ML19220C442
| ML19220C442 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 01/27/1969 |
| From: | Howe P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7905010580 | |
| Download: ML19220C442 (1) | |
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UNITE STATES j.
f4 T','3 ATOMIC ENERGY COMMISSION 1
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D January 27, 1969 y'
s R. S. 3cyd, Assistant Director f or Reactor Proj ects, D?J_
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S. Levine, Assis tant Director for Peactor Technology, C?1 EXCLUSICM RADIUS 00SE CALCULATIONS FOR OYSTER CRIEK ?LAST C'i!T 50. 2 Our ec=orandu: to you dated Nove=ber 29, 1908, regarding exclusion radius dose calculations for the preposed Oyster Creek Un'.: No. 2 noted that the crocesed containment spray system would not provide sufficient iodine renoval folicving the less of coolant accident to teet 10 CFR 100 guidelines.
3ased en standard staff meteorology, the change in site location to Three Mile Island will not alter the basic conclusion reached in paragraphs one and two of our Nove=ber 29, =c=orandu=.
In reaching this conclusien en the Three Mile Island Site, we used a 2000 foot exclusien radius as was used c.n the first Three Mile Island Unit.
The required iodine reduction f actor en this basis is 5.5.
If this is compared to the maximu= credit of 3.5 which we previously calculated for the spray syste= described in the Oyster Creek No. 2 PSAR, it will be noted that additional iodine re= oval will also be needed at the Three Mile Island site.
'4e recognize that the fortheccing atendment to the PSAR may contain data which will alter the conclusion reached above.
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RT-3SA Radiation Safety Technology 3 ranch E&RST3 : DRL:'4FN Division of Reactor Licensing cc:
R. Tedesen, RP #2 R. Pcwell, ?? '/2 F. Schreeder, DRL q
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A sine R. S. Soyd, Assistant Director for Reactor Projects, DRL THRU:
S. Levine, Assistant Director for Reactor Technology, DRL EXCLUSION RADIUS DOSE CALCULATIONS FOR OYSTER CREE ** PLlCIT UNIT No. 2 Our memorandum to you dated Nove=ber 29, 1968, regarding exclusion radius dose calculations for the proposed Oyster Creek Unit No. 2 noted that the proposed contmimnt spray syste:s would not provide suf ficient iodine re= oval following the loss of coolant accident to meet 10 CFR 100 guidelines.
Based on standard staff meteorology, the change in site location to Three Mile Island vill not alter the basic conclusion reached in paragraphs one and two of our November 29, memorandu=. In reaching this conclusiou cn the Three Mile Island Site, we used a 2000 foot exclusion radius as was used on the first Three Mile Island Unit. The required iodine reduction factor on this basis is 5.5.
If this is compared to the mmv4 mum credit of 3.5 which we previously calculsted for the spray system described in the Oyster Creek No. 2 PSAR, it vill be noted that additional iodine renoval vill also be needed at the Three Mile Island site.
We recognize that the forthcoming amendment to the PSAR may contain data which will alter the conclusion reached above.
P. W. Howe, Chief, Environmental &
RT-88A Radiation Safety Technology Branch E&RST3:DRL:PL'E Division of Reactor Licensing cc:
R. Tedesco
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