ML20210G952

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Forwards Tables Providing Scope & Results of Sensitivity Studies on Dose Consequences from Containment Venting Reported in 860908 Memo,In Response to 860911 Request.Subj Studies Used Maccs Code & Conducted W/Bnl Assistance
ML20210G952
Person / Time
Issue date: 09/23/1986
From: Congel F
Office of Nuclear Reactor Regulation
To: Rosztoczy Z
Office of Nuclear Reactor Regulation
Shared Package
ML20209E138 List:
References
FOIA-87-10 NUDOCS 8609260015
Download: ML20210G952 (7)


Text

I s [e UNITED STATES j'

p, NUCLEAR REGULATORY COMMISSION O

.j WASHINGTON, D. C. 20555 9

j SED 2 31986 PEMORANDUM FOR:

Zoltan R. Rosztoczy, Chief Regulatory Improvement Branch, DSR0 FRON:

Frank J. Congel, Chief Reliability and Risk Assessment Branch, DSR0

SUBJECT:

DOSE CONSEQUENCES FROM CONTAINMENT VENTING Your memorandum dated September 11, 1986 (copy enclosed) requested sensitivity studies on results reported in my September 8,1986 memorandum to M. W.

Hodges, RSB/BWR, on the subject " Post-Accident Doses Off-site from Nable Gases."

Enclosed Tables A-E provide the scope and results of sensitivity studies performed in this branch (per your request) using the MACCS code with assistance from the Brookhaven National Laboratory.

MACCS runs were made for ten (10) cases of release of noble gases:

release of 100% of noble gases after 1, 2, 3, 4, 5, and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> hold-up following scram; release of 50% of noble gases after 1, 2, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> hold-up following scrar:;

and release of 25% of noble gases after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> hold-up following scram. These release scenarios with their other parameters are shown in Table A.

Other data or assumptions common to these MACCS runs were the same as in the earlier study: a) Core inventory of radionuclides of a 3412 Mwt LWR, b) One year's meteorological data for New York City, c) No offsite emergency response, d) Shielding pro'tection factors for normal activity, e) Uniform population density of 100 persons per square mile, and f) Exclusion area boundary (EAB) radius of 0.5 mile.

Table B shows the mean, median, and 95-percentile values of person-rem for the 10-mi and 50-mi regions. Table C shows statistics of early fatality radius (EFR). Fror Table C it appears that there is non-negli s",

to extend beyond EAB for Release Scenarios (of Table A)gible potential for EFR

  1. 1, 2, 3, 4, 7, 8, and 9, and that EFR would likely be inside EAB for Release Scenarios #5, 6, and 10.

Individual risk of early fatality as a function of distance is shown in Table D.

Risk of early fatality is virtually zero beyond 3.5 miles. Table E shows the mean, median and 95-percentile downwind individual dose as a function of distance.

All of the Release Scenarios studied may exceed the epa guidelines for evacuation to more than 5-miles.

For/1 M Dfo.

(c@yQ#LS~ &,pe

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2. Rosztoczy Advance copies of Tables A-E have been given to Frank Coffman and Farouk Eltawila of your branch on September 22, 1986. You may contact Sarbes Acharya (x29738), RRAB, for any additional information. As a suggested bibliographical reference, please see pp. S20, S132-134 of the report of the APS Study Group on Severe Accidents at Nuclear Power Plants, Reviews of Modern Physics, Vol. 57 Number 3 Part II, July 1985.

l Trank J. Congel, Chief Reliability and Risk Assessment Branch

, Division of Safety Review and Oversight

Enclosure:

As stated cc:

R. Bernero D. Ross R. W. Houston G. Lainas L. G. Hulman M. W. Hodges T. E. Collins E. Jordan, IE J. Martin, RES T. Margulies, RES P. K. Niyogi, RES l

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