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Category:ANNUAL OPERATING REPORT
MONTHYEARML20247E7541988-12-31031 December 1988 Berkeley Research Reactor Annual Rept 1988 ML20148Q6841987-12-31031 December 1987 Berkeley Research Reactor Annual Rept of Operations for 1987 ML20206P4761986-12-31031 December 1986 Berkeley Research Reactor Annual Rept of Operations,1986. W/Undated Ltr ML20207R8691986-12-31031 December 1986 Berkeley Research Reactor Annual Rept of Operations, Jan-Dec 1986 (Berkeley Research Reactor Tech Specs 6.7.2). W/Undated Ltr ML20154S1561985-12-31031 December 1985 Revised Pages 8 & 10 to 1985 Annual Rept,Reflecting Revised Fission Product Releases & Environ Surveys ML20199E3111985-12-31031 December 1985 Berkeley Research Reactor Annual Rept of Operations for 1985 ML20203P3511985-12-31031 December 1985 Berkeley Research Reactor Annual Rept of Operations,1985 ML20100A9331984-12-31031 December 1984 Berkeley Research Reactor Annual Rept of Operations,1984 (Brr Tech Specs 6.7.2) ML20117N3611984-12-31031 December 1984 Berkeley Research Reactor Annual Rept of Operations,1984 ML20081D0371983-12-31031 December 1983 Berkeley Research Reactor Annual Rept of Operations,1983 ML20071E8461983-03-0808 March 1983 Berkeley Research Reactor Annual Rept of Operations for 1982 ML20042B7941982-03-18018 March 1982 Berkeley Research Reactor Annual Rept of Operations,Jan- Dec 1981. ML19305C0601980-03-15015 March 1980 Annual Rept of Operations,1979. ML19259C1031979-05-0707 May 1979 Annual Operating Rept 1978 1988-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20247G0321989-09-12012 September 1989 Safety Evaluation Supporting Dismantling of Facility & Disposition of Component Parts,Per Licensee 880108 Application & 890131 & 0414 Ltrs ML20247E7541988-12-31031 December 1988 Berkeley Research Reactor Annual Rept 1988 ML20153A9221988-07-0505 July 1988 Safety Evaluation Supporting Amend 5 to License R-101 ML20147D7691988-01-31031 January 1988 Decommissioning Plan for Triga Mark III ML20148Q6841987-12-31031 December 1987 Berkeley Research Reactor Annual Rept of Operations for 1987 ML20206P4761986-12-31031 December 1986 Berkeley Research Reactor Annual Rept of Operations,1986. W/Undated Ltr ML20207R8691986-12-31031 December 1986 Berkeley Research Reactor Annual Rept of Operations, Jan-Dec 1986 (Berkeley Research Reactor Tech Specs 6.7.2). W/Undated Ltr ML20154S1561985-12-31031 December 1985 Revised Pages 8 & 10 to 1985 Annual Rept,Reflecting Revised Fission Product Releases & Environ Surveys ML20199E3111985-12-31031 December 1985 Berkeley Research Reactor Annual Rept of Operations for 1985 ML20203P3511985-12-31031 December 1985 Berkeley Research Reactor Annual Rept of Operations,1985 ML20138M5181985-10-23023 October 1985 Ro:On 850916,reactor Scrammed When Constant Air Monitor Showed 500 Cpm.High Radiation Alarm Activated.Fission Gas Activity Ceased When Instrumented Fuel Elements,Containing Defective Thermocouples,Replaced IR 05000224/20030011985-02-24024 February 1985 Paper 128,entitled Exam of Graded Response Strategy in Emergency Planning & Preparedness, Presented at 850224-0301 Ans/Ens Topical Meeting on Probabilistic Safety Methods & Applications,Vol 2:Sessions 9-16 in San Francisco,Ca ML20100A9331984-12-31031 December 1984 Berkeley Research Reactor Annual Rept of Operations,1984 (Brr Tech Specs 6.7.2) ML20117N3611984-12-31031 December 1984 Berkeley Research Reactor Annual Rept of Operations,1984 ML20081D0371983-12-31031 December 1983 Berkeley Research Reactor Annual Rept of Operations,1983 ML20071E8461983-03-0808 March 1983 Berkeley Research Reactor Annual Rept of Operations for 1982 ML20042B7941982-03-18018 March 1982 Berkeley Research Reactor Annual Rept of Operations,Jan- Dec 1981. ML20062K1321980-11-19019 November 1980 Safety Evaluation Supporting Amend 3 to License R-101 ML19305C0601980-03-15015 March 1980 Annual Rept of Operations,1979. ML19259C1031979-05-0707 May 1979 Annual Operating Rept 1978 1989-09-12
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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
.- s. * .- ,.
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.
~
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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