate intervals.
The staff will require that the magnitude of the RTD bypass loop flowrate be l
verified to be within required limits at each refueli This requirement will be incorporated in the plant Technical Specificat ons.
7.2.2.3 Design Criteria for Circuits and Equipment used To Trip the Turbine Following a Reactor Trip It was not clear from the drawings provided and the description of-the turbine trip circuits in the $NUPPS FSAR if the circuits used.to trip the tertine i
following a reactor trip meet the criteria applicable to equipment perfoming l
7-7 l-l 8407060176 840201 PDR ADOCK 05000 A
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