ML20134C479
| ML20134C479 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/09/1985 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8508160325 | |
| Download: ML20134C479 (2) | |
Text
,
g GPU Nuclear Corporation
- UOgMf 100 interpace Parkway Parsippany, New Jersey 07054-1149 (201)263-6500 TELEX 136-482 Writer's Direct Dial Number:
August 9, 1985 Director, Division of Licensing Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Dear SJ
/
ubject:
Oyster Creek Nuclear Generating Station
/
Docket No. 50-219
/
Generic Letter 83-28 Pursuant to our letter of November 20, 1984, please find attached our response to Item 4.5.1 of Generic Letter 83-28.
Item 4.5.1 addresses system functional testing of the reactor trip system.
Very truly yours, Jhm 1 M
Vice President and Director Oyster Creek 1r/1985f cc: Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.
19406 J
NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N. J.
08731 8508160325 050809 t
DR ADOCK 050 9
I g Il o l GPU Nuclear Corpoiation is a subsidiary of General Public Utilities Corporation
ATTACHMENT Oyster Creek Nuclear Generating Station Generic Letter 83-28 Item 4.5.1 4.5 Reactor Trip System Reliability (System Functional Testing)
Position On-line functional testing of the reactor trip system, including independent testing of the diverse trip features, shall be performed on all plants.
1.
The diverse trip features to be tested include the breaker undervoltage and shunt trip features on Westinghouse, B&W (see Action 4.3 above) and CE plants; the circuitry used for power interruption with silicon controlled rectifiers on B&W plants (see Action 4.4 above); and the scram pilot valve and backup scram valves (including all initiating circuitry) on G.E.
plants.
Response
'On-line functional testing of the scram pilot valves and associated initiating circuitry is conducted at the Oyster Creek Nuclear Generating Station.
During normal system operation, each of the two Reactor Protection System (RPS) bases energize one of the two three way solenoid operated diaphragm scram inlet and outlet valves.
Routine surveillance testing of the RPS sensors dictates placing the RPS in a half scram mode and results in actuation of the scram pilot valves.
In addition, rod insertion time surveillance testing, in which individual rods are scrammed manually and timed, provides direct verification of the operability of the associated pilot scram valves.
Surveillance testing requirements related to the scram pilot solenoid valves assure that the probability of undetected failure of these independently acting solenoid valves is small.
The instrument air header to all scram pilot valves has two backup scram pilot valves. Like scram pilot solenoids, backup scram solenoids are actuated by the RPS. Deenergization of the RPS actuation relays, via RPS surveillance testing, would result in deenergizing the backup scram solenoid coil and opening the valve. Functional testing of backup scram valves would require a plant scram, as a result such testing is not performed. The backup scram valves are non-safety related and are intended only to enhance the reliability of the safety related trip system. No explicit credit is taken for these valves in plant safety analysis.