ML20037A466
| ML20037A466 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/29/1974 |
| From: | Grimes B US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20037A467 | List: |
| References | |
| NUDOCS 8002010279 | |
| Download: ML20037A466 (1) | |
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V. A. Moore, Assistant Director for Light Water Reactor, Group 2, L H. R. Denton, 'Assiotadt'Difesti6ir for Sit'e'S5fety,'L"
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TECGICAL SPECIFICATIO!;S - OCONEE NUCLEAR STATION UNITS 2 AND 3 Enclosed is the proposed text for the sections of the Technida1 Specifi-cations for the Oconce Uncicar Station Units 2 and 3 on prinary and secondary coolant activities reficcting our current position on this topic.
The enclosed Technical Specifications linit the prir'a_ry coolant activity to 2.0 pCi/gren due to I-131 equivalent, and to 200/E pC1/grau due to all nuclides excluding tritiun with half-lives of rnore than 30 ninutes.
The I-131 equivalent concentration in the accendary coolant is linited to 0.05 pC1/ gram.
The prir.ary coolant iodine concentration linit has been reduced by a factor of three to account for the effects ofl.a possible iodine spiking phenonenon as a result of the accident. - This factor will be reduced or eliminated once sufficient' data have been accumtlathd to denonstrate that this reduction is not required. A X/Q value of 2.3 x 10~4 sec/m3 and a primary to secondary leakage of 1 gpm were used in these calculations.
This work was perforced by H. M. Fontecilla of the Accident Analysis Ernnch.
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Brian Crines,, Chief Accident Analysis Branch Directorate of Licensing
Enclosure:
As Stated cc: v/o enclosure OO A. Giarbusco 9
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