ML19261F042
| ML19261F042 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/13/1972 |
| From: | Harold Denton US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910180658 | |
| Download: ML19261F042 (2) | |
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JUL ! 3 M72
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R. C. DeYoung, Assistant Director for PWR's, L Tm MILE ISLA!D UNIT 1 ACES EPORT PLA'IT NAME: Three Mile Island Unit 1 LICEIiSLG SM CL gh 0
DOCKET ID EER: 50-289 RESPCT.S DLE ERANCH; Site Analysis Rranch
.,i REQUESTED CCHPLETION DAIE: June 26, 1972
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APPLICAITIS RESPG 53 DATE ECECSAEY FOR hEXT ACTION PIANED ON PROJECT: N/A DESCRIPIIOU OF RESPOUSZ: ACES Report REVIEW STATUS: Ccurplete Attached is our evaluation of Sections 9.0 and 2.1 of the Three Mile Island Unit 1 IEAR for inclusion in the ACPS - Safety Evaluation Report.
The site description and accident analysis sections of our input conclude that the site does not meet 10 CFR Fart 100 requirements. The calculated 0-2 hour thyroid dose that might result from the lost of coolant accident (LOCA) is 439 ren. This dose is based on a dose reduction factor (DRF) of 5 58 for the containment spray system, a containment leak rate of.2%
perday,andPasquilltype"F"meteorologywith0.6 meter /sec.vindspeed.
The applicant has agreed that the site meteorology is "F" and 0.6 m/s without an allowance for meandering. We conclude that sufficient data are not available to give credit for meandering. The 5 58 DRF for the sodium thiosulfate spray system is based on the current AEC spray model, for which no change is anticipated on the time scale of the Three Mile Island review. We conclude that the applicant must reduce his centain-ment leak rate or make other system changes to reduce the LOf'A doses to levels within 10 CFR Part 100 guidelines.
Drfg!nal afgned hv
' IL R. Dent u
A W R. Dentoni. Assistant Directer for Site Safety Directorate of Licensing
Enclosure:
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