ML20154S156

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Revised Pages 8 & 10 to 1985 Annual Rept,Reflecting Revised Fission Product Releases & Environ Surveys
ML20154S156
Person / Time
Site: Berkeley Research Reactor
Issue date: 12/31/1985
From:
CALIFORNIA, UNIV. OF, BERKELEY, CA
To:
Shared Package
ML20154S154 List:
References
NUDOCS 8603310375
Download: ML20154S156 (2)


Text

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  • e 8

normal operations.

The total released was 6.13 Ci as Ar-41 of a maximum permitted release of 2,785 Ci which corresponded to 0.22% of the allowabic release.

Maximum concentration at one particular period at stack discharge was 2.54 x 10pCi/ml. This concentration is 81% of the allowable maximum concentration for this facility of 3.12 x 10pCi/ml. No average concentration was calculated due to frequent periods of-time when the reactor was idle more than 50% of normal operational time (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per day, 5 days a week, excluding legal and university holidays).

Filter paper air samples showed that no particulate radioactivity above naturally ocurring levels could be detected in the exhaust stream.

Trace amounts of fissien products from a leaking instrumented fuel element were detected during the months of September and October 1985.

During this incident, the estimated average concentration of detectable fission gasses (Kr-85m, KR-87, KR-88)'in the reactor room were found to be lower than the allowable maximum concentration in unrestricted areas averaged over a year, as stated in 10 CFR 20, Appendix B. Most of the fission products were confined to the reactor room and disappeared by decay.

The Icaking fuel. element has been isolated and' removed from the core.-

This incident was reported to the NRC Region V Office.

Solid (Dry) Waste No solid (dry) waste was released for disposal during the year.

Personnel Radiation Exposure Recorded radiat. ion exposures for the year to personnel included:

8603310375 860324 PDR- ADOCK 05000224 R PTA

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10-Average dose is meaningless due to excessive influence of a few positions.

c). Routine quarterly area TLD dosimeter. readings totalled 52 at 13 locations.

- maximum total dose at any location for the year - 299 mrem E

. minimum-total dose at any location for the year - O mrem Average dose is meaningless due to excessive influence of a few positions.

Note that the period reported for quarterlyfilm and TLD is .2/1/85 -through .

to 1/31/86.

d) Routine weekley swipe program generated 2040 swipes of which 63 showed contamination above normally expected level.

. -2 2

- maximum swipe activities recorded was 8.4~x 10 pCi/100 cm from nonna11y contaminated surfaces. This was due to tritium not associated with reactor operations.

- minimum activities for both categories was zero.

Averages were not detennined due to excessive influence of a few swipes.

Environmental Surveys Environmental TLD measurements at 9 locations outside the facility '

generated 36 radiation readings.

- maximum total recorded exposure at any cutside location for the year was 299 mrem.

- minimtsn total recorded exposure at any location for the year was 0 mrem.

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Averages were not detennined because the majority of locations had very low or no exposure, and only a few locations had significant readings.

Note that the period reported was 2/1/85 through to 1/31/86.

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