ML19289F339
| ML19289F339 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 05/29/1979 |
| From: | Wilson W WASHINGTON STATE UNIV., PULLMAN, WA |
| To: | Ramos S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906070249 | |
| Download: ML19289F339 (2) | |
Text
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WASHINGTON STATE UNIVERSITY PULLMAN, WASillNGTON WM NUCLEAR RADIATION Ck.NTER May 29, 1979 Mr. Steve Ramos U.S. fluclear Regulatory Commission Was)ington, D. C.
20555
Dear Mr. Ramos:
This morning I noted two typographical errors in the exponents on Page 10 of t!e Environmental Impact Appraisal that we recently submitted.
En-closed are 20 corrected copies of Page 10 of tbe EIA.
Sincerely, W. E. Wilson 2233 170 Associate Director WEW:eb enclosures m.
E h
s ili 7906070 AY9
i 10 activation of argon contained in air. The Argon-41 content of reac-tor nool room exhaust is continuously monitored with a special gamma-ray spectrometer set to detect Argon-41.
Over the past 5 years the annual averaged Argon-41 discharged from the facility amounts to 2.25% of the applicable release limit of Appendix B, Table II, Column 1 of 10 CFR 20.
A small amount of tritium is produced in the pool water through neutron capture in the deuterium present in the pool water.
Measurements of the H level in the pool water of a number of TRIGA reactors including the W.S.U. reactor are reported on Page 170 of the August 1976 issue of Health Physics. Measurements made by the W.S.U.
Radiation Safety Office agree with the reported value for the W.S.U.
reactor of.045 pCi/1.
The pool evaporation rate amounts to 560 10 3
liters per day and the pool room exhaust discharge is 8.16 x 10 cm 3
cer day.
If we make the conservative assumption that the H content of the pool water and evanorated water are the same, then the onal 3
room exhaust would contain 3.1 x 10-10 pCi/cm of tritium. This is
-7 significantly below the annlicable limit in 10 CFR 20 of 2 x 10 3
pCi/cm.
No other significant quantity of gaseous radioactive mate-rial or particulate radioactive material with a half-life greater than eight days has been released by the facility during the past 10 years.
In the event of a Loss of Coolant Accident or the Design Basis Accident, the SAR of May 1974 has shown the gaseous radioactive dis-charges to be minimal.
The whole body dose from a cloud of fission products discharged from the facility as a result of the DBA is only 1.5 mrem.
The maximum thyroid dose outside the facility was found to be.26 rem.
Thus no realistic hazard to the general public would
~
result from the DBA or a LOCA.
2233 171