ML20148E345
| ML20148E345 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 03/14/1988 |
| From: | Neely Research Reactor, ATLANTA, GA |
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| References | |
| NUDOCS 8803250068 | |
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{{#Wiki_filter:INCIDENT REPORT Cadmium spill on August 18, 1988 l
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l NEELY NUCLEAR RESEARCH CENTER GEORGIA INSTITUTE OF TECHJF01.DGY ATEANTA, GEORGIA 30332 8803250068 880314 PDR ADOCK 05000160 Q DCD
l NOTE l This document is intended to be a final report. Time constraints however prevented a thorough and complete review of all parts. Consequently we reserve the right to edit and/or change any portion thereof. NNRC Management L F O
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l TABLE OF CONTEN'8S, i Abstract 1 I. History of the Incident I- 1 II. Analysis II - 1 Power History II - 2 Activity of Cd II - 7 ' Heat Generation II -11 Metallurgical Consideration II -13 Activity and Appearance II -13 1 Isotopic Analysis II -13 Scanning Electron Microscopo Analysis II -14 Estimates of Dose II ml8 III. Records and Experiment Data III - 1 Power History of First Topaz Run Power History of Second Topaz Run ) Building Air Handling System Isotopic Analysis of Smears & Cadclium Gas Monitor Moving Air Particulate Filter Kanne Ionization Chamber Charcoal Cartridge Filter Containment Building Air Sampler Floor Surveys Dose Rate Survey Downs' Apartment Survey Personnel Data TLD Records Film Badge Records Bioassay Index Whole Body Counts Fxperiment Forms l Memos ' IV. Questions of Reportability IV - 1
,V. Lessons Learned v-1 :
Control of Experiments V- 1 : Overirradiation of Samples V -14 Handling Irradiated Sample V -21 1 Health Physics v -25 VI. Conclusions VI - 1 VII. Long Term Durability of Cadmium Fuse Filaments VII - 1 VIII. Characteristics and Analysis of VIII - 1 Radon-222 Daughters
l ABSTP.ACT t This report describes a cadmium spill that occurred at the Neely Nuclear Research Center on August 18, 1987. The information presented is drawn from the records of the facility, l personal interviews with the people involved, and from calculations to reconstruct the incident. 1 1 After investigation we believe the incident was minor in that no contamination left the containment building and no personnel were exposed to excessive concentrations of radioactive material. However, the investigation revealed several weaknesses in management control, personnel, and procedures. Management control of experiments and personnel is being addressed by procedural changes and addition of new management j positions in NRRC. i 1 Operational mistakes in running experiments and handling of samples is being addressed through administrative action, l training, and revised procedures.
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l 4 Health physics failure to take proper action during cleanup or to properly document their actions is being handled by replacement of the health physics staff with better qualified
personnel and complete revicion of all haalth physics procedures. Af ter sober reflection, management admits that rather than waiting for all facts to be analyzed, as was the intent in this case, an interim report should have been made immediately. The delay in preparing an incident report was to analyze why the cadmium had disintugrated. It now appears that the little-known matallurgical phenomenon of low temperature cadmium sublimation played an important' role in the incident. It is as yet too early to speculate on the significance of cadmium sublimation to power or research reactors. However, it must be vigorously pursued because the implication of this phenomenon has safety signif.icant. s p
HISTORY OF THE INCIDENT
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In April 1987 an experiment was designed to study the effect of fast neutron irradiation on topas gemstones. Other experiments have reported that large doses of radiation will change the topaz color to a deep blue which significantly increases their value. This experiment was intended to see if fast neutrons would cause any color change to occur. The planned experiment was to place topaz, aluminum flurosilicate, in a cadmium capsule and irradiate it in the V21 experiment- f acility for 30 MWH. The experiment was conceived as a multi-step process. The first step was a very shore irradiation at low power to chock the reactivity worth of sample, the cadmium capsule, and the aluminum can which held the capsule. The second step was to irradiate the topas for 15 MWH and v'isually inspect the sample before continuing up to the 30 MWH desired. A drawing of the experiment is shown in Figure 1. On April 3, 1987 a minor experiment appreval form was completed. This form authorized irradiation up to 30 MWH after the reactivity effect determined. The experiment approval form also listed the expected activation of the sample, i.e., the Cd
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capsule and topas. Since the activity of the sample was expected to be within the range routinely handled by reactor operations an entry of "nil" was made on the experiment approval form. This entry documented the activity associated with the
short run (4 min.) conductsd to datermina the reactivity of tho sample. The operators understood that there would be significant activity at the end of the run. l 1 The experiment was scheduled the same date as the approval. ' Reactivity measurements were very close to estimated values and the sample was left in V21 to begin accumulating dose. The experiment approval form, schedule form, and experiment status l operating logs are included in the next section. l l By April 22, 1987 the experiment had accumulated 15.7 MWR. ' No further operation took place until the sample was removed on l April 28. At time of removal the entire sample including l aluminum can had measured activity of 250 ar/hr at 1 foot. The l topaz was poured into a glass beaker for examination. As there l was no apparent color change, the topas was returned to its container and stored in a lead pig on the reactor top. l The cadmium capsule was not inspected visually at that l time. It did, however, rattle within the aluminum can and there I was no reason to suspect any problem. ; l i on July 14, 1987 thG sample was again placed in V21 for
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additional irradiation. It remained in V21 until August 14, 1987 at which time it had accumulated an additional 41.8 MWH. The reactor was not operated over the weekend and the following Monday afternoon, August 17, 1987 the sample was removed and 2 i
l placed in a lead pig on the rocctor top. Tha measured radiation i level was 3 rad /hr at 1 foot above the top of -the can positioned I inside an open pig.
- l The afternoon of the following day, August 18, gypp zf4 a senior reactor operator working alone, poured the topaz from 1
its container into a glass beaker which was then placed behind a lead pig on the reactor top. Although Fpf 44- saw some black j l granular material mixed with the topas , he did not suspect a ' problem. 64h1 #14L monitored the area using an Eberline ionization chamber both before and after removing the topaz. The readings were not recorded but he states that there was no unusual amount of radiation. Fwf ib4- then left the area after checking himself with friskers at the exit of the reactor control zone. No activity was detected. After returning to his office for a short time shy SL4 went home to his apartment. The next day he returned wearing the same clothes. Sp1 44- performed his normal duties in the reactor building, and in doing so, passed by the frisker in the reactor control zone 4 or 5 times. In none of these trips was any contamination detected. On the afternoon of August 19, a student making a routine surve.y of the containment building floor found a small amount of I 1 activity (100 to 200 cpm above background) on a masslinn mop which had passed over an area of 400 square feet near the 3
roactor baso. This is eroa 97 on tho floor plan. During a s follow up survey by health physics, a masslinn mop passed over the reactor top showed contamination of approximately 20 mrem /hr at near contact with 'a panoramic beta detector with cap off. When examined on a '.nultichannel analyzer, the masslinns showed peaks at 0. 336 and 0.528 MEV. The step off pad at the reactor top showed no contamination thus indicating that contamination on the floor had fallen from the reactor top but had not been tracked to other areas. At that point ggp -d: 4- informed the staff that he had opened the topaz the previous day. It was then apparent that the contamination was probably cd-ll5. Smears of the reactor floor counted 95-109 dpm. The masslinns from the reactor top counted 500,000 dpm. Decontamination' was started and cleanup continued for the rest of the day. During the afternoon health physics examined the gas monitor, MAP-1, and Kanne recorder charts for evidence of airborne contamination. None was found. Gw9 67 attempted to notify WsT but E3 f e T'. was unavailable and on route out of town. After cleanup on August 19, 1987 Go9 4L 4- was found to have contaminated his pants cuff. The cuff was cut off and disposed of in radioactive waste. A further examination of Gtf 94 was made by placing a 3 inch NaI crystal with a canberra Model 30, 1024 channel gamma analyser against his chest. After 4
l a 5 minuto count a slight indication of Cd 115 was noted, health physics concluded that it was from his clothing and was too small to warrant further action. ppf & 4- was dismissed and allowed to return home. Health Physics did not record any data from these measurements. Even though the floor survey taken August 19, showed no contamination in the vestibule (area 3 on the floor plan) or carpets in front of the air lock, M tl{ asked m e p t to take a geiger counter home and to survey his apartment to' report the results. Although Fh3P 14 , does not now remember doing the survey, several staff members remember him taking the counter home. F M WT' . said that Ecp 4 reported perconally to him that no contamination was found. The next morning, August 20, health physica repeated the I same chest count on 6pNr tL4- for 15 minutes and no activity above background was observed. The sensitivty of this measurement is approximately 1 nanocurie. In addition a urine sample was obtained and counted in a Packard 2000 liquid scintillation counter. Neither channel A nor channel B showed any unusual activity and channel A was consistent with a urine i sample taken a year earlier. No further action was considered ! necessary. A record of the counts in channel B was not preserved. l Decontamination work continued that morning. The final S
I i post decontcmination surysy on August 21 showed a maximum of 274 i i 2 l - d/m/100 cm on the reactor top. The maximum count anywhere was l 2 3208 d/m/100 cm on top of'the lead pig. A further survey of l the containment building floor including the exit path from the building showed a maximum count rate of 157 d/m/100 cm2 at the entrance to the emergency air lock, a point well removed from the site of the spill. l Finally the daily masslinn survey reports and the daily dose rate survey reports were examined to be sure that no l contamination had spread around the building at any time during the incident. The containment building air sampler was counted. l l The survey showed no evidence of airborne contamination or l spread of particulate matter. l l The preliminary conclusion was that the incident had been contained. Subsequent verbal and written reports to Synp W f-revealed no new information. ppp # 4't then made verbal report ' l to G4Pf 46 15' , who had just returned from out of town. After due consideration of all parties involved, it was concluded that there had been no unintentional release of contamination , from the containment building and that no NNRC personnel had been exposed to contamination or radiation exceeding limits of 10 CPR 20. Purthermore there was no reason to believe that any employee had failed to report or mi s-repor ted any pertinent information or had any employee l 6
fallcd to parforn his duties in a satisfectory mannar.
' j By August 31, 1987 further decontamination of the lead , pig l 2
had reduced the activity to 400 d/m/100 cm . FW99 d 4' TLD was read on August 27 and showed 60 mrem accumulated since July 11. (A subsequent report from Landauer of Gh+f #E44 film badge l showed 30 mrem for the month of August). At this point all data ; were consfstent with the preliminary conclusion of a contained incident with no health hazards to the public or staff. i Further investigation of the incident was suspended to allow the activity of the topas and its container to decay l sufficiently to permit safe inspection. This matter remained i suspended until reopened during the NRC inspection of December 16, 1987. l At that time the inspector felt our records were incomplete l and it was suggested that Georgia Tech perform a whole body coun t on Fy+f -tL4 . . Whole body counts of Ev>f 44- and two other persons involved in cleanup operation, were done. No internal contamination was found. In January 1988 Georgia Tech was ordered to perform another survey of Ghyf%k45 s apartment. No contamination was found. Results of these actions arc
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included in this report. l The NNRC also reopened its investigation of the' incident. The events leading up to the incident have been reconstructed, 1 l 1 l
records hava besn reviewrd, personal interviews conducted, calculations of activity levels performed, and extensive smear surveys conducted to search for evidence of airborne contamination. A complete description of what was done and the results is contained in the following sections of this report. While none of the results have contradicted the initial assessment of the situation nor indicated any unintentional ; release or personnel contamination, the investigation has identified shortcomings in record keeping and procedures. The end of this report discusses the lessons learned and discusses the remedies which are being adopted. ! l l l l l l l 0 l
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II. Analysis The August 18, 1987 spill of cadmium on top of the GTRR was analyzed to determine quantities of radioactive cadmium formed during the four month lo'ng irradiation. Also evaluated are estimates of the heat generation and removal. Metallurgical considerations and estimates of l skin, body and extremities doses are given. i The irradiation of topaz gemstones began on April 3, 1987 and ended on August 14, 1987. On April 22, 1987 a seven hour irradiation at 1 MW took place. At the end the cumulative megawatt hours were 15.704. Six days later, with no more intervening exposure to neutrons the container holding the topaz was removed from the reactor for inspection. The inspection performed by Mr. L. D. McDowell revealed that not much has happened to the topaz; it was clean and clear; i.e. no indication of melting or sublimation of the cadmium. The cadmium itself was not l inspected. There was no reason to suspect that the I cadmium was affected by the irradiation. On July 14, 1987 the topas and container were placed back into the reactor and irsadiation was continued, on and off, until August 14, 1987. The irradiation history is shown in Table II-1. Table II-2 shows the stable and radioactive isotopes of cadmium. Note that the isotope with the biggest cross section cd-113, upon absorbing one neutron in one of its
TiGLE II-1A Power Histor Prepared by:ygnet of ist 4-Topaz t on Run January - 04/03/87 26, 1988 to 04/22/87 I Date Time Power Level MWH Total MWH 04/03/87. O h 15 a 1 Mw .250 0 h 16 m 550,Kw .250
.147 .397 l 0 h 01 a 55 Kw .001 .398 0 h 11 a 500 w <.001 .398 04/06/87 1 h 30 a 1 Nw 1.5 04/07/87 4h 0a 4 1.898 1.Mw 4.0 5.898 0 h 46 m 603'Kw
.46 6.358 0h 6a lH) Kw .006 6.364 04/13/87 0 h 20 a 500 Kw .167 0 h 18 m 6.531 50 Kw .015 6.546 04/14/87 0 h 37 a 1 Hw .617 0 h 47 a 7.163 750 Kw .588 7.751 0 h 29 a 75 Kw .036 7.787 04/21/87 0 h 22 a 1 Mw .367 0 h 45 a 8.154 500 Kw .375 8.529 0 h 15 a 300 Kw .075 8.604 O h 31 a 100 Kw .052 0.656 0 h 31 a 50 Kw .026 8.682 0 h 13 a 10 Kw .002 8.684 0 h 39 a 5 Kw .003 8.687 0h 1a 1 Kw <.001 8.687 04/22/87 7h 1a 1 Hw 7.017' 15.704 l
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TABt2 II-1B \ Power Histor l Preoared by:y [Mf+9 of 2nd Topaz Run - 07/14/87 on January 26, 1988to 08/14/87 I Date Time Power Level MWH Total MWH 07/14/87 3 h 31 a 1 Mw 3.517 3.517 07/15/87 0 h 42 a 1 Mw .7 4.217 07/20/87 2 h 30 a 1 Hw 2.5 6.717 0h 4m 100 Kw .007 6.724 07/21/87 0 h 22 a 11Mw .367 7.091 0h 7m 100 Kw .012 7.103 0 h 16 a 10 Kw .003 7.106 0h 2a 1 Kw <.001 7.106 07/22/87 0 h 18 m i Hw .3 7.406 0 h 18 a 100 Kw .03 7.436 1 0 h 36 a 10 Kw .006 7.442 07/23/87 0 h 13 a 1 Mw .217 7.659 1 0h 6m 500 Kw .05 7.709 0 h 48 a 10 Kw .008 7.717 0 h 31 a 1 Kw .001 7.718 0.7/24/87 1 h 17 a 1 Hw 1.283 9.001 0 h 12 a 100 Kw .02 9.021 0h 7a 10 Kw .001 9.022 07/28/87 0 h 11 a 10 Kw .002 9.024 07/29/87 0 h 52 a 1 Hw .867 9.891 0 h 46 a 10 Kw .008 9.899 > 07/30/87 4h 0a 1 Mw 4.0 13.899 0h 5m 100 Kw .008 13.907 f'3/03/87 0h 4a 1 Hw .067 13.967 0h 2m 750 Kw .025 13.999 i Oh 3a 500 Kw .025 14.024 l 0h 2a 250 Kw .008 14.032 0h 8a 100 Kw .013 14.045 0h 7a 1 Kw <.001 14.045 08/06/87- 6 h 56 m 1 Mw 6.97 21.015 0h 8a 100 Kw .013 21.028 0h 5a 30 Kw .003 21.031 l l 08/11/87 5 h 38 m 1 Mw 5.633 26.664 1 h 22 m 100 Kw .137 26,801 08/12/87 6h 0m 1 Mw 6.0 32.801 08/13/87 6h 0m i Hw 6.0 38.801 08/14/87 _ 3h 0m , i Hw 3.0 41.801 II-3 i
e l i TABLE II-2 Isotopes of Cadmium ! Percent Natural Isotope Abundance c, barns = Ma'lflife Cd-106 1.22 1.0 Stable cd-107 0.00 unknown 6.49 hrs. ! 1 Cd-100 0.88 3.0 Stable Cd-109 0.00 unknown 453 days Cd-110 12.39 0.1 Stable ! Cd-lli 12.75 un'cnown Stable cd-lllm 0.00 unknown 48.6 min. Cd-ll2 24.07 0.03 Cd-ll3 Stable 2.2 Cd-113m l Cd-ll3 12.26 20,000 1.3 x 10 yrs Cd-ll3m 0.00 unknown 13.6 yrs. Cd-ll4 28.86 1.1 Stable cd-115 0.00 unknown 53.5 hrs. Cd-115m 0.00 unknown 43 days Cd-116 7.58 1.4 Cd-ll7 10 yrs. 0.7 Cd-117m 1 Cd-ll7 0.00 unknown 2.4 hrs. Cd-ll7m 0.00 unknown 3.4 hrs. zz-4 I _ ,. - *---s -- '
nucloi, it doos not b0cono radiocctivo. It simply bscomss Cd-ll4 which is stable. The huge cross section for Cd-113 profoundly influences the neutron flux inside the relatively thin cadmium sheet of which the container is made. This phenomenon is known as self shielding. The value of the flux as a function of depth in the 0.05 cm thick cadmium wall is shown in Figure II-1. The symbol $4 ,in Figure II-1 is the value of flux at the surface of the container. fgisthevaluefluxatxemwithinthecadmium. The drop from~the outside to the inside in the value of flux is more than three orders of magnitude. Considerations of flux perturbation due to the presence of the cadmium and of temperature effects when combinedwithselfshielding,yieldavaluefordh/pa , the volume averaged flux to the upreturbed flux, of 0.043. The main radioactive isotopes produced by irradiating natural cadmium are cd-109, Cd-113m, Cd-ll5m, and Cd-ll5. The production of these isotopes was calculated as a function of the irradiation history shown in Table II-1. The activities of these isotopes as computed by a simple subroutine at 3:23 P.M. on August 18, 1987 and also at 3:00 P.M. on January 25, 1988 are listed in Table II-3. The unpreturbed flux assumed in these II-5
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TABLR II-3 Estimated Activities of Cadmium Isotope 3 on 8/18/87 and on 1/25/88 Activities, millicuries
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Cd-109 Cd-ll3m Cd-ll5m Cd-ll5 i 08/18/87 0.136 0.67 8.99 311 l 01/25/88 0.107 0.66 0.69 negligible f l G a calculations was 1 x 10 n/cm sec. i l l Using these activities, on August 18, 1987 the i I expected dose rate due to gamma rays only was 4.32R/hr. at ; one ft. The measured dose rate due to gammas and betas on 1 the same date was 3R/ hour at one f t. On January 21, 1988, the 6ose ratio was measured to be 6.25. If one multi-plies the gamma dose rate (4.32 R/hr) by this ratio one gets 27 R/hr at one ft. for August 18, 1987. l I l II-7 i
Tho dose rate was also measured on April 28, 1987 to i be 250 mR/hr. at one ft. The calculated value for that date is 787 mR/hr. The sources of discrepancies are not known. TABLE II-4 compares measured and calculated activities referenced to January 20, 1988 Since it is known that the cadmium container experienced melting and sublimation, the self shielding factor could have decreased significantly. TABLE II-5 shows measured activities obtained from cadmium. Note that Ag-110m, Cd-109, Cd-llSe, Co-60, 1 Sb-124, Sn-113, and Zn-65 are found. II-8
Table 11-4 C0FFMIISON OF MEASURED AM) CALC 1 LATED ACTIVITIES VALUES FOR JANUARY 20, 1900 0)-100 (453d) CD-115e (44.6d) SMFLE Mmed Amesured Calculated Calculated Measured Measured Calculated Calculated Sp. 7ctivity87g Activity in Activity in Activity in Sp. Activity Activity in Activity in Activity in 679 with 67g with uC1/g 679 (uC1/g) 5 1E+13
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Speck #1 6.95 uCi/g 485 uti 2515 uti 110.6 afi 15.5 uC1/g 1036.2 uCi 19,100 tri 840 uti Spock #2 5.45 365 2515 110.6 9.02 604.3 19,100 840 Speck #3 25.62 1718 2515 110.6 66.9 4483 19,100 840 Speck #4 11.2 750,4 2515 110.6 35.5 2378.5 19,100 840 E Spedc #5 9.62 644.5 2515 110.6 28.0 1876 19,100 880 Speck #8 9.41 830.5 2515 110.8 21.8 1447.2 19,100 840
- no self-shielding
** asith self-shielding Notes: Speck #1: Cryotel from seem of can W #2: Smell piece from selted bottae Speck J3: Piece from solder joint Speck #4: Top of can Speck f5: Side of con Spock #6: Side of can
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TABLE II-5 PEASLEED ACTIVITIES OF SPECKS OBTAINED FROR IRRADIATED CADRILM LMIT: iC1/mg 2/18/88 Ag-11the cd-10s Cd-11Sm Co-60 Sb-124 Sm113 zn45 e y=r* #1: 40A (8.93+/ .21)E-3 (1.55+/.15)E-2 MA (2.53+/.03)E-2 (1.h/.02)E-3 00A Spock #2: 00A (5.45+/.40)E-3 (9.02+/-3.33)E-3 M A (5.69+/.06)E-2 (5.%/.06)E-3 004 Spock f3: (7.24+/-1.27)E-5 (2.m/ .03)E-2 (6.70+/.09)E-2 (6.29+/ .90)E-5 (5. W / .06)E-3 (5.01+/ .09)E-4 (1.3O+/.03)E-3 Speck I4: (2.93+/ .59)E-5 (1.12+/ .01)E-2 (3.55+/ .07)E-2 (4.54+/-2.98)E-6 (4.07+/ .43)E-5 (7.h/-1.83)E4 (3.b/ .11)E-4 speck 75: (1. W / .28)E-5 (9.62+/ .10)E-3 (2. h / .03)E-2 00A (7. W / .08)E-4 (9.m/-1.63)E-8 (2.10+/ .07)E-4 Speck #6: (1.51+/ .30)E-5 (9.41+/ .09)E-3 (2. m / .03)E-2 00A (2.13+/ .02)E-3 (6.21+/.22)E-5 (2.41+/ .06)C-4 U' D Spock #1: Notees Crystal from seen of can ey =r* #2: Small piece from molted bottae Spedc #3 Piece from solder joint
'q=r* #4: Top of can ey =r* #5: Side of can Speck #6 Side of can 00A indicates that semple activity was below minimum detectable activity
HEAT GENERATION ' Heat generation in the container was estimated for gammas from neutron capture in cadmium, reactor gamma rays (estimated at 1 x 10' rada per hour at one MW, and for gammas from radioactive decay of cadmium. The watts produced from each source were estimated ao follows. 1 l Capture (-rays 100.4 watts , bs from reactor 6.0 watts Induced activity 0.2 watts TOTAL 106.6 watts l l Estimates of heat losses referenced to a temperature of 300*C are as follows. Due to Radiation 33 watts Due to Conduction (effect) 588 watts i Loss due to convection = negligible Observation: At 15.704 Mwhr the cadmium container is believed to have experienced no melting. Self shielding of the neutron flux at thispointwassignificant;h[ho= 0.043. Melting could have started because of eutectic formation between Sn and Cd (eutectic temperature = 177*C; melting point of cadmium is 321*C.) Sublimation of l l cadmium also takes place at relatively low temperatures. i i II-11
Both ef fects could and must have contributed to the unsealing of the cadmium container. Once the cadmium ; container became unsealed, the self shielding factor decreased rapidly. Sublimation would tend to make the reaction rate in cadmium to be proportional to a value of the flux of 1 x 1013 n i.e. no self shielding. em 2 see Table II-4 which compares measured activities of cadmium isotopes to calet:ations confirms this observation. Additionally as melting and sublimation take ; place and self shielding decreases, the heat generation also increased. I 1 l l l l l l LI-12
METALLURGICAL CONSIDERATIONS On January 21, 1988 the aluminum can holding cadmium capsule was removed from the reactor top and placed in the hood in the decontamination room for inspection. The dose at 1 foot above the sample was 25 mrads/hr beta plus gamma. This measurment may be compared with the 3 rad /hr measurement on August 17 when the sample was removed from the reactor. The most intense radiation was 130 mrads/hr beta and gamma, 1 foot from the side of the aluminum can. The aluminum can was intact. The cadmium canister was badly damaged. There was some evidence of melting and a resolidified metallic disk was removed from bottom of the can. The remains of the cadmium were chared (possibly oxidized) and numerous brownish-black granules were present. The consistency of the material varied from fine sand to course chunks. The upper portion of the cadmium was the least damaged and the cadmium top was intact. This physical evidence is consistent with the damage being caused by gamma heating of the topaz . Five smears of the aluminum can, cadmium, and topaz were made for isotopic analysis. Three smears showed approximately 10 ~ 3 microcuries of each of Cd-109,,Cd-ll5, Sb-124, and 2n-65. The Sb and Zn were probably from the solder used to fabricate the cadmium capsule. The smear from the aluminum can also II-13
showtd 2.3 X 10'4 microcurioc of co-60 which we believe to be contamination from the lead pig. The most active smear was of the black granular material which contained microcurie amounts of Cd and Sb. Three samples of the residue from the cadmium and one of the topaz stones were examined with a scanning electron microscope (SEM). The surface of each sample, expecially the topaz, showed evidence of cadmium crystal growth. The grains were well connected and their size was greater than 0.1 microns. The grain formation is consistent with sublimation of Cd with subsequent 'redeposition on the topaz and the aluminum can. i l A study of cadmium by Georgia Tech Physical Sciences l Divison has showed that cadmium sublimation rates at 145 C in an oxygen-nitrogen mixture will approach 5 micrograms /cm2 min. The l I sublimation rate increases as the temperature approaches the j melting point of Cd at 321 C. (See Attachment) Assuming that the cadmium was maintained at 145 C for 67 hours during which the reactor was operated, approximately 6 grams could have sublimed from both the outer and inner surfaces of the capsule. Although oxydation of the cadmium slows the sublimation process, any defect in the oxide layer allows a cavity to form ! under the oxide. The oxide then crumbles and exposes fresh cadmium. The brown-black residue from the capsule is consistent with this process. II-14
The SEM analysis also found dmall amounts of tin from the solder. .Sowever, the tin is separated from cd and no evidence of a eutetic was noted. One of the granules contained zine and chlorine. The source of the chlorine is unknown. Since a SEM cannot detect oxygen, no quantative measurement of the degree of oxydation could be made. l l l l II-15
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_ 3 i Defect Opens Exposing Fresh Cd Coating Seals Open Defect and which will Sublimate Traps Vapor,Prchibiting Sublimation
. - l.i- [. Cd Va po r '
. . . ' . '
- Cd Vacor
[- i TCoating QMl__Cd0 "9} ( ,{/) rdo ( Cd W.@$"4:d@C e' i I Cd h Cavity Forms as Cd Sublimates Coating Restricts Oxide Crumbling _. . bN. f)Cd. Vapor '- . ,'.;,[t - Cd Vacor 0 - Cdo / &meine l
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c' _ Oxide Crumbles as Cavity Enlarm. ard Coating Limits lapsr Flow from Yt por Flow From Cavit) Increasss Cavity Thus Limt ting Sublimation T ' ga re. 9. Nucication end Grt:str. cf a Cavity. (Shown schematically along Mit f.ome po3siols benefits of surface coatings.)
!!~17
ESTIMATED DOSE TO fmP # 4-On February 5, 1988 FrP 4 4 , reenacted the opening of the l
)
topas on the reactor top. The total time of exposure was l approximately 46 seconds. Kmf d J estimated the hand dose to be 125 mrem beta and gamma i ' l and whole body dose to be 34 area beta and gamma. This estimate 2 is consistent with GP
- MS TLD and film badge readings.
Additional details on the estimate are contained in Gmp # 1's l memo. l l I l I l s i
- 1 l
l l l II-18 l
/ t, Georgia Institute of Technology J
,. 4 7 NEELY NUCLEAA RESEARCH CENTE A
'W 4 -
900 ATLANTIC CRIVE g / ATLANTA, GEOAGlA 30332-0425 February 12, 1988 MEMORANDUM
'IO : Dr. R. A. Macdonald, Associate Director NNRC FROM: R. M. Boyd, Manager, Office of Radiation Safety
SUBJECT:
Estimated Exposure to Bill Downs On February 5, 1988 FW P d 6; Df" Ik ^
- AT 4 4- 1.
witnessed a reenactment of the August 18, 1987 incident in which ErnP it 4 opened on aluminum outer can and cadmium inner can filled with topaz samples on top of the Georgia Tech Research Reactor. It appears that as this was being done the l top of the reactor was contaminated with Cd-115. AhnP tt 4_ demonstrated for us the method that he stated that he used to remove the topaz from the can. An estimate of the external dose was made based on this reenactment and from dose rate measurement that appear to have been present when the incident occurred. I estimated that the whole body dose to Go 9 4 4 was 34 mrem beta gamma and that his hand dose was 125 mrem beta-gamma. As a starting point the beta-gamma dose rate was estimated l to have been 15 rem /hr at 20 inches from the side of the can. Our written documents indicate that the dose rate was 3 rem /hr at 1 foot. However, this measurement was taken at approximately 1 foot over the top of the open lead shield with the can setting ; upright. (NOTE: Most of the radioactivity was approximately 8" j down from the top of the can.) It is not unusual for the l beta gamma dose rate to be a factor of 5 higher at a fixed distance brqad side to this can vs over the top of the can when it is in a shielded container with the top off of the shielding. Therefore, the higher dose rate was used. The time required for 6+a4to lift the can from the lead l pig, remove the topaz from the can, and return to empty aluminum can with the cadmium inner contrainer to the lead pig was d II-19 A ure d the urwn.ty symm e ceoga e cw gevey,oa w Emvormem ocoow, iau v ca i
approximately 46 seconds. Thirty seconds (30 sec.) of the period was at an estimated dose rate of 15 rem /hr or (250 mren/ min ) at a distance of 20' (tong length) from the can of topas. (250 aren/hr . 0.5 min = 125 mrea) Also 30 seconds of the 46 seconds was at a distance to the body of approximately 3.5 ft. at approximately 4 ren/hr or (67 arem/ min) . (67 mrem / min . 0.5 min = 3 4 area) . It is my professional judgment, after reviewing the facts that I have, that those estimates are reasonably accurate.
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- , - - - - - , - - - - - - - - , .-------n-------n--.r--
RECORDS This section con.. ins the records which were available or constructed during the it.sident. It also includes bioassays and a survey of G4vP du A '* apartment which were done in January i 1988. The Items Included Ater Power History and Experime- Status Logs of first topaz run ; Power History and Experiment Status Logs of second topaz run Smears f rom Air Handling Syst i Isotopic Analysis of Smears an ( s'mium Capsule Gas Monitor Charts Moving Air Particulate Filter Cha.it Kanne Chamber Chart Charcoal Cartridge Filter Analysis , Air Sampler Analysis Floor Surveys j Dose Rate Surveys Downs' Apartment Survey Personnel Data TLD's Film Badge l Whole Body Counts i Experiment Forms l l Memo's and Other Records i
)
( i Power Histor Prepared by:ygyg> of istg Topaz Run - 04/03/87 4 ; on January 26, 1988to 04/22/87 Date Time Power Lavel MWH Total MWH 04/03/87 0 h 15 m 1 Mw .250 .250 0 h 16 m 550 Kw .147 .397 O h 01 m 55 Kw .001 .398 0 h 11 m 500 w <.001 .398 04/06/87 1 h 30 m 1 Mw 1.5 1.898 04/07/87 4h 0m 1 Mw 4.0 5.898 0 h 46 m 600 Kw .46 6.358 0h 6m 60 Kw .006 6.364 04/13/87 0 h 20 m 500 Kw .167 6.531 0 h 18 m 50 Kw .015 6.546 04/14/87 0 h 37 m 1 Mw .617 7.163 0 h 47 m 750 Kw .588 7.751 0 h 29 m 75 Kw .036 7.787 04/21/87 0 h 22 m i Hw .367' 8.154 0 h 45 m 500 Kw .375 8.529 0 h 15 m 300 Kw .075 8.604 0 h 31 m 100 Kw .052 8.656 0 h 31 m 50 Kw .026 8.682 0 h 13 m 10 Kw .002 8.684 0 h 39 m 5 Kw .003 8.687 0h 1a 1 Kw <.001 8.687 04/22/87 7h 1m 1 Mw 7.017 15.704 19 h 54 n P e i i
GEOFCIA TECH RESEARCH REACTOR Chapter Procedurc 2012 4 Operatinj bg Approved Ol/2J/87 Experiment Status Latest Rev. 01/ 20/d7 Normal Operation Page 2 of 2 Rev. 2 Date /// #f [J 1 Completed By @ Facility Experiment CTRR Ref. No. WH Remarks v >/ Ewer Mua& 39P _ _ _ _ . _ _ _ _ l/-H bx U% . 3 9 h' p-l G ra) 1273s0 ./W _ _ . l
=
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Power Level Hours-Min Mi Time In _ Time Out ! ( 6t u.) - If .26 . 660V4) - )b , /t/7
.$bYN -
I oaoI htO - It
- M*1 for Day .396 Previods M for week O Total M forWeek to Date 39P Previous Total M41 /o/1v.971 Tutal Mi to Date /s /14. 49 /
General Notes: InclLX3e SCRM cause; asstne normal shutcom if no r.ote. R4 R 73T t t a t>-M ha #Ma - ene (t) PJ 27vzo % o -2 :
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GEOFCIA TECH RESEARCH REACTOR Chapter Procedure 201.2 4 OperatirN (49 Approved 01/ 2J/87 ' Experiment Status Latest Rev. 01/20/07 Normal Operation Page 2 of 2 Rev. 2 Date (!6 7 Completed By TO - Facility Experiment GTRR Ref. No. WH Remarks , U-at Toony R N O3- /.S~ A MF _ __ l/ -M (2ocx 12*N30@) /. s' u-M /2kk A7Wsdd / s' . Power Level Hours-Min $54 Time In Time Out MG \ 30 /d
~
\
l mit for Day / f" Previous M for neek 39s Total M for~ Week to Date /./ff Previous Total *11 /s/35.19/ , Tutal WH to Date M/PL DW ' General Notes: Include SCRAM cause; assume normal shutdown if no c.ote. IL us 17 tvtn K u.2 Lf 973vo u+M in v-M-
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1 l l GEOR3IA TECH RESEARCH REACTOR Chapter Procedure 2012 4 Operatinj lag Approved Ol/2J/87 Experiment Status Normal Operation Latest Rev. 01/20/87 l Page 2 et 2 Hev. 2 Date Al.f . V") Completed By b, pacility Experiment GTRR Ref. No. tW1 Remarks k{ f ro.A /275Go , t/66 _ WOI /2WDA- Y, Y66 -_& %sf fyay ud /2ocre 12 7430 f. 4% S. 9u . 1 Power Level Hours-Min M41 Time In Time Out
\W@ 4 -
/
ht6u@ -d ,e _ lphVU " N .004 M41 for Day Ndd Previous M41.for Week /, MP Total t*H for Week to Date /, .43/ Provlous Total fMi /ed4. M/ Total PhH to Date /e/.// _54 7 General Notes: Include SCRAli cause; assutte normal shutdown if no e,ote. Ormd MMSob b 0W
\um. 04 m - d i4 c'O boo k \hh6- Nih (2) 60VO \*4 - idio M booiM Mis- tw9 /s)
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b GEOECIA TECH RESEARCH REACr0R Chapter procedure 2012 4 OperatirN Ing Approved 01/20/87 Experiment Status Latest Rev. '.11/20/87 Normal Operation page 2 of 2 Pev. 2 Date i
/3 6f 7 Compl9ted By Facility Experiment GTRR Ref. No. bHH Remarks ll-( @ t ae.Q 273so , if* 2 -
U ') { TopA g 02?Vo3- e/Yb lo.bh V -> </ )?oee 27y3d4) .It2 - L . I49 l l l l Power I Level Hours-Min t&H Time In Time Out { Smm - 20 . /6 7 nov<> - IV , ots
- l I
t441 for Day . /82_ Previous FMI [or week cP Total tHi for Week to Date . /FL previous Total MWH
/a/4// 357 Total thH to Date forvi 639 i Ceneral Notes: Include SCRM cause; assune normal shutcown if no note.
M 40 - 160s r424 So M I bua - 1644 l
GEOR3IA TECH RESEARCH REACTOR C3 apter 4 Procedurc 2012 Operating Log Approved 01/20/87 Experiment Status latest Rev. 01/20/37 Normal operation Page 2 cf 2 Mv. 2 i Date // V d7 Completed By M Facility Experir. tent GTRR Ref. No. bhH Rec. arks HJ G r*& /27 % o a3
~~~
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% I(tA I04'1- litL W W2_ (It7- I l y '4 tm3 tytt, - l%3 mehem 6
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GEORGIA TECH RESEARCH REACTOR Chapter 4 Proceduro 2012 P Last Rev. 04-09-37 Operating Log Last Rev. App 04-09-37 Normal Operation Experiment Status page 2 of 2 Rev 3 __ Date '/
/!] ?_ _ Completed By: M __
Faci 1ity Experiment G'.'RR Ref. No. MWH Remarks _. V - 3 ( __ Tops 3 R940%- '
.? ___ __ __
' _ // -/ 5 Ten,_,_ R 77 t. ,03 __ _ _ _ _ _ _ _ _
._$1L___ _sLCN4/9 27M2- '00 6 _ .______ _
t/ 'l1 T&c 1272/O t01b red
# -/ g % > eo s , /273Go ,1\ \
__#-/ /bd (2__ R7352 . ld _ __ _As ?, cod / m, , S ,W ___ _
~~ -
_ _ _ . _ l l General Notes: Include SCRAM cause; assume normal shutdown if no ra te l G7V02.~~GnAs ikw a m_,e M- 9 7%2. t u M -! Annu D 27%o _Reo*l binL. c,kzte ' Amn) //% - 110(e '
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1
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- 3cc L IcotS-/426 Power Level Hours-Min MWH MWH for Date *f
/ &_A._) -
32 , 3/,7 Previous MWH for Week 6,o r<J _ __ [ ______ v4 e 379
, b v44 -
/C .079 Total MWH-Week to Date , 9__ ___
/ 4 a i<w - 2/ ,o63 44_F<J ._ - J / ,02h MWH for Date _
,f_______,
to K'W - j '3 ,003* _6RR 77 ,003 Previous Tota 1 MWH /6///,7, 779 __ _//H, - I '~~~ Tota 1 MWH to Date /0/d N
1 I i l GEORGIA TECH RESEARCH REACTOR Chapter 4 Proceduro 2012 e Last Rev. 04-09-37 Operating Log Last Rev. App 04-09-37 j Normal Operation Experiment Status Page 2 of 2 Rev 3 l Date //22/O __ _ Completed By: O Facility Experiment GTRR Ref. No. MWH Remarks _--- l 0 2l Kay /27,/02- p, oir _. tha Y Wem L?fuskur 7. ci v- ._
/ _ _ _ - _ - _
i
.-_-_-__-- l
- 1 General Notes: Include SCRAM cause; assume normal shutdown if no ho
_2?V01 + M14 ch422- rewa M __, _pa m(y _: 16y ' ~~~ ~ ~~~
~
~~~
Power
,_ __ Le v e l Hours-Min MWH MWH for Date 7 O/7
)Mc 4 4 7.0/7 Previous MWH for Week _ _2 jf ___ _
Total MWH-Week to Date_ Kf/7 MWH for Date _ 7, o e 7_ _ _ _ _ _ Previous Total MWH /CiV3. 6 97 __ __ __ Total MWH to Date /0/50,7/f_______.
6 Power Histor Prepared by:y of 2nd Topaz Run - 07/14/87 on January 26, 1988to 08/14/87
,. 8443 d 4 Date Time Power Level HWH Total MWH 07/14/87 3 h 31 ni 1 Mw 3.517 3.517 07/15/87 0 h 42 m 1 Mw .7 4.217 07/20/87 2 h 30 m 1 Mw 2.5 6.717
'0h 4m 100 Kw .007 6.724 07/21/87 '
0 h 22 m 1 Mw .367 7.091 0h 7m 100 Kw .012 7.103 0 h 16 m 10 Kw .003 7.106 , Oh 2m i Kw <.001 7.106 07/22/87 0 h 18 m 1 Mw .3 7.406 0 h 18 m 100 Kw .03 7.436 0 h 36 m 10 Kw .006 7.442 07/23/87 0 h 13 m 1 Mw .217 7.659 0h 6m 500 Kw .05 7.709 0 h 48 m 10 Kw .008 7.717 0 h 31 m i Kw .001 7.718 07/24/87 1 h 17 m 1 Mw 1.283 9.001 0 h 12 m 100 Kw .02 9.021 0h 7m 10 Kw .001 9.022 ; 07/28/87 0 h 11 m 10 Kw .002 9.024 ' 07/29/87 0 h 52 m 1 Mw .867 9.891 0 h 46 m 10 Kw .008 9.899
,07/30/87 4h 0m 1 Mw 4.0 13 899 1 , Oh 5m 100 Kw .008 13.907 3/03/87 0h 4m 1 Mw .067 13.967 0h 2m 750 Kw .025 13.999 0h 3m 500 Kw .025 14.024 0h 2m 250 Kw .008 14.032 0h 8m 100 Kw .013 14.045 0h 7m i Kw <.001 14.045 i 08/06/87 6 h 58 m i Hw 6.97 21.015 0h 8m 100 Kw .013 21.028 0h 5m 30 Kw .003 21.031 08/11/87 5 h 38 m 1 Mw 5.633 26.664 1 h 22 m 100 Kw .137 26.801 08/12/87 - 6h 0m 1 Mw 6.0 32.801 08/13/87 6h 0m 1 Mw' 6.0 38.801 1 08/14/87 3h 0m 1 Mw 3.0 41.801 !
47 h 31 m 1
Chapter GEORGIA TECH RESEARCH REACTOR 4 Procedure 2012 Operating Log i' Last Rev. 04-09-37 Normal Operation Last Rev. App 04 00-37 Experiment Status page 2 of 2 Rev 3 Date ///'/ / 7 _, Completed By: b Facility Experiment GTRR Ref. No. MWH , Remarks _.f! .69_ad A ?3 % -._
, 5?-1 _L u. r z..__ _
-H'
.f &, n - t h. v o n 3..G'?
&& 2n4- *
.i1 77 General Notes: Include SCRAM cause; assume normal shutdown if no note
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_ //_?/ - /8/20 ( 2L -(N
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__ /kd // 71 % _.
~
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Power LeVe1 Hours-Min, MWH MWH for Date J. O 7
/.[#f41._ . 3 & 7, 3.E P r ev io u s _MWH for Week (f)
Tor.al MWH-Week to Date .7. 5/~2
, MWH for Date '
f 3~/ 7 __ _. Previous Total MWH __
/d/M,/# " __
Total MWH to Date O/fd, 7/[ . 9
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. -. ~. -
GEORGI A TECH RESEARCH REACTOR
- hapter Proceduro 2012 4 .* Last Rev. 04-09-07 Operating Log Last Rev. App 04-09-37 Normal operation __
Experiment Status Page 2 of 2 Rev 3 ___ Date "J//,f[k ~7 _ Completed By: _ Facility Experiment CTRR Ref. No. MWH Remarks U ~AI _ T50% _
/2 7WO L*' ')
W"b Y $> c '<. J 739/ __
.0 _ __
_.__((c- - TC- 121> /0 t 0U i. 4 General Notes: Include SCRAM cause; assume normal shutdown if no note ~~
- O k 2.3.If! " U ~.22C_ __
\
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~ _.. ___
Power Level H o u r s- M i n_ . MWH MWH for Date < 7 __
////_qM - 9' 2.- ,7 Previous MWH for Week J.f/7 Total MWH-Week to Date be 2/7 MWH for Date ,2 _____ ,
_ _ _ _ _ Previous Total _MWH /d/fo.<.7/f _- Total MWH to Date /'//I/, //[
, _ , - - - _ , . - ~ ,
i GEORGI A TECH RESEARCH REAR' TOR 2hapter Procedur0 2012 4 Last R'e v . 04-09-07 Operating Log Last Rev. App 04-JG-67 Normal Operation _____ Experiment Statuu ><
,____ Page 2 of 2 Rev 3 e
Date 'O7/2p t-], __ Completed ay: y.' Facility Ex pe r imerit GTRR Ref. No. - MWH_ _ - Remarks ---. .. ...
-- t/-9f m gy R_m ,- _2.fb 9 OM- -- EaEbf.- -- -_ _ Eh.
d/ -/f~ t'd /27/'53 /
//- 15~ t/M? mas /27193 /
General Nott.G: Include SCRAM causo; assume normal shutdown if ne :g _ _ _ ,
-/.e u al to)- litc/ QO
.- /00 - # 3/ ( Q . -- -
..LLMd:_U Yh J.k)-
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' l
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- _. - ------.. l Power Level Hours-Min MWH MWH for Date .7. S~d ? - -----
.__ ZW c9- %)
d[ Previous MWH for Week . -_k - - .. .. .. . - - -
/#4/Ad .- -_--.___/._- -. d o '?
, Total MWH-Week to Date -- -- 2'3 62~ . - - - - . - - - - - -
l
\
MWH for Date J---------
.T'0 7 Previous Total HWH [f/ 9 /. 4/f __-
Total MWH to Date / #/ f d S R I 1
GEORGZA TECH RESEARCH REACTOR Chapter Procedurc 2012 4 Last Rev. ;14-09-37 Opcrating Log Last Rev. App M .)C-3 7 Normal operation _ ____Ekperiment statuu Page 2 of 2 Rev 3 , Date i C),/ _{J ___ Completed By: _ _ _ _ _ Facility Ex pe r imerit CTRR Ref. No. MWH Renarks tl * > \ TOpa} ._ L]4n v ._> 35 > _ _ _ _ _ - _ _ . . . _ _ . .
._ A_ G_ _ T_v__A_l _ _ .___- ___ _ s 5. t - . _______....... , !,
_~I_~d_
~_ __ ._ _f(.. C_ _ _ _ _R2Ato _ , oJ 3-
.-_N - l _Q raek /?7.560 .233
~
s + f__. _ _ _ _ . . . _ - _ . . I i l General Notes: Include SCRAM cause; assume normal shutdown if no r.v _.).y to Lg:2( - . _ /oo ~7 _ _(.t.) ' i p u.> /J~af- h~/1 ( V) # __ _ . __ ..
.l.q$2 I oM _ 't o b} is ) '* _. I a o n L A ll' . /f2 P d5) -_..__. .
_LQ%. ~__l9_4 9_ lO ' . 4 L . .'L* ' M - - - - . - . . _. _ _. _ _1. I 'Ma - I I *L o _ _ Un ' - f lg4 - 1I63 _ L 4) '
.2d it')&L3_" 4"W /?'l%d_m N-f LLYL_._l}Rl W '
_J %a -
-~
72/o
._LN w _LLoo ~_L41 _ _*g.f >f '
tw3 .Lvvr c u) / _ _ _ _ _ _ _. _ _ _ . _ _ _ . _ Power Level Hours-Min MWH MWH for Date , 3_ S '2. _ _ _ _. _ -
/N4I "
2L. . . Ne '/ Previous MWH for Week __8 - [dd/N """.".] , c/ t Total MWH-Week to Date e 3 / 1 _- __.____. 10 N ~ N i 00 7 M%H tor Date ild'2 '
~
__ __ _.A..__ __ Previous Total MWH M/ 9/,6/7__ ____
- - - - __ _ _ . _ . Total MWH to Date /4/ 7/, Yo /_ _ _ _ _ _ _
9
GEORGI A TECll RESEARCH REACTOR Chapter Procedure 2012 4 Last Rev. 04-09-37 Operating Log Last Rev. App 04-JC-S7 Normal Operation ______ Exper1 ment Status Page 2 of 2 Rev 3 __, Date o_f/Jy1t? Completed By: @ _
. Facility Experiment GTRR Ref. No. MWH Remarks --_. .._-.
V-2! 1~'pa.) /22Vo v .TM _----.-- ... 114
._ N & ~79 A. ---- ~ _ _ - -- ------ --. .
/-l - / S~ _.Ah _v 7+1.. R4'29/ =
, 002- .- - _ . _-_
N -/
@ rab - - - - Rf)Go - _ . //1 . 1.,---- -_- __---..
_ /f . /.f' /3f o t_ew_ /2 ?so 4_ . / 7F __ _ , _ _ _ _ _ _ _ _ , , _ General Notes: Include SCRAM cause; assume normal shutdown if ne t w '. s
/Dk4- 10.%l?.=/o.5Se' (d d / 0_ w j A 4 1. -- /_rs Y U) / ____. -...
l0_0L% //tr- sizi _ c n / ) cue /t. iu - ts, z t. On - _ _ _ _ . . _ _ _ . . .
.lO./M ' //47 - //_s~o D .),. d _ E2ar> ht;7-/4W ( 11 - _ _ _ . _ _ _ _ _ _ .
.----- Oto-Gir n 3_/ _
. .l.W. / M1_- !?s t (9 W . - __-----------.
LQQ M 140 f- /4/9 (8) / _ _ _ . _ _,, l lelM L4.%. - n21 CD' . -- - _ _ ---- ----. l
.---- L'ti.2.-- NCL- U) ' '
- l4!/ ~ LCr-- .L1). ' -- ---.
- If'Ji- 1431 O) V __ ___ -_____ __.
Power Level Hours-Min MWH MWH for Date L. fib--._---..
/ Wlx)
---- --~ /(_ ,5 Previous MWH for Week 3r L._ -----.
//d//4_)-
- / 03 Total MWil'.sek to Date . "// P' ,
[d/Al _ ' /_d -
, 004 MhH for Date ,JM __- .
Previous Total MWH / 0/f /.vo/ - -_- Tota 1 MWH to Date / o / 9/, 2/J. _ _ _ _ _ _ .
G EORG T A TECH RESEARCH REACTOR
' Chapter Procedure 201:
4 L a :i t Rev. 24.cy-37 Opcrating Log Last R e v . /s pp 0 4 ,10 -S 7 Normal;0peration Ekpertment Statuu Page 2 of 2 Rev 3 Date o7/p3h, __ completed By: @ _ _ __, Faci 1ity Experiment GTRR Ref. No. MWH Remark:1
._. _021.:_ ~7#Ad)_
- 41Yo1- . 176 __ _ _ _ . . _ - . . . .
.A. l L. T l/ & -
.216
--- H _ _-l ._@_rak --
itTw _ 2 i,
..Lt_o ----_. .......
l 1
.G e n e r a l N_o t t. s : Include SCRAM cause; assume normal shutdown if no ..,n ._ .L (W (> tit
- M[1_ fit).< /Ow__LTto --LD L f.L1w -_____. ..--...
../J2MW__/.cz6 - u n' fid2.'_-- _ /M 7 - /6V. "1- _ _ _ . . . . . . .JLuu) // o 2 = _ Lit V__Lt)__' _ _ i s< f - ISM C11 ' --_ _ ......
S Qc N _ _LL3 3 ~ tr B (<> '
._f NO --] .)l
- 1 t 51 (in ) ' _ _ _ _ _ _ _ . .
._f.atM __I161 '1353 to u _ .____... -- . _L':leL_'_f.Yt.o._..Q. 'Lv . _ _ _ . _ = __ __ _.. .__ . . .
_ . _ _ J US*- Ivw_ tsv
.- __tmeL_ H%. f.s 1 v = ______. _ .. . _ _ ifo2 _.t.rnf__41.Lv_ ____ __ _ _ __.._._ _ ..
Power Level Hours-Min MWH MWH for Date ,21.4-________. ,_ Mg /3_ . _, 277 Previous MWH for Week 7/J _ .____..
,fg;p_s_0__
" (,' , o f' ,99[
Total MWH-Week t_o Date __. l o v.O. _. - ff . , ed MWH for Date _., 17_4_.___. -- IN . ~~ O_.f _ ,40 / Previous Total MWH /o/9/,737 __ -_ - . _ . _ _ _ . _ __ . Total MWH to Date /d/ff , O/J a ._ _ . . - 4 4
)
GEORGI A TECH RF; SEARCH REACTOR Chapter iroceduro 2012 ' ' 4 Last Rev. 04-09-37 Operry.in? log LM t Rev. App 04-J0-3. Normal OJerati.ori _
.-n---- Sk pc;y_ icer; t Status ,
patie 2 of 2 Rev 1 --- Date i m/ g :.'o Nl e c e u B y : _'Y%--___- D . Facili:x* _. E .: p3 r it..e ri t. GTRR Re_f. No. MWK . Remarks V -21 '7 '
.- epa 2. _
R g y e 1-- f.Jo V _ - - - - - - - . - - - - . .
- 4ct- Wd.- __
-~~
--- f.h/
H*-----r-- IfW - __LI A.creas - 2.~7113 -
^
i?r-- . - --- ---...... 1 General Notes: Include SCRAM causo; assume norraal shutdown if ne tw a l.hu,L 912L fo +'s Ok M _
\
.LO.L.y.sd //02- //oL_ (D __
- /L24.~ 1/_1f L D- . __
IQ
-- - -- M.W - //'/7
. joy _u) ~
// h- l * //ff f d
\
---- ... l
.- - - - _ -__- l
.i - . . .
Power Level Hours-Min MWil MWH for Date - / , Td '/ --=- - - - _
. --[ h_ud. --
-. l l'7 . -_/,2 d . Previous MWH for Week -2g_s[_._- _---
t'D ' (OO _ -Q-
-.- l'). . , O 'y Total MWil-Week to Dato W 7,8#I (d.
-. - 'l -
, col MWH f_or Date .f.Jo/.---.
_ _ . - _ Previous Total MWH __ / o/ 94 4 /5 _ _ _ - - - T ,_ Total MhH to Date - /.#ff >. / / /
/ d/f S.} L Y w
s l l GEORGI A TECil RESEARCH REACTOR ! Chapter . 4 Pt'ocedurc 2012 l Last Rev. 04 ,DJ-37 l Operating Log Last Rev. App 04-J9_;7 l Normal Operation ___ _Ekper1 ment Statua Page 2 of 2 Rev 3 Date _ f_2l2. 7 _ __ __ _ Completed By: ,_%_ _ _ ,, , _ _ , _ , Paci1ity Experiment GTRR Ref. No. MWH Remarks I
.. 1
- _4_ _* \ __ ._TDPA f2No1-- -
, so t -
_0-IL_ Ple_mus ._@_~7[0 ' __ do v . _ _ _ _ _ _ _ _ . . . . . . , 1 _ _ _ _ _ _ _ _ _ . _ _ _ __ .__ __ _____________.. I l l 1 1 General Notes: Include SCRAM cause; assume normal shutdown i f rio .
~U~ ' "'# -
____ _______ l Power Level Hours-Min MWH MWH for Date , o_o 2____ _ _ _ _ _ _ _
. . . /O_lfg/_._ """ l i ., _
. i dO2. - Previous MWH for Week ___ ,_______,
_. .,_ _ _ ._ _ _ _ _ _ _ _ , _ To tal MWil-Week to Date ,an _ _ , _ _ , , MWH for Date .__ , 40 2__. _ _ _ _ _ _ . __ _ Previous Total MWH /0/hS 8M _ _ _
. _ _ _ _ . . _ _ _ _ _ . _ _ _ _ Total MWH t_o Date /d/9[ /_l_d __ _ __..
- ~ . , - .
^ Chapter 4
GEORG7A TECH RESEARCH CTOR REA Normal Operation Operating Log Ekperiment Ptoceduro 2012 atc 67 Statuu Las t Rev. 0 4-e)-3 7 J_"L , ___,_, _ , .. Last Rev. App 0.;-JG-J' Page 2 of 2 nev 3 Faci 1ity completed By: . Experiment h haL___ GTRR Ref. No.
._1ap4 3 _ MWH Perarks
_//-/I_' . ___47_% v G-if fle*fce_ ._dh hLa'ex .__R_ZAY___ _ _., 00 6 _y_ g]_ R 73W _________ Toer_. . R.*e*, l' I _J,tg.- __ __..
.K1 - .___ ____ ______. ,
General Notes: _ _ Nah$7bM' i64 Include SCRAM cause. __ __ _ __._.
.f2}chs Lk / Y'fo - (VlI 624. . l 'fje ' assume .._.._.
normal shutdown
. _____ 1420 ~ ikte (%)) .
if no n*;;. Power .______ _ ____ _.
'.evel _
Hours-Min __ MWil m ___ - MWH for Date 52 _ . 667 , 8 75 2(th ) " Yd f608 Previous MWH for Week ______. _ _ _ , 4:13_ Total MWH-Weekto Date MWH for Date A 7' 7 .. _,,,,,, , , , Provious Total MWH . - _. ,_s fr ,, , _ ,,, ,
/4/9f"$2/,,
Tota 1 MWH to Date
. /d/94. 76 /_, ,,,,, .
**'"%W4.h.A 8N g. .pt.hese e
D.m. m .
GEORGIA TECll RESEARCH REACTOR Chapter 4 P cceduro 2012 La:it Rev. 04-09-37 Operating Log Last Rev. App 04-J9-37 Normal _ operation __,__ _Skperiment status Page 2 of 2 Rev 3 Dato _ oj ) '"), _ Completed By: Q _ __ _,____ Facility Experiment GTRR Ref. No. MWH Remarks v-5t 70943__ (22% 1_. Wsoy .-- -_____-____
?l3 _ M .. - !2L'f ame
,144- #a_roA> ----__ /2 Orz _ def _ - . _ - - - - - _ _ _ . .
Aea. Awe OT I __ __ General Nott. G: Include SCRAM cause; assume normal shutdown if ne g_ _ _ , (2't4.2 ( A 47.-
. b r A n t o_ r um
. 200542 -Qt 0 # 12. ---_. .....
L?c w w s & R 2 W e usa _ @ v -!?ri Power Level Hours-Min MWH MWH for Date [#d8 f.f_ddyp4_ Y, .Y __ Previous MWH for Week ,3,Q ____-__
. fy_Y4/ ----- .""~_I _
.2#_d{ Total MWH-Week to Date Ngd_3
-- __ . _ - , MWH for Date Q df __,,,,
Previous Total MWH /o/94.'/oI _ ____ Total MWH to Date /4208. N _,___,,_
GEORGKA TECH RESEARCH REACTOR Caapter 4 Pt'ocedure 2012 Last Rev. 04-JV-37 Opcrating Log Last Rev. A p p 0.; ,10 - 3 'i Normal Operation ____ Ekperiment Statuu Page 2 of 2 Rev 3 Dato gf,3[Y7 Completed By: O __ __ l'acility Experiment GTRR Ref. No. MWH Remarks
- $-~ A_f.,_- JapA3-_ lENQ).' _ e 130
$l-l- - - - , SS0 ,W _ - - - ._ - - -
da F4 '.s - -
- mils Jeneral Nott.G: Include SCRAM causo; assume normal shutdown i, f r.o r., h
_]xD - U1h_UM
._ _ 11.11. - /n9' - .- _ _ _ h h a !d!5 __ ---_/EM-IDI __-- /.2*w LW3 - /W- .
Law J %% - r3S7 _ 7,3bA3.J 3M_- N dsb o N - /Ve
- . . . . l h_ vd_LY.#2 - _.
l
.LQOl!~ !@K- IVof-
-___- -.. \
Power Level Hours-Min MWil MWH for Date . / 3 1- _ , , _ _ _ _ , .
.lW _ _ _.__ -
,M Previous MWH for Week _ [ ,_______,
.-7_1_ "D hD _ - -
L .t Q }_ Total MWH-Week to Date . / 3 }' WM - 3 s0 L kW
- 3 -
,an6 MWH for Date r /37 ----.
k_ ~ h_ _Ak Previous Total MWH J n ? no_. lp. _ _ _ . - _
._ _~~ ]_ - Total MhH to Date /d200. M
GEORGfA TECH RESEARCH REACTOR Chapter Proceduro 2012 4 Last Rev. 04 i:9-37 O pc r a t ing Log Last Rev. App 04 .C-M Normal Operation Experiment Status Page 2 of 2 Rev 3 D tc 8 87 Completed By: _ Fac11ity Experiment GTRR Ref. No. MWH Remarks _,,,,,,,_ __0 *b l _ .
%kI k$8 l Wl# _ ___ --. ___. _- . i
_taL__ Roce R?y]oe __ j.m ._ ___ _________ _ y_-r/ ._ _R_ oc k __ _/_?__*?f&c _ b.M _ _ _ _ _ _ - - - . . _ _ . . . l 1 ___lt--- -_ 12.C__-_ _ 27=)/o_
,oo3 1
._'3_ _ _m_-_ Rf y _ 2 7 4 5_3 _4
=
.00 . _ _ _ _ _ _ _ _ _ _ _ _ _ . .
_ _ _.-_..---. 1 _ - _ _ _ -- = _ ___ __- .. . General Notes: Include SCRAM cause; assume normal shutdown if no '-,s _' Puf A280B_AuP_-44_0 M -Q9_oS _@p 21bois.u-2% M Mto N U-V3 --__..- ?
.-_ownese_Riaut___ ____ _ _ ____ ____ _ _ - - - _ _ _ . . . . .
10DKm. 0929 - 04.M W 01 % - 1634 Power Leve1 Hours-Min MWH MWH for Date /, uk$ _--__-____
._ .l _Mq)- _-._ b h_ . (f.47 Previous MWH for Week a.1 &-- __---.
-${. ( yd -I ... o f.1 Total MWH-Week to Date ~7 l k __ __-_.
s
- --- - -- .D. _ . MWH for Date f.M
_ _. Previous Total MWH /OZpo, W7 _____
.- -_____ ..__ _ __ __ Total MWH to Date, l 6101 S'A
GEORGI A TECil ItESEARCH REACTOR Chapter Ptoceduro 2012. 4 Last Rev. 04-J9-37 Operatin9 Lo9 Last Rev. A p p 0 4 - 0 9 - d '. Normal Operation ____ _Ekper1 ment S t a t u :.5 Page 2 of 2 Rev 3 Date 8 [/ d7 Completed By: - _ _ _ Faei1ity E x pe r ime ri t GTRR Ref. No. MWH Remarks _ . . . .....
--.-)(
U -
. '}.@6.J_ 2J_VO 2 - S. ') *7 __ ________........
_ V 41 ?oct _ _. ._ E z e So k __ - -.S 27 -. is.ots B. -IK__ Erhuum__ - _.!E2S'oW _ - MZ. __ -_.---_... ....
. b _'_I[__ tznzg.3g,_ _ 1273l_] __ . J.3[ _ _ _ _ _ _ _ _ _ . _ _ . _ .
General Nott.S: Include SCRAM cause; assume normal shutdown if ru n tc _LWw _A28YB - Lo%.__(.lk .nl ) _-. .-_. . It'lA _) (.I h 21 ) _l.O D X M _L O LhtLQ_-_.lLVR - I QJeNS__J ~% _ . . - . . Power Level Hours-Min MWH MWU for Date I '/Z.
. [M .6 JS. dfJ3 , Previous MWH for Week M__ .___-__-.
_/.8dS%.L. . _ _/ __ h. ../37_ Total MWH-Week to Date f.77_______ MWH for Date _ _ _ d ._7 2_ _ _ _ ., . Previous Total MWH /03o7.63.3 - .-- Total MhH to Date /4,2 / 7 f_d_]. - - -- .
GEORGIA TECH RESEARCH REACTOR Chapter Proceduro 2012 4 Last Rev. 04-09-3^ Operating Log Last R e v . A p p 0 4 - J ') - 3 'l Normal Operation Ekperiment Statuu Page 2 of 2 Rev 3 Dato 8//c"Ith'7 ___ Completed By: , Facility Experiment GTRR Ref. No. MWH Remarks U-dl 4,4 MWo 2 _ - 6 ___ _ ________. UOI - - E.wlt ' __22.1004- b fan.__________.. _ _ _ _ . _ _ _ lk__SD e. son _
-,o __ trb_ ______.. ____.
_=- _. _ __ _____________. General Natec: Include SCRAM cause; assume normal shutdown if ne
. .s ..J*.tC- Q823=P_Cao._ _-- ___ ___...__... .- J3fD.- /m_ = - _ ..... . . _ _ _ _____ = __ _________.
Power Level Hours-Min MWH MWH for Date f_,
../kLd d' _ ._ d Previous M'WH for Week _S__7'2__..____
~
Total MWH-Week to Date //,'J'/_________
=_ __ _ _____
MWU for Date ,_ _ / ______. Previous Total MWH /6.3 / 3._4_63_ . . _
. __ ____ . Total MWH to Date /0,2/9.do'3
GEORGIA TECH RESEARCH REACTOR
, .hapter Proceduro 2012 4 Last Rev. 04-d()_JT Operating Log Last Rev. App 0 4-J0-5
. Normal Operation Ekperiment Status Page 2 of 2 Rev a. _ _ __
Date- 8f/3k7____-_-__ _ Completed By: ._ __ . Facility Experiment GTRR Ref. No. MWH Remarks ,___,__,,,
._. \/ -A l 1 I b 1- b 3
V-M Poc_ br__ D3Qh J.d 2 2 _/f. /r___
. ._ AaVd. _' -- /27/33 /
{ I j
' General Notes: Include SCRAM cause; assume normal shutdown if no n .e __,
- JHud . />A_^w- //M . . ._-.-_. .. ,
_ __/377- /H[__._ .--__.._.__. l l 1
.______ =_ _ ______
-__ i Power Level Hours-Min MWH MWH for Date ( _ - _ _ _ _ _ . .
i i
._ _ _/_N___A_ .) [P ~_ . d . Previous MWH for Week //.7J Total MWH-Week to Date /7,77 MWH for Date d, Previous Total MWH / O .2 / 9 /, 0.3 _ _ _ .,_
.= .- _ -___, _._
Total MWH to Date [d M N do_._I______ t
1 G EORGI A TECH RCSEARCH REACTOR j Chapter Ptocedure 2012 4 Last Rev. 04-09-G O pe r a t ing Log Last Rev. App 0 4-09-0. Normal Operation Ekperiment S t a t u :.4 page 2 of 2 Rev j ___ Date 8_ // f 7 Completed By: M_ _ _ _ _ _ Facility Experiment GTRR Ref. No. MWH Remarks V-at ._%py___ l273o 1.- 3 ____ __..__.. ....
._ VQ. I **M.,___ ._Sl_YS0_Y __ _ ._ ___ ____... -. .
. _ _ _ _ .. = . _ _ _ . . . . . _
General Note.s: Include SCRAM causo; assume normal shutdown if no :. 3_ ,_,
.-Lold__._t2P.2.5-/123._ __ -_. ..... .
_ _ _ - _ _ _ _ _ - - -= _ _ _._ __ . _.___.______. Power Level _ . Hours-Min
._ MWH . M_WH for Date ___8________... ._. ]_M_ t4) . - __ 3 , . _ m2 Previous MWH for Week /7.77 Total MWH-Week to Date 2",7______. )
MhH for Date _ _3___.____ , l _ __ _. .Prevlous Total MWH / p 1 2 T~ 4_d 1 -__ I _ _ . _ _ . Total MhH to Date N888' N ________
1 1 1 l i GEORGI A TECH RESEARCH REACTOR hapter Ptocedure 2012 4 Last Rev. 04-6!!'-J7 Operating Log Last Rev. App 0 4-09-3 ' Nornal operation _---_- Ekperiment Statuu Page 2 of 2 Rev 3 -_-- Date - O& g N __ Completed By: .-- - . 1 1 Facility' Experiment GTRR Ref. No. MWH Remarks ..--____. , I l
--_ _ - - -___ .. .... l l
1 i 1 i
- - - - - - - - ___ __ _ __-- _________. i
- - - - _ _ - --_ _- -- ._ _ ____......... 1 I
( - -- . -_--._-- .
- General NotLS; Include SCRAM cause; assume normal shutdown if no nutt ~~~
- NO i, 6 _-__ - . - ---..._--
- _____.-_. . l
-Pu.Gr4 2_2.Ye2 + 2 713o J .1I 1
_.- --_- 1 --
- .r .
- - - s~~ .
1 _ l g J'. _1.:. . u 1 l
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, -3 g. Ay I l
~. - .2 - 7 L. = _ .. : :x -m _ _ - _ _ _ . !
e .. - x .
.L g_ ;. ... .5.g m _____ _,,
- -- 3 pr. 1 - ,
Power -.
+ L* * #% ..
- 3. -u - % :q -- -- _gy l
_ Level _ HWufs Mint.JG MWH MWH fo'r#Da d _
- 4. _ , w O E Previ"6us MWH!for Week
.,...~_
1-Total MWH-Week ~ to Date __..__- i
- MWH for Date _
- -- _ k b
* "* ,Previ6ss' Total MWH /0 2 2_F. do 3 -
.-------- . - - - - - . . __ . Total MWH to Date - _ _ _ _ - - - - -
SMEARS FROM AIR HANDLING SYSTEM To evaluate the possibility of the cadmium residue being small enough to become airborne, a thorough survey of the building air flow was made. Figure III-1 is a schematic diagram of the containment building air handling system. i l The main air handler combines fresh and recirculated air which is discharged across the reactor top. Exhaust air enters intake grills just below the~ reactor top. Immediately below the t j l reactor top is a ; plenum area in which actuators for the l regulating rod- and experiment port shutters are located. ) Exhaust. air . flows through the glenum and into an exhaust duct.
.x v
~ '
All air which ieaves the butiding is continuously sampled by a
~
s - gas monitor, MAP l, Kanne Chamberycind ,cparcoal filter. All W 2
~
exhaust air _ must pass by" these__ instruments and through the
% - W. L 2hr building air filtgrE .~ _ r.:c i - @g. , .
W LMid~'Bqi 4 - - . = =
- .y -
>U !Q* , , _. C
.(. vE The recorders for the gas monitor, MAP-1, and Kanne Chamber showed no evidence of unusual radiation levels. The particulate filter in front of the charcoal sampler was normal. Further test smears were taken from the main air handling intake 1
louvers, the intake grills, and the air plenum. In addition sections of the prefilters were cut out and analyzed. l l
Smears of the reactor side and entainment building walls were made and counted. Analysis of these samples was done on February 1, 1988. One hour counts using a GeLi detector and a Nuclear Data 6700 gamma spectromoter showed no trace of any isotope of cadmium. Smears from the cadmium capsule and the aluminum can showed both Cd-109 and Cd-115m in the amounts of 10 microcuries. 1 Our conclusion is that any particulate matter which spilled was too course to become airborne. Inhalation of any particles by NNRC personnel is unlikely. 1 l g * - vg - 2 _r* f.
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\ u GEORGIA TECH RESEARCH REACTOR O* COA D'U CON T A !M As s:a r ,1 wm w l=28.& Vu'N ! !L A T104 '
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Figne III-2 I uous
TO: DR. R. MCDONALD FROM: D. COX
SUBJECT:
CADMIUM SURVEY IN CONTAINMENT BUILDING VENTILATION PATH DATE: January 26, 1988 Monday, January 25, 1988, the ventilation path of t reactor containment building was sampled using canvas pat:
"swipes" and sections cut 'm the roughing pre-filters that wc in the containment buildt .ilter bank.
' Swipes 1 thru 4 and 7 were taken on two of the louver st4 of the five intake air grills around the reactor pedestal. 1 area of each slat was 11 3/4" x 3/4". The effective area swig-was 10 1/2" on each slat or about 100 saem.
Swipe number 5 was taken above the regulating rod dri' motor in the with an "S" motion of about a meter in length. Swipe number 6 was taken on the floor of the air passa! near the operators for H-7 and H-6 in the one meter "S" motion.. Swipes 8 and 9 were taken from one stat near the center! the intake louvers of the main air handler over the control roc < Each slat is about,48" long and 3/4" wide or about 230 sqcm. A section from each pre-filter was taken from an u obstructed spot near the outer quarter of the filter. 1 section of the filter was sealed in a poly bag and an image q
] made on a photo-copier with two scales to f acilita te at:
calculation. The filters and a new filter were photographed 8d show the approximate location of the sectioning and a new filt' gQ for comparison.
)
Sh N "Dk The following swipes were taken from the aluminum cl containing the cadmium can and topaz stones. l
) q}y)DTS . 1 (A) Aluminum can
, 2 (B) black material in aluminum can s :
' '? 3 (C) chunks from bottom of Cd container 4 (D) Cadmium can 5 (E) dust off topaz i
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GAS MONITOR The gas monitor continuously samples the main exhaust air l just after it has passed across the reactor 4 top. The trace on following pages are annotated to show the events from August 14 through the beginning of the cleanup on August, 19, 1987. The chart reads 0 to 1004 with full scale set at 50 counts per second. This recorder is turned off when the reactor is not operating. The monitor is able to detect gamma radiation or energetic beta particles in the air stream. No unusual activity was noted when the recorder was turned on the morning after the spill or during cleanup.
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