ML20031A749
| ML20031A749 | |
| Person / Time | |
|---|---|
| Site: | 05000142 |
| Issue date: | 09/21/1981 |
| From: | CALIFORNIA, UNIV. OF, LOS ANGELES, CA |
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| NUDOCS 8109250364 | |
| Download: ML20031A749 (19) | |
Text
[
e ANNUAL REPORT 1980 Nuclear Energy Laboratory l
SCHOOL OF ENGINEERING AND APPLIED SCIENCE t.NIVERSITY OF CALIFORNI A, LOS ANGELES 8109250364 81092P c PDRADOCK05000g4y; R
l
'tr CONTENTS l
Section Pa ge 1
REACTOR OPERATING EXPERIEilCE 1
if l
2 UNSCHEDULED SHUTDOWriS AtlD ABNORMAL OCCURREllCES 3-5 3
PRLvENTIVE AtlD CORRECTIVE MAlflTENAf4CE 6
4 CHAf4GES TO FACILITY, PROCEDURES, TESTS AND EXPERIliEllTS 7-9 5
RADIOACTIVE MATERIAL RELFASES TO THE ENVIR0flMENT 10-11 i
Gaseous Effluents 10 Liquid Effluents 10-11 Solid Hastes 11 6
EfiVIR0f4MEf1TAL SURVEYS 12-17 7
PERSONilEL RADIAT10ft EXPOSURES 18 3
4 a
U
)
J L'
TABLES Table Page 2
1 Reactor Usage 2
Film Badge Location and Type 15 3
Film Dadge Readings--1980 16 i
t r
[
l
)
t10t1EllCLATURE
)
BH = Boelter Hall E
= East FB# = Film badge number HP = Health Physics mo. = month MSA = Math Science Addition N
= florth T4EL = Nuclear Energy Laboratory NELF = Nuclear Energy Laboratory and Fusion Engineering ON = Zero neutrons Qt = Quarter year (3 months' RHB = Reactor High Bay Rm = Room S
= South W
= West 1000 = ground floor 2000 = second floor 2000 = third floor, etc.
s
= Beta Radiatior, y
= Gamma Radiation 4
i Section 1 REACTOR OPERATIf1G EXPERIEf1CE Operations during the calendar year 1980 totaled 594 port hours of service accomplished in 381 actual operating hours, or 289 equivalent full power hours.* The total energy expended was 28.9 megawatt hours, down by 2% from the previous year.
Prudent scheduling allowed this decrease with an actual increase of 33% in port operating hours over the previous year.
Table I shows the overall comparison with the four previous years.
It should be noted that all class, maintenance and demonstration hours are considered as one port hour per operating hour, whereas the remaining user hours may represent up to 3 port hours per operating hour.
The fact that the reactor does not operate at its full licensed power 100'!, of its operating time explains the distinction between the actual run time and the equivalent full power hours.
l
- Port hours are the product of the number of irradiation ports in use and the number of hours those ports are in use.
Port hours are a measure of service.
E> aivalent full power hours at 100 kw or megawatt heurs are useful for fuel burnup and effluent release calculations.
Table 1.
Reactor Usage CATEGORf 1976 1977 1978 1979 1980 (LA55 ROOM INSTRUCTION 17 83 52 31 4~
MA]NTENANCE 23 14 34 1
38 RESEARCH NEL STAFF USERS 4
31 9
1 27 OTHER UCLA USERS 109 106 105 91 101 COLLEGE E UNIVERSITY USERS 45 47 37 53 20 OTHER EXTR AMUR AL USERS 1
5 95 264 360 DEMONSTRATIONS 10 6
7 5
2 TOTAL PORT HOURS 208 290 340 446 594 ACTUAL RUN TIME 184 238 271 372 381 EQUIVALENT FULL POWER HOURS 131 159 203 294 289 PORT HOURS ARE A MEASURE OF USER DEMAND, TWO CONCURRENT USERS FOR ONE HOUR CONTRIBUTE TWO PORT HOUR 5.
INSTRUCTIONAL AND MAINTENANCE HOURS ARE COUNTED A5 ONE PORT-HOUR PER HOUR.
[LA55R00M INSTRUCTION INCLUDES GRADUATE AND UNDERGRADUATE LABORATORY WORK INVOLVING BASIC COUNTINF, ACTIVATION ANALYSIS, Rt ACTOR PARAMETER DETERMINATIONS AND OPER ATOR TRAINING AND REQUALIFICATION.
N!L_itarr USERS INCLUDSS EXPERlMENTS CONDUCTED BY THE REACTOR STAFF, SUCH AS SEED IRRADIATION, GEM COLOR ING E sPER IME NTS, ACTI V AT I ON ANALYSIS, TR ACER S TUDi[5 C ISOTOPE PRODUCTION USING THE N-P REACTIGN.
C_T Hf R UCLA USERS INCLUDED, IN THE PAST, THE DEPARTMENTS OF CHEHISTRY, GEOLOGY, GEOPHYSICS, METEROLOGY, AND NUCLEAR MEDICINE. THE TYPES OF EXPERIMENTS HAVE INVOLVED ACTIVATION ANALY5I5, TRACER STUDIES, AND DELAYED NEUTRON COUNTING.
[pk(EGE & UNIVERSITY USERS HAVE, IN THE PAST, INCLUDED CALIFORNIA POLYTECHNIC INSTITUTE, CALIFORNIA INSTITUTE OF TECHNOLOGY, CALIFORNIA STATE UNIVERSITY - LOS ANGELES, CALIFORNIA STATE UNIVERSITY - NORTHRIDGE, HARVEY MUDD COLLEGE, MT. SAN ANTONIO COLLEGE, PIERCE COLLEGE, UN! vet 517Y OF CALIFORNIA - SAN DIEGO,CUNIVERSITY OF CALIFORNIA - SANTA BARBARA. THE TYPES OF EFPERIMENTS PERFORMED WERE ACTIVATION ANALYSIS, FISSION TRACK COUNTING, TRACER STUDIE!,
REACTOR PARAMETER DETERMINATIONS, REACTOR OPERATING CHARACTERISTICS, REACTOR OPERATIONS, SHIELDING STUDIES, AND HEALTH PHYSICS TRAINING.
OTH!R EXTRA"VRAL USEPS INCLUDE GEOCHEMISTS, GEMOLOGl5TS, AND ENGINEERING FIRMS.
HINERAL ASSAY THROUGH ACTIVATION ANALYSIS AND DELAYED NEUTRON COUNTING, GEH COLOR ALTERATIONS, AND RADI ATION $HIELDlNG STUDIES TYPlFY THE TYPES OF EXPERIMENTS PERFORMED.
OEw3N57 RATIONS WERE ACTUAL REACTOR RUNS IN WHICH THE REACTOR WA5 TAKEN CRITICAL TO DEMONSTRATE REAC'OR PARAMETERS, CHARACTERISTILS OR OPERATION. YOUR$ IN WHICH THE REACTOR WAS SHUT DOWN ARE NOT INCLUDED. HIGH SCHOOL 5, PIERCE COLLEGE, THE PRESS, SOUTHERN CALIFORNIA EDISON COMPANY WERE RECIFIENTS OF REACTOR DEMONSTRATIONS.
TpTAL PQRT HOURS. ACTUAL R UN T I ME. EOUIVALENT FULL POWER HOUR 1 ARE INCLUDED IN THIS TABLE.
DEVIATIONS BETWEEN THE REPORTED PORT HOUR 5 AND THE TOTAL PORT HOURS ARE DUE TO ROUND-OFF ERROR $.
"THis TABLE !$ AN ADAPTATION OF A TABLE PRtPARED FOR THE USNRC IN THE COURSE OF RENEWING THE REACTOR OPERATING *.! CENSE.
?
l Section 2 UNSCHEDULED SHUTDOWNS AND ABNORMAL OCCURRENCES The seven unscheduled shutdowns in 1980 are described below in the order of their occurrence. There were no abnormal occurrences in 1980.
6 February 1980.
Shortly af ter the reactor leveled at 100 KW during a rabbit run, the reactor experienced a high flux scram.
Examination of the linear chart showed that the reactor went from 100 KW to 120 KW in one minute which indicates a positive period of
=330 seconds. The rabbit was discounted as the cause since the scram occurred = 2 seconds af ter the rabbit was inserted, while the power had been climbing for at least a minute prior to scram. The scram was attributed to a line transient which set the reactor to manual when the reg rod was on the positive side of its cycle.
(See Section 4, c.)
15 February 1980. While holding at IW in preparation for a class experiment, the reactor experienced a full scram. Neither the Log N
~
and period amplifier noi the safety amplifier were in alarm, indicating that they could not have taused the scram.
The manual scram indicator on the full scram bus (which is a 13tching indicator reset by the acknowledge button) was normal, indicating that the retrete manual scram has not been initiated. A momentary breach of the c Lsures could have caused the scram but no earthquakes were reported or felt in the area.
A power transient could have caused the dumovalve to open, and there was an electrical storm going on at the time, but it does seem unusual that none of the other instruments were affected. The source of the 3
_~
i i
scram was therefore listed as unknown.
j 10 March 1980.
The reactor was shutdown on a secondary radiation-alarm during an open thermal column experiment being conducted by the reactor health physicist.
The area was being monitored for neutrons, 8 and y, by the health physicist while the power was being increased in i
discrete steps. When the reactor reached 700 Watts, the scram occurred.
It appears that (n,y) reactions in the vicinity of the detector caused the scram as the North and South area eonitors were reading = 0.3 mR/hr a
at the time.
28 March 1980. A period scram resulted with the reactor on auto ik' due to'a faulty fluorescent light socket in the log H Recorder inducing transients into the Log N and period amplifier. The l
fluorescent light has been removed pending the replacement of the defective socket.
12 May 1980.
The reactor shutdown on a period scram while holding at lW awaiting the completion of the weekly health physics survey of the top of the reactor by the part-time student health physics aide. The i
period scram was attributed to the vibrations in the Lon N and period amplifier signal cable caused by the sudent heuith physicist sicmming the barrier gate as he left the top of the reactor. The student was admonished to exercise t.uution while working near the signal Cable tray.
30 September 1980. Power line transients induced into the CIC compensation power supply by the dirty contacts of the flashing light circuit caused the reactor to shutdct;n on a short period scram. Cleaning the flashing light circuit contacts corrected the problem.
{.
21 November 1980. The reactor shutdown on a short period scram 4
- m..
- =, -
m
l during a " control rod calibration experiment" being conducted by an Engineering class. The scram is attributed to the prompt jump caused by the 20c step of reactivity added to the reactor as the rabbit was fired out of the core.
The prompt jump is usually precomoensated by establishing the reactor on a negative period prior to firing the rabbit out.
2 June 1980.
The reactor shutdown on a period scram on the approach to 1 llatt for the initial readings of the run. The cause of the period scram was determined to be the -30V CIC power supply.
Bypassing the -30V power supply and the outputs at the connector to each chamber corrected the problem.
The original run was cancelled but a test run showed the reactor performed in a normal manner.
i 5
Section 3 PREVENTIVE AND CORRECTIVE MAINTENANCE The annual tests and calibrations as required by the technical specifications were completed in the month of January. The semi-annual calibrations of the various reactor radiation monitoring instrumentation were performed in January and July.
Non-scheduled correccive maintenance having safety significance is t mmarized as follows.
28 January 1980.
tailure of a diode in the bridge rectifier circuit of the magnet power supply prevented the energizing of the rod drive magnetic clutches during a pre-start check-ut of the s eactor.
The unit was repaired, tested, and returned to service.
2,4 June 1980.
Noise in the CIC compensating voltage power supply caused unsatisfactory operation of the Log N and period amplifier channel.
Both CIC power supplies were bypassed with capacitors and the compensating power supply was placed on the sola rer;ulated bus.
30 September 1980. Noise in the CIC neutron channels was traced to the CIC power supplies. The noise appeare:1 in time with the reactor flashing light circuit.
Cleaning the flashing light contact points cleared the problem.
6
Section 4 CHAflGES TO FACILITY, PROCEDURES, TESTS AND EXPERIMENTS Pursuant to 10 CFR 50.59, the following modifications have been performed.
8 January 1980. A water trap was placed in the dump tank vent 4I line to prevent any air and Ar conteined in the dump tank from venting into the reactor c/haust under normal operatin9 conditions, yet allow the dump tank to vent to the stack should pressure build up in the tank.
17 March 1980. A protective key switch in series with the reactor console key switch was installed on the console. This key switch prevents the operation of the reactor when the key is checked out to maintenance men working in the third floor service area located above the reactor.
There are only two keys.
One is held by the reactor health physicist and the other is used by either maintenance men or the reactor operator.
19 tiarch 1980.
The pre-start check-off sheet and the procedures to delineate operator action were updated.
28 March _lj98_0_.
At the recommendation of the Radiation Use Committee, the following circuit modifications were made in the reactor console.
A. The linear recorder, 109 recorder and Ar4l system power switches were tied into the circuit failure scram bus.
This prevents disabling any of the critical instrumentation 0
7
during on opera'. ion.
B. The AC power switches to the linear amplifier, the Log N and period amplifier, and the CIC power suppites were removed as those instruments are permanently powered.
The switches were removed to reduce potential operator confusion.
C. An inhibit safety circuit was added to cause rod 4 to
's drive down should and inhibit signal occur. The audio alarm also sounds and a red LED will indicate that rod 4 is driving down.
This curcuit is intended to slowly shut the reactor down wh!1e alerting the reactor operator to take action should an inhibit signal switch the reactor to the manual mode of operation.
D. The pre-start check-Off and the operating procedures were updated to reflect the above modifications.
E. The rabbit procedures and emergency procedures call list were also urfated.
17 June 1980. A " Reactor Use Authorization" was inittcted in 45 order to more fully inform the reactor operator as to the nature of 4'
the proposed run, and to inform the reactor supervisor of the current reactor condition and sample disposition at the conclusion of the run.
22 July 1980.
The start up procedure was modified to allow rods 1, 2 and 3 to be pulled from 44% to 48% as recommended by the Radiation Use Committee, and approved by the Director.
31 July 1980. The carbon vane stack effluent sampling pump was replaced by a diaphragm pump.
~
l 8
4 2 September 1980. Provisions to introduce N2 gas into the reactor core through the thermocouple' conduit were installed. The system i
consists of the appropriate plumbing, a flow meter, a pressure-regulator, and a high pressure liquid nitrogen source.
This 4I modification was instituted as an experiment to reduce Ar production 1
by displacing the air in the reactor core with nitrogen gas.
3 November 1980. The fuel inventory procedures were updated.
6 November 1980. The reactor high bay ventilation shutdown circuit was extended to include a shut down. switch in the rabbit room and a shutdown circuit connected to the reactor high bay high radiation detector.
4I correction factor form was instituted 17 November 1980. An Ar to recone:.le the actual stack gas concentration and the gas 4l monitor' ion chamber.
concentration as seen by the Ar I
I L
I l
i t
b 2
-9
Section 5 RADI0 ACTIVE MATERIAL RELEASES TO THE ENVIRONMENT The total releases for 1980 were as follows.
A. Gaseous: argon-41, 83.0 Ci B. Liquid: zinc-65, 4.1 pCi C. Solid:
none (see paragraph on Solid Waste below).
Identification of the principal radionuclides of each were conducted in the following manner.
Gaseous Effluents. 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 verified by quantitative / qualitative gamma spectroscopy on batch samples) which has been calibrated in microcuries per milliliter versus ion current. This data is recorded 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. The total discharge of 83 Ci divided by the 289 equivalent full power hours of 1980 yields a release rate of 0.287 Ci/ full power hours, and an effective concentration of 1.2 x 10-5 pCi/ml. Because the argon-41 release rate lags the reactor power (both in build-up and decay),
and operations at less than 100 kw are common, the effective concentration of 1.2 x 10-5 Ci/mi is never achieved in practice. Peak values in_ excess of 10-5 pCi/ml are not observej under normal conditions.
Liquid Effluents. A release of 400 gallons of water on March 11, 10 l
l
s 1980 contained 41 pCi (2.7 x 10-0 pCi/ml) identified by gamma spectroscopy as zinc-65. That concentration is approximately 2.7% of
-4 the permissible concentration of 10 pCi/ml (10 CFR 20, Appendix B, Table II, Column 2) for release to uncontrolled areas. The isotope is believed to have arisen as either a corrosion-activation product, a decontamination product, or some combination thereof. A release of 500 gallons of water on June 13, 1980 contained no observable radioactivity.
Solid Waste. No low level solid waste disposals or shipments for disposal were made by the NEL in 1980.
[A small shipment
( < 1 kg U235) of irradiated fuel was made to Exxon Nuclear, Scoville, Idaho, on June 21, 1980. Upon return of the rental cask to General Electric, Pleasanton, California, the cask and trailer were found ;o be contaminated with cobalt-60. An investigation by the Department of Transportetion failed to identify the source of the contamination.]
A w
Section 6 ENVIRONMENTAL SURVEYS i
The r'eactor room (1000 Boelter Hall, called the Reactor High B_ay'(RHB) at the helear Energy Laboratory (NEL)f, is completely surrounded by a radiaticn controlled buffer zone area of limited access. The unrestricted area (uncoatroll 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 fiic) 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).
Neutron surveys are done with an Eberline PRN-4 Neutron REM Counter; no flux can be found.
A complete area radiation survey (beta, gamma, and neutron).was 1
taken while the reactor was at steady state, full power on June 12 1980.
This survey was taken with the normal biological radiation shielding in place. The shield had 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.
Direct radiation from facility effluents is not detectable above
-12
background with low ;evel GM st.evey instruments (i.e., < 0.04 + 0.03 mR/hr) outside of any NEL controlled areas. This is due to the very low concentration of isotopes, dilution and dispersion of stack effluents j
and to the isolated waste and cooling systems of the liquid effluents.
This is verified for effluent air by both the area survey and an environmental film badge monitoring program.
Results are listed in the latter part of this section. 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 cancentration release limits.
liineteen environmental routine wipe tests were made weekly (as well J
as many rccorded non-routine tests) at the most probable radioactively contaminated areas both i.. side and outside the controlled areas for the calendar year 1980. No activity above background statistics (i.e.,
none greater than three times background) was detected outside of the s
controlled areas. The detection limit for 95% confidence (10 minute 3
-8 count times, 60 minute background times) is between 9 x 10 to 9 x 10 pCi/cm with 10% + 3% efficiency for beta counting.
The continuous particulate air monitoring system samples the facility exhaust stack and intake duct at the tnird floor (3000 level). The limit
~I o sensitivity for the system is in the range of 2 x 10 pCi/ml to r
2 x 10-pCi/ml. The system fcr collection of 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 subtraction a
13 e
r i
from the exhaust sample to eliminate natural radon and thoron daughters collected as a result of this type of sampling system.
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
-12 the worst case concentration for 1980 would be from 1.8 x 10 Ci/ml without intake subtraction to 0.8 x 10^2 pCi/ml with intake subtraction.
Since the only i :otopes that NEL handles regularly with restrictions in this category are natural uranium and natural thorium which have
-I2 uncontrolled release limits of 5 x 10-12' pCi/ml and 2 x 10
-pCi/mi annual average concentrations, it is concluded that there were no radioactive particulate releases from the facility which exceed 10 CFR 20 Appendix B Table II, Column 1 for air releases, There is currer.tly an environmental area film badge program conducted in and around the NEL. This program consists of 29 film badges which are designed to measure both the beta and gamma radiation.
The badges are divided into 1 month and 3 month integrating periods and are located (see Tables II and III) at strategic locations inside and outside of Boelter Hall, Math Science Addition, and the NEL. There are two badges (which may be described as source badges) iouited inside -
the exhaust stack, one at the exhaust far and the other at the center of the exhaust exit.
Table II is divided into 3 categories.
A.
The area films in the Math S_cience A_ddition (MSA) are on 3 month issue.
B.
The area films inside the !Juclear Energy Laboratory (NEL) 14
Table 2.
Film Badge Location and Type U
ISSUE FILM BADSE FILM BADGE A
1 B AM DM A FILM PERIOD NUMBER LOCATION A.
MATH SCIENCE ADDITION 2372 MSA RM 8331 INSIDE AIRSHAFT S-11 8,y 3 MO.
2357 MSA RM 7331 INSIDE AIRSHAFT S-10 8,y 3 MO.
2367 MSA RM 6 331 INSIDE AIRSHAFT S-9 B,y 3 MO.
2349 MSA RM 5329 INSIDE AIR $ HAFT S-8 8,y 3 MO.
3202 MS A RM 5907 MR.W.KEHL'S OFFICE (INNCR4 8,y 3 MO.
2312 MSA RM 5308 MR.W. DRAIN'S OFFICE (OUTER) 8,y 3 MO.
2298 MSA RM 4302B MR.M. STEPHEN'S OFFICE (INNER) 8,y 3 MO.
2287 MSA RM 4128C COMPUTER AIR SUPPLY SHAFT 2,y 3 MO.
2374 MSA RM 43280 INSIDE AIRSHAFT S-6 S,y 3 MO.
2395 MS A RM 3940 INSIDE AIRSHAFT S-4 B,y 3 MO.
2268 MSA RM 3901 MR.D. ARCHER'S OFFICE 8,y 3 MO.
2378 MSA RM 2334 KEYPUNCH ROOM WlHDOW 8,y 3 MO.
0834 MSA RM 2334 KEYPUNCH ROOM VENT INTAKE 8,y 3 MO.
0426 MSA RM 3316 PROF.P.KOOSIS'S OFFICE 8,y 3 MO.X S.
NUCLEAR ENERGY LABORATORY INCLUDING 'OKAMAK RESEARCH AREA u
0218 BH RM 2001 REACTOR CONTROL ROOM EAST WINDOW 6,y 3 MO.
0219 BH RM 1005 SttPLE REFINING AND CONC. LAB 8,y 3 MO.
0220 BM RM 2567 NEL BUSINESS OFFICE BADGE RACK 8,y 3 MO.
0230 BM RM 1561 S?'SP SOUTH OF R.H.B.
8,y 3 MO.
1581 MSA RM 2000A HEALTH PHYSICIST'S OFFICE 8,y 1 MO.
1914 MS A RM 2000 NEL CLASSROOM 2,y 3 MO.
1944 BH RM 1000A EAST WALL TOKAMAK LASHM 6,y 3 MO.
1951 BH RM 1000A WEST WALL TOKAMAK LABEM S,y 3 MO.
1965 MSA RM 1000B EAST END HEAT TRANSFER LABMX 8,y 3 MO.
2048 MSA RM 10008 CENTER OF HEAT TRANSFER LAB 8,y 3 MO.
C.
ROOF REGIONS - BOELTER HALL AND MATH S C IC*lCE ADDI TION 0203
'. H RM 8000 INSIDE EXHAUST DOGHOUSE 6,y 1 MO.
0265 BH RM 8000 EXMAUST STACK EXIT GRILLE 6,y 1 MO.
030:
MSA RM 9000 MATH SCIENCE INTAKE DUCT 6,y 1 MO.
0820 BH PM 8000 SOUTH OF REGION I TOWARD 8500 BH 2,y 1 MO.
N1 MONTH NEUTKON FILM IN SAME HOLDER
"* READINGS PRIMARILY FROM FUSION RESEARCH 00E 10 BR!MSSTRAHLUNG CREATEL X-RAYS.
15
I 1
Ta bl e-3.
Film Badge Rodings - 1930
. FILM SADGE L
NUMBER 2372 0
0 0
0 0
2357 0
0 0
0 0
2367 0
0 0
0 0
2349 0
0 0
0 0
3202 0
0 0
0 0
2312 0
0 0
0 0
2298 0
0 0
0 0
2287 0
0 0
0
'O 2374 0
0 0
0 0
2395 0
0 0
c.
O 2268 0
0 0
0 0
2283 0
0 0
0 0
2378 0'
0 0
0 0-0834 0
0 0
0 0
0426 0,0N 0,0N 0,0N 0,0N 0,0N 0218 0
0 60 0
60 0219 0
0 0
0 0
0220 0
0 0
0 0
0230 0
0 0
0 0
1581 0
0 0
0 0
1914 0
0 0
0 0.
1944 195" 320" 360" 850" 1725" 1951 560" 3243" 470" 320" 4593" 1965 0
190" 0
0 190" 2048 0
0 0
0 0
0203""
1258 1008 958
<608
<3808 0265""
708 708 658
<608
<2658 0302 0
0 0
0 0
0820 0
0 0
0 0
"THE$E films REFLECT'TOKAMAK OPERATION, SEE SECTION 6.
xxTHESE FILMS SHOWED NO GAMMA RADI ATION AND ARE LOCATED IN THE REACTOR EXHAUST -
STACK MAIN AIRSTREAM BEFORE DISPER$10N.
16
including the Tokamak research area are of mixed 1 month L
and 3 month issue.
C. The area films on the roof regions I and II of Boelter Hall and the Math Science Addition are of 1 month issue.
These films are Kodak double emulsion, personnel monitor film type 2 and neutron NTA film in filtered standard type metal holders, the same as used in personnel monitoring.
The threshold detection levels for these films are:
x-ray ( < 150 kev) 10 mR Kodak Type 2 hard gamma ( > 150 key) 20 mR Kodak Type 2 beta 20 mrad Kodak Type 2 neutron (thermal & fast) 40 mrem Kodak NTA Neutron badges are changed monthly to minimize track fading, others are on either one month or three month issue. As a badge exposure is cumulative, those on three month issue will detect lower exposure rates (by a factor of three) than those changed monthly. The films are orocessed and read by UCLA's Office of Research and Occupational Safety.
Area film badge measurements for 1980 are shown in Table III.
Film badges #1944, #1951, and #1965 in the NEL area are reflecting Tokamak operations, and prior to the initiation of that program, badges at those locations were either zero or had exposures related to reactor core maintenance.
Film badges #203 and #265 located in and on the exhaust stack are observug the electrons emitted by the radioactive decay of argon-41.
The film badge read,gs are reasonably compatible with direct beta observations of 2 to 4 mR/ hour (2n or 4n geometry respectively) at those locations after several hours of steady operation at 100 kw.
17
Section 7 l
l PERSONNEL RADIATION EXPOSURES Film Badge Records.
During 1960, seventeen individuals categorized as reactor-related personnel were carried on the UCLA film badge program. These individuals are considered to be covered by the USNRC license R-71.
The highest exposure to any of these individuals was 80 mR (beta) and 25 mR (gamma). A second individual received 35 mR (beta), no gamma. The remaining 15 individuals had no measurable film badge exposures. There were no visitor badge exposures above minimum detectable limits All permanent exposure records are kept at the UCLA Radiation Safety Office, A6-060J, Center for Health Sciences, Los Angeles, California, 90024.
Duplicate copies in NRC format are also on file at the NEL facility to provide current exposure histories of key individuals should this be necessary in emergencies, during in-core maintenance operations, or inspections by regulatory agencies.
Pocket Dosimeter Records. Pocket dosimeters were issued on 37 occassions The highest quarterly exposure (gamma only) to an individual was 17 mR and the highest single exposure to an individual was 14 mR.
It was the same individual in both cases and the exposures ere received in the course of calibrating the portable moni
-ing equipment.
18
______ _ ___________