ML20203A115
| ML20203A115 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 12/31/1985 |
| From: | Johari Moore, Tuttle R ROCKWELL INTERNATIONAL CORP. |
| To: | |
| Shared Package | |
| ML20203A095 | List: |
| References | |
| RI-RD86-140, NUDOCS 8604160230 | |
| Download: ML20203A115 (78) | |
Text
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Rl/RD86-140 4
ROCKETDYNE DIVISION ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT DE SOTO AND SANTA SUSANA FIELD LABORATORIES SITES 1985 e
RockwellInternational Rocke' dyne Division 6633 Canoga Avenue Canoga Park. CA, U.S.A. 91303 8604160230 860408 PDR ADOCK 07000025 C
Rl/RD86-140 v
l ROCKETDYNE DIVISION ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT DE SOTO AND SANTA SUSANA FIELD LABORATORIES SITES 1985 By J. D. Moore APPROVED:
Lt Q
R. J7TUTTLE Manager Radiation and Nuclear Safety Rockwellinternational nocheidyne civision Sano$a'"pa$ ce*iEfo n a 91303 ISSUED: APRIL 1986
CONTENTS I
Page I.
I n t ro d u c ti o n......................................................
1 II. Summary and Evaluation of Environmental Monitoring Results........
11 III.
Envi ro nmental Moni tori ng Resul ts..................................
15 A.
Radi oac ti ve Materi al s--1985...................................
15 B.
Nonradioacti ve Materi al s--1985................................
27 IV.
Environmental Monitoring Program..................................
29 A.
De sc r i p ti o n...................................................
29 B.
Sampl i ng a nd Sampl e P reparati on...............................
29
- 1. So11......................................................
29 2.
Vegetation................................................
37
- 3. Water.....................................................
38 4.
Ambient Air...............................................
38 C.
Counti ng and Cal i brati on......................................
40 D.
Nonradi oacti ve Materi al s......................................
42 V.
Ef fl uent Moni tori ng P rogram.......................................
45 A.
Treatment and Handlir.g........................................
45 B.
Faci l i ty De sc ri pti on s.........................................
47 1.
De Soto Site..............................................
47 2.
Santa Susana Field Laboratories Site......................
47 C.
Estimation of General Population Dose Attributable to Nucl e ar Ope rati o ns--1985......................................
48 Appendices A.
Comparison of Environmental Radioactivit Wi th Previous Years.....................y Da ta for 1985 57 B.
Envi ronmental Moni toring Program Qual i ty Control..................
65 C.
California Regional Water Quality Control Board Criteria for Discharging Nonradioactive Constituents from Roc k e tdy ne D i v i si o n, SSFL.........................................
67 0.
References........................................................
69 E.
Ex te rn a l D i s t ri b u ti o n.............................................
71 r
l F.
Al ternati ve Uni ts for Radiol ogical Data...........................
73 RI/RD86-140 111
1 TABLES Page 1.
Soil Pl utoni um Radioactivi ty Data--1985...........................
16 2.
- So f i Radi oac ti vi ty Da ta--1985.....................................
18 3.
Vegetation Radioacti vi ty Data--1985...............................
18 4.
Supply Water Radioacti vi ty Data--1985.............................
20 5.
Bell Creek and Retention Pond Radioactivf ty Data--1985............
22 6.
Ambi ent Ai r Ra di oac ti vi ty Da ta--1985..............................
24 7.
De Soto and SSFL Sites--Ambient Radiation Dosimetry Data--1985....
25 8.
De Soto and SSFL--State of Califortifia Ambient Radiation Do s i me t ry Da tsi 198 5..............................................
27 9.
Nonradioactive Constituents in Wastewater Discharged to Unrestricted Areas--198d..........................................
28 10.
Sampl i ng Location Description.....................................
33 11.
Mi nimuin Radi oacti vi ty Detection Level s (MDLs ).....................
41 12.
Atmospheric Emi ssions to Unrestricted Area s--1985.................
46 13.
Maximum Downwind Plume Centerline Concentrations of Atmosp heri c Emi s si ons--1985.......................................
53 14.
Exposure to the Public in the Vicinit Facil i ties--1985.....................y of Rocketdyne 54 15.
Population Dose Estimates for Atmospheric Emissions from SSFL Fac i l i ti e s--1985.............................................
56 FIGURES 1.
Rocketdyne Di vi si on--De Soto Si te.................................
3 2.
Rocketdyne Division--Santa Susana Field Laboratories Site.........
4 3.
Map of Santa Susana Field Laboratories Site Facilities............
5 4.
Map of General Los Angeles Area...................................
7 l
S.
Map of Canoga Park, Simi Valley, Agoura, and Calabasas
)
S amp l i n g S ta ti o n s.................................................
30 6.
Map of De Soto Si te and Vicinity Sampling Stations................
31 7.
Map of Santa Susana Field Laboratories Site Sampling Stations.....
32 l
RI/RD86-140 iy l
i i
FIGURES Page 8.
Weekly, Monthly, and Annual Averaged Long-Lived Airborne Radioactivity at the De Soto and Santa Susana Field La bora tori e s si te s--198 5..........................................
39 9.
Santa Susana Field Laboratories Site-Centered Demography to 8 km Distance.....................................................
50 10.
Santa Susana Field Laboratories Site-Centered Demography to 16 km Distance....................................................
51 11.
Santa Susana Field Laboratories Site-Centered Demography to 80 km Distance....................................................
52
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RI/RD86-140 v
I.
INTRODUCTION In a Rockwell International Corporation organizational realignment, ef-fective on 1 October 1984, the Energy Systems Group was merged with Rocketdyne Division and is no longer a separate organization. Annual reports will here-after reflect this change.
Environmental and facility effluent radioactivity monitoring at the Rocketdyne Division of Rockwell International (California operations) is per-formed by the Radiation and Nuclear Safety Group of the Health, Safety, and Environment Department.
Soil, vegetation, and surface water are routinely sampled to a distance of 10 miles from Division sites.
Ground water from site supply water wells and other test wells is periodically sampled to measure radioactivity in these waters.
Continuous ambient air sampling and direct radiation monitoring by thermoluminescent dosimetry are performed at several on-site and off-site locations for measuring airborne radioactivity concentra-tions and site ambient radiation levels.
Radioactivity in emissions dis-charged to the atmosphere from nuclear facilities is continuously sampled and monitored to ensure that amounts released to unrestricted areas are below appropriate limits and to identify processes that may require additional engineering safeguards to minimize radioactivity in such discharges.
In addi-tion, selected nonradioactive chemical constituent concentrations in surface water discnarged to unrestricted areas are detenained.
i l
l The environmental radioactivity reported herein is attributed to natural sources and to residual fallout of radioactive material from past atmospheric testing of nuclear devices.
Work in nuclear energy research and development in.what has become the Rocketdyne Division of Rockwell International Corporation began in 1946.
Rocketdyne is currently working on the design, development, fabrication, and I
testing of components and systems for central station power plants, on the l
R7 /RD86-140 1
decladding of irradiated nuclear fuel, and on the decontamination and disposi-tion (080) of facilities program in addition to a broad spectrum of conven-tional programs in rocket propulsion, utilization of space, and national defense.
The administrative and scientific research facilities associated with these efforts are located at several major facilities in Canoga Park, California, including the De Soto site, (Figure 1), approximately 23 miles northwest of downtown Los Angeles and in the Simi Hills.
The De Soto site is typical of the San Fernando Valley floor, at an altitude of 875 ft above sea level.
Several nuclear research programs, licensed by the State of Cali-fornia, are conducted here.
These include Building 104 analytical chemistry and applied nuciaar research laboratories and the Gamma Irradiation Facility 60 containing approximately 35 kCi of Co.
Tne 290-acre Santa Susana Field Laboratories (SSFL) site (Figure 2) is located in the Simi Hills of Ventura County, approximately 30 miles northwest of downtown Los Angeles. The SSFL site, situated in rugged terrain typical of mountain areas of recent geological age, is underlain by a sandstone bedrock
,I unit called the upper cretaceous Chatsworth formation.
The site may be de-scribed as an irregular plateau sprinkled with outcroppings above the more level patches and with peripheral eroded ravines.
Elevations of the site vary from 1650 to 2250 ft above sea level.
The surface mantle consists of uncon-solidated gravel, sand, silt, and clay.
Both Department of Energy (D0E) and Rockwell International owned facilities, shown in Figure 3, share the Area IV portion of this site. The SSFL site also contains facilities in which nuclear operations licensed by the U.S. Nuclear Regulatory Commission and the State are conducted.
The licensed facilities include (1) the Rockwell Interna-tional Hot Laboratory (RIHL) (Building 020), (2) the Nuclear Materials Devel-opment Facility (NMDF) (Building 055), (3) a former neutron radiography facil-ity containing the defueled L-85 nuclear examination and research reactor (Building 093), (4) several X-ray and radioisotope industrial radiography in-spection facilities, and (5) a nuclear instrument calibration laboratory.
RI/RD86-140 2
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Map of Santa Susana Field Laboratories Site Facilities
The location of these sites in relation to nearby communities is shown in
.i Figure 4.
Much of the land surrounding the De Soto s te is used for light industry and other commercial uses and for residential apartments and single-family dwellings. Most of the land surrounding the SSFL site is barren, with some minor cattle grazing on the southern portion and some orchard farming at the eastern boundary.
At greater distances, residences and some light indus-tries become prevalent.
Within 30 km of the SSFL site, there is no signifi-cant agricultural lano use and, except for the Pacific Ocean about 20 km south, there is no significant body of water reserved for recreational use.
There are four major reservoirs within 50 km of the site, which provide domestic water to the greater Los Angeles area. The nearest of these is more than 16 km distant.
Included within the SSFL site is a6 82-acre government-optioned area where DOE contract activities are conducted, primarily by the nonnuclear Ener-gy Technology Engineering Center (ETEC).
The major operational nuclear in-stallation within the DOE-optioned area is the Radioactive Material Disposal Facility (RMGF). This facility is used for storage of irradiated fuel and for packaging radioactive wastes generated as a result of the D&D program and fuel decladding operations.
Several deactivated nuclear reactor and support facilities, all within the optioned area, are affected by the D&D program.
Licensed programs conducted during 1985 included (1) the operation of the RIHL for nuclear reactor fuel decladding and reactor system component examination and the fabrication of sealed radiation sources and (2) the dis-mantling of the previously defueled L-85 nuclear examination and research reactor.
The basic policy for the control of radiological and chemical hazards requires that, through engineering controls, adequate containment of such materials be provided and that, through rigid operational controls, facility effluent releases and external radiation levels be reduced to a minimum.
The environmental monitoring program provides a measure of the effectiveness of RI/RD86-140
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Map of General Los Angeles Area RI/RD86-140 7
l safety procedures and of the engineering safeguards incorporated into facility designs. Specific radionuclides in facility effluent or environmental samples are not routinely identified because of the extremely low radioactivity levels I
normally detected, but they would be identified by analytical or radiochemis-try techniques if significantly increased radioactivity levels were observed.
Relatively few different radionuclides are involved in these operations.
Occasional gama-spectral analyses of bulk samples such as soil, water, and air confirm that the major radionuclides present are those of the natural-ly occurring thorium and uranium decay chains, plus other natural radionu-40 7
clides such.as the primurdial X, and Be, produced by cosmic ray inter-actions in the atmosphere.
In addition to environmental monitoring, work area air and atmospheric emissions are continuously monitored or sampled, as appropriate.
This pro-vides a direct measure of tne effectiver.ess of engineering controls and allows remedial action to be taken Defore a 'significant release of hazardous material con occur.
Environmental sampling stations located within the boundaries of the De Soto and SSFL sites are referred to as "on-site" stations; those located out-side these boundaries, or rElatiVely distant from any nuclear facilities, are referred to as "off-site" stations.
The De Soto and SSFL sites are sampled montnly to determirA the concentration of ' radioactivity in typical surface soil, native vegetation, and water. Soil is sampled on-site (SSFL) and off-site semiannually for plutonium analysis.
Similar off-site environmental sam-ples, except for plutonium anh1/ sis, are obtained quarterly.
Continuous ambi-ent air sampling provides information concerning long-lived airborne particu-late radioactivity. On-site ambient radiation monitoring using thermolumines-cent dosimetry (TLD) measures environmental radiation levels at the De Soto and SSFL sites and also at several off-site locations.
RI/RD86-140 8
Nonradioactive wastes discnarged to unrestricted areas are limited to liquids released to sanitary sewage systems and to surface water drainage sys-tems.
No intentional releases of any liquid pollutants are made to unre-stricted areas. Sanitary sewage from all DOE and Rocketdyne facilities at the SSFL site is treated at an on-site sewage plant.
The plant outfall drains into retention pond R-2A, located toward the southern portion of SSFL.
The surface water drainage system of SSFL, which is composed of catch ponds and open drainage ditches, also drains to retention pond R-2A.
Water from the pond may be reclaimed as industrial process water or released, as necessary, off-site into Bell Creek, a tributary of the Los Angeles River.
The pond is periodically sampled for radioactivity and sampled at discharge for both ra-dioactive and nonradioactive pollutants as required by the discharge permit issued to Rocketdyne Division by the California Regional Water Quality Control Board.
This report summarizes environmental monitoring results for 1985, which are presented in Section III. The sampling and analytical methods used in the environmental monitoring program for radioactive materials are described in Section IV. A comparison of 1985 radioactivity results with the results from previous years appears in Appendix A, with a summary of the Environmental Mon-itoring Drogram Quality Control in Appendix B.
Appendix C shows regulatory limits on nonradioactive pollutants in water released from the site.
Refer-ences are listed in Appendix D.
The external distribution of this report is shown in Appendix E, and a table of alternative units for radiological data is shown in Appendix F.
The gross alpha and beta radioactivity is reported as results of the monitoring program.
Estimates of radionuclide components in effluents provide the basis for dose commitment calculations.
RI/RD86-140 9
/
II.
SUMMARY
AND EVALUATION OF ENVIRONMENTAL MONT0 RING RESULTS All radioactivity levels observed in environmental samples for 1985 show close agreement with radioactivity levels measured during recent years and re-ported in the previous issues of this report.
Local environmental radioactiv-ity levels, which result from ooth natural and man-made radionuclides and snowed the presence of fallout from past atmospheric testing of nuclear de-Vices, have decreased to generally constant levels during the past several years. These levels are now due mainly to the primordial radionuclides.
The local effects of foreign atmospheric nuclear tests, which had been readily ob-servable in daily ambient airborne radioactivity levels, were not evident in 1985. The long-term effect of airborne radioactivity on surface sample radio-activity levels also has not been discernable in recent years.
The continuing relative constancy in environmental radioactivity levels is primarily due to the dominance of naturally occurring radionuclides in the environment.
The results of this environmental monitoring indicate that there are no significant sources of unnatural radioactive material in the vicinity of the Rocketdyne sites.
Additionally, identical results obtained for on-site and off-site samples further indicate that there is no contribution to general en-vironmental radioactivity attributable to nuclear operations at Rocketdyne.
Potentially significant exposure pathways to the general public resulting from Rocketdyne nuclear operations are limited to the atmospheric discharge of ra-dioactive materials for which the only exposure pathways to people result from wnole body external exposure and from inhalation exposure to released materi-als, and to direct radiation exposure of individuals and the general public beyond the site boundary.
No discharge of liquid radioactive wastes is made to tne environment.
All such materials are processed for disposal at regu-lated disposal sites.
1 The maximum individual annual exposures estimated for persons at the site boundary and also at the residence nearest the SSFL site are small when com-pared with natural radiation and with all applicable guidelines.
The esti-mates of exposure due to inhalation at the ' boundary and the nearest residence RI/RD86-140 11
were derived from the AIRDOS-EPA calculated concentrations at those locations
.I and incorporated the dose conversion factors appropriate for radionuclides in process at each nuclear facility.
This inhalation exposure estimate is the sum of contributions calculated for the measured releases from each facility.
The external radiation exposure estimates at the maximum exposed boundary location and at the nearest residence are based on results for site ambient radiation dosimeters and also for several facility workplace radiation dosime-ters. The unattenuated external annual exposure due to operations conducted at the RMDF is estimated to be 80 mrem at the nearest' boundary-line location and less than 0.1 mrem for the nearest residence for operations conducted at the RMDF.
The boundary-line exposure is conservative in that the rugged ter-rain at the site boundary nearest the RMDF precludes anything more than the occasional and temporary presence of any person at that location.
These values were determined by calculating the unattenuated exposure expected at tne boundary and nearest residence on the basis of the highest annual result for area dosimeters in place around the facility.
For the nearest residence, radiation attenuation due to air absorption and also to the intervening rock formations will lower direct radiation to practically nonexistent levels with only natural background radiation inherent to the residence location being present. Boundary-line direct radiation exposures for the State of California and U.S. NRC-licensed operations at other Rocketdyne nuclear facilities were very much below 10 mrem for the year.
The topography of the SSFL site sur-rounding the nuclear facilities and out to the site boundary is extremely ir-regular. Hills and rock outcroppings shieid the off-site areas, significantly reducing off-site exposures from on-site sources.
l Similarly for the De Soto site, internal dose estimates at the boundary l
and at the nearest residence are not significantly different from zero.
Esti-l mates of the external radiation exposure at the De Soto boundary (4110 mrem) l and at, the nearest residence (0.01 10.01 mrem) are based on the' difference between the single highest on-site TLD measurement and the average of off-site l
measurements. The difference is more likely the result of random variability in the measurements than from actual radiation exposure.
RI/RD86-140 12
Supply water at the SSFL site is monitored at two locations.
This water consists of ground water from deep wells on the site blended with potable wa-ter from the Ventura County Water District 17.
In addition, shallow ground water is periodically sampled at a standpipe adjacent to the basement level of a deactivated systems for nuclear auxiliary power (SHAP) reactor test facility (Building 059). These samples are evaluated to detect the transfer of activa-tion product radioactivity from the underground reactor test vault containment and into the surrounding soil.
None has been detected.
Therefore, these analyses serve as a measure of radioactivity naturally present in the ground water.
1 Quality assurance measures incorporated into the environmental monitoring program include participation in DOE-sponsored programs such as tha Environ-mental Dosimeter Intercomparison Program and the DOE Environmental Measure-ments Laboratory Quality Assessment Program (EML-QAP).
Participation in two EML-QAP sample analysis sets (QAP XXIII and XXIV) was done in 1985.
Analysis of the results indicates that accuracy in measuring radioactivity in the sam-pie media provided for the intercomparison improved; however, additional work is required to develop counting standards that are more representative of the types of samples and analyses addressed in the quality assessment program.
In addition to participation in these programs, laboratory analyses of split and replicate samples are routinely used to evaluate the reproducibility of sample radioactivity measurements of water and soil gross radioactivity.
Control charts of counting system radiation response are maintained.
These data are periodically evaluated to determine the correla-tion between sample sets and trends in background.
RI/RD86-140 13 l
III.
ENVIRONMENTAL MONITORING RESULTS A.
RADI0 ACTIVE MATERIALS--1985 The average radioactivity concentrations in local soil, vegetation, sur-face water, and ambient air for 1986 are presented in Tables 1 through 6.
The data snown for gross alpha activity in samples that are generally thick com-pared with tne range of the alpna particles represent a marked change in the manner of calculating and reporting them, compared with prior reports.
This change reflects the gradual redirection of the monitoring program from moni-l toring to measurement.
Previously, alpha count rate data had been converted to alpha activity concentrations by using an efficiency factor for a thin electroplated source, and the results were monitored for changes from prior val ues.
This resulted in artificially low numerical values for the alpha activity in several sample media.
Starting with the 1984 report, the alpha activity concentrations for these media are reported based on an efficiency factor derived from a sample with distributed alpha activity that is thick relative to the alpha particle range.
For monitoring purposes, this has no effect.
However, the values reported more closely represent the actual alpha activity existing in the environment.
In calculating the average concentra-tion values, all values, including negative values, are included.
This method of noncensorea data averaging, reconnended by DOE Order 5484.1, affords a bet-ter estimate of the central value and dispersion of tne data.
All limits of error reported in the tables are for one standard deviation (1 sigma).
Usual-ly, these show the dispersion of the measured values about the mean.
These two changes in data interpretation result in noticeable differences in the data shown in the historical comparisons.
It must be recognized that these differences do not reflect changes in environmental radioactivity but are merely consequences of the evolution of the monitoring program.
The presentation of data in the tables includes the annually averaged data for each sample type and the maximum radioactivity level detected for a single sample from the annual set, which is reported because of its signiff-cance in indicating the occurrence of a major episode or an area-wide incident RI/RD86-140
- 15
--r,
-l of radioactive material deposition.
None of the maximum observed values, 4
which (as the tables show) occurred randomly during the year, shows a great increase over the average values beyond inherent variability.
The ambient air sampling data show no greatly increasing or decreasing trends for most of the year and can be described as generally constant, with some increase in local airborne radioactivity levels occurring during the second and fourth quarters.
To achieve much higher detection sensitivity for plutonium than gross i
alpha measurements can provide, soil samples are collected and sent to an l
independent testing laboratory for specific analysis for plutonium.
In this analysis, the individual soil samples are leached with acid, and the leachate i
is treated chemically to separate and concentrate any plutonium present in the l
sample.
In this way, minute quantities of plutonium, such as that distributed i
globally by testing of nuclear weapons, can be detected and quantitatively j
measured by alpha spectroscopy.
The results are shown in Table 1.
Alpha 239Pu + 240Pu, predominantly from weap-i spectroscopy permits identifying of 238 ons tests, and Pu, from the destructive reentry of a Transit satellite over the Indian Ocean in April 1964.
TABLE 1 S0IL PLUT0NIUM RADI0 ACTIVITY DATA--1985 j
26 June 1985 Survey Results 4 December 1985 Survey Results 238 239Pu + 240Pu 238 239Pu + 240Pu Pu Sample Pu Location (pC1/g)
(pCi/g)
(pCi/g)
(pCi/g) 1
~
S-56 0.0001 + 0.0002 0.0009 + 0.0003 0.0005 + 0.0004 0.0051 + 0.0006 S-57 0
+ 0.0001 0.0038 + 0.0004 0.0003 + 0.0003 0.0028 + 0.0005 l
S-58 0.0001 + 0.0001 0.0020 + 0.0004 0
+ 0.0001 0.0048 + 0.0006 S-59 0.0001 + 0.0001 0.0025 + 0.0004 0.0001 + 0.0001 0.0017 + 0.0004 S-60 0.0001 + 0.0001 0.0019 + 0.0004 0
+ 0.0002 0.0008 + 0.0004 a
S - 61 0
+ 0.0001 0.0005 + 0.0002 0
+ 0.0001 0.0003 + 0.0002 a0ff-site location RI/RD86-140 16
For comparison with the plutonium present as a result of fallout from nuclear weapons tests and failure at launch of a radioisotope-powered satel-lite, published data from soil tests in nearby Burbank, California, in 1970-71 239 show a plutonium concentration of approximately 2 x 10-9 pCi/g for Pu +
238 240Pu and approximately 0.06 x 10-9 pCi/g for Pu.
The data in Table 1 show no significant increases in on-site soil plutonium relative to the Bur-bank values.
Table 1 shows no significant variation in soil plutonium concentrations for the 1985 sample sets.
The results of the gross radioactivity measurements in soil (Table 2) and in vegetation (Table 3) show no significant difference between on-site and off-site samples.
The detected gross radioactivity in soil and vegetation is due to vari-aus naturally occurring radionuclides present in the environment and to radio-active fallout of dispersed nuclear weapons materials and fission product radioactivity produced by past atmospheric tests of nuclear weapons.
No at-mospheric nuclear weapons tests were announced during 1985. Naturally occur-87 147 ring radionuclides include Be, 40g, Rb, 5m, and the uranium and thori-um series (including radon and daughters).
The radionuclide composition of 40 local area surface soil has been determined to be predominantly K, natural thorium, anr1 natural uranium, both in secular equilibrium with daughter nu-I clides, with less than 1% fission-produced radionuclides, principally Cs.
90 Radioactivity in aged fallout consists primarily of the fission produced Sr-90 137 147 234 239 y,
Cs, and Pm, and also 0 and Pu.
Gamma spectrometric analy-sis of composited ambient air samples collected during 1985 detected only the cosmogenic radionuclide Be, plus additional natural radionuclides of ter-40 restrial origin, the natural uranium and thorium series, and K.
Relative 40 7
amounts of these radionuclides were approximately 65%
K, 34%
Be, and the remainder due to the natural uranium series and natural thorium series.
The 7
l value for Be is representative for the mixture only at the time of measure-l ment since the physical half-life is extremely short compared with those of the other radionuclides detected.
i.
RI/RD86-140 17
TABLE 2 S0ll RADICACTIVITY DATA--1985 Grcss Radioactivity (pci/g)
Nueer Maximum Observed of Annual Average Value Value4 and Area Activity Sanples and Dispersion Month Observed On-site Alpha 144 25.2 + 7.3 48.36 (monthly)
(April)
Beta 144 24.2 + 1.9 32.7 (Septeder)
Off-site Alpha 48 26.3 + 7.8 46.00 (quarterly)
(July)
Beta 48 23.9 + 3.3 30.2 (April)
" Maximum value observed for single sample.
TABLE 3 VEGETATION RADI0 ACTIVITY DATA--1985 Gross Radioactivity (pci/g)
Dry Weight Mh Percent of Samples Nueer Annual Average Annual Average Maximum Valuea With of Value Value and Month Activity Area Activity Samples and Dispersion and Dispersion Observed RlWLb On-site Alpha 144 0.49 + 0.58 3.76 + 4.44 22.0 100 (monthly)
(December)
Beta 144 18.5 + 9.0 134.8 + 53.4 268.9 0
(October)
Off-site Alpha 48 1.05 + 1.73 4.68 + 6.25 25.3 100 (quarterly)
(January)
Beta 48 26.2 + 13.7 132.8 + 49.2 242.4 0
(January) aMaximum value observed for single sample, b inimum detection level: 2.27 pCi/g alpha; 0.36 pCi/g beta (ash).
M i
l RI/RD86-140 l
18
Supply water is sampled monthly at De Soto and at two widely separated SSFL site locations. The average supply water radioactivity concentration for each site is presented in Table 4.
Supply water used at the De 'Soto site is supplied by the Los Angeles Department of Water and Power.
Supply water used at the SSFL site is ootained partly from the Ventura County Water District No.17, which also supplies nearby communities, and from local well water and l
1s distributed on the site by the same piping system previously used when all facility supply water was obtained from on-site wells.
Two on-site water wells (wells 5 and 13) were operated during 1985 to reduce the consumption of the Ventura County water.
The well water proportion in the blend averaged about 51% for the year, for a total well water consumption of about 2.8 x 105,3 7
(7.4 x 10 gal ).
Pressure for the water system is provided by elevated storage tanks.
A shallow standpipe, connected to a French drain at foundation level, placed during construction of a modification to a now deactivated SNAP reactor test facility, is being used for sampling of ground water adjacent to the un-derground reactor test vault.
The well is periodically sampled for the pur-pose of detecting any transfer of activation product radioactivity from the containment to the soil bed. Radioactivity in samples taken during 1985 aver-aged 3.7 x 10-8 Ci/ml beta with no alpha activity detected.
Gamma spectro-60
-7 metric analysis, witn a minimum detection limit for Co of about 5 x 10 pCi/ml, nas not identified any specific unnatural radionuclides in the water; thus, this activity is attributed to dissolved radioelements of natural origin in the soil bed.
A recent hydrogeologic study at SSFL describes two ground water systems at the site:
a shallow, unconfined system of alluvial surface mantle on the Burro Flats area and along the major drainage channels, and a deeper ground water system in the fractured Chatsworth sandstone.
Alluvium along the major surface drainage systems may store and transmit ground water to the underlying Chatsworth Formation through fractures. Water levels in the alluvium respond to recharge resulting from surface flows and may vary considerably between wet and dry periods. The alluvium, composed of a heterogeneous mixture of gravel, RI/R036-140 19
TABLE 4 SUPPLY WATER RADI0 ACTIVITY DATA--1985 Gross Radioactivity (10-9 uCi/ml) a Number Maximum Value of Average Value and Month Area Activity Samples and Dispersion Observed De Soto Alpha 12 2.76 + 1.82 5.73 (monthly)
(November)
Beta 12 3.17 + 0.78 4.60 (March)
SSFL Alpha 24 2.45 + 2.61 8.63 (monthly)
(December)
Beta 24 2.80 + 0.51 3.95 (October) aMaximum value observed for single sample.
sand, silt, and clay, has an estimated hydraulic conductivity ranging from 0.1 2
to 1000 gal / day /ft,
The Chatsworth Formation is composed of well-consolidated, massively bedded sandstones with interbedded layers of siltstone and claystone.
The layer may be as thick as 6,000 ft at the SSFL site.
The direction of ground water flow in the formation is probably radially off-site toward the surround-ing lowlands and is probably controlled by fracture zones.
The hydrogeologic environment at the SSFL site is a dynamic system.
Ground water is recharged at the site, moves through the aquifers, and dis-charges to the surface or to other aquifers down-gradient of the site.
The ground water system is recharged by precipitation and by unlined ponds and drainage channels.
Because of the meager rainfall in the area and the rela-tively large variability in annual precipitation, ground water recharge may vary greatly from year to year.
Specific pathways of possible contaminant RI/RD86-140 20
1 4
transport are difficult to predict on the basis of on-site well data.
The most likely pathways are along fracture zones that trend off-site.
~
As discussed earlier, surface waters discharged from SSFL facilities and the sewage plant outfall drain southward into Rocketdyne retention pond R-2A.
Wnen full, the pond may be drained into Bell Creek, a tributary of the Los Angeles River in the San Fernando Valley, Los Angeles County.
Pursuant to the i
requirements of Los Angeles Regional Water Quality Control Board Resolution 66-49 of 21 September 1966, a sampling station for evaluating environmental radioactivity in Bell Canyon was established in 1966.
It is located approxi-mately 2.5 miles downstream from the southern Rockwell International Corpora-tion boundary.
Samples, obtained and analyzed monthly, include stream bed S
mud, vegetation, and water. Average radioactivity concentrations in Retention Pond R-2A and Bell Creek samples are presented in Table 5.
Comparison of the radioactivity concentrations in water from the ponds and from Bell Creek with that of the supply water shows no significant differ-ences in either alpha or beta activity.
Similar comparisons between on-site and off-site soil and vegetation samples and those of Bell Creek show no sig-nificant differences.
The SSFL site surface water and the ambient air radioactivity concentra-tion guide values selected for each site are the most restrictive limits for those radionuclides currently in use at Rocketdyne facilities and should not be taken to indicate the identification of these radionuclides in the sam-
}
pl es. Radioactivity concentration guide values are those concentration limits adopted by DOE, Nuclear Regulatory Connission (NRC), and the State of Cali-fornia as maximum permissible concentrations (MPCs) for unrestricted areas.
The MPC values are dependent on the radionuclide and its behavior as a soluble l
or an insoluble material.
For comparison with results of environmental and effluent monitoring, the single lowest MPC value for the various radionuclides j
present is selected rather than a derived MPC for the mixture.
Accordingly, l
for SSFL site surface water, the guide values of 5 x 10-0 pCi/ml alpha ac-239Pu and 3 x 10-7 uCi/ml beta activity corresponding tivity corresponding to RI/RD86-140 21
-l TABLE 5 BELL CREEK AND RETENTION POND RADI0 ACTIVITY DATA--1985 Gross Radioactivity Concentrations Percent of Samples Number Annual Average Maximum Valuea With Area of Value and Month Activgty (monthly)
Activity Sanples and Dispersion Observed EMDL Bell Creek mud Alpha 12 21.9 + 6.5 31.9 0
no. 54 (pCi/g)
(January)
Seta 12 22.7 + 1.1 24.7 0
(November)
Pond R-2A mud Alpha 12 31.4 + 6.0 43.7 0
no. 55 (pci/g)
(May)
Beta 12 24.0 + 1.1 25.3 0
(Decader)
Bell Creek vege-Alpha 12 1.34 + 1.25 2.82 100 tation no. 54 (January)
(pCi/g-ash)
Beta 12 137.1 + 28.6 178.8 0
(August)
Bell Creek vege-Alpha 12 0.23 + 0.20 0.49 100 tation no. 54 (Septeder)
(pci/g dry weight)
Beta 12 22.4 + 6.1 32.94 0
(Septeder)
Bell Creek water Alpha 12 1.38 + 7.09 19.68 100 N6 pCi/ml)
Beta 12 2.49 + 0.75 3.79 0
(Decader) l Pond water no. 6 Alpha 12 2.06 + 4.44 13.65 100 (10-9 pCi/ml)
(October)
Beta 12 3.53 + 0.%
4.92 0
(Noveder) i l
SSFL pond R-2A Alpha 12 3.07 + 1.94 6.61 100 water no. 12 (April) l (10-9 pCi/ml)
Beta 12 3.49 + 0.76 5.56 0
l (October) aMaximum value observed for single sample.
bMinimun detection level: Approximately 6.40 x 10-9 pCi/ml alpha; 0.64 x 10-9 pCi/ml beta for water: approximately 2.3 pCi/g alpha; 0.23 pC1/g for soil: approximately 2.3 pCi/g alpha; 0.36 pCi/gn for vegetation ash.
RI/RD86-140 l
22
1 90 to Sr are appropriate.
These values are established in 10 CFR 20, California Administrative Code Title 17, and DOE Order 5480.lA.
i Ambient air sampling for long-lived particulate alpha and beta radioacti-vity is performed continuously by automatic sequential samplers located at the De Soto and SSFL sites. Air is drawn through Type A glass fiber filter media, j
which are analyzed for retained long-lived radioactivity after a minimum 120-h decay period that eliminates naturally occurring short-lived particulate ra-dioactivity (most radon' daughters). The average concentrations of ambient air alpha and beta radioactivity for 1985 are presented for the various sampler locations in Table 6.
The guide value of 6 x 10~I4 pCi/ml for SSFL site ambient air alpha activity is due to work with unencapsulated plutonium.
The value of 3 x 10-II 90 pCi/ml for beta activity is due to the presence of Sr in fission products in irradiated nuclear fuel at the SSFL site.
The guide value of 3 x 10-12 pCi/ml for De Soto ambient air alpha activity is due to work with unencapsu-lated uranium (including depleted uranium).
Tne guide value of 3 x 10-10 60 pCi/ml is for Co, for which the ambient air beta activity guide is appro-priate since it is the most restrictive limit for any beta-emitting radio-nuc1ide in use at the De Soto site. Guide value percentages are not presented for soil or vegetation data since none have been established.
Monitoring of ambient radiation is performed with TLDs.
Each dosimeter set uses two calcium fluoride (CaF :Mn) low background, bulb-type chip do-2 simeters. The dosimeter sets are placed at locations on or near the perime-ters of the.De Soto and SSFL sites.
Each dosimeter, sealed in a light-proof energy compensation shield, is installed in a sealed plastic container mounted about 1 m above ground at each location.
The dosimeters are exchanged and evaluated quarterly.
During the year,18 on-site TLD monitoring locations were used. Five additional dosimeter sets, placed at locations up to 10 miles from the sites, are similarly evaluated to determine the local area off-site amoient raciation level, which averaged 11 prem/h for 1985. The quarterly and t.
RI/RD86-140 23 l
O TABLE 6 AMBIENT AIR RADI0 ACTIVITY DATA--1985 Gross Radioactivity Concentrations-Fentocuries per cm3 (10-15 pCi/ml)
Percent of Samples Number Annual Average Maximum Valuea Percent With Area of Value and Month of Activity (monthly)
Activity samples and Dispercion Observed Guideb
< Mote De Soto on-site Alpha 544 2.7 + 2.2 38.0 (01/07) 0.09 89 (2 locations)
Beta 40.0i14.0 180.0 (05/10) 0.01 2
s5FL on-site Alpha 1725 2.0 + 1.6 44.0 (07/04) 3.3 93 (5 locations)
Beta 40.0 i 13.0 170.0 (07/05) 0.01 2
55FL sewage Alpha 360 2.3 + 1.9 25.0 (01/29) 3.8 89 treatment plant SSFL control Alpha 365 1.6 2 1.4 13.0 (07/04) 2.7 93 center Beta 38.0 i 12.0 160.0 (07/15) 0.1 3
All locations Alpha 2994 2.1 1.8 44.0 (07/04) 0.07 92
~
Beta 40.8 i 15.2 240.0 (05/07) 0.01 2
aMaximum value observed for single sangle 3 x 10-3D Ci/ml beta; 10 CFR 20 Appendix B.
s5FL site:
bGuide:
a x 10-12 pCi/ml alpha,13 pCi/mi beta; 10 CFR 20 Appendix B, CAC 17, doe Order 5480.lA.
p 6 x 10-14 pCi/ml alpha, 3 x 10-cMDL = 6.4 x 10-15 pci/ml alpha; 1.3 x 10-14 pCi/ml beta.
annual radiation exposures and the equivalent absolute and altitude-adjusted annual exposures, and exposure rates detennined for each dosimeter location are presented in Tables 7 and 8.
Table 7 shows that radiation exposures and equivalent annual exposure rates monitored on-site are nearly identical to levels monitored at five widely separated off-site locations.
These data reflect natural background radiation from cosmic radiation, radionuclides in the soil, radon and thoron in the atmosphere, and radioactive fallout from atmospheric nuclear device tests.
Locally, the natural background radiation level as measured by these RI/RD86-140 24
?.
TABLE 7 DE SOTO AND SSFL SITES--AMBIENT RADIATION DOSIMETRY DATA--1985 Equivalent Quarterly Exposure Exposure at (mrem)
Annual 1000 ft ASL TLD Exposure Location Q-1 Q-2 Q-3 Q-4 (mrem)
(mrem)
(prem/h)
De Soto DS-1 22 31 26 28 107 109 12 DS-2 20 24 30 26 100 102 12 DS-3 20 29 26 26 101 103 12 DS-4 23 31 25 a
105 107 12 DS-5 21 28 22 25 96 98 11 DS-6 24 32 24 a
107 109 12 DS-7 20 26 21 24 91 93 11 DS-8 21 28 20 24 93 95 11 Mean value 21 29 24 26 100 102 12 SSFL SS-1 23 35 26 a
112 100 11 SS-2 20 35 30 32 117 105 12 SS-3 24 35 30 32 1 21 109 12 SS-4 a
33 31
'32 128 115 13 SS-5 24 34 29 30 117 1 04 12 SS-6 26 37 30 32 125 114 13 SS-7 19 36 26 29 110 98 11 SS-8 b
38 29 32 132 120 14 SS-9 b
40 34 40 152 140 16 SS-10 b
34 28 30 123 112 13 Mean value 23 36 29 32 124 112 13 Off-site OS-1 22 32 29 29 112 114 13 OS-2 21 27 23 26 97 95 11 OS-3 20 34 24 26 104 106 12 0S-4 22 30 24 27 103 1 01 12 OS-5 23 32 25 30 110 111 13 Mean value 22 31 25 28 105 105 12 aMissing dosimeter; annual exposure estimated from data for three quarters.
Dosimeter location established at the beginning of the second quarter.
Annual exposure estimated from data for three quarters.
.s RI/RD86-140 25
O dosimeters is about 100 mrem / year. The small variability observed in the data is attributed to differences in elevation and geologic conditions at the vari-ous dosimeter locations.
The altitude range for the dosimeter locations is from about 875 ft ASL (above sea level) at the De Soto site to a maximum of about 1900 ft ASL for one of the SSFL dosimeters. When normalized to a spe-cific altitude by adjusting the measured value by an altitude adjustment fac-tor equal to 15 mrem /1000 ft elevation difference, derived radiation exposures i for all locations are essentially identical.
The 1985 averaged exposure val-ues adjusted to 1000 ft ASL are 102 + 6 mrem for the De Soto site,112 + 12 mrem for the SSFL site, and 105 + 8 mrem for the off-site control dosimeters.
During the 4-year period of 1977 through 1980, a steady increase was observed in the TLD readings for all locations. Although the increases were variable from year to year and between locations, averaged over 4 years, the increases were in the range of 14 to 17 mrem / year. The values for 1985 show a slight increase from the previous year's results when adjusted to a consnon al titude.
Supplementary measurements of ambient radiation levels with high-pres-
~
sure ion chamber (HPIC) monitors are made at two locations at the SSFL site.
The HPIC values for 1985 were equivalent to annual exposures of 111 mrem for the Building 207 monitor and 120 mrem for the Building 363 monitor.
These values are in good agreement with results for nearby TLD locations for the year.
For independent monitoring of radiation levels in this area, the Radio-logic Health Section of the State of California Department of Health Services provides pac,kages containing lithium fluoride (LiF) chip dosimeters for place-ment with the packets used for the bulb dosimeters.
The State dosimeters are returned to the Radiologic Health Section in Sacramento for evaluation.
Data for tnese TLDs, placed at eight Rocketdyne dosimeter locations, both on-site and off-site, are presented in Table 8 for 1985.
Considering the total inde-pendence of these measurements and the use of different thennoluminescent mate-rials, the agreement is reasonably good; however, the State results are some-what lower for each location jointly monitored.
RI/RD86-140 26
,~
TABLE 8 DE SOTO AND SSFL SITES--STATE OF CALIFORNIA AMBIENT RADIATION 00SIMETRY DATA--1985 Equivalent Quarterly Exposure Exposure at (mrem)
Annual 1000 ft ASL TLD Exposure Location Q-1 Q-2 Q-3 Q-4 (mrem)
(mrem)
(prem/h)
De Soto DS-2 23 12 17 19 71 73 8
DS-6 24 20 21 a
87b 89 10 DS-8 a
16 20 19 73b 75 9
Mean value 24 16 19 19 78 79 9
SSFL SS-3 27 20 24 22 93 81 9
SS-6 27 24 21 30 102 91 10 SS-7 21 21 24 a
88b 76 9
Mean value 25 22 23 26 96 83 9
Off-site OS-1 22 20 21 26 89 91 10 OS-5 26 19 18 26 89 90 10 Mean value 24 20 20 26 89 91 10
~
aMissing dosimeter; annual exposure estimated from data for the three quarters.
Annualized value.
B.
NONRADI0 ACTIVE MATERIALS--1985 Processed wastewater and most collected surface runoff discharged from the SSFL site flows to Rocketdyne retention pond R-2A.
Water samples from the pond are analyzed for various constituents, as required oy the Regional Water Quality Control Board, for each discharge to Bell Canyon.
Such discharges are normally done only as a result of excessive rainfall runoff; however, during 1985, only four off-site discharges occurred due to a dry year.
The results of analyses for each discharge for 1985 are presented in Table 9.
RI/RD86-140 27
TABLE 9 NONRADI0 ACTIVE CONSTITUENTS IN WASTEWATER DISCHARGED TO UNRESTRICIED AREAS--1985 (Analysis Results for Wastewater Discharged from Pond R-2A to Bell Creek on Date Indicated - %mple Station W-12)
January 29" March 7 March 28' November 25 8
8 of of of of
=
Result Guide Result Guide Result Guide Result Guide Total dissolved solids (mg/l) 340 35.8 480 50.5 380 40.0 224 23.6 Chloride (mg/1) 40 26.7 52 34.7 40 26.7 21 14.0 Sulfate (mg/1) 110 36.7 124 41.3 108 36.0 52 17.3 Suspended solids (mg/1) 24 17 20 39.4 3
Settleable solids (mg/1) 0.1
<0.1
<0.1
<0.1 D
B005 (mg/1) 7 23.3 3
30.0 4
13.3 4.3 14.3 k
011 and grease (mg/1) 1.6 10.7
<5
<33.3
<5
<33.3 2.6 17.3 h
Turbidity (TU) 14 4
11 51 o
Fluoride (mg/1) 0.4 40.0 0.4 40.0 0.5 50.0 0.1 10.0 Boron (mg/1) 0.3 30.0 0.3 30.0 0.2 20.0 0.2 20.0 Residual chlorine (mg/1)
<0.04
<40.0
<0.04
<40.0
<0.04
<40.0
<0.04
<40.0 Fecal coliform (MPN/100 ml)
<2
<8.7
<2
<8.7
<2
<8.7
<2
<8.7 Surfactants (MBAS) 0.03 6.0 0.08 16.0 0.03 6.0 0.04 26.7 pH 8.6 8.3 8.4 7.8 Rainfall (cm) 1.4 0.9 2.8 6.5 Estimated rainfall runoff (m3) 47,250 28,350 86,940 151,200 3
Release volume (m )
23,247 15,974 7,401 13,986 aRainfall-related discharge 0003Y/slw 8
IV.
ENVIRONMENTAL MONITORING PROGRAM A.
DESCRIPTION A program of soil and vegetation sample collection and analysis for ra-dioactivity was begun in 1952 in the Downey, California area where the nuclear research and development work of the predecessor company to Rocketdyne was initially located.
Environmental sampling was subsequently extended to the then proposed Sodium Reactor Experiment (SRE) site in the Simi Hills in May 1954.
In addition, sampling was begun in the Burro Flats area, southwest of SRE, where other nuclear installations were planned and are currently in oper-ation. Tne Downey area survey was terminated when nuclear activities were re-located to Canoga Park in 1955. The primary purpose of the environmental mon-itoring program is to adequately survey environmental radioactivity to ensure that Rocketdyne nuclear operations do not contribute significantly to environ-mental radioactivity.
The locations of sampling stations are shown in Fig-ures 5 through 7 and listed in Table 10.
B.
SAMPLING AND SAllPLE PREPARATION 1.
Soil Soil is analyzed for radioactivity to monitor for any significant in-crease in radioactive deposition by fallout from airborne radioactivity.
Since soil is naturally radioactive and has been contaminated by atmospheric testing of nuclear weapons, a general background level of radioactivity exists.
The data are monitored for increases beyond the natural variability of this background. For most radionuclides, gross alpha and beta radioactivity meas-urements are adequate for this purpose.
Chemically specific analyses are performed for plutonium to provide improved sensitivity.
RI/RD86-140 29
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Map of Canoga Park, Simi Valley, Agoura, and Calabassas Sampling Stations
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Map of De Soto Site and Vicinity Sampling Stations
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Map of Santa Susana Field Laboratories Site Sampling Stations
TABLE 10 SAMPLING LOCATION DESCRIPTION (Sheet 1 of 4)
Frequency of a
Station Location Sampling SV-1 SSFL Site, Building 143, southeast side (M)
SV-2 SSFL Site, Building 143, at perimeter drainage system (M)
SV-3 SSFL Site, Building 064, north parking lot area (M)
SV-4 SSFL Site, Building 020, at west fence (M)
SV-5 SSFL Site, Building 363, east parking lot area (M)
SV-6 SSFL Site Interim Retention Pond, south side (Q)
SV-10 SSFL Site Access Road, at upper mobile home park entrance (Q)
SV-12 SSFL Site, Building 093, at reactor building driveway (M)
SV-13 SSFL Site, between SRE Water Retention Pond and former sodium cleaning facility (M)
SV-14 SSFL Site, Building 028, upper parking lot area (M)
SV-19 SSFL Site Entrance, Woolsey Canyon (Q)
~
SV-24 De Soto Site, Building 104, east side (M)
SV-25 De Soto Avenue and Plummer Street, southeast corner (Q)
SV-26 Mason Avenue and Nordhoff Street, southeast corner (Q)
SV-27 De Soto Avenue and Parthenia Street, northeast corner (Q)
SV-28 Canoga Avenue and Nordhoff Street, northwest corner (Q)
SV-31 Simi Valley, Alamo Avenue and Sycamore Road, southeast (Q) corner SV-40 Agoura - Kanan Road and Ventura Freeway at Frontage Road (Q)
SV-41 Calabasas - Parkway Calabasas and Ventura Freeway at Frontage Road (Q)
SV-42 SSFL Site, Building 886, at old sodium disposal facility gate (M)
SV-47 Chatsworth Reservoir Site North Boundary at north gate (M)
SV-51 SSFL Site, Building 029, at driveway (M) l S
RI/RD86-140 33
TABLE 10 SAMPLING LOCATION DESCRIPTION (Sheet 2 of 4) 9 d
Frequency of Station Location Sampling" 4
i SV-52 SSFL Site, Burro Flats Drainage Control Sump, G Street i
and 17th Street (M) i SV-53 SSFL Site Pond R-2A (Q)
SV-54 Bell Creek at Ventura County Line (M)
SV-55 SSFL Site, Pond R-2A (Pond Bottom Mud), north side (M) l SV-56 SSFL Site, F Street and 24th Street (S)~
S-57 SSFL Site, J Street, south of Building 055 exhaust stack (S)
S-58 SSFL Site, Building 353, south of road (S)
S-59 SSFL Site, Test Area CTL 4, entrance, east side (S)
S-60 SSFL Site, Pond R-2A, northwest side (S)
S-61 Simi Valley, east end of Alamo Avenue (S)
W-6 SSFL Site Interim Retention Pond, south side (M)
W-7 SSFL Site Supply Water, Building 003, washroom faucet (M)
W-ll SSFL Site Domestic Water, Building 363, washroom faucet (M)
W-12 SSFL Site, Pond R-2A, north side (M)
W-16 Bell Creek at Ventura-Los Angeles County Line (M) l A-1 De Soto Site, Building 102 roof (D)
A-2 De Soto Site, Building 104 roof (D) 4 l
A-3 SSFL Site, Building 100, east side (D)
)
A-4 SSFL Site, Building 011, west side (D)
A-5 SSFL Site, Building 600, Sewage Treatment Plant, north side (D) i A-6 SSFL Site, Building 207, Security Control Center, north side (D)
A-7 SSFL Site, Building 074, south side (D)
A-8 SSFL Site, Building 163, Box Shop at east side (D)
A-9 SSFL Site, Building 363, west side (D)
A-10 SSFL Site, Building 100, east side day sampler (168 h) 1 4
S RI/RD86-140 4
34
~
TABLE 10 SAMPLING LOCATION DESCRIPTION (Sheet 3 of 4)
Frequency of Station Location Sampling" On-Site--De Soto - Ambient Radiation Dosimeter Locations (TLD)
DS-1 De Soto Site, south of Building 102 (Q)
DS-2 De Soto Site, west boundary inside water supply enclosure (State of California TLD Location Number 2)
(Q)
DS-3 De Soto Site, Guard Post 1, Building 102 (Q)
DS-4 De Soto Site, northeast corner of storage yard fence (Q)
DS-5 De Soto Site, north coundary at parking lot entry (Q)
DS-6 De Soto Site, east boundary, southeast corner of fence (State of California TLD Location Number 1)
(Q) 05-7 De Soto Site, south boundary in parking lot telephone pole stay (Q)
DS-8 De Soto Site Guard Post 4, southwest corner of Building 101 (State of California TLD Location Number 7)
(Q)
On-Site--SSFL (TLD)
SS-1 SSFL Site, Building 114 on telephone pole (Q)
SS-2 SSFL Site, SRE Retention Pond on pump motor control panel (Q)
SS-3 SSFL Site, Electric Substation 719 on boundary fence (State of California TLD Location Number 3)
(Q)
SS a SSFL Site, west boundary on H Street (Q)
SS-5 SSFL Site, southwest boundary at property line gate (Q)
SS-6 SSFL Site, Building 854 (State of California TLD Location Number 4)
(Q)
SS-7 SSFL Site, Building 363, north side on HPIC monitor (State of California TLD Location Number 8)
(Q)
SS-8 SSFL Site, Sodium Disposal Facility north boundary (Q)
SS-9 SSFL Site, Radioactive Materials Disposal Facility, northeast boundary (Q)
SS-10 SSFL Site, Building 600, Sewage Treatment Plant (Q) e RI/RD86-140 35
5 TABLE 10 SAMPLING LOCATION DESCRIPTION (Sheet 4 of 4)
Frequency of Station Location Sampling
- Off-Site (TLD) 0S-1 Off-site, Northridge, approximately Oakdale Avenue and Lassen Street (State of California TLD Location Number 5)
(Q) 05-2 Off-site, Simi Valley, approximately Tapo Canyon and Walnut Streets (Q) 05-3 Off-site, San Fernando Valley, Northridge, approximately Plumner Street and Vanalden Avenue (Q)
OS-4 Off-site, Simi Valley, approximately Tapo Canyon and Walnut Streets (Q)
OS-5 Off-site, Simi Valley, approximately Erringer Road and Highway 118 (State of California TLD Location Number 6)
(Q)
HPI-l High-Pressure Ion Cnambers (HPIC) Ambient Radiation Monitor at Building 207, north side (C)
HPI-2 HPIC Ambient Radiation Monitor at Building 363, north side (C)
" Code Description SV Soil and vegetation sample station S
Soil sample station W
Water sample station A
Air sampler station TLD Tnermoluminescent dosimeter D
Daily sample M
Monthly sample Q
Quarterly sample S
Semiannual sample j
C Continuous i
RI/RD86-140 36 i
I
Surface soil types available for sampling range from decomposed granite to clay and loam.
Samples are taken from the upper 1 cm of undisturbed ground 4
surface for gross radioactivity analysis and to a depth of 5 cm for plutonium analysis. The soil samples are packaged in plastic containers and returned to the laboratory for analysis.
Sample preparation of soil for gross radioactivity determination consists 2
of transferring the soils to Pyrex beakers and drying them in a muffle furnace at about 500*C for 8 h.
After cooling, the soil is sieved to obtain uniform particle size. Two-gram aliquots of the sieved soil are weighed into copper i
planchets.
The soil is wetted in the planchet with alcohol, evenly distrib-l uted to obtain uniform sample thickness, dried, and counted for alpha and beta radiation.
Soil plutonium analysis is performed using a chemically specific method
^
by a certified independent testing laboratory according to the guidelines specified in the U.S. NRC Regulatory Guide 4.5 titled " Measurements of Radio-nuclides in the Environment--Sampling and Analysis of Plutonium in Soil."
1 2.
Vegetation The analysis of vegetation, performed as an adjunct to the soil analysis, is done to determine the uptake of radioactivity by plants.
These plants do f
not contribute to the human food chain, and there is no significant agricul-i ture 'or grazing in the insnediate neighborhood of either site.
l Vegetation samples obtained in the field are of the same perennial plant types, wherever possible; these are usually sunflower or wild tobacco.
Vege-tation leaves are stripped from plants and placed in waxed cardboard contain-ers for transfer to the laboratory for analysis.
Ordinarily, plant root sys-tems are not analyzed.
Since the analysis is done to determine uptake only, and not fallout deposition, vegetation is first washed with tap water to remove soil, dust, and other foreign matter and then thoroughly rinsed with distilled water.
RI/RD86-140 l
37
Washed veg'etation is vacuum-dried in. tared beaker,s at 100*C for 24 h for dry weight determination, then ~asned in a muffle furnace at about 500*C for 8 h, producing a completely burned' ash.
One-gram aliguots of pulverized ash from each beaker are weighed into copper planchets.
The vegetation ash is wetted in the planchet with alcohol, evenly distributed to obtain uniform sample tnickness, dried, and counted for alpha and beta. radiation.
The dry / ash weight ratio is used for determining the equivalent dry weight gross radio-activity concentration value,. The moisture content of the vegetation is about 80% of the total plant weight,'
3.
Water Surface and supply water sr.mples are obtained' monthly at the De Soto and SSFL sites and from Bell Creek.
The water is drawn into 1-liter polyethylene bottles and transferred to the 1 Aa atory.
Five-hundred-milliliter volumes of water are evaporated to dryness in crystallizing dishes at about 90*C.
The residual salts are redissolved into distilled water, transferred to planchets, dried under heat lamps, and counted for alpha and beta radiation. '
4.
Ambient Air Air sampling is performed continuously at the De Soto and SSFL sites with continuous air samplers operating on 24-h sampling cycles.
Airborne particu-late radioactivity is collected on Type A glass fiber filtsr media, which are automatically changed daily at the end of each sampling period (midnight).
The samples are counted for alpha and beta radiation following a minimum 120-h 3
decay period. The volume of d typical daily ambient air sample is about 25 m.
Figure 8 is a graph of the weekly, averaged long-lived alpha and beta ambient air radioactivity concentrations for the De Soto and SSFL sites during 1985. The daily data were mathematically smoothed in a movitig weekly average RI/RD86-140
(
38
,, ',,j LOCAL AREA RAINFALL OCCURFkED ON DAYS INDICATE [i BY DOT '
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Weekly, Monthly, and Annual Averaged Long-Lived Airborne Radioactivity at the De Soto and Santa Susana Field Laboratories Sites--1985 I
1 of daily data for the year.
The average alpha and beta radioactivity concen-trations for each month are indicated by horizontal bars.
The graph shows small decreasing trends in airborne radioactivity during the first and third l
quarters, with a small increase in the sununer and again late in the year; how-ever, overall levels were genarally constant for the year.
Several transient peak concentration levels were observed within the general trend.
This activ-ity is attributed to naturally occurring airborne radioactive materials and, to a minor degree, to residual aged fallout from past foreign atmospheric tests of nuclear devices.
Nuclides identified in air samples collected during 40 1985 include Be, and K, plus several of the naturally occurring radio-nuclides from the uranium and thorium series.
While the data for airborne alpha activity are nearly all below the minimum detection level for a single sample, averaging values from 9 daily air samples over 7 consecutive days and over calendar months reveals the long-tenn behavior of this activity, which for 1985 shows relatively constant levels with the exception of depressed air-borne alpha radioactivity coincident with periods of rainfall.
C.
COUNTING AND CALIBRATION Environmental soil, vegetation, water, and ambient air samples are counted for alpha and beta radiation with a low-background gas flow propor-tional counting system. The system is capable of simultaneously counting both alpha and beta radiation. The sample-detector configuration provides a nearly 2n geometry.
The thin-window detector is continually purged with methane counting gas.
A preset tine mode of operation is used for all samples.
The minimum detection levels shown in Table 11 are those for a single sample de-termined by using. typical values for counting time, system efficiencies for detecting alpha and beta radiation, background count rates (approximately 0.05 cpm alpha and 1.0 cpm betO, and sample' size. For the table, the minimum statistically significant aw.r of radioactivity, irrespective of sample con-figuration, is taken 0; %t a ount equal in count rate to three times the standard deviation of the system background count rate.
The minimum detection level (MDL) is that value that would be statistically' expected to be exceeded by random variation in background in only 0.135% of the measurements.
RI/RD86-140 40
i TABLE 11 MINIMUM RADI0 ACTIVITY DETECTION LEVELS (MDLs)
Sample Activity Minimum Detection Level Soil Alpha (2.3 j; 1.4) 10-6 pCi/g Beta (2.3 f; 1.2) 10-7 pCi/g Vegetation Alpha (2.3 f; 1.3) 10-6 pCi/g ash Beta (3.6 f;1.8) 10-7 pC1/g ash Water Alpha (6.4 j; 3.9) 10-9 pCi/ml Beta (6.4 j; 3.2) 10-10 pCi/ml Air Alpha (6.4 j; 3.8) 10-15 pC1/ml Beta (1.3 f; 0.6) 10-14 pCi/ml Counting system efficiencies are determined routinely with Ra-D+E+F (with O
235 239 40 alpha absorber),
C1, 230Th, U, and Pu standard sources and with g,
in the form of standard reagent-grade kcl, which is used to simulate soil and vegetation samples, and with soil containing known amounts of fully enriched i
Self-absorption standards for beta counting are made by dividing sieved kcl into samples that increase in mass by 200-mg increments, from 100 to 3000 mg. The samples are placed in planchets of the type used for environ-mental samples and are counted.
The ratio of sample activity to the observed net count rate for each sample is plotted as a function of sample mass and a smooth curve is drawn through these points.
The correction factor (ratio) corresponding to the mass of environmental samples is then obtained from the graph.
Tne product of the correction factor and the net sample count rate yielas the sample activity (dpm).
This method has been proven usable by applying it to various-sized aliquots of uniformly mixed environmental samples and observing that the resultant specific activities fell within the expected statistical counting error, showing the absence of any systematic bias.
RI/RD86-140 41
Since the observed radioactivity in environmental samples is primarily the result of natural sources and weapons testing and is at such low concen-trations, no identification of constituent radionuclides is done for each sample; however, collected samples are composited for gamma spectrometry of accumulated sample materials.
The detection of significant levels of radio-activity would lead to an investigation of the radioactive material involved, the sources, and the possible causes.
D.
NONRADI0 ACTIVE MATERIALS The Rocketdyne Division of Rockwell International Corporation has filed a Report of Waste Discharge with the California Regional Water Quality Control Board and has been granted a National Pollutant Discharge Elimination System permit to discharge wastewater, pursuant to Section 402 of the Federal Water Pollution Control Act.
The permit, NPDES No. CA0001309, which became effec-tive 27 September 1976, was renewed with minor changes effective 17 September 1984. This permit covers discharge of overflow and storm runoff from water reclamation retention ponds into Bell Creek.
Discharge generally occurs only during and immediately after periods of heavy rainfall or during extended periods of rocket engine testing that release large amounts of cooling water to the ponds.
Only one of the retention ponds receives influent from the nuclear oper-ating areas of the SSFL site.
It is identified as retention pond R-2A, Water Sample Station W-12 in Table 10.
The influent includes sewage treatment plant outfall and surface runoff water.
Grab-type water samples taken at the retention pond prior to a dis-charge are analyzed by a California State certified analytical testing labor-atory for nonradioactive chemical constitutents and for radioactivity.
The specific constituents analyzed for, and their respective limitations in dis-charged wastewater, are presented in Appendix C.
Wastewater originating from facilities locatea throughout the SSFL site is collected at the retention pond.
RI/RD86-140 42
The point of origin of staall amounts of most nonradioactive constituents nor-mally found in wastewater is difficult to determine; however, in the event of excessive amounts of any of these materials in wastewater, the origin could be determined from the knowledge of facility operations involving their use.
Four off-site discharges of wastewater from pond R-2A occurred during 1985.
In addition to the wastewater discharge limitations, atmospheric pollu-tant discharge limitations were imposed by the Ventura County Air Pollution Control District ( APCD) Permit 0271 on two natural-gas / oil-fired sodium heat-ers operated by ETEC.
The limitations are 0.12 tons / year for reactive organic compounds, 79.63 tons / year for oxides of nitrogen,1.87 tons / year for particu-lates, 0.11 tons / year for oxide of sulfur, and 3.2 tons / year for carbon diox-ide.
Based on fuel corsumption records for this facility during 1985, there was essentially no discharge to the atmosphere in comparison with the dis-charge limits.
During 1985, the APCD permit was renegotiated with Ventura County resulting in the more restrictive pollutant discharge limitations described above as compared to 1984.
1 j
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RI/RD86-140 43
l-V.
EFFLUENT MONITORING PROGRAM Effluents that may contain radioactive material are generated at the Rocketdyne Division facilities as the result of operations performed under contract to DOE, under NRC Special Nuclear Materials License SNM-21, and under the State of California Radioactive Material License 0015-70.
The specific facilities are identified as Buildings 020, 021-022, and 055 at the Santa Susana site, SSFL, and Building 104 (previously identified as 004) at the De Soto Facility.
A.
TREATMENT AND HANDLING Waste streams released to unrestricted areas are always limited to atmos-pheric emissions. No contaminated liquids are discharged to unrestricted areas.
The level of radioactivity contained in all atmospheric emissions is 3
reduced to the lowest value by passing the emissions through certified, high-efficiency particulate air (HEPA) filters.
These emissions are sampled for particulate radioactive materials by means of continuously operating stack exhaust samplers at the points of release.
In addition, stack monitors in-stalled at Buildings 020, 021-022, and 055 provide automatic alarm capabil-f ity in the event of the release of gaseous or particulate activity from Build-ing 020 and particulate activity from Buildings 021-022 and 055.
The HEPA filters used for filtering atmospheric emissions are at least 99.97% efficient for particles 0.3 um in diameter.
Pa'rticle filtration efficiency increases for particles above and below this size.
The average concentration and total radioactivity in atmospheric emis-sions to unrestricted areas are shown in Table 12.
The effectiveness of the air cleaning systems is evident from the fact that in most cases the atmos-pheric emissions are less radioactive than is ambient air.
The total shows that no significant quantities of radioactivity were released in 1985.
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RI/RD86-140 l
45
TABLE 12 ATMOSPHERIC EMISSIONS TO UNRESTRICTED AREAS--1985 Smipling Percent Approximate Period Total of Approximate Minimum Annual Maxique Radio-Sanples tmissions Detection Average Observed activity Percent with Volume Activity Level Concentration Concentration Released of Activity (m3)
Monitored (10-15pCi/ml)
(10-15 pCl/ml)
(10-15 pCi/ml)
(Ci)
Guidea
<MDL Alpha 0.21 1.10 4.50 1.5 x 10-7 0.04 7
104 1.3 x 108 De Soto Beta 0.72 3.42 7.34 4.5 x 10-7 0.001 20 Alpha 0.09 1.77 102.80 4.5 x 10-7 2.95 7
020 2.5 x 108 55FL Beta 0.30 354.22 22410.00 9.0 x 10-5 1.18 0
Alpha 0.09 0.17 1.80 3.9 x 10-8 0.28 71 021-022 2.3 x 108 N
SSFL Beta 0.30 39.13 673.28 9.0 x 10-6 0.13 0
Alpha 0.29 0.24 1.34 5.3 x 10-8 0.40 73 1
055 2.2 x 108 55FL Beta 0.%
6.51 25.56 1.5 x 10-6 0.22 4
Total 8.3 x 108 Total 1.0 x 10-4 Annual average an6ient air radio-Alpha 2.0 Anblent activity concen-centrationD - 1985 Beta 35.0 equivalente 3.1 x 10-5 aAssuming all radioactivity detected is from Rocketdyne nuclear operations.
pci/ml alpha, 3 x 10-lu pCi/ml beta; 3 x 10-R10 CFR 20 Appendix B.
Guide: De Soto site: 3 x 10- M 55FL site:
6 x 10-14 pCl/ml alpha, 3 x 10-11 pCi/mi beta, pCi/ml beta (055 onlyl 10 CFR 20 Appendix B CAC-17, and 00E Order 5480.1 Chapter XI.
b veraged result for 7-day (200 i=5l 55FL continuous air s,anpler, A
cNatural radioactivity contained in equivalent volume of air discharged through exhaust systems after filtration.
Note: All release points are at the stack exit.
0003Y/bjb
B.
FACILITY DESCRIPTIONS 1.
De Soto Site a.
Building 104--California State Licensed Activities Operations at Building 104 that may generate radioactive effluents con-sist of research studies in applied physics and physical chemistry.
Only atmospheric emissions are released from the building to uncontrolled areas.
Major quantities of radionuclides present in encapsulated form are limited to 60Co.
Small amounts of irradiated metallurgical samnles and depleted uranium are used for research purposes.
2.
Santa Susana Field Laboratories Site a.
Building 020--NRC and California State Licensed Activities Operations at Building 020 that may generate radioactive effluents con-sist of hot cell examination and decladding of irradiated nucle'ar fuels and examination of reactor components.
Only atmospheric emissions are released from the building to uncontrolled areas.
The discharge may contain particu-late msterial, as well as radioactive gases, depending on the operations being performed and the history of the irradiated fuel or other material.
No radio-l active liquid waste is released from the facility.
Radioactive material handled in unencapsulated form in this facility includes the following radio-nuclides:
Th, U, Pu, as constituents in the various fuel materials; and 85 I47 137Cs, 9037, Kr, and Pm as mixed fission products, b.
Buildings 021 and 022--00E Contract Activities Operations at Buildings 021 and 022 that may generate radioactive efflu-ents consist of the processing, packaging, and temporary storage of liquid and dry radioactive waste material for disposal.
Only atmospheric emissions are RI/RD86-140 47
released from the building to uncontrolled areas.
No radioactive liquid waste is released from the facility. Nuclear fuel material handled in encapsulated 137Cs, 90Sr, 85Kr, or unencapsulated form contains uranium and plutonium plus 147 and Pm as mixed fission products, c.
Building 055--NRC and California State Licensed Activities i
j Operations at Building 055 that may generate radioactive effluents con-sist of decommissioning and decontamination of the facility and equipment pending release for unrestricted use. Only atmospheric emissions are released from the facility to uncontrolled areas.
No radioactive liquid waste is released from the facility.
The various fuel materials that have been used at the facility (depleted and enriched uranium and plutonium) contained the following radionuclides:
U i
238 239 240 241 plus Pu, Pu, Pu, and Am.
No irradiated fuel materials have been processed at the facility.
C.
ESTIMATION OF GENERAL POPULATION DOSE ATTRIBUTABLE TO NUCLEAR OPERATIONS--1985
]
The Los Angeles basin is a semiarid region whose climate is controlled primarily by the semipermanent Pacific high-pressure cell that extends from l
Hawaii to the southern California coast. The seasonal changes in the position of this cell greatly influence the weather conditions in this area.
During the summer months, the high-pressure cell is displaced to the north.
This results in mostly clear skies with little precipitation.
During the winter, the cell moves sufficiently southward to allow some Pacific lows with their associated frontal systems to move into the area.
This produces light to moderate precipitation with northerly and northwesterly winds.
The release of airborne material at-the De Soto site for sunner season weather conditions would generally be under a subsidence inversion into an I
l RI/RD86-140
.I 48
l i,
atmosphere that is typical of slight neutral to lapse conditions.
Nocturnal cooling inversions, although present, are relatively shallow in extent.
Dur-i l
ing the summer, a subsidence inversion is present almost every day.
The base t
and top of this inversion usually lie below the elevation of the SSFL site.
Thus, any atmospheric release from the SSFL site under this condition would result in Pasquill Type D lofting diffusion conditions above the inversion and considerable atmospheric dispersion, prior to any diffusion through the inver-sion into the Simi or San Fernando Valleys.
In the winter season, the Pacific j
l high-pressure cell shifts to the south and the subsidence inversion is usually t
absent.
The surface airflow is then dominated by frontal activity moving easterly through the area, resulting in high-pressure ' systems in the great l
basin region. Frontal passages through the area during winter are generally I
accompanied by rainfall.
Diffusion characteristics are highly variable de-
{
pending on the location of the front.
Generally, a light to moderate south-westerly wind precedes these frontal passages, introducing a strong onshore flow of marine air and producing lapse rates that are slightly unstable.
Wind speeds increase as the frontal systems approach, enhancing diffusion.
The diffusion characteristics of the frontal passage are lapse conditions with l.
light to moderate northerly winds.
Locally, average wind speeds for the var-j ious stability categories range from 0 to about 4.4 m/s with the greatest fre-l quency occurring for winds from the north to northwest sectors.
Local popula-tion distribution estimates projected for 1986, based on the 1980 federal cen-sus and on direct observation of nearby residences, for areas surrounding the SSFL site and out to 80 km for 16 sectors are shown in Figures 9 through 11.
The downwind con:entration of radioactive material emissions to the l
atmosphere during 1985 from each of the three major Rocketdyne nuclear facil-ities has been calculated with the AIRDOS-EPA computer code using site-spe-cific input data including local area windspeed, directional frequency, and stability plus facility-specific data such as stack heights and exhaust air velocity.
l RI/RD86-140 49
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/
HILLS f'
sW2 100 p'
ONICA MOUNTAINS SCALE 0
1 2
3 4
5 utLES 0 1 2 3 4 5 6 7 8 KILOMETERS D43024
)
Figure 10. Santa Susana Field Laboratories Site Centered Demography to 16 km Distance RI/RD86-140 51
e e
105
,g
,- v g.
M.
/#1 948
' r, 714 258 6200 N'
21772 4036o 19322 9
8 86 N
12424 -
65091 8962 267834 Q-Jw-:
s
~
28731 96738 594648 41575
\\
7 rpy.9 1264 80255 1
7 i
8277 l
4808 e'
5155 a* t 18m 164108.A e,
\\..
l 4, sig 6
I
'k
$$1152F r pf PACIFIC OCEAN w
,.'a 7g
-a p
g
. 1, 4'
N.
s SCALE o
to to 30 40 so wiles o
to to so 40 50 so 70 80 MILOMETERS D4302-9 Figure 11. Santa Susana Field Laboratories Site Centered Demography to 80 km Distance (heavily populated areas are shown by shading)
RI/RD86-14O 52 l
i L.---.
t To determine the maximum possible radioactivity concentrations at the site boundary location nearest to each release point and at the nearest resi-dence, a mean wind speed of 2.2 m/s for each stability class was assumed and used to evaluate the plume centerline (maximum) concentrations toward the sec-tor in which those locations lie.
The 80-km concentration was calculated for the greatest wind frequency, which is toward a northerly direction.
The con-centration estimates are shown in Table 13, and both internal 'and external radiation dose estimates are shown in Table 14.
The internal dose calcula-tions in Table 14 assume a constant unsheltered exposure, adjusted for wind direction frequency, throughout the year and therefore considerably overestimate the actual annual-averaged doses at the nearest boundary and nearest residence.
The external dose calculations assume that differences in TLD readings represent true differences in local exposure.
These differences are extrapolated to the boundary and nearest residence using an inverse square distance relation from an assumed source of radiation.
TABLE 13 MAXIMUM DOWNWIND PLUME CENTERLINE CONCENTRATIONS OF ATMOSPHERIC EMISSIONS--1985 Downwind Concentation Release Distance (m) to (10-15 pCi/ml)a Rate Facility (Ci/ year)
Boundary Residence Boundary Residence 80 km B/104 6.0 x 10-7 200 W 315 SW 0.0021 0.002 0.000013 B/020 9.0 x 10-5 305 NW 1900 SE 0.13 0.066 0.0022 B/022 9.0 x 10-6 350 NW 2300 SE 0.005 0.0037 0.0002 B/055 1.6 x 10-6 400 NW 1830 SE 0.00016 0.000052 0.0000013 aAssume II = 2.2 m/s average wind speed, wind direction averaged for full year.
RI/RD86-140 53 4
l l
TABLE 14 EXPOSURE TO THE PUBLIC IN THE VICINITY OF ROCKETDYNE FACILITIES--1985 (rem)
De Soto Building 104 SSFL-1/020 (RIHL)
SSFL-T/021-022 (RMDF)
SSFL-T/055 (NMDF)
Air Pathway Organ Boundary Residence Boundary Residence Boundary Residence Boundary Residence Gonads 3.5 x 10-12 1.1 x 10-12 0
0 0
0 0
0 Breast 2.2 x 10-12 6.8 x 10-13 0
0 0
o o
o Red bone nuirrow 1.8 x 10-12 5.4 x 10-13 2.9 x 10 8 1.0 x 10-8 1.0 x 10-9 5.3 x 10-10 3.9 x 10-9 8.7 x 10-10 Lungs 3.9 x 10-8 1.2 x 10-8 6.8 x 10-8 2.3 x 10-8 2.0 x 10-9 1.1 x 10-9 1.7 x 10-8 3.7 x 10-9 Thyroid 0
0 0
0 0
0 0
0 Bone surfaces 0
0 5.7 x 10-8 2.0 x 10-8 1.9 x 10-9 9.8 x 10-10 1.2 x 10-8
- 2. 7 x 10-9 Liver 1.9 x 10-12 5.7 x 10-13 2.3 x 10-8 7.9 x 10-9 7.5 x 10-10 3.8 x 10-10 5.7 e 10-9 1.3 x 10-9 Kidney 0
0 0
0 0
0 0
0 3
Spleen 0
0 0
0 0
0 0
0 N
Thymus 0
0 0
0 0
0 0
0 g
Adrenals 0
0 0
0 0
0 0
0 oo Pancreas 0
0 0
0 0
0 0
0 i
Stomach 0
0 0
0 0
0 0
0 Small intestine 0
0 0
0 0
0 0
0 ULI + LLI O
O O
O O
O O
O Remainder 0
0 0
0 0
0 0
0 50-yr connitted whole body dose equivalent 3.9 x 10-8 1.2 x 10-8 1.8 x 10-7 6.1 x 10-8 5.7 x 10-9 3.0 x 10-9 3.9 x 10-8 8.6 x 10-9 Other pathways 0
0 0
0 0
0 0
0 External direct Total exposure - rem 4 x 10 5 1 x 10-5 4 x 10 3 1 x 10-4 8 x 10-2 1 x 10-4 0
0 whole body - rea 4 x 10 3 1 x 10-5 3
3 SI equivalent-SV 4 x 10-1 x 10-7 4 x 10 5 1 x 10 6 8 x 10-2 1 x 10 6 3.9 x 10-8 8.6 x 10-9 4
4 4 x 10-1 x 10-8 x 10-4 1 x 10-3.9 x 10-10 8.6 x 10-II 0003Y/emh I
1 The general population person-rem dose estimates are calculated from the j
demographic distribution and the sector total inhalation intake (person-pC1/
{
year) generated by AIRDOS-EPA, which uses release rate, wind speed, wind di-rection and frequency, inversion, lapse, and effective stack height parameters as input data.
Population dose estimates centered on the SSFL site are pre-sented in Table 15.
Inhalation is the only significant exposure pathway like-4 ly to exist, with the lung the critical organ for Pu, and bone for Sr.
The 1
doses reported for SSFL site emissions are sumed for all release points and nuclides.
i j
The estimated off-site doses are extremely low compared to the maximum permissible exposures recommended for the general population in the vicinity 1
of DOE facilities.
The effective dose equivalent for any member of the
)
public, for all pathways, shall not exceed 500 mres/ year for occasional exposures, and 100 mres/ year for prolonged periods of exposure.
For the air
)
pathway only, the limits are 25 mres/ year for whole body dose, and l-75 mrem / year for any organ.
The maximum estimated internal and external i
exposures to an individual for 1985 at the De Soto and SSFL site boundaries
),
and also at the nearest residence are shown in Table 14.
Estimated internal l
radiation doses due to atmospheric emission of radioactive materials from j
De Soto and the SSFL nuclear facilities are several orders of magnitude below the radiation standards and are far below doses due to internal exposure to i
natural radioactivity in air.
)
l The external exposures, above background, are based on the greatest exposure adjusted to a constant altitude (1000 ft ASL) measured by a single dosimeter compared with average adjusted off-site measurements.
The mean adjusted value for five off-site dosimeters was 105 mrem'with a maximum i
l observed value of 114 mrem.
Boundary dose estimates assume 100% occupancy, f
whereas the actual presence of persons at the boundary is rare or nonexist-ent. Review of the data indicates that these derived values, except for the RM0F, are not statistically different from Zero, as shown by the uncertainties j.
being near the reported value, but result from assumptions in the analysis.
\\*
RI/RD86-140 i
55 l
l'
i.'
TABLE 15 POPULATION DOSE ESTIMATES FOR ATMOSPHERIC EMISSIONS FROM SSFL FACILITIES--1985 Dose to Receptor Population Segment (person-rem) 22.5*
Sector 0-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total N
4.6 x 10 1.1 x 10 1.0 x 10 1.8 x 10" 2.0 x 10 1.7 x 10~
5.8 x 10 NNW 2.8 x 10 4.8 x 10 4.5 x 10 0
0 2.5 x 10 2.9 x 10
~
NW 5.7 x 10 0
2.7 x 10' O
3.7 x 10 8.0 x 10 6.0 x 10
~
WNW 8.2 x 10 4.8 x 10' 6.0 x 10~
5.3 x 10~
6.0 x 10~
0 1.0 x 10 W
0 4.4 x 10~
1.4 x 10 2.2 x 10 8.0 x 10~
0 4.8 x 10 WSW 9.5 x 10~
1.9 x 10 1.5 x 10 2.1 x 10~
3.9 x 10 0
3.7 x 10 SW 7.8 x 10 6.9 x 10~
2.1 x 10 0
0 0
7.2 x 10~
~
SSW 6.4 x 10 4.(s x 10 1.5 x 10~
0 0
0 1.3 x 10~
~
~
5 4.6 x 10~
9.8 x 10 2.0 x 10~
0 0
0 1.2 x 10 SSE 8.0 x 10 9.6 x 10~
2.2 x 10~
0 0
0 1.0 x 10 SE 2.3 x 10 1.7 x 10 3.4 x 10 4.5 x 10 1.0 x 10~
3.2 x 10 2.3 x 10~
ESE 1.4 x 10 3.7 x 10 4.6 x 10 2.6 x 10 1.8 x 10~
1.2 x 10~
6.3 x 10~
~
E 1.0 x 10 5.6 x 10 9.1 x 10 7.6 x 10 7.3 x 10 4.9 x 10 3.6 x 10~
ENE 1.8 x 10~
1.6 x 10 4.0 x 10 5.2 x 10' 6.2 x 10 '
7.6 x 10" 6.3 x 10
~
~
~
~
NE 1.1 x 10 1.6 x 10 5.9 x 10~
1.5 x 10 5.1 x 10 5.1 x 10~
1.4 x 10 NNE 2.4 x 10 2.4 x 10" 1.2 x 10 1.8 x 10' 5.8 x 10 2.7 x 10~
4.1 x 10
~
Total 2.8 x 10~
1.8 x 10~
2.8 x 10' 3.9 x 10~
3.7 x 10 2.1 x 10'
. 0.017 Average individual dose = 2.1 x 10"' rem for the 80-km radius area total population.
RI/RD86-140 56
APPENDIX A COMPARIS0N OF ENVIRONMENTAL RADI0 ACTIVITY DATA FOR 1985 WITH PREVIOUS YEARS This section compares environmental monitoring results for the calendar year 1985 with previous annual data.
The data presented in Tables A-1 through A-5 sunnarize past annual aver-age radioactivity concentrations.
These data show the effects of both the short-lived and long-lived radioactive fallout from nuclear weapons tests superimposed on the natural radioactivity inherent in the various sample types.
Over the considerable period of time that the environmental program has been in operation, evolutionary changes have been made in order to provide more effective data.
In some cases, this is readily apparent in the data.
For example, in Table A-1, a small but abrupt increase in the alpha activity reported for soil occurs in 1971.
This increase, which is observed in both the on-site and the off-site samples, resulted from use of an improved count-ing system with a thinner sample configuration.
The thinner sample increases the sensitivity of the detector to alpha-emitting radionuclides in the sample, thus producing a higher measured specific sample activity.
Similarly, prior to 1971, gross activity in ambient air was measured, including both alpha and beta activity.
In 1971, measurements were begun that allowed separate identification of these two types of radiation.
In 1984, recalibration of the alpha counting method for thick samples was achieved, resulting in determination of the absolute alpha activity in tnese samples rather than the relative values previously used for monitoring purposes.
Comparison of the values for 1985 as determined by the relative I
method with those for prior years shows no significant difference.
RI/RD86-140 57
The ambient radiation monitoring results show a continuing long-term variation that had been apparant in previous years but is unrelated to opera-tions on-site.
Independent measurements and intercomparisons support the values measured by the bulb-type dosimeters.
With the exception of apparent changes resulting from improvements.in analytical methods and interpretation of the data, the soil, vegetation, water, and air radioactivity results are notably constant over the past 20 years.
In particular, environmental radio-activity data for the De Soto site show no reduction in the measured levels below those that had been observed during'tne fuel fabrication operations that were discontinued in 1982 confirming that those levels represent natural radioactivity.
For all types of samples, the data indicate that there is no concentrated local source of unnatural radioactivity in the environment.
Also, the simi-larity between on-site and off-site results further indicates that Rocketdyne operations contribute essentially nothing to general environmental radio-activi ty.
RI/RD86-140 58
TABLE A-1 S0ll RADI0 ACTIVITY DATA--1966 THROUGH 1985 On-site Average Off-site Average (pC1/g)
(pCi/g)
Number of Number of Year Samples Alpha Beta Samples Alpha Beta a
1985 144 25.2 24 48 26.3 24 a
1984 144 25.8 24 48 26.2 23 1983 144 0.61 24 48 0.59 23 1982 144 0.69 25 48 0.68 23 1981 144 0.69 25 48 0.64 23 1980 144 0.60 24 48 0.58 23 1979 144 0.64 25 48 0.50 23 1978 144 0.63 24 48 0.51 24 1977 144 0.56 24 48 0.53 23 1976 144 0.56 25 48 0.56 24 1975 144 0.60 25 48 0.58 24 1974 144 0.60 25 48 0.54 24 1973 144 0.57 25 48 0.51 24 1972 144 0.56 25 48 0.57 24 1971 144 0.55 25 48 0.53 23 1970 144 0.47 27 48 0.48 25 1969 144 0.42 27 48 0.42 25 1968 144 0.47 26 48 0.48 26 1967 144 0.42 28 48 0.39 24 1966 144 0.41 29 48 0.44 25 aThe change in alpha activity after 1983 is the result of an improved calibration method that provides a true measure of alpha activity in thick samples rather than the relative values used previously. This l
is discussed in detail in Part III, Section A.
Values for 1985 using the prior method would be 0.63 for the on-site average and 0.66 for the off-site average.
l 0003Y/bjb RI/RD86-140 59
TABLE A-2
^
VEGETATION RADI0 ACTIVITY DATA--1966 THROUGH 1985 On-site Average Off-site Average 4
(pCi/g-ash)
(pCi/g-ash)
Number of Number of Year Samples Alpha Beta
. Samples Alpha Beta 8
1985 144 3.8 135 48 4.7 133 8
1984 144 4.0 136 48 5.9 136
^
1983 144 0.i 8 149 48 0.24 143 1982 144 0.16 140 48 0.17 130 1981 144 0.20 137 48 0.21 129 l
1980 144 0.25 160 48 0.19 142 1979 144 0.24 139 48 0.23 1.34 l
1978 144 0.24 166 48 0.24 143 l
1977 144 0.22 162 48 0.-21 142 1976 144 0.19 170 48 0.22 147 j
1975 144 0.21 155 48 0.21 141 1974 144 0.20 152 48 0.27 1 41 l
1973 144 0.24 155 48 0.24 142 i
1972 144 0.23 145 48 0.36 125 f
1971 144 0.24 165 48 0.31 132 f
1970 144 0.33 159 48 0.30 142 1
1969 144 U.40 165 48 0.36 144 1968 144 0.51 158 48 0.51 205 l
1967 144 0.62-286 48 0.39 413 1966 144 0.37 169 48 0.37 123 i
The change in alpha activity after 1983 is the result of an improved i
a calibration method that provides a true measure of alpha activity in i
thick samples rather than the relative values used previously. This is discussed in detail in Part III, Section A.
Values for 1985 using the prior method would be 0.19 for the on-site average and i
0.23 for the off-site average.
l 0003Y/bjb RI/RD86-140 i
60
TABLE A-3 SSFL SITE SUPPLY WATER RADI0 ACTIVITY DATA--
1966 THROUGH 1985.
~
Number of Average Alpha Average Beta Year Samples (10-9 pCi/ml)
(10-9 pCi/ml) a 1985 24-2.05 2.8 1984 24 3.53 2.9 8
1983 24 0.12 3.0 1982 24 0.14 3.0 1981 24 0.24 2.8 i
1980 24 0.22 2.4 1979 24 0.23 2.8 i
1978 24 0.26 3.0 1977 24 0.25 2.5 1976 24 0.25 2.0 1975 24 0.24 2.3 f
1974 24 0.24 2.7 1973 24 0.26 3.4 1972 24 0.22 3.7 1 971 24 0.28 4.9 1970 24 0.18 5.3 l
1969 24 0.11 5.0 I
1968 24 0.16 5.0 i
i 1967 24 0.13 6.1 1966 24 0.13 4.6 i
1 aThe chan9e in alpha activity after 1983 is the result of an improved calibration method that provides a true
. 4 measure of alpha activity in thick samples rather than the relative values used previously. This is discussed in detail in Part III, Section A.
The value for 1985 using the prior method would be 0.09.
i 0003Y/sjv RI/RD86-140 61
.,,.e
,-e..
--,,p
.-+,,,,
,,e.
,,.,n.
,-s--.-
TABLE A-4 Sell. CREEK AND RDCKETDYNE O! VISION RETENTION PONO RADIDACTIVITY DATA-1966 THROUGH 1985 Samples Interim Retention Final Retention Pond Bell Creek Mud Bell Creek Vegetation Bell Creek Water Pond Water R-2A Water 54 54 16 6
12 (Thp[/ml)
(ih"p[/ml) h Mr (p
h) thsdwr hr hr (10 pc /ml) hr of of of of of Year Samples Alpha Beta Samples Alpha 8 eta Samples Alpha Beta Samples Alpha Beta Samples Alpha Beta 1985a 12 21.9 23 12 1.34 137 12 1.38 2.5 12 2.06 3.5 12 3.07 3.5 1984a 12 20.8 24 12 1.70 138 12 4.15 2.9 12 2.07 4.6 12 U.15 4.2 l
1983 12 0.54 23 12 0.12 136 12 0.08 3.3 12 0.12 3.6 12 0.13 4.4 1982 12 0.64 25 12 0.00 160 12 0.03 3.3 12 0.17 3.9 12 0.11 3.9 3
1981 12 0.58 24 12
<0.13 103 12
<0.23 3.8 12
<0.23 4.3 12
<0.25 5.2 i
N 1980-12 0.51 23 12
<0.18 150 12
<0.22 2.9 12
<0.22 2.9 12
<0.22 3.9 E
1979 12 0.46 23 12
<0.26 136 12
<0.23 3.2 12
<0.25 3.1 12
<0.23 4.5 m
N m
1978 12 0.42 23 12
<0.26 156 12
<0.24 2.5 12
<0.25 4.3 12
<0.25 4.6 1977 12 0.29 22 12
<0.19 155 12
<0.24 1.8 12
<0.24 4.3 12
<0.25 5.2 1976 12 0.38 23 12
<0.17 164 12
<0.25 2.2 12
<0.24 4.3 12
<0.28 4.4 1975 12 0.29 22 12
<0.19 123 12
<0.22 2.4 12
<0.24 4.2 12
<0.31 4.5 i
1974 12 0.32 22 12
<0.16 142 12
<0.21 2.5 12
<0.22 4.2 12
<0.21 4.5 1973 12 0.34 24 12
<0.17 147 12
<0.21 2.7 12
<0.23 4.5 12
<0.37 5.6 1972 12 0.32 22 12 0.12 139 12 0.20 2.5 12 3.22 5.3 12 0.22 5.5 1971 12 0.36 23 12 0.19 128 12 0.15 3.8 12 0.18 6.2 12 0.16 6.4 1970 12 0.44 24 12 0.23 165 12 0.15 3.7 12 0.15 6.9 12 0.12 7.4 1%9 12 0.35 27 12 0.28 166 12 0.04 4.0 12 0.07 5.9 11 0.10 5.7 1968 11 0.32 24 11 0.39 170 0
0.05 4.6 11 0.23 8.1 12 0.33 7.7 1967 12 0.40 24 12 0.38 ISO 12 0.07 5.8 12 0.19 6.6 10 0.17 7.0 1966 3
0.39 25 3
1.1 108 3
0.75 2.5 9
0.11 5.8 8
1.1 6.3 The change in alpha activity after 1983 is the result of an improved calibration method that provides a true measure of alpha activity in thick samples rather than the relative values used previously. This is discussed in detail in Part Ill, j
Section A.
Values for 1995 using the prior method would be as follows:
Bell Creek aud:
0.55 Interim retention pond: 0.09
~
Bell Creek vegetation: 0.07 Final retention pond:
0.15 Bell Creek water:
0.03
i l.
l TABLE A-5
. AMBIENT AIR RADI0 ACTIVITY CONCENTRATION DATA--1966 THROUGH 1985 DeSotogiteAverage SSFL S: le Average (10-l uCi/ml)
.(10- Z pCi/ml)
Number of Number of Year Samples Alpha Beta Samples Alpha Beta 1985 544 0.0026 0.044 2450 0.0020 0.040 1984 712 0.0019 0.027 2461 0.0014 0.024 l
1983 644 0.0024 0.026 2328 0.0010 0.023 j
1982 727 0.0017 0.026 2347 0.0013 0.022 l
1981 704 0.0069 0.12 2518 0.0068 0.12 j
1980 685 0.0065 0.039 2342 0.0064 0.035 f
1979 697 0.0066 0.021 2519 0.0065 0.020 j
1978 71 3 0.0084 0.091 2402 0.0072 0.088 1977 729 0.0066 0.17 2433 0.0066 0.17
/
1976 71 9 0.0067 0.096 2520 0.0065 0.11
'~
1975 709 0.0063 0.076 2450 0.0060 0.073 1974 663 0.0056 0.16 2477 0.0057 0.16 1973 71 5 0.0075 0.041 2311 0.0072 0.038 l
1972 708 0.0085 0.14 2430 0.0086 0.14 a
1971 730 0.0087 0.30 2476 0.0086 0.33 0.36 0.34 2434 1970 668 1969 687 0.26 0.27 2364 b
1%8 6b0 0.32 0.32 2157 i
0.41 0.39 2400 1967 712 0.17 0.18 2205 1966 706 1
aAmbient air alpha radioactivity values were ir.cluded in the beta j
values and not reported separately prior to 1971, i
1 i
)
j.
0003Y/sjv l
RI/RD66-140
- l~
63
APPENDIX B ENVIRONMENTAL MONITORING PROGRAM QUALITY CONTROL This appendix describes the quality assurance (QA) elements that are incorporated into the Rocketdyne program to ensure that data produced are as meaningful as possible.
PROCEDURES Procedures followed include sample selection; sampic collection; packag-ing, shipment and bandling of samples for off-site analysis; preparing and analyzing samples; using radioactive reference standards; calibration meth-ods and instrument QA; and evaluating and reporting data.
RECORDS Records generally cover the following processes:
field sample collec-tion and laboratory identification coding; sample preparation method; radio-activity measurements (counting) of samples, instrument backgrounds, and ana-lytical blanks; and data reduction and verification.
Quality control records for laboratory counting systems include the results of measurements of radioactive check sources, calibration sources, backgrounds, and blanks, as well as a complete record of all maintenance and service.
Records relating to overall laboratory performance include the results of analysis of quality control samples such as analytical duplicates, inter-laboratory cross-check samples and other quality control analyses; use of standard (radioactive) reference materials to prepare working standards; and calioration of analytical balances.
l it RI/R086-140 65
The following specific elements of quality control are used for the Rocketdyne program:
1)
Reagent Quality--Reagent-grade chemicals and certified grade counting gas used.
2)
Laboratory Ventilation--Room air supply is controlled to mini-mize temperature variance and dust incursion.
3)
Laboratory Contamination--Periodic laboratory contamination surveys for fixed and removable surface contamination are per-formed.
Areas are cleaned routinely ard decontaminated when necessary.
4)
Control Charts--Background and reference source control charts for counting equipment are maintained to evaluate stability and response characteristics.
5)
Laboratory Intercomparisons--Rockwell participates in the DOE-EML-QAP, and also participates in the DOE Environmental Dosim-eter Intercomparison Project.
6)
Duplicate Samples--Duplicate samples are obtained monthly at randamly selected environmental sampling locations.
Analytical data are statistically evaluated to determine the correlation coefficients for each media type for the annual sample set.
7)
Calibration Standards--Counting standard radioactivity values are traceable to the National Bureau of Standards primary standards.
RI/RD86-140 66
APPENDIX C CALIFORNIA REGIONAL WATER QUALITY CONTROL BOARD CRITERIA FOR DISCHARGING NONRADI0 ACTIVE CONSTITUENTS FROM ROCKETDYNE DIVISION, SSFL The discharge of an effluent in excess of the limits given in Table C-1 is prohibited.
TABLE C-1 NPDES NO. CA00-01309, ORDER 84-85, EFFECTIVE 17 SEPTEMBER 1984 Discharge Rate Concentration Limit (1b/ day)*
(mg/ liter) 30-Day Constituent Average Maximum Total dissolved solids 1,267,680 950 Chloride 200,160 150 Sulfate 400,320 300 a
Suspended solids 66,720 Settleable solids" B00 26,690 30 5
l Oil and grease 13,350 15 Chromium 6.67 Fluoride 1,340 1.0 Boron 1,340 1.0 0.1 Residual chlorine 3
2.2 Fecal coliform (MPN/100 ml)
Surfactants (as MBAS) 667 0.5 pH 6.0 to 9.0 aNot applicable to discharges containing rainfall runoff during or imediately after periods of rainfall.
b Wastewater shall be considered adequately disinfected if the median number of coliform organisms does not exceed 23/100 ml.
- Based on a total waste flow of 160 x 106 gal / day.
l 1
RI/RD86-140 67 1
APPENDIX D REFERENCES 1.
DOE Order 5484.1 2.
DOE Order 5480.1 A 3.
Code of Federal Regulatio'ns, Title 10, Part 20 (10 CFR 20) 3 4.
California Radiation Control Regulations, California Administrative Code, Title 17, Public Health 5.
California Regional Water Quality Control Board, Los Angeles Region, Order No. 84-85, NPDES No. CA0001309, Effective 17 September 1984 6.
R.
E.
Moore, 1979.
AIRDOS-EPA:
A Computerized Methodology for Estimating Environmental Concentrations and Doses to Man from Airborne Releases of Radionuclides, ORNL-5532 7.
D. E. Dunning, Jr.,1981.
Estimates of Internal Dose Equivalent to 22 Target Organs for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, Volume III, ORNL/NUREG/TM-190
~.
8.
J. P. Corley, ed., " Committed Dose Equivalent Tables for U.S. Department of Energy Population Dose Calculations," U.S. Department of Energy, Office of Operational Safety 9.
J. D.
- Moore,
" Radiological Environmental Monitoring Program,"
N00105P000001, Rocketdyne Division, fockwell International (9 July 1984) 10.
J. D. floore, " Radiological Environmental Monitoring Program Sampling Procedures, Aralysis Procedures, and Radioactivity Measurement Methods,"
N001DWP000008, Rockwell International, Rocketdyne Division (9 July 1984) 11.
J. D. Moore, " Radiological Environmental Mor)ltoring Program Quality Assurance," N001DWP000009, Rocketdyne Division, Rockwell International (25 September 1984) 12.
" Investigation of Hydrogeologic Conditions - Santa Susana Field Labora-tory, Ventura County, California,". Hargis & e Associates, Inc., Tucson, Arizona (22 February 1985)
~
RI/RD86-140 69
APPENDIX E EXTERNAL DISTRIBUTION 1.
Radiologic Health Branch, Department of Health Services, California 2.
Occupational Health and Radiation Management, Los Angeles County Health Department, California 3.
Resources Management Agency, County of Ventura, California 4.
U.S. Nuclear Regulatory Commission, Region V, Walnut Creek, California 5.
U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, Washington, D.C.
6.
U.S. Department of Energy, Environment, Safety and Quality Assurance Divi-sion, San Francisco Operations Office, California 7.
U.S. Department of Energy, Office of Operational Safety, EP-32, Technical Information Center, Washington, D.C.
8.
Rocky Flats Plant, Health, Safety, and Environment, Colorado 9.
Rockwell Hanford Operations, Safety and Quality Assurance, Washington
'O RI/RD86-140 71
i e
APPENDIX F ALTERNATIVE UNITS FOR RADIOLOGICAL DATA Conversion In Non-SI In SI Factor From Units Units Non-SI to SI Unitsa Activity concentrations
( Environmental)
Airborne particulates and gas pCi/m3 8q/m3 3.70E - 02 Liquids (water, milk, etc.)
pCi/L Sq/L 3.70E - 02 Solids (soil, sediment, vegetation, foodstuff, etc.)
pCi/g Bq/kg 3.70E - 05 Activity concentrations (effluent)
Gas (air)
(pCi/mL)b Bq/m3 3.70E + 10 Liquid (pCi/mL)b Bq/L 3.70E + 07 Exposure rate (environment)
R/h C/kg h 2.58E - 10 Absorbed dose mrad Gy 1.00E - 05 Dose equivalent mrem Sv 1.00E - 05 Dose equivalent rate (comitment) mrem / year Sv/ year 1.00E - 05 aTo convert non-SI units to SI units, multiply the non-SI units by the conversion factor, bAdopted because of established convention and use in maximum permissible concentration (MPC) tabulations.
~
1 0003Y/bjb
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