ML20004D067
| ML20004D067 | |
| Person / Time | |
|---|---|
| Site: | 05000375 |
| Issue date: | 05/27/1981 |
| From: | Johari Moore, Tuttle R EMVROCIE, ROCKWELL INTERNATIONAL CORP. |
| To: | |
| Shared Package | |
| ML20004D062 | List: |
| References | |
| ESG-81-17, NUDOCS 8106080294 | |
| Download: ML20004D067 (57) | |
Text
ESG 81-17
- O .
ENERGY SYSTEMS GROUP ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT 1980 l
l Rockwell International Energy Systems Group 8900 De Soto Avenue Canoga Park Cahfornia 91304 8106080
ESG-01-17 l
c ENERGY SYSTEMS GROUP ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT 1980 i
BY J. D. MOORE APPROVED: ,t 4 R. J. TUTTLE Manager Radiation and Nuclear Safety Rockwell International Energy S(stems Group 8900 De Soto Avenue Canoga Park, Cahfornia 91034 r
e ISSUED: 27 MAY 1981
l CONTENTS l
r
. Page Abstract................................................................. 6
, I. Introduction....................................................... 7 II. Envi ronmental Moni tori ng Summa ry Resul ts . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 A. Radi oacti ve Ma teri al s - 1980. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 B. Nonradioactive Material s - 1980. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 III. Environmental Monitoring Program................................... 27 A. Ge ne ral Des c ri p ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 B. Sampli ng and Sample Preparation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27
- 1. S0i1....................................................... 27
- 2. V e g e ta t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34
- 3. Water...................................................... 34
- 4. Am b i e n t A i r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 C. Cou n ti ng a nd Ca l i b ra ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 D. Nonradioactive Materials....................................... 38 IV. Effluent Monitoring Program........................................ 39 A. Treatnent and Handling......................................... 39 B. Energy Systems Group Facili ty Descriptions . . . . . . . . . . . . . . . . . . . . . 41
- 1. De Soto Site............................................... 41
- 2. Santa Susana Field Laboratories Site....................... 43 C. Estimation of General Population Dose Attributable to ESG 0perations..................................................... 44 Appendices A. Comparison of Environmental Radioactivity Data for 1980 with Previous Years................................................. 50 B. California Regional Water Quality Control Board Criteria for Discharging Nonradicactive Constituents from Rocketdyne Division, SSFL................................................. 56 C. References..................................................... 57 D. External Distribution.......................................... 57 0
ESG-81-17 3
TABLES Page ,
1-A. Soi l Ra d i oa c ti vi ty Da ta -- 1980. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 1-B. Soil Plutonium Radioactivity Data - 1980. . . . . . . . . . . . . . . . . . . . . . . . . . . 18
- 2. Vegetation Radioactivi ty Da ta - 1980. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19
- 3. SSFL Si te -- Domestic Water Radioactivity Data - 1980. . . . . . . . . . . . . . . 19
- 4. Bell Creek and Rocketdyne Site Retention Pond Radioactivity Data - 1980........................................................ 20
- 5. Ambient Ai r Radioacti vi ty Data -- 1980. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21
- 6. De Soto and SSFL Sites - Ambient Radiation Dosimetry Data -- 1980... 25
- 7. Nonradioactive Constituents in Wastewater Discharged to U n re s t r i c te d A rea s -- 19 80 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26
- 8. Sample Station Locations........................................... 31
- 9. Mi nimum Radioactivi ty Detection Limi ts (MDLs) . . . . . . . . . . . . . . . . . . . . . . 37
- 10. Atmospheric Discharges to Unrestricted Areas - 1980................ 40
- 11. Liquid Effluent Discharged to Sanitary Sewer - 1980................ 42
- 12. Su r face Wi nd Co nd i ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45
- 13. Maximum Downwind Plume Centerline Concentrations of Gar.eous Em i s s i o n s -- 19 80 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46
- 14. Population Dose Estimates for Atmospherically Discharged Emi ssions from the De Soto Facili ty - 1980. . . . . . . . . . . . . . . . . . . . . - . . . 47
- 15. +;1ation Dose Estimates for Atmospherically Discharged Emi ssions from SSFL Facili tic; - 1980. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 A-1. Soil Radioactivity Data - 1957 Through 1980........................ 51 A-2. Vegetation Radioactivi ty Data - 1957 Through 1980. . . . . . . . . . . . . . . . . . 52 A-3. SSFL Site Domestic Water Radioactivity Data -- 1957 Throu9h 1980.... 53 A-4. Bell Creek and Rocketdyne Division Retention Pond Radioactivity Data - 1966 Through 1980........................................... 54 A-5. Ambient Air Radioactivity Concentration Data -- 1957 Through 1980... 55 B-1. NPDES No. CA00-01309, Effective September 27, 1976................. 56 j ESG-81-17 4
l
FIGURES
. Page
- 1. Energy Sys tems Group - De Soto Si te. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
, 2. Energy Systems Group - Santa Susana Field Laboratories Site......... 9
- 3. Map of Santa Susana Field Laboratories Site Facilities. . . . . . . . . . . . . . 11
- 4. Map of General Los Angeles Area..................................... 13
- 5. Map of Canoga Park, Simi Valley, Agoura, and Calabasas Sampling Stations............................................................ 28
- 6. Map of De Soto Site and Vicini ty Sampling Stations. . . . . . . . . . . . . . . . . . 29
- 7. Map of Santa Susana Field Laboratories Site Sampling Stations....... 30
- 8. Daily Averaged Long-Lived Airborne Radioactivity at the De Soto and Santa Susana Field Laboratories Sites - 1980.................... 36 i
I l
P l-1 ESG-81-17 5
E ABSTRACT j Environmental and facility effluent radioactivity monitoring at the E.,ergy
- l Systems Group (ESG) of Rockwell International (California operations) is performed
.! by the Radiation and iiuclear Safety Group of the Health, Safety and Radiation -
Services Department. Soil, vegetation, and surface water are routinely sampled q
to a distance of 10 miles from ESG sites. Continuous ambient air sampling and
) radiation monitoring by thermoluminescent dosimetry are performed on-site for measuring airborne radioactivity concentrations and site ambient radiation levels.
Radioactivity in emissions discharged to the at.nosphere from ESG facilities is i continuously sampled and monitored to ensure that levels released to unrestricted c
! areas are within appropriate limits and to identify processes that may require l additional engineering safeguards to minimize radioactivity levels in such dis-
- charges. In addition, selected nonradioactive constituent concentrations in
! surface water discharged to unrestricted areas are detennined. This report l summarizes and discusses monitoring results for 1980.
The random variations observed in the environmental monitoring data indicate that no local source of unnatural radioactive material exists in the environs.
! Ad'.iitionally, the similarity between on-site and off-site results further indi-l tates that the contribu". ion to general environmental radioactivity due to opera-tions of ESG is essentially nonexistent.
] The environmental radioactivity reported herein is attributed to natural sources and to fallout of radioactive material from foreign atmospheric testing of nuclear devices.
i I
l
~ '
ESG-81-17 6
I. INTRODUCTION
- The Energy Systems Group (ESG) of Rockwell International Corporation has been engaged in nuclear energy research and development since 1946. ESG is cur-
- i. rently working on the design, development, fabrication, and testing of components and systems for central station power plants; on the fabrication of nuclear fuel for test and research reactors; and on the Decontamination and Disposition of
! Facilities (D&D) program. Other programs include the development and fabrication of systems for stack gas S02 control, production of gaseous and liquid fuels from coal, and solar and ocean thermal energy development.
The administrative, scientific research, and manufacturing facilities (Fig-ure 1) are located in Canoga Park, California, approximately 23 miles northwest of downtown Los Angeles. The site is level, typical of the San Fernando Valley floor. Certain nuclear programs, under licenses issued by the Nuclear Regulatory
[
Commission (NRC) and the State of California, are conducted here. These include (1) Building 001 uranium fuel production facilities and (2) Building 004 analyti-l cal chemistry laboratories and a gamma irradiation facility. The 290-acre Santa l Susana Field Laboratories (SSFL) site (Figure 2) is located in the Simi Hills of Ventura County, approximately 23 miles northwest of downtown Los Angeres. The
! SSFL site, situated in rugged terrain typical of mountain areas of recent geolog-ical age, is underlain by the Chico formation, which is Upper Cretacious in age.
The site may be described as an irregular plateau sprinkled with outcroppings above the more level patches and with peripherai eroded gullies. Elevations of the site vary from 1650 to 2250 ft above sea level. The surface mantle consists
! of sand and clay soil on sandstone. Both Department of Energy (D0E) and ESG ,
owned facilities share this site, shown in Figure 3. The SSFL also contains
- facilities in which nuclear operations licensed by NRC and the State are con-I ducted. The licensed facilities include
- (1) the Rockwell International Hot Laboratory (RIHL), Building 020; (2) the Nuclear Materials Development Facility (NMDF), Building 055; (3) a neutron radiography facility containing the L-85 nuclear examination and research reactor, Building 093; and (4) several X-ray and radioisotope radiography inspection facilities. The location of these sites in relation to nearby communities is shown in Figure 4.
4 ESG-81-17 7
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g Figure 4.
(Copyright Automobile Club of Southern California.
Map of General Los Angeles Area Reproduced by permission) p F"""
Also 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 optioned area is the Radioactive Material Disposal Facility (RMDF),
Buildings 021 and 022. This facility is used for packaging wastes generated as ,
a result of the D&D program, begun in 1975. Several deactivated nuclear reactor and support facilities, all within the optioned area, are affected by the D&D program. Currently involved are several facilities that had been used for SNAP (Systems for Nuclear Auxiliary Power) reactor test operations, Buildings 024 and 059, and the Sodium Reactor Experiment (SRE), Building 143. No fissile material is located at any of these facilities.
Licensed programs conducted during 1980 included: (1) commercial operation of the L-85 reactor for central staticn power plant operator training and for
! neutron radiography inspection of precision forgings, castings, and electronic and explosive devices for manufacturing defects; (2) the operation of the RIHL for nuclear reactor fuel and system component examination and the fabrication of sealed radiation sources; and (3) the operation of nuclear fuel manufacturing facilities for the production of experimental and test reactor fuel involving enriched uranium, and the development of processes for the fabrication of advanced fuels.
The basic policy for control of radiological and chemical hazards at ESG requires that, through engineering contrcls, adequate containment of such mate-rials be provided and that, through rigid operational controls, facility effluent releases and external radiation levels be reduced to a minimum. The environmen-tal monitoring program provides a .neasure of the effectiveness of the Group safety precedures and of the engineering safeguards incorporated into facility designs. Specific radionuclides in facility effluent or environmental samples are not routinely identified due to the extremely low radioactivity levels nor-mally detected, but would be identified by analytical or radiochemistry techniques if significantly increased radioactivity levels were observed.
m ESG-81-17 14
In addition to environmental monitoring, work area air and atmospherically discharged emissions are continuously monitored or sampled, as appropriate. This
- provides a direct measure of the effectiver.ess 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 ESG sites are referred to as "on-site" stations; those located within a 10-mile radius of a site are referred to as "off-site" stations. The on-site environs of the De Soto and SSFL sites are sampled monthly to detennine the concentration of radioactivity in typical surface soil, vegetation, and water. Soil is sampled on-site semiannually for plutonium analysis. Similar off-site environmental samples, except for plutonium analysis, are obtained quarterly. Continuous on-site and off-site ambient air sampling provides information concerning long-lived airborne particulate radioactivity. On-site ambient radiation monitoring utiliz-ing thermoluminescent dosimetry (TLD), begun in 1971, measures radiation levels in the environs of both the De Soto and SSFL sites and at several off-site locations.
Nonradioactive wastes discharged to unrestricted areas are limited to liquids released to sanitary sewage systems and to surface water drainage systems. No intentional releases of any liquid pollutants are made to unrestricted areas. i Liquid wastes generated at the De Soto site are discharged into the city sewage system. This effluent is. sampled to determine radioactivity. Sanitary sewage from all DOE and ESG facilities at the SSFL site is treated at an on-site sewage plant. The plant outfall drains into retention pond R-2A, located on the adjoin-ing Rocketdyne Division site. The surface water drainage system of the SSFL is composed of catch ponds and open drainage ditches leading to retention pond R-2A.
Water from the pod may be reclaimed as industrial process water, or it may be released off-site into Bell Creek, a tributary of the Los Angeles River. The pond is monitored at discharge for radioactive and nonradioactive pollutants by Rocketdyne Division as required by discharge permits issued to Rocketdyne by the California Regional Water Quality Control Board.
ESG-81-17 15
This report summarizes environmental monitoring results for 1980. A compar-ison of 1980 radioactivity results with results from previous years appears in Appendix A. -
(
4 J
I i
ESG-81-17 16 2
I
II. ENVIRONMENTAL MONITORING
SUMMARY
RESULTS A. RADI0 ACTIVE MATERIALS -- 1980 The sampling and analytical methods used in the environmental monitoring program for radioactive materials are described in Section III.
The average radioactivity concentrations in local soil, vegetation, surface water, and ambient air for 1980 are presented in Tables 1 through 5. In calcu-lating the averaged concentration value for the tables, those individual samples having radioactivity levels less than their minimum detection levels (MDL) are assumed to have a concentration equal to the MDL. This method of data averaging, required by DOE Manual Chapter 0513, affords a significant level of conservatism in the data, as evident in the tables, in that most radioactivity concentrations are reported as "less than" (<) values. Thus, for measurements in which sone apparent radioactivity concentrations are below the MDL, the true averaged value is actually somewhat less than the value reported.
The maximum level of radioactivity detected for a single sample is reported because of its significance in indicating the existence of a major episode or area-wide location of radioactive material deposition. None of the maximum observed values, which occurred randomly during the year as shown in the tables, shows a great increase over the average values beyond natural variability. The ambient air sampling data show no greatly increasing or decreasing trends for most of the year and can be described as generally constant with some increase in local airborne radioactivity levels occurring during the fourth quar + r.
i The results reported in Tables 1-A and 2 show no significant difference between on-site and off-site samples. Table 1-B shows no significant variation in soil plutonium concentrations for the 1980 sample sets. The detected activity 1
is due to a variety of naturally occurring radionuclides, and to radioactive fallout resulting from dispersal of nuclear weapons materials and fission pro-ducts by atmospheric testing. One atmospheric test in the northern hemisphere O
ESG-81-17 17 l
i
(
e TABLE 1-A S0Il RADI0ACTI'e'TY DATA - 1980 Gross Radioactivity (pCi/g)
Maximum Observed -
No. Annual Average Value Value* and Area Activity Samples (95% Confidence Level) Month Observed a 144 (6.0 1 1.5) 10-7 11.4 x 10-7 (January)
On Site g 144 (2.4 0.1) 10-5 11.0 x 10-5 (January) a 48 (5.6 1.5) 10-7 10.3 x 10-7 (April)
Off Site g 48 (2.3 i 0.1) 10-5 3.0 x 10-5 (October)
- Maximum value observed for single sample.
TABLE 1-B S0Il PLUT0NIUM RADI0 ACTIVITY DATA - 1980 9 July 1980 Survey Results 22 DF. ember 1980 Surve) Results Sample 238 238 Pu Pu239 + Pu240 Pu Pu239 + Pu240 Location (pCi/g) (pCi/g) (pCi/g) (pCi/g)
S-56 ( 0.7 2.4) 10-9 (0.5 t 1.3) 10-9 (-0.8 1.4) 10-9 (13.0 3.0) 10-9 S-S7 ( 1.4 3.4) 10-9 (9.5 4.8) 10-9 (-0.3 1 2.3) 10-9 ( 5.6 i 3.2) 10-9 S-58 (-0.2 2.4) 10-9 (1.6 t 2.0) 10-9 ( 0.4 3.1) 10-9 ( 9.9 4.6) 10-9 S-59 (-1.2 2.3) 10-9 (8.2 3.8) 10-9 (-0.8 2.1) 10-9 ( 4.2 2.7) 10-9 S-60 (-1.1 1.9) 10-9 (1.7 1 1.8) 10-9 (-1.6 -9 1.7) 10-9 (29.5 1 6.5) 10 l Note: Minus (-) indicates sample value less than reagent blank.
ESG-81-17 -
18
t 7 40 was announced . ring 1980. Naturally occurring radionuclides include Be , K ,
I Rb 87 , gy W and the uranium and thorium series (including the inert gas radon and its radioactive daughters). Radioactivity from fallout consists primarily 4 of the fission products Sr90 _ y90 , Cs 137 , and PmI47, and also U235 and Pu 239 ,
TABLE 2 VEGETATION RADI0 ACTIVITY DATA - 1980
! Gross Radioactivity l (pCi/g) % of
- Samples No Ash Area Activity e.,pj,3 Dry Weight with Activity
~
Annual Maximum Value* <MDL Average Annual Average Value and Month Value (95% Confidence Level) Observed 4
a 144 (<3.1 2.1) 10 B2.5 2 1.7) 10~7 1.3 x 10 46 i On Site (January)
! S 144 (2.1 ! 0.04) 10"5 (1.60 2 0.C3) 10'4 2.71 x 10-4 0
- (November)
I a 48 (<4.2 3.3)10 (cl.9 ! 1.5) 10~7 5.2 x 10~7 44 Off Site -5 (Octooer) 1 I
6 48 (3.110.06)10 (1.42 2 0.03) 10~4 2.21 x 10'" C (January)
- Maximum value observed for single sample.
TABLE 3
, SSFL SITE - DOMESTIC WATER RADI0 ACTIVITY DATA - 1980 i
Gross Radioactivity j (pCi/ml)
Maximum
- No. Average Value Value and Area Activity Samples (95% Confidence Level) Month Observed ESG-SSFL a 24 (<2.2 2.7) 10-10 <2.2 x 10-10 l (100% <MDL)
B 24 (2.4 0.7) 10-9 3.4 x 10-9 (February)
J
- Maximum value observed for single sample.
t I
ESG-81-17 19
TABLE 4 -
BELL CREEK AND ROCKETDYNE SITE RETENTION POND RADI0 ACTIVITY DATA - 1980 .
Gross Radioactivity Concentration I0 Area Activity 3, j,3 Avera e Value Maximum
- g of 3,,f,,
Guide
- with tivity Confiden Level) Mont bserved Bell Creek a 12 't 4 1.4) 10'7 9. 3 x 10'7 NA 0 Mud No. 54 (February)
(pC1/g) 8 12 (2.3 2 0.1) 10-5 3 0 x 10-5 NA 0
( February)
Pond R-2A a 12 ( 5.1 2 1. 4) 10~7 7.4 x 10~7 NA 0 Mud No. 55 ( December (LCi/g) 8 12 (2.2 0.1) 10-5 2.4x10'g NA 0 (Jan & Nov)
Bell Creek a 12 (<1.8 i 1.5) 10~7 3.6 x 10~7 NA 42 Vegetation ( February)
No. 54 8 12 (1.50 2 0.03) 10'4 2.22 x 10'4 NA ^
(LCi/g-ash) (January)
Bell Creek Vegetation a 12 (<3.1 2.6) 10-8 1.1 x 10-7 NA 42 No. 54 (February (pC1/g 8 12 (2.420.1)10-5 4. 4 x 10'g NA 0 dry weight) ( February)
Bell Creek a -10 12 (<2.3 2 2.7)10 <2. 3 x 10-10 <0.005 100 Water No. 16 (l)
(uci/ml) 8 12 (2.920.8)10-9 5.2 x 10-9 1. 0 0 (October)
Pond Water a 12 (<2.3 2.7)10-10 <2. 3 x 10-10 <0.005 100 No. 6 (1) '
(LC1/ml) 8 12 ( 2. 9 2 0. 7) 10~9 4.7 x 10-9 1.0 8 (Nnvemhari SSFL Pond R-2A a 12 (<2.3 2 2.7)10-10 <2. 3 x 10-10 <0.005 100 Water Nc.12 (1)
(LCi/ml) 8 12 ( 3. 9 0.8) 10~9 5. 7 x 10 9 1.3 0
( November)
- Maximumvalueogservedfor single sample.
+ Guide: 5 x 10- pCi/mla, 3
NA - not applicable, no Guide value having been established.
l All samples were <MDL for 1980.
ESG-81-17 20
I i
(
i TABLE 5
]
, AMBIENT AIR RADI0 ACTIVITY DATA - 1980 Maximum
- Site Activity No. Average Value Value % of
% of Samples
. Location Samples (95% Guide t with Activity Confidence Level) efy$ <MDL 5
De Soto a 685 (<6.5 ? 7.7) 10-15 4.5 x 10-14 <0. 2 2 92 On Site ..
(pCi/ml) 685 (12/28)
- 3. 8 x 10-13 i S (<3.9 1.4) 10-I4 <0.013 47
! (12/25) i 6 -15 SSFL a 1611 (<6.4 7.8) 10 2.5 x 10-14 <10.7 94 i On Site .. (07/11)
(pCi/ml) 8 1611 (<3.6 1.4)10~34 4.5 x 10-13 <0.12 52 I l (12/25)
! SSFL Sewage s
' 5 Treatment a (<6.3 7.6) 10-15 1.8 x 10'I4 <10.5 95 Plant .. 366 (07/09)
Off Site 8 (<3.2 1.6) 10'g4 3.1 x 10-13 <0.11 63 (pCi/ml) (12/e5)
I -15 2.0 x 10-14 <10.5 SSFL Control o (<6.3 7.9)10 97 Center .. 365 (07/11)
Off Site 8 (<3.7 1.4)10~14 3.6 x 10-13 <0.12 62 l (pCi/ml) (12/25) i
- Maximum value observed for single sample.
tGuide: De Soto site, 3 x 10-12 pCi/mla 3 x 10-10 pC1/ml8; 10 CFR 20 Appendix B, SSFL site, 6 x 10-14 uCi/mla, 3 x 10-11 pCi/nl8; 10 CFR 20 Appendix B, CAC 17, and DOE Manual Chapter SMDL =6.1x10g24pCi/ml - Individual daily samples with activity levels of 0 to 6.1 x 10-15 pC1/ml are recorded and averaged as 6.1 x 10-15 pCi/ml
- MDL = 1.2 x 10-14 pCi/ml - Individual daily samples with activity levels of 0 to 1.2 x 10'I4 pCi/ml are recorded and averaged as 1.2 x 10-14 LCi/ml. Indicated average values are upper i
limits, since most data were below the minimum detection levels.
i l
Domestic water used at the SSFL site is obtained from Ventura County Water District No. 17, which also supplies nearby communities, and is distributed on
! site by the same piping system previously used when all facility process water was obtained from on-site wells. Two on-site water wells were operated during 1980 to reduce comsumption of Ventura County domestic water. The well water pro-portion in the blend averaged about 40% for the year for a total well water con-7
, sumption of approximately 7.8 x 10 gal. Pressure for the water system is 1
provided by elevated storage tanks.
4 i~ ESG-81-17 i 21 i
. = - . . . - - _ _ - , - , - - - . . - . _ - - - . ,. -
1 Water from the system is sampled monthly at two widely separated SSFL site locations. The average domestic water radioactivity concentration is presented in Table 3. -
As discussed earlier, surface waters discharged from SSFL facilities and .
the sewage plant effluent drain southward into retention pond R-2A on Rocketdyne property. When full, the pond may be drained into Bell Creek, a tributary of the Los Angeles River in the San Fernando Valley, Los Angeles County. Pursuant to the requirements of Los Angeles Regional Water Quality Control Board Resolu-tion 66-49 of 21 September 1966, a sampling station for evaluating environmental radioactivity in Bell Canyon was established in 1966. It is located approximately 2.5 miles downstream from the southern Rockwell International Corporation boun-dary. Samples, obtained and analyzed monthly, include stream bed mud, vegeta-tion, and water. Average radioactivity concentrations in Rocketdyne and Bell Creek samples are presented in Table 4.
Comparison of the radioacti';ity concentrations in water from the ponds and from Bell Creek with that of the domestic water supply shows no significant variation in either alpha or beta activity.
The SSFL site surface water and the ambient air radioactivity concentration Guide values selected for each site are the most restrictive limits for those radionuclides currently in use at ESG facilities. Radioactivity concentration guide values are those concentration limits adopted by DOE, NRC, and the State of California as maximum permissible concentrations (MPC). The MPC values are dependent on the radionuclide and its behavior as a soluble or an insoluble material. For comparison with results of environmental and effluent monitoring, the lowest MPC value for the various radionuclides present is selected. Accor-dingly, for SSFL site surface water, the Guide values of 5 x 10 6 Ci/ml alpha activity corresponding to Pu 239 and 3 x 10 -7 pCi/ml beta activity corresponding to Sr 90 are appropriate. The corresponding most restrictive Guide value for De Soto site wastewater radioactivity discharged to the sanitary sewage system, ESG-81-17 22
a controlled area, is 8 x 10-4 pCi/ml alpha activity corresponding to U235 and 1 x 10-3 Ci/ml beta activity corresponding to Co60 These values are estab-lished in 10 CFR 20, California Administrative Code Title 17, and DOE Manual I Chapter 0524.
~
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 10-11 pCi/ml for beta activity is due to the presence of Sr 90 in fission products in irradiated nuclear fuel at the SSFL site. The Guide value of 3 x 10-12 pCi/ml for De Soto ambient air alpha activity is due to work with unencapsulated uranium (including depleted uranium). The Guide value of 3 x 10-10 pCi/ml is for Co60 for which the ambient air beta activity Guide is appropriate since it is the most restric-tive limit for beta-emitting radionuclides present at the De Soto site. Guide value percentages are not presented for soil or vegetation data since no concen-tration Guide values have been established.
Ambient air sampling for long-lived particulate alpha and beta radioactivity is performed continuously with automatic sequential samplers at both the De Soto and SSFL sites. Air is drawn through Type HV-70 filter media, which are analyzed for long-lived radioactivity after a minimum 120-h decay period that eliminates
- naturally occurring short-lived particulate radioactivity. The average concen-i trations of ambient air alpha and beta radioactivity for 1980 are presented l
separately in Table 5.
i Radioactivity levels observed in environmental samples for 1980, reported in Tables 1 through 5, compare closely with levels reported for recent years.
l Local environmental radioactivity levels, which result primarily from beta-emit-ting radionuclides and which had shown the effect of fallout during past exten-f sive atmospheric testing of nuclear devices, have decreased and have been generally constant during the past several years. The effects of foreign atmos-pheric nuclear tests continue to be occasionally observed in daily ambient air-borne radioactivity levels. This effect was readily discernible during late l
1980. The long-term effects of airborne radioactivity on surface sample radio-l' activity levels are not discernible for recent years. The continuing relative 1
ESG-81-17 I
I 23 i
. - , - - . - - - - ~- , ,, . - , - , , - - ~
l constancy in environmental radioactivity levels is due primarily to the dominance of naturally occurring radionuclides in the environmant and to the longer-life fission product radioactivity from aged fallout. -
Site ambient radiation monitoring is performed with thermoluminescent dosi- .
meters. Each dosimeter contains two calcium fluoride (CaF :Mn) low background, 2
bulb-type chip dosimeters. The dosimeter sets are placed et locations on or near the perimeters of the De Soto and SSFL sites. Each dosimeter, sealed in a light-proof energy compensation shield, is installed in a polyethylene container which is mounted %1 m above ground at each location. The dosimeters are exchanged and evaluated quarterly. There were 13 on-site TLD monitoring locations used during the year. Three additional dosimeter sets, located at locations up to 10 miles from the ESG sites, are similarly evaluated to determine the local area off-site ambient radiation level, which averaged 0.019 mrem /h for 1980. The averaged radiation dose rate and equivalent annual dose monitored at each dosimeter location are presented in Table 6.
The table shows that radiation dose rates and equivalent annual doses moni-tored on-site are nearly identical to levels monitored at three widely separated off-site locations. These data include natural background radiation from cosmic radiati'an, radionuclides in the soil, radon and thoron in the atmosphere, and radioactive fallout from nuclear weapons tests. Locally, the natural background radiation level is approximately 160 mrem / year. The small variability observed in the data is attributed to differences in elevation and geologic conditions at the various dosimeter locations. Since the data for the on-site and off-site locations are nearly identical, no measurable radiation dose to the general population or to individuals in uncontrolled areas resulted from ESG operations.
B. NONRADI0 ACTIVE MATERIALS - 1980 Processed wastewater and most collected surface runoff discharged from the SSFL site flows to retention pond R-2A, operated by Rocketdyne. Water samples from the pond are analyzed for various constituents, as required by the Regional ,
Water Quality Control Board for each discharge to Bell Canyon. Such discharges ESG-81-17 24
TABLE 6
< DE S0TO AND SSFL SITES - AMBIENT RADIATION DOSIMETRY DATA -- 1980 Equivalent Average Dose Rate Annual Dose TCD (mrem /h) (mrem) 1 De Soto 0.019 166 2 De Soto 0.017 149 3 De Soto 0.016 140 4 De Soto 0.018 158 5 De Soto 0.019 166 6 De Soto 0.022 193 7 De Soto 0.020 175 1 SSFL 0.018 158 2 SSFL 0.019 166 3 SSFL 0.021 184 4 SSFL 0.020* 175 5 SSFL 0.018*t 158 6 SSFL 0.018 158 1 Off-Site Control 0.018 158 2 Off-Site Control 0.019 166 3 Off-Site Control 0.019 166 l
- Excludes second quarter data due to missing dosimeter.
tExcludes third quarter data due to damage to the dosimeter from a brush fire.
I are normally required only as a result of excessive rainfall run-off. During such releases, the NPDES permit concentration limits for turbidity and for sus-pended and settleable solids do not apply. The results of analyses for each
! discharge for 1980, most of which were rainfall-related discharges, are presented in Table 7.
ESG-81-17 25
F l TA8tt 7 40hAAD10ACTitt C0h5f! Tut 4T514 hAstinAfte DISCHARGED 70 UhattitICTED ARIA 5 - 1980 (Analysts Results for usstemater Otscharged from Pond R.24 to 8 ell Creen en Date Indicated - Sample Station W.12)
Janu ary 9* Janu ary 16* February 11* February 11 Coast s tuents g ,, g ,, , , , g ,,
Result Guide Result Guise Result Guide Result Gutae Total 01sscIved Solids (og/1) 300 31.6 354 37.5 190 20.0 56 5.9 Chlertoe (og/1) 32 21.3 37 24.7 21 14.0 51 34.0 Sulf ate (ag/1) 83 27.7 85 28.3 44 14.7 106 35.3 kwended Solids' (eg/1) 58 38.7 18 12.0 75 50 10 6.7 5ettleetle solids' (al/1) <0.1 < 33. 3 < 0.1 < 3 3. 3 <0.1 < 33. 5 = 0.1 a 33. 3 8005 (eg/1) 6 10.0 11 18.3 5 8.3 hA .
011 and Grease (eg/1) 4 26.7 <1 6. 7 3 20 <1 4.7 furbidity (TV) 38 . 21 . 72 - 6 .
C%catum (og/1) U.004 40.0 0.005 60.0 0.007 70.0 0.004 40.0 Flaortde (ag/1) 0. 7 70.0 0. 9 90.0 0.6 60.0 1.0 400.0 Soron (ag/1) <0.2 <20.0 v.3 30.0 < 0. 2 < 20. 0 0.2 20.0 Residual Chlorine (eg/1) < 0. 04 < 40. 0 <0.04 -40.0 <0.04 < 40.0 < 0.04 < 40.0 Feca) Coltform (MP4/100 ml) =2.2 a t.5 <2.2 <9.5 5.1 22.2 5.1 22.2 Surfactants (NAS) 0.02 4.0 0.04 4.0 0.01 20.0 0.02 4.0 pt4 8.2 7.8 7.9 8.4 Ratafs11 (In.) 4.5 3.0 Included to February 13 I I Estlaated *ataf all Runoff (gal) 9 a 10 6 a 10 Same 0 6 Release Volee (gel) 1.7 s 10 1.2 a 10 Same February 13* February 20* March 1 March 3*
Constituents 1 of 5 of 1 of 1 of Result Guide Result Guide Result Guide Result Guide total Olssolved Solids (eg/1) 247 26.0 142 14.9 359 37.8 208 21.9 Chloride (og/1) 24 16.0 8 5.3 38 25.3 20. 13.3 Sulfate (og/1) to 20.0 36 12.0 98 32.7 47 15.7 Sugendcs Solte.' (ag/1) 85 56.7 24 16.0 6 4.0 80 53.3 5ettleable Solnis' (al/l) 0. 4 133.0 0.2 66.6 = 0.1 < 3 3.3 <0.1 < 3 3. 3 80Dg (og/1) 9 15.0 1 1.7 hA , 3 5.0 011 and Grease (eg/1) 2 13.3 <1 <6.7 <1 < 6. 7 <1 < 6. 7 Turtidtty (70) 128 . 52 - 8 . 45 .
Chroete (og/1) 0.022 220.0 0.020 200.0 0.010 100.0 0.010 100.0 Fluoride (ag/1) 0.6 60.0 0. 5 $0.0 0.9 90.0 0. 7 70.0 Boron (ag/1) <0.2 < 20.0 <0.2 < 20. 0 0.2 20.0 0.2 20.0 Residual Chlori'io (ag/1) 0.04 < 40. 0 < 0. 01 <10.0 < 0.04 < 40. 0 <0.04 < 40.0 Fecal Collform (*Fn/100 ol) 9. 2 40.0 >16 '49.5 MA . 2.2 9.6 Surf actants (9AS) 0.02 10.0 <3.01 < 20. 0 0.1 20.0 0.2 4.0
'rH B.2 7. 7 7.9 7.8 Ratafall (In.) 4.2 9.6 2.81 8
5.6 a 10 I Estimated Rataf all Ru n off (gal) 8.4 s 10 1.92 a 10 5
Release votee (gal) 1.5 a 106 1 a 10 6 1.5 a 10 1.35 a 100 March 16* May 2* hoveseer to Decenter 4*
Constt twents g ,, g ,, g ,, g ,,
Result Guide Result Guide Result Guide Result Guide Total Dissolved Solids (eg/I) 449 47.3 395 41.6 664 69.9 421 44.3 Chloride (mg/1) 42 28.0 57 38.0 90 60.0 50 33.3 Sulfate (og/I) 98 32. 7 110 36.7 142 47.3 111 37.0 Suspeaded Solids' (eg/1) 15 10.0 16 10.7 11 7. 3 85 56.7 5ettleable Solids' (el/I) < 0.1 < 33. 3 <0.1 < 3 3. 3 < 0.1 < 33. 3 0.2 66.6 8005 (eg/1) 6 10.0 3 5.0 3. 5.0 30 50.0 01 and Grease (eg/1) <1 < 6. 7 <1 < 6. 7 <1 <6.7 7 46.7 Turtidtty (YU) 52 . 13 . 3 . 33 .
Chrost um (eg/1) 0.004 40.0 0.003 30.0 0.002 20.0 0.001 10.0 Fluoride (ag/1) 0. 7 70.0 0.7 70.0 0.8 80.0 0.6 60.0 Soron (og/1) 0. 3 30.0 0.2 20.0 0.2 20.0 0.2 20.0 Restdual Chlottae leg /1) 0.04 40.0 < 0. 04 < 40.0 <0.04 < 40. 0 0.04 40.0 Fecal Califore (MPt/100 ml) <2.2 9.6 < 2.2 9.6 >16 >69. 5 9.2 40.0 bef actants (alas) 0.03 6.0 0.03 0.05 0.01 2.0 pH 8. 3 8.1 8.1 8. 0 Rataf all (tr.) 0.56 0.15 1.07 Estimated Rataf all Runof f (gal) 1.1 a 10 I
3 a 10 6 2.1 a 10 6
Release votee (gal) 1.s a 10 6 1.8 a 10 0 ,
2.3 a 10 1.3 a 10 .
hA
- tot Avatlable; analysis not requested er not performed.
- Ratafall related discharge.
- 90t appitcatie to discnarges cogtaining catafati runoff during er issnedtately af*er periods of reinfall.
Note: Pond R-2A capacity . 2.5 a 10 gs).
ESG-81-17 26
III. ENVIRONMENTAL MONITORING PROGRAM A. GENERAL DESCRIPTION Soil and vegetation sample collection and analysis for radioactivity were
~
initiated in 1952, in the Downey, California area, where the Energy Systems Group was initially located. Environmental sampling was subsequently extended to the then proposed SRE site in the Simi Hills in May of 1954. In addition, sampling was begun in the Burro Flats area, southwest of SRE, where other nuclear instal-lations were planned and are currently in operation. The Downey area survey was terminated when nuclear activities were relocated to Canoga Park in 1955. The primary purpose of tne environmerital monitoring program is to survey environmen-tal radioactivity adequately to ensure that ESG operations do not contribute significantly to environmental radioactivity. The locations of sampling stations are shown in Figures 5 through 7 and listed in Table 8.
B. SAMPLING AND SAMPLE PREPARATION
- 1. Soil Soil is analyzed for radioactivity to monitor for any significant increase in radioactive deposition by fallout from airborne radioactivity. Since soil is naturally radioactive and has been contaminated by atmospheric testing of nuclear j weapons, a general background level of radioactivity exists. The data are moni-l tored for increases beyond the natural variability of this background.
Surface soil types available for sampling range from decomposed granite to clay and loam. Samples are taken from the top 1-cm layer of undisturbed ground surface for gross radioactivity analysis and to a depth of 5 cm for plutonium analysis. The soil samples are packaged in plastic containers and returned to the laboratory for analysis.
Sample preparation for gross radioactivity determination consists of trans-U ferring the soils to Pyrex beakers and drying in a muffle furnace at 'G00 C for
. ESG-81-17 27
T APO CANYON
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% 413190 Figure 5. M5p of Canoga Park, Simi Valley, Agoura, and Calabasas Sampling Stations
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UM 7. Map of Santa Susana Field Laboratories Site Sampling Stations
TABLE 8 SAMPLE STATION LOCATIONS (Sheet 1 of 3)
Station Location SV-1 SSFL Site, Bldg. 143 SV-2 SSFL Site, Bldg. 143 Perimeter Drainage System SV-3 SSFL Site, Bldg. 064 SV-4 SSFL Site, Bldg. 020 ,
SV-5 SSFL Site, Bldg. 363 SV-6 Rocketdyne Site Interim Retention Pond SV-10 SSFL Site Access Road SV-12 SSFL Site, Bldg. 093 (L-85 Reactor)
SV-13 SSFL Site, at SRE Water Retention Pond SV-14 SSFL Site, Bldg. 028 SV-19 SSFL Site Entrance, Woolsey Canyon SV-24 De Soto Site, Bldg. 004 SV-25 De Soto Avenue and Plummer Street SV-26 Mason Avenue and Nordhoff Street SV-27 De Soto Avenue and Parthenia Street SV-28 Canoga Avenue and Nordhoff Street SV-31 Simi Valley, Alamo Avenue and Sycamore Road
( SV-40 Agoura - Kanan Road and Ventura Freeway SV-41 Calabasas - Parkway Calabasas and Ventura Freeway SV-42 SSFL Site, Bldg. 886 SV-47 Chatsworth Reservoir North Boundary SV-51 SSFL Site, Bldg. 029 ,
SV-52 SSFL Site, Burro Flats Drainage Control Pond, G Street and i 17th Street SV-53 Rocketdyne Site Pond R-2A Spillway, Head of Bell Canyon SV-54 Bell Creek
, S-55 Rocketdyne Site Retention Pond R-2A (Pond Bottom Mud)
S-56 SSFL Site, F Street and 24th Street
- SV - Soil and Vegetation Sample Station I S - Soil Sample Station ESG-81-17 I 31 i
i a, , -
TABLE 8 SAMPLE STATION LOCATIONS (Sheet 2 of 3)
Staticn Location S-57 SSFL Site, J Street at Bldg. 055
~
S-58 SSFL Site, Bldg. 353 S-59 Rocketdyne Site Test Area CTL 4 S-60 Rocketdyne Site Retention Pond R-2A W-6 Rocketdyne Site Interim Retention Pond (drains to Pond R-2A)
W-7 SSFL Site Domestic Water, Bldg. 003 W-11 SSFL- Site Domestic Water, Bldg. 363 W-12 Rocketdyne Site Area II Final Retention Pond.R-2A W-16 Bell Creek A-1 De Soto Site, Bldg. 001 Roof A-2 De Soto Site, Bldg. 004 Roof A-3 SSFL Site, Bldg. 009, West Side A-4 SSFL Site, Bldg. 011, West Side '
A-5 Rocketdyne Site, Bldg. 600, North Side A-6 Rocketdyne Site, Bldg. 207, North Side =
A-7 SSFL Site, Bldg. 074, South Side A-8 SSFL Site, Bldg. 143, West Side A-9 SSFL Site, Bldg. 363, West Side TLD-1 De Soto Site, South of Bldg.102 TLD-2 De Soto Site, West Boundary TLD-3 De Soto Site, Guard Post No. 1, Bldg. 201 I
TLD-4 De Soto Site, East Fence TLD-5 De Soto Site, North Boundary TLD-6 De Soto Site, East Boundary TLD-7 De Soto Site, South Boundary l
i TLD-1 SSFL Site, Bldg. 114 l
S - Soil Sample Station W - Water Sample Station A - Air Sampler Station ,. '
TLD - Thermoluminescent Dosimeter Location ESG-81-17 32
TABLE 8 3 AMPLE STATION LOCATIONS (Sheet 3 of 3)
Station Location TLD-2 SSFL Site, SRE Water Retention Pond
~
TLD-3 SSFL Site, Electric Substation No. 719 TLD-4 SSFL Site, West Boundary on H Street TLD-5 SSFL Site, at Southwest Boundary TLD-6 SSFL Site, Bldg. 854 TLD-1 Off Site, Northridge TLD-2 Off Site, Simi Valley TLD-3 Off Site, Northridge TLD - Thermoluminescent Dosimeter Location i
l l
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, ESG-81-17 l
33
8 h. After cooling, the soil is sieved to obtain uniform particle size. Two-gram aliquots of the sieved soil are weighed into copper planchets. The soil is wetted in the planchet with alcohol, evenly distributed to obtain unifonn sample thick- ,
ness, dried, and counted for alpha and beta radiation. Soil plutonium analysis is performed according to the guidelines specified in U.S. NRC Regulatory Guide 4.5 titled " Measurements of Radionuclides in the Environment-Sampling and Analy-sis of Plutonium in Soil" by a certified independent testing laboratory.
- 2. Vegetation The analysis of vegetation, performed as an adjunct to the soil analysis, is done to determine the uptake of radioactivity by plants. These plants do not contribute to the human food chain, and there is no significant agriculture or grazing in the immediate neighborhood of either site.
Vegetation samples obtained in the field are of the same perennial plant
, types, wherc ter possible; these are usually sunflower or wild tobacco. Vegeta-tion leaves are stripped from plants and placed in ice cream cartons for transfer to the laboratory for analysis. Ordinarily, plant roo'. systems are not analyzed.
Vegetation is first vashed with tap water to remove foreign matter and then thoroughly rinsed with distilled water. Washed vegetation is dried in tared beakers at 100 C for 24 h for dry weight determination, then ashed in a muffle furnace at N500U C for 8 h, producing a completely burned ash. One-gram aliquots of pulverized ash from each beaker are weighed into copper planchets. The vege-tation ash is wetted in the planchet with alcohol, evenly distributed to obtain uniform sample thickness, dried, and counted for alpha and beta radiation. The dry / ash weight ratio is used for determining the equivalent cry weight gross radioactivity concentration value.
- 3. Water Surface and domestic supply water sampler vc cotained monthly at the SSFL site and from Bell Creek. The water is d y um 1-liter polyethylene bottles and transferred to the. laboratory.
ESG-81-17 34 i
Five-hundred-milliliter volumes of water are evaporated to dryness in crys-U tallizing dishes at 4 0 C. The residual salts are redissolved into distilled water, transferred to planchets, dried under heat lamps, and counted for alpha and beta radiation.
~
- 4. Ambient Air Air sampling is performed continuously at the De Soto and SSFL sites with dutomatic air samplers, operating on 24-h sampling cycles. Airborne particulate radioactivity is collected on Type HV-70 filter media, which are automatically changed daily at the end of each sampling period. The samples are counted for alpha and beta radiation following a minimum 120-h decay period. The volume of a typical daily ambient air sample is approximately 25 m3, Figure 8 is a graph of the daily averaged long-lived alpha and beta ambient air radioactivity concentrations for the De Soto and SSFL sites during 1980. The average beta concentration for each month is also indicated by horizontal bars.
The graph shows a generally increasing trend in airborne radioactivity during the ;
final quarter of the year. Several transient peak concentration levels were observed within the general trend. This activity is attributed to a foreign atmospheric test of a nuclear device during October.
I l
C. COUNTING AND CALIBRATION Enironmental soil, vegetation, water, and ambient air samples are counted for alpha and beta radiation with a low-background gas flow proportional counting i system. The system is capable of simultaneously counting both alpha and net beta radiation. The sample-detector configuration provides a nearly 2n geometry. The thin-window detector is continually purged with methane counting gas. A preset time mode of operation is used for all samples. The minimum detection limits shown in Table 9 were determined by using typical values for counting time,
- system efficiencies for detecting alpha and beta radiation, background countrates (approximately 0.05 cpm a and 1.0 cpm 8), and sample sin. For the table, the l-ESG-81-17 35 i
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mir.imum statistically significant amount of radioactivity, irrespective of sample configuration, is taken as that amount equal in cour.trate to three times the
- standard deviation of the system background countrate.
e TABLE 9 MINIMUM RADI0 ACTIVITY DETECTION LIMITS (MDLs)
Sample Activity Minimum Detection Limits
-8 Ci/g a (5.7 6.8) 10
" -7 Ci/g s (2.3 2.3) 10 a (1.1 1.4) 10-7 Ci/g ash ege adon 3.7) 10-7 uCi/g ash 8 (3.7 a (2.2 2.7) 10-10 Ci/ml ater -10 s (6.2 6.2) 10 Ci/ml a (6.1 8.0) 10-15 Ci/ml Ar s (1.2 1.3) 10-14 Ci/ml)
Counting system efficiencies are determined routinely with Ra-D+E+F (with alphaabsorber),Cl 36 , Th 230 ,U 235 , and Pu 239 standard sources and with K40, in :
the form of standard reagent grade kcl, whicn is used to simulate soil and vege-tation samples. Self-absorption standards are made by dividing sieved kcl into samples, increasing in mass by 200-mg increments, from 100 to 3000 mg. The sam-ples are placed in copper planchets, of the type used for environmental samples, and counted. The ratio of sample activity to the observed net countrate for each sample is plotted as a function of sample weight. The correction factor (ratio) corresponding to sainple weight may be obtained from the graph. The product of
( the correction factor and the net sample countrate yields the sample activity (dpm). This method has been proven usable by applying it to various-sized ali-quots of uniformly mixed environmental samples and observing that the resultant specific activities fell within the expected statistial counting errer.
ESG-81-17*
37
I Since the observed radioactivity in environmental samples results primarily from natural and weapons-testing sources, and is at such low concentrations, no effort is made to identify individual radionuclides. The detection of signifi- .
cant levels of radioactivity would lead to an investigation of the radioactive material involved, the sources, and the possible causes. ,
D. NONRADI0 ACTIVE MATERIALS Rockwell International Corporation, Rocketdyne Division, 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 Con-trol Act. The permit, NPDES No. CA0001309, became effective on 27 September 1976 and supersedes all previously held permits for wastewater discharge from the Rocketdyne Division, SSFL. Discharge of overflow and storm runoff is only per-mitted into Bell Creek from water reclamation retention ponds. Discharge gener-ally occurs only during and immediately after periods of heavy rainfall or during extended periods of rocket engine testing.
Only one of the retention ponds receives influent directly from the ESG SSFL site. It is identified as retention pond R-2A, Wter Sample Station W-12 in Table 8. The influent includes sewage treatment plant effluent and surface run-off water. Grab-type water samples, taken at the retention pond prior to a dis-charge, are analyzed for nonradioactive chemical constituents and for radioactiv-ity by a California State certified analytical testing laboratory. The specific constituents analyzed for, and their respective limitations in discharged waste-water, are presented in Appendix B. Wastewater originating from facilities located throughout the SSFL site is collected at the retention pond. The point of origin of nonradioactive constituents normally found in wastewater is impos-sible to detennine; however, in the event of excessive amounts of any of these materials in wastewater, the origin may be determined from the knowledge of facility operations involving their use. Twelve off-site discharges of waste-water from Pond R-2A occurred during 1980. ..
ESG-81-17 38 l
IV. EFFLUENT MONITORING PROGRAM
- Effluents that may contain radioactive material are generated at ESG facili-ties as the result of operations performed under contract to DOE, under NRC Special Nuclear Materials License SNM-21, and under State of California Radio-active Material License 0015-71. The specific facilities are !dentified as Buildings 001 and 004 at the De Soto site, and Buildings 020, 021, 022, and 055 at the Santa Susana site, SSFL.
A. TREATMENT AND HANDLING Waste streams released to unrestricted areas are limited, in all cases, to gaseous emissions. No contaminated liquids are discharged to unrestricted areas.
The level of radioactivity contained in all atmospheric discharges is reduced to the lowest values by passing the emissions through certified, high-efficiency particulate air (HEPA) filters. These emissions are sampled for par-ticulate radioactive materials by means of continuously operating stack exhaust samplers at the points of release. In addition, stack monitors installed at i
Buildings 020 and 055 orovide automatic alann capability in the event of the release of gaseous or particulate activity from Building 020 and particulate activity from Building C55. The HEPA filters used for filtering gaseous emissions are 99.97% efficient for particles of 0.3-pm diameter. Particle filtration efficiency increases for particles above and below this size.
l l
The average concentration and total radioactivity in gaseous releases to l unrestricted areas are shown in Table 10. The effectiveness of the air cleaning systems is evident from the fact that, in most cases, the gaseous emissions are I less radioactive than is ambient air. The total shows that no significant quantities of radioactivity were released in 1980.
Liquid wastes released to sanitary sewage systems, a controlled area as provided for by CAC 17 and 10 CFR 20, are generated at the De Soto site only.
ESG-81-17 1 39 L
1 TABLE 10 ATMOSPHERIC DISCHARGES TO UNRESTRICTED AREAS - 1980 Approximate Sampling Period Total % Of Approximate Annual Maximum Radfo-MI"I""* T ft Emissions Activity Avera e Observed activity . Sd*PleS Buildin9 Monitored Detection Concentration Guide with Activity Volume Limit Concentration Released
( Cf/ml) *NL (ft3) (pCi/ml) (pCi/ml) (Ci) 10 < 1. 0 x 10~I4 1.8 x 10-13 < 5. 3 x 10-6 <0.33 46 001 1. 9 x 10 a 1. 9 x 10-16 De Soto -16 -15 -I4 37 6 6.I x 10 <8. 2 x 10 9. 4 x 10 < 4. 3 x 10-6 <0.003
-15 004 2.4 x 10 10 a 2.5 x 10 -16 <1.2 x 10 1.4 x 10-14 <1. 0 x 10-6 <0.04 38 De Soto -6 0
8.7 x 10 -16 < 7. 3 x 10-15 1.1 x 10-13 < 4. 9 x 10 <0.002 34 rri 020 1. 3 x 10 10 a 0.9 x 10 -16 <4. 6 x 10-16 1. 4 x 10-15 <1. 7 x 10-7 <0.77 15 4.6 x 10'I4 2.4 x 10-13 1. 7 x 10-5 0.15 0 g 8 3.0 x 10-16 021- 1. 3 x 10 10 a 1.0 x 10-16 <1.6 x 10
-16 5.7 x 10 -16 <6.1 x 10'8 <0.27 65
[
u 022 SSFL 0
3.1 x 10-16 < 4. 7 x 10-15 3. 5 x 10'I4 <1.7 x 10-6 'O.02 10 9 -16 -16 -15 < 8. 2 x 10-8 <0.62 94 055 7.9 x 10 a 2. 7 x 10 <3. 7 x 10 4. 8 x 10 SSFL 8 8.9 x 10-16 <4 9 x 10-15 3. 5 x 10'I4 <1.1 x 10-6 <0.002 12 Annual average ambient air . Total <3. 5 x 10-5 radioactivity concentration - 1980 a < 6.4 x 10 .5
~I4 8 < 3. 6 x 10
-12 pCi/ml alpha, 3 x 10 -10 4 Guide: De Soto site, 3 x 10 Ci/ml beta,10 Cg 20 Appendix B.
! SSFL site, 6 x 10-14 pCi/ml alpha, 3 x 10-11 pCi/ml beta 3 x 10' pCi/ml beta (055 only); 10 CFR 20 Appendix B, CAC-17, and OCE Manual Chapter 0524.
Note: All release points are at the Stack Exit I
l l
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Liquid wastes are discharged from Building 001 following analysis for radioactiv-ity concentration. There is no continuous flow. Building 004 chemical wastes
. are released to an automatic discharge cycle retention tank system which periodi-cally samples and composites aliquots of the tank contents prior to each dis-6 charge of a fixed volume of wastewater to the facility sanitary sewerage. No radioactive liquid effluents are released from Santa Susana Buildings 020, 021, 022, or 055. Liquid radioactive waste generated at SSFL is solidifid for land burial. The average concentration and total radioactivity in effluents discharged are shown in Table 11.
B. ENERGY SYSTEMS GROUP FACILITY DESCRIPTIONS
- 1. De Soto Site
- a. Building 001 - NRC and California State Licensed Activities J
j Operations at Building 001 which may generate radioactive effluents consist l of production operations associated with the manufacture of enriched uranium fuel elements. Only atmospherically discharged emissions are released from the build-i ing to uncontrolled areas. Following analysis for radioactivity concentration, liquid wastes are released to the Janitary sewage systent, which is considered a controlled area, as provided by CAC 17 and 10 CFR 20. Nuclear fuel material handled in unencapsulated form in this facility contains the uranium isotopes 234 U ,U 235 ,U 236 , and U 238 ,
- b. Building 004 - NRC and California State Licensed Activities Operations at Building 004 that may generate radioactive effluents consist l
l of research studies in physics and chemistry, and the chemical analysis of small quantities of fuel materials, usually limited to a few grams. Only atmospheric-ally discharged emissions are released from the building to uncontrolled areas.
Liquid laboratory wastes are released to an interim retention tank installation which samples and retains an aliquot of wastewater each time a fixed volume is released to the facility sanitary sewage system. The aliquots are composited and ESG-81-17 41
l TABLE 11 LIQUID EFFLUENT DISCHARGED TO SANITARY SEWER - 1980 Sample Approximate Annual Total Appr mate Average M Radioactivity % of f Building Point of Effluent Activity Observ d Release Volume Monitored Conc ntration Concentration ne ed Guide
( Ci/ml)
-8 -7 -5 a 1.2 x 10-9 <7. 3 x 10 4.1 x 10 1.3 x 10 < 0.009 Retention 48,000 001 -9 -8 -7 Tank 3.7 x 10 <6.2 x 10 2.8 x 10 1.1 x 10-5 < 0. 006 g 8
-9 -7 <0.003 a a 1.2 x 10 <2.4 x 10-0 1.5 x 10 <1.6 x 10-4 ro ~ Flow 1,717,000 004 5 -7 3.7 x 10-9 <6.3 x.10-8 6. 5 x 10 <4.1 x 10-4 <0.006 h Sampler B 0
i 020* - - -
021 - 022*
0 - -
055* 0 - -
- All liquid radioactive wastes are solidified and land buried as dry waste.
tGuide: f5 x 10-4 pCi/ml alpha,1 x 10-3 pCi/al beta; 10 CFR 20 Anpendix B, CAC-17 5% of samples <MDL: 52.3% alpha activity, 47.6% beta activity
analyzed for radioactivity. Nuclear fuel material handled in unencapsulated form in this facility contains the uranium isotopes U 234 U 235 ,U 236 ,and U 238 o Major quantities of other radionuclides in encapsulated fora include Co 60 and 147 Pm . No significant quantities of these radionuclides were released.
- 2. Santa Susana Field Laboratories Site
- a. Building 020 - NRC and California State Licensed Activities Operations at Building 020 that may generate radioactive effluents consist of hot cell examination of irradiated nuclear fuels and reactor components. Only atmospherically discharged emissions are released from the building to uncun-trolled areas. The discharge may contain particulate material, as well as radio-active gases, depending on the operations being performed and the history of the irradiated fuel or other material. The chemical form of such materials may be U metal, UO2 , UC, mixed fission products, and various activation products. No radioactive liquid waste is released from the facility. Radioactive material handled in unencapsulated form in this facility includes the following radio-nuclides: Th 232 ,U 233 ,U 234 ,U 235 ,U 236 , and U 238 as constituents in the various fuel materials; and Cs 137 , 3790, Kr85, and Pm 147 as mixed fission products.
11
- b. puildings 021 and 022 - 00E Contract Activities Operations at Buildings 021 and 022 that may generate radioactive effluents consist of the processing, packaging, and temporary storage of liquid and dry I
radioactive waste material for disposal. Only atmospherically discharged emis-sions are released from the building to uncontrolled areas. No radioactive liquid waste is released from the facility. Nuclear fuel material handled in encapsulated or unencapsulated form contains the uranium isotopes U 234 ,U 235 ,
U 236
,U 238 , plus Cs 137 , Sr 90 , and Pm 147 as mixed fission products.
4 Y
s.
ESG-81-17 43
- c. Building 055 - NRC and California State Licensed Activities Operations at Building 055 that may generate radioactive effluents consist
~
of fabricating depleted uranium carbide fuel pellets and converting UC waste to the oxide state. Only atmospherically discharged emissions are released from the facility to uncontrolled areas. No radioactive liquid waste is released from the --
facility.
The various fuel materials (depleted and enriched uranium and plutonium) contain the following radionuclides: U 234 ,U 235 ,U 236 ,U 238 , Pu 238 , Pu 239 ,
240 241 241 Pu , Pu , and Am ,
C. ESTIMATION OF GENERAL POPULATION DOSE ATTRIBUTABLE TO ESG OPERATIONS The release of airborne material at the De Soto site for summer seascn weather conditions would generally be under a subsidence inversion into an atmos-phere that is typical of slight neutral to lapse conditions. Nocturnal cooling inversions, although present, are relatively shallow in extent. During the sum-mer, a subsidence inversion is present almost every day. The base and top of m >; inversion usually lie below the elevation of the SSFL site. Thus, any atmospheric release under this condition from the SSFL site would result in Pas-quill Type D lofting diffusion conditions above the inversion and considerable atmospheric dispersion prior to diffusion, if any, through the inversion into the Simi or San Fernando Valleys. In the winter season, the Pacific high-pressure cell shifts to the south and the subsidence inversion is usually absent. The surface air flow is then dominated by frontal activity moving through the area or to the east, resulting in high-pressure systems in the great basin region.
Frontal passages through the area during winter are generally accompanied by pre-cipitation. Diffusion characteristics are highly variable depending on the loca-tion of the front. Generally, a light to moderate southwesterly wind precedes these frontal passages introducing a strang onshore flow of marine air, and lapse rates which are slightly neutral. Wind speeds increase as the frontal systems approach, enhancing diffusion. The diffusion characte; i . tics of the frontal passage are lapse conditioas with light to moderate northerly winds. Surface _
wind directions and average windspeed for the local area are summarized in Table 12.
l ESG-81-17 44
TABLE 12 SURFACE WIND CONDITIONS: FREQUENCIES OF WIND DIRECTIONS
, AND TRUE-AVERAGE WIND SPEEDS Wind Speeds for Each Stability Class
. Wind Toward Frequency A B C D E F G N 0.188 1.84 2.92 4.33 3.78 3.70 1.79 0.0 NNW 0.118 1.89 2.87 4.13 3.84 3.73 1.85 0.0 NW 0.085 1.86 2.65 3.62 4.01 3.98 1.92 0.0 WNW 0.131 1.85 2.58 3.75 4.02 4.03 1.95 0.0 W 0.053 1.31- 1.74 2.70 2.82 3.58 1.75 0.0 WSW 0.024 1.16 1.34 2.37 3.25 3.35 1.49 0.0 SW 0.017 1.55 1.05 2.30 5.79 3.47 1.27 0.0 SSW 0.021 1.29 1.22 2.65 5.67 3.37 1.50 0.0 S 0.043 1.16 0.97 2.04 4.80 3.44 1.63 0.0 j SSE 0.059 1.36 1.23 2.75 5.51 3.65 1.59 0.0 SE 0.052 1.46 1.13 2.89 5.32 3.72 1.52 0.0' ESE 0.046 1.24 1.24 2.58 4.63 3.74 1.63 0.0 E 0.030 1.46 1.39 2.08 3.73 3.60 1.46 0.0 ENE 0.022 1.24 1.39 2.52 3.00 3.05 1.30 0.0
[ NE 0.034 1.47 1.7s 2.70 2.94 2.92 1.24 0.0 NNE 0.077 1.66 2.36 3.85 3.46 3.42 1.28 0.0 ;
l Average 1.72 1.74 2.95 4.16 3.55 1.57 -
l The downwind concentration of radioactive material discharged to the atmes-phere during 1980 from each of the four major ESG nuclear facilities has been
[ calculated with the AIRDOS-EPA computer code methodology.
i To determine the nearest site boundary and nearest residence radioactivity concentrations, a mean wind speed for each stability class of 2.2 m/s was selected '
l to evaluate the plume centerline (maximum) concentrations toward the sector in which those locations lie. The 80-km concentration is not direction specific,
- -. but is given for comparison with the nearby concentration values. These are shown in Table 13.
1 ESG-81-17
- 45 l
i
r TABLE 13 MAXIMUM DOWNWIND PLUME CENTERLINE CONCENTRATIONS OF GASE0US EMISbiONS - 1980 ,
Release Distance (m) to Downwind Concentration (pCi/cm3 ),
Rate -
Facility (Ci/yr) Boundary Residence Boundary Residence 80-km B/001 9.6 x 10-6 110 W 171 SW 6.7 x 10-17 7.6 x 10-17 1.8 x 10-19 B/020 1.7 x 10-5 305 NW 1900 SE 1.9 x 10 -17 1.5 x 10 -17 2.4 x 10 -19 B/022 1.8 x 10-6 350 NW 2300 SE 7.2 x 10-19 7.3 x'10-19 2.2 x 10 -20 B/055 1.2 x 10-6 400 NW 1830 SE 3.7 x 10-19 1.8 x 10-18 1.8 x 10-20
- Assume U = 2.2 m/s average wind speed, constant direction, full year.
The demos. .phic information used to estimate the general population dose distribution around the De Soto and SSFL sites was based on the 1970 general census data projected to 1980. The projection was based on an average growth rate of 5.17%/ year. The population distribution surrounding the De Soto facility and to a radius of 8 km is centered on the De Soto site. Beyond 8 km and out to 80 km, the De Soto distribution is centered on coordinates 34 14' 25" north and 118 39' 00" west. This is between the De Soto and SSFL sites, which are approx-imately 10 km apart. The population distribution surrounding the SSFL site out to a radius of 80 km is site centered for all distance segments.
The general population man-rem dose estimates are calculated from the demo-graphic distribution and the sector-averaged downwind radioactivity concentrations generated by AIRDOS-EPA, which uses release rate, wind speed, wind direction and frequency, inversion, lapse, and E.'fective stack height parameters as input data.
Population dose estimates are presented in Tables 14 and 15 for the De Soto and SSFL sites. The exposure mode is by inhalation with lung, the critical organ for U 235 and Pu239, and bone for Sr90 The doses for the SSFL site are summed for all release points and nuclides.
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ESG-81-17 46
TABLE 14 POPULATION DOSE ESTIMATES FOR ATM0 SPHERICALLY DISCHARGED
. EMISSIONS FROM THE DE SCT0 FACILITY -- 1980 Dose to Receptor Population Segment (man-rem) g Sector 0-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-60 km Total N 6.3E-4 2.1E-6 5.4E-5 4.3E-6 2.8E-6 2.3E-7 6.9E-4 NNW 3.4E-4 2.7E-6 6.4E-6 6.4E-7 3.0E-7 7.1E-6 3.6E-4 NW 1.3E-4 1.1E-4 1.1E-4 1.3E-6 9.4E-7 4.5E-7 3.5E-4 WNW 2.6E-4 2.4E-3 1.9E-4 3.8E-4 2.6E-4 1.1E-5 3.5E-3 W 6.2E-4 8.3E-5 4.2E-4 7.2E-4 8.9E-4 2.3E-6 2.7E-3 WSW 1.5E-3 2.4E-5 3.3E-4 4.2E-5 2.8E-5 0 1.9E-3 SW 1.5E-3 5.0E-5 4.9E-5 0 0 0 1.6E-3
- SSW 1.3E-3 3.8E-5 2.0E-5 0 0 0 1.4E-3 S 1.9E-3 1.1E-4 9.9E-5 0 1.4E-6 0 2.1E-3 SSE 4.1E-3 1.1E-3 2.0E-3 1.4E-3 2.1E-3 2.8E-4 1.1E-2 SE 2.6E-3 2.0E-3 5.2E-3 1.2E-2 7.7E-3 4.3E-3 3.4E-2 l
I ESE 2.2E-5 3.0E-3 5.4E-3 7.2E-3 4.9E-3 3.0E-3 2.4E-2 1.2E-3 1.9E-3 2.4E-3 ' 8E-4 4.9E-4 2.9E-4 7.3E-3 f E .
ENE 1.0E-3 7.0E-4 8.4E-4 9.3E-6 2.6E-6 1.2E-5 2.5E-3 l
l NE 6.4E-4 4.4E-6 1.8E-4 1.4E-5 8.5E-5 1.3E-4 1.1E-3 NNE 3.4E-4 5.7E-6 3.5E-4 1.7E-5 1.8E-5 1.5E-5 7.4E-4 r Total 1.8E-2 1.2E-2 1.8E-2 2.3E-2 1.6E-2 8.0E-3 9.5E-2
- 1. Average individual dose = 7.3E-9 rem for the total population of 80-km radius area.
I
- 2. Total 80-km radius man-rem dose estimate from naturally occurring airborne i radioactivity dose to the lung of %.1 rem / year = 1,300,000 (1.3E+6) man-rem.
I i
l i
l f
c t
ESG-81-17 47 l
I TABLE 15 POPULATION DOSE ESTIMATES FOR ATM0 SPHERICALLY DISCHARGED-EMISSIONS FROM THE SSFL FACILITIES -- 1980 .
Dose to Receptor Population Segment (man-rem) g Sector 0-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total N 3.5E-4 1.8E-6 4.3E-6 1.1E-6 1.1E-6 3.3E-7 3.6E-4 l
NNW 6.2E-4 1.3E-7 3.1E-5 1.4E-7 1.2E-7 1.3E-6 6.5E-4 NW 7.5E-4 1.8E-5 2.8E-5 1.6E-5 1.5E-6 1.7E-7 8.1E-4 WNW 2.1E-4 1.7E-5 1.1E-4 5. _- 5 9.3E-5 1.8E-5 5.1E-4 1
W 0 3.5E-5 9.4E-5 2.6E-4 2.9E-5 0 4.2E-4 a WSW 0 1.5E-4 3.9E-5 3.0E-5 0 0 2.2E-4 SW ,
1.4E-5 3.8E-5 8.2E-6 0 0 0 6.0E-5 SSW 6.6E-5 2.8E-5 1.0E-5 0 0 0 1.0E-4 5 4.3E-6 1.4E-5 8.5E-6 0 0 0 2.7E-5 SSE 1.0E-5 2.2E-5 4.3E-5 0 6.6E-5 1.6E-5 1.6E-4 SE 1.7E-4 2.4E-4 1.7E-4 1.2E-3 1.4E-3 8.5E-4 4.0E-3 ESE 1.5E-4 3.5E-4 6.8E-4 1.2E-3 1.1E-3 6.3E-4 4.1E-3 l E 8.3E-5 9.9E-5 6.9E-4 2.2E-4 1.2E-4 5.5E-5 1.3E-3 ENE 2.1E-5 2.1E-5 1.1E-4 5.6E-6 3.5E-6 1.3E-5 1.7E-4
)
I NE 1.8E-4 5.3E-5 3.9E-5 4.1E-E 6.8E-6 4.0E-5 3.6E-4 NNE 1.4E-4 1.1E-6 8.2E-6 1.8E-6 1.1E-6 8.6E-7 1.5E-4 i Total 2.8E-3 1.1E-3 2.1E-3 3.0E-3 2.8E-3 1.6E-3 , '. 3E-2 Average individual dose = 1.9E 9 rem for the 80-km radius area total population.
m
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ESG-81-17 48 i
l The off-site doses are extremely low compared to the maximum permissible exposures recommended for the general population. These values are 3 rem / year for bone and 1.5 rem / year for the lung for an individual, and they are one-third of these values for the general population. The highest average individual dose
. for 1980 is for the De Soto 0-8 km segment, which is equivalent to an average dose / man-year of 0.00005 mrem, or 0.00003% of the maximum permissible exposure for an individual and 0.00001% of the general population exposure limit. Esti-mated radiation doses due to atmospheric discharges of radioactivity from all ESG facilities are a small fraction of the recommended limits and are far below doses due to internal deposit:on of natural radioactivity in air, which is s50 to 100 mrem / year.
I
\
4 I'
,[ ESG-81-17 49 i
i
- ~ - - - .,_.. _ . . _ . _ , , - _ . - - . - . - - , , - - _ - - - - _ - - - - _ - . , . - - . _ . _ _ . _ . - . - _ . - -
APPENDIX A COMPARIS0N OF ENVIRONMENTAL RADI0 ACTIVITY DATA FOR 1980 WITH PREVIOUS YEARS ;
This section compares environmental monitoring results for the calendar year 1980 with previous annual data.
The data presented in Tables A-1 through A-5 summarize all past annual average radioactivity concentrations. These data show the effects of both the short-lived and long-lived radioactive fallout from nuclear weapons- tests super-imposed 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 effec-tive data. In some cases, this is readily apparent in the data. For example, in Table A-1, a small but abrupt increase in the alpha activity reported for soil occurs in 1971. This increase, which is observed in both the on-site and the off-site samples, resulted from use of an improved counting system with a thinner sample configuration. Tne thinner sample increases the sensitivity of the detec-tor to alpha-emitting radionuclides in the sample, thus producing a higher measured specific radiation.
Similarly, prior to 1971, gross activity in ambient air was measured, including both alpha and beta activity. In 1971, measurements were begun which allowed separate identification of these two types of radiation.
The types of random variations observed in the data indicate that there is no local source of unnatural radioactivity in the environment. Also, the simi-larity between on-site and off-site results further indicate that the contribu-tion to general environmental radioactivity due to operations at ESG is essentially
- nonexistent.
ESG-81-17 -
50
._. .- l
TABLE A-1
. S0IL RADI0 ACTIVITY DATA - 1957 THROUGH 1980 On Sige-Average Off Site - Average (10- Ci/g) (10-6 pCi/g)
Year Number Nunber
" O " 8 Samples Samples 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 l 1977 144 0.56 24 48 0.53 23 l
1976 144 0.56 25 48 0.56 24 1975 144 0.60 25 48 0.58 24 1974 144 0.60 25 48 0.54 24 1973 144 0.57 25 48 0.51 24 1972 144 0.56 25 48 0.57 24 1971 144 0.55 25 48 0.53 23 i
1970 144 0.47 27 48 0.48 25 1969 144 0.42 27 48 0.42 25 1968 144 0.47 26 48 0.48 26 1967 144 0.42 28 48 0.39 24 l 1966 144 0.41 29 48 0.44 25 1965 144 0.46 36 142 0.47 29 1964 152 0.46 32 299 0.44 26 1963 156 0.43 45 455 0.42 42 1962 147 0.44 48 453 0.41 47
! 1961 120 0.37 34 458 0.33 23
! 1960 115 0.41 23 362 0.37 19 1959 107 0.43 15 377 0.32 14 1958 80 0.27 21 309 0.26 10 1957 64 0.32 11 318 0.35 10 ESG-81-17
( 51 l
l
TABLE A-2 VEGETATION RADI0 ACTIVITY DATA - 1957 THROUGH 1980 On Site - Average Off-Sjte - Average (10-6 pCi/ gash) (10- pCi/g ash) -
Year Number Number
" " 0 Samples Samples ,
1980 144 <0.25 160 48 <0.19 142 1979 144 <0.24 139 48 <0.23 134 1978 144 <0.24 166 48 <0.24 143 1977 144 <0.22 162 48 <0.21 142 1976 144 <0.19 170 48 <0.22 147 1975 144 <0.21 155 48 <0.21 141 1974 144 <0.20 152 48 <0.27 141 1973 144 <0.24 155 48 <0.24 142 1972 144 0.23 145 48 0.36 125 1971 144 0.24 165 48 0.31 132 1970 14' O.33 159 48 0.30 142 1969 144 0.40 165 48 0.36 144 1968 144 0.51 158 48 0.51 205 1967 144 0.62 286 48 0.39 413 1966 144 0.37 169 48 0.3' 123 1965 144 0.56 162 142 0.61 138 1964 154 0.50 211 293 0.51 181 l 1963 156 0.44 465 456 0.37 388 1962 147 0.45 500 453 0.44 406 4 1961 120 0.35 224 459 0.29 246 1960 115 0.35 137 362 0.25 136 1959 96 0.29 212 293 0.18 168 1958 65 0.57 683 250 0.39 356 1957 58 1.1 208 304 0.89 200
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ESG-81-17 52
TABLE A-3 SSFL SITE DOMESTIC WATER RADI0 ACTIVITY DATA -
1957 THROUGH 1980 Number Av Av Year Samples (10gragea (10grage8 pCi/ml)
UCi/ml) 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 1967 24 0.13 6.1 1966 24 0.13 4.6 1965 24 0.22 6.0 1964 23 0.18 5.3 1963 24 0.18 7.0 1962 24 0.21 12.0 1961 24 0.08 2.9 1960 22 0.08 1.9 1959 18 0,08 1.6 1958 13 0.16 4.7 1957 17 -
13.0 0
O ESG-81-17 53 ,
i l
. . . . . ,- -. . - -- -- -.- . ~ . - . . .. . . -. - . - _ _ - _. .
TABLE A-4 BELL CREEK AND ROCKETDYNE DIVISION RETENTION POND RADI0 ACTIVITY DATA - 1966 THROUGH 1980 Sanples Interim Retention Final R e t on Pond i Bell Cmek Hud Bell Creek Vegetation Bell C m k Water 6 12 Average Average Average Average .
Average
-0 pCi/g) O -6 Ci/g ash) pCi/ W pCi/ml) (10 pCi/ml)
Year 3 jes (10 3 jg, (10 3, jes O 3, jes (10 Sa les a 8 a 8 a 8 a B a 8
<0.22 2.9 12 <0.22 2.9 12 <0.22 3.9 1980 12 0.51 23. 12 <0.18 150. 12 0.46 23. <0.26 136. 12 <0.23 3.2 12 <0.25 3.1 12 <0.23 4.5 l @ 1979 12 12 4.3 <0.25 4.6
, p 1978 12' O.42 23. 12 <0.26 156. 12 <0.24 2.5 12 <0.25 12 0.29 22. <0.19 155. 12 <0.24 1.8 12 <0.24 4.3 12 <0.25 5.2 7 1977 12 12 G 1976 12 0.38 23. 12 <0.17 164. 12 <0.25 2.2 12 <0.24 4.3 12 <0.28 4.4' 1975 12 0.29 22. 12 <0.19 123. 12 <0.22 2.4 12 <0.24 4.2 12 <0.31 4.5 1974 12 0.32 22. 12 <0.16 142. 12 <0.21 2.5 12 <0.22 4.2 12 <0.21 4.5 1973 12 0.34 24. 12 <0.17 147. 12 <0.21 2.7 12 <0.23 4.5 12 <0.37 F.6 1972 12 0.32 22. 12 0.12 139. 12 0.20 2.5 12 0.22 5.3 12 0.22 5.5 1971 12 0. 36 23. 12 0.19 128. 12 0.15 3.8 12 0.18 6.2 12 0.16 6.4 1970 12 0.44 24, 12 0.23 165. 12 0.15 3.7 12 0.15 6.9 12 0.12 7.4 1969 12 0.35 27. 12 0.28 166. 12 0.04 4.0 12 0.07 5.9 11 0.10 5.7 1968 11 0.32 24. 11 0.39 170. 8 0.05 4.6 11 0.23 8.1 12 0.33 7.7
. 1967 12 0.40 24. 12 0.38 180. 12 0.07 5.8 12 0.19 6.6 10 0.17 7.0 1966 3 0.39 25. 3 1.1 108. 3 0.75 2.5 9 0.11 5.8 8 1.1- 6.3
+ ?T . .
TABLE A-5 AMBIENT AIR RADI0 ACTIVITY CONCENTRATION DATA -
1957 THROUGH 1980 0
DeSoto Site Average SSFL Site Avera9e (10-12 pCi/ml) (10-12 pCi/ml)
Year
- Number Number
" O " 0 Samples Samples 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 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 1967 712 --
0.39 2400 --
0.41 1966 706 --
0.18 2205 -
0.17 1965 483 -
0.83 1062 -
0.21 1964 355 --
2.7 --
t 1963 360 -
6.6 292 --
4.7 1962 343 --
7.3 314 -
5.6 1961 313 -
4.2 176 --
3.6 1960 182 --
0.24 44 -
0.44 1959 215 --
2.5 257 -
0.93 1958 366 --
4.9 164 --
2.7 1957 63 --
1.6 141 -
2.7
- Ambient air alpha radioactivity values were included in the beta values and not reported separately prior to 1971 tInsufficient data Sincludes Rocketdyne Site Air Sampler Data
}
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ESG-81-17 55
I APPENDIX B CALIFORNIA REGIONAL WATER QUALITY CONTROL BOARD CRITERIA FOR DISCHARGING NONRADI0 ACTIVE CONSTITUENTS FROM ROCKETDYNE DIVISION, SSFL The discharge of an effluent in excess of the limits given in Table B-1 is
~
prohibited.
TABLE B-1 NPDES NO. CA00-01309, EFFECTIVE SEPTEMBER 27, 1976 Discharge Rate Concentration Limit (1b/ day) (mg/t) 30-day 30-day Average Maximum Average Total Dissolved Solids 1,267,680- -
950 Chloride 200,160 -
150 Sul fate 400,320 -
300 Suspended Solids
- 66,720 50 150-i Settleable Solids * -
0.1 0.3 B005 26,690 20 60 011 and Grease 13,350 10 15 Chromium 6.67 0.005 0.01 Fluoride 1,340 -
1.0 Boron 1,340 -
1.0 Residual Chlorine - -
0.1 Fecal Coliform (MPN/100 mt) - - 23.0
, Surfactants (as MBAS) 667 -
0.5 pH 6.0-9.0
- Not applicable to discharges containing rainfall runoff during or imediately after periods of rainfall.
(
i ESG-81-17 i
56 l
APPENDIX C REFERENCES
. 1. DOE Manual Chapter 0513
- 2. DOE Manual Chapter 0524, Appendix
- 3. Code of Federal Regulations, Title 10, Part 20
- 4. California Radiation Control Regulations, California Administrative Code, Title 17, Public Health
- 5. Californis Regional Water Quality Control Board, Los Angeles Region, Order No.74-379, NPDES No. CA0001309, Effective September 27, 1976
- 6. Meteorology and Atomic Energy - 1968, TID 24190
- 7. Report of Committee II on Permissible Dose for Internal Radiation (1959),
ICRP Publication 2
- 8. Deposition and Retention Models for Internal Dosimetry of the Human Respiratory Tract, ICRP Committee II Task Group on Lung Dynamics
- 9. Document TI #N001TI000-046 titled " Method of Estimating General Population Radiation Dose Attributable to Atmospheric Discharge of Radioactivity from ESG Nuclear Facilities," J. D. Moore
- 10. AIRDOS-EPA: A Computerized Methodology for Estimating Environmental Concen-trations and Doses to Man from Airborne Releases of Radionuclides, 6RNL-5532
- 11. Environmental Impact Assessment of Operations at Atomics International Under Special Nuclear Materials License No. SNM-21, AI-76-21 APPENDIX D EXTERNAL DISTRIBUTION
- 1. Radiologic Health Section, State Department of Public Health, California
- 2. Radiological Health Division, Los Angeles County Health Department California
- 3. Resources Management Agency, County of Ventura, California
- 4. U.S. Department of Energy, San Francisco Operations Office
- 5. U.S. Nuclear Regulatory Commission, Division of Reactor Licensing
- 6. Gordon Facer, Division of Military Applications, DOE
- 7. Andrew J. Pressesky, Reactor Research and Development, DOE
- 8. James Miller, Division of Biomedical and Environmental Research, DOE
- 9. DOE-Headquarters Library, Attention: Charles Sherman
)
ESG-81-17 57
Rockwell International Energy Systems Group 8900 DeSoto Avenue Canoga Park, California 91304