ML20210E874
| ML20210E874 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/30/1987 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20210E800 | List: |
| References | |
| NUDOCS 8702100387 | |
| Download: ML20210E874 (1) | |
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'S Th$ purpose of an engineering evaluation is to determine if the components protected by the snubber were adversely affected by the inoperability of the snubber. This ensures that the protected component remains capable of meeting the designed service. A documented visual inspection will usually be sufficient to determine system operability.
B:cause snubber protection is required only during low probability events, a p:riod of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements.
Secondary containment (5) is designed to minimize any ground level release of radioactive materials which might result from a serious accident. The reactor building provides secondary containment during reactor operation when the drywell is sealed and in service and provides primary containment when the reactor is shutdown and the drywell is open, as during refueling.
Because the s:condary containment is an integral part of the overall containment system, it is required at all times that primary containment is required. Moreover, secondary containment is required during fuel handling operations and whenever work is being performed on the reactor or its connected systems in the reactor building since their operation could result in inadvertent release of radiot.ctive material. The Trunnion Room as designed, is part of the secondary containment boundary. However, momentary access to the Trunnion Room during periods when secondary containment is required is permitted for inspection and maintenance activities without incurring a loss of secondary containment integrity.
When secondary containment is not maintained, the additional restrictions on operation and maintenance give assurance that the probability of inadvertent releases of radioactive material will be minimized. Maintenance will not be performed on systems which connect to the reactor vessel lower than the top of the active fuel unless the system is isolated by at least one locked closed isolation valve.
The standby gas treatment system (6) filters and exhausts the reactor building atmosphere to the stack during secondary containment isolation conditions, with a minimum release of radioactive materials from the reactor building to the environs.
Two separate filter trains are provided each having 100% capacity.(6)
If one filter train becomes inoperable, there is no immediate threat to secondary containment and reactor operation may continue while repairs are being made.
Since the test interval for this system is one month (Specification 4.5), the time out-of-service allowance of 7 days is based on considerations presented in the Bases in Specification 3.2 for a one-out-of-two system.
References:
(1) FDSAR, Volume I, Section V-1 (2) FDSAR, Volume I, Section V-1.4.1 (3) FDSAR, Volume I, Section V-1.7 (4) Licensing Application, Amendment 11, Question III-25 (5)
FDSAR, Volume I, Section V-2 (6) FDSAR, Volume I, Section V-2.4 (7) Licensing Application, Amendment 42 (8) Licensing Applicaticn, Amendment 32, Question 3 (9) Robbins, C. H., " Tests on a Full Scale 1/48 Segment of the Humboldt Bay Pressure Suppression Containment,"
GEAP-3596, November 17, 1960.
0YSTER CREEK 3.5-10
-15739 8702100387 870130 PDR ADOCK 05000219 P