ML20236E505
| ML20236E505 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 03/31/1988 |
| From: | Tuttle R ROCKWELL INTERNATIONAL CORP. |
| To: | |
| Shared Package | |
| ML19311A788 | List: |
| References | |
| RI-RD88-144, NUDOCS 8906050296 | |
| Download: ML20236E505 (78) | |
Text
.
t Rl/RD86-144 APPENDIX B TO RI/RD 88144 EM 35 ROCKETDYNE DIVISION ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT DE SOTO AND SANTA SUSANA FIELD LABORATORIES SITES 1987 RockwellInternational u
Rocketdyne Division 6633 Canoga Avenue 8906050296 890525
Canoga Park, CA, U.S.A. 91303 PDR ADOCK 070000?S B
PDP
Rl/RD88-144 3
O ROCKETDYNE DIVISION ENVIRONMENTAL MONITORING j
AND FACILITY EFFLUENT ANNUAL REPORT DE SOTO AND SANTA SUSANA FIELD LABORATORIES SITES 1987 By J. D. Moore x
O APPROVED:
(
Q R. J7TUTTLE Manager Radiation and Nuclear Safety RockwellInternational Rocketdyne Division Cano a Par. Cal 10 nia 01303 o
ISSUED: March 1988
1 CONTENTS j
Page f
3' I.
Introduction......................................................
1 II. Summary'and Evaluation of Environmental Monitoring Results........
11 III.
Environmental Monitoring Results..................................
15 o
A.
Rad i oa ct i ve Ma te ri a l s --19 87...................................
15 8.
Nonradioacti ve Mate rial s --19 87................................
31 IV.
Envi ronmental Moni to ri ng Prog ram..................................
33 A.
Description...................................................
33 B.
Sampling and Sample Preparation...............................
33 1.
5011......................................................
33 2.
Water......
42 3.
Ambient Air...............................................
43 C.
Counting and Calibration......................................
43 D.
Nonradioactive Materials......................................
45 V.
Effluent Monitoring Program.......................................
47 A.
Treatment and Handling........................................
47 8.
Facility Descriptions.........................................
49 1.
De Soto Site..............................................
49 O -
2.
Santa Susana Field Laboratories Si te......................
49 C.
Estimation of General Population Dose Attributable to R oc k e td yn e Ope ra t i o n s --19 8 7...................................
50 Appendices A.
Comparison of Environmental Radioactivity Data for 1987 with Previous Years...............................................
59 B.
Environmental Monitoring Program Quality Control..................
65 C.
California Regional Water Quality Control Board Criteria for Discharging Nonradioactive Constituents from Rocketdyne Division, SSFL.....................
67 D.
Bibliography......................................................
69 E.
External Distribution.............................................
71 F.
Alternative Units for Radiological Data...........................
73 0
RI/RL88-144 iii
TABLES Page
(
1.
Soil Radioactivity Data--1987.....................................
17 2.
Soil Plutonium Radioactivity Data--1987...........................
17 3.
Supply Water Radioactivity Data--1987.............................
19 4.
SSFL Site Retention Pond, Site Runoff, and Well Water Radioactivity Data................................................
21 5.
Ambi ent Ai r Rad ioac ti vity Data--1987................ -..............
26 6.
De Soto and SSFL Sites--Ambient Radiation Dosimetry Data--1987....
29 7.
Nonradioactive Constituents in Wastewater Discharged to Unc on t ro l l ed A rea s --19 87..........................................
32 8.
Sampl i ng Loc a t i on De s c ri pt i on.....................................
37 9.
Lower Limits of. Detection..........................
44 10.
Atmospheric Emissions to Uncontrolled Areas --1987.................
48 11.
Maximum Downwind Plume Centerline Concentrations of Atmo s ph e ri c Emi s s i on s --19 8 7.......................................
55 12.
Exposure to the Public in the Vicinity of Rocketdyne F a c i l i t i e s --1 9 8 7..................................................
56 c
13.
Population Dose Estimates for Atmospheric Emissions f rom SS F L F a c i l i t i e s --19 8 7.............................................
58 C
C e
RI/RD88-144 iv
m l
l FIGURES Page 1.
Rocketdyne Division--De Soto Site.................................
3 l
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...................................
6 l
l 5.
Weekly, Monthly, and Annual Averaged Long-Lived Airborne Radio-activity at the De Soto and Santa Susana Field Laboratories S i t e s -- 1 9 8 7.......................................................
28 6.
mcp of Canoga Park, Simi Valley, Agoura, and Calabasas Sampling Stations.................................................
34 7.
Map of De Soto Site and Vicinity Sampling Stations................
35 8.
Map of Santa Susana Field Laboratories Site Sampling Stations.....
36 9.
Santa Susana Field Laboratories Site-Centered Demography to 8 km Distance.....................................................
52 10.
Santa Susana Field Laboratories Site-Centered Demography to 16 km Distance...................................................
53 11.
Santa Susana Field Laboratories Site-Centered Demography to 80 km Distance....................................................
54 O
=
9 RI/RD88-144 v
I.
INTRODUCTION Environmental and facility ef fluent radioactivity monitoring at the Rocketdyne Division of Rockwell International is performed by the Radiation and Nuclear Safety Group of the Health, Safety, and Environment Department.
Soil and surf ace water are routinely sampled to a distance of 10 miles f rom Division sites.
Ground water f rom site supply water wells and other test wells is periodically sampled to measure radioactivity in these waters.
Con-tinuous ambient air sampling and direct radiation monitoring by thermolumines-cent dosimetry are performed at several on-site and off-site locations for measuring airborne radioactivity concentrations and site ambient radiation levels.
Radioactivity in effluents discharged to the atmosphere from nuclear f acilities is continually sampled and monitored to ensure that amounts re-leased to uncontrolled areas are below appropriate limits and to identify processes that may require additional engineering safeguards to minimize radioactivity in such discharges.
In addition, selected nonradioactive chemi-cal constituent concentrations in surf ace water discharged to uncontrolled n
areas are determined.
The environmental radioactivity reported herein is attribJted to natural sources and to residual f allout of radioactive material f rom past atmos-pheric 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.
In addition to a broad spectrum of conventional programs in rocket propulsion, utilization of space, and national defense, Rocketdyne is working on the de-sign, development, and testing of components and systems for central station nuclear power plants, the decladding of irradiated nuclear fuel, and the decontamination and decommissioning of facilities.
6 e
RI/RDB8-144 1
I b
The administrative and scientific research f acilities associated with the nuclear efforts are located at the De Soto site in Canoga Park, California (Figure 1), approximately 23 miles northwest of downtown Los Angeles.
The De Soto site is typical of the San Fernando Valley floor, at an altitude of 875 f t above sea level.
Nuclear research programs licensed by the State of Calif ornia are conducted here.
These include Building 104 Applied Nuclear Research laboratories and the Gamma Irradiation Facility containing approxi-60 I37 mately 35 kCi of Co and 570 kCi of Cs.
The Santa Susana Field Laboratories (SSFL) site (Figure 2) occupies 2,668 acres 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 sand-stone bedrock unit called the upper cretaceous Chatsworth formation. The site may be described 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 un-consolidated gravel, sand, silt, and clay.
Both Department of Energy (DOE) and Rocktell International owned f acilities, 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 ar.d the State are conducted.
The licensed facilities include (1) the Rockwell Inter-national Hut Laboratory (RIHL) (Building 020), (2) a former neutron radio-graphy f acility which contained the dismantled L-85 nuclear examination and research reactor (Building 093), the license for which was terminated in April l
1987, (3) several X-ray and radioisotope industrial radiography inspection l
facilities, and (4) a radiation instrument calibration laboratory.
The location of these sites in relation to nearby communities is shown in Figure t.
Much of the land surrounding the De Soto site 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 f arming at R1/RD88-144 2
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Map of General Los Angeles Area RI/RD88-144 6
the eastern boundary. At greater distances, residences and some light indus-tries become prevalent. Witnin 30 km of the SSFL site, there is no signifi-cant agricultural land 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 domes-tic water to the greater Los Angeles area.
The nearest of these is more than 16 km distant.
Included within the SSFL site is an 82-acre government-optioned area where DOE contract activities are conducted, primarily by the nonnuclear Energy Technology Engineering Center (ETEC).
The major operational nuclear installation within the DOE-optioned area is the Radioactive Naterial Disposal Facility (RMDF).
This facility is used for storage of irradiated fuel and for packaging radioactive wastes generated as a result of the decommissioning and fuel decladding operations.
Licensed programs conducted during 1987 included (1) the operation of the RIHL for nuclear reactor fuel decladding and reactor system component examination, and (2) the final dismantling of the L-85 nuclear examination and research reactor f acility.
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, f acility effluent releases and external radiation levels be reduced to a minimum.
The environmental monitoring program provides a measure of the effectiveness of safety procedures and of the engineering safeguards incorporated into facility designs. Specific radionuclides in facility ef fluent or environmental samples are not routinely identified because of the extremely low radioactivity levels normally detected, but they would be identified by analytical or radiochemist-try techniques if significantly increased radioactivity levels were observed.
Relatively few different radionuclides are involved in these operations.
RI/RD88-144 7
Occasional gamma-spectral analyses of bulk samples such as soil, water, and air sample collection filters confirm that the major radionuclides present are nurmally those of the naturally occurring thorium and uranium decay J
chains, plus other natural radionuclides such as the primordial K, and
)
7Be, produced by cosmic ray interactions in the atmosphere.
l In addition to environmental monitoring, work area air and' atmospheric effluents are continuously monitored or sampled, as appropriate.
This pro-vides a direct measure of the effectiveness of engineering controls and allows remedial action to be taken before a significant release of hazardous material can occur.
Environmental sampling stations located within the boundaries of the De Soto and SSFL Area IV sites are referred to as "on-site" stations; those located outside these boundaries, or relatively distant from any nuclear facilities, are referred to as "off-site" stations.
The De Soto and SSFL sites are sampled quarterly to determine the concentration of radioactivity in typical surface soil. Soil is also sampled on-site (SSFL) and..
site semi-annually for plutonium analysis. Similar off-site environmental samples, ex-cept for plutonium analysis, are also obtained quarterly. Water samples are obtained monthly at the De Soto and SSFL sites from supply uater uurcm, re-tentinn ponds, and also f rom deep and shallow wells on a seasonal frequency.
Continuous ambient air sampling provides information concerning long-lived airborne particulate radioactivity.
On-site ambient radiation monitoring using thermoluminescent dosimetry (TLD) measures environmental radiation levels at the De Soto and SSFL sites and also at several off-site locations.
Nonradioactive wastes discharged to uncontrolled areas are limited to liquids released to sanitary sewage systems and to surf ace water drainage sys-tems. No intentional releases of any liquid pollutants are made to uncon-trolled 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 boundary of the SSFL RI/RD88-144 8
- _ - _ _ =.
Jsite.
The surf ace water drainage system of SSFL, which is composed cf catch ponds and open drainage ditches, also ' drains to retention pond R-2A.
Water f rom the pond may be reclaimed as industrial process water or-released, as necessary, of f-site into Bell Creek, a tributary of the Los' Angeles River.
The pond' is sampled monthly for radioactivity 'and also sampled at discharge for both radioactive and nonradioactive pollutants as. required by the dis-charge ' permit issued to Rocketdyne Division by the California Regional Water ~
Quality Control Board.
In addition, an automatic water sampler takes samples from the discharge stream channel (Bell Creek) whenever water is present.
lhis report summarizes environmental monitoring results for 1987, which are' presented in Section III.
The gross alpha and beta radioactivity is re-ported as results of the monitoring program.
Estimates of radionuclides compo-nents in effluents provide the basis for dose commitment calculations.
The-sampling and analytical methods used in the environmental. monitoring program for radioactive materials are described in Section IV.
A comparison of 1987 radioactivity results with the results f rom previous years appears in Appen-dix A, with a ' summary. of the Environmental Monitoring Program Quality Control in Appendix B.
Appendix C shows regulatory limits on nonradioactive pollu-tants in water' released f rom the site.
References are listed in Appendix 0.
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.
W i
RI/RD88-144 9
i
\\
- 11.
SUMMARY
AND EVALUATION OF ENVIRONMENTAL MONITORING RESULTS i
Except as noted below, all radioactivity levels obse ved in environmental samples for 1987 show close agreement with radioactivity levels measured dur-ing recent years and reported in the previous issues of this report.
Local environmental radioactivity levels, which result f rom both natural and man-mac' radionuclides and have shown the presence of f allout f rom past atmo-scherir, testing of nuclear devices, and the Chernobyl reactor accident, have i
decreased to generally constant levels during the past several years.
These levels are now.We mainly to the primordial natural radionuclides.
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 l
off-site samples f urther indicate that there is no contribution to general environmental 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 radioactive materials for which the only exposure pathways to people result f rom whole body external exposure and f rom Inhalation exposure to released materials, and to direct radiation exposure of individuals and the general public beyond the site boundary. No discharge of liquid radioactive wastes is made to the environment.
All such materials are processed for disposal at regulated disposal sites.
The maximum individual annual exposures estimattd 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 were derived from the AIRDOS-EPA calculated concentrations at those locations and incorporated the dose conversion f actors appropriate for radionuclides in process at each nuclear f acility.
This inhalation exposure estimate is the
~
sum of contributions calculated for the measured releases from each facility.
Rl/RD88-144 11
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 f acility workplace radiation dosim-eters.
The unattenuated external annual exposure due to operations conducted at the RMDF is estimated to be 55 mR at the nearest boundary-line location and less than 0.1 mR for the nearest residence.
The boundary-line exposure is conservative in that the rugged terrain at the site boundary nearest the RMDF precludes anything core than the rare and temporary presence of any person at that location.
These values were determined by calculating the unattenuated exposure expected at the 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.
The topography of the SSFL site surrounding the nucicar f acilities and out to the site boundary is extremely irregular.
Hills and rock outcroppings shield tb? off-site areas, significantly reducing off-site exposures froa on-site creces.
Boundary-line direct radiation expo-sures for the State of California and U.S. NRC-licensed operations at other Rocketdyne nuclear f acilities were very much below 10 mR for the year.
Similarly for the De Soto site, internal dose estimates at the boundary and at the nearest residence are not significantly dif ferent from zero.
Esti-mates of the external radiation exposure at the De Soto boundary (less than 0.01 1 0.01 mR) and at the nearest residence (less than 0.01 10.01 mR) are based on the difference between the single highest on-site TLD measurement and the average of of f-site measurements.
The dif ference is more likely the result of random variability in the measurements than f rom actual radiation exposure.
Rl/RDB8-144 12
l l
Supply water at the SSFL site is sampled monthly at two locations. This water consists of ground water f rom deep wells on the site blended with potable water f rom the Ventura County Water District 17-.
In addition, shallow
[
ground water is periodically sampled at a standpipe adjacent to the basement 1
d level of a deactivated reactor test f acility (Building 059).
These samples are evaluated to detect any transfer of activation 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.
Deep well water samples are also evaluated to determine the impact, if eny, on the deep ground water system underlying the SSFL aue to Rocketdyne Division nuclear operations.
Quality assurance measures incorporated into the environmental monitoring program include participation in DOE-sponsored programs such as the 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 XXVI and XXVII), and in the DOE Environ-mental Dosimeter Mini-Intercomparison Project, was done in 1S87.
Analysis of the QAF results indicate tl.at accuracy in measuring radioactivity in the sample 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 ass:ssment program.
In addition to participation in these programs, laboratorf 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 niaintained.
These data are periodically evaluated to determine the correlation between sample sets and trends in background.
e RI/RDBB-144 13
III.
ENVIRONMENTAL MONITORING RESULTS A.
RADIOACTIVE MATERI ALS--1987 The average radioactivity concentrations in local soil, surf ace and ground water, and ambient air for 1987 are presented in Tables 1 through 5.
The data shown for gross alpha activity in samples that are generally thick compared to the range of the alpha particles represent a marked change in the manner of calculating and reporting them, compared with earlier reports. This change reflects the gradual redirection of the monitoring program from monitor-ing to measurement.
Previously, alpha count data had been converted to alpha activity concentrations by using an ef ficiency factor for a thin electroplated source, and the results were monitored f or changes f rom prior values.
This resulted in artificially low numerical values for the alpha activity in sever-al sample media.
Starting with the 1984 report, the alpha activity concentra-tions f or these media are reported based on an ef ficiency f actor derived f rom a sample with distributed alpha activity that is thick relative to the alpha particle range.
For monitoring parposes, this has no ef fect.
However, the values reported more closely represent the actual alpha activity existing in the environment.
In calculating the average concentration values, all values, including negative values, are included.
This method of noncensored data averaging, recommended by DOE Order 5484.1, af fords a better estimate of the central value and dispersion of the data.
All limits of error reported in the tables are for one standard deviatior, (1 sigma).
Usually, these show the dis-persion of the measured values about the mean.
These two changes in data in-terpretation result in noticeable dif ferences in the data shown in the histor-ical comparisons.
It must be recognized that these differences do not reflect changes in environmental radioactivity but are merely cr nsequences of the a
evolution of the nionitoring 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 f rom the annual set, which is reported because of its signif-icance in indicating the occurrence of a major episode or an area-wide inci-
~
dent of radioactive material deposition.
Except for soil, supply water, and RI/RD88-144 15 L
air samples, none of the maximu:.1 observed values, which (as the tables show) generally occurred randomly during the year, show a great increase over the j
annually averaged values beyond inherent variability.
Except for March, the ambient air sampling data show no greatly increasing or decreasing trends for j
the year and can be described as generally constant, with some increase in airborne radioactivity occurring during the third and fourth quarters.
To achieve much higher detection sensitivity for plutonium than gross alpha measurements can provide, soil samples are collected and sent to an independent testing laboratory for specific analysis for plutonium.
In this analysis, the individual soil samples are leached with acid, and the leachate is treated chemically to separate and concentrate any plutonium present in the sample.
In this way, minute quantities of plutonium, such as those distrib-uted globally by testing of nuclear weapons, can be detected and quantita-tively measured by alpha spectroscopy.
The results are shown in Table 2.
239Pu + 240Pu, predominantly Alpha spectroscopy permits identification of 38 f rom weapons. tests, and Pu, partly f rom the destructive reentry of a Transit satellite o/er the Indian Ocean in April 1964.
The results of the gross radioactivity measurements in soil (Table 1) show no significant difference between on-site and off-site samples.
For comparison with the plutonium present as a result of fallout f rom nuclear weapons tests and f ailure 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 0.002 pCi/g for Pu &
240 238 Pu and approximately 0.00006 pCi/g for Pu.
The data in Table 2 show i
no significant increases in on-site soil plutonium relative to the Burbank i
values and no significant variation in soil plutonium concentrations for the 1987 sample sets.
RI/R088-144 16
TABLE 1 S0ll RADI0 ACTIVITY DATA--1987 Gross Radioactivity (pCi/g)
Number Maximumgbserved of Annual Average Value Value and Area Activity Samples and Dispersion Month Observ(d On-site Alpha 48 27.1 2 7.7 40.1 (quarterly)
(December)
Beta 48 25.4 + 2.1 30.7
~
(April)
Off-site Alpha 48 25.7 + 7.7 55.1 (quarterly)
~
(April)
Beta 48 23.9 + 3.5 29.1
~
(April) l mud No. 55
~
33.1 Pond R-2A Alphi 4
24.1 + 6.4 i
(April)
~
25.0 Beta 4
23.6 + 1.2 (April)
Bell Creek Alpha 4
24.9 1 7.7 34.0 upper stream (January) bed soil Beta 4
24.0 + 0.8 25.2 No. 62 l
~
(April) aMaximum value observed for single sample.
TABLE 2 50ll PLUTONIUM RADIOACTIVITY DATA--1987 22 June 1987 Survey Results 7 December 1987 Survey Results 238 239Pu + 240Pu 238 239Pu + 240Pu Pu Sample Pu Location (pCi/g)
(pCi/g)
(pCi/g)
(pCi/g)
S-56 0
i 0.0001 0.0006 1 0.0002 0.0006 1 0.0002 0.0018 i 0.0003 S-57 0.00L1 0.0001 0.0012 1 0.0003 0.0006 1 0.0002 0.0031 1 0.0004 S-58 0.0002 1 0.0001 0.0022 1 0.0003 0.0032 1 0.0007 0.0071 1 0.0010 S-59 0.0001 0.0001 0.0033 1 0.0005 0.0012 i 0.0003 0.0032 ! 0.0006
^
S-60 0
i 0.0001 0.0017 0.0004 0.0046 1 0.0007 0.0024 ! 0.0005 a
S-61 0.0002 0.0002 0
1 0.0002 0.0017 1 0.0004 0.0001 1 0.0001 a0ff-site location Rl/RD88-144 l-
1 i
l The detected gross radioactivity in soil is due to some residual Cher-nobyl related radioactivity, to various naturally occurring radionuclides present in the environment, and to radioactive fallout of dispersed nuclear 1
weapons materials and fission product radioactivity produced by past atmos-pheric tests of nuclear weapons.
No atmospheric nuclear weapons tests were i
announced during 1987.
Naturally occurring radionuclides include Be, 40 87 I47 g,
Rb, 5m, and the uranium and thorium series (including radon and daughters).
The radionuclides composition of local area surf ace soil has 40 been determined to be predominantly K, natural thorium, and natural urani-um, both in secular equilibrium with daughter nuclides, with less than 1%
i 137 fission-produced radionuclides, principally Cs.
Radioactivity in aged 137 O
90Sr 90y, Cs, and fallout consists primarily of the fission produced 147 234 239 Pm, and also U and Pu.
Ganna spectrometric analysis of compos-ited ambient air samples collected during 1987 detected the cosmogenic radio-I nuclide Be, plus additional natural radionuclides of terrestrial origin, 40 the natural uranium and thorium series, and K.
Relative amounts of these 40 radionuclides were approximately 65%
K, 24%
Be, and the remainder due I
to the natural uranium series and natural thorium series.
The value for Be is representative for the mixture only at the time of measurement since the physical half-life is extremely short compared with those of the other radio-nucHdes detected.
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 3.
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 obtained partly f rom the Ventura County Water District No.17, which also supplies nearby communities, and f rom local well water, and is distributed on the site by the same piping system previously used when the total site water supply was obtained f rom on-site wells.
Two on-site water wells (wells 5 and 13) were operated during 1987 to reduce the consumption of the Ventura County water.
The well water proportion in the blend averaged s
Rl/RD88-144 18
i ~
TABLE 3 SUPPLY WATER RADI0 ACTIVITY DATA--1987 O
l Gross Radioactivity l
(10-9 pCi/ml) a Number Maximum Value of Average Value and Month Area Activity Samples and Dispersion Observed De Soto Alpha 12 5.1416.62 25.12 (monthly)
( Nevai.ba r)
Beta 12 3.40 1 0.72 4.52 (November)
SSFL Alpha 24 5.1013.81 14.98 (mor.chly)
(April)
Beta 24 3.59 i 1.03 6.04 (November) aMaximum value observed for single sample.
about 72% for the year, f or a total well water consumption of abcut 1.4 x 0 3 7
10 m (3.8 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 construc. ion of a modification to a now deactivated SNAP reactor test facility, is being used for sampling of ground water adjacent to the underground reacter test vault.
Water in the standpipe is periodically sam-pled for the purpose of detecting any transfer of activation product radio-activity f rom the containment to the outside envirr:nment.
Radioactivity in 56 samples taken during 1987 averaged 8.0 x 10-9 vci/ml bete with no alpha activity detected.
Gamma spectrometric analysis, with a minimum detection 60 limit for Co of about 5 x 10~I pCi/ml, has not identified any specific I
unnatural radionuclides in the water; thus, the observed activity is attrib-uted to dissolved radioelement of natural origin in the soil bed.
i RI/RD88-144 19
h c
A 'recent 'hydrogeologic study at SSFL describes two ground water systems at'the site:
a shallow, unconfined system in the alluvial surface mantle of 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 f ractures.
Water levels in the allu-L vium respond to recharge resulting f rom surf ace flows and may vary consider-
' ably between 4e'; and dry periods.
The alluvium, composed of a heterogeneous mixture of gravel, sand, silt, and clay, has estimated hydraulic conductivi-2 ties ra..ging from 0.1 to 1000 gal / day /ft,
The Chatsworth formation is composed of well-consolidated, massively bed-ded 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 surrounding icwlands 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 throuch the aquifers, and dis-charges to the surface or to other aquifere down-gradient of the site.
The ground water system is recharged by precipitation and by unlined pends and drainage channels.
Because of the meager rainfall in the area and the rela-tively larg variability in annual precipitation, ground water recharge may vary greatly f rom year to year.
Specific pathways of possible contaminant transport are dif ficult to predict on the basis of on-site well data.
The most likely pathways are along f racture zones that trend off-site.
As discussed earlier, surf ace waters discharged from SSFL f acilities and the sewage plant outf all drain southward into Rocketdyne retention pond R-2A.
When +5e pond is f ull, the water may be discharged into Bell Creek, a tribu-tary of the Los Angeles River in the San Fernando Valley, Los Angeles County.
Average radioactivity concentrations in Retention Pond R-2A, upper Bell Creek, and test well samples are presented in Table 4.
~
RI/0088-144 i
20
TABLE 4 SSFL SITE RETENTION POND, SITE RUN0FF, AND 'ilLL WATER RADIOACTIVITY DATA b.
(Sheet 1 of 4)
Gross Radioacti i Concedration (x 10 i/ml)
Percent of Samples Number Annual Average Maxinum Valuea; With l
of Value and Month Activgty Area Activity Samples
.id Dispersion Observed
<LLD Pond No. 6 Alpha 12 1.75 1.65 3.87 100 (Monthly)
(October)
Beta 12 4.66 + 0.9R 5.76 0
~
(October)
Pond No. 12 Alpha 12 2.78 + 1.98 5.35 100 (R-2A) (Monthly)
~
(October)
Beta 12 4.38 + 0.61 5.67 0
~
(October)
Upper Bell Creek Alpha 3
2.03 g 0.69 2.76 100-No. 17 (Seasonal)
(March)
Beta 3
3.28 + 0.93 3.85 0
~
(November)
Well WS-4A Alpha c
(Seasonal)
Beta Well WS-5 Alpha 12 4.06 + 3.50 10.52 75 (Seasonal)
~
(December)
Beta 12 3.96 + 0.63 4.91 0
~
(December)
Well W5-6 Alpha c
(Seasonal)
Beta Well WS-7 Alph3 c
(Seasonal)
Beta RI/RDB8-144 21
TABLE 4 SSFL SITE RETENTION POND, SITE RUN0FF, AND WELL WATER RADI0 ACTIVITY DATA j
(Sheet 2 of 4)
GrossRadioactigi Concentr& tion (x 10-l/ml)
Percent of S q les Number Annual Average Maximum Valuea With of Value and Month Activ{ty Area Activity Samples and Dispersion Observed I
<LLO Well WS-8 Alpha 2
6.86 + 0.28 7.06 0
(Seasonal)
~
(September)
Beta 2
3.12 + 0.36 3.37 0
~
(September)
Well WS-9 Alpha c
(Seasonal)
Beta Well WS-9A Alpha 1
1.09 + 0 1.09 100 (Seasonal)
~
(January)
Beta 1
3.55 + 0 3.55 0
~
(January)
Well WS-9B Alpha c
(Seasonal)
Beta Well WS-11 Alpha 1
4.40 + 0 4.40 100 (Seasonal)
(December)
Seta 1
4.49 + 0 4.49 0
~
(September)
Well WS-12 Alpha 2
12.97 + 5.19 16.64 0
(Seasonal)
~
(September)
Beta 2
3.70 + 1.21 4.56 0
~
(June)
Well WS-13 Alpha 12 3.99 + 2.08 8.63 92 (Seasonal)
~
(Septembec)
Beta 12 4.01 + 0.32 4.62 0
~
(May)
RI/RD88-144 22 l
l
l -
TABLE 4 l
SSFL SITE RETENTION POND, SITE RUNOFF, AND WELL WATER RADIOACTIVITY DATA i
f (Sheet 3 of 4)
GrossRadioactigityConcentration (x 10-pci/ml)
Percent of Samples Number Annual Average Maximum Valuea With of Value and Month Activ{ty Area Activity Samples and Olspersion Observed
<LLO Well WS-14 Alpha 2
4.82 + 0.93 5.48 100 (Seasonal)
~
(September)
Beta 2
4.07 + 0.92 4.71 0
~
(September)
Well 05-1 Alpha 4
5.49 + 3.20 9.46 75 (Seasonal)
~
(March)
Beta 4
4.23 + 0.57 4.88 0
~
(March)
^
Well 05-2 Alpha 4
7.50 + 4.87 14.24 25 (Seasonal)
~
(March)
Beta 4
2.88 + 0.78 3.37 0
~
(March) a Well 05-3 Alpha 2
8.89 + 1.75 10.13 0
(Seasonal)
~
(June)
Beta 2
3.90 + 0.12 3.99 0
~
(March)
Well 05-4 Alpha 2
4.50 + 5.70 8.54 50 (Seasonal)
~
(March)
Beta 2
4.50 + 1.10 5.28 0
~
(farch)
Well 05-5 Alpha 4
2.44 + 1.97 3.76 100 (Seasonal)
~
(December)
Beta 4
4.44 + 0.27 4.85 0
~
(Decenter)
Well 05-8 Alpha 4
3.88 + 2.38 6.44 100 (Seasonal)
~
(December)
Beta 4
3.18 + 1.04 4.73 0
~
(September)
RI/RD88-144 23
TABLE 4 SSFL SITE RETENTION POND, SITE RUN0FF, AND WELL WATER RADI0 ACTIVITY DATA (Sheet 4 of 4)
GrossRadioactigi Concentration (x 10-t/ml)
Percent of Sanples Number Annual Average Maximum Valuea With of Value and Month Activgty Area Activity Samples and Dispersion Observed
<LLD Well 05-10 Alpha 4
1.84 + 1.65 3.78 100 (Seasonal)
~
(March)
Beta 4
1.32 + 0.10 1.48 0
~
(March)
Well 05-13 Alpha 3
3.32 + 3.86 7.24 100 (Seasonal)
~
(March)
Beta 3
3.18 + 0.45 3.64 0
~
(Septenber)
Well 05-15 Alpha 3
14.32 + 2.89 16.12 33 (Seasonal)
~
(June)
Beta 3
5.49 + 1.13 6.64 0
~
(March)
Well 05-16 Alpha 3
10.32 + 7.65 15.74 33 (Seasonal)
~
(March)
Beta 3
4.71 + 0.63 5.09 0
(June)
Well RS-20 Alpha 2
1.37 + 1.16 2.19 IC^
(Seasonal)
~
(Occember)
Beta 2
1.28 + 0.50 1.63 50
~
(Septenber)
Well RS-21 Alpha 2
7.73 + 9.67 14.57 50 l
(Seasonal)
~
(June)
Beta 2
2.06 + 0.07 2.11 0
(June)
Well RS-22 Alpha 2
-0.88 + 0.005
-0.88 100 (Seasonal)
~
(June)
Beta 2
0.93 + 0.35 1.18 50 (June) aMaximum value observed for single sanple.
blower limit of detection: Approximately 0.4 x 10-9 pCi/mi alpha; 1.10 x 10-9 pCi/mi beta for water: approximately 3.2 pCi/g alpha; 0.37 pCi/g beta for soil.
cNot sampled during year due to well being out of service.
RI/RDBB-144 24
{
L.
Comparison of the radioactivity concentrations in water f rom the ponds with that of the supply water shows no significant differences in either alpha or beta activity.
Similarly, comparisons between on-site and of f-site soil samples and those of upper Bell Creek stream bed show no significant differences.
The SSFL site surf ace 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 f acilities and should not be taken to indicate the identification of these radionuclides in the samples.
Radioactivity concentration guide values are those concentration limits adop-ted by DOE, Nuclear Regulatory Commission (NRC), and the State of California as maximum permissible concentrations (MPCs) for uncontrolled areas.
These values are established in 10 CFR 20, California Administrative Code Title 17, and DOE Order 5480 l A.
The MPC values are dependent on the radionuclides and its behavior as a soluble or an insoluble material.
For comparison with re-sults of environmental and ef fluent monitoring, the single lowest MPC value for the various radionuclides present is selected rather than a derived MPC for the mixture.
Accordingly, for SSFL site surface water, the guide values of 5 x 10-6 pCi/mi alpha activity corresponding to Pu and 3x 239 90 10~ uti/mi beta activity corresponding to 5.
re used.
Ambient air sampling for long-lived particulate alpha and beta radio-activity is performed continuously by automatic sequential samplers located at the De Soto and SSFL sites.
Air is drawn through glass fiber filters, which are analyzed for retained long-lived radioactivity af ter a minimum 120-h decay period that eliminates naturally occurring short-lived particulate radio-activity (most radon daughters).
The average concentrations of ambient air alpha and beta radioactivity for 1987 are presented for the various sampler locations in Table 5.
l l
RI/RDB8-144 25
TABLE 5 AMBIENT AIR RADIOACTIVITY DATA--1987 9
3 Gross Radioactivity Concegrations--Femtocuries per m j
(10-pci/ml)
Percent of Samples Number Annual Average Maximum Valuca Fercent With Area of Value and Month of (monthly)
S.cthity Samples and Olspersion Observed Guideb Activigy
<LLO De Soto on-site Alpha 690 1.9 + 2.6 15.3 (05/16) 0.06 99 (2 locations)
Beta 26.9i20.4 111.9 (08/03)
<0.01 65 SSFL on-site Alpha 1770 1.9 + 2.4 36.1 (10/25) 3.2 99 (5 locations)
Bata 26.8118.3 106.7 (11/13) 0.09 64 SSFL sewage Alpha 353 2.1 + 2.4 17.1 (10/02) 3.5 99 treatment plant Beta 27.6 ~ 18.6 111.8 (11/13) 0.09 65 SSFL control C pha 338 1.9 + 2.1 9.0 (09/19) 3.2 99 center Beta 27.9i20.1 104.1 (11/13) 0.09 64 All locations
( Alpha 3151 1.9 + 2.4 l Beta 27.0i19.0
'Maximumvalueobservedforsgglesample.
Guide De Soto site:143 x 10--
uti/mi alpha 3 x 10-10 pCi/mi beta; 10 CFR 20 Appendix B, CAc 17.
b SSFL site: 6 x 10-pCi/mi alpha, 3 x 10-g pCi/mi beta; 10 CFR 20 Appendix B, cAC 17, DOE Order 5480.1A.
LLO = 8.5 x 10-15 pCi/mi alpha; 3.1 x 10-I4 pCi/ml beta.
C 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 pCi/ml for beta activity is due to the presence of Sr in fission 90 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 prior work with unencapsulated depleted uranium.
The guide value of 3 x 10-10 vCi/ml 60 is for Co, for which the ambient air beta activity guide is appropriate, since it is the most restrictive limit for any beta-emitting radionuclides in use at the De Soto site.
Guide value percentages are not presented for soil data, since nont have been established.
RI/RDBB-144 26
I.
p 4
Figure 5 is a graph of the weekly averaged long-lived alpha and beta ambient air radioactivity concentrations for the De Soto and SSFL sites during 1987. The daily data were mathematically smoothed in a moving weekly average 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 an abrupt decrease in airborne radioactivity during March'which is due to the movement into the Southern California area of a series of intense rain -
storms.
By the end of May, activity returned to normal levels and continued 3
to be generally constant or slightly increasing during the remainder of 19b7.
The activity detected in ambient air is attributed to naturally occurring radioactive materials and to aged fission products from past' atmospheric tests of nuclear devices.
Radionuclides detected in air samples collected during 40 1987 include Be and K plus several naturally occurring radionuclides f rom the ur6r.ium and thorium series. While the data for airborne alpha activ-ity are nearly all' below the minimum detection level for a single sample, averaging values f rom nine daily air samples over seven consecutive days and over calendar months reveal the long-term behavior of this activity.
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 ambient radiation level, which averaged 16 pR/h for 1987.
The quarterly and annual radiation exposures and the equivalcnt absolute and altitude-adjusted annual exposures, and exposure rates determined for each dosimeter location, are presented in Table 6.
e RI/RD88-144 27
4 I
\\
T 1
.A s
C 8
O 3
0 D
/
i D s
E 4
Y B
D m
E
/
TA s
I 1' s
O C
i V OM e
N I
S.
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TABLE 6 DE SOTO AND SSFL SITES--AMBIENT RADIATION DOSIMETRY DATA--1987 Equivalent Quarterly Exposure Exposure at (mrem)
Annual 1000-ft ASL TLD Exposure Location Q-1 0-2 Q-3 Q-4 (mrem)
(mrem)
(prem/h)
De Soto DS-1 27 30 36 28 121 122 14 05-2 27 29 47 26 129 131 15 0S-3 26 30 49 27 132 133 15 DS-4 28 31 39 31 129 130 15 DS-5 26 29 38 28 121 122 14 05-6 28 32 55 30 145 147 17 DS-7 23 37 51 31 122 124 14 05-8 25 28 28 27 108 109 12 Mean value 26 31 40 28 126 127 14 SSFL SS-1 26 30 54 41 151 139 16 SS-2 34 35 57 42 168 155 18 SS-3 29 51 47 40 167 155 18 SS-4 31 56 57 44 188 175 20 SS-5 23 a
31 30 112 99 14 SS-6 30 54 38 32 154 143 16 SS-7 22 41 58 30 151 139 16 SS-8 32 65 36 30 163 150 17 SS-9 35 58 42 37 172 160 18 SS-10 28 54 37 32 151 141 16 Mean value 29 49 46 36 158 146 17 Off-site 0S-1 23 24 34 24 105 108 12 05-2 24 46 48 25 143 140 16 05-3 24 48 39 30 141 143 16 05-4 25 49 51 27 152 150 17 OS-5 29 42 44 33 148 149 17 Maan value 25 42 43 28 138 138 16 aMissing dosimeter; annual exposure estimated from data for three quarters.
RI/RD88-144 29
u -
During the second, third, and fourth quarters of 1987, TLD exposure data were erratically higher than expected for the on-site and also for the off-site dosimeters. 'Although no specific causes for the inconsistent and higher values for 'these. quarters have been identified, and since the higher res::lts are noted for the off-site dosimeters as well as the on-site dosimeters, the higher values are attributed to an intermittent bias in the dosimeter readout 1 instrumentation.
Results observed for the fourth quarter showed fewer erratic values.
Improvements in dosimeter calibration methods, field deployment and storage conditions, and in evaluating and recording specific radiation response characteristics for each dosimeter are being implemented.
Table 6 shows that radiation exposures and equivalent annual exposure rates monitored on-site are nearly identical tr levels monitored at the five widely separated of f-site locations.
These data reflect natural background radiation from cosmic radiation, radionuclides in the soll, radon and thoron
.in the atmosphere, and local radioactive fallout.
Locally, the natural back-ground radiation level as measured by these dosimeters is about 100 mrem / year-(1 mSv/ year).
The small variability observed in the data is attributed to differences in elevation and geologic conditions at the various 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 specific altitude by adjusting the mer.sured value by an altitude adjustment f actor equal to 15 mR/
1000-f t elevation dif ference, derived radiation exposures for all locations are essentially identical.
The 1987 averaged exposure values adjusted to 1000-f t ASL are 127 1 11 mR for the De Soto site, 146 1 14 mR for the SSFL site, and 138 1 17 mR for the off-site control dosimeters.
Supplementary measurements of ambient radiation levels with high-pres-l-
sure icn chamber (HPIC) monitors are made at two locatJions at the SSFL site.
The HPIC values for 1987 were equivalent to annual erposures of 10E mR (1.06 mSv/ year) for the Building 207 monitor and 101 mR (1.01 mSv/ year) for the Building 363 monitor.
These values are in good agreement with results for nearby TLD locations for the year.
RI/RD88-144 30
For independent monitoring of radiation levels in this area, the Radio-logic Health Section of.the State of California Department of Health Services provides packages containing calcium sulfate (CaSO ) dosimeters for place-4 merit in the field deployment containers used-for the bulb dosimeters.
The State dosimeters are returned to the Radiologic Health Section for evaluation by a vendor laboratory.
Data for these' TLDs, placed at eight Rocketdyne dosimeter locations, both on-site and off-site, were not available from the state for inclusion in this report at the time of publication.
During 1987, Rocketdyne participated in the U.S. DOE-sponsored Environ-mental Dosimeter Mini-Intercomparison Project.
This project involved exposure 137 60 of sets of TLDS to Cs and to Co radiation to evaluate a discrepancy I
noted in results reported by various laboratories using only Cs as cali-bration source for periodic DOE-sponsored dosimeter intercomparison projects.
The results of.Rocketdyne participation in the project were not available for inclusion in this report at the time of publication.
B.
NONRAD10 ACTIVE MATERIALS--1987 Processed wastewater and most of the collected surface runoff discharged from the SSFL site flows to Rocketdyne retention pond R-2A.
Water samples from the pand are analyzed for various constituents, as required by the Re-gional Water Quality Control Board, for each discharge to Bell Canyon.
Such discharges are.normally done only as a result of excessive rainfall runoff.
During 1987, only six off-site discharges f rom pond R-2A occurred, due to a relatively dry year.
The results of the analyses for each discharge during 1987 are presented in Table 7.
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RI/RD80-144 31
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IV.
ENVIRONMENTAL MONITORING PROGRAM A.
DESCRIPTION A program of soil and vegetation sample collection and analysis for radioactivity was begun in 1952 in the Downey, California area where the nu-clear 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 operation.
The Downey area survey was terminated when nuclear activities were relocated to Canoga Park in 1955.
Af ter review of the needs and results of the environmental monitoring program, sampling of vegetation for radioactivity analysis was terminated and the sampling frequen:y for soil was reduced to quarterly in 1986.
Although the reduction in the number of on-site soil sam-ples taken annually is significant, the number of off-site soil samples taken annually remains the same.
Table A-1 shows that the 1987 averaged values for soil activity compares well with values for prior years.
The primary purpose of the environmental monitoring program is to adequately survey environmental radioactivity to ensure that Rocketdyne nuclear operations do not contribute significantly to environmental radioactivity.
The locations of sampling sta-tions are shown in Figures 6 through 8 and listed in Table 8.
B.
SAMPLING AND SAMPLE PREPARATION 1.
Soil Soil is analyzed for radioactivity to monitor for any significant in-crease in radioactive deposition by f allout f rom airborne radioactivity.
Since soil is naturally radioactive and has been contaminated by atinospheric testing of nuclear weapons, a general background level of radioactivity exists. The data are monitored for increases beyond the natural variability G
RI/R088-144 33
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TABLE 8 SAMPLING LOCATION DESCRIPTION (Sheet 1 of 5)
Frequency of a
Station Location Sampling S-1 SSFL Site, Building 143, southeast sida (Q)
S-2 SSFL Site, Building 143, east side (Q)
S-3 SSFL Site, Building 064, north parking lot area (Q)
S-4 SSFL Site, Building 029, at west fence (Q)
S-5 SSFL Site, Building 363, east parking lot area (Q)
S-6 SSFL Site, Interim Retention Pond, south side (Q)
S-10 SSFL Site Access Road, at upper mobile home park entrance (Q)
S-12 SSFL Site, Building 093, at reactor building driveway (Q)
S-13 SSFL Site, above SRE Retention Pond (Q)
S-14 SSFL Site, Building 028, upper parking lot area (Q)
S-19 SSFL Site Entrance, Woolsey Canyon (Q)
S-24 De Soto Site, Building 104, ecst side (Q)
De Soto Avenue and Plummer Strect, southeast corner (Q)
S-25 S-26 Mason Avenue and Nordhoff Street, southeast corner (Q)
S-27 De Soto evenue and Parthenic Street, northeast corner (Q)
S-2B Canoga Avenue and Nordhoff Street, northwest corner (0)
S-31 Simi Valley, Alamo Avenue and Sycamore Road, southeast (Q) corner S-40 Agoura - Kanan Road and Ventura Freeway at Frortage Road (Q)
S-41 Calabasas - Parkway Calabases and Ventura Freeway at Frontage Road (Q)
S-42 SSFL Site, Building 886, at old sodium disposal facility gate (Q)
S-47 Chatsworth Reservoir Site Nnrth Boundary at north gate (Q) 5-51 SSFL Site, Building 029, at driveway (Q) 5-52 SSFL Site, Btero Flats Crainage Control Sum). 3 Street and 17th Street (Q)
S'53 SSFL Site, Pond R-2A (Q)
RI/RDBB-144 37
TABLE 8 SAMPLING LOCATION DESCRIPTION (Sheet 2 of 5)
Frequency of Station Location Sampling #
S-55 SSFL' Site, Pond R-2A (Pond Bottom Mud), north side (Q)
S-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)
S-62 SSFL Site, near south boundary, Bell Creek Weir, Well 9 (Q)
W-6 SSFL Site Interim Retention Pond, south side (M)
W-7 SSFL Site Domestic Water, Building 003, washroom faucet (M)
W-11 SSFL Site Domestic Water, Building 363, washroom faucet (M)
W-12 SSFL Site, Pond R-2A, north side (M) e W-13 De Soto Site, Building 104, washroom faucet (M)
L'-17 SSFL Site, Pond R-2A, discharge to Bell Creek (Seasonal)
A-1 De Soto Site, Building 102 roof (D)
A-2 Ce Soto Site, Buildi99 104 roof (D)
A-3 SSFL Site, Building 100, east side (D)
A-4
$5FL Site, Building 011, west side (D)
A-5 SSFL Site, Building 500, Sewage Treatment Plant, nortti side (D)
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 SSFL Site, Building 363, west side (D)
A-10 SSFL Site, Building 100, east side day sampier (168 h)
RI/RD88-144 38
I TABLE 8 SAMPLING LOCA110N DESCRIPTION (Sheet 3 of 5)
Frequency of a
Station Location Sampling On-Site--De Soto -' Ambient Radiation Dosimeter locations (TLD) 05-1 De Soto Site, south of Building 102 (Q) 05-2 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 boundary 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) i DS-8 De Soto Site Guard Post 4, southwest corner of Building 101 (State of California TLD Location Number 7)
(Q)
Gn-Site--SSFL - Ambient Radiation Dosimeter locations (TLD)
SS-1 SSFL Site, Building 114 on telephone pole (Q) 55-2 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-4 SSFL Site, west boundary on H Street (Q)
SS-5 SSFL Site, southwest boundary at property line gate (0)
SS-6 SSFL Site, Building 854 (State of California TLD location Number ()
(Q)
SS-?
SSFL Site, Building 363, rorth side on HPic monitor 1
(State of California TLD Location Number 8)
(Q) 55-8 SSFL Site, Sodium Disposal Facility north boundary (Q)
SS -9 SSFL Site, Radioactive T4aterials i
Disposal Facility, northeast boundary (Q)
)
- S->10 SSFL Site, Building 600, Sewage Treatment Plant (Q)
- t. _
4 e
RI/RD88-144 39
- f..
l 1
TABLE 3 SAMPLING LOCATION DESCRIPTION (Sheet 4 of 5)
I i
l Frequency I
of J
a Station Location Sampling Off-Site (TLDl' 05-1 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) 0S-3 Off-site, San Fernando Valley, Northridge, approximately Plummer Street and Vanalden Avenue (Q) 05-4 Off-fite, Simi Valley, approximately Tapo Canyon'and Walnut Streets (Q) 05-5 Off-site, Simi Valley, approximately east Los Angeles Avenue and Stow Street (State of California TLD Location Number 6)
(Q)
HPI-l High-Fressure Ion Chamber (HPIC) Ambient Radiation Monitor at Building 207, north side (C)
HPI-2 High-Pressure Ich Chamber (HPIC) Ambient Radiation Monitor at Building 363, ncrth side (C) acode Description S
Soil sample station k
Water sample station A
Air sampler s'.ation TLD Thermoluminescent dosimeter 0
Daily sample M
Monthly sample Q
Quarterly sample S
Semiannual sample C
Continuous a
RI/RD88-144 40
i TABLE B SAMPLING LOL,' ION DESCRIPTION (Sheet 5 of 5)
~
GROUNDWATER SAMPLING STATIONS DEEP AND SHALLOW TEST AND PRODUCTION WELLS (Sampled Quarterly or Seasonally Depending on Groundwater Recharge)
Well Description of General Location WS-4A On-site:
On north boundary WS-5 On-site:
1500 ft from southeast boundary WS-6 On-site:
2500 ft from north boundary WS-7 On-site:
550 ft from north boundary WS-8 On-site:
300 f t east of Silvernale Reservoir WS-9 On-site:
1500 ft east of Silvernale Reservoir WS-9A On-site:
1000 ft south of Pond R-2A in drainage channel WS-9B On-site:
1000 ft from north boundary WS-11 On-site:
2500 ft from northwest boundary WS-12 On-site:
800 ft from north boundary WS-13 On-site:
200 ft from north boundary WS-14 On-site:
On northeast boundary 05-1 Off-site:
1350 ft from site north boundary 05-2 Off-site:
1750 f t f rom site northwest boundary OS-3 Off-site:
1100 f t f rosn site northwest boJndary 05-4 Off-site:
1100 ft from site northwest boundary 05-5 i Off-site:
1100 f t f rom site northwest boundary 05-8 Off-site: 1750 f t f rom site north boundary (Spring) 05-10 Off-site: 4250 ft from site north boundary LU-13 Off-site:
900 ft from site East boundary US-15 Off-site:
2900 f t f rem site northeast boundary 1
05-16 Off-site:
800 ft from site northeast boundary RS-20 On-site:
a400 f t f rom east boundary RS-21 On-site:
860 ft from north boundary RS-22 On-site:
1000 f t f rom north boundary I
WS SSFL on-site water supply well (drilled before 1960) 05 Of f-site water well for ground water monitoring l
RS SSFL on-site shallow zone ground water monitoring well.
RI/R088-144 41 a
a of this background.
Fcr most radionuclides, gross alpha and beta radioactiv-i ity measurements are adequate for this purpose.
Chemically specific analyses are performed for plutonium to provide improved sensitivity.
J Surf ace soil types available for sampling range f rom decomposed granite i
ta clay and loam.
Samples are taken f rom the upper 1 cm of undisturbed ground q
surface for gross radioactivity analysis and to a depth of 5 cm for plutonium' analysis.
The soil samples are packaged in paper containers and returned to the laboratory for analysis.
Sample preparation of soil for gross radioactivity determination consists 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 ti,e sieved soil are weighed into stain-less-steel planchets.
The soil is wetted in the planchet with alcohol. evenly distributed to obtain uniform sample thickness, dried, and counted for alpha and beta radiation.
Soil plutonium analysis is performed using a chemically specific method J
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."
2.
Wcte r, Surface and supply water samples are obtained monthly at the De Soto and SSFL sites and f rom upper Bell Creek during periods of off-site discharge due to rainfall.
The water is drawn into 1-liter polyethylene bottles and trans-
]
ferred to the laboratory.
Five-hundred-milliliter volumes cf water are evaporated to drynecs in crystallizing dishes at about 90'C.
The residual salts are redissolved into distilled water with dilute nitric acid, transferred to planchets, dried under heat lamps, and counted for alpha and beta radiation.
RI/RD88-144 42 5
1 :.
L,
. 3.
Ambient Air Air sampling is performed continually at the De Soto and SSFL sites with air samplers operating on 24-h sampling cycles.
Airborne particulate radio-activity is~ collected on glass-fiber filters, 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 decay period.
The vol-3 ume of a typical daily ambient air sample;is about 25 m,
C.
COUNTING AND CALIBRATION Enviror. mental soil, water, and ambient air samples are counted for alpha and beta radiation.with a low-background gas flow proportional counting system.
- The system is. capable of simultaneously counting-both alpha-and beta radia-
. tion.
The sample-detector configuration provides 'a nearly 2r geometry.
The
- thin-window detector is continually purged with argon / methane counting gas. A preset time mode of operation is used for all samples.
The lower limits of 7
' detection shown in Table 9 are those for a single sample determined 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 beta), and sample size.
These limits'of detectability, for single samples, are calculated according to U.S. NRC Regulatory Guide 4.16, and assure a 95% probability that the. measured activity would be identified as "above background."
99 36 Counting system ef ficiencies are determined. routinely with 1c, C1, 230Th,.235U, and Pu stand'ard sources and with 40 239 K, in the form of standard
- reagent-grade KC1. w'lich is used to simulate soil, and with soil containing known amounts of highly enriched uranium.
l 4
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RI/RD88-144 43
1, I
{
TABLE 9 Li'R LIMITS OF DETECTION (LLDs)
]
1 l
Sample' Activity Soil Alpha (3.2 i 1.8)-10-6 pCi/g (118.4 1 66.6 Bq/kg)
~
Beta (3.7 2.0) 10-7 pCi/g (1 6.9 1 74 Bq/kg)
Weter Alpha (4.011.9)10-10 pCi/ml (0.0148 1 0.007 Bq/1)
Beta (1.1 1.2) 10-9 pCi/ml-(0.0407 1 0.044 Bq/1) i Air Alpha
'(8.512.4)10-15 pCi/ml (0.0003 0.0001 Bq/m )
3 Beta (3.1 i 1.4) 10-14 pCi/ml (0.0011 1 0.0004 Bq/m )
3 Self-absorption standards for beta counting are made by dividing sieved kcl into semples that increase in mass by 200-mg increments, f rca 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.
The product of the correction f actor and the net sample count rate yields 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.
Since the observed radioactivity in environmental samples primarily re-suits f rom natural sources and is at low concentrations, no identification of constituent radionuclides is done for each sample.
However, collected samples are composited foi ganna spectrocaetry of accuinulated sample materials.
The detection af shnificaat levels-of radioactivity would lead to an investiga-t',on of the radioactive material involved, tne sources, and the pussible causes.
RI/RDB8-144 44
0.
NONRADI0 ACTIVE MATERIALS The Rocketdyne Division af 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 ef fective 17 September 1984.
This permit covers discharge of overflow and storm runof f f rom water reclamation retention ponds into Bell Creek.
Discharge generally occurs only during and immediately af ter periods of heavy rainf all 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 f rom the nuclear operating areas of the SSFL site.
It is identified as retention pond R-2A, Water Sample Station W-12 in Table 8.
The influent includes sewage treatment plant outf all and surf ace runoff water.
Grab-type water samples taken at the retention pond prior to a dis-charge are analyred by a California State certified analytical testing labora-tory for nonradioactive chemical constituents and for radioactivity.
The specific constituents analyzed for, and their respective limitations in dis-charged wastewater, are presented in Appendix C.
Wastewater originating from f acilities located throughout the SSFL site is collected at tha retention pond.
The point of origin of small amounts of most nonradioactive constit-uents normally found in wastewater is difficult to determine.
In the event of excessive arnounts of any of these materials in wastewater, the origin could be det crmined f rom the knowledge of f acility operations involving their use.
In addition to the wastewater discharge limitations, atmospheric pollu-tant discharge limitations were imposed by the Ventura County Air Pollution RI/RD88-144 45
Control District (APCD) Permit 0271 on two natural-gas /cil-fired sodium heaters operated by ETEC.
The limitations for 1987 are 0.34 tons / year for reactive organic compounds, 63.89 tons / year for oxides of nitrogen, 1.82 tons / year for particulate, 20.15 tons / year for oxide of sulfur, and 7.23 tons / year for carbon monoxide.
Based on fuel consumption records for this f acility during 1987, there was essentially no significant discharge to the atmosphere in comparison with the discharge limits.
Durlog 1987, the Ventura County APCD permit was renegotiated, resulting in less restrictive
. pollutant discharge limitations during 1988 for some pollutants.
C o.
RI/RD88-144 46
V.
EFFLUENT MONIl0 RING 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 and 021-022 at the Santa Susana site, SSFL, and Building 104 (previously identified as 004) at the De Soto Facility.
A.
TREATMENT AND HANDLING The only release of radioactivity to uncontrolled areas is by way of dis-charge to the atmosphere.
No contaminated liquids are discharged to unre-stricted areas.
The level of radioactivity contained in all atmospheric effluents is reduced to the lowest practical value by passing the effluents through certi-fied high-efficiency particulate air (HEPA) filters.
The effluents are sam-pled for particulate radioactive materials by means of continuously operating stack exhaust samplers at the point of release.
In addition, stack monitors installed at Buildings 020 and 021-022 provide automatic alarm capability in the event of the release of gaseous or particulate activity from Baild'ng 020 and par ticulate activity f rom Buildings 021-022.
The HEPA filters used f or filtering atmospheric ef fluents are at least 99.97% efficient for particles 0.3 pm in diameter.
Particle filtration ef ficiency increases for particles above and below this size.
The average concentration and total radioactivity in atmospheric efflu-ents to uncontrolled areas are shown in Table 10.
The effectiveness of the air cleaning systems is evident from the fact that the atmospheric effluents are less radioactive than is the ambient air. The total shows that no signif-icant quantities of radioactivity were released in 1987.
RI/RD88-144 47
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B.
FACILITY DESCRIPTIONS 1.
De Soto Site d
a.
Building _104--California State Licensed Activities Operations at Building 104 that may generate radioactive ef fluents con-I sist of research studies in applied physics and physical chemistry.
Only atmospheric ef fluents are released f rom the building to uncontrolled areas.
Major quantitles of radionuclides present in encapsulated form are limited to 60 137 Co and Cs.
Small amounts of irradiated metallurgical samples were used for research purposes but most of these have been removed f rom the facility.
2.
Santa Susana Field Laboratories Site
.i.
Building 020--NRC and California State Licensed Activities 6
Operations et Building 020 that may generate radioactive effluents con-sist of hot cell examination and decladding of irradiated nuclear f uels and examination of reactor compor,ents.
Only atmospheric effluents are released f rom the building to uncontrolled areas.
The discharge may contain radio-active gases as well as particulate material depending on the operations being performed and the history of the irradiated fuel or other material.
No radio-
? '
active liquid waste is released from the facility.
Radioactive material han-died in unencapsulated f orm in this f acility includes the following radio-137
'7, nuclides:
U, Pu, as constituents in the various fuel materials; and Cs, g
90Sr, 85Kr, and Pm as mixed fission products.
I47 3 - )
b.
Buildings 021 and 022--00E Contract Activitie,s_
Operations at Buildings 021 and 022 that may generate radioactive ef flu-ents consist of the processing, packaging, and temporary storage of liquid and dry radioactive waste material for disposal.
Only atmospheric effluents are RI/RD88-144 49
, released from the building to uncontrolled areas. No radioactive liquid waste
^
is released!from the facility.
Nuclear fuel material handled in encapsulated 137Cs, 90Sr, or unencapsulated form contains uranium and plutonium plus I47 85
- and Pm as' mixed fission products.
gp, C.' -
ESTIMATION OF GENERAL POPULATION DOSE ATTRIBUTABLE TO ROCKETDYNE OPERATIONS--1987 The Los Angeles basin is. a semiarid region whose climate is controlled primarily by the semipermanent Pacific high-pressure cell that ' extends f rom Hawaii 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 suf ficiently 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 summer season weather conditions would generally be under a subsidence inversion into an atmosphere.that is typical of slight r.eutral to lapse conditions.
Nocturnal cooling inversions, although present, are relatively shallow in extent.
During the summer, a subsidence inversion is present almost every day.
The base 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 0 lofting diffusion conditions above the inver-sion and considerable atmospheric dispersion, prior.to any diff usion through the inversion into the Simi or San Fernando Valleys.
In the winter season, the Pacific high-pressure cell shif ts to the south and the subsidence inver-
. sion is usually absent..
The surface airflow is then dominated by f rontal activity moving easterly through the area, resulting in high-pressure systems in the Great Basin region.
Frontal passages through the area during winter
. are generally accompanied by rainf all.
Diffusion. characteristics are highly RI/RD88-144 50
variable depending on the location of the front.
Generally, a light to mod-erate southwesterly 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 f rontal systems approach, enhancing diffusion.
The dif f usion characteristics of the f rontal passage are lapse conditions with light to moderate northerly winds.
Locally, average wind speeds for the various stability categories range from 0 to about 4.4 m/s with the greatest f requency occurring for winds f rom the north to northwest sec-tors.
Local population distribution estimates projected for 1987, based on the 1980 federal census 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 concentration of radioactive material emissions to the atmosphere during 1987 f rom each of the three major Rocketdyne nuclear f acil-ities has been calculated with the AIRDOS-EPA computer code using site-specific input data including local area windspeed, directional frequency, and stability plus f acility-specific data such as stack heights and exhaust air velocity.
lo 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.f requency, which is toward a northerly direction.
The con-centration estimates are shown in lable 11, and both internal and external radiation dose estimates are shown in Table 12.
The internal dose calcula-tions in Table 12 assume a constant unsheltered exposure, adjusted for wind direction f requency, throughout the year and therefore considerably over-estimate the actual annual-averaged doses at the nearest boundary and nearest residence.
The external dose calculations assume that dif ferences in TLD readings represent true differences in local exposure. These differences are Rl/RD88-144 51
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Santa Susana Field Laboratories Site-Centered Demography to 8 km Distance RI/RD88-144 52
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Santa Susana Field Laboratories Site-Centered Demography to 80 km Distance (heavily populated areas are shown by shading) 54 i
1 TABLE 11 MAXIMUM DOWNWIND PLUME CENTERLINE CONCENTRATIONS 0F ATMOSPHERIC EMISSIONS--1987 Downwind Concentration Release Distance (m) to (10-15 pCi/ml)a Rate Facility (Ci/ year)
Boundary Residence Boundary Residence B0 km 8/104 9.6 x 10~
200 W 315 SW.
0.0025 0.0025 0.000019 B/020 3.9 x 10-6 305 WW 1900 SE 0.0036 0.0023 0.000086
-5 C/022 1.2 x 10 350 NW 2300 SE 0.0065 0.0049 0.00026 aAssume'u = 2.2 m/s average wind speed, wind direction averaged for full year.
extrapolated to the boundary and nearest residence using an inverse square distance relation from an assumed source of radiation.
Except for the nearest boundary line exposure for the Radioactive Mate-rials Disposal Facility (RMDF), the estimated off-site doses are extremely low compared to the maximum permissible exposures recommended for the general pop-1 ulation in the vicinity of DOE facilities.
The effective dose equivalent for any member of the public, for all pathways, shall not ex:eed 500 mrem / year for occasional exposures, and 100 mrem / year for prolonged periods of exposure.
For the air pathway only, the limits are 25 mrem / year for whole body dose, and 75 mrem / year for any organ.
The RMDF boundary to the north of the facility, which received an estimated 55 mrem during the year, is an isolated area with no direct access for unobserved members of the general public.
No identifia-ble members of the general public were present at the site boundary during any significant portion of the year.
The maximum estimated internal aid external exposures to an individual for 1987 at the De Soto and SSFL site boundaries and also at the nearest residence are shown in Table 12.
Estimated internal radiation doses due to atmospheric emission of radioactive materials from 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 natural radioactivity in air.
RI/RD88-144 55
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The external exposures, above background, are based on the greatest expo-sure adjusted to a constant altitude (1000-f t MSL) measured by a single dosim-
~
eter compared with average adjui,ted off-site measurements.
The mean adjusted value for five off-site dosimeters was 138 mR (1.38 mSv) with a maximum annu-ally observed value for a single location of 150 mR (1.50 mSv).
Boundary dose estimates assume 100Y, occupancy, whereas the actual presence of persons at the boundary is rare or nonexistent.
Review of these data indicate that the de-rived values, except for the RMDF, are not significantly different from zero, as shown by the uncertainties being near the reported value, but result from assumptions in the analysis.
The general population person-rem dose estimates are calculated from the demographic distribution and the sector total inhalation intake (person-pCi/
year) generated by AIRDOS-EPA, which user release rate, wind speed, wind direction and f requency, inversion, lapse, and ef fective stack height param-eters as input data.
Population dose estir.at<rs centered on the SSFL site are presented in Table 13.
Inhalation is the nniy significant exposure pathway likely to exist.
The doses reported for SSFL site emissions are summed for all release points and nuclides.
l 0240Y/sjv RI/RD88-144 57
- - _ _ _ ~ - - - -
_ ~
TABLE 13-POPULA110N DOSE ES11 MALES FOR ATMOSPHERIC EMISSIONS FROM SSIL FACILIllLS--1987 1
22.5 00:e to Receptor Population Segment (person-rem)
. Degree c
Sector
' 0-8 km -
8-16 km 16-32 km 32-48 km 48-64 lun 64-80 km Total-N 2.1 x 10~4 5.0 x 10 4.7 x 10~0 8.4 x 10 9.2 x 10' 7.9 x 10 8 2.6 x 10'#
-7
-6
~
'NNW 9.4 x 10 2.2 x 10~
2.1 x 10'0 0
0 1.2 x 13~
9.9 x 10-5
~
NW 2.5 x 10 0
1.2 x 10-5 0
1.7 x 10~
3.7 x 10 2.6 x 10-4
~#
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-5
-5
-5 WNW 3.5 x 10 2.1 x 10 2.7xIC 2.4 x 10 2.7 x 10 0
4.5 x 10
'W 0
1.9 x 10~
6.2 x 10 9.8 x 10~
3,6 x 10-5 0
2.2 x 10'4
-5 WSW 2.6 x 10~
8.3'x 10~
6.6 x 10 9.3 x 10 1.8'x 10 0
1.6 x 10~#
-5
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0 0
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-5
-6 SE 6.3 x 10-7.5 x 10 1.5 x 10 2.0 x 10 4.6 x 10~
1.5 x 10 1.0 x 10-3
-5 ESE 5.9 x 10-1.6 x 10~
2.1 x 10~
1.2 x 10" 8.4 x 10~
5.6 x 10 3.0 x 10~3 E
4.1 x 10 2.4 x 10~
4.0 x 10-3.4 x 10~
3.3 x 10 2.2 x 10-#
1.6 x ~'
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2.3 x 10 2.8 x 10-9 3.4 x 10'I 2.7 x 10-#
-6
-5 NE 4.1 x 10 6.8 x 10~
2.6 x 10 6.7 x 10 2.2 x 10 2.3 x 10-5 6.2 x 10-5
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-5 NNE 9.8 x 10-1.1 x 10 5.1 x 10~
8.2 x 10 2.6 x 10~
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1.7 x 10~
~
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1.7 x 10" 9.7 x 10 0.0077 Average individual dose = 9.6 x 10 ' rem for the 80-km radius area total population.
RI/RD88-144 58
--.----------__---~--_-----_--.--.-a
APPENDIX A a
COMPARISON OF ENVIRONMENTAL RADI0 ACTIVITY DATA FOR 1987 WIlH PREVIOUS YEARS This section compares environmental monitoring results for the calendar year 1987 with previous annual data.
The data presented in Tables A-1 through A-4 summarize past annual aver-age radioactivity concentrations.
These data show the effects of both the short-lived and long-lived radioactive f allout f rom nuclear weapons tests and the 1986 Chernobyl accident 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 ef fective data.
In some cases, this is readily apparent in the data.
For exampla, in Table A-1, a small but abrupt increase in the alpha activity
~
reported for soil cccurs 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, total activity in ambient air was measured, combining 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 i
was achieved, resulting in determination of the absolute alpha activity in these samples rather than the relative values previously used for monitoring purposes.
Corparison of the values for 1987 as determined by the relative method with those for prior years shows no significant dif ference.
i
{
}
RI/RD88-144
]
4 59 J
y t..
TABLE A-1 SO'l RADIDAC11VITY DATA--1968 THROUGH 1987 C
On-site Average Off-site Average (pCi/g)
(pCi/g)
Number of Number of Year Samples Alpha Beta-Samples Alpha.
Beta a
1987 48 27.1 25 48 25.7 24 a
1986 48 26.7 26 48 25.1 25 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 12 4 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 aThe. change in alpha activity af ter 1983 is the result of an improved l
calibration method that provides a true measure of alpha activity in l
thick samples rather than the relative values used previously. This is discussed in detail in Part III, Section A.
Values for 1987 using the prior method would be 0.87 for the on-site average and 0.83 for'the off-site average.
~
RI/RD88-144 60
TABLE A-2 L
SSFL SITE SUPPLY WATER RADI0 ACTIVITY DATA--
1968 THROUGH 1987 Number of Average Alpha Average Beta Year Samples (10-9 pCi/ml)
(10-9 pCi/m))
1987" 24 5.10 3.6 1986 24 6.55 3.6 1985 24 2.05 2.8 1984 24 3.53 2.9 1983 24 0.12 3.0 1982 24 0.14 3.0 1981 24 0.24 2.8 1980 24 0.22 2.4 1979 24 0.23 2.8 1978 24 0.26 3.0 1977 24 0.25 2.5 1976 24 0.25 2.0 1975 24 0.24 2.3 1974 24 0.24 2.7 1973 24 0.26 3.4 1972 24 0.22 3.7 1971 24 0.28 4.9 1970 24 0.18 5.3 1969 24 0.11 5.0 1968 24 0.16 5.0 aThe change in alpha activity af ter 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 III, Section A.
The value for 1987 using the prior method would be 0.32.
RI/RD88-144 61
l l
l TABLE A-3 ROCKE1 DYNE OIVISION RE1EN110N POND RAD 10ACTIV11Y 9
DA1A--1968 THROUGH 1987 Interim Retention Final Retention Pond Pond Water R-2A Water 6
12 Average Average Number (10-9 pCi/ml)
Number (10-9 pCi/ml) of of Year Samples Alpha Beta Samples Alpha Beta 1987a 12 1.75 4.7 12 2.78 4.4 1986a 12 2.51 2.9 12 4.18 3.6 1985a 12 2.06 3.5 12 3.07 3.5 1984a 12 2.07 4.6 12 0.15 4.2 1983 12 0.12 3.6 12 0.13 4.4 1982 12 0.17 3.9 12 0.11 3.9 1981 12
<0.23 4.3 12
<0.25 5.2 1980 12
<0.22 2.9 12
<0.22 3.9 1979 12
<0.25 3.1 12
<0.23 4.5 1978 12
<0.25 4.3 12
<0.25 4.6 1977 12
<0.24 4.3 12
<0.25 5.2 1976 12
<0.24 4.3 12
<0.28 4./
1975 12
<0.24 4.2 12
<0.31 4.d 1974 12
<0.22 4.2 12
<0.21 4.5 1973 12
<0.23 4.5 12
<0.37 5.6 1972 12 0.22 5.3 12 0.22 5.5 1971 12 0.18 6.2 12 0.16 6.4 1970 12 0.15 6.9 12 0.12 7.4 1969 12 0.07 5.9 11 0.10 5.7 1968 11 0.23 8.1 12 0.33 7.7 aThe change in alpha activity after 1983 is the result of an improved calibration method that provides a trae mcasure of alpha activity in thick samples rather than the relatise values used previously.
This is discussed in detail in Par. III, Section A.
Values for 1987 using the prior method would be as follows:
Interim retention pond:
0.13 Final retention pond:
0.19 RI/RD88-144 62
D TABLE A-4 AMBIENT AIR RADI0 ACTIVITY CONCENTRATION DATA--1968 THROUGH 1987 De Soto Site Average SSFL Site Average (10-12 pCi/ml)
(10-12 pCi/ml)
Number of Number of Year Samples Alpha Beta Samples Alpha Beta 1987 690 0.0019 0.027 2460 0.0019 0.027 1986 687 0.0029 0.058 2415 0.0028 0.061 1985 544 0.0026 0.044 2450 0.0020 0.040 1984 71 2 0.0019 0.027 2461 0.0014 0.024 1983 644 0.0024 0.026 2328 0.0010 0.023 1982 727 0.0017 0.026 2347 0.0013 0.022 1981 704 0.0069 0.12 2518 0.0068 0.12 1980 685 0.0065 0.039 2342 0.0064 0.035 1979 697 0.0066 0.021 2519 0.0065 0.020 1978 713 0.0084 0.091 2402 0.0072 0.088 1977 729 0.0066 0.17 2438 0.0066 0.17 1976 719 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 715 0.0075 0.041 2311 0.0072 0.038 1972 708 0.0085 0.14 2430 0.0086 0.14 a
1971 730 0.0087 0.30 2476 0.0086 0.33 1970 668 0.34 2434 0.36 1969 687 0.27 2364 0.26 1968 650 0.32 2157 0.32 aAmbient air alpha radioactivity values were included in the beta values and not reported separately prior to 1971.
Q RI/RD88-144 63
i in late 1985, a new automatic low-background gas flow proportional counting system was placed in operation for the counting of most environmental d
sdmples.
Following characterization and calibration, the new system was used for all sample types that were analyzed during 1987.
Gamma spectroscopy is e
performed with a high-purity germanium detector (HPGe) coupled to a multichan-nel analyzer (MCA) with programmable radionuclides libraries and ef ficiency calibrations.
The ambient radiation monitoring results show a continuing long-term variation that had been apparent 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 analyticsl 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 the 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 concen-trated local source of unnatural radioactivity in the environment.
Also, the similarity between on-site and of f-site results further indicates that Rocket-dyne operations contribute essentially nothing to general environmental radioactivity, i
f RI/RD88-144 64
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; sample collection; packag-s ing, shipment and handling of samples for of f-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-1 activity measurements (counting) of samples, instrument backgrounds, and ana-I lytical blanks; and data reduction and verification.
l 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 mat ; rials to prepare working standards; and calibration of analytical balances.
G Rl/RD88-144 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-f o rmed.
Areas are cleaned routinely and 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 in the DOE Environmental Dosimeter Intercomparison Project.
6)
Duplicate Samples--Duplicate samples are obtained monthly at randomly 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.
I J
RI/RD88-144 j
66 i
APPENDIX C i
CALIFORNIA REGIONAL WATER QUALITY CONTROL E0ARD CRITER/.A FOR DISCHARGING NONRADIOACTIVE CONSTITUENTS FROM ROCKETDYNE DIVISION, SSFL o
The discharge of an ef fluent in excess.of the limits given in Table C-1 is prohibited.
TABLE C-1 NPDES NO. CA00-01309, ORDER 84-85, EFFECTIVE 11 SEPlEMBER 1984 Discharge Rate Concentration Limit (Ib/ day)a (mg/ liter) 30-Day Constituent Average Maximum lotal dissolved solids 1,267,680 950 Chloride 200,160 150 Sulfate 400,320 300 b
Suspended solids 66,720 b
Settleable solids B00 26,690 30 5
Oil and grease 13,350 15 Chromium 6.67 Fluoride 1,340 1.0 Boron 1,340 1.0 Residual chlorine 0.1 Surf actants (as MBAS) 667 0.5 pH 6.0 to 9.0 a
6 Based on a total waste flow of 160 x 10 gal / day, Not applicable to discharges containing rainfall runof f during or imme-diately af ter periods of rainf all.
Rl/RD88-144 67
APPENDIX D BIBLIOGRAPHY 1.
DOE Order 5484.1, " Environmental Protection, Safety, and Health Protec-
. tion Information Reporting Requirements" (24 February 1981) 2.
DOE Order 5480.l A, " Environmental Protection, Safety, and Health Protec-tion Program for DOE Operations" (13 August 1981) 3.
DOE /EP-0023, "A Guide For:
Environmental Radiological Surveillance at U.S. Department of Energy Installations" 4.
Code of Federa' Regulations, Title 10, Part 20 (10 CFR 20), " Standards for Protection gainst Radiation" 5.
California Rad' i ; ion Control Regulations, California Administrative Code, Title 17, Publi: :'-alth 6.
California Regional Water Quality Control Board, Los Angeles Region, Order No. 84-85, NPDES No. CA0001309, Ef fecti's 17 September 1984 7.
R. E. Moore, 1979.
AIRD05-EPA:
A Computerized Methodology for Estimat-ing Environmental Concentrations and Doses to Man from Airborne Releases of Radionuclides, ORNL-5532 8.
D. E. Dunning, Jr., 1981.
Estimates of Internal Dose Equivalent to 22 Target Organs for Radionuclides Occurring in Routine Releases from Hu-o clear Fuel Cycle Facilities, Volume III, ORNL/NUREG/TM-190 9.
J. P. Corley, ed.1, " Committed Dose Equivalent Tables for U.S. Depart-ment of Energy Population Dose Calculations," U.S. Department of Energy, Office of Operational Safety
- 10. AI-76-21, " Environmental Impact Assessment of Operations at Atomics International Under Special Nuclear Materials License No. SNM-21" (30 April 1976)
- 11. ESG-82-32, Supplement to AI-76-21, " Environmental Assessment of Opera-tions at Energy Systems Group of Rockwell International Under Special Nuclear Materials License SNM-21" (1982 Supplement to AI-76-21, 25 August j
1982)
- 12. NUREG-1077, " Environmental. Impact Appraisal for Renewal of Special Nu-
- clear Material License No. SNM-21" (June 1984)
U.S. Nuclear ReCulatory Commission, Office of Nuclear Material Safety and 13.
Safeguards, " Environmental Impact Appraisal of the Atomics International (AI) Commercial Nuclear Fuel Fabrication Facilities Canoga Park and Chatsworth, California" (September 1977)
~
l RI/RD88-144 69 t
J
1 14.
ESG-00E-13288, " Environmental Analysis of Decommissioned Facilities at Santa Susana Field Laboratory"
]
15.
00E-SF-3 (ESG-DOE-13365), " Radioactive Materials Disposal Facility Leach Field Environmental Evaluation Report" q
i 16.
J. D. Moore, " Radiological Environmental Monitoring Program,"
j N00105P000001, Rocketdyne Division, Rockwell International (9. July 1984) i 17.
J. D. Moore, " Radiological Environmental Monitoring Program Sampling Procedures, Analysis Proceoures, and Radioactivity Measurement Methods,"
N001DWP000008, Rocketdyne Division, Rockwell International (9 July 1984) 18.
J. D. Moore, " Radiological Environmental Monitoring Program Quality Assurance," N001DWP000009, Rocketdyne Division, Rockwell International (25 September 1984) 19.
"lavestigation of Hydrogeologic Conditions - Santa Susana Field Labora-tory, Ventura County, California," Hargis & Associates, Inc., Tucson, Arizona (22 February 1985) e d
4 RI/RD88-144 70 L
APPENDIX E EXTERNAL DISTRIBUTION
(
1.
Radiologic Health Section, Department of Health, California 2.
Occupational Health and Radiation Management, Los Angeles County H';alth Department, California 3.
Resource Management Agency, County of Ventura. California 4.
U.S. Nuclear Regulatory Commission, Region V, Walnut Creek, California 5.
U.S. Nuclear Regulatory Commission, Office for Analysis and Evaluation of Operational Data, Washington, D.C.
6.
U.S. Department of Energy, Environment, Safety and Quality Assurance Divi-sion, San Francisco Operations Office, Oakland, California 7.
U.S. Department of Energy, Of fice of Operational Safety, EP-32, Technical Information Center, Washington, D.C.
8.
Rocky Flats Plant, Health, Safety, and Environment, Golden, Colorado s
v RI/RD88-144 71
APPENDIX F b
ALTERNATIVE UNITS FOR 9 RADIOLOGICAL DATA Conversion In Non-SI In SI Factor From Units Units Non-SI to SI Unitsa Activity concentrations (envi-ronmental)
Airborne particulate and gas pCi/m Bq/m 3.70E - 02 Liquids (water, milk, etc.)
pCi/t Bq/1 3.70E - 02 Solids (soil, sediment, vegetation, foodstuff, etc.)
pC1/g Bq/kg 3.70E - 05 Activity concentrations (effluent)
Gas (air)
(uCi/mt)
Bq/m 3.70E + 10 l
Liquid (uCi/mt)
Bq/t 3.70E + 07 l
Exposure rate (environment)
R/h C/kg h 2.58E - 10 h
Absorbed dose mrad Gy 1.00E - 05 Dose equivalent mrem Sv 1.00E - 05 Dose equivalent rate (commitment) mrem / year Sv/ year 1.00E - 05 "To convert non-SI units to SI units, multiply the non-SI units by the l
I conversion factor.
]
bAdopted because of established convention and use in maximum permissible concentration (MPC) tabulations.
l l
l 3
i RI/RDB8-144 73 f