ML20234A834
| ML20234A834 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/10/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20234A836 | List: |
| References | |
| NUDOCS 8709180146 | |
| Download: ML20234A834 (1) | |
Text
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PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEM The OPERABILITY of the control room emergency habitability system ensures that the control room will remain habitable for i
operations personnel during and following all credible accident conditions.
The ambient air temperature is controlled to prevent exceeding the allowable equipment qualification temperature for the equipment and instrumentation in the control room.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5
rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A", 10 CFR 50.
3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM (SLCRS)
The OPERABILITY of the SLCRS provides for the filtering of postulated radioactive effluents resulting from a Fuel Handling Accident (FHA) and from leakage of LOSS OF COOLANT ACCIDENT (LOCA) activity from systems outside of the Reactor Containment building, such as Engin-eered. Safeguards -Features (ESF) equipment, prior to their release to the environment.
This system also collects potential leakage of LOCA activity from the Reactor Containment building penetrations into the contiguous areas ventilated by the SLCRS except for the Main Steam-Valve Room and Emergency Air Lock.
The operation of this system was assumed in calculating the postulated offsite doses in the analysis for a
FHA.. System operation was also assumed in that portion of the Design Basis Accident (DBA) LOCA analysis which addressed ESF leakage following the. LOCA, however, no credit for SLCRS operation was taken in the DBA LOCA analysis for collection and filtration of Reactor l
containment building' leakage even though an unquantifiable amount of l
l contiguous area penetration leakage would in fact be collected and filtered.
Based on the results of the analyses, the SLCRS must be OPERABLE to ensure that ESF leakage following the postulated DBA LOCA and leakage resulting from a FHA will not exceed 10 CFR 100 limits.
3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allow-able limits in the event of ingestion or inhalation of the source material.
The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39'(c) limits for plutonium.
Leakage of sources excluded from the l
requirements of this specification represent less than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.
3/4.7.10 and 3/4.7.11 RESIDUAL HEAT REMOVAL SYSTEM (RHR)
Deleted BEAVER VALLEY - UNIT 1 B 3/4 7-5 Amendment No.719,112 Correction letter dated 98/87 8709180146 870910 PDR ADOCK 05000334 p
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