ML20210P208

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Responds to 860815 Request for Bibliography of post-accident Radiation Offsite Dose Estimates from Releases of Noble Gases.Listed Refs Most Useful.Summary of Dose Estimates Encl.Graphs Discussed
ML20210P208
Person / Time
Issue date: 09/25/1986
From: Lainas G
Office of Nuclear Reactor Regulation
To: Bernero R
Office of Nuclear Reactor Regulation
Shared Package
ML20209C630 List:
References
FOIA-87-10 NUDOCS 8610060728
Download: ML20210P208 (3)


Text

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qi e MEMORANDUM FOR: Robert M. Bernero, Director Division of BWR Licensing FROM: Gus C. Lainas, Assistant Director Division of BWR Licensing

SUBJECT:

POST-ACCIDENT OFFSITE DOSES FROM VENTING NOBLE GASES DURING A SEVERE ACCIDENT

References:

(1) NUREG-0851, " Nomograms for Evaluation of Doses from Finite Noble Gas Clouds"; January, 1983 (2) "American Physical Society (APS) Study Group cn Severe Accidents at Nuclear Power Plants"; Rev. Mcd. Phys.,

Vol. 57, No. 3, Part II, July,1985 (3) Memo from F. Congel to M. W. Hodges, " Post Accident Doses Off-Site from Noble Gases," September 8, 1986 (S. Acharya study)

This is in reference to your memo, dated August 15, 1986, in which you recuested a bibliography of post-accident radiation off-site dose estimates frem releases of noble gases.

We have reviewed available literature and studies, and concluded that the three references listed above are most useful. Using these references we have compiled dose estimates at various distances due to a release of 100% of the noble gases from near ground level. Unless otherwise noted the following conditions were assumed: a) reactor operating power of 3412 MWt, b) mean meteorological and topographical conditions, c) finite plume, and d) normal activity of dose recipients (no evacuation).

Enclosures 1 and 2 represent a sumary of the dose estimates. The graphs are identical, except that enclosure 2 shows projected dose up to 60 miles, while enclosure 1 is limited to 10 mi]es distance. Please note that doses are directly proportional to reactor power and, therefore, for operating BWRs which vary in thermal power from 3400 MWt to approximately 1600 MWt (exclusive of Lacrosse and Big Rock Point) the doses scale directly. Superimposed on enclosure 1 is a graph depicting individual early fatality risks.* It is 1

Contact:

F. Skopec, RSB, x29468

  • This risk factor is based on an LD - 50/60 dose of 400 rads. Current perception is that the LD-50/60 dose may te as low as 290 rads. a r

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- DISTANCE (miles) =

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