ML19330C735

Annual Rept-UCLA Nuclear Reactor,Jan-Dec 1979.

ML19330C735
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Site:	05000142
Issue date:	07/29/1980
From:	CALIFORNIA, UNIV. OF, LOS ANGELES, CA
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ML19330C729	List: ML19330C728 ML19330C735
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ANNUAL REPORT-UCLA NUCLEAR REACTOR 1 January 1979 through 31 December 1979 A. Reactor Operating Experience Operations during calendar 1979 totaled 446 port hours (a port opera-ting hour is the number of irradiation ports used times the irradiation time) for the year 1979 and expended 29.4 megawatt hours of thermal energy.

Research occupied 92.2% of the total operating time and class instruc-tion and demonstrations accounted for 7.6% of the total. Reactor mainte--

nance time was at an all time low, approximately 0.2% since the annual calibrations for 1979 were actually done in December of 1978 while the annual calibrations for 1960 were done in January of 1980.

The total operating time in port hours was up by 31% over the pre-vious year and is attributed to the increased demand by users coupled with reduced down time. The total energy expended was up by 45% and is attributed to the higher power demand per port hour. Table 1 shows the overall comparison with the four previous years.

TABLE I 1975 1976 1977 1978 1979 Research hours 146 158 188 244 411 Class instruction 39 27 88 60 34 Maintenance 31 23 14 36 1 i Total Port hours 216 208 290 340 446 Equiv.100 kw hrs 119 131 159 203 294 Mwh (th) 11.9 13.1 15.9 20.3 29.4 800811 oj391i

B. Unscheduled Shutdowns and Abnormal Occurrences

1. Unscheduled Shutdowns

a. 30 July 1979. A rabbit worth 154 was fired out of the reactor under automatic timing. This caused an initial positive period of less than 6 seconds which switched the reactor to manual control. Since 15c worth of reactivity generates a 56 second stable reactor period, the prompt jump coupled with this positive stable period gave the operator less than 10 seconds to respond. With the control rod withdrawn to 49%, the maxi-mum negative reactivity insertion rate was 2.5c/sec., thereby requiring 6 seconds to negate the amount of positive reactivity added by the departing sample. The unsuspecting operator with approximately 4 seconds to evaluate the situation and respond, failed to do so, and the reactor shut down on a high flux scram.

b. 19 December 1979. An operator while inking the linear power recorder-controller pen, turned the unit off when it was slightly below its demand set point. Since the controller, on auto at 10 KW, saw a need to increase power, it began with-drawing the reg rod at a constant rate. The operator, pre-occupied with the recorder and pen, could see no change on the disabled recorder. The power increased exponentially from 10 KW to 125 KW at which time the reactor shut down on a high flux scram. Since the operator was not aware of the impending scram and had done nothing to prevent it, the incident was reported as an abnorral occurrence.

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2. Abnormal Occurrences

a. 19 December 1979. During the course of a routine reactor operation, the operator noticed that both power recorders had ceased inking. The reactor was running at 10 KH on automatic control. The operator had completed inking one recorder and was working on the second when a high flux scram occurred. All ,

operations were suspended pending an investigation into the Cause.

The re-inked logarithmic power recorder showed a ramp power increase suggestive of a rod drive mechanism failure.

Checks of each drive indicated their functions were nornal .

Debriefing of the operator revealed that he had turned off the linear recorder while refilling the inkwell. What transpired has been described in 3.1.b.

Operator error, training inadequacy, and control circuit deficiency were cited as contributing factors by the Radiation Use Committee. The committee therefore recommended that the reactor supervisor:

1. institute monthly meetings of all reactor operators;

2. devise a plan to interlock all critical instrumentation into the scram circuitry; and i.

3. devise circuitry which will drive the reg rod down and emit an audible alarm if an inhibit signal causes the reactor to revert from auto to manual control.

These recommendations have been implemented at this writing.

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C. Preventive and Corrective Maintenance Advantage was taken of a scheduled shut-down in December 1978 to perform the tests and calibrations of 1979. The various radiation measuring systems including the Ar 4I stack monitor were calibrated on a semi-annual basis as required by the technical specification. Preventive mainte-nance is performed on all instrumentation prior to the tests and calibrations.

Corrective maintenance having safety significance is divided into two categories, electrical and mechanical. A brief summary of the main-tenance follows:

1. Electrical

a. 21 February 1979. The +300V power supply on the safety amplifier was found to be slightly low. Replacing the recti-fier tube and regulators and a voltage dropping resistor cor-rected the problem, The system was calibrated and performed satisfactorily.

b. 27 February 1979. During a prestart checkout, the +300V power supply on the safety amplifier was found to be reading

+200V. Four voltage divider resistors in the magnetic clutch l

control circuit were found to have abnormally low values which overloaded the +300V supply, Replacing these resistors cor-rected the problem; they were probably responsible for the prob-lem of 21 February 1979. One resistor had changed from a nominal value of 82K to a value of 1.5K, a change of 98%. The unit I was calibrated and checked out satisfactorily.

c. 5 June 1979. The magnetic clutch power supply on the safety amplifier malfunctioned when one of the silicon diodes on the full wave bridge power supply shorted. Three voltage 4

regulator tubes which were found to be marginal were also changed and the current on the -150V power supply adjusted to specs.

The unit was checked, calibrated and returned to service.

d. 28 August 1979. The control room intercom master station malfunctioned when a power transistor in the output stage overheated and shorted out. The transistor was replaced with a substitute and the unit returned to service.

e. 2 October 1979. The control room intercom master station failed, requiring replacement of the following components: (1) the power transformer, (2) the rectifier diode in the +20V power -

supply, and (3) both power output trarsistors and their emitter resistors. The repaired unit functioned properly and was returned to service.

f. 1 November 1979. The blinking red light flasher contacts were cleaned when it was noticed that the blinking lights were performing in an erratic manner.

2. Mechanical

! a. 6 August 1979. The rabbit terminal was removed from the reactor and cleaned, the remote terminal dismantled and cleaned and the polyethylene tubing replaced. The system was reinstalled and test fired. Operation was satisfactory.

b. 29 August 1979. Because rabbits fired into the core would occassionally fail to leave, the rabbit remote terminal system was dismantled for inspection of the flapper check valves.

l The check valve in the main air supply to the remote receiver was found to be defective and was finally replaced on the 17th 5

of September. A ball check PVC valve was substituted for the flapper check valve to allow use of the rabbit system from the 29th of August through the 17th of September.

c. 11' December 1979. The flapper valve on the reactor side of the rabbit system was found to be defective and replaced

v. hen a rabbit; failing to return, required several manual firings to return it. -The system checked out OK and was returned to service.

d. 13 December 1979. The damper system on the reactor side

' of the rabbit system was readjusted to further slow down the rabbits entering the reactor when some of the rabbits began showing damage (small chip marks around the leading edges).

Blank rabbits tested in the system showed no damage. The system was then returned to service.

e. 19 December 1979. The damper Tee on the reactor side of the rabbit system was inspected and found to have been damaged after a rabbit was stuck in the Tee. Inspection of previously fired rabbits revealed chip marks around the leading edges.of l

most of these rabbits which leads one to the conclusion that the damper adjustment of the 13th of December only delayed the ultimate failure of the damper Tee rather than alleviated it.

The dampe- Tee was machined to remove the sharp bent leading edge and reinstalled in the rabbit system. A hose clamp placed over the sharp leading edge holds the polyethylene tubing firmly against the leading edge of the Tee. This prevents any rabbit l

making contact with this edge. The system checked out satis-l l factorily and was returned to service.

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D. Facility and Procedure Changes

1. Administrative and Organizational Changes The UCLA Office of Environmental Health and Safety has been reorganized and renamed the Office of Research and Occupational Safety. The new office has been placed under the direction of Dr. Walter F. Wegst, and Dr. Wegst has been named by UCLA as the official representative of UCLA for correspondence between UCLA and the Nuclear Regulatory Commission.

2. Engineering Change Orders Modifications were made to the reactor air supply system when a dump valve failure occurred during a prestart checkout.

Examination revealed that the original flapper check valve (isolating the reactor air supply and backup compressor from the building air supoly) was leaking. The leakage was overloading the backup compressor motor: thermal protection limits the operating cycle, and the excessive demand could not be satisfied.

The following changes were made. A new ball and 0-ring check valve was installed in the air line at the building supply shutoff valve. This allowed the backup air compressor to supply raw air to the reactor control system regulator rather than parallelling the regulated utility air as originally installed, and returned the regulated reactor air system to its normal configuration. The rabbit system air supply line was rerouted to the main building air supply in order to satisfy the pressure and demand of 'the rabbit system. Pressure gauges were installed on the console to indicate both the reactor air supply pressure and the building air supply pressure.

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3. Revised Procedures A temporary operating procedure was initiated between April and May to allow safe operation of the reactor until the changeover of the rabbit air supply from the reactor supply to the building supply could be made.

On the recommendation by the Radiation Use Committee the following procedures were reviewed:

a. Sample handling procedures, rabbit system - a statement was added requiring the operator to drop all rods if the rabbit sample was found to be worth more than 28c.

b. Stuck rabbit procedures were provided.

c. The prestart check-off sheet reflected the following additions and changes:

1) operator review of the operating log is required;

2) air pressure readings were added; and

3) process pit check moved from step 1 to step 9.

With the initiation of the revised log keeping system using a bound volume and rubber stamp format, the normal startup procedures were modified to accomodate this change.

Supplementary rabbit procedures were instituted when problems not covered by the previous Stuck Rabbit Procedures were identified.

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E. Radioactive Material Releases to the Environment

1. The total releases for 1979 are:

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a. gaseous Argon 82.9 Ci

b. liquid none released

c. solid none released *

2. Identification of the principal radionuclides of each were conducted in the followiag manner:

a. The principal radioactive gaseous effluent as monitored in the building exhaust stack is identified as Argon-41. The actual concentration of this gas is determined by a 4.3 liter ion chamber (and varified by quantitative / qualitative gamma spectroscopy on batch samples) which has been calibrated in microcuries per milliliter vs. ion current. This data is re-corded on a strip chart recorder whenever the reactor is running.

The data are periodically integrated using a compensating polar planimeter to obtain the total curie discharge.

b. Liquid effluents: There were no liquid effluents released in the calendar year 1979. Although a sample of the reactor core primary water was collected and analyzed, it was unneces-sary to release the water.

Although no primary coolant (H2O) has been released for three years (the water is in a closed clean system and is con-tinuously filtered and deionized during operation), routine periodic analyses (batch type samples) have been done. The analysis is done by Scintillation and GeLi gamma spectrometry,

• See 2c. Identification of Solid Waste.

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liquid scintillation counting and end window GM gross counting.

The analysis detects sub-microcurie levels of corrosion pra-ducts such as Co-60, Na-24, Fe-59 and Zn-65. The liquid scintillation result was a tritium (H-3) concentration of

-3 3.08x10 pCi/ml resulting in approximately 2.3 millicuries of tritium in the 200 gallons of primary water. This.will be considered if and when the primary water is changed.

Liquid decontamination wastes are similarly analyzed prior to release. There were no such releases in this reporting period.

c. Solid waste: There was no solid waste released to the i environment. All solid waste is packaged in Department of Transportation (DOT) approved steel drums at the reactor site.

This waste includes such items as activation analysis containers, samples, gloves, shoe covers, rags, paper, plastic bags, irradia-tion tubes, string, etc. The drum is gasketed and sealed and external wipes are taken because no drums can be removed that show l

l external removable radioactive contamination. The outside is surveyed for external radiation which must be less than 200mR/hr.

at the maximum spot. The hottest external reading of the four drums in 1979 was 0.25mR/hr. beta, gamma. This information, along with an estimate of the isotopes and curie content of each, is then recorded and posted on the drum and the drum is officially transferred to the UCLA California State Radioactive Materials Byproduct License

• at the NEL boundary.

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• The UCLA California State Byproducts License Number is 1335-70 and is kept on file at the Radiation Safety Office.

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The resident health physicist accompanies this state licensed shipment, containing no liquids, to the UCLA Radiation Controlled Waste area within the campus boundaries. The waste is held at this site under the supervision of the Radiological Safety Officer until a sufficient number of drums are collected from the entire campus to warrant calling the University's commer-cial waste disposer company (Thomas Gray Associates) for pickup and ultimate burial at the Beatty, Nevada Commercial Burial Site.

There were four such 55 gallon drums transferred from NEL to the UCLA State license during the year 1979. Records of these transactions are filed at the NEL and at the UCLA Radiation Safety Office.

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F. Environmental Surveys The reactor room (1000 Boelter Hall, called the R_eactor H_igh B_ay (RHB) at the UCLA Nuclear Energy Laboratory (NEL) is completely surrounded by a radiation controlled buffer zone area for which entry requires a special security pass, a unique key (off all masters and NRC approved locks), health physics qualification by examination, and mandatory per-sonnel dosimetry. The unrestricted area (uncontrolled) beyond the buffer zone and available to the University population and general public, begins at the laboratory concrete wall outside of this second perimeter. Measured levels (records in area survey file) of direct radiation (beta, gamma and neutron) in this uncontrolled area are not detectable above background

(< 0.04 : 0.03 mR/ hour) with a calibrated GM survey instrument during steady state full power reactor operation (100 Kilowatts thermal). Neutrons are measured with an Eberline PNR-4 Neutron REM Counter; none are present.

1. A complete area radiation survey (beta, garmia and neutron) was taken while the reactor was at steady-state, full-power on May 21, 1979. This survey was taken with the normal biological radiatron shielding in place. The shield has not been changed or disturbed since the previous annual area survey. The data reveal that no loss or change in shield integrity has taken place since the previous survey. Monitored values, locations, and isodose maps are on file at the NEL to validate NEL compliance with occupational and non-occupational area radiation limits as set forth in 10 CFR 20.

2. Direct radiation from facility effluents is not detectable above background with low level G'1 survey instruments (i.e., < 0.04 2 0.03 mR/hr.) outside of any NEL controlled areas.

This is due to the very low concentration of isotopes, dilution 12

and dispersion of stack effluents and to the isolated waste and cooling systems of the liquid effluents. This is verified for ef-fluent air by both the area survey and an environmental film badge monitoring program. Results are listed in F5 of this report. The liquid waste is batch sampled for activity concentrations prior to discharge and this release is permitted only when the batch measures less than the 10 CFR 20 concentration release limits.

3. Eighteen environmental routine wipe tests were made weekly (as well as many recorded non-routine) at the most probable radioactively contaminated areas both inside and outside the controlled areas for the calendar year 1979. No activity above background statistics (i.e., none > three times background) was detected outside of the controlled areas. The detection limit for 95% confidence (10 minute count times, 60 minute background times) is between 9 x 10-8 to 9 x 10-7pCi/cm2 with 10 3% efficiency for beta counting.

4. The continuous particulate air monitoring system samples the facility exhaust stack and intake duct at the third floor (3000 level),

The limit of sensitivity for the system falls in the range of 2 x 10-12pci/ml to 2 x 10-13 Ci/ml. The system for collection of f

particulates is more conservative than specified in ANSI 13.1-1969 and the particulate filters are counted routinely on a batch basis.

The system includes an upwind (intake duct) sample of volume identical to the exhaust sample, it is used for background subtrac-tion from the exhaust sample to eliminate natural radon and thoron daughters collected as a result of this type of sampling system.

There were six incidents of the facility exhaust filters exceeding the intake filters by twice the standardized laboratory statistical l

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background count. There were no exhaust filter counts greater than 3 times the intake filter counts. Following the routine technique of instrument background subtraction, before subtracting the intake from the exhaust filter count the worst case concentration for 1979 2

would be from 2.6 x 10 pCi/ml without intake subtraction to 1.2 x 10-12pCi/ml with intake subtraction. Since the only isotopes that NEL handles regularly with restrictions in this category are natural uranium and natural thorium which have uncontrolled release limits of 5 x 10'I2pCi/mi and 2 x 10-12pCi/ml annual average con-centrations, it is concluded that there are no radioactive particu-late releases from the facility which exceed 10 CFR 20 Appendix B table II, Column 1 for air releases.

5. There is currently an environmental area film badge program conducted in and around the NEL. This program consists of 29 film badges which have the ability to read beta (through the beta window) and gama. The badges are divided into 1 month and 3 month inte-grating periods and are located (see tables IV and V) at strategic l

locations inside and outside of Boelter Hall, Math Science Addition, and the NEL. There are two badges (which may'be described as source badges) located inside the exhaust stack, one at the exhaust fan l

and the other at the center of the exhaust exit.

l Table IV is divided into 3 categories, A. the area films in the Math Science Addition (MSA) on 3 month issue, B. the area films inside the Nuclear Energy Laboratory (NEL) including the Tokamak research area of both I month and 3 month issue, and C. the area films on the roof regions I and II of Boelter Hall and the Math Science Addition of 1 month issue. These films are Kodak personal 14

monitor film type 2 and neutron NTA film in filtered standard type metal holders, the same as used in personnel monitoring. The mini-mum detection level, per film, has been established at 20 mR hard gamma ( > 150 kev),10 mR soft gamma or x ray ( < 150 kev), 20 mrad beta and 40 mrem neutron (fast > 0.4 MeV and thermal). The three month issue film sensitivity would then divide the values by a factor of 3 yielding minimums of 6.67 mR hard gamma, 3.33 mR soft gamma, 6.67 mrad beta, and no change in neutron because neutron films are on one month issue only due to track fading. There is only one neutron film in this group which is changed monthly and that is in film badge #0426 located in room 3316 MSA which is adjacent to the north side of the NEL facility at the 3000 level (3rd floor).

The MSA area film badge program began in October 1979 and as a result only one 3 month period is available for this report.

The NEL area film program has 4 complete quarters for 1919; how-ever badges 1944,1951 and 1965 have exposures which correlate to the Tokamak fusion research (under DOE and State of California Byproducts license #1335-70). These three area badges prior to 1976 (Before Fusion) had zero readings or exposures which related to open core reactor maintenance only.

The films located in the exhaust ~ stack which indicate beta exposure from the A-41 release, correlate to both the release quan-tities per month and the direct beta radiation rate measurements taken inside the exhaust stack and in the exiting plume to better than 250% (Beta dose rate at 100 Kw thermal steady state 2 mR/hr for 2s, 4 mR/hr for 4n geometry).

No radiation above background is measurable during 100 Kw steady 15

state operation at any other location in either region I or. II and this was verified by a separate set of measurements taken by the l

USNRC I&E division during a requested surprise inspection in 1979.

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G.

Personnel Radiation Excosures 1.

Individual Records The personnel radiation exposures for the UCLA Nucl Laboratory were minimal with no NEL personnel or exceeding 2 the entire year 1979.

These minimal exposures are attributed to no reactor -

e in cor maintenance or fuel handling where large previous exposures been accumulated.

Even with the increased reactor usage. the per-sonnel radiation has been kept at a minimal level in keeping w ALARA.

There were from 70 to 80 people per month (average) carrie on the film badge program at the NEL.

These were roughly divided into the following categories:

18 Reactor occupational level exposure personnel , RO's, (SR0's students, technicians,etc.)

8 Fart time assistants (Professors, RA's, TA's, etc ).

23 Full time Tokamak Fusion Research employees 22 Students (Undergrads, Grads, Classes, etc.)

1 71 TOTAL, not counting a few terminations.

None bf the ter-minations recorded any radiation exposure.

Only the 18 Reactor occupational level exposure personnel are considered in the indi-vidual and statistical tables because they are the ones considered to be covered by the Reactor R-71 license while the vered others are co by the California State Byproducts License #1335-70 .

There were no visitor badge exposures above detectable background levels of radiation (minimum detectable limits set at 10 mR x-ray. 20 mR g ,

20 mrad beta and 40 mrem neutron). The dosimetry at UCLA is processed 17

in-house and uses Xodak Personal Film edouble 2 for emulsion x-ray, gamma and beta; and Kodak Fersonal Neutron type "A" m Monito (NTA) for neutrons.

The issue periods are monthly for all reactor personnel and full time employees.

It is also monthly for ,

all neutron badge users.

Part time personnel not associated with

. neutron work are on 3 month issue periods.

In table II and table III the individual and statistical exposure data are all f rom 1 month issue beta, gamma and neutron film packets.

There are no 3 month coverage periods under the R-71 license.

All permanent exposure records are kept at the UCLA radia Safety Office, A6-060J, Center for Health Sciences , Los Angeles.

Califernia 90024 Duplicate copies in NRC format, are also on file at the REL facility to provide current exposure r es of histo i key individuals should this be necessary in emergencies , in-core maintenance or inspections.

The individual exposures (NOT BY NAME) are in listed table III, in table II with their statistical evaluation liste 2.

Statistical Summary 1979 Only the 18 individuals directly connected with the USNRC R -

license are considered in the personnel dosimetry program fo report.

All other employees, students and visitors are covered under the State of California Byproducts license which also reg -

lates the remainder of the laboratories activities

. . , Tokamaks , (i e subcriticals, radioisotopes, accelerators, etc.),

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TABLE II 1979 Individual Exposures in mrems

1. . Individual Quarters

1. SR0 1st NP 0

1st 0

P NP2nd 0

P 2nd NP 3rdNP3rd 4th NP4th Annual Total P P 0 0 0 P

2. 0 0 0 SR0 0 0 0 0 0 0 0 0 0 0

3. SRO O O 0 O O O O O O

4. R0 0 0 O O 0 0 0 0 0 0 0

5. R0 0 0 0 0 0 0 0 0 0

6. R0 0 0 0 0 0 0 T6/79 -- --

0

7. R0 55/79 0 0 0 0 0 0 0

8. R0 0 0 0 0 0 0 T6/79 -- --

0

9. R0 S4/79 0 0 0 0 0 T8/79

10. R0 0 0 0 0 0 0 0 0 0 0

11. TS -- --

0 0 S10/79 0 0 0

12. TS 0 0 0 0 0

0 0 0 0

13. TS 0 0 0 0 0 20 0 0' 0 0 0

14. TS 0 0 0 0 20 0 0 0 0

15. TS -- - -- -

0 0 S10/79 0 25 0

16. TS 0 0 0 0 25 0 0 0 0 0

17. TS -- -- -- --

0 510/79 0 0 0

18. TS -- -- -- --

0 510/79 0 0 0 0 SRO - Senior Reactor Operator R0 - Reactor Operator NP - noncenetrating TS - Technical Staff P - penetrating i

S - Start occupational program i

T - Terminate occupational program i

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TABLE III Estimated Whole Body Exposure Range (REttS)*

thmber of Individuals

1. in each range tio measurable exposure

2. ( < 0.01) 16 Measurable exposure

3. (0 01 to 0.1) 2

4. (0.01 to 0.25) 0

5. (0.25 to 0.5) 0

6. (0.5 to 0.75) 0

7. (0.75 to 1.0) 0

8. (1.0 to 2.0) 0

9. (2.0 to 5.0) 0

10. (5.0 to 12.0) 0

( > 12.0)

TOTAL If1DIVIDUALS 1 18

• As of this year the UCLA Film Badge Personnel monito i r ng program estab-lished the fol_ lowing minimums for each radiation type b levels (threshold of meaningful measurement): ased on confidence

a. Hard gamma

( > 150 kev) 20 mR

b. X ray

c. ( < 150 kev) 10 mR Beta

d. 20 mrad fleutron (Thermal + Fast) 40 mrem 3.

Pocket Dosimeter Records 1979.

Pocket dosimeters were required for 30 projects e year during th The highest quarter by exposure (gama only)e was 17 mn and th highest single exposure was 14 mR both received by the h ealth physicist during routine portable instrument calibrations .

The next highest exposures were 8 mR exposure. quarterly and 7 mR single The remainder were less or zero and therefore cant.

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TABLE IV B

FB{ . LOCATION AREA FILM BADGE DATA A. TYPE 2372 MSA Rm 8331 inside airshaft 5-11 2357 MSA Rm 7331 s, y, 3 mo.

inside airshaft S-10 2367 ftSA Rm.6331 s, y, 3 mo.

inside airshaft S-9 s, y, 3 mo.

2349 MSA Rm 5329 inside airshaft S-8 3202 MSA Rm 5907 s, y, 3 mo.

2312 MSA Rm 5308 Mr. Wm. Kehl's office (inner) S, y, 3 mo.

2298 Mr. Wm. Drain's office (outer) 3, y, 3 mo.

2287 MSA Rm 4302B Mr. M. Stephen's office (inner) s, y, 3 no.

MSA Rm 4328C computer air supply shaft 2374 s, y, 3 mo.

MSA Rm 43280 inside airshaft S-6 2395 MSA Rm 3' s, y, 3 mo.

.e airshaft S-4 2268 MSA Rm S 8. y, 3 me.

terminal room 2283 MSA Rm 3901 3, y, 3 mo.

Mr. D. Archer's office 2378 MSA Rm 2334 keypunch rm window 8, y, 3 mo.

0834 MSA Rm 2334 S, y, 3 mo.

keypunch rm vent intake 0426 MSA Rm 3316 a, y, 3 mo.

Prof. P. Koosis office B. 3, y, 3 mo.*

0218 BH Rm 2001 reactor control rm east window s, y, 3 mo.

0219 BH Rm 1005 sample refining & conc. lab 0220 BH Rm 2567 s, y, 3 mo.

NEL business office badge rack 0230 BH Rm 1561 shop south of R.H.B. s, y, 3 mo.

1531 8, y, 3 mo.

MSA Rm 2000A H.P. office S, y, 1 mo.

1914 MSA Rm 2000 NEL classroom 1944 BH s, y, 3 mo.

Rm 1000A east wall Tokamaki lab 1951 BH 8, y, 3 mo.

' Rm 1000A west wall Tokamak t lab 1965 3, y, 3 mo.

2048 MSA Rm 1000B east end heat transfer t lab 3, y, 3 mo.

MSA Rm 10008 center of heat transfer lab 3, y, 3 mo.

C.

0203 BH Rm 8000 inside exhaust doghouse 0265 BH Rm 8000 8, y, 1 mo.

exhaust stack exit grille 0302 MSA Rm 9000 8, y, 1 mo.

i Math Science intake duct 3, y , 1 mo.

0820 BH Rm 8000 So. of Region I toward 8500BH 5, y , 1 mo.

• 1 month neutron film in sane holder I

Readings x-rays primarily from Fusion research due to gBremsstrahlun created 21

MSA = Math Science Addition BH = Boelter Hall Rm = Room i

RHB = Reactor High Bay NEL = Nuclear Energy Laboratory NELF = Nuclear Energy Laboratory and Fusion Engineering HP = Health Physics S = Beta radiation y = gamma radiation 1000 = ground floor, 2000 = second floor, 3000 = third floor, ete-N = north, S = south, E = east, W = west mo. = month FB# = film badge number Qt = quarter year (3 months)

N = neutron ,

ON = zero neutrons

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TABLE V 1979 Area Film Badge Exposures mR

1. FB# 1st Qt 2nd Qt 3rd Qt 4th Qt Total

1. 2372 --- begin 10/79 0 0

2. 2357 --- 0 0

3. 2367 --- 0 0

4. 2349 --- 0 0

5. 3202 --- 0 0

6. 2312 --- 0 0

7. 2298 --- 0 0

3. 2287 --- 0 0

9. 2374 --- 0 0

10. 2395 ---

0 0

11. 2268 ---

0 0

12. 2283 ---

0 0

13. 2378 --- --- --- begin 2/80 ---

14. 0834 --- --- --- begin 2/80 ---

15. 0426 0, ON 0, ON 0, ON 0, ON 0, ON

16. 0218 0 0 60 0 60

17. 0219 0 0 0 0 0

18. 0220 0 0 0 0 0

19. 0230 0 0 0 0 0

20. 1518 0 0 0 0 0

21. 1914 0 0 0 0 0

22. 1944 640* 940* 75* 210* '1865*

23. 1951 13042* 3842* 1927* 1250* 20.061*

24. 1965 800* 190* 115* 95* 1200*

25. 2048 0 0 0 0 0

26. 0203** 65s 110s 135s 115s 4253 r 27. 0265** 55s 70s 120s 105s 350s

28. 0302 0 0 0 0 0

29. 0820 0 0 0 0 0

• These badges reflect Toakmak operation, see section F.5 page G-3.

• • These films showed no gamma radiation and are located in the Reactor exhaust stack main airstream before dispersion.

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