ML090920467
| ML090920467 | |
| Person / Time | |
|---|---|
| Site: | 05000017 |
| Issue date: | 04/01/2009 |
| From: | Industrial Reactor Labs |
| To: | NRC/FSME |
| References | |
| FOIA/PA-2009-0104 | |
| Download: ML090920467 (226) | |
Text
VOLUM1E ITI\
UPPLEMENT TO RPR FINAL SURVEY, RESULJTS AFER DECONTAMINATIONW SINDUSTRIAL REACTO LAIAORE-o __6
'FACILITIES,-.-
PLAINSBORO, NJ N'
COPY NO. A0 VOLUME II SUPPLEMENT TO REPORT Final Survey Results After Decontamination Industrial Reactor Laboratories Facilities, Plainsboro, New Jersey February 28; 1977 ATCOR, INC.
Peekskill, NY (This Copy Supersedes All Previous Reports)
Prepared By:
Industrial Reactor Laboratories Inc.
Plainsboro, NJ 08536
TABLE OF CONTENTS PREFACE - USNRC Letter, February 10, 1977 Docket No.: 50-17 USNRC QUESTION APPENDIX TOPIC ANSWERED As Potential Biological Pathways for Soil and Ground Water Contamination.
B, Ambient Gamma Exposure Levels. 2
- 1. "IRL Ambient Radiation Survey".
- 2. IRL Radiation Zone Plant
- 3. ATCOR Supplement, "Radiation Levels Expected After Backfilling the South Corridor Excavation" C, Base Line Environmental Information. 3
- 1. IRL Environmental Summary Report to TRL Safeguards Committee 25 October 1974; Industrial Reactor Laboratories, Inc., Health Physics Department, Hotte, E.D., M.S.
- 2. Six Year Summary of IRL Environmental oq-iiEor----ng Data 1-959--65, Industrial Reactor Laboratories, Inc., Report No.
TSP-23, January 1967, Pelrine, J.R. and Fetzko, G.
- 3. Environmental-Radiological Surveillance Program; New Jersey State "Department of Environmental Protection, Division of Environmental Quality, Bureau of Radiation Protection, McCurdy, David, Ph.D, Radiation Protection Laboratory Director, Russo, John T., Chief, Bureau of Radiation Protection.
- 4. 1971 Environmental Radiation Levels in the State of New Jersey; New Jersey State Depart-ment 0-E--vironmental Protection, Division of Environmental Quality, Bureau of Radiation Protection, Laboratory Section.
- 5. Berm Area - Supplement to ATCOR Basic Report 3
Page 2 USNRC QUESTION APPENDIX TOPIC ANSWERED D, Analysis of Leaching Field Radioactive 4 Contamination. ATCOR Supplement, "Estimate of Radioactivity in Leaching Field".
E0 Expanded Data to better define total 5 curie quantities in soil.
- 1. ATCOR Supplement - "Estimated Quantity
'.,--of Activity Remaining in the South Corridor".
- 2. "Report of Failures in the IRL Radwaste System Piping", Leter, August 30,,1976, to L. Norrholm, Region I Office of Inspec-tion and Enforcement, King of Prussia, PA 19406, from industrial Reactor Labora-tories, Inc., Leigh, D.W. Decommissioning Project Manager.
F, Additional Water Sample information to support 6 conclusion that water contamination is not a problem.
- 1. See Item (2) in APPENDIX E.
- 2. ATCOR Supplement, "Supplemental, Environ-mental Radiation Surveys".
a) Report of Analysis Run Date 11/15/76.
b) Report of Analysis Run Date 1/21/77.
- 3. ATCOR Supplement, Facility "B-Waste" System Piping.
- 4. ATCOR Supplement, "South Corridor Water Analysis".
- 5. ATCOR Supplement, "Supplemental Environ-mental Water Surveys".
- NOTE: This report also contains information which expands answers to questions: 1, 3,-6 and 10.
- NOTE: This report also contains information which answers questions: 1, 4, 5, 7, 8 and 11.
Page 3 USNRC QUESTION APPENDIX TOPIC ANSWERED Contamination Problems of any piping 7 left in place.
- 1. ATCOR Supplement, "IRL Septic System:
- 2. ATCOR Supplement, "Al Piping Runs -
Reactor Pool to Valve Pit".
3.. ATCOR Memo, August 9, 1976, "Reactor Pool Low Gutter Drain"
- 4. IRL Memo, October 8, 1974, "Consequences of Leaks in theý Reactor Primary System During Normal Operation".
H, IRL Assumption that potential SR-90 contamina- 8 tion of walls and floors is not a problem.
ATCOR Supplement, "Isotopic Analysis of the Surface Contaminant".
USNRC Question 9 is responded to in the Amended 9 Report, Volume A of this submittal.
I, Demonstrate accordance with ALARA philosophy. 10
b) Expenditures to date.
c) Estimate to remove remaining activity.
J, Leach samples of water from formerly radio- 11 active tanks.
ATCOR Supplement, "Radioactive Waste Tanks Leach Test".
PREFACE UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 10, 1977 :FLý LWRS 6 1977 Docket No.: 50-17 Industrial Reactor Laboratories, Inc.
ATTN: Mr. David W. Leigh Project Manager Plainsboro, New Jersey 08536 Gentlemen:
By letters dated November 26, 1976 and December 7, 1976, you requested termination of Facility License No. R-46 and Byproduct Materials License No. 29-03686-02 following dismantling of the Industrial Reactor Laboratories facility at Plainsboro, New Jersey. During our review of your applications for license termination, we determined that additional information was required. .The information needed as discussed with you is listed in the enclosure..
Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Request for Additional Information
I REQUEST FOR ADDITIONAL INFORMATION INDUSTRIAL REACTOR LABORATORIES, INC.
REQUEST TO TERMINATE jl LICENSE NO. R-46 (POSSESSION ONLY - REACTOR LICENSE)b 1.. IRL should analyze potential biological pathways for soil and.
I ground water contamination. Sr-90 and Cs-137 in particular should be analyzed in detail-as they are the most limiting isotopes. The report should include site geology and relate ion. exchange properties of the soil and movement of radioactivity i .- from the soil to ground water. Estimates of maximum individual and population doses should be made using conservate pathways
' . to man, e.g., drinking water for milch animals.
.2. Ambient gamma exposure levels should be addressed for each area of the facility. These measurements should generally be made at three feet above the floor.
- 3. Base line environmental information should.be expanded. What were environmental radiation levels prior to plant startup?
What are environmental radiation levels in this general location away from any potential influence by plant?
- 4. Provide a comprehensive analysis of leaching field radioactive S .contamination.
- 5. Expand data and analysis to better define total curie quantities
-i. .in soil.
6.. Additinnal water sample information is needed to support 1:he conclusion that water contamination is not now a problem and will not be a problem in the future. If additional water sample
. . data is available in State of Mew Jersey reports, include that El;..*," data in the IRL submittal. Samples of leach field water should be included as well as base line environmental-control sampl1es.
- I* : :*
+-im, " "" *'.,.
I. -
Ir
.! 7. Discuss contamination problems at any piping left in place, e g. , sewver ,pi ping.
eý
- 8. Include specw ra a.;l,, sis data to support IRL assumpti6n that potential Sr-90 cot aiin ation of walls and floors is not a
. !probl erm.
.9. The reported results of the radiation surveys should be adjusted for background. radiation. As now written many of, the surveyed grids have randatio~n levelsabove the IRL maximum. facility release specification cf ",13 mr/hr (pg. 3 ofreport).
10 .T...L sh"- di; ...... C that leaving 1-hn remain n: r t ad . c t v"
- material in e - is In accordance with the ALARA oh ii" L.:cavati osophy.
In demonstr.ating that leavingi the remainingradioactive mris in the excavationj is in acoordanc- with the ALA,/A philosophv, t,.
licensee may considerý the economic impact and the potential radi ,ticn dose to the individals performing the excavationJ. for each aiddii-incremental removal of radio,-_ctive materials; versus the enviror,me-al benefit derived from the addit-ional increm,,ntal removel o" radi.t
' Mdter i I s.* *.
- 1. Leach s".;i:il_'; of I"ater ,- .'c fo .er!', rad c ctive .,n_ s shou'd
- be .a ilyacl for rdi onuc! cic ui n 1 jr-90.
APPENDI-X A Potential Biological Pathways The following hypothetical pathway is presented in answer to question l.
The dose resulting to individuals or population groups from this pathway can never be exceeded by any other reasonable postulated pathway includ-ing vegetation, milch animals, meat, etc. Thus, if doses calculated via this pathway are less than maximum permissible doses, the calcu-lation of doses via other hypothetical pathways becomes moot.-
(1)
The MPC values for a radionuclide are applicable to a 50 year exposure period and imply intake at these values for 50 years. Since no additional release of activity will occur, the concentrations will decrease with time because of radioactive decay. It is reasonable to assume that persons drinking water at the IRL site will be working rather than residing at the IRL site so that their daily intake of water would be 1/2 of the value for continuous non-occupational exposure. The intake, I, of a person drinking water from the water taken at concentrations equal to those observed in the stagnant water sample corrected for radioactive decay, only, may be calculated for a single radionuclide.
a a* P, where Co = initial activity concentration of a particular radionuclide in the stagnant water sample, .Ci/ml Fw = volume intake rate during a working day = 1/2 FD, where FD = daily volume intake rate.
t = exposure period = 50 years.
A maximum permissible intake of a particular radionuclide P, for an individual in the general population may be calculated:
P =MPC FD t =MPC ( 2 Fw)t.
The fraction f of the maximum permissible intake that I represents is obtained for the quotient.o I by P:
(b)RR
- (1) RE: ICRP Report #2 (1959).
For all of the radionuclides present in the stagnant water sample the total fraction,* ft. ofmaximum permissible may be calculated:
Radionuclide Co. MPCq i f 54 1.59 X I0-7 1 X 10-4, 8.09 X 101 1.97 X 10 n6 5,-
6 0.Co 5.22 X 10 X210 l1.31X.10. 7..96,X 10 137Cs 2.5 X 10-7 2 X 10-5 2.30 X 10-2 3.71 X 10 900. 7.2 X 10-7 3 X 10-. 2.40 X 10-2 0.70 4
= 7.12 X 101 (2) See Appendix F, Item 4, Table I, Page 1.
Actual exposures would be considerably less than maximum permissible for the following reasons:.
- 1. Wells in the area are at a minimum depth of 30 feet, while the above calculation was at the depth of the stagnant water sample at a depth of 12 feet.
- 2. Thus, wells are located normally below the clay strata which would greatly limit the migration of radionuclide and their final concen-tration at the intake of the well point due to the ion exchange capacity of the clay type soil.
- 3. No horizontal dispersion is included in the calculation.
- 4. No dilution by-uncontaminated ground water is included.
- 5. No decay in transit from the contaminate site to the well point intake is included.
- 6. The probability of anyone placing a well point at this location is extremely small since (1) there are two deep wells on site that yi6ld a plentiful supply of potable water:, (2) the site is inside the
building, (3) the site is within 200 feet of the septic/leaching field, and (4) for such a well to serve a residence, the existing building would have to be razed.
APPENDIX B I
I I
I I
,I I
I I
I I
I I
APPENDIX B IRL AMBIENT RADIATION SURVEY DATA This information answers Question #2 in the enclosure to .USNRC letter to IRL, Inc., (Docket 50,17),dated February 10, 1977.
BACKGROUND DETERMINATION MR Scatter Chambers Landsverk Model 120 were used to measure background and to calibrate the eberline model E-120, with 190 probe, G-M survey instruments which were used to perform this survey.
Table 1 contains observations made at Rutgers University, New Jersey.
Table II contains observations made at IRL, Inc., Plainsboro, New Jersey.
TABLE 1 Landsverk Model 120 Scatter Chamber observations at Rutgers Univer-sity, New Jersey.
22 Hour Exposure (Cave)
Background Background Chamber No Serial No. MR I IP/HR MR MR/HR lA.
126 0.235 0.011
- ,163 0.96 0.044 114 0.11 0.005 3 219 0.46 0.021 4 S ,177 0.71 0.032 5 187 -0.12 .0.005 6 213 0.26 0.012 7 164 0.74 0.034 8 '196 0.085 0.004
TABLE II I Landsverk Model 120 Scatter Chamber observations at IRL, Inc.,
Plainsboro, NJ. _
- '-*:Background,.
Chamber No. Serial No. Location MR/HR 5 157 Reactor-- 0.044 Pool 2 8 196 .Reactor--Pool 1 0.040 2 11l4 *Gt 0.018I
- Gate located 1000 feet S.W. of the Dome at the intersection of Shallow Brookand the IRL access road.-
AMBIENT RADIATION SURVEY Figure I is the record of an Ambient Radiation Survey conducted at IRL, Inc.,-Plainsboro 2/17/77.
NOTES:
- 1) Units of measure are MR/HR observations of Meter Readings I and therefore include background.
- 2) All readings are less than or equal to valves-shown. .
- 3) Ambient Background.was observed to.be 0.02 MR/HR at the Gate which is located 1000 feet S.W. of the Dome at the inter-section of Shallow Brook and the IRL access road.
- 4) All measurements were made at an elevation of three feet above, the floor/ground surface where it was made.
- 5)
- Radiation Readings above open excavations which will be back-filled and will have concrete floors replaced.
- 6) **Surface Reading of some soil which was removed from the excava-tion north of the waste evaporator building. This soil will be returned to the bottom of that excavation and into the 10K waste tank basin.
I
-m.*m-'= :-:m --.
- m INDUSTRIAL REAJCTOR LAB RADIATION .. ZONE PLAN AMBIENT RADIATION SURVEY 2/17/77 w
BA!FNT LI' EL EE WASTE OUSE STORAGE 7T~~GP4 U~
ROW2.
LOCATEDON AN 600 FT.
RADIUS CIRCLE WITH REACTOR DOME AT CENTER SAM,.
CaEu.A.'
INDUSTRIAL REACTOR LAB RADIATION ZONE PL AN SGATE WASTE HOUSE STORAGE
]
Radiation Levels Expected after Backfilling the South Corridor Excavation The "B Waste" system piping failed and released quantities of activity into certain defined areas within the IRL facility.
The quantity and degree of activity at each failure was as-sessed and the largest fraction of the released activity was removed, packaged and was disposed of as radioactive waste.
Each excavation was analyzed and it was determined that the south corridor was -the worse case due to the quantity of activity remaining , location in which activity is confined, and the resulting radiation dose rates.
To further assess what conditions would result if the ex-cavation was backfilled, it was necessary to anticipate the highest exposure which could result due to replacing ten (10) feet of earth over contaminated soil that has a contact radia-tion dose rate of 0.8 millirem per hour (mr/hr.)
The radiation will be reduced due to geometry and shielding factors as shown below.
Geometry Factor Using ORNL DWG 67-11653R1, "Ratio of Dose at P to Dose on the Surface Based on Cosine 2 Flux Distribution on the Surface",
determine -the ratio of dose at P to dose on surface.
Rp P
R = 13 feet H = 6 feet, width of corridor W = 8 feet, exposed source length N-S direction P = point 3 feet above hall floor after backfilling ATCOR
Geometry Factor (continued)
The ratio of dose at P to dose on surface is 0.12.
Shieldin7 Factor Using shielding of ten (10) feet of earth at a density of 1.8 grams per cubic centimeter, calculate attenuation for 0.662 Mev gamna rays. From APEX-176, "Miscellaneous Data For Shielding Calculations", Fig. 1-7 Mass Absorption Co-efficients for Aluminum, the mass absorption coefficient used for -this calculation is 2 7.7 x 10-2 cm 2 per gin.
= 7.7 x 10-2 cm x 1.8g gm cm3
= 1.386 x 10-1 cm-I X 10 ft x 12 in x 2.54 cm ft in X = 304.8 cm A'X = 1.386 x 10-1 cm-I x 304.8 cm
,,aX = 42.24 e lux = 4.52 x 10-19 The shielding factor is B
- e-7Qx where B is the buildup factor.
From reference APEX-176, Fig. 11-13, "Dose Buildup" Factor in Water for a Plane Monodirection Source", the B was deter-mined to be about 3 x 102.
B'e-Axx = 3 x 102 x 4.52 x 10-19 B-e-aX = 1.36 x 10-16 The combined factors tending to reduce the radiation from the contaminated earth is the product of the geometry and shielding factors.
A.F.= (0.12) x (1.36 x 10-16)
A.F.= 1.63 x 10-17 It can be concluded that the dose rate level of 0.8 mr/hr from the contaminated soil in the south corridor excavation will
_ -r::
A r
Shielding Factor (continued) contribute 'to the general area exposure after backfilling an additional radiation increase of 0.8 mr/hr x A.F or 1.304 x 10-18 mr/hr.
Measured natural background in -the IRL facility is 0.04 mr/hr.
This increase is not measurable.
All calculations were made using assumptions such that the results stated above are conservative.
A -T-,- /-\ r-)
APPENDIX C TO: D.W. Leigh FROM: E.D. Hotte DATE: 25 October 1974
SUBJECT:
Summary of IRL Environmental Analysis Because of the uncertainty of radionuclide movement through the environment, any environmental monitoring program at a reactor site must be initiated with an understanding of the climatology and hydrology of the area. It is for the reason that comprehensive studies of the climatology and hydrology of the IRL site and sur-rounding area were completed in 1959 by Thornthwaite Associates.
The study on Pollution Climatology was prepared to determine pollution hazards in the event of an accident in the reactor.
Primarily, it examines those meteorological conditions which would interfer with the rapid dilution of contaminants in the atmosphere, but the report also summarizes seasonal variations in the weather.
For example, the data available on prevailing wind directions would be useful in an air sampling program. The seasonal wind directions are shown in Fig. 1. While northerly winds prevail during winter months, it is the south westerly and westerly wind which dominates through the remainder of the year. It would be these wind direc-tions which would be taken into account when organizing an air sampling program today. The same would hold for any surface water or soil sampling done for the purpose of looking for particulate radionuclides which are daughters of gaseous fission products. A second study of the climatology was completed by Huston in 1965.
It confirms Thornthwaite's earlier report.
Another important aspect of climatology is the'water balance.
A detailed picture of the moisture relationship of the Plainsboro area is needed to understand the movement of contaminants in the environment. Precipitation alone does not tell whether a climate is moist or dry or whether there will be ground water storage and stream flow. It becomes necessary to consider evaporation from the ground and transpiration from plants to produce an accurate picture of the water balance. Fig. 2 is a graphic representation of the water balance for a full year for the region around Hightstown.
While precipitation is quite uniform through the year, the wettest months are July and August and the driest is November. On the other hand, evapotranspiration is distributed quite differently. In the winter when temperatures are below freezing, evapotranspiration is negligible. As temperature increases, it rises, until a maximum in
" 2 -
mid summer and then falls again.*. During the winter, precipitation.
is greater than evapotranspiration and there is a surplus of water which recharges the ground water. With the spring rise in evapo-transpiration, it soon equals precipitation and by.June it is greater than precipitation. As evapotranspiration continues to in-crease in July and August, more-demands are made on the stored soil moisture and ground water levels fall and stream flow decreases, In the fall, evapotranspiration again drops below precipitation; the soil is recharged and a surplus becomes available for stream runoff...
During the winter months, with an excess of water, any release of contaminants would quickly become dilute because of the large volume of water present in the soilý. In the summer', any effluent
-- from the reactor would rapidly sink into.the soil and be held there, it would neither reach the ground water table nor the nearby streams.
The movement of water through the soil is poorly, understood.
When the soil moisture content is below field capacity, all of the water in the soil is held in the capillaries between soil particles.
There is virtually no movement of water vertically or horizontally in the soil. It is only when the moisture content is above field capacity that movement of water can occur. The velocity of this movement depends on the porosity of the soil and the slope of the soil layers in which the water is flowing. Because of the relative flatness of the terrain in the Plainsboro area, the ground water gradient towards the streams is very-gentle. With the porosity of the soil close to 40 percent, it can be determined that for the first of any applied water to travel 200 feet underground to the nearest stream would require a period of about a month. It is reasonable to assume a rate of movement of water through moist soil of no more than
.10 feet per day. In the summer, with dry soils, there would be no ground water flow, and any water added to the soil would be used by vegetation or held in places in the soil until enough water has been added to moisten the soil above field capacity.
Taking all factors of climatology, hydrology and geology into consideration, it would seem reasonable to institute a monitoring program which concentrated on vegetative and soil sampling during the summer months when contaminants would most likely be held in the soil and stream sampling during periods of field capacity.
The Six Year Summary of IRL Environmental Monitoring Data 1959-1965 (TSP 23) is the result of an environmental monitoring program initiated in 1959 to determine any significant increase in radio-activity concentration levels due to the operation of the IRL reactor.
Primarily the data shows fluctuations in radioactivity concentration levels which resulted from fallout. Through the 6 year period,.
changes in both the scope and sampling frequency occurred. As, of 1965, a modest program consisting of a routine air sampling program, weekly analysis of collected stream samples and semi-annual collection of vegetation, mud and soil samples was carried out. The reduction of the monitoring program to that level was brought about as more and more experience showed that operation of the reactor produced no measurable effect on the radioactivity concentrations which-exists in the atmosphere. Continued environ-mental monitoring today would then primarily serve as a safety check that.no accidental release results from normal reactor opera-tion.
The one exception to this is the controlled release of con-taminated water to the berm. The present use of the evaporator.
to process all liquid waste prior to discharge to the berm has greatly reduced radioactivity concentrations. However, it might be suggested that frequent water samples be taken from the berm to ensure compliance with release limits.
The Bureau of Radiation Protection of the New Jersey State Department of Environmental Protection conducts periodic radiation surveillance programs in areas surrounding several nuclear plants*
in New Jersey. A moderate surveillance program has been maintained in the Plainsboro area since 1970. Surface stream, vegetation, bottom sediment and potable water have been included in the state's sampling program.
Fig. 3 is a map of the Plainsboro area where collection stations are located. Stream samples were taken at two areas along Devil's Brook. These are of particular importance because the reactor site is situated between the two streams. Samples are tested for gross alpha, beta and gamma emitting nuclides throughout the year. Water samples are also analyzed for tritium, strontium 90 and several other fission products.
Six local farms submit agricultural produce including corn, wheat and barley. Radionuclide concentrations appear to be consistent with expected concentrations in whole grain produce.
Surveillance of nearby water supplies was also undertaken because of the possibility of seepage of radionuclides from the berm area into adjacent municipal ground water supplies. Five'water companies cooperated with a mail-in-program. The investigation showed the potable water supplies to be within annual average per-missible drinking water concentrations as stated by the U.S. Public Health Service.
-4 -
In general, the state's surveillance program further supports the IRL environmental monitoring program results. In no case did the state find radioactivity levels significantly above background.
In recent years, the IRL environmental monitoring program has been subject to inconsistent sampling procedures, which ranged from daily water sampling of Devil's Brook to semi-annual sampling of vegetation in the berm. There are also extended periods in which no environmental sampling was carried out. It seems that in the future, a modest but consistent sampling program would best serve our interest.
133 135 Presenily, weekly reports are made on the release of Xe, 1 JXe and Ar from the H.U.T. vent and on the release of-short lived particulates from the stack and normal exhaust. Generally, the con-centration of these nuclides are far below allowable release limits.
Continued monitoring in such a manner should be sufficient to ensure compliance with release limits.
An air monitoring station set up in the prevailing down wind direction might be used to determine gross particulate activity in the event of an accidental or intentional release from the reactor or laboratories. Water sampling may be broken down into two parts; surface water and ground water. Our best bet here is a periodic check on the well points surrounding the laboratory and berm areas. It would be from these well points that a release would be first detected.
It is suggested that samples be taken quarterly and analyzed for a wide range of radionuclides. With frequent releases of effluent to the berm area, a monthly surface water sampling program would assure us that we are not releasing evaporator waste which is above the allow-able MPCw. It might be interesting, but not necessary to also occasionally sample the vegetation in the berm area.
Because the state continues to monitor the surface stream water in the area, and because of the unlikelihood of contaminants reach-ing Devil's Brook or Shallow Brook, particularly during the summer months, semi-annual water sampling (during the spring and fall months) should be sufficient.
Certain radionuclides tend to be concentrated by vegetation.
Produces from nearby farms mig t occasionally (once a ear) be analyzed for such fission products as Mn, 6 0 Co, 6 5 Zn, 1 3 7 Cs, Cs, 9 5 Zr, 1311, 1 4 0 Ba and 9 0 Sr. These nuclides are likely to be found in vegetation, if they are present in the soil.
At present, the environmental program consists of:
- 1. Continu6us monitoring of long-lived particulate radionuclides released from the laboratory hoods and reactor stack (Filter samples are changed and collected weekly).
- 2. Weekly analyses of gaseous fission products and activation product releases from the HUT vent.
- 3. Analysis of effluent from evaporator to be discharged to the berm (when needed).
What might be added to this:
- 4. Quarterly analysis of ground water from the well points on the IRL site.
- 5. Monthly analysis of surface water in the berm.
- 6. Semi-annual study of surface stream water near the IRL site (comparison of upstream and downstream samples from Devil's Brook and Shallow Brook).
- 7. Establishment of an air sampling station in the prevailing down wind direction for use in the event of an accidental or in-tentional release from the dome.
- 8. Review the annual reports by the Bureau of Radiation Protec-tion of the New Jersey State Dept. of Environmental Protection, particularly in reference to crop and soil analysis in the Plains-boro area.
References:
I 1. Hazards Siummary Report for IRL, Thorthwaite 1959.
- 2. 1971'Envi ronmental Radiation Levels in the State of New Jerse y.
- 3. TSP Repor t 23 - Six Year Summary Of IRL Environmental I Monitorin g Data 1959-1961.
- 4. Progress Report No. 1 - Air Pollution Climatology for the IRL Area. Huston 1965.
- 5. Miscellan eous Environmental Reports:1959-1968.
I* 6. TSP Repor t 19 - Semi-annual Report of Airborne Radioacti vity Levels for the Period Ending 9/30/63.
Doyle and Fetzko.
I ,.
CC: R.T. Canfield L.C. Thelin M.B. Shymlock I
I I
,SEASONAL PREVA ILING WIND DIRECTIONS-FREQUENCY I.
N
- iI
[
w E SPRING I, N
w E
I S
- C UM MER AUTUMN I From doto for Philodelphiao Pa. airport 0 I
Percent af Occurrence 5
I 10 15 20 25 30 35 I I" I - -I I I
I '~ Figure 2 AVERAGE MARCH OF PRECIPITATION:(O--e)j POTENTIAL EVAPOTRANSPIRATION (o-o), AND ACTUAL EVAPOTRANS-PIRATION.(*-.--}-) AT HIGHTSTOWN, NEW JERSEY
¶Lff1l Water surplus Soil moisture utilization f"Z" Water deficit Soil moisture recharge 6
5 4
2 I
I 0 J F M A M J J A S 0 N D J I
I 4D
WguAM3 Efttf MWea otl" tnvironmental Collection Statidns r-77
i .... * .....
Uz oe1 I -
op.-
-ls- *-: T4-I,~~~~ I E,~..
14U We Ita n I. R L LTP AN to I. e//0Ih ,7
Copy No.: 7
- udustrial Reactor Laboratories Operatcd by Columbia University SIX-YEAR S*UIIRY OF IRL ENVIRO1?NENTAL flO TiTORIiC, DATA 1959-1965 by J. R. Pelrine & G. Fetzko Technical Services Special Projects TSP - 23 January$ 1967 Approved byi "?. .. - . . _L Manager, Technical Services This document has been prepared for internal use only and should not be reproduced without permission of Industrial Reactor Laboratoriesq Inc.
It is intended for the information of the:Laboratories Operating Staff and Resident Scientific Staff in connection with their activities at the IRL facility. It may contain preliminary, unchecked or incomplete results and is subject to revision.
DISTIZIBUTTON TSP-23 Copy No..
(1). R. U. Van Wyck (2) J. R. Pelrine (3) G. Fetzko
' . (4) L. Cushen (5) F. J. Wiedenmann (6) Circulate to:
We Gibson Do Arbach A. Demko Technical Services Special Projects File (7) Technical Services Special Projects File (8) Operations Department R, We Houston (9) p 6
I' .. a Iii TABLE OF CONTENTS Page SUI% 4A Y-. . . . . .- . .. . . . . . . .. _ . _
- .,-.J'* DISCUSSION. . . . .. 2 I. STREAM SAMPLES
.A, Sample Process-...-.
Itions-- -. . . .' -
2 B. Sampling Points and Loca Co. Brief Summaryy.---. 2 Road-- - '- - - - ' . . - - 3 D. -Devil's Brook - Shalk's-BE Shallow Brook - IRL Site 3 Fe Shallow Brook - Dye Road 4 Junction-'- ---. . .-- ...- 4 C. Devil's Brook - Monmouth He Walker-Gordon Pond---- 5
- i. Manalapan Brook - Jamesb 5 J# Devil's Brook - Monroe T*ownshi[p- - -- :- . .-- _ =-. . : 6 IL SURFACE WATER SAMPLES A, Berm - IRL Site--... 6 e -lIIIIl l ,1., qn ,S,-ea llm -,1* ll l lm l11 1 1 J4, Be IRL Rain Gauge - IRL Sit 8 III WASTE SAMPLES A. Clear Water Waste Wast 8 IV. WELL POINT SAMPLES A, North Well Point 96---- 10 B. East Well Point #7---- 10 Co South Well Point #8A (Be 10 D. South Well Point #8B (Be: rm) .. --- . . 11 Be South Well Point #8C (Be: rm) -- - -- 11 Fi South Well Point #8D (Be: 11 C.. West Well Point #9--.- 12 V, DEEP WELL SAMPLES "15 A. IRL Deep Wells~------
Be IRL Deep Well #1--.-. 15 Co IRL Deep Well 02----- 15 Do IRL Drinking Fountain-- 16
TABLE OF CONTENTS.
.(continued)
Page VI. VEGETATION, SOIL AND MUD SAMPLES A, Sampling Points and Locations--. . . ..--- ---- - - 16 B. Devil's Brook (Off Site)--.---- ... -- -- ..... --- 18 Co Shallow Brook - IRL (On Site)---- -.-------..... .. 18 Do Shallow Brook - Dye Road (Off Site) -.. ..------ ....... 19 Be Devil's Brook - Monmouth Junction (Off Site)- . ..--------.-- 19 F. North Well Point,_(On Site) --.............. ....... 20 Go East Well Point (On Site)- ---------- 20 H. South Well Point (On Site)--.. ...... ..-- ............ 21
-I Walker-Gordon Pond (Off Site)------................. .. 22 Jo West Well Point (On Site) - -- ---- ----- 22 K. Hanalapan Brook - Jamesburg (Off Site) --------- --- . 23 L IRL Site -- -- 23 VII SPECIFIC ISOTOPES (Soil, Vegetation, Mud):.
A, Soil Samples- 24 Be Vegetation Samples-- ........... -------.... 25 2"5.......
Co Mud Samples- 26 VIII. SPECIAL ANALYSIS A.. Identification of Mn-54 in Vegetation and Soil Samples ----- 26 IX, AIR SAMPLES A* Summary 29 Be. IRL Gatehouse (On Site)-------- .....................--- 29 C. Health Service, Trenton, N. J.*----------- .......- 31
I1 V
LIST OF FIGURES Figure No. . Page Ie STREAM SAMPLES- 7 (Devil's Brook, Shallow Brook, Manalapan Brook)
I1. SURFACE WATER SAMPLES-- ----------------- - --- 9 (IRL Berm, Rain Water)
III. WELL POINT SAMPLES--------- -----........-----------....--------- 13 (North, South, East, West Wells)
IV... SOUTH WELL POINT (BE-.-----------------. 14 V. GAM4A SPECTRA OF ENVIRONMENTAL SAMPLE------------ ...- ......- . 27 VI. HALFLIFE OF Ma-54 (ENVIRONMENTAL SAMPLE)-- -.. .-. .--------- 28 VII. AVERAGE CONCENTRATION OF AIR S-PLES -- --- 30 (IRL Gatehouse, U. S. Public Health Service, Trenton, N. J.)
1
SUMMARY
An environmental monitoring progtam was initiated during the Fall of 1959 prior to routine operation of IRL's 5 megawatt swimming pool reactor. This report summarizes the data obtained from this program through 1965. The data show primarily fluctuations in radioactivity concentration levels which resulted from fallout of atomic bomb debris, most noticeably the resumption of nuclear weapons testing by the USSR from September, 1961 through 1963. The only signifi-cant environmental effect which can be attributed to the IRL operational program is observed in the sampling of surface water in the berm area. The effect, which
.onsisted of a significant decrease in the radioactivity concentration in the surface water, resulted from installation and utilization of an evaporator to process all liquid wastes prior to discharge to the environment. Routine use of the. evaporator was initiated during the latter part of 1960.
S.."D I S C UJ S S 1 0 N An environmental monitoring program was initiated at IRL during the Fall of 1959 prior to routine operation of the 5 megawatt swimming pool reactor.
This report summarizes the data obtained from the program through 1965. It should be noted that substantial changes in both the scope and sampling frequency have occurred during the six-year period, Currently, a modest program is carried out which consists primarily of a routine air sampling program, weekly analysis of a continuously collected stream sample and semi-annual collection of vegeta-tion, mud and soil samples. The reduction of the program to its present level was brought about over the six-year period as more and more experience showed that operation of the reactor produced no measurable effect on the radioactivity concentrations which exist in the environment.
Most of the data contained in the report is summarized on a seasonal basis and in some cases on an annual basis. The radioactivity concentrations observed are attributed to the fallout of atomic bomb debris, In general, environmental radioactivity levels increased following the resumption of atmospheric bomb testing by the USSR during September, 1961 and have shown a general decline since the moratorium of atmospheric testing went into effect during 1963. The
2 only measurable environmental monitoring effect which can be attributed to IRL operations is a substantial reduction in the radioactivity concentration levels In surface water collected from the berm area after the latter part of 1960.
This effect resulted from construction and routine use of an evaporator to pro-cess all.IRL liquid wastes to insure that no operationally produced radioactivity Is added into stream water. Use of the evaporator was initiated during the latter part of 1960.
- 1. STREAI SAMPLES
-A. Sample Process:
A liter sample is boiled down to near-dryness then transferred to a planchet, evaporated and counted for gross beta-gamma activity. All stream samples are collected, processed and counted in the same manner.
B. Sampling Points and Locations:
From 1959 to 1965, stream samples have been taken from seven sample points, Below are sampling points and locations:
- 1. Devil's Brook - Shalk's Road
- 2. Shallow Brook IRL Site S3. Devil's Brook - Monmouth Junction
- 4. 'Shallow Brook - Dye Road
- 5. Walker-Gordon Pond 6o Manalapan Brook - Jamesburg
- 7. Devil's-Brook - Monroe Twp, C. Brief Summary:
Samples were collected as .routine samples at one time or another for various reasons. Of the seven sample points, only the sample from Devil's Brook at Shalk's Road is collected as a routine sampling point.
Beginning in 1959, the stream samples showed a downward trend of environmental radioactivity since the cessation of bomb testing in 1958, This downward trend continued until the second half of 1961. These
. samples were also in agreement with data from the Public Health Service
3 Radiation.Surveillance Network. During the second half of.1961, the background radioactivity of the samples showed an increase caused by the resumption of nuclear weapons testing by the Russians in September of 1961. In 1962 and the first part of 1963 the samples remained relatively
'high. At the end of 1963, a downward trend in background wasnoted and the trend continued into 1964 and 1965 (Figure I).
D. LOCATION: DEVIL'S BROOK- Shalk's Road CODE NO.: E-1 Concentration (.ic/.ml) ,
Year Season Noo of Samples Average Maximum Minimum 1959 Fall 46 1.2xi0"8 1.5x10- 7 50xlO-10 1959 Winter 62 23xlO" 8 4.4x10- 7 9.0x10-1 0 1960 Spring 61 1.1x107 8 1.4x10- 7 1.4x10-9 1960 Summer 61 8.2x10- 9 3.9x10- 8 4.6x10-1 0 1960 Fall & Winter 68 8.,5x10- 9 l.7x10"7 2.3x10-1 0 1961 Spring 90 6.6xi0- 9 3.OxlO- 8 4.6x10-1 0 1961 Fall 120 1.7x10- 8 l.lxlO-7 2.3xi0-9 1962 Spring 126 3.3x10- 8 2.4x10- 7 9.1x10-9 1962 Fall 116 2.2x10- 8 1.2x10- 7 9.1x10_ 9 1963 Spring 107 4.0x10- 8 1.9xl0- 7 <1.3x10-9 1963 Fall 124 1.4x10, 8 3.7x10- 7 8.7x10-1 0 1964 Entire Year 146 9,4x10- 9 4.8xi0- 8 <1.3x10-9 1965 Entire Year 231 3.4x10- 9 1.5x10- 8 1.3x10-9 COMIENTS:
Routine sampling of Devil's Brook at Shalk's Road is continuing.
(Refer to Figure I.)
E. LOCATION: SHALLOW BROOK -. IRL Site CODE NO.: E-2 Concentration Ue/_ml)
Year Season No. of Samples Average Maximum Minimum 1959 Fall 3 5.9Xi0- 9 ....
1959 Winter 24 2.3x10-8 3.1xlO- 7 2.3xi0-9 9 4.0xlO-8 1.8xlO-9 1960 Spring 62 9.5x10-1960 Summer 60 8.6xi0-9' 6.8xi0- 8 4.6x10- 0
4 E. Continued, Year Season No. of Samples Concentration (Vc/ml)
- -of Samples____ " Average Maximum Minimum 1960 Fall & Winter 68 9.8x10- 9 5.9x10- 8 4.6x10- 10 1961 Spring 95 6.7xi0-9 3.1x10- 8 4.6xi0-2 0 1961 Fall 120 2.1x10- 8 2.0x10- 7 1.9x10-9 1962 Spring 126: : 4.0xlO- 8 2.5x10" 7 9.1x10-9 8 7 9.1xi0-9 1962 Fall 116 2.8x0 3.4x10" 106 5.1xlO- 8 1.9xlO- 7 6.4xi0-9 1963 Spring .,
1963 Fall 7 2,6x10- 8 6.5x10- 8 1.1x10-8 COM.MENTS.
Routine sampling of Shallow Brook on the IRL site was discontinued as of January 1, 1964. Termination of this sample point was caused by weather conditions. During the winter, sample point would freeze completely and during the summer, the sample point was dry. (Refer to Figure I.)
F. LOCATION: SIHALLOW BROOK - Dye Road CODE NO.: E-3 Year Season No. of Samples Concentration (-cfml)
Average Maximum Minimum 1959 Fall 2 6.8x10- 9 --.---
1959 Winter 3 .. lxl0"8 1.5x10- 8 8.2xi0-9 1960 Spring 3 7.6xI0" 9 1.2x10- 8 4.1x10-9 1960 Summer " 3 1.2xlO- 8 1.4x10- 8 l.xl0-8 1960 Fall & Winter 4 " 5.0x10- 9 6.8xi0"9 2.3xi0-9 COMIENTS:
Routine sampling of Shallow Brook'at Dye Road was discontinued as of January 1, 1961. Termination of this sample point was caused by weather conditions. During the winter, sample point would freeze completely and during the summer, the sample point was dry.
C. LOCATION: DEVIL'S BROOK - Monmouth Junction CODE NO.: E-4 Year Season No. of Samples Concentration (c/mnl) ,
_erSesnNo _fSape Average Maximum Minimum 1959 Fall 2 6,5x0- 9 -- -
8 8 1959 Winter 3 1.6xlO- 8 2.3xi0- 1.3xlO
5 C. Continued.
Concentration (pc/ml)
Year Season No. of Samples Averape Maximum Minimum 1960 Spring 3: 1,3x10" 8 2.1X0- 8 9.1x10-9 1960 Summer 3 l.2x10- 8 l.8x10- 8 9.1x10"9 1960 Fall & Winter S 4* 3.7xl0"9 4.6x10- 9 2.3x10-9 COMMENTS:
Routine sampling of Devil's Brook at Monmouth Junction was discontinued as of January 1, 1961.
B. LOCATION: WIALKER-GORDON POND CODE NO.: E-5 Concentration (uc/ml)
Year Season No. of Samples Average Maximum Minimum 1959 Winter 3 7.4x10- 9 1.0x10, 8 3.2xi0" 9 1960 Spring 3 1.2xlO- 8 2.6xi0- 8 2.3xi0-9 1960 Summer 4 5.7x10- 8 2.2x10- 7 2.3x10-9 1960 Fall & Winter 4ý 6.2xi0- 8 2.4xi0- 7 2.3xi0-9 COHMENTS:
Routine sampling of Walker-Gordon Pond was discontinued as of January 1, 1961.
I -Is. LOCATION:
CODE NO.:
MANALAPAN BROOK E-14
- Jamesbur.p I Year Season No. of Samples Concentration (uc/ml)
Average Maximum Minimum 1960 Summer x 9 9,xi0- 1.8x10- 8 4.6xi0-1 0 I 1960 Fall & Winter 5 1.2x10-8 3.4xi0- 8 2.3xi0-9 1961 NO SAMPLES I 1962 1962 Spring Fall 3
7 9.6xi0- 8 2.0x10- 8 2.7xi0- 7 3.6xi0- 8 9.lxl0-9 9.lx10-9 1963 Spring . 9 2,5x10- 8 5.0x10 8 3.8xi0-9 1963 Fall 4. 1.9x10- 8 5.0x10- 8 6.4x10, 9 COMMENTS:
The.sampling of water from a remote off-site brook was initiated in the summer of 1960 in order to obtain a direct comparison of results for our on-site brook samples. Sampling point has since been discontinued.
(Refer to Figure I.)
6
.N J, LOCATION: - DEVIL'S BPOOK - Monroe Township CODE NO,: E-18 Concentration (vc/ml)
'Year Season No. of Samples Maximum Minimum Average 1.963 Spring 15 2.5x10' 8 5.0xlO- 8 3.8xi0-9 COMMENTS:
In January, 1963, sample point #18 was initiated in conjunction with work being done on IRL Report #111, in order that the origin of water flow-ing into Devil's Brook 'could be traced. Sampling from this point was dis-continued in February, 1963,
- 11. SURFACE WATER SAMPLES A. LOCATION: BERM - IRL Site CODE NO.: 8E Concentration (U c/ml)
Year Season No. of Samples Ave rasý,e Mtaximumn MIinimum 7 6 1960 Spring 51 8.4x10- 6.86x1- 6.Bx1- 9 1960 Summer 58 1-.5x10- 6 l.2x10-5 3.2x108B 1960 Fall & Winter 42 5.7X10-7 3.7xl10 6 3.8xl10 8 1961 Spring 21 6.6xl10 7 2.3xl10 9 1961 Fall 251 7.2x1O- 8 4.6xl10 7 6.4x10-9 1962 Spring 26 7 .4x108S 2.5x10-7 9.1X10-9 1962 Fall 24 3.6xl10 8 6.4x10-8 9.1X10-9 1963 Spring 25 3.9xl10 8 1.3x1- 7 1.3xl10 9 1963 Fall 25 3*9x10-8 1.7x10-7 1.3x10-9 8 7 9 1964 Entire Year 48 1 .2x10- 1.4x10_ 1.3xl10 1965 Entire Year so 5.2x10-9 2.2xl10 8 1.3x!0-9 COMENTS:
The sampling of surface water from within the berm area was initiated in the Spring of 1960, in order to study the percolation of low level radio-active waste through the upper layers of soil. During the Summer of 1960, the average radioactivity level of the berm surface water doubled. This resulted from an increase in the average concentration at which liquid wastes were dumped to the berm and the lesser dilution from rainfall as Compared with the Spring quarter.
"".FIGURE I STREAM SAM'PLES 3 4d Sampling Points L' tDiscontinued 22 II I 7.
6 I-.i - "-
Resumption of Nuclear Weapons 4 ~Testing, I, , .
1960. 1961 1962 1963 1964 1965 1966 1..Year
.0 Devil's Brook - Shalk's Road I L~Shallow Brook - IRL Site 0 Manalapan Brook -Jonesburg
8 Beginning in 1961, a downward trend in radioactivity in samples taken in the berm had been evident. This-trend was due to the installation of the waste evaporator and simultaneous cessation of discharging liquid radio-active waste to the berm at or below AEC maximum permissible concentrations.
Routine sampling is continuing. (See Figure II.)
B. LOCATION: IRL RAIN GAUGE - IRL Site
'CODE NO.: 15 Year No.1of Samples Concentration (pc/ml)
- - No. of Samples__ Average, Maximum MIlinimum 6
1961 Fall 9. 8.2xi0- 7 1.8x10- 7.2xi0-9 6 4.2xi0-5 2.2xi0-7 1962 Spring 1.8 4.5xi0-5 1962 Fall 12 1.2xi0- 5 9.6xi0- 3.1xi0-9 7
1963 Spring I7- 2.4xi0-5 1.4x10- 1.3xi0-9 1963 Fall .18 5.OxlO-5 3.8xIO14 1.4xlO-8 7
1964 Entire Year 24 2.5x10- 7 9.4xi0- 4.8x10-9 1965 Entire Year 31 7.6x10- 8 3.9x10- 7 6.5xi0-9 COMIENTS:
The rain gauge, installed in September of 1961, provided regular ana-lysis of rain water samples. Prior to this, spot checks of rain water samples taken since 1958 had shown below stream background radioactivity levels.
An increase in the radioactivity level can be seen (Figure II) begin-ning in the Fall of 1961. This increase was due to the resumption of nuclear weapons testing by the USSR in September of 1961. Routine sampling is continuing.
III. WASTE SA74PLES A, LOCATION: CLEAR WATER WASTE - Waste Tank Area CODE NO.: 17 Year Season No. of Samples Concentration (jic/ml)
Average Maximum Minimum 1962' Fall 17 2.4x10- 8 l.0xl0- 7 9.1x10-9 0
1963 Spring 25 1.9x10 9 5.0xl0- 9 7.3xi0-1
9 FIGURE II I - SURFACE WATER SAMPLES I'
II I.-r Ii.o...
I Was I . *.
iIi
- :.... 10-P ..
I 1964 1965 1966 1960 1961 1962 1963 Year o!RL Berm E1Racin Mater - IRL Rain Gauge
10 A* Continued.
Concentration ,(Cc/ml)
Year .. Season No. of Samples Maximum Minimum Average 1963, Fall 22 2.0x10- 9 4.5xi0- 9 7.3x10- 1 0 1964 Entire Year 49 8.6x10-9 6.2x10-8 1.ixlO-9 1965 Entire Year 50 5.8xI0-9ý 4.5xi0- 8 1.3xi0-9 COM1ENTS:
Routine sampling is continuing.
IV. WELL POINT SAMPLES A. LOCATION: NORTH -JELL POINT CODE NO.: 6 Concentration (pc/ml)
Year Season No. of Samples Average Maximum Minimum 1959 Fall 2 3.lxlO-8 ---
1959 Winter 3, 8.5x10- 9 1.2x10- 8 3.6x10-9 8 1.5x10- 7 1.0x10-8 1960 Spring 2 8.0x10-1960 Summer 3 9.8xi0- 8 1.5x10l 7 4.6x10-8 1960 Fall & Winter 3 7.1x10- 9 1.0x10- 8 2.3x10-9 B.e LOCATION: EAST WELL POINT CODE NO.: 7 Concentration (ic/ml)
Year .Season No. of Samples Maximum Minimum Average 1959 Fall 7 1.4x10- 8 5.9x10- 8 1.4xi0"9 1959 Winter 1960 Spring 1 2.2x10-8 1960 Summer 1.2x10-7 1.5x1- 7 8.2.x1- 8 3
1960 Fall & Winter L1.3lc 8 2.lxl10 8 9.1x10-9 C. LOCATION: mBl SOUTH WELL POINT CODE NO.: 8A (Berm) i * ! l Concentration (ucfml)
Year Season No. of Samples Average Maximum Minimum 8
1959 Fall 6 5.0x10- 8 8.0x10- 3.7x10-9
11 C. Continued.
No of Samples Concentration (pcml)
Year Season No. ofSamples Average Maximum Minimum 8
1959 Winter -13, 2.1x10" 8 4.4xi0- 3.6x10-9 1960 Spring 23 4.7x10- 8 1.4x10- 7 5.5x10-9 1960 Summer 9 5.OxlO 8 8.2xi0- 8 2.3xi0' 8 1960 Fall & Winter 7 4.1x0-8 1.3xl0O7 2.3xi0-9 D, LOCATION: SOUTH WELL POINT CODE NO.:
-- , ii 8Bu , (Berm)
% f_
Concentration (vc/ml)
Year Season No. of Samples Averare Maximum Minimum 1959 Winter 14 t.3x10- 8 4.2xi0- 8 4.6xi0" 9 1960 Spring 25 4.3x10- 8 3.6x10- 7 2,7x10-9 1960 Summer 19 2.2x10" 8 7.3xi0- 8 7.6xi0"9 1960 Fall & Winter 1 9.1x10-9 E, LOCATION: SOUTH ,ELL POINT CODE NO.: SC (Berm)
Concentration (pc/ml)
Year Season No. of Samples Average taximum Minimum 8 7 1959 Winter 15 3.1xlO- 1.3x10- 4.6xi0-9 1960 Spring 27 9.4x10-8 9.4x10- 7 l.8x10-9 5.7x10- 8 4.8x10- 7 4.6xlO-9 1960 Summer 21 1960 Fall & Winter 10 2.3xi0- 8 3.6xi0- 8 9.1xi0-9 F. LOCATION: SOUTH WELL POINT CODE NO.: 8D (Berm)
Concentration (vcfml)
Year Season No. of Samples Average Maximum Minimum 1959 Winter 14 lgx10- 8 5.2x10- 8 3.6xi0-9 8 7 10 1960 Spring 25 9.7x10- 8.8xi0- 9.1x10-1960 Summer 21 3.2x10- 8 2.4x10- 7 4.6x10-9 1960 Fall & Winter 10 1.2x10-8 4.6x10- 8 4.6x10-9
12
.: G 0 LOCATION: WEST WELL POINT CODE NO.: 9 Year Season No. of Samples Concentration (i.c/ml) 11inimum
-. .... Average Maximum
.1959 Fall 3 1.5xlO- 8 --
8 8 1959 Winter 3 3.4xi0-8 6.7x10- 1.0x10 1960 Spring 1 2.0x10-7 --
1960 Summer 3 7.0x10- 8 1.0x10"7 1.3x10-8 1960 Fall & Winter 3 2.6xi0-8 6.8xi0"8 2.3xi0-9 COMMENTS:
in the Fall of The sampling of ground water near the surface was initiated at background 1959, this coincided with the use of the berm for dumping wastes about 10' deep levels. These samples were taken from four well points driven and located about 500' north, east, south and west of the Laboratory.
south well The initial data indicated that the radioactivity level at the 8 was less than point, located within the berm, averaged 5.0xl0" uc/ml, which
- three times the normal background. All samples taken in the Fall of 1959 were of far below AEC permissible concentrations (for unidentified isotopes) 1.0x10- 7 pc/ml. (See Figure III.)
ground water In addition to the four well point samples, the sampling of area was initiated from three well points located at the periphery of the berm in the Winter of 1959. (See Figure IV.)
the berm During the Spring of 1960, the sampl'ing of surface water within began. The purpose was to study the percolation of low level radioactive the radioactivity waste through the upper layers of soil. The result was that surface averaged level of water taken from well points located 3-4' below the only 1/10 of that of surface water samples from the berm area.
S-~-.- ...... ~-.*-. --.--.-- *. *. .**-.
13 FIGURE III WELL POINT SAMPLES 10-7 1~(
U
- 1 0 - Located -I-
.54 43 within the S.' Berm 43 -
0 U
0 C) 0 U,
S.'
V 2.
I i
I I I 1959 1960 1961 Year 0 North Well Point Code No, 6 No. 7 El East Well Point Code A South Well Point Code No. 8A (Berm)
West Well Point Code No, 9
I 14 I
FIGURE IV SOUTH WELL POINT (BEPM)
I I
I I
jO" 7 I 10-I 4 0
I 0 0
4J.
C3 I
I I 10- 8 I
I I I I I I i
I I
I I
1959 1960 1961 Year 0 Code No. 8B (Berm)
Iy.i) E3 Code No. 8C (Bezm)
Code No. 8D (Berm)
I
15 V. DEEP TELL SAMPLES Ai LOCATION: IRL DEEP WELLS CODE NO.: E-10 Concentration. (pc/mI)
Year Season No. of Samples Average Maximum Hinimum 1959 Fall 2 3.3xi0- 8 ---
1 " 5.4x10--9 1959 Winter 1960 Spring .6 2.4x10- 8 6.4x10- 8 4.6x10-9 1960 Summer 4 5.6x10- 8 1.3x10- 7 1.4x10-8 1960 Fall & Winter 3 6.4x10- 9 l.0xl0- 8 4.6xi0-9 B. LOCATION: IRL DEEP VELL #1 CODE NO.: E-10A Concentration (pc/ml)
Year Season No. of Samples AveraF~e Maximum Minimum 1962 Spring 2 9.1x10- 9 9.lxlO-9 9.1x10-9 1962 Fall 2 9.1xlO- 9 9.1x10" 9 9.1xl0-9 1963 Spring 2 5.4xi0- 9 3.8xi0- 9 <1.3x10"9 9
1963 Fall llxlO 1964 Entire Year 2 2.9xi0-9 ....
1965 Entire Year 2 1.3xlO9 1.3x10- 9 1.3x10-9 C. LOCATION: I.L DEEP WELL #2 CODE NO.: E-IOB Concentration (pc/ml)
Year Season No. of Samples Avera e Maximum Minimum 1962 Spring 3 -3.OxiO- 8 4.6x10-8 9.1x10-9 9
.1962 Fall 2 9.1x10" 9 9.1x10- 9.1xl0-9 Spring 3 1.7x10- 9 2.5xi0- 9 <1.3x10-9 1963 Fall 2 <i*3x10- 9 .
1963
.1964 Entire Year 4 1.9xi0- 9 .
1965 Entire Year 4 8.8x10- 9 2.9x10" 8 1.3x10-9
Q" 16 Do LOCATION: IRL DRINKING FOUNTAIN CODE NO.: E-16 Concentration (,c/ml)
.6Year Season No. of Samples Minimum Average Maximum 8 8 <l.0x10-9 1962 Spring 5 2,2xi0- 6.4x10 1962 Fall 1.6x10- 8 3.6xi0"8 9,lxlO-9 1963 Spring 6 1.2x10"9 1.3x10- 9 1.Oxl0-9 l4lX1O-9 1.2x10-9 l.Ox10-9
.1963 Fall
.46 1964 Entire Year 2.4x10- 9 5.5x10- 9 <1.3x10-9 9 1.4xlO- 9 1.3x10-9 1965 Entire Year 2 1.3x10-COMMENTS:
Starting in the Fall of 1959 sample point (code no. E-10) of the IRL .deep wells began. Sampling of this point continued to 1960.
In 1962, deep well #I (code no. E-10A) and deep well #2 (code no. E-lOB) were reported as two different sampling points. In addition to these two sampling points, IRL drinking water (code no. E-16) was included as a routine sampling point.
Deep well #1 and #2 and IRL drinking water are analyzed on a routine basis.
VI. VEGETATION, SOIL, & MUD SAMLES I A. Sampling Points & Locations:
Vegetation, soil and mud samples have been collected since 1959. They I had been collected as "on site" samples and "off site" samples. Below is a list of the sampling points:
I Off Site SamDles Code No. Location On Site Samples Code No,. Location I E-1 E-3 Devil's Brook Shallow Brook E-2 E-6 Shallow Brook North Well Point I E-5 E-14 Walker-Gordon Pond Manalapan Brook - Jamesburg E-7 E-8 East Well Point South Well Point U E-9 E-19 West Well Point IRL Site I.
17 The results obtained from these sampling points can only be used in com-parison with other, sampleswtaken at the same sampling period. Sampling points, have varied so much in. the past years that the-comparing of-data is practically Impossible. In 1964, three permanent sampling points were established: Shallow
.Brook at Dye Road (off site), Walker-Gordon Pond (off site)-and IRL Site (on
-site). With these three permanent sampling points, results obtained should be more meaningful*
The following results are gross beta-gamma activity levels, obtained at the various sampling points from 1959 to 1965.
M ., m- - - m -m M-.. - m - - - -
IN, VEGETATION, SOIL, MUD SA4P-LES YEAR SEASON NO. OF VEGETATION (NcTOm) NO. OF SOIL (Nc/cm) NO. OFP MUD (pc/,im)
SA4PLES AVERAGE MAXIMUM MINIMIUM SAMPLES AVERAGE MAXIM.UM MIt011U0 SAMPLES AVERAGE MAXIMUM MINIMUM B. LOCATION: DEVIL'S BROOK (Off Site)
CODE NO.: E-1 1 2.7x10-5 2 4.8x10-6 1959 Fall 3.6xlo-4 1959 Winter none o*m none 3 1.3xlO-S 2.6xlrS 2.4xlOG6 1960 Spring 1 2.3x10-4 1 4.2x10-6 3 6.0xl10 6 7 .OxlO-6 3.3xlO-G 7
1960 Summer 2 9.2xl10 5 1.6xlO-4 2,3xlO-S 2 1.4x10-6 1.4x10.6 1.U10-6 3 2.4xl10 6 3.8x106G 8.OX1lO Fall &
Winter 1 2.5XIO-4 -- I-1 5.5xlO-6 -- 3 . ý4.7xl10 6 8.4x10 6G 1.8x106G C. LOCATION: SHALLOW BROOK - IRL (On Site)
CODE NO.: E-2 1959 Fall 1 4.6x10 4 .- 1 7.7xi0" 6 2 1.5X10-6 1959 Winter none --- none --- 3 8.5X10-6 2.2x10"' 5 1. 2x0-6 1960 Spring 1 3.2xlO-4 1 6.5x10" 6 3 4.7x106G 6.8xlOSG 2.0xlO-6 1960 Summer 2 1.8XI- 4 2.OXlO 4 1.6x10I 4 2 2.0xlO-6 2.6x10OS 1.4x10-6 3 6.6xlO?7 8.ox 10- 5.3xi0-7 Fall & 3.6x10- 4 --- 6 8.0xl0- 6 5.1x10-7 Winter 1 .1 . 3.3x10-6 3 3.4x10, 1961 Entire none none none =m,,* ,,,, m*
Year 6
1962 Spring 2 9.2xlO (vegetation) 2 - 4.4x10-6 "-- 2 5.2xi0-6 3
1.6xlO- (ash) 1962 Fall 1 6.lxlO-- - 3. 6.6x10-6 1 1.0XlO-5 D*m 1963 Spring 1 6.0xlO- 5 --- 1 1.2x105s 1 8.6xlOG I-'
0
- - - - -. - - m-U VEGETATION, SOIL, T.UD SAMLES YEAR SEASON NO. OF VEGETATION (uC/qrM) NO. OF SOIL (uc/qm) NO. OF MUD 4ic/qm)
SAMPLES AVERAGE MAXPIAUM MINIRUM SAMPLES AVERAGE MAXT1iU. MINVIUV SAMPLES AVERAGE MAXEI4UM MINIM1UM D. LOCATION: SHALLOW BROOK - Dye Road (Off Site)
CODE NO.: E-3 1959 Fall 1 1.0xI0-3 1--i lx10xO-5 2 2.9x10"6 5 4 1959 Winter none -- none 3 4.7x10 1.2xlO- 3.4xlO-6 6
1960 Spring 1 2.3x10o4 1 3.4xI0-6 3 1.4x10-5 2.9x10-5 6.5x10" 2 1.lxl0-4 2 2.9xi0-6 4.9x10" 6 8.6x10 7 1960 Summer 1.2x10-4 1.3x10-4 3 4.4x10-6 8.5x10-6 1.2xl0-6 1960 Fall & 1 1 1.0.xlO-6 -
Winter 2.5x10-4 3 5. 1x10-6 8.2x10- 6 3.5x10-6 1964 Spring ,1 5.5x1O-6 9 .4x,1 6 -
1 none
,1/ 4 1965 Spring 4.1x0-l (ash) 2.4xI0-6
" 1965 Fall 1 5.2xi0-6 1 8.5xl0-6 E. LOCATION: DEVIL'S BROOK -Mon. Jct. (Off Site)
CODE NO.: E-4 1959 Fall 1 1. ix10-3 1 1.2xlO-S --- 2 9.0xlO"7 1959 Winter none -- none 3 5.5x10- 6 9.8xlO, 6 6.7x10-7 1960 Spring 1 3.2xlO'. 1 7.5xlO-G -3 9.4x10- 7 1.3x10-6 5.6x10- 7 6 7 1960 Summer 2 2.9xi0-4 3.7xlo-4 2.Oxl0"4 2 2.0xlO- 6 2.7x10- 6 1.3xlO" 6 3 2.6x10- 6 5.3x10- 6.4x10-Fall & 1 4 6 6 1960 Winter 3.0xlO" 1 1.4xl1- --- 3 2.3x1o- 3.xlo-6 1.lxlO-6
%0
VEGETATION,-SOIL, MUD SAMPLES SS NO. OF VEGETATION (.cm) NO. OF SOIL Nc/am NO. OF MUD (vc/,qm)
SAMPLES AVERAGE MAXIMUM MINIMUM SAMPLES ASVERAGE MAM ! MINI..fU SAMPLES AVERAGE MAXIMUM MINIMU F. LOCATION: NORTH WELL POINT (On Site)
CODE NO.: E-6 4 4 1.8xl)-4 1959 Fall 2 .3.4xl10 5.OXI.O 3 1.3xlO- 5 1959 Winter none 1960 Spring 1 2.5x10-4 1 4.8xl0-6 1960 Summer 2 2.0X10-4 2.4x10" 4 1.6x1O-4 2 2.3x10-6 2.6xlOG6 1.9X10- 6 Fall &
Winter 1 2.5xi0-4 1 J1.6xlO&6 G. LOCATION: EAST WELL POINT.(On Site)
CODE NO.: E-7 1959 Fall 3 4.Ox0l- 4 7.2x10- 4 2.3xi0 -4 3 1.1x10-5 1959 Winter 110 ie' -
1 1960 Spring 2. 7x10-4 1 1.8x10-6 1960 Summer 2 1.5x10-4 2.0X10-4 q.1x10- 5 . 2 1.lxlO 6 1.3xi0- 6 8.3xi0-7 Fall &
Winter 1 2.7x10-4 1 7.3x10-7 0
-- -n - -. --
VEGETATION, SOIL, 1MD SA1OLES SOIL (uc/,qm) NO. OF MUD (izo/n)
YWAR SEASON NO. OF VEGETATION (uc/i) NO. OF SAMPLES AVERAGE MAXIMU MINIMUM SAMPLES AVERAGE MAXIMUM MINPR'U4 SA"IPLES AVERAGE AIAXR!.U7, MINIRAN
- 11. LOCATION: SOUTH WELL POINT (On Site)
CODE NO.: E-8 3 7 l.lxlO-5 1959 Fall 6 1.2xl10 3 1.gxlO" 5.5x10l4 1959 Uinter none
.1960 Spring 1 6.4x10-4 1 5.5x10-6 1960 Summer 2 3.5x10- 3.6x10-4 3.5X10-4 4 2 2. 0X10 6
2.4x10-6 1.6xlO 6 Fall & 2.5xI10 4 -- 1 2.2x10-6 1
Winter 1961 Entire none Year 1962 Spring 1 6.2x105S (veqetation) 1 1*8x10-5 3
3.4x10- (ash) 1962 Fall 1 4.1x10-5 1 2.1x105S 1 5 1963 Spring 1 3.4xI10 5 1. X0xl0 I-h
VEGETATION, SOIL,"MU- SANP.ES YEAR SEASON NO. OF VEGETATION (vc/qm) NO. OF SOIL (vc/am) NO. OF MUD (Uc/,m)
SAM4PLES AVERAGE MAXIMUM MINIMUM SAMPLES AVERAGE MAXI,!U?! MINIMUM SAMPLES AVERAGE MAXIMUM MINIMUM I. LOCATION: WALKER-GORDON POND (Off-Site)
CODE NO.: E-5 4
1959 Fall *1 4.6x10- none 1 2.lxlO 5S 1959 Winter none none 3 1.6x10-5 1. x,10-S B.oxlO-6 4 S1 1960 Spring 1 2.9XI10 7.7x1- 6 3 3.4x10- 6 6.8x1- 6 .
1.310-6 ,
1960 Summer 2 2.2xl0-4 2.5xl0~ 1.qX10-4 2 4.9x10-6 6.8x10-6 3.OxlO-6 3 3.3xl10 6 4.8x106G 1.6X10-6 1960 Fall &
Winter 1 3.4xl0-4 1 6.3x10-6 3 6.9X10-6 1.1io10 5 2 .8x106G 1961 Entire none none none Year 1964 Entire 6 8.4x10- 1 1.9X10-6 Year -1 1965 Spring 3.lX10-4 (ash) 1 9.6x10-7 m*m 1
1965 Fall 7 5.6x10- (ash) 1 1.2xl10 5 im*m
- 3. LOCATION: WEST WELL POINT (On Site)
CODE NO.: E-9 1959 Fall 3 5,3x1- 4 . 7.5x10-4 4.Ox10- 4 1 1.2x10-5 .
1959 Winter none --- none 1960 Spring 1 ---
3.Ox10-4 1 4.8x10-6 1960 Summer 1 -- 2 3.7x10-6 5.6xl0" 6 1.8xl1 0-6 1.6X10-4 v Fall &
1960 2.5xl104 1 2.1xlO-6 Winter
VEGETATION, SOIL, M SAMPLES
.D VEGETATION (uc/pm) NO. OF SOIL (Nc/qm) NO. OF MUD (iic/qm)
YEAR SEASON NO. OF MAXI4MU MINIMUM SAMPLES AVERAGE MAXI4UM MINIMUM SAMPLES AVERAGE MAXIMUM MINIMUM SAMPLES AVERAGE K. LOCATION: MIANALAPAN BROOK - Jarnesbure (off Site)
CODE NO.: E-14 1962 Spring 2 2.6xi0-S (vegetation) 2 5.5xi0-6 2 7,3x10-6 * .u m 5.6xi0- 3 (ash) 1962 Fall 1 3.4xi0-5 1 9.5xl0 6G 1 8.2x10-6 1963 Spring 1 5,8xi0-s. 1 9.2xl10 6 L. LOCATION: IRL SITE CODE NO.: E-19 1964 Entire Year. 1 1.2xl0 5 1 4.4xl10 6 1965 Spring 1. 6.6xlo-4 1 1.2x10-6 1965 Fall 1 6.2xi0-6 1 2.4xl10 5
24 VII, SPECIFIC ISOTOPES In addition to the gross beta-gamma results, the soil, vegetation and mud samples were analyzed for specific isotopes. Specific isotopes identified were Zr-95, Nb-95, Ru-103, Ce-141, Co-60, Cs-137, Mn-54, and K-40. Analysis of the specific isotopes did not begin until the Fall of 1962.
A. SOIL S*APLES CODE SPECIFIC LOCATION YEAR SEASON RESULT pic/qm NO. ISOTOPE
.1962 SHALLOW BROOK 2 Fall Zr-Nb-95 7.58x10-8 Ru-103 3.60xi0" 9 Ce-141 1.2 xl0-7 BERII *8 .1962 Fall Co-60 1.6 x10-5 Ce-141 1.25x10- 5 MANALAPAN BROOK 14 1962 Fall Ce-141 ý.4.0 x10-8 WALKER-GORDON POND 5 1964 Spring Ce-141 1.07x10-7 Ru-103 7.26xi0-8 Ce-137 1.39x10-7 1¶n-54 2.26xi0-7 1964 Fall Ce-141 1.74x10-7 Mn-54 2.94xi0-7 1965 Spring Mn-54 7.78xi0-8 DYE ROAD 3 1964 Spring Ce-141 9.51xi0-7 Ru-103 1.12xl0-7 Cs-137 3.95x10-7 1964 Fall Ce-141 5.05xi0-7 Cs-137 2.05x10-7 Mn-54 9.18xi0-8 1965 Spring Mn-54 1. 84x10 7 IRL SITE 19 1964 Spring Ce-141 2.22x10-7 Ru-103 2.73x10-8 Cs-137 5.59xi0-8 Mn-54 1076xi0-7 1964 Fall Cs-141 1.34xi0-7 Mn-54 6.42xi0-8 1965 Spring Mn-54 9. 06x10-8
I I 25 B. VEGETATION SAMPLES U .LOCATION i i CODE iCODE YEAR SEASON SPECIFIC ISOTOPE RESULT vc/gm NO, 5
SHALLOW BROOK 2: 1962 Fall Zr-Nb-95 2.28xi0-Ru-103 4.20xi0-6 Ce-141 6.90xi0-6 1963 Spring Ce-141 5.02x10" 6 Ru-103 3.14xi0-6 Zr-?b-95 3.62x10-5
.BER11 8 1962 Fall Zr-Nb-95 1.42xlO-Ru-103 2.2 xl0-6 Ce-141 3.62xi0-6 6
1963 Spring Ce-141 1.06xi0*
Ru-103 5.92xI0-7 Zr-Nb-95 9.85xi0-6 MANALAPAN BROOK 14 .1962 Fall Zr-Nl-95 2.76x10-5 Ru-103 5.40x10- 6 Ce-141 4.36x10-6 1963 Spring Ce-141 2.72xi0-6 Ru-103 1.76xi0-6 Zr-Nb-95 2.18x10-5 WALKER-CORDON 5 1964 Spring Ce-141 2.75xi0-7 Ru-103 5.82xi0-8 Cs-137 2.19x10-7 Mn-54 7.56x10- 8 1964 Fall Ce-141 3.19xi0-7 Cs-137 3.41x10-7 Mn-54 1.14x10-7 1965 Spring K-40 3 .17xi0-6 Mn-54 5. 74x10-8 DYE ROAD 3 1964 Spring Ce-141 8.74x10-8 Ru-103 5.87x10-8 Cs-137 2.41x10-7 14n-54 1.50x10-6 1964 Fall Ce-141 5.98xi0-8 Cs-137 1.14xlO-7 Mn-54 1.05x10-6 1965 Spring K-40 3.73xi0-6 Mn-54 2.50x10-7 IRL SITE 19 1964 Spring Ce-141 2o58xi0-7 Cs-137 5.46xi0-9 Mn-54 5°0 x10-7 1964 Fall Ce-141 1.49x10-7 Cs-137 2. 06xi0-7 Mn-54 1.02x10-6 K-40 5.56xi0-6 Mn-54 2.76xi0-7
- 1~
.4
26 C. U SM-1PLES
LOCATION O YEAR SEASON SPECIFIC RESULT vc/lm SHALLOW BROOK 2 1962 Fall Ce-141 4.0 xl0-8 MANALAPAN BROOK. 14 1962 Fall Zr-Nb-95 1.75x10-7 Ru-103. 1.41x10-7 Ce-141 I.20xlO-7 VIII. SPECIAL ANALYSIS A$ Identification of Tn-54 -InVegetation aTnd "Soil Samples Vegetation and soil samples collected in 1964 showed a dominant peak at 984 MeV which was tentatively identified as Mn-54. In order to positively identify this peak as Mn-54, the decay of the peak was followed on the RIDL spectrometer. 1 The following results were obtained by analyzing sample #E-3445-A for decay of the .84 MeV peak.
COUNT COUNT DATE DECAY (days) COUNTS/IIN.
NO. _ _ _ _ _ _ _ _ _ _ _
- 3. 8/5/64 0 --
2 8/10/64 5 81.5
- . , 3 10/6/64 62 69.3 4 11/18/64 105 63.8
.5 1/28/65 176 52.8 On January 28, 1965, the analysis of the .84 MeV peak was completed.
The half-life of the peak was 275 days which corresponds to the half-life of Mn-54 of 280 days. (See Figure VI.)
This isotope became dominant during the year because of the decay of S..horter lived isotopes which previously masked any evidence of the lln-54 gamma photopeak.
- Figure V is the gana spectra of the sample number E-3445-A, the spectra oearly shows the dominant peak at .84 MeV. Also identified are Ce-141, 144
... 7, 4 .14 MeV, Cs-137 .66 MeV, and K-40 1.46 MeV. The K-40 is a naturally occurring isotope.
i
,. .27
" "FIGURE V GAJmmA SPECTPA OF ENVIFOM!ENTAL SAMPLE 4-,.07 MeV E.vironmentaZ Sample E-3445A i .14 1eV " .84 MeV "
.66 Me'!
1 8' " "" "a'
++
I0
-.. ,- I . . . .I I 102 I.. . ".' .
(t20 40 60 8010
.. hannel
I UK 0 28 FIGURE VI I HALPLIFE OF M'n-54 KaMR~fO1'TlNITAL SAMPLE)
V 4J
'7 U) 41 U
0 50 100 150 200 250 300
-Days
29 t
IX. AIR SAIMPLES A.*.
During the Spring of 1961, a continuous monitor was put into operation at the IRL gatehouse to sample the airborne activity in the environment. Our results are compared with those reported by the Public Health Service at Trenton, New Jersey.
The results from both locations are approximately the same for the average long lived particulate airborne radioactivity concentrations. Maximum and minimum values differ due to the difference in sampling periods, one week com-pared to one day.
An increase in environmental radioactivity can be seen (Figure VII) during of the early part of 1963. This increase of activity was due to the resumption nuclear weapons testing by the Russians in September of 1961. All isotopes identified were fission products which are indicative of fallout.
The downward trend of environmental radioactivity was noted during the latter part of 1963, and continued through 1965.
B. LOCATION: IRL GATEHOUSE CODE NO.,: FPA 21 Year Season No. of Samples Averag Maximum Minimum 1961 Spring 26 9.7x10-13 2.9x10- 12 l.lxl10 1 3 1961 Fall 25 4.4xl10 12 l.4x10-1 1 l.2x10-1 3 1962 Spring 26 4.1x101 2 8.0x10-1 2 l.-5x10-1 2 1962 Fall 25 2.7xl10 12 l.1x10-11 3.7x10-1 3 12 1963 Spring 26 5.8x10'12 l.1x10-11 2.8xl10 1963 Fall 26 1.4x10-1 2 7.3x10-1 2 l.6x10-13 14 1964 Entire Year 28 7.2x10-13 5.1x10-12
- 1.5x10-13 1965 Entire Year 46 5.3x10-1 3 1.0X10-1 2 <5.0xl10
I
- 30 FIGURE VII IAVERAGE CONCENTRATION OF AIR SAY4TPLES 3 V.1..
10-11 Resumption of
-Nuclear Weapons I ° *, . 1
'44 I
I.... U0 ,
I 10-13
,1961 1962 1963 1964. 1965 1966 0 PAM 21 Gthueat TRL
)Health Service at Trenton, N. J.
- £ 31 C. LOCATION: HEALTH SERVICE, Trenton, N. J.
Concentration (tc/ml)
Year Season No. of Samples Average Maximum Minimum 1962 Spring 71 4.0x10- 1 2 1.lxlO-10 1 2.7xi0- 1 3 13 1962 Fall 152 ,4.3x10- 1 2 3.0xlO 1 1 1.1xlO-1963 Spring 158 7.4x10- 1 2 1.8x10 1 1 3.1x10- 1 3
.1963 Fall 154 3.6x10- 1 2 l.2x1O-1 1 5.0x10- 1 3 1964 Entire Year 268 6.5x10- 1 3 1.4xlO- 12 4.8x10- 13 1 3 13 13 1965 Entire Year 269 2.2xlO- 2.9x10- 1.OxIO I
I-
I.
NEW JERSEY STATE OF ENVIRONMENTAL PROTECTION
- ..DEPARTMENT DIVISION OF ENVIRONMENTAL QUALITY
- BUREAU OF RADIATION PROTECTION'
- V..
.ý A .St.~t.
I- * ..
ENVIRONMENTAL-RADIOLOGICAL SURVEILLANCE PROGRAM I
I I)irector David McCurdy, J~ohJ . Russo Ph.D.
of Radiation Protection Laboratory A. ". .
- o*..-.. i,<'.."... . ::i*
Chi~ef B~ureau or Radiati.on P'rotection May 1971.
PREFACE Department The Bureau of Radiation Protection of the New Jersey of Environmental Protection has maintained a state-wide radiological environmental surveillance pro.gram since 1958. The original objective of this program.was to quantify radioactivity levels in the environment occurring terrestrial radionuclides and from resulting from naturally testing fallout. With the increased utilization of.
nuclear weapons of nuclear radioactive materials by industry and the development power, the Bureau modified its program to emphasize the determination of radioactive materials to the environment from of possible releases these nuclear facilities.
This report presents a summary of environmental radiation surveillance data gathered by the Bureau of Radiation Protection:
Since the total amount of data is voluminous, during the past year.
presented in a short concise form with little the information is elaboration. A brief summary is given starting on page 32.
I.". .. . . . ." :..... , . ".. " ".: . * * "."t" ' .. .
VIM I . .: . . ' .. .): .-...,
ii
1
- 2. Industrial Reactor Laboratories, Incorporated
.2a. Facility Location The Industrial Reactor Laboratories, Inc. (IRL) is a
-multipurpose complex located on a 300 acre plot east of
.. Princeton, New Jersey. The site is located in Plainsboro V Township in the southwest corner of Middlesex County, New Jersey and lies between Trenton and New Brunswick.
I . The site is crossed by three streams flowing in a south-westerly direction with the main branch of Devils Brook passing approximately 200 yards northwest, another branch 1
S.passing some 800 feet to the south, and the third
..along the northwest boundary parallel to the Pennsylvania flowing II Railroad.'
- The 10 mile surrounding area is primarily a sparsely
...... :populated' agricul~tnral,.axen. 'Tbe ,neares t population center.
is Princeton located about five miles west of the facility.
major populated areas are.;-Hightstown and New Bruns-wick.located six miles, southeast of the site and eleven ii~
- : :*LI U". . .
miles. northeast of . the site, respec.tively. .....-.
" ...." /......*..
2b.. Facility-Description . ......... ...
" The Industrial Reactor Laboratories, Inc. complex is ii
..currently I:The owned and operated by the Cambridge Nuclear Company of 575 Middlesex Turnpike, Billerica, complex consists of a research reactor,, support and Massachusetts. N
-research laboratories, and laboratories utilized for the preparation of radiopharmaceuticals. The reactor is a 5
... megawatt pool-type research reactor, which is classified as a light-water-moderated, heterogeneous solid fuel I " :'...reactor. The Cambridge Nuclear Radiopha~rmaceuti~cal Company -...
I' utilizes a "hot" laboratory for the preparation of technetium-99 metastable and-xenon-133 for commercial sale to hospitals r
-...engaging in diagnostic. studies., Technetium-99 metastable
.is effectively used in the diagnosis of tumors of.the brain, salivary gland, and the thyroid, and as- a serum albumen agent for- scanning human placenta and cerebrospinal fluid distributions. Xenon-133, being a radioactive. noble gas, is primarily employed in pulmonary studies involving
. he diagnosis of bronchial.carcinomas, cardio-pulmonary I.
!disorders and scanning blood circulation in the brain.
"2c. Surveillance Program The results compiled in this report were obtained from I "
-. a pre-1971 environmental surveillance program which has been
".. currently modified. The previous program was established
.1957 and mainly consisted of collecting water, bottom sediment, soil, and vegetation at eleven sampling stations,
.. from two adjacent dairy farms, Perrine Dairy Farms, Perrine and milk in 4
Road, Plainsboro, and Walker-Gordon Products Distribution, Princeton Road, Plainsboro. Milk analysil was discontinued in 1968 when the aforementioned dairy farms cessated the i
I production of milk or became uncooperative.
. I I
1 ii.)
~i. listed The collection stations maintained during 1970 are in Table 16 and shown on a general map of the I! surrounding-area, Figure 10.
were the collection stations on Devils Brook which passes approximately 200 yards from the facility.
Of particular importance Low-level
'I processed radioactive liquid wastes (liquids containing a total concentration less than, 10-7pCi/cc) are normally discharged onto a plot of groundsituated behind the ii facility known as the berm area.
radioactive liquids may move laterally Consequently, the as well as vertically I. *to the various watersheds. However, seepage of radioactive.
21 material into Devils Brook or aquifers would depend upon several parameters, mainly, permeability of the soil, moisture content (a variable which fluctuates~with the
,soil I
II season),. water capacity of the soil
'/.dilution of applied liquids by-soil moisture, ion exchange at the time of discharge, I.
- n -
'capacity ,o.f ýthe .varios
.,Iife of the radionuclide.
lsye~rs ýolfclay and sand loam
.substratum typical of t1his area,' and.the physical half-
- ..... L L ... In-order to proc.ure a profile of the distribution of radioactivity along the Devils Brook and the-Millstone River,
. three collection stations (125403, 125401, 126601) were .
-.... maintained along the stream and-two stations (116501, 183601,)
were selected on the Millstone River downstream of the
- confluence of Devils Brook.: One additional station was -
- selected on the east branch of Devils Brook (125402).
II Specimens collected
- sediment,. soil, for at these sites and vegetation.
gross alpha and beta activity, included and tritium.
water, bottom Water samples were analyzed The remaining II -sample types were analyzed for gross alpha and beta activity
.- - -. .. . - *. S S
- - At the four remaining off-site stations (125406, 125405,
.125407, 125404), soil and vegetation samples were collected
" and analyzed for gross activity
-. as an indication of airborne
" . deposition. -- In addition,. soil and plant specimens were ii a ..- . *.
usually collected area very close to established simultaneously with water specimens at water collection stations.
an 2 0 As pointed out by Sedlet, et. al.( ), grass and.soil.....
II sampling can be utilized
- ".-.releases of radioactive to delineate particulates the path of airborne and halogens.- Vegetation, indicator of
.- especially grass., has proven to.be a sensitive II *,
-"fallout and of iodine release.and S.to the IRL facility,
.from three atmospheric releases sources, the exhaust hoods of the "hot" cells, deposition. In regards are generated Tfl the exhaust hoods of the laboratory, of the reactor from the "hot" cells facility. Radioactive airborne and the discharge stack would include technetium-99 metastable releases and its parent, molybdenum-99 (66 hour7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> half-life). The radio-active noble gas xenon-133 constitutes the major atmospheric release from the research laboratory section. Ventilated
- -29-":
exhausts from the laboratory and "hot" cells are passed through absolute particulate filters prior to release
.. into the atmosphere via stacks on the laboratory buildings.
. . The radioactive activation gas argon-41 as well as the
" fission gases of xenon-133 and 135 constitute the major gaseous.
releases from reactor operations. Radioactive airborne
. . particulates of concern include strontium-89 and other
.,.short-lived fission products. However, airborne particulate
.. releases are kept to a minimum by passing the airborne I.. " "exhausts through absolute particulate and ch-arcoal filters
. before discharging them-to the atmosphere through a stack I -eighty feet above ground level.
Since radioactive wastes aredischarged to the surface
" soil at the IRL facility, seepage of radionuclides into
, adjacent municipal ground water supplies is a possibility.
. -Although geological and hydrological studies have established
' that radioactivity moves at a very slow rate through geological'.
formation, the relatively long operation time of the facility I " may be sufficient to cause radioactivity to be transported to. the various water. supplies. .Ground water sampling of the nearby watersheds within a seven-mile-radius of the 3 Z*/'facility was maintained through the cooperation of five municipal water companies. One liter samples of treated
"" water from the water-companies were routinely mailed to this Bureau on.a monthly schedule. -Potable water was also -k
- . ""sampled from the. facility's well (station 125408) at three separate intervals, during,1970. Potable water from the Sfacility as well as the municipal water companies were analyzed for gross alpha and beta activity. -_ * . ..... ',-.
Results ... .. . - ". - :
Gross alpha and beta concentrations measured in stream water
... . samples during 1970 are summarized in Table 17. In no instance
.. did the-.gross beta concentration of surface water in the IRL area exceed 10 pCi/liter. At the most northernly station (126601),.
- -;located approximately two miles above the-facility, the average
, ... gross beta concentrations was found to be 8.1 pCi/liter or
.......,-approximately twice the concentrations -measured at the Devils Brook station 125403 located downstream of this site. : The two.
tributaries of the Devils Brook drainage basin ranged in 6 S .concentrations of 1.4, pCi/liter at station 125401 to 8.2- pCi/liter at station 125402. The annual 8 concentrations of the main stream of Devils Brook at Shalks Road- (125403) fell between the tributary.
Ivalues, 3.9 pCi/liter.
were consistent with those measured at station Activity levels in the- Millstone River 125403 before-the confluence of the east branch of Devils Brook into Devils Brook.
At the Millstone River station 116501, three miles downstream of station 125403, the annual gross alpha and beta concentrations were 0.8 and 3.8 pCi/liter, respectively. Activity levels in the river at Route 27, the most distant downstream station (183601), were similar to those measured in main stream of Devils
-Brook. During 1970, a portion of the water specimens from six
,.collection stations was filtered and submitted for tritium S. analysis. As indicated by the results presented in Table 17, tritium levels in surface water at these sites were less than 1500 pCi/liter. In all cases, radioactivity levels measured in surface streams were below permissible concentrations for unidentified radionuclides as well as potable water radioactivity criteria. It is felt that water concentrations in this area
. typify radioactivity levels of small unpolluted streams of the
- . surrounding area. For example, the gross a levels in Stony Brook in the Pennington area ranged from 7 to 10 p'Ci/liter during this sampling period. Furthermore, radioactivity levels
.of the upper Delaware River (See Table 3) were approximately of the same magnitude.
.Results of radioanalyses performed on potable ground water samples of the five adjacent water companies are presented in
- Table 18. The outlining potable well water supplies were found to contain higher gross beta concentrations than the IRL supply, but were below five pCi/liter in all cases. The average concentra-
- tion of three well water samples from the IRL facility was <M.S.
for alpha and 1.9 pCia/liter (See Table 17.). Based on an annual average radioactivity content, all potable water supplies met the U.S. Public Health drinking water criteria for radioactivity.
- Gross a concentrations of bottom sediment collected at the water stations were typical of silts in this area. The annual average gross a concentrations ranged from a minimum of 31 pCi/
gram at the Devils Brook at Penn Central Railroad (125401) to a maximum of 50 pCi/gram at Devils Brook at New Road (126601). The mean beta concentration for this area was 40 pCi/gram, whereas the.
average gross alpha concentration was found to be 14 pCi/gram.
Measured radioactivity content in bottom sediment was similar to concentrations found along the upper Delaware River (see collection stations 195601, 211202, 218001, 217601, of Table 3) and Stony Brook in the Pennington area. Bottom sediment from the Stony Brook at Route 569 in Lawrence Township, Mercer County contained S g..*oss alpha and beta concentrations of 16 and 34 pCi/gram, respectively. These values are consistent with sediment activity
.. concentrations in the IRL area. . .. * -
. . . -* . , I- .. .2..- .
...... Vege.tation samples collected at ten collection stations ranged in gross beta concentrations from 130 pCi/gram-ash at station 125407 to 480 pCi/gram-ash at station 125405. Gross alpha concentrations in vegetation were almost 40 times less than the measured beta activity. The range of gross alpha concentration was 5 pCi/gram-ash at station 125403 to 12 pCi/
gram-ash at station 125407. During 1969, the average gross beta activity levels in vegetation at stations 125407 and 125405 were *
. 288 pCi/gram-ash and 300 pCi/gram-ash, respectively. As a comparison, vegetation specimens (grass and weeds) collected at six collection stations in the Pennington area ranged in gross beta concentrations of 170 to 380 pCi/gram-ash. Radioactivity levels in this area are not influenced by radioactive discharges from nuclear facilities and thus are indicative of the
accumulationof atmospheric fallout and natural radioactivity.
Radioactivity levels at these stations were statistically similar to those-measured in the IRL area.
Soil collected at the IRL sampling stations was found to contain gross alpha and beta concentrations less than 11 and 30 pCi/gram, respectively. The minimum a concentration of
" 16 pCi/gram was measured at station 125403 on Devils Brook at Shalks Road, whereas a maximum of 30 pCi/gram was noted at.
"Dey Road at Scotts Corner (125407).. For this particular area, the ratio of gross beta to alpha concentrations in soil was 3.6.
"For the six collection stations maintained in the Pennington area, the ratio of B/. in soil was 4.9.
m -.
- I.
I I. 4
- 9. . .
I.
I
- ,. * -... ,~ .- - - - -
I - -
I -
Stations Area Denoting Environmeý.ttal Collection.
Figure 10 .. Geteral M4 of Plainsboro I.-
Pr n e o-Cranbury Rd.: -
Table,. 16
.Industrial Reactor Laboratories, Inc.
Monthly Environmental Surveillance Location # Description Map #
.11-65-01 Millstone River at U.S. Rt.#1,. " Site #1 Penns Neck 1 2-54-03 Devil's Brook at Shalks Rd., *Site #2 Plainsboro 12-54-01 Devil's Brook along Penn Central. Site #3
.R.R., 0.5 miles north of Shalks Road,.Plainsboro 12-54-02 East Branch Devil's*Brook at Site # 4 I.R.L. driveway, Plainsboro 12-66-01 Devil's Brook at New Road, Site #6 Monmouth Junction 12-5 4-04 Intersectionat Perrine and Site #7 Shalks Road, Plainsboro 18--36-01 Millstone River at State Rt.#27, Site #8 Kings-ton 12-54-08) I.R.L. Well #1, Pick up at -Site #9 desk (Call ahead 799-1800) 12-54-06 Left bend of Friendship Road Site #10 12-54-05 Intersection of Scotts Corner Site #11
& Friendship Road 12-54-07 Dey Road at Scotts Corner Site #12 .. . . . -- .5.. -.
. .... '-31c-...
-Ta: l' 17 Industrial Reactor Laboratories, Inc. 1970 Environmental Monitoring Results Alpha Beta 3H Station-Location Tp Samples 6 Samples 6" 2 16501 Millstone Water <M!
(pCi/liter) Avg. 0.8 Avg. 3.8 <M.
iver at *Max. Rt.#1l 1.7 Max. 6.3 JMap #i
'I Mini. <M.S. Min. 2.3 Samples 6 Samples 6 Silts (pCi/gram) Avg. 18 Avg. 36
" Max. 28 Max. 46 Mini. 11 Mini. 32 Soils Samples 3 Samples 3
. Avg. 21 (pCi/gram) Avg. 5.1 Max. 99.1 Max. 26 Min. <M.S. Min. 13 Samples 3 Samples 3 Vegetation Avg. 6- Avg. 290 (pCi/gram-ash)
Max. 9.5 Max. 360 Min. 1.2 Min. 230 Samples 6 Samples 6 25403 Devil's Water*
Avg. <M.S. Avg. 3.9 <1
,ok at Shalks Rd. (pCi/liter)
Max. <M.S. Max. 6.1 12 Min. <M.S. 14in. 2.7 Samples 6 Samples 6 Silts Avg. 14 Avg. 39 (pCi/gram)
Max. 31 Max. 44 Min. 6 Min. 24 S.. Samples 3 Samples 3 Soils Avg. 3.7 Avg. 16 (pCi/gram)
Max. 5.5 .Max. 20
.'Min. 2.6 Min. 11 Samples 3 Samples 3" Vegetation Avg. 5.1 Avg. 260 (pCi/gram-ash) 260 Max. 8 Max.
Min. <M. S. Min. " 260 Samples 6 Samples 6 125401 Devil's *Water Avg. .8 Avg. 1.4 < M, Brook at Penn. (pCi/liter) 2'2 Max. 3.1 Max.
,Central R.R. Min. <M.5 . Min. .<M.S.
- 3 Samples 6 Samples 6
- Silts Avg. 9.1 Avg. 31 (pCi/gram)
Max. 14 Max. 43 Min. 5.8 Min. 22
table 17(continued)
-lph a Beta
ýType "tion-Location Samples 3
.Soils Samples 3 Avg. 22 25401 Devil's Avg. 3.9 Max.- 30 (pCi/gram) Max. 5.9.)
rook at Penn. Min. 18 R.R. Min. .3.1 entral Map #3 Samples 3 Vegetation Samples 3 Avg. 430 Avg. 11 730 (pCi/gram-ash) Max.
Max. 25 Min. 120 Min. 1.8 6
Samples-S25402 East Bra Samples 6 . 8.2 2
<M.S.
Water Avg.
nch Avg. 0.4 (pCi/liter) 1.0 Max. 9.7 <H.S.
evil's Brook Max. 7.0
. Min.
map #4 Min. <M.S.
Silts Samples 6 Samples 6.
Avg. 14 Avg. 41
- (pCi/gram) Max. 4.8 Max. 8.7 Min. 2.7 Min. 4.4 Samples 20 Soils 3 Avg. Samples 3 Avg. 5.5 (pCi/gram) Max. 26 Max.- 9.4 13 Min.
Min. 2.6 Samples 3 3 Vegetation Avg. Samples 260 h) Avg. 8.3 (pCi/gram-asl Max. 380 Max. 16 1.4 Min . 93 Miin.
Samples Samples 2 Avg. 8.1 2
.126601 N.W. Branch Water Avg. <M.S.
(pCi/ liter) Max. 9.7 i Devil's Brook at Max. <M.S. Min. 6.6 Min. <M.S.
New Road Map #6
- Samples -2 Silts " Samples .2 ]Kvg. 50 Avg. 16 Max. 64 (pci/gram)
... :.Max.
% 16 Min. 16 3 samples S 3 Samples Avg. 19 Soils Avg. 4.7 (pCi/gram) Max. 26 Max. 8 15 Min.
." Min. <M.S.
Samples 3 .'
Avg. Samples 310 3 Vegetation Avg. 9.4 (pCi/gram-ash) Max. 400 Max. 6.8
-Min. 250 Min. 1.6 0
-3.-
" Table 17 (continued) 3H Alpha Beta Type 3 t tion-Loc'ati~on . ~ Samples "Soils " Samples 3 Avg. 20 125404 Intersection (pCi/gram) Avg. 7.6 Max. 22 f Perrine and Max. 9.2*2 Min. 17 halks Road Min. 5.2 Map # 7 Samples 3 Vegetatior Samples 3 ,Avg. 300 (pCi/gram-a ash) Avg. 6.5 Max. 370 Max. 12 260 Min.
Mini. <M.S.
.Soils Samples 3 3 Avg.: Samples 29 125405 Intersection Avg. 5.6 (pCi/gram) Max. 38 f Scotts Corner, Max. 11 2.,6 Min. 23 riendship Road Min.
"*ap" l. Samples Vegetatioin Samples 3 Avg. 480 3 (pCi/gram- ash) Avg. 9.4 500 Max.
Max. 13 Min.. 460 Miii. 6.5 Samples Samples 6 2l 183601 Millstone Water Avg. <M.S.
6 Avg. 5.1 <M.s .
(pCi/liter ) Max. 5.9 <M.S .
iver at Rt.#27 Max. -0.6 Min. 4.7 ap #8 Min. <M.S.
Samples Samples 6 Avg. 45 6 Silts Avg. 12 (pCi/gram) Max. 54 Max. 15 Min. 37 Min. 6.5 Soils Samples 3 Avg. Samples 29 3" Avg. 8.1
.(pCi/gram) Max. 39 Max. 8.5 Min. 24 Min. 7.4 3 Samples 3 Samples Vegetation Avg. 290 Avg. 6.4 (pCi/gram-ash) Max. 500.
Max. 10 Min. 140 Mini. 2.3 Samples 3 Samples 3 1125406 Friendship Soils (pCi/gram) Avg.
Max.
7.1 11 Avg.
Max.
23 34
.Road Min. 12 Map #10 Min. 3.4.
Samples 3 Vegetation Avg. Samples 280 3 Avg. 8.1 370 (pCi/gram-ash) Max.
Max. 12 200 Min.
Min . 4 Samples 3 Soils 11 Avg. Samples 30 3 1"325407 Dey Road Avg.
(pCi/gram) Max. 32 S*Scotts Corner Road Max. 17 Min. 27 I Map #12 Min. 3.8
- Table. 17 (continued)
.. aItion-Lo'cation Alpha Beta 3H
'Dey Road Vegetation Samples 3 Samples 3 125407 12 Avg. 130 (pCi/gram-ash) Avg.
Eat Scotts Corner Road Max. 280 Max. 200
- Map # 12. Min. 6.6 Min. 30 f,')Q Industrial Water Samples 3 Samples 3 Avg. <M.S. Avg. 1.9 2
.,ReactOrLaboratory (pCi/liter)
Max. 0.6 Max. 2.9 : .
...Well Water <M.S. Min. 1.1 Min.
.1.Map #9
",i"
-31d-Table 18 Gross Radioactivity Content in Potable Water Supplies in the
.. Vicinity of the Industrial Reactor Laboratories, Inc.
A1pha Beta 1tation-Location A11-20-01 Hightstown Water Samples 12 Samples 12 Pumping Station,. (pCi/liter) Avg. 0.5 Avg. 3.2 Sightstown Max. 2.2 Max. 14 Min. <M.S. " Min. <M.S.
S2-09-01 'Cranbury .. Water Samples 12 Samples i2 ater Company, (pCi/lit e r) Avg. 1.2 Avg. 3.5 <1 S ranbury Max. 2.9 Max. 8.5.
Min. <M.S. Min. 1.7 Samples <11. S.
t2-24-0.1 Jamesburg Water, Samples 12 12 Water Company, (pCi/liter) Avg. 2.3 Avg. 4.2 amesburg Max. 5.8 Max. 8.5 Min. <H.S. Min. <M. S.
i8-36-02 Princeton Water Samples 11 Samples 11 (pCi/liter) Avg. <M.S. Avg. 1.4 urseries, Princeton Max.
Min.
<M.S.
<M.S .
Max.
Min.
3.2
<,. S. <m S, 2
I18-72-01 Rocky Hill Water Samples 2 Samples
- er Supply, . (pCi/liter) Avg. 0.9 Avg. 1.6 1 ucky Hill Max. 1.0 Max. 2.3 Min. 0.8 Min. 0.9 a
A-A1though levels fluctuated-ar th m sensitivity of the
,counting instrument, average, concentrations were: less than one
=I;z:_-thousandths of--the maximum permi-ssible-concent-,rat-ion -allowed for off-site streams.
- During the first calendar quarter of 1971, off-site potable
- water supply wells in the vicinity of the Oyster Creek. facility contained less than 8 pCi B/liter. Gross alpha activity in the water supplies was less than 2 pCi/liter at three of the four supplies.
The alpha concentration in the water supply at the New Jersey State S Marina, Forked River, was-greater than 3 pCi/liter. All water supplies met U.S. Public Health Service's water standards for gross beta and strontium-90 content.
nEEnvironmental radiation surveillance of the Industrial :Reactor aboratories, Inc. located in Plainsboro Township has not revealed radioactivity levels in water, soil, vegetation, and bottom sediment different than surrounding areas. Gross beta and alpha concentrations at drain six age bai collection water w (ereeo stations n of ~/iersetvl.
the Devils Brook and Millstone Wtr e River specimens from the Millstone Rive~r contained beta activity averaging less than six pCi/liter during 1970. Tritium concentrations in Devils drookand the Millstone River were less than 1500 pCi/liter. Five potable well water supplies in the immediate area of the facility contained gross beta activity less than five pCi/liter. All pctable weli water supplies met radioactivity criteria for public water supplies 1 The well supply utilized by the IRL facility contained gross activity concentrations below values measured in the surrounding municipal water supplies.
Radioanalysis of bottom sediment specimens collected at the IRL water collection stations revealed gross concentrations less than 50 pCi s/gram and 18 pCi a/gram. Radioactivity levels of bottom sediment were similar to those measured along the upper Delaware River and Stony Brook in Pennington .To*.znship. There was no apparent difference in radioactivity concentrations of sediment from Devils Broo and Millstone River.
1 The variance in the radioactivity content in soil collected at the ten IRL stations was very small compared to other specimens Gross beta activity in soil ranged between 16 and 30 pCi/gram at nine of the ten collection stations. The gross alpha concentration iw soil was less than 12 pCi/gram for all stations.
During 1970, radioactivity content of local weeds and grass was
- smiarto concentrations measured during 1969. Vegetation samples ollected at ten collection stations ranged in gross beta concentrations from 130 pCi/gram-ash to 480 pCi/gram-ash. The range of b concentratiot of vegetation near the v IRL facility was similaro to concentrations easured in vegetation collected at six collection stations in the Pennington area during 1970. No unusually high radioactivity levels Pen noted during 1970.
I k
~
14*° El I
RADIATION LEVELS 1971"ENVIRONMENTAL STATE OF NEW JERSEY I'
I IN TLE By David E. McCurdy, Ph. D.
4 I
I I'
'1 II IJ PROTECTION
-I " NEW: JERSEY STATE DEPARTMENT OF ENVIRONMENTAL QUALITY DIVISION OF ENVIRONMENTAL BUREAU OF RADIATION PROTECTION LABORATORY SECTION I *4
incorporation of radiocobalt has been associated with the dissolved fracti0 .
of the nuclide. The areas affected by the aqueous discharge plume coincide with the Bay circulation patterns measured by-Carpenter in 1963.
Radionuclides associated with liquid effluent discharges, of the Oyster, Creek NPGS have been measured in bottom sediments of the'Oyster Creek, Forked River, and Barnegat Bay. The greatest concentrations were measured 13 in Oyster Creek during June. The reactor-oriented nuclides detected were jf 6 0 Co, 5 4 Mn, 5 8 Co, and 1 3 7 Cs Sediment specimens from eighteen stations throughout Barnegat Bay collected during October have-been analyzed and the data reported within the text. Bay sediments containing the greatest Il activation products were found at stations nearest to the Oyster Creek Bay inlet. A significant correlation between the organic content of the Forked River sediments and radionuclide content was developed. The factý that aqueous effluents are recirculating has been proven by the presence of radionuclides in the sediments of Forked River. Cobalt-60 sediment concentrations of the order of 20,000 pCi/kg-dry have been observed in Oyster Creek near the area of established commercial boat marinas.
significant Only three levels reactor-oriented radionuclides have been detected in in hard clams of Barnegat Bay. The radionuclides measured were 6 0 Co, 5 8 Co, and 5 4 Mn. Typical 6 0 Co concentrations in clam meat ranged from 40 to 470 pCi/kg-fresh in five areas of the Bay monitored.
Cesium-137 was also detected in several of the specimens collected. The total man-rem dose resulting from the ingestion of clams consumed during 1971 has been estimated as: 60Co - 2 man-rem; 5 4 Mn - 0.2 man-rem; 1 3 7 Cs -
0.6 man-rem. Specific details of the population dose calculations have been presented within the text. Radionuclide concentrations in shellfis',
crabs, and fin-fish were 1/100 to 1/10,000 of permissible concentration.-)
recommended by the Federal Guidelines.
Aqueous radionuclide levels below the Oyster Creek discharge point were found to be less than the sensitivity of detection, '5 pCi/liter, for I most gamma-emitting radionuclides.
waters ranged from less than 0.2 to 0.7 pCi/liter The dissolved radiostrontium in bay concentration in Oyster Creek, Forked River, and Barnegat Bay was below during 1971. The tritium 800 pCi/liter. Radionuclide levels in Oyster Creek were well below maximum permissible concentration values established by the Atomic Energy Commissior Locally grown food products and wildlife specimens near the Oyster Creek NPGS were found to contain no reactor associated radioactivity.
Radiocesium was measured in both cranberries and white-tailed deer from the immediate area.
Preoperation surveillance of the Salem Nuclear Power Generating Static was begun in 1971. Background radioactivity measurements have been perforr
- on surfacewater, sediment, locally produced food produce and raw milk, anc potable water supplies. The acquired preoperational data has been present(
in this report.
A moderate surveillance program was maintained for the Industrial Reactor Laboratories, Inc. at Plainsboro, and the Medotope Division of E. R. Squibb and Co. at New Brunswick. The radionuclides detected in the surface water, sediment, and food produce were related to stratospheri) fallout rather than to the facility. No radionuclides associated with radiopharmaceuticals of the Squibb facility were detected in food produce of the Agronomic farms maintained by Rutgers University.
IV.C. Industrial Reactor Laboracories,_, Incorporated
..... The Industrial. Reac-to~r La.oratories,. Inc.. complex, located in Plainsboro Township:.-b~etween Trenton- and..New-.Brun.swick, is currently owned
. -a-bndoperated by -the._Camrbridge'Nuclea, . Companyo.f 575 MiddesexTurnpike, Billerica, Massachusetts. The complex consists of a research* reactor with support and research laboratories,. and laboratories utilized.for
..the preparation of radiopharmaceuticals on a commercial production basis.
The reactor is a 5 megawatt pool-type research reactor, which is classified as a light-water-moderated, heterogeneous solid fuel reactor.
The:Cambridge Nuclear Radiopharmaceutical Company utilizes a "hot".
laboratory.for the preparation of technetium-99 metastable and xenon-133 for commercial sale to hospitals engaging.in diagnostic studies. A more
. .detailed description of the facility ha*. been presented in the 1970 2 9 annual report.( )
IV.C.I. Surface Stream. Surveillance 3 a total Low-level processed radioactive liquid wastes (liquid containing concentration less than 10-7 ujCi/cc) are normally discharged ontc a plot of ground situated behind the facility known as the berm area.
On four separate occasions, March, May, June, and December, two streams most likely to be affected by the aqueous discharges to the Industrial Reactor Laboratory's Berm area were sanipled. Of particular importance were the collection stations of Devils's Brook which passes approximately 200 yards from the facility. Two areas along Devil's Brook were sampled
.during this report period; one at.. the upper section of the stream at New Road utilized as a background area (Map No. 6 of Figure 22), and 3 one below the confluence radioactivity of Shallow Brook (Map No. 2). The dissolved content of Devil's Brook at these two points was below one pCi/liter gross alpha and 10 pCi/liter gross beta (See Table 50). Duriný December, the gross alpha and beta concentrations of the stream was similar for both areas (<1 pCi a/liter and 5 to 6 pCi -/liter). Isotopic gamma analyses of the water specimens during May.revealed no measurable quantities of gamma-emitting radionuclides (<10 pCi/liter for most radionuclides with a gamma abundance of one). The water concentrations of Devil's Brook were very similar to measured concentrations of its tributaries. The various tributary branches sampled included: one on t
.. East Branch near the facility (Map No. 4), and one along the Penn Centra:
.,Railroad north of the.facility (Map-No. 3). Table 50 summarizes the.
" results obtained for the various streams.
Since Devil's Brook flows into the Millstone River near U.S. Route I after passing through Gorden's Pond, two surveillance stations were I maintained along this stream; one below the confluence of the two.
streams and another at a downstream site near Route 27. Except for the month of June, the radioactivity concentrations of the Millstone River and Devil's Brook were of the same. magnitude. During June both the grosf alpha and beta water concentrations of the Millstone River at Route 1 were a factor of three greater than typical values, of the other months.
- No- measurable quantity of gamma--emitting radionuclides was detected in this sample..
The tritium level of the various streams was below 1,000 pCi/liter.
for most samples analyzed during this period. The different reporting levels for tritium reflect the minimum sensitivity of the analytical technique. Analyses earlier in the year (March) were based upon a using a 200-minute time period.
The strontium-90 content-of-tthe East-Br:anmch .Devil-'s Brook during December was '1.OO.+/-.3 pCi/liter. As a comparison, the 9 0 Sr concentration at the IRL Berm area was 0.4t0.3 pCi/liter during the same month.
1
m m 2- m - - --. - m- --... Envi ronmen
-D-i- m-C Figur 22. Geberal Map of"Plainsboro Area Denoting Environment~al Collectiton St~ations"
.IV.C.2. Potable Water Supplies:
Since low-level aqueous radioactive liquids are discharged to the surface .soil known as the berm area at the IRL facility,,
seepage of radionuclides into adjacent municipal ground water supplies is a possibility. However, intrusion of radionuclides into the surrounding aquifers would be very unlikely since it depends upon such parameters as permeability of the soil, soil moisture content, water capacity of the soil at the time of discharge, dilution of applied liquids by soil moisture, ion exchange capacity of the various layers oi clay and sand loam substratum characteristic of this area, and the physical half-life of the radionuclide.
I Ground water surveillance of the nearby watersheds within a seven-mile area encompassing the facility
.through a mail-in program in cooperation with five municipal was accomplished water companies. On nine separate occasions, samples of treated and untreated (raw) water specimens were sent to the Trenton laboratory for radiochemical analysis. Each specimen was routinely tested for gross alpha and beta activity and occasionally for tritium. Specific radium and radiostrontium analyses were performed on selected samples if the gross activity screening tests indicated high gross alpha and beta activity.
The summarized results of radiochemical analyses for potable water supplies adjacent to the Industrial Reactor Laboratories, Inc. are presented in Table 51. Four of five municipal supplies show consistently elevated gross alpha concentrations but "spot" radium determinations indicate that radium levels are below 3 pCi/
liter for most supplies. A more detailed discussion of results
.for the South Brunswick Municipal Water Supply is presented in Section III.B.. under State-Wide Potable Water Surveillance.
The strontium-90 and tritium content were less than 5 pCi/
liter and 1,000 pCi/liter, respectively for the samples tested.
The potable water supplies were within annual average permissible drinking water concentrations as stated by the U.S. Public Health
,......Service. A further investigation of South Brunswick Municipal
.Supply will be initiated in 1972.
INOUSTRAIL REACTOR LABORATORIES, Ic-. 1:971 IN THE VICINITY O THE ABLE 50 SuRrACE STREAM CONCENTRATIONS RADIONUCLIDE CONCENTRATION PC I/L GRoss GROSS io6Ru 13 7 Cs 140 OTHER.
ZO LLECT ION COLLECT ION 95zR BA ALPHA BETA 90s RH# DATE o LOCAT ION <1000 15558 12-6 1:.3o.5 N10.~09 tAST BRANCH 2.0-0.5 0 DEVIL'S ROOK AT IRL AP #4 <2000
<2 <60 <5 DEVIL'S BROOK 14568 3-23 AT NEw ROAD HAP #6 4 11 0.7-0.3 8.2o0.7 <2 <5 11734 5-11 :0.5-+0.2 DEvIL'S BROOK 6.9-o0.7 AT NEW ROAD HAP #6 <1000 5+0 1556o 12-6 077,.7 DEVIL'S BROOK 0.3-0.3 5.9-0.7 AT NEw ROAD HAP #6 I 14741 5-11 0.5 6. oto .7 6.o-o.7 MILLSTONE RIVER 0.5 AT ROUTE 27, KINGSTON MAP #8 6.5-+0.7 14746 6-23 0.7-0.5 <2 q~,5 MILLSTONE RIVER 0.5 8.:0-.7 AT ROUTE 27, KINGSTON MAP #8
---6o .:5 <8oo 12 .6o.8 <2 111937 6-23 2 +
BERN AREA Or 13.3-1.0 <'1000 .0.11+/-0.3 9051 IRL DISCHARGE 12-5 1.51o.6 9.1-t0.7 BERM AREA or 15569 IRL DISCHARGE T4,-7-154-1 44 71
- - - - - - - - - - -* m --
, mm: -mm u TABLE 50 SURrACE STREAH CONCENTRATIONS IN THE VICINITY O0 THE INOUSTRAIL REACTOR LABORATORIES, INC.' 1971 RAOIONUCLIDE CONCENTRATION PCI/L ,
COLLECTION GROSS GROSS COLLECTION lo 6 Ru 137 LOCATION RH# DATE ALPHA BETA 95ZR cs oBA OTH4ER o.6to.14 MILLSTONE RIVER 114550 3-23 7.61?0.7 - 2500
!AT U.S. RT. 1 0.760.4 7.8lo.7
- MAP #1
'MILLSTONE RIvtR 114728 5-11 o.6to.5 6.144 .7 < 60
- AT U.S. RT. I o.6o1 6.6-o.7 M!ap #1 MILLSTONE RIVER AT U.S. RT. 1 114926 6-23 8+. 19 oz : '.60 "-5 800 MAP /1 MILLSTONE RIVER 15563 12-6 -. 1000 AT U.S. RT. 1 MAP #1 DEVIL'S BROOK 14554 3-23. 2000 AT SHALKS Ro. o.61 6:5!0.7 .0 MAP #2 DEVIL'S BROOK 14729 5-11 0.6+0 . -,.210.7 -. 60 ".5 .- 1 AT SHALKS RoD 5.2-0.7 MAP #2 DEVIL'S BROOK 14927 6-23 3.010.14 '--2 -.60 *5 , -- 4 8oo AT SHALKS RD. 3.3-0.14 MAP #2
'1000 DEVIL'S BROOK 15562 12-6 0.610. 4 AT SHALKS RD. o.6+-o.14 MAP #2
- U INC. 1971 TABLE 50 SURFACE STREAM CONCENTRATIONS IN THE VICINITY or THE INDUSTR&IL REACTOR LABORATORIES, RAOIONUCLIOE CONCENTRATION PCI/ ..
GROSS GROSS 1o6Ru 137cS BA -IN OTHtI COLLECT ION COLLECT tON ALPHA BETA RH# DATE LOCATION <2000 3-2'3 0.11!0-o3 DEVIL'S BROOK 14558 0.5 ALONG PENN CENTRAL R.R.
MAP #3
<2 <6o <5 14731 5-11 a 0: 0.3 i DEVIL'S BROOK )4 9to.)4 ALONG PENN CENTRAL R.R.
MAP #3
<6o <5 <Ii 8w0 6-23 o.5to.4 2.010.J4 DEVIL'S BROOK ALONG PENN 5
1o.soo,4 CENTRAL R.R.
MAP #3 <1 000
.12-6 )4.310.6 DEVIL'S BROOK 15564 ALONG PENN CENTRAL R.R. o.8o.)4 MAP #3 0
<2AV) 3-23 0.5-0.3 EAST BRANCH 14574 *9:ý! 0.7 OF DEVIL'S
- BROOK AT IRL MAP #4 oJ o.3
- " <800*
5-11 6. 2+0.6 EAST BRANCH 14733 o.710.3 7.3!0.6 or DEVIL'S BROOK AT IRL MAP bh <5 <4i 80o 8.3 0.9 <2 -.6o 14931 6-23 0-3-0-5 I: . +0.
9.0-o.9 EAST BRANCH or DEVIL'S BROOK AT tRL MAP #4
- ~-*-- .-. .- w~A~*
Tine ** I - 1971 Summary of Radioanalyses of 'table Water Supplies,
-- Industrial Reactor Laboratories. Surveillance
- ollection Potable Water Alpha Total Radium Beta Water Date Supply Concentration Concentration Concentration Other Type pCi/l pCi/l pCi/l pCi/l 1-6-71 Jamesburg Water 1.310. 8 5. 2+/-1.2 Treated-Co., Jamesburg, NJ Well 2-8-71 Jamesburg Water 3.910.5 Treated-Co., Jamesburg, NJ Well 3-18-71 Jamesburg Water 2.6+/-0.9 4.0'0.7 Treated-Co., Jamesburg, NJ Well 3-18-71 Jamesburg Water " ' <0.5 4.2 0.7 Raw-Co., Jamesburg,* NJ Well 5-3-71 Jamesburg Water 3.3'0.8 1.0'0.3 6.4+/-0 9 Treated-Co., Jamesburg, NJ Well 5-3-71 Jamesburg Water 5.2 +/-0. 8 6.7:0.9 Raw-Co., Jamesburg, NJ Well 6-1-71 Jamesburg Water 25. 1+/-1. 7 1.1*0.*2 12.3'1. 1 Treated-NJ Well Co., Jamesburg, 6-1-71 Jamesburg Water 1.5 +/-0. 2 Raw-Co.., Jamesburg, NJ Well 6-23-71 Jamesburg Water 25.1'1.7 0. 8+/-0. 2 12.3P1.1 Treated-NJ 1.1+/-0. 2 Well Co., Jamesburg,
- 3. 2'0. 8 4.9O0.7 Treated-7-13-71 Jamesburg Water NJ Well Co., Jamesburg, Jamesburg Water 8.5*0.8 Raw-7-13-71 Well Co., Jamesburg, NJ 8-9-71 10.3'1.0 Raw-Jamesburg. Water 7.411. 0 We Ill Co., Jamesburg, NJ S-.------ --- - ~- -- -.
Tab-- 51 Total Radium Beta Water Type-collection* Pota e* Water Alpha Concentration Concentration Concentration Other pCi/i Supply pCi/l pCi/i Date pCi/l 6.7*0.7 Treated-Well Jamesburg Water 6.6'1.0 8-9-71 Co., Jamesburg, NJ 10.8*0.8 Treated-9.811.1 Well 11-23-71 Jamesburg Water Co., Jamesburg, NJ 8.3*0.9 (<1l000 3H) Raw-6.9'1.0 Well 11-23-71 Jamesburg Water Co., Jamesburg, NJ.
6.4*0.8 4.4i1.1 Treated-Well 2-4-71 South Brunswick Municipal Utilities Authority Treated-14.3*1.1 14.3'1.4 3.9*0.7 Well 3-19-71 South Brunswick Municipal Utilities Authority 1715 Raw-17'4 Well 3-19-71 South Brunswick Municipal Utilities Authority Raw-11.*6*1.9 90 4.4*1.2 Sr Well South Brunswick 9.0*1.1 10.5*0.9 4-30-71 9.7*1.2 Municipal Utilities Authority 9.7*D.9 4.7'1.1 8.3*0.9 4-30-71 South Brunswick
- 5.6*1.2 Municipal Utilities Authority 17.0*1.1 Treated-3.0*0.4 Well South Brunswick 18.0'1.6 3.3*0.2 5-28-71 Municipal Utilities Authority
~. r-~ ~
M M -m -m : - - m -m - -m -*m -* -m -m* -- U
,llecti6n Potable Water T"--51 .M Alpha Tota.L Radium Date Supply Concentration Concentration *Beta Concentration.n Water pci/1 Other ' Type pCi/I pCi/i pCi/i i-28-71 South Brunswick 20. 3'1.5 3.-7:0.5 Municipal 15.8 i 1.1 Raw-Utilities Well Authority
-- 18-71 South Brunswick 15127 1.4-0.2 Municipal 1310Treated-Utilities Well Authority 71 South Brunswick 11.311.3 Municipal Raw-Utilities Well Authority 71 South Brunswick 11.2*1.3 Municipal 11.410.9 <800 3H Treated-Utilities Well Authority 71 South Brunswick 23 *2. 3.310.4 Municipal 19.0*1.4 0.5*1.7 9 0 Sr, Raw-Utilities <1000 3H Well Authority 71 South Brunswick 22*2 2. 3*0. 3 Municipal 14.511.2 0.8l1.1 9 0 Sr, Treated-Utilities <1000. 3 H Well Authority 17-72 South Brunswick Municipal 0.610.1 Well #3 Utilities Authority 17-72 South Brunswick 3.3*0.4 Municipal Storage Utilities Tank Authority
- - - :- .-. . - m
- Tine Beta ater rotele.Water Alpha To -1 Radium
ýollection d" her Type S"bpply Concentratidni Concentration Concentration Date I pCi/i. pCi/i pCi/l pCi/1 3.210.3 Well #12*
1-17-72 South Brunswick Municipal Utilities Authority 5.0+/-0.7 Raw-5-3-71 Princeton <0.5 Well Water Co.,
Princeton, NJ 2.7*0.7 Treated-Princeton <0.5 Well Water Co.,
Princeton, NJ 3.3I0.5 <800 H Raw-5-24-71 Princeton 0.9t0.5 2.2*0.4 Well Water Co., 0.8'0.4
.Princeton, NJ 2.0+/-0.5 <800 3H Raw-7-15-71 Princeton 1.0+/-0.6 Well Water Co.,N
-Princeton, NJ' 0.410.2 41.111.7 -<800 3
.o.8,,2 Treated-*
7-15-71 Princeton 11.711.8- 96Sr Well Water Co.,
,Princeton,. NJ..
10001800 3H 3.1*0.8 Treated-8-6-71 Princeton 4.0 *1.0 Well Water Co.,
Princeton, NJ 4.3'0.8 <800 3H Raw-8-6-71 Princeton 4.31.1 Well
.Water Co.,
Princeton, NJ.,
tank. Water .is treated by adjusting
- Well #12 supplies 1,300,000 gallons per day to the.storage to the storage tank.
the pH from 4 to 5 up to 7. Well #3 supplies only 80,000 gallons per day IRI,
['; * ! : , ,; ; * ' ;
". *; i ,* ...
--- mIr-$% m,- -
ol...lection " .
ollection Potable Water Alpha Total Radium Beta Water Date Supply Concentration Concentration Concentration Other Type pCi/ 1 pCi/l pCi/i pCi/i 11-15-71 Princeton 0.5+/-0.7 1.7+/-0.5 Raw-Water Co., Well Princeton, NJ 11-15-71 Princeton 1.0t0.8 2.4+/-0.5 <i000 3 H Treated-Water Co., Well Princeton, NJ 1-11-71 Cranberry Water 4.0o1.6 Treated-Co., Cranberry, NJ Well 2-2-71 Cranberry Water
- 1.9*0.9 Treated-Co., Cranberry, NJ Well 3-22-71 Cranberry Water 7.211.1 2.1 0.6 13.5*0.9 Treated-Co., Cranberry, NJ Well 3-22-71 Cranberry Water 4.2*0.7 1.1+/-0.4 5.010.8 Raw-Co., Cranberry, NJ Well 5-3-711 Cranberry Water 4.5+/-0.8 5.2i0.7 Treated-Co., Cranberry, NJ Well 5-3-71 Cranberry Water 2. l 0.6 6.0*0.9 Raw-Co., Cranberry, NJ Well 5-24-71 Cranberry Water 2.0*0. 7 7 .510.8 Treated-Co., Cranberry, NJ Well 71 Cranberry Water 0. 810.4, 0.5*0.2 2 .90 .5 Raw-Co., Cranberry, NJ Well 6-18-71 Cranberry Water 2.8'0.9 .0.5*0.1 4.1*0.9 Well #1 Co., Cranberry, NJ (Treated:
5-18-71 Cranberry Water 1.9'0.2 Well #2 Co., Cranberry, NJ (Treated'
I- ýotg MCOaddM atawater N M ;O er-, Mm APMm A1 ..rM ncentration Concentra flon M OAR M Ty"
- oDate Concentration pCi/i1 pCi/l pCi/i
.Date Supply pCi/l Well l'&*
(Treate.
16.
6-18-71 Cranberry Water Composi Co., Cranberry,.NJ Treated
<800 3H Well 2.1*0.6
- 3.2*0.6 7-6-71 Cranberry Water Co., Cranberry, NJ Well #3 6.4*0.7 3.9*0.8 (Treate, 8-9-71 Cranberry Water Co., Cranberry, NJ 3.3*0.7 Well #1 2.2*0.5 (Raw) 8-9-71 Cranberry Water Co., Cranberry, NJ Treated-
- 3. 50. 8 <1000 3H Well 0.5*0.1 3.2*0. 7 11-16-71 Cranberry Water, Co., Cranberry, NJ 7.6*0.7
<1000 31 Raw-3.3*0.7. 0.5*0.1 Well 11-16-71 Cranberry Water Co., Cranberry, NJ Treated-1.710.5 Well 2-8-71 Hightstown Public Water Supply, Hightstown, NJ Treated-
<0. 5 1.720.6 Well 3-29-71 Hightstown Public Water Supply, Hightstown, NJ 0. 8*0. 6
<0.5 Raw-Well 3-29-71 Hightstown Public Water Supply, Hightstown, NJ Raw-1.5'0.4 2.1*0.5 Well
- 0. 7*0. 3 5-5-71 Hightstown Public 0.8*0.4 Water Supply, lHightstown, NJ 1.8*0.7 Treated-Well 0.4 0.3 5-3-71 Hightstown Public Water Supply, Hightstown, NJ Agency at Winchester, Mass.
- Analysis conducted by the u.s. Environmental Protection
- - - - - - m - -m - - - - - -¸ m m Table 51 ollection Potable Water Alpha Total Radium - Beta Date Supply Concentration Water Concentration Concentration Other Type
.pCi/l pCi/l pCi/l - pCi/I 5-24-71 Hightstown Public <0.5 1.7+/-0.5 Treated-,'
Water Supply, Hightstown, NJ Well 5-24-71 Hightstown Public 0.8t0.4 2.1'0.5 Raw-Water Supply, Hightstown, NJ Well 7-7-71 Hightstown Public <0.5 Water Supply, 1.010.5 <800 3H Treated-Hightstown, NJ Well 7-7-71 Hightstown Public 0.7*0.3 1.410.5 <800 3H Raw-Water Supply, Hightstown, NJ Well B-5-71 Hightstown Public 3.1'1.0 3H 5.311.1 lOOO800 Raw-Water Supply, Hightstown, NJ Well 3-5-71 Hightstown Public 5.5*0.9 9.110.8 <1000 3H Treated-Water Supply, Ilightstown, NJ Well L-16-71 Hightstown Public <0.5 2.810.5 Treated-Water Supply, Well:
Hightstown, NJ k-16-71 Hightstown Public 1.0'0.6 1.4'0.5. Raw-Water Supply, Well Hightstown, NJ
I . .. ...li*
i Produce ..
IV.C.3. Agricultural Reactor the immediate area adjacent to the Industrial production
'.In is sufficient agricultural Laboratories complex there Six local D in farms the summer cooperated to substantiate in our efforts, a sampling program.
to attain locally grown food corn, wheat, and barley.
produce. The produce sampled included other in Table 52, no gamma-emitting radionuclides As illustrated *in the specimens. The stated 1 3 7 Cs were prevalent 3.than possibly wheat and barley appear to be consistent
- . 1 3 7 Cs concentrations for quoted whole grain products of 30 pCi/kg with concentrations in The strontium-90 Chicago area (1968 data).
I 9 by Harley(1 ) for the was measured as 55+/-3 pCi/kg-fresh and is Content of whole wheat than values for processed whole greater approximately seven times 9
a lower 0Sr Barley exhibited grain products during 1968. (19) (21+/-8 pCi/kg-fresh).
" concentration than did the wheat specimens I.. :.
Id 4-m
. ....
- a *-t
' .. i * : :' " " *. 4*I A:j-
.1 IA
" *":. 1 i . . .
n
- *q . ., ' . . "
.IV.C.4. Bottom Sediment Sampling I....sediment As a- ca-ry --over-from- -theo-ýl9T&
was sampled from-five, areas O.survella nce- -program, bot-to-m .
adjacent to the stream I sampling stations (See Figure 22 and Table 53for station locations).
The collection schedule for the sediment sampling at these sites
..coincided to the frequency schedule maintained for the surface water collection. Sampling was greatest during the early half of 1971 and diminished somewhat during the latter part'of the year
.ue to other priorities.
Each sediment specimen was dried on a hot plate at a low
-temperature, crushed, and passed through a number 10 mesh screen.
... The type of radioanalyses.performed included gross radioactivity I concentration and specific isotopic gamma analysis. Gross alpha content measurements during 197.1 were predicated on Thorium-230 self-absorption curves, whereas, values reported for 1970(29)
I* were obtained using Radium-226 .self-absorption beta analysis were based on Cesium-137 self-absorption curves. Gross curves.
The dry-weight radioactivity concentrations *of sediment of the various streams are summarized in Table 53. Of the gamma-
... emitters evaluated, only the dry-weight content of the fallout radionuclide 1 3 7 Cs is-tabulated. With thie exception of 2 2 6 Ra I and 2 3 2 Th and their radioactive progeny, no other radionuclides were found in significant quantities. The gross beta concentrations of sediment for these streams were of.the same magnitude as the background streams near Salem, New Jersey. Radiocesium levels were, however, somewhat greater for these sediments as compared to the. Salem area (for three of the six samples analyzed).
I
- m_i - - - - - - -~i -,.. I -i .
I FROM THE REACTOR LABORATORIES, INC. VICINITY.
, IN VEGETABLES INDIISTRIAL I ABSE tc RCADI ONUCLI DE tONCCNTRATI ON 1~0 COLLECTION (PCI/KC-fR RHr-t RADIONUCLIDE CONCENTRATION
- SPEC IMEN RH# DATE LOCATION 9 5 ZR. 137 Cs 54MN 58c0 6 Oco 65ZN 134cs 131t 10BA 6o 90 80 80 ý-90 80 150 20-30 70 MINIMUM SENSITIVITY SHALKS ROAD N.D. N.D. 50+30 N.D. N.D. N.D. 90+-0 N.J). 11 .7!1 .
,CORN 15180 .8-13-71 12-5~4-12-4o N.D. 110-50 3.2!1.8 N.D. N.D. N.D. N.D. N.D. N.D., 70-'o CORN 15178 .8-13-71 SMALKs ROAD N.D. N.D. N.D. N.D. :":N.D. I 70-+4O N.D. N.D.
N.D.
CORN 15177 8-i 3-71 0DEY ROAD 12-5-lo-ko 80+30 N .0. N.D.
N.D. N.D. N.D. N.D. N.D. N.D.
CORN 15176 8-13-71 .DY ROAD N.D.-
12-54-lo-ko Dry ROAD N.D. N.D. N.D. N.D. N.D. N.D. i6o*6o CORN 15175 8-13-71 N.0.
12-54 40 N.D. N.D. 55-3 WHEAT 15132 7-28-71
- PETTY NM-D.
5t+/-I-+
ND, N.0o 15134 7-28-71 SIMONSON WHEAT N.D. N.D.
?,-+8
.-- . .- - 52!16 BARLEY 15135 7-28-71 PETTY 95 PERCENT CONFIDENCE LEVEL 9 5N.
- IN EQUILIBRIUM WITH q#7 7
Table 53, iRaýIotivity Concentrations of Bottom Sediment from Streams near IRL, 1971 Colle ction Gross a Gross 0 1 37 Cs Location Date RH# Concentration Concentration Concentration (pCi/g)
(pCi/g) .(pCi/g) 11-65-01-20 3-23-71 14551 45+/-4* 41+/-2*
Millstone River at U.S. Rt. 1 - Map #1 12-54-01-20 3-23-71 14559 26+/-9 22+/- 5 Devil's Brook. along Penn Central R.R. - 5-11-71 14732 28*4 42*3 2.5*0.4 Map #3 6-23-1rl 14930 27*5 29*3 0.040*0.005 12-54-02-20 3-23-71 14575 29*8 38*.5 East Branch of Devil's Brook at I.R.L. - Map #4 12-54-03-20 3-23-71 14555 18+/-9 27*6 Devil's Brook at Shalks Rd. - 5-11-71 14730 28*4. 4513 2.7*0.1 Map #12 6-23-71 14928 25*4 29.8+/-1.7 0.44*0.03 12-66-01-20 3-23-71 14569 30* 20 39215 Devil's Brook at New Road - 5-11-71 14735 37*4 4403 Map 116 7127-71 15015 29*4 37A2 0.0510.03 12-6-71 15561 2.9'.1.2 6.8'1.0 Errurs are at the 95% confidence level. (Dry weight)
-~ -Elio.,
FROM RUTGERS AGRoNOMIC rlELOS.
TABLE 54 RADIOACtIVITY CONTENT O1 VEGETABLES COLLECTED COLLECTION RADIONUCLIDE CONCENTRATION (PCI/KG-r*RS.H),
RH# OATE 137 Cs SPECIMEN 95 ZR* 134Cs 1311 14 BA 54mm 58co 6oCo 65ZN goS 90 70 6o 90 80 8o 8o 150 20-30, MINIMUM SENSITIVITY N.D. N.D. N.D. N.D, N.D.
N.D. N.D. N.O. N.DN.
SQUASH 15170 8-9-71 N .0.
ZUCCHINI N.0. N.D. N.D. N.D# N.D. 111!2 12!2 N.D. N.D, N.D.
PEPPER 15168 8-9-71 N.0, SWEET N.D. N.D. N.D. IlO, N.D. 6o+20 N.D.
15166 8-9-7 1 YELLOW SQUASH N.D.
N .0.D. N.D. N.D. N.D. N.D.
.8-9-71 N.D, N.D.
TOMATOE 15171 (AMPELL #132T) N.D.
N.D. N.D. N.D. N.D.. N.D. 90130 N,.D.
15167 8-9-71 N.D.
PICKLING CUCUMBER S +
N 0D. N.D.
8-9-71 N.D. N.D. N.D.
MARKETEER CUCUMBER 15169 N.D. 80.30 N.D, N .D.
N.D. N.D.
N.D. N.0.-
SWEET CORN .15165 8-9-71
I
- ASSUMING EQUILIBRIUM Of 95NB.
IS STATED fOR THE 95 PERCENT CONFIDENCE LEVEL.
pSTANDARO DEVIATION r:4--t q
Berm An area south of the IRL facility and south of the IRL access road was isolated from the general environment by the construction of earth dams. The area is a natural swamp and consists of six to eight inches of organic debris on top of a clay deposit. The clay deposit is considered to be impervious to surface water. This area was designated as the IRL berm.
IRL analyzed radioactive liquid waste prior to discharging and with approval of management discharged to the berm area.
A sampling program was established for the berm area that considers the following criteria:
- 1. Concentrations of activity is more likely -to be at discharge point.
- 2. Buildup of activity may have occurred in the organic material and in the top few inches of clay soil under the organic material.
- 3. 'Migration from the discharge point would follow the topographical features.
.4. Low points along suspected "run off" were sampled for potential buildup of radioactivity.
Samples were taken at the locations and depths listed in the final report to determine if radioactivity in the berm had built up from IRL plant operations.
Results indicate that the discharging of potentially con-taminated water by IRL has not caused a buildup of activity in the soil above 10 CFR 20 Appendix B, Table II, Column 2 limits (for the final report,units of microcuries per cubic centimeter were used instead of microcuries per millileter.)
AT(ORP
APPENDIX D Estimate of Radioactivity in Leaching Field Additional samples were taken in the two (2) leaching fields in order to determine their radiological status. The two (2) leaching fields are about twenty-five (25) feet wide and sixty (60) feet long. The tiles are one (1) foot below ground level and water table is about ten (10) feet below ground level.
Assume that dispersion of water from the tiles is in the pattern shown in the diagram below:.
S11 S4 and S7 are sample point locations at depths
- ,: ' *iJX iof 1 ft, 4 ft and 7 ft.
-N . 'j : '
Soil samples were taken at the distribution box and far ends of each leaching field at depths of one (1), four (4) and seven (7) feet. A water sample was also collected at the water table.
The water was analyzed and was determined to be less than or equal to 1.5 x 10-7 ci/ml counted as equivalent to Strontium-90 and gamma isotopes by an independent laboratory. Table 1 contains results of soil contamination:
ATCOR
Table 1 Leaching Field Soil Anal ysis Identification Depth A (pci/gm)
(ft) Co 6 0 Cs! 3 4 Cs 1 3 7 Sr 90 South Field 1 2.24 x 10-1 3 x 10-2 2.36 x 10-1 Z0.08 Distribution box 4 9.53 x 10-2 1.22 x 10-1 9.78 x 10-1 40.08 end 7 2.76 x 10-1 1.16 x 10-1 3.76 x 100 0.22 South Field 1 3.79 x 10-1 1.97 x 10-1 2.28 x 100 40.08 ar End .4 3 x l0-2 4 x 10-2 4 x 10-2 <0.08 7 2 x 10-2 3 x ]0-2 4.06 x 10-2 40.08 North Field 1 7.59 x 10-2 3 x 10-2 '4.56 x 10-1 40.08 Distribution box i4 2 x 10-2 3 x 10-2 3.63 x 10-1 <0.08 end 2 7 4.27 x 1 0 -2 3 x 10- 4.51 x 10-1 <0.08 North Field 1 5.34 x 10-2 3 x 10-2 1.97 x 100 Z0.08 Far End 4 2 x 10-2 3 x 10-2 12 1.29 x i0-0 <0.1 7 6.76 x 10-2 3 x 10-2 1.18 x 100 40.I verage NA 1.09 x 10-1 4.46 x 10-2 9.91 1k 0-1 9.5 x 10-21 The estimated contaminated volume is calculated below:
V : [(W + D) (L + D) (D)] x 2 3
V 34' x 69' x 9' x 2 '4.22 x 104 ft 3
= 5.1 x 104 gm/ft M = V.P 3 3 2.15 x 109 gin M = 4.22 x 104 ft x 5.1 x 104 gm/ft ATCOR
Table 1 (continued)
Calculation for activity C (pci/gm)
- ,r x M (gm) 4-
= A (Qci) or A mci 1.09 x 10-1 x 2.15 x 109 2.32 x 108 0.23 4.46 x 10-2 x 2.15 x 109 9.58 x 107 0.10 9.91 x 10-1 x 2.15 x 109 2.13 x 109 2.13 9.5 x 10-2 x 2.15 x 109 2.04 x 108 0.20 I
- Highest concentration noted was at 7 ft. depth below ground level and was 6.6 x 10-6 ,ci/cm 3 , Cs137. If this activity were to be released into an equal volume of water, the water would be within acceptable limits (2 x 10-5aci/ml, Cs 1 3 7 ).
ATCOR
APPENDIX E
'a Estimated Quantity of Activity Remaining in the South Corridor In the evaluation of the south corridor, an estimate was made for the radioactivity remaining. This estimate was based on analyses where the concentration of activity was known to be at the highest concentration and was based on trends noted during the excavation work. A conservative estimate was ob-tained by multiplying the high concentration times an esti-mated volume thought to contain the contaminated soil. The calculation showed about 167 millicuries remained in the ex-cavation.
Since this estimate was made, additional samples and measure-ments were taken to attempt to obtain the necessary informa-tion to refine this estimate. Enclosure 1, Teledyne Isotope Report, dated 11/18/76 and Enclosure 2, Teledyne Isotope Report, dated 1/21/77, contain soil analysis at various depths and locations in the south corridor excavation., En-closure 3 contains radiation profile readings at the locations of samples referenced in Enclosure 2.
From the results in Enclosure 3, it can be shown that the' radiation levels decrease with distance from the clean out.
Decreases in the concentration of the activity per gram with distance were also noted. In order to refine the estimate of activity remaining in the south corridor excavation, average activity concentrations were calculated for two different volumes of earth, the activity in each volume was calculated and were summed to obtain the refined estimate. See diagram 1 for volume identification.
/ 4 I __ 2 'J,~t~ATC\
Table I contains the mathematical averages of the activity in the excavation by isotope.
Table 1 Average Concentrations in Earth from 12' to 18' within 4' of the Clean Out in South Corridor Distance from Concentration of Activity in pci/gm CL 6 0 3 7 6 5 90 Mn 5 4 Co Cs134 Cs1 Zn Sr 0' 12.90 33.3 5.31 252.4 2.33 4.48 4'S 0.17 24.4 0.23 42.6 0.56 0.65 4'N 0.64 27.6 1.99 23.9 1.10 1.78 28.4 2.51 106.2 1.33 2.30
_jverage4.57 Table 2 contains averages of the activity in the excavation by isotope.
Table 2 Average Concentrations in Earth from 10' to 12' within 4' in the Clean Out in South Corridor Isotope A (/ci/gm) 90 Sr 1.5 x 10-4 5
4Mn 6.79 x 10-5 6 0 Co 4.65 x 10-4 1 3 10-4 4Cs 3.49 x 1.37Cs 2.38 x 10-3 65Zn 2.56 x 10-4 15 4E,,(
7.25 x 10-6 ATCOR
Calculations for radioactivity contained in Va and Vb follow:
- 1. Activity in Va Va = (16' x 6' x 2') + 1/2 (8? x 4' x 6')
3 3 = 288 ft 3 Va = 192 ft + 96 ft Ma = Vae e= 62.5 #/ x 1.8 x 453.6 9_
- I
= 5.1 x 104
= 288 ft 3 x 5.1 x 1014 gm/ft3 Ma Ma = 1.47 x 107 gm Activity Estimate in Va Isotope [_ei/gm] x NM1 (gim) = A- . ( ci) or A. (mci)
Mn5 4 6.79 x 10-5 x 1.47 x 107 = 9.98 x 102 or 1.00 6 0 1.47 x 107 Co 4.65 x 10-4 x = 6.84 x 103or 6.8 4.
Cs1334 10-4t x 1.47 x 107 5.13 x 103 or 5.13 3.49 x -
1 37 10-3 x 1.47 x 107 3.50 x 10 or 35.0 Cs 2.38 x 65 4 x 1.47 x 107 Zn 2.56 x 10- = 3.76 x 103 or 3.76 E 154 7.25 x 10-6 x 1.47 x 107 - 1.07 x 102 or 0.11 90 1.47 x 107 Sr 1.5 x 10-4 x = 2.21 x 10 or 2.21
- 2. Activity in Vh Vb = 16' x 6' x 6' 3
Vb =.576 ft Mb = Vb)
P =62.5 #/ x 1.8 x 453.6 gm
.. Ift 3
e = 5.1 x 104 gm/ft3 3 3 Mb = 576 ft x 5.1 x 104 gm/ft Mb 2.94 x 107 gm ATCOR
Activity in Vb Isotope [pci/g*IIb x (gim) !b-ý pci) Ai, (mci) 5 Mn 4 4.57 x 2.94 x 107 1. 34 x 108 0.13 6 0 Co 28.4 x 2.94 x 107 8. 35 x 108 0. 84 1 34 107 Cs 2.5]. x 2.94 x 107 7. 38 x 0.07 1 3 Cs 7 106.2 x 2.94 x 107 3 .12 x 109 3.12 6
Zn 5 1.33 x 2.94 x 107 3 .91 x 107 0.014 90 Sr 2.30 x 2.94 x 107 6. 76 x 107 0. 07 Table 3 contains a summary of total activity in the excavation.
Table 3 Activity Left in South Corridor Excavation Isotope At (mci)*
HMI54 1.13 Co 60 7.68 Cs 1 34 5.20 37 Cs1 38.12.
6 5 Zn 3.80 E 154 0.11 90 Sr 2.28 A + Ab Conclusion Based on the data now available, it has been shown that the total activity in the south corridor excavation is less than 167 millicuries previously reported and is about 60 millicuries.
ATCOR
- I , -,,,, -,n n n - -
I- -: -,n: - - ,,- .-
,n t¸ OF ANA LYS I S RE POR T RUN DATE 11/18/76.
`rTELEDYNE ISOTOPEc-S07G, Wo:-Maodc, Now Jorw 50 Von~flurar Ava.,
TELE DYNEISOTO TELEDYNE ISOTOPES REPORT OF AN1ALYSIS RUN DATE 11/18/1 WORK ORDER NUMBER CUSTOMIER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 3-1982 11/05/76 11/17/76 ATCOR ITIC PARK MALL PEEKSKILL N Y 10566
..LIQUID PADWASTE TELEDYNE COLLECTION-DATE NU CL-UNIT- v MID-COUNT CUSTOMER'S STA START NU.K DATE STOP ACTIVITY ASH-WGHT-% TIME NUMBER IDENTIFICATION TIZE DATE TIME NUCLIDE ( uCi/l ) U/ ** DATE TIME VOLUME - UNITS LAB.
29121 H20 WASTE EVAPORATOR 11/0R SR-90 1.9 +-1..I E-08 11/15 3 BE-7 t.T. 3. E-07 11/12 4 K-40 L.T. 8. E-07 11/12 4 MN-54 L.T. 4. E-08 11/12 CO-58 L..T. 4. E-0O 11/12 4 CO-60 L.T. 4. 'C-08 11/12 ZR-q5 L.T. 6. E-08 11/12 4 SU-103 L.T. 4. 11/12 4 P11- 106 L.T. 4. E-07 11/12 4 L.T. 4 1-131 7. B-08 11/12 Cs- 134 L.T. 4. E-08 11/12 44t CS-137 L.T. 4. B-0O 11/12 4 BA-140 L.T. 1. E-07 11/12 4 CE- 14 1 L.T. 5. E-08 11/12 4 CE- 1 4 L.T. 2. E-07 11/12 4 RA-226 L.T. 6. E-07 11/12 4 TH-228 L.T. 5. E-08 11/12 4 29122 H20 SUB CELL(S.CORR) 1 1/OR SR-90 L. T. 2. E-o08 11/15 "BE-7 L.T. 3. E-07 11/14 K-40 L.T. 6. E-07 11/14 IN- 54 L.T. 3. B-0O 11/14 CO-5B T_ T. 2. E-08 11/14 CO-GO L.T. 3. E-08 11/14 ZR-95 L.T. 5. E-08 11/14 It> RU-103 L.T. 3. E-08 11/14 RU-106 L.T. 2. E-07 11/14 B-0O 1-131 I.T. 7. F-08 11/14 CS-134 L.T. 3. 95E-08 11/14 CS-137 7.644-2. E-07 11/14 BA-140 L.T. I. 11/14 CE-l 41 L.T. 6. E-08 11/14
cm -
TELEDYNE ISOTOPES RUN DATE 11/18/76 REPORT OF ANALYSIS PAGE 2 DATE RECEIVED DELIVERY DATE CUSTOMER P.O. NUMBER WORK ORDER NUMBER .11/17/76 11/05/76 3-1982 ATCOR INC PARK MALL 10566 PEEKSKILL I LIQUID RADWASTE NUCL-UNIT-% MID-COUNT COLLECTION-DATE ASN-WGHT-% TIME ACTIVITY VOLUME -UNITS LAB.
TELEDYNE START STOP U/7 DATE TIME STA uci/.2. -
CUSTOMER'S NUCLIDE SANPLE IDENTIFICATION NUM DATE TIME DATE TIME NUMBER E-07 11/14 4 CE-144 L.T. 2.
11/0R B-07 11/14 4 RA-226 L.T. 5.
'29122 H20 SUB CELL(S.CORR) E-08.
11/14 TH-228 L.T. 5.1
TELEDYNE ISOTOPES REPORT OF ANALYSIS RUN DATE 11/18/76 WORK ORDER NUMBER CUSTOMER P.Oi. NUMBER DATE RECEIVED DELIVERY DATE PAGE 3 3-1982 11/05/76 11/17/76 ATCOR INC PARK MALL PEEKSKILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NUCL-UNIT-% MID-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-% TIME NUMBER IDENTIFICATION NUM DATE TIME DATE TIME qUCLIDE (pci/gM DRY) U/M ** DATE TIME VOLUME - UNITS LAB.
19123 S WASTE EVAPORATOR 11/OR SR-90 1..5 4-o.:2 E*i0o uci/gmn 11/15 BED-7 L T_ I. 'P,--.06 DR-Y *4 3 u C i /g rn DRY *4 uCi/gnl 1 1/12 14 K-40 6.6'4 -0.86E-06 11/12 u Ci1 9 M, DRY 14
- 4 NIN-54 f /_4/1~
CO-58 CO-60 ZR-95 L.T.
-. T.
9.
1.
7.56+-0..76Er-05 L.T. 2.
E-03 E-07 E707 uCi/gm DRY 44 u Ci /q r uCi/gm DFY *4 DRY 4*
uCi/gm DR Y 4*
11/12 11/12 11/12 11/12 14 41 14 R U-103 L.T. 1. E-07 uCi/gm DRY 4* 11/12 14 R U- 106 L.T. 1. E-06 uCi/grn 11/12 uCi/gmn DRY 4* 14 1-131 L.T. 3. E-07 DRY 44 11/12 14 CS- 134 3.22+-0.32E-06 uCi/gmn 11/12 DRY *4 14
- CS-137 3. 14+-0.31E-05 uCi/grn 11/12 uCi/gmn DRY *4 BA-140 L.T. 5. E-07 u1Ci / '1In DRY *4 11/12 14 CICE-144 L.T.. 2. E-07 uC i/g uuCi/grm I Ci/gm DRY *4 11/12 uC i/gmI 14 I.T. 6. E-07 uCi/gm .DRY *4 11/12 PA-226 L.T. 2. .E 06 11/12 14 DRY *4 TU-228 2.7 9+-0. 38 E-07 uCi/gm DRY *4 11/12 14 ZN-65. 3. 17+- 1. 93E-07 DRY *4 11/12 34 uCi/gq 14 2q124 S HIGH LEVEL L.C.R 11/O0 SR-9o 5-0 4-0.1 E-05 uCi/gm DRY *4 11/15 B Er,- 7 L.T. 5. E-06 uci/gmn DRY *4 11/12 14 i.13+-0.14E-05 uCi/gm DRY *4 11/12 2440+-0. 2T4E-05 uCi/gm DRY *4 11/12 3 CO-60 I.T. 5. E-07 uCi/g-n 11/12 14
- 1. 86+-0.19E-04 u Ci/grm DRY *4 11/12 uCi/gm DRY ** 14 ZR-95 L.T. 8. E-07 DRY *4 11/12 u4 RU- 103 L.T. 5. E-07 uCi/gm DRY 44 11/12 14 RU-106 I.T. 4. E-06 uCi/gq DRY 11/12 DRY *4 14 1-131 L.T. 9. E-07 DRY 4* 11/12 14
& CS- 13 4 1.81.-0.1!8-E-05 uCi/gm DRY *4 11/12 14 CS-137 3.81+-0.38E-0OU uCi/gn DRY *4 11/12 14 BA-140 L.T. 2. E-06 uCi/gm DRY *4 11/12 CE-1'4I E-07 L.T. 5. *4 11/12
TELEDYNE ISOTOPES REPORT OF AhaLYSIS RUN DATE 11/18/7 WORK ORDER NUMBER. CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 3-1982 11/05/76 11/17/76 XTCOR INC PARK MALL PEEKSKILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NUCL-UNIT-% MIID-COUNT SArPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-% TIME NOMBER IDENTIFICATION NUM DATE TIME DATE TINE NUCLIDE (pCi/gm DRY) U/M ** DATE TIME VOLUME - UNITS LAB.
29124 S HIGH LEVEL L.C.R 11/OR CE-144 L.T. i2. E-06 uCi/gm DRY 11/12 RA-226 L.T. .5. E-06 uCi/gm DRY 11/12 TU-228 L.T. ,5. E-07 uCi/gm DRY 11/12 Z1ZN-65 1.43+-0. 1 E-05 uCi/gm DR Y 11/12 29125 S SOUTH CORR. 11/OR SRLI-90 1.5 +-0.1 E-04 uCi / m DRY ** 11/15 BE-7 L.T.. 1. E-05 uCi/grn DRY ** 11/12 K-40 1.20+-0.12E-05 uCi.~ DRY *4 11/12 6.79+-0.68E-05 u ci -~:
CC-5R uCi/gm DRY 4* 11/12 CO-58 L.T. 6. E-07 uCi/gm DRY *4 11/12 C0-60 6 5 -Q. 47F -04 DRY *4 11/12 ZR-95 L.T. 1. E-06 1C i /g m DRY 44 11/12 RU-103 L.T. 1. F-06 uCi/gm
, Ci /g i DRY *4 11/12 RU- 106 L.T. 7. E-06 uCi/gm DRY *4 11/12 1-131 L.T. .2. uCi/gm E-06 DRY *4 .11/12 CS-134 3.49+-0.35E-04 u Ci /g m DRY 4* 11/12 CS-137 2.38+-0.214,-03 uCi/gin DRY 11/12
- 4 BA- 14 0 L.T. 3. E-06 uCi/gm DRY *4 11/12
.CE-141 L.T. 8. E-07 uCi/gm DRY 44 11/ 12 CE- 144 L.T. 3. E-06 uCi/gqrm DRY *4 11/12 RA-226 L.T. 8. E-06 uCi/gm DRY *4 11/12 TH-228 L.T. 8. E-07 uCi/gm DRY 44 11/12 ZN-65 2.56+-0. 26E-04 uCi/gm DRY 4* 11/12 EU- 154 7.25+-0.99E-06 uCi/gm DRY *4 11/12 29126 S EAST CORR. 11/OR SR-90 5.5 +-0.1 r-05 uCi/gin DRY *4 11/1.6 BE-7 L.T. 6. E-06 uCi/gin DRY 44 11/12
. - K-40 1.15+10-1 4E-05 uCi/gm DRY *4 11/12 M,17*-5 41 1. 16÷-O. 12E-05 uCi./g m DRY *4 11/12 CO-58 L.T. 6. E-07 uCi/gri DRY 4* 11/12 C0-60 1.96+-0.20E-04 uCi/gm DRY ** 11/12 ZR-95 L.T. 1. B-06 uCi/gm DRY 44 11/12
- RU- 1.03 L.T. 7. E-07 tiCi/gm DRY *4 11/12
- - - - - TELED Y I - - -
TELEDYN*E ISOTOPCS REPORT OF ANALYSIS RUN DATE 11/18/7ý WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 3-1982 11/05/76 11/17/76 ATCOR InC PARK MALL PEEKSKILL N Y 10566 SOIL T BL DY':E COLLECTION-DATE NUCL-UNIT-¶% MID-COUNT NSMIPLE CUSTOMERIS STA START STOP ACTIVITY ASF-!GHTL- *
- NU ZE ER TIME IDENTIrFICATION NUM DATE TIME DATZ TIME NUCLIDE (pCi/gm DRY) U/1', ** DATE TIME VOLUME - UNITS LAE.
29126 S EAST CORR. 11/OR RU- 106 L.T. 5. F-06 U Cii/gm DRY 1-131 uCi/gm *4 11/12 4 L.T. 1. E-06 DRY *4 11/12 CI- 13 4 uCi/gm 4 8.99+-0.90E-05 DRY 4* 11/12 4 CS- 137 3.58+-0.36E-04 uCi/gm DRY ** 11/12 4 BA-140 L.T. 2. E-05 uCi/gm DRY 4* 11/12 4 CF- 14 1 L.T. 5. t-07 uCi/gm DRY uCi /g(m 4* 11/12 CE-144 L.T. 2. E-05 DRY 44 11/12 RI-226 L.T. 6.. E-06 u Ci/gm CRY uCi/gm DRY 4* 11/12 TH-228 L.T. 5. E-07 uCi/gm *4 11/12 ZN-65 3.54+-0.35E-05 DRY 4* 11/12 uCi/qm 3 29127 S DECONTAM P 11/OR SR-90 2.1 +-0.1 E-05 uCi/gm DRY 4* 11/16 "4
BE-7 L.T. 1. B-06 UCi /g n DRY *4 11/12 4
K-40 1.00+-0. 10E-05 uCi/gm DRY *4 11/12 I'N-54 L.T. 3. DRY *4 .4 E-07 11/12 4 E-07 uCi/gm fVrZf C0-58 L.T. 3. DRY *4 uC i/gm 11/12 4$
CO-60 7. 34+-0.73;-05 DRY *4 11/12 4 ZR-%5 L.T. 4. E-07 u Ci/gm DRY *4 11/12 RU-103 L.T. 2. Ci /gcj DRY *4 11/12 E-07 uuCi/gm 4 RU- 106 L.T. 2. B-06 DRY *4 11/12 1-131 L.T. 3. E-07 uCi/gm DRY *4 11/12 CS-134 1.22+-0.28:-06 uCi/gm DRY *4 11/12 CS- 137 1.39+-0. 14E-06 uCi/gm uCi/gm DRY 4* 11/12 4t4 14 BA-140 L.T. 7. E-07 uCi/gm DRY 44 11/12 CE- 141 L.T. 1. E-07 uCi/gm DRY ** 11/12 4
- 4 CE-144 L.T. S. E-07 uCi/gm DRY *4 11/12 RA-226 L.T. 1. E-06 uCi/gm DRY DRY 4* 11/12 4*
TH-228 2.70+-0.30E-07 *4 11/12
..-- r m n r EDY : m n -T m -ISOOPE TELEDYNE ISOTOPES REPORT OF ANALYSIS RON DATE 11/18/1 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 3-1982 11/05/76 11/17/76 ATCOR I NC PARK MALL PEEKSKI LL N Y 10566
.WATER - GROUND TELEDYN B - COLLECTION-DATE NUCL-UNIT-% MID-COUNT SAMPLE CUSTOMERIS STA START STOP ACTIVITY ASH-WGUT--% TIME NUMBER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE (pCi/liter) U/M ** DATE TIME VOLUME - UNTS LAB.
29120 H20 SITE WELL 11/0R SR-90 L.T. 2. E 01 11/15 BE-7 L.T. 3. E 02 11/12 K-40 L. T. 8. E 02 11/12 L.T. 3. E 01 11/12
- CO-58 L.T. 3. . 01 11/12 CO-60 L.T. 4. E 01 11/12
- ZR-95 L.T. 6. Z 01 11/12 RU-103 L.T. 3. Z 01 11/12
. P1U-106 L.T. 3. E 02 11/12 1-131 L.T. 7. B 01 11/12 CS-13I L.T. 4. E 01 11/12
- CS-137 L.T. 3. E 01 11/12
. BA- I1O L.T. I. E 02 11/12
- C -F141 L._T. 7. E 01 11/12 CE-144 L.T. 3. E 02 11/12 RA-226 L.T. 7. B 02 11/12 TH-228 L.T. 6. E 01 11/12 LAST PAGE OF REPORT APPROVED BY K. ROACH 11/18/76 SEND 1 COPIES TO AT100S 2 - GAS LAB. 3 - RADIO CREMISTRY LAB.S 4- Ge(Li) GAE5A SPEC LAB, 5 - TRITIUM GAS/L.S. LAB.
-- . ...-P- - -
-I -A - - - - -
.1' REPORT OF ANALYS IS J ANUARY 21, 977
`P-TELEDYNE ISOTOPES
~r 5 0 Vi n ptA an A W t,,a
. A, d. Ii e.%,iJr5 ~7 1 G7 5
TELEDYNE ISOTOPES REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 1 3-2293 01/12/77 01/24/77 L ATCOR INC PARK MALL PEEKSKILL N Y 10566 S O IL TELEDYNE COIIECTION-DATE NUCL-UNIT-% MID-COUNT S AMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-%
- TIME NU '!BzR IDENTIFICATION NDM DATE TIME DATE TIME NUCLIrE fpCi/gm DRY) U/y ** DATE TIME VOLUME - UNITS LAB.
ai437 NO LCH FLD INLT 2/3 H 20TB 01/OR 55-7 L-T. 2. E-01 01/15 14 X-40 8.99+-0.90E 00 01/15 L.T. 2. E-02 01/15 14 CC-S8 I.T. 2. E-02 01/15 14 CO-60 4. 27+-2.02F-02 01/15 4 Z R-S9 L.T. 4. E-02 01/15 14 RU- 103 I.T. 2. E-02 01/15 14 I.T. 2. E-01 01/15 14 1-131 I.T. 3. E-02 01/i5 :4 CS- 134. L.T, 2. r-02 01/15 14 CS- 137 4.51+-O.45E-01 01/15 :4 BA-140 L.T. 7. 5-02 01/15 14, CE-141 L.T. 4. E-02 01/15 14 CE-144 L.T. 2. E-01 01/15 :4 RA-226 8.94+-1.36E-01 01/15 :4 TH-228 6.43+-0.64E-01 01/15 31438 NO LCH FLD OUTLET AT TILE 01/OR EE-7 T,.T. 2. E-01 01/15 :4 K-LO 6..15+-0.61E 00 01/15 :4 Mi-5S4 L.T. 2. E-02 01/15 14 C0-58 L.T. 2. E-02 01/15 14 CO-6o 5. '4+-2. 13E-02 01/15 14 ZR-95 L.T. 3. E-02 01/15 RU-103 I.T. 2. E-02 01/15 $4 RU-IC6 L.T. 2. E-01 01 ,/15 14 1-131 L.T. 3. V-02 01/15 14 CS-134 .L.T. 2. E-02 0,1/15 :4 CS- 137 %.97+-0.20E 00 01/15 14 BA-940 L.T. 6. E-02 01/15 14
- 4 CE-141 *L.T. 3. E-02 01/15 CE-144 L.T. 1. E-01 01/15 14 BA-226 9.46+-i. 16E-01 01/15 14
S -m I mm m m m m- - mm - mm- m.
TELEDYNE ISCTCPES REPORT OP ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 2 3-2293 01/12/77 01/24/77 ATCOR INC PARK MALL PEEKSKILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NECL-UNIT-% MID-CCUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-% TIME NUMtER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE (pCi/gm DRY) /M ** DATE TIME VOLUME - UNITS LAB.
,38 NO LCH ELD OUTLET AT TILE 01/OR TH-22E 3..21+-0.32E-01 01/15 4 31439 NO LCH ELD OTLT 2/3 0 20TE 01/0R DE-7 Iý.T. 1. E-0 1 01/15 4 K-40 9.86+-0.99E 00 01/15 4 MN-54 L.T. 2. E-02 01/15 4 CC-S8 I.T. 1. F-02 01/15 4 CO-60 6. 76+- 1. 67E-02 £4 01/15 ZR-95 L-T. 3. E-02 01/15 4 Ro- 103 1-.T. 2. E-02 01/15 4 RU-I106 _T . 1. E-01 01/15 4 1-131. L..T. 2. E-02 01/15 4 CS-1134 L.T. 2. E-02 01/15 4 CS-137 1..18+-0. 12E 00 01/15 4 BA- 140 L.T_ 5. E-02 01/15 4 CE-141 1..T. 2. E-02 01/15 C*--14 4 I.T. 9. E-02 01/15 R.-226 8.59+-0.89E-01 £4 01/15 TF.-228 3.55+-0.35E-01 01/15 4
£4 31440 NO ICH FLD OTLT 1/3 E 20TB 01/OR BE-7 I.T. 2. E-01 01,/15 4 K-40 1..05+-0o1OE 01 01/15 L.T. 2. E-02 01/15 £4 CC-SB 44 L..,T. 2. E-02 01/15 CC-60 !..T. 2. E-02 01/15 zT-95 L.T. 4. E-02 01/15 4 RU-103 L..T. 2. E-02 01/15 £4 RU- 106 T.. T. 2. E-01 £4 01),/15 1-131 L..T. 3. E-02 01/15 4 4
CS-134 L.T. 2. E-02 01/15 4
£4 4
CS- 137 1., 29--0. 17E-01 01/15 BA-140 L.T. 6. E-02 01/15 CE-i141 L.T. 2. E-02 01/15 CE- 1 44 T-.T. 1. E-01 01/15
TELEDYNE ISOTOPES REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 3 3-2293 01/12/77 01/24/77 ATCOR INC PARK "ALL PEEFSKILL V Y 10566 SOIL TELEDYNE COILECTION-DATE NUCL-UNIT-% MID-COUNT SA1PLE CUSTOMERIS STA START STOP ACTIVITY ASH-WGHT-
- TIME IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE [pCi/gm DRY) U/M ** DATE TIME VOLUME - UNITS LAB.
40 NO LCH FLD OTLT 1/3 19 20TB 01/OR RA-226 6.62+-I.08E-01 01/15 4 TH-228 5.60+-0.56E-01 01/15 4 31441 NO LCH FLD I3LT AT TILE 01/0R BE-7 I1.-. 1. E- 01 01/15 4 K-40 7.39+-0.74E 00 01/15 4 MN-5 4 L.T. 1. E-02 01/15 4 I.T. 1. E-02 01/15 4 CC-60 7.59+- 2.00,-02 01/15 4 ZR-95 L.T. 2. E-02 01/15 £4 RU-103 L..T. 1. E-02 01/15 4 RU-1106 L.T. 1. E-01 01/15 .4 LT. 2. E-02 01/15 4 CS-134 L.T. 2. E-02 01/15 '4 CC- 137 4. 5 6 +-0. 4 6--0 1 01/15 EBA- 14 C0 L.T. 5. E-02 01/15 CE- 141 i.T. 1. E-02 01/15 '4 CE- 144 L.T. 6. E-02 01/15 6.08+-0.77E-01 01/15 £4 TH-228 2. 96+-0. 30E-0 1 01/15 31442 NO LCH FLD INLT 1/3 H 20TB 01/0O
- 3.-7 L.T. 1. E-01 01/15 4 F-40 1. 16+-0.12E 01 01/15 £4 rlN-5'4 L.T. 2. E-02 01/15 4
CC-SO L.T. 2. E-02 01/15 l.T. 2. E-02 01/15 DC- 103 L.T. 3. E-02 01/15 4
L.T. 2. E-02 01/15 PU-lOS L.T. 2. E-01 £4 01/15 1- 13 1 '4 L.T. 2. E-02 01/15 4
CS-i134 L.T. 2. E-02 01/15 t4 CS-137 3.63+-0.36E-01 01/15 ;4 13A-140 1ZT. 5. E-02 01/15.
CE-141 L.T. 3. E-02 01/15
TELEDYNE ISCTCPES REPORT OF ANALYSIS RUN DATE 01/21/77 WORK CEDER NUMBER CUSTOMEH P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE £4 3-229.3 01/12/77 01/24/77 ATCOR INC P42K MALL PFKSKILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NUCL-UNIT-% MID-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY. ASH-WGNT-% TIME NUm DEl IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE (pCi/gm DRY) U/M ** DATE TIME VOLUME - UNITS LAE.
'£42 NO LCH FLD INLT 1/3 H 20T5 01/OR CE-14q L.T. 1. E-01 01/15 14 RA-226 L.T. 3. E-01 01/15 4 TEi-228 C.56+-0.66E-01 01/15 £4 31443 SO LCH FLD INLT 1/3 H 20TB 01/OR BE-7 L.T. 3. E-01 01/15 K-140 1.08+-0.11E 01 01/15 MN-54 I.T. 3. E-02 01/15 C0-58 L.T. 3. E-02 01/15 CO-60 9..53÷-3.62E-02 01/15 ZR-95 L.T. 5. E-02 01/15 RU-103 L..T. 3. E-02 01/15 L.T. 3. E-01 01/15 1-131 L..T. 4. E-02 01/15 CS- 134 1.22+-0.39E-01 01/15 Cs-137 9,.78+-0.98E-01 01/15 BA-I*O L.T. 9. E-02 01/15 CE- 141 1.T. 5. E-02 01/15 cE-l14 i.,T. 2. E-01 01/15 RA-226 1.68+-0.84E 00 01/15 TH-228 1,.20+-0.12E 00 01/15
- "44 SO LCH PLD INLT AT TILE 01/OR BF-7 L..T. 2. B-01 01/16 K-40 3.67+-0.53S 00 01/16 KN-5 4 L..T. 2. E-02 01/16 CO-5E L.T. 2. E-02 01/15 CC-SO 2.24+-0.35E-01 01/16 ZR-95 L.T. 5. E-02 01/16 RU- 103 I.T. 3. E-02 01/16 RU- 1 C6 L.,T. 2. E-01 01/16 1-131 L..T. 4. E-02 01/16 CS- 134 L.T. 3. E-02 01/16 CS-137 2.36+-0° 35E-01 01/16 BA-140 L.T. 9.- E-02 01/16
TELEDYNE ISOTOPES REPORT OF ANAlYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 5 3-2293 01/12/77 01/24/77 ATCOR INC PARK MALL PEEKSKILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NUCL-UNIT-% MID-CCUNT SAMPLE CUSTOMERtS STA START STOP ACTIVITY ASR-WGHT-% TIME NUMBER IDENTIFICATION NUN DATE TIME DATE TIME NUCLIDE (pCi/gm DRY) U/M #* DATE TIME VOLUME - UNITS LA2.
'44 SO LCH FLD INLT AT TILE 01/OR CE-141 L.T. 5. E-02 01/ 16 4 CE-144 L.T. 2. E-01 Oi/ 16 4 RA-226 1.10+-0.19E 0O 01/ 16 4 T11-228 3.59+-0.36E-01 01/ 16 4 31445 SO LCH FLD OTLT 1/3 H 20TB 01/OR BE-7 L.T. 3. E-01 01/16 4 FN-5 4 9.39+-0.95E 00 01/16 4 I.T. 3. E-02 01/16 4 CO-58 I.T. 3. E-02 01/16 4 L.T. 3. E-02 01/16 4 ZR-9S I.T. 6. E-02 01/16 4 R;)- 103 I.T. 3. E-02 01/16 4 RU-1 06 I.T. 3. F-Cl 01/16 4 1-131 I.T. 4. E-02 01/16 4 CS-134 I.T. 4. E-02 01/16 4 CS- 137 L.T. 4. E-02 01/15 4 BA- 140 L.T. 1. E-01 01/16 4 CF- 141 L.T.. 5. E-02 01/16 4 CE- 144 L.T. 2. E-i1 01/16 RA-226 1.45+-0.21E 00" 01/1.6 4 TI - 228 7.82+-0.78E-01 01/15 4
- ,46 SO LCH FLD OTLT 2/3 H 20TB 01/OR BE-7 L,.% 2. F-Cl 01/16 4 K-O4 9.65+-0.90E 00 01/16 4 Nr'-54 L.T. 2. E-02 01/16 4 CC-58 L.T. 2. E-02 01/16 4 CO-6C L.T. 2. E-02 01/16 4 ZR-95 T./P 4. E-02 01/16 4 RU- 103 L.T. 2. E-02 01/16 u RU- 106 I.T. 2. E-0I 01/16 4 1-131 L.T. 3. E-02 01/16 4 CS-134 L.T. 3. E-02 01/16 4 CS- 137 4. 06+-2. 27E-02 01/16
TELEDYNE ISOTCPES REPORT Cf ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER 2.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 6 3-2293 01/12/77 01/214/77 ATCOR INC PARK MALL PZEXSKILL N Y 10566 S OI TELEDYNE COLLECTION-DATE NUCL-UNIT-% MID-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-% TINE NUMBER IDENTIFICATION NUN DATE TIME DATE TIME NUCLI.E (pCi/gm DRY) U/?i ** DATE TIME VOLUME - UNITS LAB.
'46 SO LCH FLU OTLT 2/3 H 20TB 01/OR BA-140 L.T. 8. E-02 01/16 4I CE- 1 L1 L..T. 3. E-02 01/16 4 C '-i 14 4 L.T. 1. E-01 01/16 R*-226 14 8.79+-1.29Z -01 01/16 4I TH-228 6..57+-0.661-01 01/16 41 31447 SO LCH FLD INLT 2/3 E 20TB 01/OR 51-7 L.T. 3. E-01 01/16 4 K-40 8-05+-0.81E 00 4 NN-514 L,.T. 3. 01116 E-02 01/16 CO-SO. L..T. 3. E-02 01/16 4 2_76+-0 45. -01 01/16 Z3-95 LI L..T. 5. E-02 01/16 RU- 103 L,.T. 4
- 3. E-02 01/16 RU-1OS 4 1-13 1 01/16 L..T. 5. E-02 01/16 4 CS-i 13 1. 16+-0.34E-01 cs- 137 01/16 3..76+-0.38E 00 4 01/16 L.T. 1. E-01 4 01/16 '4 L,.T. 1. E-02 01/16 CE-I 14 L.,T. 1. E-01 01/16 RA--226 7_37+-1.37f-01 T1- 228 01/16 4.. 84+-0.48E-01 4
5E,7 01/16 31448 SO LCH FLD OTLT AT TILE 01/0O _. T. 2. E-01 14 01/16 3..67+-0.392 00 01/16 4 IIN-5LI L..To 2. E-02 01/16 14 CO-5S L.T- 2. E-02 01/16 CO-60 3.79+-0.42P-01 44 Z 3-95 01/16 RU-103 L.T° 3. E-02 01/16 RU- 106 L.T. 2. E-02 01/16 1-131 L.T. 2. E-01 01/16 CS-134 1.T.7 . E-02 I,. 97+-0.30E-01 01/16
-m -m -* - -m - m I-m -- - - - - m TELEflYNE ISCTOPIS REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSIOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 7 3-2293 01/12/77 01/24/77 ATCOR INC PARK MALL PEEFSKILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NUCL-UNIT-T MID-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-%
- TIME NUFMBER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE (pCi/gm DRY) U/M ** DATE TIME VOLUME - UNITS LAE.
1448 SO LCH FLD OTLT AT TILE 01/0R CS- 137 2.28+-0.23E 00 01/16 4 BA- 140 L.T. 8. E-02 01/16 4 CE- 1I 1 L.T. 2. E-02 01/16 4 CE- 11q4 ,.T. 9. E-02 01/16 4 RA-226 6. 23+-1.0OE-01 01/16 1.
TH- 2 28 3.03+-0.30E-01 01/16 14 31449 SC CO 4FT WO 12FT DP 01/OR BE-7 L.T. 1. E 00 01/16 `4 K-40 1.34+-0.13E 01 01/16 4 MN-54 2..36+-0.24E 00 01/16 14 CO-58. L.T. 2. E-01 01/16 4 CO-60 7.C04+-0.70U 01 01/16 4 ZR-95 L.T. 3. E-01 01/16 4 RU- 103 L.T. 2. E-01 01/16 4 RiU- 106 LT. 1. F 00 01/16 4 1-131 I.,T... 2. E-01 01/16 4 CS- 134 7.54+-0.75B 00 01/16 4 CS- 137 9.83+-0.881 01 01/16 4 BA- 140 L.T. 5. E-01 01/16 4 C- 141 L.T. 2. E-01 01/16 4 CE-144 L..T. 8. E-01 01/16 4 OA-226 5.93+-2.85E 00 01/16 4 TH-228 9.20+-2.58E-01 01/16 '4 zN-65 41,42+-0.44E 00 01/16 .4 31450 SC CO 4FT SO 12FT DP 01/OR BE-7 L.T. 8. L-01 01/16 14 K-140 1.76+-0.18E 01 01/16 .4 MN- 514 6.50+-1.301-01 01/16 4 CO-58 I.T. 1. E-01 01/16 ,4 CC-60 1.74+-0.17E 01 01/16 14 ZR-95 L.T. 2. E-01 01/16 4 RU- 103 L.T. 9. E-02 01/16 4 R'U-106 L.T. 9. E-01 01/16
TELEDYNE ISCTCPFS REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 8 3-2293 01/12/77 01/24/77 ATCOR INC PARK m&LL PZEMSXILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NUCL-UN IT-% MID-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-% TIME NUMBER IDENTIFICATION NUM DATE TIME tATE TIME NUCLIDE (pCi/gm DRY) U/ ** DATE TIME VOLUME - UNITS LAB.
'150 SC CO 4FT SO 12FT DP o1/OR 1-131 I.T. 1. E-0C 01/16 C5-134 L. 79+-1.34E-0 1 01/16 CS- 137 1.67+-0.17E 01 01/16 BA- 140 1,.T. 3. E-01 01/16 CF- 141 L.T. 9. E-02 01/16 CE- "14 4 CE-11414 L.T. 4- E-01 01/16 RA-226 L.T. 1. E 0o 0C 16 TH-228 ,.61t-1..38E-01 01/16 Z N1-6 5 2-.25+-0.27E 00 0)1/16 31451 SC CO 4FT NO 14FT DP 0I/Ol BE-7 L..T. 9. E-01 01/16 4 K-40 1.214+-0.12E 01 01/16 4 C0-58 L1T. 1. E-01 01/16 4 CC-SO L..T. 1. E-01 01/16 4 3.. 33+-0.33E 01 0C1/16 4 ZR-C5 !,.jT. 2. E-01 01/16 4 RU- 103 I.. T. 1. E-01 01/16 4 L..Tý 1. E 00 01/16 4 1- 13 1 L.T. 2. E-01 01/16 4 CS-134 L-T. 2. E-01 01/16 4 CS- 137 6.. 42+- 1.37E-01 01/16 4 BA-1 40 L..T. 4. E-01 01/16 4 CE- 1141 ,T. 1. E-01 01/16 4 CE-144 L.Tý 5. E-01 0 1/16 '4 Fk-226 1.85+-0.28E 00 01/16 '4 TH-228 1.. 23+-0. 12E 00 01/16 4 31452 SC CO 12FT DP 01/OR L.oT. 5. E 00 01/16 '4 K-40 1..21+-0.12E 0l 01/16 4 MN-5 4 '4..35+-0.44E O0 0 1/16 4 L..T. 3. F-01 01/16 4 CC-60 9.70+-0.97E 01 01/16 4 ZR-95 L.T. 4. B-01 01/16 1$
TELEDYNE ISCTCPES REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 9 3-2293 01/12/77 01/24/77 ATCOR INC PARK MALL PEEKSKILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NUCL-UNIT-1 MID-COUNT SAMPLE CUSTOMERIS STA START STOP. ACTIVITY ASF-WGRT-% TIME NUMBER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE (pCi/gm DRY) U/M 4* DATE TIME VOLUME - UNITS LAB.
-1452 SC CO 12FT DP 01/0R RU- 103 L.T. 5. E-01 01/16 4 RU-106 L.T. 3- E 00 01/16 4 i-131 L.T. 7- E-01 01/16 4 CS-134 .01+-0.20E 01 01/16 14 CS- 137 9.53+-0.95E 02 01/1.6 4 F'- 140 LT. 1. E 00 01/16 4 CE-I 41 L.T. 4. E-01 01/16 41 CE- 144 L-T. 2. E 00. 01/16 4 RA-2 26 I.T. 5. B 00 01/16 4 TH- 228 L.. 4-. E-01 01/16 4 ZN-65 . 9.31+-0.93E 00 01/16 41 31453 SC CO 4FT SO 14FT DP 01/OR r F-7 L.T. 4. E-01 01/16 4 K-40 I. 52+-0.15E 01 01/16 4 NN-51J L.T. 7. E-02 01/15 t4 C0-58 L.T. 7. E-02 01/16 4 CC-CO 1.34+-0.13E 01 01/16 4 I.T. 1- E-01 01/i6 4 RU- 103 . T. 5. E-02 01/16 EU- 106. L. T . 5. E-01 01/16 4 1-131 L.T. 7. E-02 01/16 4 CS-13t4 LWT. 7. E-02 01/16 4 Cs- 137 ,5.2 1+-0.67E-0 1 01/16 4 LA- 140 LWT. 2. E-01 CE- 141 01/16 4 CE-l14 W.T_ 5. E-02 01/16 4
.E m LEDYN ISC TELEDYNE ISCTCPES REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 10 3-2293 01/12/77 01/24/77 ATCOR INC PARK MALL PEEKSKILL N Y 10566 S OI L TELEDYNE COLLECTION-DATE NUCL-U NIT-% MID-CCUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-l
- TIME NUMER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE (pCi/g9m DRY) U/M ** DATE TIME VOLUME - UNITS LAB.
'454 SC CO 14FT DP 01/OR B1-7 L'T- 2. E 00 01/16 K- 1 40 4 9.01+-0.92B 00 01/16 41 N 'N- 554 6.81+-1.55T-0 1 01/16 4 CC-ES L.,T. 2. E-01 01/1, 14 Co-Go 3.18+-0.32E 01 01/16 4 ZR-95 L.T. 3. E-01 01/16 4 i 01J-103 L.T. 2. E-01 01/16 L.T. 1. E 00 1-131 L.T. 2. 0 1 /16 E-01 01/16 4 CS- 134 1.01+-0.19E 00 01/16 4 CS- 137 5.26+-0.535 01 01/16 4 BA-140 I.T. 5. E-01 01/16 4 CF- 141 I.T. 1. E-01 01/16 CE-!Q4 L.T. 5. E-01 01/16 4 RA-226 2.00÷-0.28E 00 4 TH-228 4.764-0.485-01 0 1/16 4 31455 SC CO 4FT SO 16FT DP 01/OR BE-7 I.T, 6. 2-01 01/16 14 K-140 1.49+-0.155 01 01/16 4 14 TlN- C-4 L.T. 1. E-01 01/i6 14 L..T- 1. E-01 01/16 14 CO-cO 1.614-0.16E 01 01/16 14 ZR-95 I.T. 2- E-01 .4 RlU- 103 L.T. 7. E-02 01/16 01/16 4 1- 131 L.T. 7. E-01 .4 LTo -9. E-02 01/16 4 CS-134 L.T., 1. E-01 01/16 14 CS- 137 3.111-0.31E 00 01/16 4 BA- 140 L..T . 2. E-01 14 CE- 141 L.T. 0 1/165
- 5. E-02 01/16 14 CE- 11414 L.T. 2. E-01 L.T. 5- B-01 01/16 14 RA-226 -. 21+-0.42-01 01/16 14 TR-228 01/16
TELEDYNE ISOTCPES REPORT CF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 11 3-2293 01/12/77 01/24/77 ATCOR INC PARK IALL PEEKSKILL N Y 10566 SO i TELEDYNE COLLECTION-DATE NUCL-UNIT-% MID-COUNT SAMPLE CUSTOMER'S STA. START STOP A.CTIVITY ASH-WGHT-%
- TI ME NUMBER IDENTIFICATION NUM DATE -TIME DATE TIME NUCLIDE (pCi/gm DRY) U/M ** DATE TIME VOLUME UNITS
- LAB.
11458 SC CO 4FT NO 16FT DP 01/0B L.T. 4. E-01 01/17 4 K-40 1,,05-0.10:E 01 01/17 4 L.T. 4. E-02 01/17 CO-58 L.T. 4. r-02 01/17 1.89+-0.19E 00 01/17 4
%R-95 L, T. 7. E-02 01/17 4 RU- 103 L.T. 4. E-02 01/17 4 R1- 1C6 L.T. 3. E-01 01/17 4 1-131 L.T. 6. E-02 01/17 CS-134 L..T. 5. E-02 01/17 4 CS-137. 4..49+-0.45E 00 01/17 BA- 140 ,1. -01 01/17 4 CE- 141 L._T 7. E-02 01/17 4 CF--14 4 L.T. 3. E-01 01/17 4 RA-22E I,.T. 8. E-01 01/17 4 THt-228 8,,9 1- .071-01 01/17 14 31457 SC CO 16FT DP 01/OR L..T. 5. E-01 01/17 K-140 2..17+-0.82E 00 01/17 4 L.T. 7. E-02 01/17 44 MN- 014 I.T. 7. E-02 01/17 14 CO-60 1.03+-0. 1OE 01 01/17 ZR-95 L..T. 1. E-01 01/17 RU- 1003 L,.T. 6. E-02 01/17 4 RU-1C6 L.T. 6. E-01 01/17 14 1-131 1.T. 7. E-02 01/17 14 CS-1314 I.T. 7. 1-02 01/17 4 CS- 137 1.27+-0.13E 00 01/17 14 EA- 140 L.T. 2. E-01 01/17 14 CE- 141 L.T. 7. E-02 01/17 14 CE- 114 L.T. 3. .E-01 01/17 RA-226 L.T. 7. E-01 01/17 TfH- 228 6..13+-0.98E-01 01/17
TELEDYNE ISOTOPES REPORT OF ANAtYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMEER DATE RECEIVED DELIVERY DATE PAGE 12 3-2293 01/12/77 01/24/77
&TCOR INC PARK MALL PEEKSKILL N Y 10566 SOIL TELEDYNE COLLECTION-DATE NUCL-UNIT-% MID-COUNT MPLE SAIN CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-% TIME NUm3ER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE (pCi/gm DRY) U/ ** DATE TIME VOLUME - UNITS LAB.
1458 SC CO 4FT SO 18FT DP 01/OR BE-7 L.T. 1. E 00 01/17 K-40 1.17+-0.12E 02 01/17 MN-5 4 L.T. 2. E-01 01/17 CO-58 I.T. 2. E-01 01/17 CC-60 5.02+-0.50E 01 01/17 ZR-g5 L.T. 3. E-01 01/17 U-103 L.T. 2. E-01 01/17 RU-106 L.T. 1. E 00 01/17 1-131 L.T. 2. B-01 01/17 CS- 13 4 2.69÷-1.77E-01 01/17 CS-i137 4.26+-0.43E 01 01/17 BA-lUG L.T. 5. E-01 01/17 CE- 141 L.T. 9. E-C2 01/17 CF-1 44 L.T. 4- E-01 01/17 2A-226 2.36+-0.24E 00 01/17 Ti-228 4.55+-0.45E-01 01/17 31459 SC CO 4FT NO 18FT DP 01/OR l.T. 5. E-01 01/17 K- 40 1.04+ 12E 01 01/17 MN-54 L.T. 7. E-02 01/17 CC-58 I.T. 7. E-02 01/17 CO-60 4.94+-0.49 E 00 01/17 ZR-9S L.T. 1. E-01 01/17 RU-103 L.T. 6. E-02 01/17 RU-106 L.T. 5. E-01 01/17 1-131 L.T. 8. E-02 01/17 CS-134 1.78+-0.93E-01 01/17 CS-137 2.13+-0.21E 00 01/17 BA-140 L.T. 2. E-01 01/17 CE- 141 L.T. 8. E-02 01/17 CE-144 L.T. 3. E-01 01/17 RA-227 L.T. 9. E-01 01/17 TH-228 7.48+-1.20E-01 01/17
S- - - -m m- m - -m - - m - - - - - n TELEDYNE ISOTOPES REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PACE 13 3-2293 01/12/77 07/24/77 ATCOR INC PARK MALL PEEKSKILL N Y 10566 S01 L TEL EDYNE COlLECTION-DATE NUCL-U NIT-% MID-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASN-WGHT-% TIME NUMBER IDENTIFICATION NUM DATE TIME DATE TI1E NUCLIDE (pCi/gm DRY) U/m ** DATE TIME VOLUME - UNITS LAE.
60 SC CO 18FT DP O1/OR BE-7 I.T. 5. E-01 01/17 4 K-40 7.78+-1.24E 00 01/17 4 L.T. 6. E-02 01/17 4 CC-58 T. r. 6. E-02 01/17 C0-60 2.58+-0.26E O0 01/17 4 ZR-95 t.T. 1. E-01 01/17 £4 P lJ- 103 L.I. 6. E-02 01/17 4 PU- 106 L.T. 5. E-01 01/17 4 1-131 L.T. 7. E-02 01/17 4 4
CS-134 Lo.T. 7. E-02 01/17 CS- 137 LýT. 7. E-02 01/17 BA- 140 T- 2. E-01 01/17 4 CE- 141 L..T. 6. E-02 01/17 4 CE-144 1.T. 3. E-01 01/17 -41 PA-226 L.T. 7. E-01 01/17 4 TH-228 3.12÷-1.00E-01 01/17 14
TELEDYNE ISOTCPZS REPORT CF ANAIYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 14 3-2293 01/12/77 0 1/24;/77 ATCOR INC PARK MALL PEEKSKILL N Y 10566 SWIPES TELEDYNE COLLECTION-DATE NUCL-UNIT-, MID-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT--T 4 TIME VU N BER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE TOTAL dpm) U/M *4 DATE TIME VOLUME - UNITS LAB.
33 NO V WST PROC AREA 01/OR BE-7 L.T. 9. E 01 TOTAL SCi 44 01/17 K-40 I.T. 1. E 02 TOTAL *4 01/17 T .T. 1. E pci r N-5 4 01 TOTAL *4 01/17 CC-58 L.T. I. E pCi 01 TOTAL pci *4 01/17 CC-60 5.9 1+-0. 59E 02 TOTAL *
- CO-95 pCi 01/17 L.T. 2. i 01 TOTAL pc~i ** 01/17 11U-103 L..T. 1. E 01 TOTAL pCi 44 01/17 iit-1C6 L.T. 9. E 01 TOTAL 4* 01/17 i-131 L.T. 2. E 01 TOTAL pc i *4 01/17 CS-134 7.04+-1.322 Ol TOTAL pCi *4 01/17 pCi CS- 137. 3.64+-0.36E 02 TOTAL pCi
- 4 01/17 BA-140 L..T. 3. E Ol TOTAL pci
- 4 01/17 CE-141 L.T. 1. E 01 TOTAL pci
- 4 01/17 CE-144 L.T. 6. E 01 T CTA L 4* 01/17 pci RA- 226 L.T. 1. E 02 TOTAL pci
- 4 01/17 TH-228 L.T. 1. E 01 TOTAL *4 01/17 pci 31434 ST GARDEN W ABV BLST AREA 01/OR BE-7 l..T. 7. E 01 TOTAL pCi 4* 01/17 K-1O0 L.T. 1. E 02 TOTAL rci *4 01/17 MN-5 ~4 L..T. 6. E 00 TOTAL *4 01/17 CO-568 i.T. 6. F 00 TOTAL *4 01/17 pCi C0-60 5.01+-1.08E 01 TOTAL pci 01/17
.1T.7. 1. 3 01 TOTAL *4 01/17 RU-103 L..T. 8. E 00 TOTAL pci *4 01/17 pCi RU-106 L.T. 5. E 01 TOTALL *4 01/17 1-131 L.T. 1. E 01 TCTAL pci 44 01/17 CS-13.4 L..T. 7. E 00 TOTAL pci *4 01/17 CS-137 7.95+-0.80Z 02 TOTAL -Ci 44 01/17 BA- 140 L .,. 2. E 01 TOTAL pCi *4 01/17 CE-141 L .T. 6. E 00 TOTAL pci *4 01/17 CE-144 1.T. 2. E 01 TOTAL Fci *4 01/17 pCi RA-226 L.T. 6. E 01 TOTAL *4 01/17 TH-228 L.T. 6. E 00 TOTAL pCi *4 01/17
TELEDYNE ISCTCPFS REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 15 3-2293 01/12/77 01/24/77 ATCOR INC PARK HALL PEEFSKILL N Y 10561E SWIPES TELFDYNE COILECTION-DATE NUCL-UNIT-% MID-COUNT SAMPLE CUSTOMER' S STA START STOP ACTIVITY ASH-WGHT-l
- TIME NUMBER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE TOTAL dpm) U/N ** DATE TIME VOLUME - UNITS LAB.
35 POOL I WALL 01/oR BE-7 1.T. 6. E 01 TOTAL Pci ** 01/17 4 L.T. 1. E 02 TOTAL Fcj 4* 01/17 4 8.8 1+-6.76E 00 TOTAL pCi ** 01/17 4 CO-58 L.T. 7. E 00 TOTAL p Ci ** 01/17 4 CO-GO 5. 19+-0.52E 02 TOT AL pCi ** 01/17 L.T. 1. E 01 TOTAL pci *4 01/17 4 Ril- 103 L.T. 7. E 00 TOTAL *4~ 01/17 4 8 U-106 L.T. 6. E 01 TOTAL *4 01/17 pCi 4 1-131 1.T. 1. E 01 TOTAL PCi *4 01/17 CS- 134 L.T. 8. E 00 TOTAL pCi *4 01/17 4 CS-17. 7.16+-0.82E 01 TOTAL pCi *4 01/17 t.
B A- 14 0 L.T. 2. E 01 TOTAL pci *4 01/17 4 CF- 141 L.T. 7. E 00 TOTAL. pCi 4* 01/17 4 CE-- 1414 L-T. 3 E 01 TOTAL pCi *4 01/17 RA-226 L.T. 7. E 01 TOTAL pCi *4 01/17 4 TF-228 L.T. 7. F c0 TOTAL pci *4 01/17 4 ZN- 65 3.23+-1.57E 01 TOTAL pCi *4 01/17 4 AG-I 1CM 1. 23*-0. 14E 02 TOTAL *4 01/17 4 pCi pci. 4 31436 POOL 2 WALL 01/OR BE-7 1..T. 2. 02 TOTAL *4 01/17 E pCi K-40 I.T. 9. E 01 TOTAL pCi *4 4 pCi 01/17 MN- 5 4 T_.T. 2. E 01 TOTAL 4* 01/17 4 CO-58 1.-T. 2. E 01 TCTAL 4* 01/17 4 CO-GO 1.20+-0. 12E 03 TOTAL pCi 4* 01/17 4 ZE-95 L.T. 3. 01 TOTAL pCi 4* 01/17 4 pCi pCi RU- 103 L.Tý 2. 01 TOTAL pCi
- 4 01/17 4 EU-1 06 L.T. 2. B E 02 TOTAL *4 01/17 I- 1 31 I.T. 3. E 01 TOTAL *4 01/17 4 pCi 4 CS- 134 L.T. 2. 01 TOTAL pCi
- 4 01/17 CS- 137 4. 69+-0. 72E 01 TOTAL 4* 01/17 4 BA-140 L.T. 7. E 01 TOTAL *4 01/17 4 pCi CE-141 L.T. 2. E 01 TOTAL *4 01/17 '4 Pei CE-144 t.T. 7. E 01 TOTAL *4 01/17 '4
- - - - - - - - - m TELEDYNE!ISCTCP3S REPORT OF ANAIýSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER LATE RECEIVED DELIVERY DATE PAGE 16 3-2293 01/12/77 01/24/77 ATCOR INC PARK nALL PEEKSKILL N Y 10566 SWIPES TELEDYNE COILECTION-DATE NUCL-UNIT-% NID-CCUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-%
- TI.E NUnEBR IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE ( TOTAL dpm) U/M ** DATE TIME VOLUME - UNITS LAE.
.36 POOL 2 WALL 01/OR RA-226 L.T.. 2. E 02 TOTAL pCi 01/17 4 TH-228 L.T. 2. E 01 TOTAL pCi
- 01/17 4 AG-110M 1.60+-0.16E 03 TOTAL pCi
- 01/17 4
TELEtYNE ISCTCrES REPORT OF ANALYSIS RUN DATE 01/21/77 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 17 3-2293 01/12/77 01/24/77 ATCOR INC PARK MALL
.PEEKSKILL N Y 10566 WATER - GROUND TELEDYNE COLLECTION-DATE NUCL-UNIT-5 Mir-CCUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITY ASH-WGHT-i% TIME NUMBER IDENTIFICATION NUM DATE TIME EATE TIME NUCLirE (pCi/liter) U/M ** DATE TIME VOLUME - UNITS LAB.
.461 STAGNANT-SO COR CLEAN OUT 01/OR KE- 7 I,- T ° 4. E 02 01/17 4 l.T. 6. E 02 01/17 1.'59 +-0.5877 02 01/17 4 C0-5 8 1.T. 6. E 01 01/17 CO-60 5.22+-0.52E 03 01/17 4 ZR-95 1.T. 1. E 02 01/17 RU- 103 1!.T. 5. F 01 0.1/17 4 pU- 1C6 I.T. 5. E 02 01/17 "4 1-131 I..T. 8. E 01 01/17 4 CS- 134 1.T. 7. E 01 01/17 4 CS- 137 2.50+-0.59E 02 01/17 4 EA-i140 I.T. 2. E 02 01/17 4 CE-1'41 I.T. 7. E 01 01/17 4 CE-144 I.T. 3. E 02 01/17 4 RA-226 1.T. 7. E 02 01/17 4 TF-228 L.T. 6. E 01 01/17 4 LAST PAGE OF REPORT APPROVED BY K. ROACH ' 01/21/77 SEND 1 COPIES TO ATI00S 2 - GAS LAB. 3 - RADIO CHEMISTRY LAB. 4 - Ge(Li) GAMMA SPEC LAE. 5 - TRITIUM GLS/L.S. LAB.
Radiation Profile Data in South Corridor Excavation Radiation in mr/hr Depth (ft) 4'S* @ CL 4'N* 12'N 10 0.025 0.40 0.05 11 0.030 0.40 0.03 0.05 12 0.025 0.60 0.50 13 0.025 0.35 0.40 14 0.15 0.40 15 0.10 0. 25 16 0.10 0. 07 17 0.08 0. 06 18 0.07 0 .05
- Locations are in reference to the clean out (CL).
ATCOR
.7.. ..
'DI*$TRIAL REACTO. LAeATO-S. INC.
Siabsid;ary of N. L. Indu;tr as Iu$nc PLAINSZOROc, "EVJJ"R:;.Y i4536 I,'DUSTRIZS August 30, 1976 Mr. Leif Norrholm USNRC - Region i Office of inspection and Enforcement
" 631 Park Avenue lKing of Prussia, Pennsylvania 19406
Dear Mr. Nvrrholm,
RE: License No. R-46, Dbcket 50-17, Report of Failures irn the IRL Radwaste System Piping
SUMMARY
Confirming our telephone conversation of May 27, 1976, this report describes failures to "Planned Safeguards" in the IRL Radwaste System.
Failures have occurred in a total of nine locations.-.
of them are reported in this notice, and .one was reported previously on March 21, 197,5.
I This report does not contain any information reportable
- under 10 CFR-20o405. However, there are clearly "Failures of Planned Safeguards"., which are reportable per paragraph 3-.6 .
amendment #21, R-46 License and which have relevence to ei.'"
I fabrication, and installationquality, control.
The Waste Evaoorator Sump failure is the only instance where radioactive materials were released into soil not wholly within the existing physical structures of the IRL facility.
In no instance have sample data indicated concentrations in excess of 10 times values in 10 CFR 20, Appendix B, TaVi iI. It should be noted that Regulatory Guide 1.86 does not address this problem in any manner.
I . *Surveys, ground water, and soil samples indicate that no I detectable amounts of radioactive materials exist in the site water table or the soil where migration could reasonably be expected.
I _---. . .. J*~- ---
DISCUSSION The initial doscovery was on March 22, 1976. The enclosed report to the IRL Safeguards. Committee, 24 May 1976, details the events from that time to 20 May 1976,'.
when the failure of the Waste Evaporator Sump was dis-covered. Until May 20, 1976, survey results indicated that each failure was localized., and'that no uncontrolled release to the environment had occurred.
On May 20, 1976, it was discovered that there had been a failure of the Waste Evaporator Sump, and that materials collected in it had leaked into the soil immediately adjacent to the North wall, and into the fill under the floor of the Evaporator Building.
Efforts were undertaken immediately to determine the extent of this leak, and of course, to assess the health hazards. The work was proceeding under a detailed work procedure, and associated special work permits and was, therefore, well under control, and protective measures were well within 10 CFR 20 and as low as practical requirements.
Other work which had been undertaken concurrent with this period required continuous pumping of the water table.0 The water was sampled regularly and showed no indication of any radionuclides being present.,
The IRL Safeguards Committee was convened on May 27,1976, and the findings reported in the May 24, 1976 memorandum were considered. The committee recommended that soil and ground water sampling be undertaken. Two test holes were excavatedC sampled and analyzed, and the results reported in a mernoranc, dated June 7, 1976, (Included as Supplement F). The commLttee also agreed that the contaminated soil should be removed to the concentrations which are roughly. equivalent to those specified in 10CFR 20, Appendix B.
The committee considered the option of leaving the then estimated 40 mci of 1 3 7Cs.and 6 0 Co. activity, on the basis of low as reasonably achievable, and the assumption that all of.
the material subjected to the annual. site rainfall would not result in the ground water activity exceeding values in 10 CFR 20, Appendix B, Table 11. However, IRL has elected to implement the more conservative approach outlined in the corrective action below.
Sampling and surveys subsequent to the May 27,. 1976 IRL Safeguards Committee meeting have shown that the contamination of the soil presents only an external radiation exposurerisk.
4- .. --.11--l- .1-111---l- -
-Therefore,' if the recommended d cme d
-r torrective.action ive is followed, . * * .,i
--the levels the radiation exposure of externalspecified-in:0 will be reduced to within limits .CR 20 for the general
",.*,public, and low as reasonably achievable. Furthermore., it
--is clear that no risk of internal-exposure exists now or in the future.
CORRECTIVE ACTION "
Soil- which clearly presents a *potential for external
- .adiation exposure in excess of 1I0 CFR 20.105 .para(ý.)will be surface- downt-.,to .:a. dI.epth o01 nio lesls than removed from the 4 feet.
Any structural surface thicýn- is contaminated from the surface to 4 feet, will be decontaminated to the limits specified in USNRC Regulatory Guide -. 86, using techniques specified in the IRL Dismantling Plan, and other proven work procedures.
If there are any questions regarding this matter, please contact us.
ry trul, u
- David eig'h e.
Industrial Reactor Laboratories, inc.
Decommissioning Project Ianager
0 IRL REPORT AUGUST 30,1976 ATTACHMENTS EXHIBIT A'- ATCOR Memorandum, with supplements A thru I, 24 May 1976, Radioactive Material Uncontrolled Release.
B ATCOR Memo, August 13, 1976
.Results of Soecial: Earth Sampling Program,, IoRoL.
C ATCOR Memo, August 18, 1976 "Radiation Profiles of the South Corridor".
ATCOR ME M 0 R A N D U M TO: IRL Ridiation Safeguards Committee FROM: Robert G. Levesque, ATCOR Project Radiation Protection Officer DATE: 24 May 1976
SUBJECT:
Radioactive Material Uncontrolled Release During the phases of work requiring the removal of radioactive liquid process systems, several places where radioactivity had leaked from the .process systems were detected by ATCOR. These areas were not known to be radiological control problems, until their discovery.
A list of those areas where leakage was detected follows:
- 1. "B" Waste clean out, East Corridor.
- 2. "B" Waste clean out, hallway outside High Level Lab.
- 3. Decontamination pan drain.
4- Blow Down Tank hole.
5- Feed Tank, flanged drain connection.
- 6. Waste Evaporator sump.
In each case sizeable quantities of radioactivity were lost from the system, but only in areas 4, 5, and 6, were radioactivity inadvertently released to the environment.
In the case of the "Blow Down Tank", all radioactivity released in the environment may be recovered due to the unique construction of the "1OK" Catch Basin.
Each area with all the findings known to date follows for your information and action.
- 1. "B Waste" clean out, East corridor A=3.8 mci (See Supplement A)
On 3Z22/76, we started to excavate "1B Waste" piping at clean out. A small hole was dug down to the pipe and it was determined the piping had failed.
l An.analysis of the dirt removed in reaching the pipe was performed. Results showed Cs 137 contaminative level to be 1x1i0 uci/cc and Co 60 to be 4xio -4 uci/cc. The earth samples were taken from the soil piled in the corridor. We then proceeded to package the soil piled in corridor in 55 gallon drums.
On 3/24/76, the crew dug contaminated soil from the excavation packaging the soil into 55 gallon drums.
Drums of packaged soil were reading 5 to 10 millirem per hour at the drum surface.
We determined that the plastic pipe had failed at the point where it was joined. The pipe sections had been plastic welded together and it was apparent that the weld was never complete.
See Diagram Below:
IUJI
~t .'
ATCOR
Vertical clean out pipe was attached to "B Waste" line by cementing (plastic weld), two 450 sections onto horizontal plastic pipe. About 3 inches of lower weld seal was never completed.
On 4/26/76, the sections of1"B Waste" piping, were extracted from under the earth. Radiation survey of excavation in East corridor showed that the removal of the "B Waste" piping did not reduce the dose rate.
The actual dose rate was 20 millirem per hour.
On 5/12/Z6, removed additional contaminated soil from below the original "B Waste" piping. Dose rate in the excavation was reduced to 10 millirem per hour.
The soil is contaminated out to the inside East wall corridor foundation. This indicated the liquid activity came up to within 18 inches of the corridor floor.
- 2. "B Waste" clean out, hallway outside High Level Laboratory A.=(S= 25mci) See Supplement B On 5/10/76, crew jackhammered area of floor in vicinity of clean out, but did not progress further.
On 5/21/76, shoveled earth around vertical riser down "B Waste" piping. Determined that the plastic piping had broken off just above or at the tee where it was joined to the horizontal piping. It is apparent that the earth has settled about six (6) inches between the hallway wall footings. This action caused the plastic pipe vertical member to be sheared from the horizontal section.
Radiation survey at the top of the excavation is 40 millirem per hour, and at the break in the piping the dose rate is 110 millirem per hour. The Cs 1 57 activity is in the order of luci/cc in the area of the break in the pipe.
- 3. Decontamination Pan Drain Az (S=O.1 mci) See Supplement C On 4/16/76, the stainless steel decontamination pan was removed from the floor inbedment. The loose surface contamination was verified to be less than 1,000 dpm/100 cm2 ,
but had fixed activity above release criteria. This pan had to be removed to reach piping below. When the pan was raised, loose surface contamination as high as 20,000 dpm/100 cm2 was noted. In addition, the sand below the decontamination pan was wet from leakage from an inadequate. pipe fit uD. See Diagram Below:
I awl ý /. a
,";' ":* b * , . *;*. 7 r. , * -; .
~ATCOR - ' VC.
d*
I
The steel piping from bottom of decontamination pan drain was fitted down into the plastic pipe. Water had..
backed up and escaped into the sand between concrete and the bottom of the decontamination pan.
On 4/27/76, packaged the sand that was below the decon. pan placing the sand into 55 gallon drums. Broke the cement base and sides off the edges of the decon. pan inbedment. Packaged this material as radioactive waste.
On 4/28/76, excavated and removed 1B Waste" piping from the decon. pan drain.
- 4. Blow Down Tank Hole Aý MPC for Cobalt 60 in water See Text On4/30/76, completed 'pumping all available sludge-possible from blow down tank, when ground water in the 1Ok catch basin broke through the bottom of the tank. Total water in leakage was approximately 1,000 gallons.
Between 5/3/76 and 5/12/76, prepared to contain and prevent loss of activity from the failed 10k Blow Dovm Tank. Plan was to remove known contaminated top soil over
..10k catch basin, excavate crush rock around the tank, pump radioactive liquid from tank until ground water level was at the bottom tank and then lift South end of tank to prevent outflow of radioactive liquid.
On 5/14/76, Lifted up South end of tank to prevent outflow of activity from tank to catch basin.
On 5/15/76, installed fiberglass patch to seal 10k Blow Down Tank. Analyzed samples of crushed stone from the South end of catch basin, in the vicinity of the leak.
Analyzed the water in the Eastern section of the 10k catch basin which is separated from remaining sections 10k catch basin, with a two (2) foot baffle. Results of the analysis of the crush rock and water shows the crushed rock and water to be at or slightly higher than NPC for Cobalt - 60 in water.
- 5. Feed Tank Flanged Drain Connection AW'ý5 x NPCw Cs 137 & 2 x MPCw Co 60
.As:. 10 x 1IPCw Ca 137 & *2 x MPCw Co 6 0 On 5/13/76, excavated feed tank, 2,500 gallon tank, on the West end and behind the tank to the building wall.
,.Noted water entering the excavation from under the feed tank. Sampled the water, analysis shows Cs 137 activity to be 5 x PCw & Co 60to be, V2xMPC W ATCOR
It was thought that the tank may have shifted or rolled to the West rupturing the bottom flange connection or that the tank was rusted through on the bottom. In order to prevent additicnal activity to enter excavation, the tank was rigged into vertical position and the plastic pipe was plugged.
We noted that the bottom fitting was never made up properly from its initial installation. See Diagram Below:
rt 4-By design a split ring flange is to be bolted together, and plastic flange attached to plastic pipe,is fitted and sealed against tank flange with 4 bolts.
We found:1) the split ring improperly assembled, 2) One bolt missing, 3) split ring broken, 4) two nuts on other bolts missing.
Only the weight of the tank onto plastic flange kept the water from running into the ground rather than into the pipe.
On 5/14/76, plugged bottom opening in feed tankz.and removed the tank from the excavation. Sampled and analyzed soil from the feed tank, excavation and on sides of excavation..
Results show that the activity was in the order of 2 to 10 x MPC w for Cs 137 'on excavated earth with sides of excgvation being 1 to 2 x MC w for Cs 1 3 7 and 2 x YCw for Cob0 at a depth of 3.5 meters. The lowest point of the excavation is at the tank footing which is below the water table (about 20 Cm Below).
- 6. Waste Evaporator Sump A- (s.= 6 mci) See Supplement E On 5/20/76, excavated earth from between the distilate tanks and the building to a depth of about 4 meters. A radiation survey of the excavation showed gamma levels at the base of the waste evaporator footing of 20 millirem per hr.,
and under the footing where earth has slumped from the floor, radiation as high as 40 millirem per hour. See Diagram on next pg.
ATCOR TOP VIEW WASTE EVAPORATORP SUMP BLDG.
1711 77
Ž I """. ' " ._ "
w
.777 t-, : .:....'" < ...- . ,,.:.,..." i ,,,' ."./
- ---ýEARTH ZREMOVED -FROM" EXCAVATION __
SIDE VIEW LOOKING SOUTH
.WASTE EVAPORATOR
- 1 BLDG.
I. ". . . - - SUMP
' *I'*.',.
- Footing '...."". I nder building 40 mr hr
..- .~2 0 m r/hr Il- * .
~I-C .10 mfr/hr
,, . ..... K.I.
, ? - . ,.-i.ii-. .-..
- mov'
, , f s /,J - -. -. /
S . ',
-, m&..n, *.4 ATCOR
See diagram on previous page.
The waste evaporator sump failure was caused byý the waste evaporator building, (which was constructed after the other IRL buildings were completed), settling 2 - 3 inches. This settling caused the "seal" around the edges and bottom to fail, which allowed liquids that were collected in the sump to drain down the East wall of the main building foundation., The main building is the fourth side of the sump and is common to the sump and the main building.
-6a-
On 5/21/76, analyzed within the vicinity of the North wall of waste evaporator building. Results of survey and a diagram showing sample location follows:
( '(/
/
'N
/ 1../
J
\-
I. '7.t!"
ATCOR
-~7-
cs137 Co6 0 SAMPLE Point uci/cc uci/cc 6 x 10-6 MDA 2 6.9 x 10-5. 1.15 x 10-5 1.6 x 10-2 1.39 x 10-4 3
4 7.4 x 1o-3 1.1 x 1o-3 5 7.7 x 10-6.
5 3.9 x 10-6 2 x lo -5 2.7 x 10-6 7 6.7 x 1o-5 1.9 x lO-5 8 3.96 x 10-4 2.5 x 10-4`
6 6 x 10 -6 3.5 x 10-9 10 6.1 x 104 2.1 x 10-4 ATCOR 8
1*.~
4 SUPPLEMENT A NOTES Estimated Activity Remaining in East Corridor 3 mr/hr Assume activity was all on surface 11/2 feet from center R/HR Z 6. C.E. @ 1 foot (1.5) 2 x 3mr/hr - 6.c. (0.662)
C= 3mci x (1.5) 1.9 mci The activity must be dispersed in the soil and self attenuation and additional distances are involved. It is also suspected that the activity decreases out radially from point to leak. Use a factor of two times the above result as a good estimate.
A-= 3.8 mci I. ATCOR
SUPPLEMENT BT Estimated Activity in High Level .Lab
- .~ .~~.VOID A 'kil-
-- -F h ~Ak~
It is assumed that the plastic pipe is lower than the break by amount of void.
Test of data for point source D1I 2 2R22 2 in2)2 40 mr/hr x (22 in) - 110 mr/hr (4 19,360 1760 The data tends to indicate a type of area source. An estimate of activity present is in the order of S= 25 mci
.
- ATCOR I
SUPPLEMENT C I Notes I Estimated activity in Decontamination Pan Area I
I ""- at 2" DR 0.2mr/hr Using surface source geometry for estimate I -3/2 S/A S A% 2 3
I S- dis 30 ft. 2 x 144 in 2 x 6.45 cm2 x 2 0.2 mr x 7.7xl02.D
- -5ph ft e w hr3 tir cmr h
hr I
Sx 3.365 x 106 dis x 3T7xlI~O disTsec I sec S- 0.909 x 104 ci I S= 0.1 mci I
I I
I I
I I.
i ATCORo
SUPPLEMENT D Notes Waste Evaporator Sump From point of the base of the sump, the activity seems to have dispersed in all downward directions radially (except west due to building foundation) and also seems to have followed the building wall down to the footing. I feel that the activity once reaching the water table dispersed rather than concentrated.
The data tends to support, the activity/gm being within 12 feet of the source of the leak. The source being in the vicinity of sample point 3 and at 12 feet sample point 6:.
& 9 , do not have activity levels above release criteria.
.2M 3M 4M 1,000 MPC 2.5 MPC NPC The concentration of activity falls off about 2 times faster.
than in point source geometry or 2/R 2 .
ATCOR
SUPPLEMENT E TO: Mr. David W. Leigh, IRL Project Manager Mr. Ted Holman, V. P. Operations, ATCOR Mr. Owen Sullivan, ATCOR Project Manager FROM: Robert G. Levesque, Project Radiation Protection Officer DATE: 2 June 1976
SUBJECT:
Waste Evaporator Sump Problems In the IRL Radiation Safeguards Committee meeting of 27 May 1976, additional samples and studies were identified to be run to better identify the nature of the release of the activity to the environment and to evaluate the release of the activity in the environment.
- 1. Estimate of Activity under the Waste Evaporator In report made to IRL Safeguards Committee dated 24 May 1976, the data shows that the radioactivity per cubic centimeter falls off inversely proportioned to one half the square of the radius from the underside of the Waste Evaporator Sump. A calculation was made to estimate the amount of radioactivity in the area of the release. The result is about 6mci and the calculation is attached as enclosure 1.
- 2. Results of Analysis of Water in the Water Table within 3 feet from the corner of the building.
The soil under the sump is contaminated with Cs'3 and Co"0 which were identified by gamma ray spectro-analysis - No other gamma emitters could be identified.
It may be possible for S.v -y ' to be present as it was in abundance in the concentrated evaporator waste. If water was to perculate through this said form above, to the water table, then it follows that the water closest to the leak should have the highest concentration of radioactivity. During the excavation ground water entered, was sampled, and analyzed. The result of the analysis was as follows:
Sample counted in Marinelli Beaker for 10 minutes A Cs137 7.9 x 10-7 uci/ml A Co 60 7.8 x 1o-7 uci/ml
- 3. Soil Analysis A sample of soil along the vertical earth wall under the Waste Evaporator footing was obtained for special study to determine:
- 1) If the activity would go back into solution.
- 2) The amount of activity which would go back into solution in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period.
- 3) The mechanism by which the activity may reach potable water. To obtain a representative sample,a 200cc sample was obtained across the face of the-excavation at a height below six inches of the Waste Evaporator building footing.
Results of the analysis was as follows:
A Cs137 1.96 x 10-3 uci/cm3 A co60 5.8 x 1o-4 uci/cm3
- 4. Leach Test The 200 cubic centimeters of soil obtained and analyzed was added to 2.5 liters of IRL tap water. The sample was mixed and allowed to stand for 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br />. The water was decanted off into a clean flask, and was filtered through Whatman filter paper. The filtered water was counted on the multi-channel analyzer in the Marinelli Beaker. Results are as follows:
A cs 137 . 3.47 x 10-5 uci/ml A Co 6 0 4.3 x 10-5 uci/ml The second set of filters used to filter the water was also counted and the count rate is present also for information.
Cs7 Cov - 2,384 cts/10 min 360 cts/10 min
- 5. Presentation of the Data for Cs 1 3 7 and Co 6 0 patios 37 For each analysis the ratio of Cs1 /Co 60 activity has been calculated: C8137f C060
- 1. Water in water table 1.o1
- 2. Soil used in test 3.38
- 3. Filtered water in leach study 0.506
- 4. Filters used to separate soil &H2 0 6.62 ATCOR The activity in the ground water and the activity in the Leac 6 0 Test water have 'the same ratios of
- Cs13 to CoP
.-..The-da* taken in 'the 24-Ma-y-1-976 report shows that the Cs!'/CobO ratio to be about 100 near the source of the leak (Sample Pt.3), and lJss than 10 at all sample points 3 meters from the release point.
- 6. Calculation to determine Quantity of Activity Removed in 68hour Leach Test Total activity in 200 cc of soil.
ACs137 - 1.96 x 1o-3 uci x 200 cc 3.92 x 10-1 uci A0 o60 - 5.8 x 10-4 uci x 200 cc 1,176 x 10-1 uci Total activity found in the Leach water:
Note: Quantity of solution used in leach testing
- was 2.5 liters ACs 1 3 7 3.47 x 10-5 uc x 2.5x103ml 8.6 x10- 2 uci ml A Co6 0 4.3 x 10-5 uc x 2.5x10 3 ml -1.08x10- 1 uci ml Percent of activity removed from 200 cc sample R Cs1 3 7%' 8.6 x 102l uci x 100 % - 21.9 %
-. 3.92 x10- uci R Co 60%/=. 1.08 x 10-1 uci x 100/ - 91.8%
1.176 x lO1 uci
- 77. Discussion of Results Due to the chemistry of Cobalt, it was expected that the percentage removed in a Leach Test study would be much lower than cesium for the following reasons:
.for~ *2ý Ion exchange would tend to hold and contain Co to a higher degree than Cs fo~r pH 7 7...
Co*++20H- " Co (0H)2\in wet solutions and will go t@°Co 0 on removal of the water.
Then by either ionexchange and filtration Co 6 0 should be retained in the soil over Cs 13 7.
This is not what is happening. Cs137 was retained in the Leach Test soil (k6 analysis .- 20% was removed),
and almost all the Co was removed.
ATCOR
- i-3* * ' -
- 8. Conclusion Cobalt was shovm to leach from the -soil and, therefore, is expected to move through the soil at a much higher rate than Cesium.
- 9. 1mp1cation of Findings In areas where soil was found contaminated from the release, it was determined that 6 the0 concentration of Cs 137 always exceeded that of Co From an independant study done for IRL to estimate effects of radioactive releases on the environment, it was learned that metalic ions of ++ (Sr9 0 ) would take about 20 years to reach a depth of 8 feet. It follows that a singular charged metalic ion in the same soil would travel about 4 times faster (rule of thumb for ellutions with ion exchange media).
Since Cs 1 3 7 was found at a depth of 8 feet, the projected time span of the release could be as far back as 5 years ago. This estimate may be in signifi-cant error in that the water released from the sump could be quite different than the average rain fall on the site which was the driving force in the pre-vious mentioned independant study.
It can also be postulated that the soil under the Waste Evaporator building may have a higher concen-tration of activity since it was not subjected to percolation effects from rain fall as the soil North of the building which was analyzed and which is the basis of this study.
The activity released from the sump to the environment as well as other contaminated soilfound in the environment does not have the same Cs to Co 60 activity ratios as the blow down tank waste. This could mean that the activity in the environment that was released, had higher concentrationf of Cs 137 than Co 60 than the waste contained in the blow down tank, or that the Co 0activities had already passed through the soil to the water table.
It is estimated that the test performed for the leach study approximates the conditions which could be expected from the average rain fall (about 32.5 in.)..
on the contaminated soil.
The water reaching the water table exceeds the potable water drinking water specifications by a factor two. It is reasonable to expect that the dilution factor of two may be applied for activity washed (leached) from soil once reaching the water table. This assumes that the'removal rate in the environs is the same as in the leach test.
ATCOR
ý_Jj.
Calculation for Activity in Vicinity of Waste Evaporator Sump Where K is concentration ENCL #I at any point Ko"1 (Emperical relationship supported by previous data in May 24, 1976 report)
K x RI 2 MPCw x , (16M2 )
R-- 4M K MPCw x 16M2 (Concentration at 4 meters was measured & shovm to be MPCw for 1 3 7 Cs- from May 24, 1976 data)
S- K.V ds - K. dv
- x. -42.JTR3 "'IYR3 3 2 dv -- J R2 dr 2 ds MPCw X 16M2 x _2' R
drR 2 ds- 24 IPCvi.mete M ? dr S-Xfds 241 I14PC x H2 4M S -- 24T'x2xlo-5 uci x 413 x I0 6 cm3 cm3 M3 S 24 x fx 20 x 4 uci uci 6, mi .137cs S -
ATCOR I
ATCOR SUPPLEMENT F TO: David Leigh, IRL Project Manager Ted Holman, V.P. Operations, ATCOR Owen Sullivan, ATCOR Project Manager.
FROM: Robert G. Levesque, Project Radiation Protection Officer DATE: 7 June 1976.
SUBJECT:
Follow-up Data for Waste Evaporator.Sump problem On June 3, 1976, two holes were dug down to the water table, samples of soil at various heights and samples of water were obtained. The first hole was dug North of sump about 30 feet from the sump._. The.second hole was dug about 75 feet North of the building.
The samples were analyzed on June 4, 1976, and the results followed:*
Isotope 30 feet from Sump 75 feet from Sump Water Cs137 1.78x1iO-*c/ml 6.9xi 0 "7uc/ml Co 60 1.45x1 0-c/ml 5 x 10 7 uc/ml All of the soil sample data statistically indicated no activity above background (at 90% confidence counting factor).
Conclusion The release of activity to the environment from Waste Evaporator sump has not caused the ground water to be above the drinking water limits of 10 CFR 20. The data also shows that the concentration near the leak to have.
a slightly higher-concentration than the point furthest away.
ATCOR I
ATCOR
,SUPPLEMIENT G TO: Davi-d Leigh, IRL Project Manager Ted.Holman, V.P. Operations, ATCO*
Owen.Sullivan,.ATCOR Project Manager FROM: Robert G. Levesque, Project Radiation Protection Officer DATE: 7 June 1976
SUBJECT:
IRL Water Table On June 3, 1976, I spoke *to Mr. Norman Banks of' Griffin Ground Water Control. He stated that for the type of soil, depth to well point, type of vacuum pump and the number of well points that for the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period, that the pumps were on the water table was depressed out to 90 feet from the well points. He also estimates that the flow from the vacuum pump discharge was about 700 gallons per min..:
Since the straight quantity of liquid pumped is slightly over 3 million gallons, and since the total space emptied is much less than the quantity pumped, it follows that the water table turnover was about 50 times (Total space emptied had to be filled an equivalent of 50 times to equal total volume pumped). The water at the point under the Waste Evaporator Building most likely flowed towards the void, was diluted with other waters flowing towards this point, and was pumped from ground to the surface water. The water being pumped from the ground was sampled several times and was analyzed, and no radioactivity levels above.background were notedt
- ATCOR
SUPPLEMENT H 7/16/76 ATCOR.
To: Owen Sullivan, ATCOR/IRL Project Mgr.
From: T.C. Weeks
Subject:
IRL Hot Cells Contamination This document for the record observations made b~o Atcor decontamination technicians of certain structural defects which appear to have been responsible for leaked radioactivity to the concrete floor beneath the steel sheathing in all three Hot Cells.
To provide access to Cell thru-floor drain lines for removal or decontamination, it was necessary to detach steel sheathing in each cell by acetylene torch (from what appeared initially to be the body of the drain cups as shown in attached sketch. However, after cutting away sheathing and removal of drain cups and rings by destruction of adjacent concrete, it became obvious that sheathing was attached by weld to the steel rings only. In the absence of sealed joints between rings and cups, liquids had been free to pass and flood free space beneath sheathing and around drain lines.
Dose rates of contaminated concrete ranged from approximately 1 mr/hr. in cell no. 1 to approximately 3 mr/hr. in cell no. 3. Cell flooring three feet thiCk had to be completely removed from around the drain line in Cell # 3.
Pe. zFox.ATs~b FLA-re C °,
0
- ca TrO SCALE=
m - - - - - - - - - - -- - - - -
F COR PARK MALL, PEEKSKILL, NEW YORK 10566 TEL: 914-739-9000 TELEX: 969535 SUPPLEMENT I TO: David W. Leigh, IRL Project Manager FROM: Robert Levesque, ATCOR Radiation Safety Officer
SUBJECT:
"B" Waste Piping in Hot Cell Corridor DATE: August 30, 1976 During excavation and removal of "B" waste piping, a system failure was detected under the floor in the corr-idor which leads to the Hot Cells from the East Rx Dome door.
At the leakage point, the soil was analyzed and was determined to have activity concentratipn in the order of 3x0 - 5 uci/cc for Cobalt-60, and 5x10 -'uci/cc for Cesium 137.
It is apparent that some leakage had occurred where the plastic "B" waste piping was joined to the Hot Shower drainage piping which was cast iron.
ATCOR has excavated 14 Cubic feet, and has determined that the leakage has contaminated the soil and footings of the hallway to a depth of 3 feet.
ATCOR proposes to excavate and remove the contamination until radiattion readings are less than.0.25 mr/hr.
TO: E.. .C. .o-olman,. Vice.Presid~ent _of.ATCOR FROM::
T Robert--G--,Levesque .'Rad-dia-t:ionr.Prdtecti6n Officer, -ATCOR
SUBJECT:
Results. of Special Earth Sampling Program, I.R..L.
DATE: August 13, 1976 "
At the. request of IRL, ATCOR instituted a sampling program to evaluate the extent of radioactive concentrations in the earth below floors where known leaks in the "B" waste system had been
- identified. A list of those areas where samples were taken is as follows:
-1. South Corridor, outside High Level Laboratory; 2.' East Corridor;
- 3. Waste Evaporator Building.
Results of these samples are.enclosed as Attachment A. In ad-dition, three sketches are.included to.enable the reader to
- better understand how the building structural walls and footings
.are shown on the IRL drawings.
I InMr. Kenneth W. Skrable's memorandum dated July 6, 1976, ad-dressed to David W.. Leigh, it was shown that the proposed re-lease Doint for contaminated soil of 0.25 ]nr/hr corresponded to drinking water limits. The actual value, as he calculated, is listed in the following table:.
Radionuclide .C ".4ci/gm)
Co6 0 4.70 x 0.-5 Cs 2.10 x 10'"
.Code of Federal Regulations,-Part 20, lists the drinking water limits for the following nuclides as follows:
I Radionuclide C (ci/ml)
Co 0 (I) 3 X 10o i csl 37 () 2 x10-5 The technique for taking earth samples above the water table is ..
described below:
- 1. Drill through existing floors; I . 2. Excavate.crushed stone;
- 3. Drive piping to sample depth;.
- 4. Remove pipe;
E. C. Holman - 8/13/76 R. G. Levesque .Page 2 S. Place smaller diameter pipe down prepared hole, obtain sample;.
- 6. Prepare 5 cc sample of extracted earth;
- 7. Count in 3" x 3" NaI (th) multichannel
. :analyzer.
A special sampling tool made to open at a required depth was used to obtain samples below the water table.
Water samples were also taken under the sub cell floor and at the water table in the South Corridor below the HLL corridor's "B" waste clean out. The samples required filtering to remove suspended solids. The results of these samples are included in Attachment A.
Findings and Discussion of Sample Results
- 1. It was determined that radioactivity re-leased from the system decreased with depth until the water table was reached.
- 2. Build-up of activity occurred at the water table. In most instances, the activity equaled or exceeded the concentration found in the vicinity of the leaking system piping.
- 3. The activity in the earth exceeds the release criteria at the water table, but then tends to fall off at further depths.
- 4. The activity in the soil to a depth of three
.(3) feet below the water table exceeds the release criteriain the South Corridor.
- 5. The activity required to be removed in the East and South Corridors extends below the building load bearing footings.
- 6. The soil or fill placed into the original footings and wall excavations as back-fill has settled and system leakage has channeled in directions of least resistance in reaching the water table.
- 7. Local pockets and strata have higher concen-trations of radioactivity.
- 8. The'water below the clean out in the South Corridor exceeds the drinking water specifi-cations.
- 9. The spread of the activity within the corridor foundations was approximated during the sampling program. It is possible that while
.excavating, additional areas above the release criteria may be uncovered.
A t- n M
E. C. Holman 8/13/76
- .R. G. Levesque Page 3
. 8. ..
Conclusions and Recommendations
- 1. Waste Evaporator Building The known contaminated earth in piles from previous excavations in the vicinity of the feed tank and I -
North wall of the waste evaporator should be packaged and disposed of as radioactive waste.
- The earth and contaminated floor with footings and sump should be removed and disposed of as radio-active waste to -a depth of eleven (1i) feet.
The known should .be,. of sections the building water-proofing reamved.
.material
" The section of wall common to the sump should be chipped to remove fixed activity.
The excavation on the North side of the waste evap-orator excavation known to oxceed the release criteria should be removed and disposed of.
The above described actions should reduce the present radiation levels and would allow further evaluation to determine if wall foundations require chipping and if additional soil is required to be removed.
- 2. East Corridor The soil under the flooring.in the vicinity of the clean out (twelve (12) feet either side) and down to where the excavations will allow removal without undermining the corridor footings should be removed and disposed of as radioactive waste.
This action will allow an evaluation of remaining
- activity requiring removal, to determine an approach to underpinning, if required, and to determine if scaling duct willthe required.and underground ventilation be f.ootings
- 3. Decontamination of Pan Area The known areas where soil exceeds the release criteria should be removed and disposed of as radio-active waste. The footings should be chipped. This action should bring the area to within release I specifications without further evaluations being necessary.
- A . . P
E. C. Holman 8/13/76 R. G. Levesque Page 4.
S .. .. *. . .
- 4. South Corr id6r.
Step A The floor from seventeen (17)'feet south of the "B" waste clean out to twenty-eight (28) feet north of the clean-out should be removed and dis-posed on site as clean waste along with the crushed.
stone that is under the floor. The earth beneath the stone should then be removed to a depth of twelve (12-) feet or to-the water tank and be packaged as radioactive waste.
Step B Extensive radiation surveys and earth samples may then be taken to accurately determine what further steps are necessary to remove the remaining activities in the local groundwater and earth. Those steps would then be performed to remove the remaining activity. *,
Step C Residual activities remaining on walls and footings could be identified by final surveys and removed to reach release specifications.
I ATCOR INC.
IEImsford, N. Y. 10523 I By Chkd. 'By Date Date _.
._. Page' Pg 5Sheet No.'
Proj, No.
" Of I .~ ~ ~ ..
... ~ .
4- . ' .... "".~ AQ ~9~
r - .*_ .
I, ' SOL)4
.L;Zop' Ill
.I.
A1
&QO7A'1 Co~iý-VOL (bJG P/-4t) V1 czj or~
1-1 t4c'/ 3cd4&~-~
- f7(u1 '3C1
I +/ " '
ATCOR IN%C5 Elmsford, N. Y. 10)523
- By Date Sheet No. __ Of Page 6 Proi. No.. ..
- "-CiChkd. By Date _
f4I
- 0.++
. ... . . . .. . . . + * . + . .
W- , -
Co~
-7&o4e Lale4
-vo)o cLI?4S/14c' ~&'ew'e
~5W3 CcZI 7,1La I,7 WI37,el, 7Z6 e /~
7II16 S6Cr/o/J I-I 6<4~)
.524Lc. J~
ATCOR INC. -.
Elmsford, 14. Y. 10523 Page 7 Sheet No. -. Of___:
By_ Date D ate ... Proj. No. __...... . .. __._
Chkd. By ..
. 4
- , - . ,,e.. . . . . I
).. . ..
i . ..
13."
jr 4" F.['"~-Z 7 ~Ez]_~1A
I.
I' E.
R.
C. Holman G.. Levesque
.8/13/76 Page 8 I Water Sample- Resu-Its - -
on 5 cc sample I Water taken below HLL "B"l waste clean out I Cs 137 Co60
- 4. 44 x 10
- 1.98 x 10-6i'c/ml
-e-C/ml I Water taken below Hot Cell floor 10 c/ml Cs6 s137 -2.06 x l 1.27 L 2.06 x lO-,e.xc/ml I
Robert G. Levesque August 13, 5.976
.RGL:pr cc: D. W. Leigh, I.R.L. Project Manager
- 0. R. Sullivan, ATCOR Project Manager W. G. Greenman, ATCOR Site Supervisor
I loo/
- 6. v AW
.
- I.1 p
4, i
7a:
- "I ** .. ° . '
'4,-I AM*]+
4.
"* . * *"+
XL6 ++
9P1 7
' )c,,/o,,,.
V x/"
x1O- KIF
-0<>
x 1.
Yk/0 i.
++
I
'1-' .*...I...I
- S. * *
.5 1 I +:I' * :, >.*i::::i~: ; :i ..:*!:: . , !::
.- .. . ~~.. . 1'i* : .:.:....:: ., .. .
Wi41l
I.. I' #1
'0',
I 6," 'I SAI-IPL;3 X0 1A5~if~iJiIJ24T 4 U....!'
I -.
.9.
I . E.
3,29 ,15-i- z -
.*,8 x<ia 3 *:
I I
7.*. j lip 8
p.
I '7 xo 3 .- "
e p42/' 4e I
.. (S27__ /O1 5. .
".i I Mr I
I. xi6 .I S. .-. .
I.. 4----
.1~*-*. '9 4 9
.4: 4
~ .> I.
I. 5
.. I - f;r,-9 59 I. jjcWlt
('-'lilt 0 * ~ ~
'9 a,
- V .9.
I
- 9.
- 9 I.
- *g.
9..
9 j** .9. 9 0 1I-1
j<, I.
L! P7ZT, 43.
I.
L~ 6 LI;/ t.
I..
4 45 S
S. K0-4
- i I i, i S
II
- a I.
- I
- I TO I I *
.~.
- ~*~*.*~4 A .. -
!I. It 2.
3....' I 4
- ~t... ~
a 3..
... .~ 4~
J*
~ *..
- a..
4,'
I (ý I
7;L-8.
(~~V~o~e
-V
/3'?
I "
I.
6.,1c) 4.
.32 66~
J . . .
Li.2 .
.. /\, /f
- , . V -
2,02 of
.J YI/
ms*
, Cx'- vI V V
- ./*' -
I A
.1.
S I J
- 1
- .3.
0
- . S. *47 I.
-I--
1(41211 I', 4.
I'*
. P1L a? l " /&7ej I 606:9
-- opoL I "
- I /
1*
,... ! .C'
___ _____ 79k/ ,.. .
.I,. . ..
. .. . . .. _?,. * . _ _ _ _ _ -
4
..... * ,E, - . - f' 4 V
V
.*. )C/O
- ",". * , ,*,,* * - "' o
.,-IO
.,: .. .. _X/_o i
. -A -
JIMP 1: "
I . . .
.I .I.
- .. "I..
=
I"I
.l
- , , *'........ LJIA
." ", " "*.I.** . .. *
. ... "" ": "- ~.""".* .'" : ". *
(
I 6.0 f~wASW?~V') ni FELT, I.Z-z I" :1 -
g *
'S.
t L x/o ,\Af*
- ~~
ISO Yf/06
'I '2 S..O?-S.-
7 Id6 .s +.
6' t e.
)<O76- el V~
1' 0-o I_ &' -- X/'O I*_
i
)4/O
>3,k)
KA,' o o oo..*
- lit "*
- 5-----..
- i. ..
I.
- ij I. I,.
I * -
3.
I.'
I a.
- j.irll z
Wag.
I I
I"
.3
..... .~" . . p s-I t
-AJ" . .. . . . .,
~2F/1 137" 6 I
.1.
. . ,0.
18,/I*,*~ ~~ X/O* 5 .... ?d iu - --.------ -*. .* ::%a *** e........................
. .. *...?...........
X10
. S * . . .* - -a . ":I:,. _
. ... . ... La*;..
V44
- . :.::i~ i . .:L a:. : '*. .* .
.I . .. .:-. ....
.* .*.V* .
. . . . . . .. .. A..
w /,J ,,, -L,(T. c v . . ,-.
- r. .... ". ..
- 4*1 0
. .. o'. 1 I " '"°°'"g . 6 . ,.
~ lf 7_* .... ... . _ _ _ __. ... C..
,.. ". .-. ' .. ' I . 5
/6 . - ..-; , .... .. .~ ,
- -. .T . . -- " . ! ; .. . .
- . .o. ..
- . -,
- :..*, -. .*.., X/0
- . ..,.......~ * ~. . :. - .
- .. .*l... * .. . ... " . .e- .... '.. . .... ... . '
- g '., '... ::7: .', ... X/c 0
71A9
' ' ' ' //
,* .. . ,: .d :
!8'-
i . .g *. , , .o
%" o Li 6. o z .~", * ,
II
I' I>.~
- a 33
- .SdI/PL £ ~C~/)22O,~J
- ... ~..:.*- 1/,77 1/
6o t1 tfPL r A-PT 33;
. *5* £ Si 5~.. ,7ol'
.7...z v 9 r.
x-o VI I/
/,62>ff 1- /0- --...
IL Yb 0*
i~.
I.
LIZZ
- .. . .5 .5 -.
- . . . *5 ~*
I
- 5 I;. ., .,
"'a . 55
. a
.5
~.
.. &... S .
- **.~../I..AJ
.... I. a3(4~Y>% 1.1,, -,
iLP'.'7~ ~ -
5
.5 .* 3
- I *:*'*.
1 5*, ~
- ~
551 * ~ .... ..
- a a **
S I.*
- 5*.
S
- SI.
.5 5 5***
60:
4W
. -°
~,.I LeU
- t 0*
41' .
Q i .#
- **, S.
b.
e.
.r x
S..
I
.1 x~V 4'
- *~~---*~ **~~* -r I..
I
- S I
- . t s.~S#
- I I. SI .
I,
- S.
, *,* I
- ** ~JI..
I.
.1
- 6
.. .. . V t I.
.5..
- a S *
- .g..:*.... **....... *.. *, ~
- S
- * . .. ?.....~ *6*... S. *I S~ .5 . * . S
- 'I
- b 2.- :1* a I I .Loo, a.., X . " '
a.
I ~2A).
a-
'L-' ( YA§C'l
.... .. . .~ . ~.
.* t . . .; . . * ' ""
Mei 226 t 1..,
"-t
'3 '.'.. - " - . " ":.. "" " .. :'.
.. '., *:. 6""
- . * : " ; * ' o . " . - ' . '. " -
- ole"#
- .. , . o * . *" . . i .-'.o. :"* .. .. . . ..." .. ., -.* . ..
- ~ ~ ~
,.. ,ý,v.oi.... ~ ~6 ..
,.**. * ,'*"."" ... , M.o.,., .
~*;":.."+%
":+- ~ . 9" -e3' '* i + . * * *.. ."".
d6'a I... 4 I.
- a a
- I.
- I%~ 6i~a 4>
AJ*)
SI ,~fP/.g ~D~'Ffl
~LL242~~ '5.
7-, .
N' I~. .
- " o .*1 9.' 9' . S.
-. .t .
- a4 I .V*
- 5,
- 2' ii. 3
~-I ______
.6 . . f, 1- 2 II K . .... . .
1K/C x/O
- I 1~* * ...
xit5 X'Z) xI/6 Wo ii .
x,,o Klj J ________________
'j- rv' ~ - ~
~~jI'=
I ..
9.
- 1f *5~* 5 *
- 4. \
S. >~ . ,.
t..
- *%~.
.9
.ih S
K' .1 I. ;5 5
II.
'5
- V
- ..A 4 ~
)
~*
- 8
.9 S
9 9. . . .9.
4*~9999 . ** *
.................. .9
- S
.1: * - L.L~> .J~d!.,'
1.6 1~(FL~2 4c472Ž~I ~x~" (2 , ('/ £ Z ..- ..
E
. I
- 1I I.. ____
AIU
- V4
7-10A U .. 4 8*4 *..
60
- i,2JIPE: ~g?'Al a. _______________________
84 I 2y 4'
I . .
.300
.Zj-7 ~'3 6 ~ ~ I.
xrT X,
7,*(2 X/T* V Z&~ )I/~56 - -.
p J,
e.
U' X/O X//o 1A.*
- . . 6 14,- 4.
A. * .
9
.0*
I -do
i..,
S,,tL g7A IMLI ... W III rZ.. -*,. .
EI T. o . . ...
_ _ _ __Z
.#"i ,
I.
I .4
~ 6 I-___:____
,__od___
g 0
' xx1o X/0-i /0_ _-:
-- /O .. ...-
. . .. * . . S
- **-*-.. *-.-,.--..**. ...-----.5-
.. . 4 I -..
.F
~'1~ __________
l
/7 JL 222~'YZ?)
157 6o tlPLrE
_____ /~J /~Y7, I.
3 I
/0**
I I
Q * .f o.
ql
- 0 8
5: I 7Z2L< -
I
' *. 1. 37 . ,. . ..
6v_ __ _
~tfpLc D,!PRI9' j~z sv/~cb /A~I FE[T, x/9
/0-
. e v
x/o
- K/O
, Ylb.
/0~
Xf(-' X___
2N _
- S - *' .,
0
'.9..
- * *.°
jSAMIL& 4e2~%?7?Ob
- 1
'%._'.-¢., ,lf¢,.
r.--<..( '7.**CE ...#.,x '* '- ,1.
A 1141. 6o S~f(PL ýtYPW AY§I~ F/J 5" Z j
I0 . ' ",,. * .o*¸. .
I. I 2*z, xio3:
- .. <i 7 . . . .
I. -I
- 0
- X/O IX/O Mo...o
'U xiO LE~
xl V fI
' Xk) i Mfr xiT ya-
?vi-"
I. . - - -.
cL..* ".. .".. .
0.
A.." * .... - -. 0i A, , s x U I
- .K~ **~~
". .~r~ D,*PT1/ .7Zoh */& d.
~
- 1*.* .7... -c. . ZL .6.CjA 6, --
I I K - 0
. :0 .* .. . ...
..v * *1
APPENDIX F Supplemental, Environmental Radiation Surveys Earth excavations were dug to the water table during the week of January 8, 1977 in order to obtain additional en-vironmental water samples. While the holes were open, a radiation scan survey was taken in each excavation prior to backfilling.
The following is a list of hole locations where radiation surveys were taken.
- 1. At *the beginning of the access road to the IRL facility used a:- a control background hole.
2, Three (3) feet east of the foundation, opposite the excavation in the TRL facility's east cor-ridor.
- 3. Thirty (30) feet east of the foundation, op-posite the excavation in the IRL facility's east corridor.
- 4. Six (6) feet east of -the waste evaporator building's foundation.
- 5. Thirty (30) feet east of the waste evaporator building's foundation.
- 6. Inlet end of north leaching field.
- 7. Far end of north leaching field.
- 8. Inlet end of south leaching field.
- 9. Far end of south leaching field.
The survey was taken utilizing an Eberline E 120 with HP 190 probe. The survey indicated that the radiation levels were n6odifferent than the levels measured in the control back-ground excavation.
The measured dose rate in the control excavation was 0.03 millirem per hour. Hence, no radiation levels above natural background exist in areas surveyed.
AT.TR
FacilitV "B-Waste" System Piping In order to remove the buried "B-Waste" system piping in the facility, it was necessary to uncover the piping at each pipe junction. Pipe junctions consisted of vertical joiners (clean outs), horizontal junctions (tees), and change in direction (45 0 and 900 elbows). Each buried junction was uncovered by removing the flooring and by excavating the earth down to the piping.
Samples of earth were obtained under each junction and were analyzed for 137Cs and 6 0 Co. A junction was said not to have leaked if the 1 3 7 Cs activity was less than 2 x 10-5 4ci/cc 7
and if the 60Co activity was less than 3 x l0- 5 /,-ci/cc.
The junctions were removed and disposed of as radioactive waste.
The remaining horizontal piping ends were plugged and the pipes were pulled through the earth. The removed piping pulled from the earth was inspected for leaks. No holes in the straight sections of piping were detected. The piping was then disposed of as radioactive waste.
All leaks where failures had occurred were evaluated to deter-mine:
- 1. Manner of failure.
- 2. Variation of activity horizontally and vertically from point of leak.
- 3. Estimated quantity of activity.
- 4. Isotopes present.
ATC(')R
South Corridor Water AnalVsis An attempt was made to establish a well in the excavation in the South corridor. A well point was driven to a depth such that the forty (40) mesh screen was at least twelve (12) inches below the water table. The water table was determined to be at a depth of eleven (11) feet from the floor level.
A Jabsco self-priming pump was attached and sealed to the well point pipe extension at the bottom of the excavation which is ten (10) feet below the floor level. The self-priming pump was unable to lift the water one (1) foot.
The soil in which the well point was placed has a high clay content. It appears that the water cannot run into the point fast enough to allow the self-priming pump to prime itself.
A hole was dug to a depth of twelve (12) feet and it took about one half hour to fill to a depth of one (1) foot.
A stagnant water sample was obtained from the well point. A sample was analyzed by gross beta counting techniques with the result being 7.6 x 10-6,ci/ml as equivalent to Strontium-90.
A portion was analyzed specifically for Strontium-90 and gamma isotopes by an independent laboratory. Table 1 contains results of their analyses.
Table 1 Concentration of Activity for Water at Water Table in South Corridor Excavation Isotope A (/zci/ml)
Mn54 1.59 x 10-7 Co 6 0 5.22 x 10-6 Cs 1 3 7 2.50 x 10-7 Sr 90 7.20 x 10-7 ATCOR
In order to demonstrate the acceptability of these results, the following calculation was made:
Ca + Cb + Cc +
MPCa MPCb MPCc where the MPC is listed in 10 CFR 20, Appendix B, Table II, column 2.
Units are eaci/ml MnS4 Co 6 0 Cs 1 3 7 90 Sr 1.59 x 10-7 + 5.22 x 10-6 + 2.50 x 10-7 + 7.2 x 10-7 1 x 10-4 5 x 10-5 2 x 10-5 3 x 10-7 0.0016 + 0.l1044 + 0.0125 +
- 2.40 = 2.5 In conclusion, it is unlikely that water can be obtained from the south corridor excavation in sufficient quantity to es-tablish a well and if it were,it follows that the concentra-tion of activity in the water would be less than the stagnant water result which is only 2.5 times greater than 10 CFR 20, Appendix B, Table II, Column 2.
ATCOR
`V_
Supplemental. Environmental Water, Surveys Earth excavations were dug to the water table during the week of January 8, 1977 in order to obtain additional sup-plemental water samples. These samples were obtained to further demonstrate that any remaining activity within the ground under the IRL facility does not contribute to radia-tion exposure to individuals.
Environmental water samples were* obtained and reported for the IRL facility. The site well was analyzed for *the limiting isotopes below:
10 CFR 20, Appendix B IsoLope Table Ii, Column 2 IRL Facility Level 9 OSr 3 x 10-7 ,ci/ml 2 x 10-8,U'ci/ml 137Cs 2 x 10-5 /jci/ml 3 x 10-8 .pci/ml 6 OCO 3 x 10-5 zci/ml _ 14 x 10-8 /zci/ml The supplemental samples were taken near areas where activity had been released to the soil. The location of these samples are listed below.
- 1. Three (3) feet east of the foundation opposite the excavation in the IRL facility's east corridor.
- 2. Thirty (30) feet east of the foundation opposite the excavation in the IRL facility's east corridor.
- 3. Six (6) feet east of the waste evaporator building's foundation.
- 4. Thirty (30) feet east of the waste evaporator building's foundation.
- 5. Inlet end of north leaching field.
- 6. Far end of north leaching field.
- 7. Inlet end of south leaching field.
- 8. Far end of south leaching field.
The supplemental water samples were analyzed by evaporating to dryness a known volume and counting remaining activity,
Supplemental, Environmental Water Surveys (continued) by gross beta, as equivalent to Strontium-90. The sample size and counting time were selected such that the minimum detectable activity counted at the ninety percent confidence level was less than the potable water limit for the most 9 0 Sr, whose limit is 3 x 10-7 aci/ml limiting isotope, (9OSr(s).)
The results of all samples were equal to or less than 1.5 x 10- 7 , m!.
ATCOR
APPENDIX G IRL Septic System A description of the IRL facility septic system follows. Lav-atories exist throughout the first floor of the IRL facility and on the operating level mezzanine of the reactor dome. The piping
ýfrom the lavatorics drain by gravity to a central collection tank located beneath the floor of the lower section of the waste process room. The piping for the most part is cast iron and is buried beneath the floors of the facility. A floor drain system exists in the lower section of the waste process room which also drains into this central collection tank. This tank has a float system, two pumps and a blender installed within it. The dis-charge from the pumps goes to a septic tank through cast iron piping. The discharge from the septic tank branches off into two separate leaching fields. Each leaching field is standard.
having a main distribution box and tile latterals.
Radiological surveys taken indicate that no detectable radio-activity exists within the septic system from -the lavatories to the central collection tan]k in the waste process room.
Sections of the cast iron piping that passed through the earth became contaminated when the "B waste" system failed. The pipe was determined to be externally contaminated. These sections were cleaned and surveyed. Results of the surveys indicated that fixed levels of contamination on the pipe exterior read 0.5 millirem per hour and the removable surface contamination was less -than 100 dpm per 100 square centimeters.
Radiological surveys indicated that the radioactivity found within the system entered through the floor drains in the waste process area floor to the central collection tank.
The bulk quantities of activity were removed from the septic system by flushing the floor drains to the central collection tank, removing the sludge from the central collection tank and attempting ATCOR
to remove the adherant material from the tank intervals with a high pressure water spray and removing the sludge from the septic tank. All the material removed from the system was packaged and disposed of as radioactive waste at a licensed waste burial site.
Radiological surveys were taken on the system components after the bulk quantities of radioactivity were removed. The following is a list of residual radiation levels after the sludge removal.
Septic System Radiation level Component Description at'l inch
- 1. Floor drain opening waste, process 0.32 mr/hr floor
- 2. Central Collection Tank
- a. Cover (under side) 0.3 mr/hr
- b. Pumps casing 1.2 mr/hr
- c. Grinder 0.8 mr/hr
- d. Walls of tank (upper) 0. 4 mr/hr
- e. Bottom of tank (general) 1.5 mr/hr
- 3. Cast iron piping to septic tank Checked at two (2) locations between 0.06 mr/hr building and septic tank
- 4. Septic Tank
- a. Upper walls and baffle 0.L4 mr/hr
- b. Bottom of tank and lower tank 0.8 mr/hr walls
- 5. At "Y" junction to leaching field 0.12 mr/hr A sample of the waste was taken from the bottom of the septic tank and was analyzed to identify the isotopes. The following are the isotopes identified above the minimum detectable.
ATCOR
Analysis was performed by Teledyne Isotopes:
Septic Sludge Anasis iscilgm 60Co 4.18 x 103 1 3 7 Cs 5.57 x 102 90Sr 3.2 x 102 It was estimated that the activity remaining in the septic system, excluding the leaching fields, was approximately 0.53 millicuries.
The following is an analysis of the radiological consequences of leaving the septic system "as is."
- 1. Radiation - The ambient radiation in the vicinity of the waste process room is 0.06 millirem per hour.
This is an increase of 0.02 millirem per hour over background. This area is not likely to have an oc-cupancy time of more than eight (8) hours per day, but for this analysis, a twenty-J'our (24) hour oc-cupancy factor was used:
0.02 mrem x 24 hr x 365.25 day = 175.32 millirem hr day year year This is less than that allowable under 10CFR 20.105 (500 millirem per year).
Other portions of the system that have residual con-tamination within do not cause an increase in the natural background greater than for the condition calculated.
.2. Se-ptic System Effusion - Water in the septic tank was analyzed to determine if it could be discharged to the leaching field as the first step in the septic system sludge removal.. A sample was analyzed while the sludge was still in the tank. The results of the analysis indicated the water was below the limits for discharge in accordance with 10 CFR 20, Appendix B, Table II, Column 2. The concentration of activity ATCOR
leaching from the tank's concrete surfaces into
-the water should be lower by an order of magnitude less than when the sludge was in the tank.
- 3. Leaching Field Ground Water - Four (4) samples of water taken at the water table in the septic system leaching field were analyzed by gross beta analysis for the most limiting isotope known to be present
.in the IRL septic waste. The results indicated that the activity was less than 10 CFR 20, Appendix B, Table II, Column 2 limits and were statistically equal to or less than 1.5 x 10-7 a-ci per milliliter.
- 4. Maintenance of Components - The components with the highest contact dose rate are the septic pumps. Their dose rate is 1.2 mr/hr. For the hypothetical condition where a pump bearing is required to be replaced, a repairman will receive the calculated exposures to the whole body and extremities:
Whole Body Calculate the dose of one (1) foot from pump using the inverse square low:
Dl RI = D2 R 2 2 where DI= 1.2 mr/hr RI =3 inches (from center)
R2 =12 inches D2 = 1.2 mr/hr x ( 3inches) 2 12 inches D2 = 0.075 mr/hr Repair would be completed within one (1) week or -the pump would have been replaced.
D = 0.075 mr/hr x 40 hr/week = 3 mrem week This is within limits allowable for unrestricted areas (100 mrem in seven (7) consecutive days.)
Extremity Exposure to the hands (D) is estimated to be:
D = 1.2 mr/hr x 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> = 48 mrem week week ATCOR
The nonoccupational extremity exposure limit should be less than 1/10 the occupational ex-tremity exposure limit. This is (1/10) 18.75 Rem per calendar quarter of a year and is ap-proximately 150 rnrem/week.
- 5. Component Activity - Individual components have re-sidual fixed activity. The removable component which has the highest dose rate is the septic pump.
An estimate of activity for this component, based on Cobalt-60, follows:
D 6 CE where D = dose rate at 1 foot, E = 2.5 Mev, D = 0.075 mr/hr, C = activity in millicuries C 0.075 mci w5 C 5 x 10-3 mci This value exceeds that quantity of Cobalt-60 classified as an exempt quantity (ljci) by a factor of 5, however, it has been shown by pre-vious conservative arguments not to cause ex-posures above allowable limits.
- 6. Leaching Field Activity - The activity contained in the leaching fields is in the order of a few millicuries spread throughout a large volume of earth. The ground water below the. leaching field is within the limits established by regulation and, if the highest con-centration of radioactivity detected in the leaching field soil was to be transferred to an equal volume of water, it too would be within the allowable limits.
The radiation being emitted is also lower than that allowable by the regulations.
- 7. Waste Process Equipment Replacement The central collection tank and the floor drain system in the waste process room are embedded into the floor. This floor level is below the water table.
ATCOR
To remove and replace this system would require depressing the water table and the removal of the floor in order to remove these components. A cost estimate to perform the replacement of this equipment would exceed $75,000.
In conclusion, the equipment, piping, tanks and fields of the IRL septic system function are a valuable asset "as is." Com-ponents have no value when removed from the system. Those components of the system do not constitute a radiological hazard to personnel who might occupy the building, to personnel who are required to make repairs on it, or to the general public.
ATCOR
u m - - -u
.0 *M T
P 0RT 0 F A NA L Y S I S Ru N DA T E 11/18/76 5~TELEDYNE iSOTOPES 07675 WoslNood, Now Jotsey 50 Van Suron Avo.,
TELEDYNE ISOTOPES REPORT OF ANALYSIS RUN DATE 11/18/76 RORK ORDER NUMBER CUSTOMER P-O°. NUMBER DATE RECEIVED DELIVERY DATE PAGE I 3-1982 11/05/76 11/17/76 ATCOR Ir-C PARK MALL PEEKSKILL N Y 10566 LIQUID PADWASTE TELEDYNE COLLECTION-DATE NUCL-UNIT-% MID-COUNT CUSTO11BR'S STA START STOP ACTIVITY ASH-WGHT-W TIfE X UNiB ER IDENTIFICATION NUM DATE TINE DATE TIME NUCLIDE ( uCi/id U/* DATE TIZME VOLUME - UNITS LAB.
29121 H20 WASTE EVAPORATOR 11/OR SR-90 19 -1.1 E-08 11/15 BE-7 L.T. 3. 11/12 L.T. 8. E-07 11/12 MN-Stt L.T. 4. E-08 11/12 L.T. 4.. t-08 11/12 LT. 4. E-08 11/12 L.T. 6. E-07 11/12 RU-- 103 L.T- 4. g-08 11/12 R1U- 106 L.T. 4. E-07 11/12 1-131 L._T. 7. E-08 11/12 CS-134 4.
L.T. B-08 11/12 CS- 137 L.T. 4. E-08 11/12 B*A- 140 L.T 1. t-07 11/12 CE- il4 1 L.T. 5. E-07 11/12 L.T. 2. E-07 11/12 RA-226 L.T. 6. E-07 11/12 Tli-228 L.T. 5. E-08 11/12 29122 F120 SUB CELL (S.CORR) 11/O0 53-90 L.T. 2. 11/15 E-08 BE-7 L. T. 3. E-07 1-1/14 K-40 L.T. 6. 11/14 t-07 MC-54 L.Tý 3. E-08 11/14
,~
CO-60 L.T. 2. 11/14 L.T. 3. g-08 11/14 ZR-95 L.T. 5. 1-08 11/14 PU- 103 L.T. 3. E-03 11/14 RU-106 L.T. 2. E-07 11/14 1-131 .- T. 7. E-08 11/14 CS-134 L.T. 3. F-08 11/14 CS-137 7.64+-2.9 5E-08 11/14 DA-1140 L.T. I. E-07 11/14 CE-141 LoT. 6. E-08 11/14
- - ~
TELEDYNE ISOTOPES REPORT OF ANALYSIS RUN DATE 11/18/76 ORIk ORDER NUMBER CUSTOMER P.O, NUMBER DATE RECEIVED DELIVERY DATE PAGE '2 3-1982 11/05/76 11/17/76 I
ATCOR INC PARK MALL PEE'KSKILL N 10566 LIQUID RADWASTE TELEDYNE COLLECTION-DATE NUCL-UNIT-% MIID-COU NT SMZLE CUSTOMER'S STA START STOP ACTIVITY ASi-WGBT-%
- TIME NUMBER IDENTIFICATION NUN DATE TIME DATE TIME NUCLIDE ( uCi/nl ) U/p
- DATE TIME VOLUME - UNITS LAB.
29122 H20 SUB CELL(S.CORR) 11/Oa -11 L.T, 2. E-07 11/14 4 RA-226 L.T. 5, E-07 11/14 4 TH-228 L.T. 5,. E-08. 1 1/14 4
T - m -SOO-Sm " -m P*M S.17EDYN 150TOPS REPORT OF ANALYSIS RUN DATE 11/18/76 WORN ORDER NbMBER CUSTOMER P..OO fNUrBER DATE RECEIVED DEtIVERY DATE PAGE 3 3-1982 11/05/76 11/17/76 ATCOR INC PA RK MALL PEEKSKILL N Y 10566 SOiL TEL EDYNig COLLECTION-DATE NUCL-UlIT-% MID-COUNT SAMPLE CUSTOMER'S STA START STOP ACTIVITI .. ASH-WGHT-3
- TIME NUMB ER IDENTIFICATION NUM DATE TIME DATE TIME NUCLIDE (pCi/gm DRY) U/M
- DATE TIME VOLUNE - UNITS LAB.
29123 S WASTE EVAPORATOR 11/oR SR-90 1.5 %-0,2 -OrG uCi/gm DRY 4* 11/15 3 BE-7 L.T. 1. E-06 uCi/qm DRY *4 11/12 4 K-4ý0 6. 6+--0. 86E-06 uCi/gm DRY *4 11/12 4 MIN-5 4 L.T. 9. 3-03 uCi/gm DRY *4 11/12 4 CO-SR L.T. 1. E-07 uCi/gm DRY *4 11/12 4
/ Co-6O ZR-OS
- 7. 56+-0o 761- 0,5 UCi / (m L.T.
L.T.
2-E-07 uCi/qm E-07 DRY DRY
- 4 44 11/12 11/12 4
4 FU-103 uCi/gm DRY 4* 11/ 12 4 RU-106 L.T. 1. E-06 DRY *4 11/12 1-131 L.T. 3. E-07 u Ci /g m DRY 4* 11/12 *4 3.22+-0. 32E-06 kU uCi/gm C i/9 m uCiigm DRY *4 11/12 t4 E4 CS- 137 3.14U+-0.31E-05 DRY 4* 1/12 u B A- 1140 L.T, 5. E-07 uci/gn DRY *4 11/12 4 L.Tý 2. *E-07 CC- 141 uuCi/gm Ci / m DRY ** 11/12 4 L.T. 6- S-07 uCi/gm DRY 4* 11/ 12 4 RA-226 L.T_ 2. E-06 uC i/g m DRY *4 11/12 4 TU-228 2.79+-O.38E-07 DRY 4* 11/12 4 ZN-O5 3. 174-I.93E-07 uCi/gm DRY 4* 11/12 4 S HIGH LEVEL L.C.R I/OR 5.0 +-0. 1 E-05 uCi/gm DRY *4 11/15 3 BF- 7 L.T. 5. E-06 uni/gm DRY *4 11/12 4 1.13+-0' 1E-05 uCi/gm DRY *4 11/12 MN- 5 2.0+-0.2413-05 uCi/gm DRY 4* 11/12 CO-sa L.T. 5. S- 07 uCi/gm DRY *4 11/12 44 1.36* 0O 1. 0 4 lci/gm DRY 4* 11/12 4 ZR-O0 LT. 5T . E-07 uCi/9m DRY ** 11/12 4 RU- 103 DRY *4 11/12 RU-i106 L.T . t-06'.ui/gl DRY 4* 11/12 4 1-13 1 L.T. q. ,C 07. uCi/gm DRY *4 11/12 4
1.21+-0o1-8-05 ".Ci/gm CS- 134 *4 11/12 3.81*-0 3*ECO04 :uCi/gm DRY 4 CS- 137 DRY 4* 11/12 L.T. 2. *-06 uCi/gm DRY 4* 11/12 CE-141 L.T. 5. [-07 uCi/gm DRY 4* 11/12 ;4
-- -m - m -- -m m-m-,nm - - - - F TELEDYNE ISOTOPES REPORT OF ANALYSIS RUN DATE 11/18/76 WORK ORDER NUMBER. CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 4 3-1982 11/05/76 11/17/76 ATCOR INC PARK MALL 2EEKSKILL N Y 10566 S 0 L T ELELDYNE COLLECTION-DATE NUCL-UNiT-% MID-COUNT SA;ýPLZ CUSTOMER'S STA START STOP ACTIVITY AlSH-WGRT-% TIME INUMBER IDENTIFICATION NUM DATE TIME DATE TIME NUC LID Z (pCiigm DRY) U/M ** DATE TIME VOLUME - UNITS LAB.
29124 S HIGH LEVEL L.C.R 1 1/OR CE- 14 4 L.T. 2. E-06 uCi/gm DRY 11/12 14 RA-226 L.T. 5, E-06 uCi/gn DRY 11/12 14 TH-228 L. T, 5, E-07 uCi;/g~a DRY 11/12 14 z (a5 1. U3+-00, 148-05 uci/gm DRY 11/12 14
.29125 S SOUTH CORR. 11/OR SR-90 1.5 +-0o1 E-04 ICi/rgm DRY ** 11/15 3 BE-7 L.T. 1. E-05 uci/gm DRY 11/12 .4 K-140 1. 20+-0.12E-05 DRY ** 11/12 14 N -5 4 6.79-'-0.68E-05 uCi/gm DRY *4 11/ 2 4 CO-53 L. T. 6. E-07 DRY ** 11/12 14 CO-rO 4. 65*-U. 1478-014 DRY *4 11/12 ZR-95 T.-T. !1 E-06 DRY *4 11/12 L. T 1 E-06 llci/gm RU-103 L.T, 71 E-06 uCi/g,, DRY 44 11/12 14 10' ~ RU- 106 1-i131 L.T. 2. 8-06 uCi/gm uli /g T DRY DRY
- 4
- 4 11/12 11/12 4
14 14 CS-i 34 3.14 9+-0.358-014 DRY ** 11/12 CS- 137 2.36+-0.21E-03 u Ci/g m DRY ** 11/12 BA- 1iO L.T. 3. E-06 DRY 4* 11/12 14 14 SCE- 1 1 L.T. 0. E-07 uC i/g,- DRY 4* 11/12 CE- 11414. L.T. 3. E-06 ,dCi/gm DRY ** 11/12 PA-226 L.T. 8. E-06 uCi/gm DRY *4 11/12 TH-228 L.T. 8. E-07 uCi/gm DRY 4* 11/12 1, ZN-OS5 2. 5G+-0.26E-014 uci/gm DRY ** 11/12 EU- 15 4 11/12 14 7.25+-0.99E-06 DRY **
14 uci/(]M 14 29126 S EAST CORR. 11/OR SR-90 5.5 +-0,, E-05 *4 uCi/gm DRY 11/16 14 BE-7 L.T. 6. E-06 DRY ** 11/12
-K-40 1.15+-0. 114E-05 uCi/gm DRY ** 11/12 N
MN-S51 14 1.1&G-0.12E-05 uC i./gm DRY *4 11/12 L.T. 6. E-07 uCi/gn DRY ** 11/12 14 CO-G0 1. 96+-0. 20E-04 uCi/gz1 DRY *4 11/12 ZR-95 L.Tý 1. E-06 uCi/gm DRY *4 11/12 R U-1.03 L.T- 7. E-07 DRY *4 11/12
- - - - - - - ~ - - - - - -
J TELEDYNE ISOTOPES U REPORT OF ANALYSIS RUN DATE 11/18/76 WORK ORDER NUMBER CUSTOMER P.O. ItNYBER DATE RECEIVED DELIVERY DATE PAGE 5 3-1982 11/05/76 11-/17/76 ATCOR *iC PARK NALL "PEýKSXILL N Y 10566 SOiL TtLEDYV2 COLLECTION-DATE NUCL-UNIT-% MID-COUNT E
_S CUSTOMERI S STA START STOP ACTIVITY N UNER IDENTIFICATION NUM DATE TIME DATE TIME ASR-WGHT-%
NUCL ID E (pCi/q* DRY) DATE TIME VOLUME - UNITS LAB.
S EAST CORR. 11/OR RU- 106 L.T. 5. F-05 uCi/jn DRY i- 11/12 1-131 L.T. I. E-06 uCi/gm DRY
- 11/12 4 CS- 134 8.99+-0.901-05 uCi/ 9 m DRY 4v 11/12 CS- 137 3.53+-0.36E-04 uCig/qn DRY
- 11/12 4 DA- 140 L.T- 2. -ý-06 uCi/gm DRY 1 1/12 44 CE.- lA 1 44 L.T. 5. F-- 07 uCi/gn DRY 4*
1/12 44 CE-14q4 L.T. 2. E-05 uCi/gmn DRY 1/12 4
- 4 PA- 22 6 L.T. 6. E-06 DRY 1 1/12 44 TH- 228 L..T. 5,, F-07 uCi/gr, DRY 1 1/112 4
- 29127 S DECONTAn PAN 11VOR 2.1 +-0.1 E-05 uCi/g0iT DRY 4* 111/
111r2 3 BE-7 L.T. ". E-06 uCi/ DRY 4* 11/12 K-4O uCi/g 0 4f 4 1.00+-0. 10:-05 DR'Z 11/12 44 L.T. 3. 1-07 uCi/gm DRY 11/12 4 4*
L.T. 3. U-07 uCi/gjm DRY 11/12 4
- 4 7.344-0.731-05 uCi/gn, DRY 11/12 4 44 4 L.T. 4. E-07 uCi/5* DRY 11/12 4
(~4~44~ *4 R U-103 L.Tý 2. E-07 uCi/gm DRY 11/12 L.T, uCi/lrn DRY 4* 4 RU- i b5 2. B-06 11/12 1-131 L.T. 3. E-07 uCi/qm DRY 44 4
- 4 11/12 4 CS- 134 1.22+-0.28E-06 uCi/g* DP.Y 11/12
- 4 4 CS-137 1.39+-0.14E-06 u Cilgq m DRY 11/12 44 BA-140 L.T. 7. E-07 uCi/g1m DRY 11/12 4*
L.T. 1. E-07 uCi/grn DRY 1.1/12 4 CE- 144 L,*T, 5. Z-07 uCi/gm~ DRY 11/12 4*
RA-226 L.T. %. B-06 uCi/gm u Ci /gp DRY 11/12 4 DRY *4 TH-228 2.70+-O.30E-07 4* 11/12 14
- -n m -n ra m mISTO - m-unun m m TEEDNEISOTOPES REPORT OF ANALYSIS RUN DATE 11/18/76 WORK ORDER NUMBER CUSTOMER P.O. NUMBER DATE RECEIVED DELIVERY DATE PAGE 6 3-1982 11/05/76 11/17/76 ATCOR INC !
PARK IALL PEKSKILL R Y 10566
.WATER - C~N TELEDYNE COLLECTION-DATE NUCL-UNIT-% MID-COUNT SAMPLE CUSTOMBRfS STA START STOP ACTIVITY ASH- WGNT-_% TIME
- NUMBER u/1, DATE ThiS VOLUtiE - UNITS LAB.
IDENTIFICATION NUA DATE TIME DATE TIME NUCLIDE i*'
29120 H20 SITE WELL 11/OR SR-90 I.T. 2. B 01 11/15 3 BE-7 L.*T 3. E 02 11/12 4 K-40 L.T,. 8 Z 02 11/12 4
-. ý 3. E 01 11/12 4 C0-58 L.T. 3. t 01 11/12 C0-S0 L.Tý 4. E 01 11/12 4
'4 ZF-95 L.T . 6. 2 01 11/12 4 RU- 103 L.T. 3. E 01 11/12 4
RU-106 L.T. 3ý F 02 11/12 4
1-131 L.T. 7., E 01 11/12 CS- 134 L.T. o4. E 01 11/12 4 CS-137 L._T 3. E 01 11/12 4 L.T. I. E 02 11/12 14 C7A- 141 7. E 01 11/12 4 L.T-CE-144 L.T. 3. E 02 11/12. 4 RA-226 'LT. 7. E 02 11/12 4 TH-228 L.T, 6.2 01 11/12 LAST PAGE 07 REPORT APPROVED BY K. ROACH 11/18/76 SEND 1 COPIES TO ATIOOS 2 - GAS LAB. 3 - RADIO CUEEISTRY LAB. 4- Ge(Li;) G*'bMA SPEC ZB S - TRITIUM GAS/L.S. LAB.
AL Piping Runs - Reactor Pool to Valve Pit The reactor exit and return lines from the reactor pool's stall end and core position two ends were mechanically and chemically decontaminated.
The chemical decontamination and rinse cleanings removed the contaminated aluminum oxide film, but failed to remove the con-crete fines which entered the piping from the pool demolishment operations. These fines were determined to contain high con-centrations of insoluble Cobalt-60.
To remove the contaminated fines, various techniques were applied.
The technique used which proved most successful was the pulling of a weighted mesh of screen with cloth wipes attached to give the screen substance and -to push along or wipe up the contami-nated fines. The high density and the size of the fines made it necessary to repeat the cleaning process many times until the pipe was visually clean.
The rags were washed out or replaced after each pass through the piping. The radiation readings on the rags were not documented during the cleaning. Instructions to the supervisor from radia-tion protection requested that the cloth wipes be replaced if workers measured an instrument response of more than 1 mr/hr, using an Eberline E 530 with a side window HP 177 probe. The cloth wipes used in the procedure were replaced because it was felt that clean wipes would remove more dirt per pass than used wipes. The wipes never reached the IRL radiation replacement limit. The foreman stated that the rag-screen bundle had only fractional mr/hr readings on the initial passes through the pipes.
The following is an estimate of the activity in a bundle of rags whose dose rate is 1/2 mr/hr:
ATCOR
- 1. Diameter of sphere of rags = 14 inches.
- 2. Beta c6ntribution to measurement = 80%.
- 3. Gamma measurement = (.2) (0.5 mr/hr).
- 4. Assume activity = Co 6 0 activity and surface Gamma source geometry.
- 5. Dose to flux = 450 ph / mr/hr.
0z3 SA 7cm sec SA = 2/3 0 S = 2/3 0 A = 2/3 ) 4 r R2 S = 2 x 4 -T (7 in) 2 x (2.54 cm) 2 x 45 ph x d x 60 sec 3 in cmsec 2ph min S 43.57 x 106 dpm Area of pipe for a typical pipe run A =i-rD'L average length = 80 feet diameter = 14 inches A = -rf14 in. x 2.54 cm x 80 ft. x 12 in. x 2.54L cm in ft in 2
A = 2.72 x 105 cm An estimate of the loose surface contamination levels in pipe as measured from thie cloth wipes follows:
SA 4 S (dpm)
A (number of 100 cm2 areas in pipe) 2 SA <1.31 x.10 3 dpm/100 cm The level of contaminant on the bundle indicated that the surface contamination in the pipes were initially near the limit. It was also known that the majority of the activity was contained in the fines. It is estimated that about twenty-five (25) passes were required to clean the concrete fines from the pipes.
Smear surveys were taken in the pipes after cleaning and the highest result noted was 200 dpm/100 cm 2 which is a factor of 5 below the release limit.
ATCOR
- ° -. ATCOR TO: IRL Safeguard Committee -
FROM: R. G. Levesqu,"e
SUBJECT:
Reactor Pool L utteDrain DATE: August 9, 1976 A°IX'01, Inc. attmiptcd to chemically remove residual activity found in the low gutter drains of the Reactor Pool. The drains had a film which appeared to be of an oxidized oil. The film had detectable surface contamination by smear of 2,500 dpm/100 cm2 .
The technique selected for decontamination was to flood the system and add KOI-I to emulsify the organic film letting the caustic work over night. A plug was installed in the aluminum piping in the valve pit and approximately 150 gallons were placed into the drains along with industrial caustic. The level appeared to hold even at the bottom of the gutter drain cups. Sometime during the night the cleaning solution was lost from the system. Only one and a half gallons of cleaning solution were recovered the following morning.
Visual inspection of the pool and valve pit did not reveal the disposition of the cleaning solution.
Based on the volume recovered from the system, the leak had to be near or at the lower horizontal run at the embedded header.
Possible causes for the system failure:
. 1. When caustic was added to the four gutter drains it is possible that some caustic settled to the bottom header. The caustic concentration at this point and aided by the heat of ionization could have caused the piping to corrode and fail.
- 2. The header could have been ruptured during the pool blasting efforts.
- 3. The leak could have existed during the periods when IRL had been operating the plant and caused to increase due to reasons 1 and/or 2 above.
Uj A leak for this system at the rate estimated could account for 30,000 gallons/yr. (A postulated annual water loss from the Reactor Pool during plant operations).
To determine if the leak had caused a build up of activity under the biological shield, a hole was drilled east of the biological shield through the trench bottom and earth was sampled down to-the water table. Results of the sampling program did not indicate any radioactivity above background at the sample point. (See diagram attached for location of sample point).
It is my opinion that if any quantity of activity had leaked along the header that some build up would be detect-able at the sample point, Therefore, only insignificant quantities if any were released..
- N. I TRUCK
,S",<ENTRANCE NEUTRON FLIGHT.
PATH PENETRATION T H NL. ..
51 11 '
- ND PLUG A
STORAG3E FaCILITY ,5/1 r POOL OeI VALVE IPOOL 02 GAMMA
~~CHAMBER].
- ~ VENTI LATION
- VEARLAGO RADIATION PERSONNEL AIRLOCK MONITORING I-.ONITORING AIRLOCK STATION STATION CLOTHING LOCKERS a 1' SHOWER AREA*
TO HOT CELLS TO OFFICES
- AND LABS REACTOR BUILDING-GROUND FLOOR PLAN I.°
TO: R. Canfield DATE: 10/8/74
- D. Leigh
./M. Shymlock Isff FROM: L. Thelin
SUBJECT:
Consequences of Leaks in the Reactor Primary System during Normal Operation
.. The Hazards Summary indicates. that ground water migra-tion during surmner months is virtually nonexistant. In winter, water released instantaneously in a large amount-would travel approximately ten.feet per day. For the type of geology that we have on site, this expansion would take the form-of an expanding cylinder.- For smaller release I rates (up to 37 gallons per minute) the expansion rate would be slightly less. The report indicates that 24 days would be required for water leaking at. this rate to get to the nearest stream - approx. 200 feet..
- 3. For normal operation of the reactor, the following con-centrations have been found typically in pool water which has been allowed to undergo radiological decay for a period of 25 days.
124 -6 Sb < 3 x10 uCi/ml
ýCs 1 I < 1.5 x 10-6 uCi/ml
- 60. -7
.. o....
6 < 9.0 x 10 uCi/ml 3 Inall cases these values are less than 1/6 of the allowable environmental discharge limits. We can also reasonably suppose that these concentrations would be diluted in ground water by a factor of at least one-hundred before reaching the nearest stream. Further dilution would be afforded by the stream before any leakage water could be transported off site.
The obvious conclusion is that gross quantities of water could leak from the primary system without causing excessive concentrations in off site areas. In actuality, a simple calculation indicates that the greatest leak rate possible is I 0.1 gallons/minute - assuming that all of the 60,000 gallons of makeup water lost each year is caused by leaks in the
- ] primary system.
I I
I 1I APPENDIX H I'
I I
I I
I I
I I
I I
I I
I
N Isotopic Analysis of the Surface Contaminant IRL records do not give reasons to suspect that alpha emitting isotopes or Strontium-90 were a part of surface contamination found within the facility.
Large surface areas were wiped where surface contamination was known to be present. These wipes were burnt and the ashes were analyzed to determine the percentage of individual isotopes in the contaminant. Table 1 is the calculate percentages from Teledyne Isotope analysis.
Table 1 Isotope Percentages in IRL Surface Contaminants 0
00 o'o 6/00 o*0 00 0 1ý0 0'
00 1110 4;y ev 0Z 0 el A,0 Isotope Percentage of Total (%)
Mn54 1.2 40.1 40.1 40.1 6 0 Co 68.5 5.9 60.9 42.8 1 3 7 93.8 37.6 40.1 Cs 13.7 Agll 0 m 16.2 <0.1 *0.i 57.0 Sr 9 0 0.3 0.3 1.5 _ _0.I ATCOR
APPENDIX I Discussion of ALARA
- 10. Radioactivity remaining at the facility may pose some small though measurable risk from internal and external sources.
Radioactivity of greatest concern has been that resulting from the release of radioactivity from the B waste system in the south corridor. Considerable work and expenditures have reduced the risk to acceptable levels. Present internal radiation risks have been documented in answer to question 1.
External radiation risks after back-filling the excavation are documented in Appendix B. The maximum initial radiation levels at the point of release of activity into soil was 1000 MR/HR.
It has been estimated that radiation workers who removed the bulk of this radioactivity received a total dose of 0.8 person rem. Total costs for this effect was $125,000. If the radio-activity had not been removed and the building had been used with the floor in place, the number of person rem due to external exposure would have been essentially 0 (i.e., the external radiation at contact of the floor was approximately 0.2 MR/HR above background). To remove the radioactivity remaining in the excavation, estimated to be 60 mCi, would require razing of 1/3 of the existing building valued at $660,000. The cost of this additional work would require an expenditure of $310,000 yielding a total cost of $970,000. The saving in exposure of individuals or population groups would be essential zero (as noted in the references cited above). The additional exposure of workers to remove the remaining radioactivity would-be about 0.1 person-rem.
0 APPENDIX J
Radioactive Waste Tanks Leach Test The following listed tanks had, at one time, contained radioactive liquids. After the contents of these tanks were removed, processed and disposed of as radioactive waste, the internal surfaces were determined to contain residual fixed activity above the release limits.
- 1. Pump room sump.
- 2. Hold up tank.
- 3. Storage tank.
In order to reduce to surface contamination on the internals of the tanks to within the guideline limitations, it was necessary to physically remove portions of cement surfaces where the protective tank coating had failed. Some disper-sion of low level activity into the cement was noted.
In order to determine whether this contaminant could leach from these surfaces and contaminate water, collected in these tanks, a leach test was conducted. In each tank, ground water had entered and been stored for the period October, 1976 to January, 1977. It was felt that this period would be of suf-ficient length for leach testing.
Samples were collected from each tank and.were analyzed by evaporating to dryness a known volume and counting by gross beta, as equivalent to Strontium-90. The sample size and counting time were selected such that -the minimum detectable activity counted at the ninety percent confidence level was less than the potable water limit for the most limiting 9 0 ( 90 Sr(s).)
isotope, Sr, whose limit is 3 x 10-7/aci/ml The results of the leach test samples were equal to or less 7
than 1.5 x l0- "-ci/ml.
ATrFR