ML20077H292

Energy Sys Group Environ Monitoring & Facility Effluent Annual Rept,1982

ML20077H292
Person / Time
Site:	05000375
Issue date:	06/30/1983
From:	Johari Moore, Tuttle R ROCKWELL INTERNATIONAL CORP.
To:
Shared Package
ML20077H282	List: ML20077H281 ML20077H289 ML20077H292
References
ESG-83-17, NUDOCS 8308090733
Download: ML20077H292 (63)

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ESG-83-17 ENERGY SYSTEMS GROUP ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT 1982 Rockwell International Energy Systems Group O 3

. ESG-83-17 a

T ENERGY SYSTEMS GROUP ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT 1982 BY J. D. MOORE APPROVED: N -

A R. J. TUTTLE Manager Radiation and Nuclear Safety l

Rockwellinternational Energy Systems Group 8900 De Soto Avenue Canoga Park, California 91034 a

1 4 ISSUED: JUNE 1983 l

CONTENTS P

. Page Abstract................................................................. 7 v I. Introduction....................................................... 9 II. Environmental Monitoring Summary Resu'lts........................... 17 A. Ra di oa cti ve . Ma teri al s -- 198 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 B. Nonradioacti ve Materi al s -- 1982. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 III. Environmental Monitoring Program................................... 29 A. General Description............................................ .29 B. Sampl i ng and Sampl e Preparation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29

1. So11....................................................... 29

2. Vegetation................................................. 36

3. Water...................................................... 37

4. Ambient Air................................................ 37 C. Counti ng and Cal i b ration. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37 D. No nra dioacti ve Matari a1 s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 IV. Ef fl uent Moni tori ng Program. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 A. Trea tne n t a nd Ha ndl i n g. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 B. Energy Systems Group Facility Descriptions..................... 45

1. De Soto Site............................................... 45

2. Santa Susana Field Laboratories Si te. . . . . . . . . . . . . . . . . . . . . . . 47 C. Estimation of General Population Dose Attributable to ESG-O p e ra t i o n s -- 19 8 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 Appendices A. Comparison of Environmental Radioa'ctivity Data for 1982 with Previous Years................................................. 55 B. California Regional Water Quality Control Board Criteria for Discharging Nonradioactive Constituents from Rocketdyne Division, SSFL................................................. 61 C. R e fe re n c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 D. Ex tern al Di s tri buti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63

, ESG-83-17 3

TABLES Page a 1- A. So i l Ra d i o a c ti v i ty Da ta -- 198 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 1-B. Soil Pl utonium Radioactivi ty Data -- 1982. . . . . . . . . . . . . . . . . . . . . . . . . . . ' 18 <

2. Vege tati on Ra di oa ctivi ty Da ta -- 1982. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19

3. Domestic Wa ter Radioactivi ty Data -- 1982. . . . . . . . . . . . . . . . . . . . . . . . . . . 20

4. Bell Creek and Rocketdyne Site Retention Pond Radioactivity Data - 1982........................................................ 21

5. Ambient Ai r Radioacti vi ty Data - 1982. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22

6. De Soto and SSFL Sites -- Ambient Radiation Dosimetry Data - 1982... 25

7. Comparison of ESG Exposure Measurements in Sixth International Environmental Dosimeter Intercomparison Project.................... 27

8. Nonradioactive Constituents in Wastewater Discharged to U n re s t ri c t ed A re a s -- 198 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28

9. Sample Station Locations........................................... 33

10. Minimum Radioactivity Detection Level s (MDLs ). . . . . . . . . . . . . . . . . . . . . . 39

11. Atmospheric Emissions to Unrestricted Areas -- 1982. . . . . . . . . . . . . . . . . 44

12. Liquid Ef fl uent Discharged to Sani tary Sewer -- 1982. . . . . . . . . . . . . . . . 46

13. D e So to S i te D e mo g ra p hy -- 1981. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50

14. Santa Susana Field Laboratories Site Demography -- 1981. . . . . . . . . . . . . 51 i

15. Maximum Downwind Plume Centerline Concentrations of Gaseous Emi s s i o n s -- 198 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52

[

l 16. Population Dose Estimates for Atmospheric Emissions from the De Soto Facility - 1982............................................ 53 l

17. Population Dose Estimates for Atmospheric Emissions from SSFL Facilities - 1982............................................. 54 A- 1. Soil Radi oactivi ty Da ta -- 1963 Through 1982. . . . . . . . . . . . . . . . . . . . . . . . 56 A-2. Vegetation Radioactivi ty Data - 1963 Through 1982. . . . . . . . . . . . . . . . . . 57 A-3. SSFL Site Domestic Water Radioactivity Data - 1963 Through 1982.... 58 A-4. Bell Creek and Rocketdyne Division Retention Pond Radioactivity Data - 1966 Through 1982........................................... 59 A-5. Ambient Air Radioactivity Concentration Data -- 1963 Through 1982... 60 B- 1. NPDES No. CA00-01309, Effective 27 September 1976. . . . . . . . . . . . . . . . . . 61 t

l ESG-83-17 4

l l

FIGURES a Page

1. Ene rgy Sys tems G roup -- De So to Si te . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10

. 2. Energy Systems Group - Santa Susana Field Laboratories Site......... 11

3. Map of Santa Susana Field Laboratories Site Facili ties. . ... . . . .. .. . . 12

4. Ma p o f Gene ral Los Angel es Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13

5. Map of Canoga Park, Simi Valley, Agoura, and Calabasas Sampling Stations............................................................ 30

6. Map of De Soto Si te and Vi cini ty Sampling Stations. . . . . . . . . . . . . . . . . . 31

7. Map of Santa Susana Field Laboratories Site Sampling Stations....... 32

8. Daily Averaged Long-Lived Airborne Radioactivity at the De Soto and Santa Sus ana Fiel d Laboratories Si tes - 1982. . . . . . . . . . . . . . . . . . . . 38

, ESG-83-17 5

ABSTRACT Environmental and facility effluent radioactivity monitoring at the Energy Systems Group '(ESG) of Rockwell International (California operations) is per-

+

formed by the Radiation and Nuclear Safety Group of the Health, Safety and Radia-tion Services Department. Soil, vegetation, and surface water are routinely sam-pled to a distance of 10 miles from ESG sites. Continuous ambient air sampling and radiation monitoring by thermoluminescent dosimetry are performed at onsite and offsite locations for measuring airborne radioactivity concentrations and site ambient radiation levels. Radioactivity in emissions discharged to the atmosphere from ESG facilities is continuously sampled and monitored to ensure that the amounts released to unrestricted areas are within appropriate limits and to identify processes that may require additional engineering safeguards to minimize radioactivity in such discharges. In addition, selected nonradioactive constituent concentrations in surface water discharged to unrestricted areas are determined. This report-sunmarizes and discusses monitoring results for 1982.

The results of this environmental monitoring indicate that there are no sig-nificant sources of unnatural radioactive material in the vicinity of the ESG sites. Additionally, the similarity between onsite and offsite results further indicates that the contribution to general environmental radioactivity due to operations of ESG 1s essentially nonexistent.

The environmental radioactivity reported herein is attributed to. natural sources and to fallout of radioactive material from past atmospheric testing of nuclear devices.

i l

e-

, ESG 17 7

I. INTRODUCTION

. The Energy Systems Group' (ESG) of Rockwell International Corporation has been enga92d in nuclear energy research and development since 1946. ESG is cur-

, 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 S0 control, production of gaseous and liquid fuels from

~2 coal, and solar energy development.

The administrative, scientific research, and manufacturing facilities (Fig-ure 1) are located at the ESG De Soto site in Canoga Park, California, approxi-2 mately 23 miles northwest of downtown Los Angeles. The site is level, typical of the San Fernando Valley floor. Certain nuclear programs, under licenses issued i' by the Nuclear Regulatory Commission (NRC)_ and the State of California, are conducted here. These include (1) Building 001 uranium fuel element fabrication 4

facilities and (2) Building.004 analytical chemistry laboratories and gamma irradiation facility. The 290-acre ESG Santa Susana Field Laboratories (SSFL) site (Figure 2) is located in the Simi Hills of Ventura County, approximately 30 miles northwest of downtown Los Angeles. The SSFL site, situated in rugged terrain typical of mountain areas of recent geological age, is underlain by the Chico formation.. The site may be described as an irregular plateau sprinkled with outcroppings above the more level patches and with peripheral 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 l

(D0E) and ESG owned facilities share this site,.shown in Figure 3. SSFL also contains facilities in which nuclear operations-licensed by NRC and the State are conducted. The licensed facilities include:

~

i (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.

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Figure 4. Map of General Los Angeles Area ESG-83-17 13

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 th? 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.

l Licensed programs conducted during 1982 included: (1) the operation of the RIHL for nuclear reactor f9el and system component examination and the fabrica-tion of sealed radiation sources and (2) the operation of nuclear fuel manufac-turing facilities for the production of experimental and test reactor fuel involving enriched uranium, and the developnient of processes for the fabrication of advanced fuels.

The basic policy for the control of rediological and chemical hazards at ESG requires that, through engineering controls, 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 measure of the effectiveness of ESG's safety procedures and of the engineering safeguards incorporated into facility designs.

Specific radionuclides in facility effluent or environmental samples are not routinely identified because of the extremely low radioactivity levels normally detected, but would be identified by analytical or radiochemistry techniques if l significantly increased radioactivity levels were observed.

l In addition to environmental monitoring, work area air and. atmospheric emissions are continuously monitored or sampled, as appropriate. This provides 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.

! ESG-83-17 ,

14 l

l

Environmental sampling stations located within the boundaries of ESG sites are referred to as "onsite" stations; those located outside these boundaries but

.- .within a 10-mile radius of a site are referred to as "offsite" stations. The De Soto and SSFL. sites are sampled .nonthly to determine the concentration of

.. radioactivity in typical surface soil., vegetation, and water. . Soil is sampled onsite'(SSFL) and offsite semiannually for plutonium analysis. 'Similar offsite environmental samples, except for plutonium analysis, are obtained quarterly.

Continuous onsite and offsite ambient air sampling provides information ' con-cerning long-lived airborne particulate radioactivity. Onsite ambient-radiation monitoring . utilizing thermoluminescent dosimetry (TLD), begun in 1971, measures environmental radiation levels at the De Soto and SSFL sites and also at several offsite locations.

Nonradioactive wastes discharged to unrestricted areas are limited to lig-

, uids released to sanitary sewage systems and to surface water drainage systems.

No intentional releases of any liquid pollutants are made to unrestricted areas.

Liquid wastes generated at the De Soto site are discharged into the city sewage system. This effluent is sampled prior to release to determine radioactivity.

Sanitary sewage from all DOE and ESG facilities at the SSFL site is treated at an onsite sewage plant. The plant outfall drains into retention pond R-2A, located on the adjoining Rocketdyne Divisicn site. The surface water drainage

- system of SSFL is composed of catch ponds and open drainage ditches leading to I

retention pond R-2A. Water from the pond may be reclaimed as industrial process water or released, as necessary, offsite into Bell Creek, a tributary of the Los Angeles River. The pond is monitorea at discharge for radioactive and non-radioactive pollutants by Rocketdyne Division as required by discharge permits issued to Rocketdyne by the California Regional Water Quality Control Board.

This report summarizes environmental monitoring results for 1982. A com-parison of 1982 radioactivity results with results from previous years appears -

in Appendix A.

J i

.. ESG 17 15 l

I

-__ . _- . _ _ _ ._ . . ._-_ . ~

II. ENVIRONMENTAL MONITORING

SUMMARY

RESULTS A. RADI0 ACTIVE MATERIALS - 1982 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 1982 are presented in Tables 1 through 5. In calcu-lating the averaged concentration value, all values, including negative ones, were averaged. The method of noncensored data averaging, recommended by DOE Order 5484.1, affords a better estimate of the central value and dispersion of the data. All limits of error reported in the tables are for one standard deviation (l a).

d The maximum radioactivity level detected for a single sample from the annual set is reported'because of its significance in indicating the sxistence of a major episode or an area-wide incident of radioactive material deposition.

None of the maximum observed values, which, as the tables show, occurred randomly during the year, shows a great increase over the average values beyond natural variability. The ambient air sampling data show no greatly increasing or de-creasing trends for most of the year and can be described as generally constant, with some decrease in local airborne radioactivity levels occurring during the third and fourth quarters.

The results reported in Tables 1-A and 2 show no significant difference between onsite and offsite samples. Table 1-B shows no significant variation in soil plutonium concentrations for the 1982 sample sets. The results for the summer sample set were initially reported with two locations having anomalously greater-than-expected levels of plutonium. All samples were consequently reana-lyzed with 50-g aliquots being processed instead of the previously used 20-g aliquots. The results for the reanalysis were consistent with all other analyses and did not confirm the initial high results. Thus, the data for the second analysis are included in the table.

ESG-83-17 17

-TABLE 1-A SOIL RADI0 ACTIVITY DATA - 1982 ,

Gross Radioactivity (Ci/g)

Number' Maximumgbserved

. of Value and Area ' Activity _ Samples Annual Average Value Month Observed Onsite a 144 (0.69 0.20) 10-6 1.18 x 10-6 (monthly) (November)

1. 144 (24.6 2.3) 10-6 30.1 x 10-6 (September)

Offsite' a 48 (0.68 0.22) 10-6 1.21 x 10-6 (quarterly) (October)

S 48 (23.3 3.7) 10-6 32.9 x 10-6 (April) a Maximum value observed for single sample.

TABLE 1-B S0Il PLUT0NIUM RADI0 ACTIVITY DATA - 1982 9 July 1982 Survey Results 16 December 1982 Survey Results 238 Pu239 ,.Pu240 238 Sample Pu Pu Pu239 + Pu240 Location ( C1/g) (pCi/g) ( Ci/g) ( Ci/g)

S-56' (-3.2 1.0) 10-9 (0.7 1.2) 10-9 (-7.6 1.1) 10-9 (0.6 1.4) 10-9 S-57 (1.0 0.4) 10-9 (3.9 0.6) 10-9 (-8. 0 1.5) 10-9 (5.1 2.2 ) 10-9 S (-3.2 1.2) 10-9 (7.1 2.3) 10-9 (0.8 2.9) 10-9 (7.3 2.8) 10-9 S-59 (0.6 0.3) 10-9 (2.3 0.6) 10-9 (-7.0 1.2) 10-9 (2.4 1. 8 ) 10- 9 S-60 (0.7 0.3) 10-9 (4.6 J.6) 10-9 (-7.6 1.5) 10-9 (5.6 2. 2) 10-9 S-61 (1.8 1.9) 10-9 (5.0 2.7) 10-9 (-8.0 2.2) 10-9 (0.4 2.5) 10-9 Nste: Minus (-) indicates sample value less than reagent blank.

ESG 17 18-

For comparison with the plutonium present as a result of nuclear weapons tests and satellite devices, published data from soil tests in nearby Burbank,

.- ' Cali fornia , in' 1970-71 show a plutonium concentration of m2 x 10~9 pCi/g for 239 Pu plus Pu 240 and s0.06 x 10-9 pCi/g for Pu 238 . ~The data in Table 1-B show no

.- significant increases relative to the Burbank values. The detected activity is due to a variety of naturally occurring radionuclides and to radioactive fallout resulting from the dispersal of nuclear weapons materials and fission products by atmospheric testing. No atmospheric tests in the northern hemisphere were an-nounced during 1982. Naturally occurring radionuclides include Be7 , g40 , Rb 87 ,

I47 Sm , and the uranium and thorium series (including the inert gas radon and its radioactive daughters). Radioactivity from aged fallout consists primarily of the fission products Sr90_y90 , Cs 137 , and Pm 147 , and also U 234 and Pu 239 Gamma .

spectrometric analysis of composited ambient air samples collected during 1982 detected only the naturally occurring radionuclides Be7 and K40 ,

TABLE 2 VEGETATION RADI0 ACTIVITY DATA - 1982 Gross Radio.tctisity (pCi/g)

Dry Weight Ash Percent of Samples Number Maximum Value, With of Annual / : age- Annual Average Value ar.d Month Activgty

. Area Activity Samples Value Observed < MDL Onsite 6 a 144 (0.03 0.07) 107 (0.16 2 0.22) 10-6 1.25 x 10-6 60 (monthly) (February)

S 144 (23.6

• 9. 6) 10-6 (140.2 48.2) 10-6 260.1 x 10-6 0 (October)

Offsite a 48 (0.03 0.02) 10-6 (0.17 0. 14 ) 10-6 0.59 x 10-6 50 (quarterly) (October) g 48 (25.2 '12.2) 10-6 (129.7 51.5) 10-6 258.4 x 10-6 0 (July) a b

Maximum value observed for single sample Minimum detection level: 0.12 x 10-6 Cf/g alpha; 0.36 x 10-6 Ci/g beta (ash).

1 ESG-83-17 19

TABLE 3 DOMESTIC WATER RADI0 ACTIVITY DATA,- 1982 Gross Radioactivity (pCi/ml) a Number Maximum Value of Average Value and Month-Area- Activity Samples Observed ESG-De Soto a 12 (0.36 0.23) 10-9 0.79 x 10-9 (monthly) (February) g 12 (3.97 1.19) 10-9 6.6 x 10-9 (September)

ESG-SSFL a 24 (0.14 0.12) 10-9 0.38 x 10-9 (monthly) (August)

S 24 (3.01 0.67) 10-9 4.91 x 10-9 (September) a Maximum valua observed for single semple Domestic water used at the De Soto site is supplied by the Los Angeles Department of Water and Power. Domestic water used at the SSFL site is obtained from Ventura County Water District No.17, which also supplies nearby commun-itses, ar.d is distributed on the site by the same piping system previously used when all facility process water was obtained from onsite wells. One onsite water well (well 13) was operated during 1982 to reduce the consumption of Ventura County domestic water. The well water proportion in the blend averaged about 49% for the year, for a total well water consumption of about 4.7 x 10 7 gal. Pressure for the water system is provided by elevated storage tanks.

I Domestic water is sampled monthly at De Soto and at two widely separated SSFL site locations. The average domestic water radioactivity concentration j for each site is presented in Table 3.

l As discussed earlier, surface waters discharged from SSFL facilities and the l

sewage plant outfall drain southward into retention pond R-2A on Rocketdyne prop-l erty. 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 Resolution 66-49 ,

l ESG-83-17 20 l

' TABLE 4 BELL CREEK AND ROCKETDYNE SITE RETENTION P0ND

. RADI0 ACTIVITY DATA - 1982 Gross Radioa:tivity Concentration

. Percent of Samples a

Number Maximum Value Percent With Area of Average Value and Month of b Activity (Monthly) Activity Samples Observed Guide < MOLc Bell Creek a 12 (0.64 0.14) 10-6 0.92 x 10-6 NA 0 mud no. 54 (February)

(pCi/g) 8 12 (23.5 t 2.1) 10-6 28.0 x 10-6 NA 0 (July)

Pond R-2A a 12 (0.74 0.14) 10-6 0.99 x 10-6 NA 0 mud no. 55 (January)

(pC1/g) b 1,2 (25.5 3.2) 10-6 26.0 x 10-6 NA 0 (December)

Bell Creek n 12 (0.08 0.08) 10-6 0.32 x 10-6 NA 75 vegetation (Cacember) 7 din-ash) e 12 (150.5 67.7) d 280.7 > Id 0 0 (November) bell Creek

• 12 (0.02 0.02) 10-6 0.07 x 10-6 NA 75 vegetation (December) b1 dry 6 12 (.'1.0 12,2) 10-6 31.5x M riA 0 (February) weiiht)

Bell Creek a 12 (0.03 2 0.06) 10'9 0.14 x 10'9 d 100 water no.16 (June)

(pC1/ml) d 8 12 .(3.29 t 0.7) 10'9 4.4 x 10-9 o (July)

Pond water a 12 (0.17 0.08) 10-9 0.35 x 10-9 d 83 no. 6 (June)

(pCl/ml) d 8 12 (3.91 2 1.08) 10-9 5.34 x 10-9 o (October)

SSFL pond R-2A a- 0.28 x 10'9 d 12 (0.11 i 0.13) 10-9 75 water no.12 (July)

(pCi/ml) d 8 12 (3.93 0.83) 10'9 5.81 x 10-9 0 (September) a Maximum value ogserved for single samp}e C

Guide: 5 x pCi/ml alpha, 3 x 10' pCi/ml beta; 10 CFR 20 Appendix B. CAC 17, 00E Order 5480.1 Minimum detection level: 0.23 x 10 'J pCf/ml alpha; 0.64 x 10-9 pCi/ml beta NA - r.ot applicable no Guide value having been established, dActivity essentially, the same as local domestic supply water.

ESG-83-17 21

TABLE 5 AMBIENT AIR RADI0 ACTIVITY DATA - 1982 ,

Percent of

• Samples a

Site Number Maximum Value Percent With Location of Average Value and Date of b

Activity (Continuous) Activity Samples Observed Guide <MDL c

De Soto a 727 '(1.7 3.1) 10-15 3.9 x 10-14 0.06 93 Onsite (07/17)

(pCi/ml) 2.6 x 10-13 0.009 20 d

0 (2.6 1.4) 10-14 (01/17) c SSFL Onsite a 1690 (1.1 2.6) 10-15 3.0 x 10-14 1.8 96 (pCi/ml) (07/17) d B (2.1 1.6) 10-14 1.8 x 10-13 0.07 27 (06/13)

C SSFL sewage a 312 (1.6 3.1) 10-15 1.6 x 10-14 2.7 95 treatment (06/07) plant 7.3 x 10-14 0.07 26 d

Offsite B (2.2 1.1) 10-14 (pCi/ml) (10/07) c SSFL Control a 345 (1.8 2.5) 10-15 1.3 x 10-14 3.0 95 Center (07/12)

Offsite (2.3 1.3) 10-14 8.8 x 10-14 0.08 21 d

(pCi/ml) 8 (04/25) a Maximum value observed for single sample Guide: De Soto site: 3 x 10-12 uCi/ml alpha, 3 x 10-10 pCi/ml beta,10 CFR 20 b

f4ppendix B. SSFL site: 6 x 10-14 pCi/ml alpha, 3 x 10-11 uCi/ml beta; 10 CFR 20 Appendix B, CAC 17, and.D0E Order 5480.1 cMDL = 6.4 x 10-15 pCi/ml alpha MDL = 1.3 x 10-14 pCi/ml beta.

of 21 September 1966, a sampling station for evaluating environmental radioac-tivity in Bell Canyon was established in 1966. It is located approximately 2.5 miles downstream from the southern Rockwell International Corporation bound-a ry . Samples, obtained and analyzed monthly, include stream bed mud, vegetation, and water. Average radioactivity concentrations in Rocketdyne and Bell Creek ,

samples are presented in Table 4.

ESG-83-17 22

~

Comparison of the radioactivity concentrations in water from the ponds and from Bell' Creek with that of the domestic water supply shows no significant dif-ferences'in either alpha or beta' activity.

. The SSFL. site surface. water and the ambient air radioactivity- concentration guide values selNted 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. (MPCs). The MPC values are dependent on the radionuclide and its behavior as a soluble or an insoluble mate-rial. For comparison with results of environmental and effluent monitoring, the

. lowest MPC value for the various radionuclides present is selected. Accordingly, for SSFL site surface water, the guide values of 5 x 10-6 Ci/ml alpha activity corresponding to Pu239=and 3 x 10-7 pCf/ml beta activity corresponding to Sr99 are appropriate. The corresponding most restrictive guide value for De Soto site wastewater radioactivity. discharged to the sanitary sewage system, a controlled area, it 9 x 10-4 pCi/ml alpha activity corresponding to U 234 and 1 x 10-3 C1/ml i

i beta' activity corresponding to Co 60 These values are established in 10 CFR 20, California Administrative Code T'tle 17. and DOE Order 5480.1.

The guide value of 6 x 10-14 Ci/ml for SSFL site ambie'nt air alpha' activity is due to work'with unencapsulated plutonium. The value of 3 x 10-11 Ci/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 C1/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 Ci/ml is for Co 60 , 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 none have -

been established.

Ambient air sampling for long-lived particulate alpha and beta radioactivity is performed continuously by automatic sequential samplers located at both the De Soto and SSFL sites. Air is drawn through Type A/E glass fiber filter media, ESG-83-17

which are analyzed for _ retained long-lived radioactivity after a minimum 120-h decay! period that' eliminates naturally occurring'short-lived particulate radio-activity. The average concentrations of ambient air alpha and beta radio- -

activity for 1982 are presented for the various locations in Table 5.

Radioactivity levels observed in environmental . samples for 1982,- reported in Tables}1 through 5,. compare closely with levels reported for recent years. Local environmental radioactivity levels, which result primarily from beta-emitting

radionuclides and which had shown the effect of fallout during past extensive atmospheric testing of nuclear devices, have decreased and have been generally constant during the past several years. The effects of foreign atmospheric nuclear tests continue to be occasionally observed in daily ambient airborne l radioactivity levels. The long-term effects of airborne radioactivity on ' surface i sample radioactivity levels are not discernible for. recent years. The continuing

relative constancy in environmental radioactivity levels is due primarily to the dominance of naturally occurring radionuclides in the environment and to the i

longer-life fission product radioactivity from aged fallout.

Site ambient radiation monitoring is perfonned with thermoluminescent dosi-

,. meters. Each dosimeter set contains two calcium fluoride-(CaF 2:Mn) low back--

I ground, bulb-type chip dosimeters. The dosimeter sets are placed at locations i on or near the perimeters of the De Soto and SSFL sites. Each dosimeter, sealed l l in a light-proof energy compensation shield, is installed in a polyethylene container which is mounted about 1 m above ground c' each location. The dosi-meters are exchanged and evaluated quarterly. Thirteen onsite TLD monitoring

! locations were used during the year. Five additional dosimeter sets, placed at

) locations up to 10 miles from the ESG sites, are similarly evaluated to deter-l mine the local area offsite ambient radiation level, which averaged 14 yR/h for

. 1982.- 'The quarterly and annual radiation exposures and the equivalent annual exposure rates monitored at each dosimeter location are presented in Table 6. 4

.The' table shows that radiation exposures and equivalent annual exposure

~

rates monitored onsite are nearly identical to levels monitored at five widely separated offsite locations. These data include natural background radiation .

1 ESG-83-17 '

24 L

a

, . , . - - . - - , . _ - - , , . ,, ., __ ___._-.m,,,- ._.-_,._,m , _ - _ _ , _ ._ - _

TABLE 6

, DE S0TO AND SSFL SITES - AMBIENT RADIATION DOSIMETRY DATA - 1982 Quarterly Exposure (mR) Annual Equivalent TLD Exposure Exposure Rate Location Q-1 Q-2 Q-3 Q-4 (mR) ( R/h)

1. De Soto 28 29 29 31 117 13

2. De Soto 28 28 28 29 113 13

3. De Soto 28 28 29 28 113 13

4. De Soto 25 32 32 32 121 14

5. De Soto 28 30 29 29 116 13

6. De Soto 34 36 33 32 135 15

7. De Soto 28 26 28 28 110 13 11ean value 118 13.4

1. SSFL 31 32 3 33 a 128 15

2. SSFL 31 34 1 34 36 135 15

3. SSFL 34 32 39- 38 143 16

4. SSFL a 34 37 37 144 17

5. SSFL a 31 36 34 135 15

6. SSFL 25 27 28 28 108 12 Mean value 132 15.0

1. Offsite control 29 30 32 32 123 14

2. Offsite control 29 30 33 31 123 14

3. Offsite control 29 31 28 31 119 14

4. Offsite control 32 32 31 32 127 14 l 5. Offsite control 27 33 34 34 128 15 1

Mean value 124 14.2 a

l Missing dosimeter, annual exposure based on data for three quarters

!. Note: The elevation for the De Soto and offsite dosimeters is about 1000 ft l less than those for the SSFL site. From sea level to a few thousand feet in elevation, the increase in annual exposure is approximately 15 mR/1000 ft. This amount subtracted from the SSFL site results

[

would provide good agreement between the three data sets.

ESG-83-17 l 25 l

l

from cosmic radiation, radionuclides in the soil, radon and thoron in the atmos-phere, and radioactive fallout from nuclear weapons tests. Locally, the natural background radiation level as measured by these dosimeters is about 125 mR/ 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 onsite and offsite locations are nearly identical, no measurable radiation dose to.the general population or to individuals in uncontrolled areas resulted from ESG operations.

During the 4-year period 1977 through 1980, a steady increase was observed in the TLD readings for all locations. Although the increases were variable from year to year and between locations, averaged over 4 years, the increases were in the range of 14 to 17 mR per year. The values for 1982 show a slight, but not statistically significant, decrease. Among D0E-contractor environmental monitoring programs, this apparent increase in radiation readings was observed by only one other contractor; that contractor is also the only other contractor using the CaF2 :Mn bulb-type dosimsters that are usad at ESG.

Thus, the ef fect appsars to be related to this particular type of dosimeter.

A study of this problem is continuing. The old TLD reader was replaced with a new, more accurate and precise reader during the first quarter of 1982. Before being used, dosimeters are-being screened for internal radioactive contamination to eliminate self-dosing TLDs and are being stored in a lead shield. Also, the special identity of each dosimeter bulb is being maintained in order to evaluate their long-term performance on an individual basis.

Supplementary measurements of ambient radiation levels are being made with a high-pressure ion chamber (HPIC) at each site. The HPIC values for 1982 were equivalent to annual exposures of 86 mR for De Soto and 108 mR for SSFL. State of California TLDs (LiF) placed with each of six ESG dosimeters at both onsite and offsite locations show an annual average exposure of 115 mR for 1982.

During 1982, ESG participated in the Sixth International Environmental Dosimeter Intercomparison Project sponsored by the U.S. Department of Energy and -

ESG-83-17 -

l 26

the U.S. Nuclear Regulatory Commission. The ESG estimates of exposures to the ESG-supplied dosimeters are shown in Table 7:

TABLE 7

- COMPARIS0N OF ESG EXPOSURE MEASUREMENTS IN SIXTH INTERNATIONAL ENVIRONMENTAL 00SIMETER INTERCOMPARIS0N PROJECT Delivered Exposure ESG Measured Exposure Type of Exposure (mR) (mR)

Field 43.5 50 Field plus pre-irradiation 202 211 Laboratory 158 174 Control 6.8 12.5 Analysis of these resul.ts indicates good agreement with the delivered exposures, with a bias of about +6 mR from the true values. If this same bias were to exist in c11 the dosimeters in use in the environmental radiatiun measurements, it would contribute 24 mR per year to the annual exposure values.

Using the intercomparison results to adjust the environmental TLD values yields an average annual exposure of 98 mR, in excellent agreement with the HPIC average of 97 mR, but slightly below the LiF average of 115 mR.

B. NONRADI0 ACTIVE MATERIALS -- 1982 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 are normally required only as a result of excessive rainfall runoff. During such releases, the NPDES permit concentration limits for turbidity and for suspended and settleable solids do not apply. The results of analyses for each discharge for 1982, most of which were rainfall-related discharges, are presented in Table 8.

ESG-83-17 27

TABLE 8 NONRADI0 ACTIVE CONSTITUENTS IN WASTEWATER DISCHARGED TO UNRESTRICTED AREAS - 1982 (Analysis Results for' Wastewater Discharged from Pond R-2A to Bell Creek on Date Indicated -- Sample Station W-12)

January 5' January 20 a February 10 8 March 11 March 18a April l a

Apr11.12' Novenber 9' November 30 a

December 22'

% of 5 of  % of s of I of  % of S of l of S of S of Constituents Result Guide Result Guide Result Guide Result Guide Result Guide Result Guide Result Guide Result Guide Result Guide Result Guide d ed 3

265 27.9 298 31.4 539 56.7 552 58.1 275 28.9 313 32.9 323 34.0 76 8 80.8 250 26.3 331 34.8 Chloride (ag/1) 28 18.7 36 24.0 67 44.7 59 39.3 32 21.3 27 18.0 32 21.3 88 58.7 27 18.0 37 24.7 Sulfate (mg/1) 10 3.3 62 20.7 166 55.3 177 59.0 76 25.3 81 27.0 94 31.3 290 96 7 79 26.3 95 31.7 ded solids D 57 38.0 110 73.3 8 5.3 77 51.3 35 23.3 100 66.7 56 37.3 33 22.0 366 244.0 44 29.3 g;pbisanos' <0.i <u.3 0.2 66.7 <0.1 < u. 3 0.2 66. no.1 <u.n o.1 <n.3 <0.1 <u.3 <0.1 <u.3 0.4 in.3 0.i . u.3 m 8005(mg/1) 10 16.7 5 8. 3 24 40.0 10 16.7 3 5.0 6 10.0 6 10.0 3 - 5.0 4 6.7 5 8.3 m

O g g yd9*5' 1.2 8.0 2 13.3 2 13.3 1 6.7 3 20.0 1.3 8.7 6 40.0 2 13.3 2 13.3 3 20.0 CD w M Turbidity (TU)b 65 - 58 -

2 -

19 -

19 - 70 - 40 -

17 -

165 -

20 -

N Chromium (mg/1) 0.008 80.0 0.008 80.0 0.002 20.0 0.007 70.0 0.005 50.0 0.011 110.0 0.002 20.0 0.006 60.0 0.016 160.0 0.005 50.0 Fluoride (mg/1) 0.3 30.0 0.5 50.0 0.4 40.0 0.3 30.0 0.4 40.0 0.4 40.0 0.3 30.0 0.5 50.0 0.4 40.0 0.3 30.0 j Baron (eg/1) 0.1 10.0 <0.2 <20.0 0.2 20.0 0.3 30.0 0.2 20.0 0.2 20.0 <0.2 <20.0 0.5 50.0 <0.2 <20.0 0.3 30.0 1 chlorine <0.04 <40.0 <0.04 <40.0 <0.04 <40.0 <0.04 <40.0 <0.04 <40.0 <0.04 <40.0 <0.04 <40.0 <0.04 <40.0 <0.04 <40.0 <0.04 <40.0

<2 <8.7 <2 <8.7 <2 <8.7 11 47.8 <2 <8.7 <2 <8.7 2 8.7 2 8.7 <2 <8.7 <2 <8.7 1

Surfactants (MBAS) 0.02 4.0 0.02 4.0 0.05 10.0 0.02 4.0 0.03 6.0 0.02 4.0 <0.01 <2.0 <0.01 <2.0 <0.01 <2.0 <0.01 <2.0*

PH 7.7 7,9 8.8 8.1 8.1 . 8.5 8.6 9.0 8.2 7.9 Rainfall (in.) 0.5 0.85 0.5 4.9 0.5 0.9 2.65 2.3 2.1

[f ,(j'" '" 22.2 x 10 7 7 2.3 x 10 I 3.9 x 10 I 2.3 x ;0 7 2.3 x 10 7 4.1 x 10 4.1 x 10 7

3.8 x 10 7 3.5 x 10 7 6

5' '*I""'

3.2 x 106 2.5 x 106 1.2 x 10 6 4.0 x 10 6 2.0 x 10 E 0.8 x 10 6 2.3 x 10 3.0 x 10 6 2.5 x 106

' Rainfall-related discharge b

Not applicable to discharges cortaining rainfall runoff during or imediately after periods of rainfall Note: Pond R-2A capacity - 2.5 x 100 gal.

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 instaliations were planned and are currently in operation. The Downey area strvey was terminated when nuclear activities were relocated to Canoga Park in 1955. The primary purpose of the environmental monitoring program is to survey environmental 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 9.

l B. SAMPLING AND SAMPLE PREPARATION

1. Soil I

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 weapons, a general background level of radioactivity exists. The data are mor.1-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 upper 1 cm of undisturbed ground 4 surface for gross radioactivity analysis and'to a depth of 5 cm for plutonium analysis. The soil samples are packaged in plastic containers and returned to the laboratory for analysis.

Sample preparation for gross radioactivity determination consists of trans-ferring the soils to Pyrex beakers and drying them in a muffle furnace at about

. ESG 17 29 i

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ESG-83-17 .

32

I TABLE 9 SAMPLE STATION LOCATIONS (Sheet 1 of 3)

Location

. Station (frequency of sampling)

SV-1 SSFL Site, Bldg. 143 (M)

SV- 2 SSFL Site, Below Bldg.143 by Perimeter Drainage System Near Pond (M)

SV-3 SSFL Site, Bldg. 064 (M)

SV-4 SSFL Site, Bldg. 020 (M)

SV-5 SSFL Site, Bldg. 363 (M)

SV-6 Rocketdyne Site Interim Retention Pond (Q)

SV-10 SSFL Site Access Road (Q)

SV-12 SSFL Site, Bldg. 093 (L-85 Reactor) (M)

SV-13 SSFL Site, at SRE Water Retention Pond (M)

SV-14 SSFL Site, Bldg. 028 (M)

SV-19 SSFL Site Entrance, Woolsey Canyon (Q)

SV-24 De Soto Site, Bldg. 004 (M)

SV-25 De Soto Avenue and Plummer Street (Q)

SV-26 Mason Avenue and llordhoff Street (Q)

SV-27 .De' Soto Avenue and Parthenia Street (Q)

SV-28 Canoga Avenue and Nordhoff Street (Q)

SV-31 Simi Valley, Alamo Avenue and Sycamore Road (Q)

SV-40 Agoura - Kanan Road and Ventura Freeway (Q)

SV-41 Calabasas - Parkway Calabasas and Ventura Freeway (Q)

SV-42 SSFL Site, Bldg. 886 (M)

SV-47 Chatsworth Reservoir North Boundary (Q)

SV-51 SSFL Site, Bldg. 029 (M)

SV- 52 SSFL Site, Burro Flats Drainage Control Channel, G Street and 17th Street (M)

SV-53 Rocketdyne Site Pond R-2A (Q)

SV-54 Bell Creek (M)

SV - Soil and Vegetation Sample Station (M) - Monthly Sample (Q) - Quarterly Sample ESG-83-17 33 I

TABLE 9 SAMPLE STATION LOCATIONS -

(Sheet 2 of 3)

Location -

Station (frequency of sampling)

S-55 Rocketdyne Site Pond R-2A (Pond Bottom Mud)-(M)

S-56 SSFL Site, F Street and 24th Street (S)

S-57 SSFL. Site, J Street at Bldg. 055 (S)

S-58 SSFL Site, Bldg. 353 (S)

S-59 Rocketdyne Site Test Area CTL'4 (S)

S-60 Rocketdyne Site Pond R-2A (S)

S-61 Simi Valley, East End of Alamo Avenue (S)

W-6 Rocketdyne Site Interim Retention Pond (Drains to Pond R-2A) (M)

W-7 SSFL Site Domestic Water, Bldg. 003 (M)

W- 11 SSFL Site Domestic Water, Bldg. 363 (M)

W-12 Rocketdyne Site Pond R-2A (M)

W-16 Bell Creek (M)

A-1 De Soto Site, Bldg. 001 Roof (D)

A-2 De Soto Site, Bldg. 004 Roof (D)

A-3 SSFL Site, Bldg. 009, West Side (D)

A-4 SSFL Site, B1dg. 011, West Side (D)

A-5 Rocketdyne Site, Bldg. 600, North Siae (D)

-A-6 Rocketdyne Site, Bldg. 207, North Side (D)

A- 7 SSFL Site, Bldg. 074, South Side (D)

A-8 SSFL Site, Bldg. 143, West Side (D)

A-9 SSFL Site, Bldg. 363, West Side (D)

S - Soil Sample Station W - Water Sample Station A - Air Sample Station (S)-SemiannualSample (M) - Monthly Sample (D) -. Daily Sample .

~

ESG-83-17 34

I l

TABLE 9 SAMPLE STATION LOCATIONS (Sheet 3 of 3)

Location l* Station (frequency of sampling)

TLD-1 De Soto Site, South of Bldg.102 (Q)

TLD-2 De Soto Site, West Boundary (Q) (State of California TLD Location)

TLD-3 De Soto Site, Guard Post No.1, Bldg. 201 (Q)

TLD-4 De Soto Site, East Fence (Q) (State of California TLD Location)

TLD-5 De Soto Site, North Boundary (Q)

TLD-6 De Soto Site, East Boundary (Q)

TLD-7 De Soto Site, South Boundary (Q)

TLD-1 SSFL Site, Bldg. 114 (Q)

TLD-2 SSFL Site, SRE Retention Pond (Q)

TLD-3 SSFL Site, Electric Substation No. 719 (Q) (State of California TLD Location)

TLD-4 SSFL Site, West Boundary on H Street (Q)

TLD-5 SSFL Site, at Southwest Boundary (Q)

TLD-6 SSFL Site, Bldg. 854 (Q) (State of California TLD Location)

TLD-1 Offsite, Northridge (Q) (State of California TLD Location)

TLD-2 Offsite, Simi Valley (Q) i TLD-3 Offsite, Northridge (Q)

TLD-4 Offsite, Simi Valley (Q) l- TLD-5 Offsite, Simi Valley (Q) (State of California TLD Location)

TLD - Thermoluminescent Dosimeter Location L (Q) - Quarterly Sample

, ESG-83-17 35

500 C for 8 h. After cooling, the soil is sieved to obtain unifom 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 uniform sam-ple thickness, dried, and counted for alpha and beta radiation. Soil plutonium ,

analysis is perfomed (according to the guidelines specified in U.S. NRC Regula-tory Guide 4.5 titled " Measurements of Radionuclides in the Environment-Sampling and Analysis of Plutonium in Soil") by a certified independent testing laboratory.

2. Vegetation The analysis of vegetation, perfomed as an adjunct to the soil analysis, 4

is done to detemine 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, wherever 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 root systems are not analyzed.

Since the analysis is done to detemine uptake only, and not fallout deposi-tion, vegetation is firs' washed t with tap water to remove foreign matter and then thoroughly rinsed with distilled water. Washed vegetation is vacuum dried in tared beakers at 100 C for 24 h for dry weight determination, then ashed in a muf-fle furnace at about 500 C for 8 h, producing a completely burned ash. One-gram l aliquots of pulverized ash from each beaker are weighed into copper planchets.

The vegetation ash is wetted in the planchet with alcohol, evenly distributed to obtain uniform sample thickness, dried, and counted for alpha and beta radiation.

The dry / ash weight ratio is used for determining the equivalent dry weight gross radioactivity concentration value. The moisture content of the vegetation is l

about 80% of total plant weight.

O ESG-83-17 36

3. Water Surface and domestic supply water samples are obtained monthly at the De Soto and SSFL sites and from Bell Creek. The water is drawn into 1-liter polyethylene

. bottles and transferred to the laboratory.

Five-hundred-milliliter volumes of water are evaporated to dryness in crys-0 tallizing dishes at about 90 C. The residual salts are redissolved into dis-tilled 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 automatic air samplers, operating on 24-h sampling cycles. Airborne particulate radioactivity is collected on Type A/E glass fiber filter media, which are auto-matically 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 about 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 1982. The data were mathematically smoothed by a program that calculates a moving weekly average of daily data for the year. The average alpha and beta radioactivity con-centrations for each month are indicated by horizontal bars. The graph shows small l

l decreasing trends in airborne radioactivity during the first, third, and fourth l quarters; however, overall levels were generally constant for the year. Several transient peak concentration levels were observed within the general trend. This activity is attributed to residual fallout from past foreign atmospheric tests of nuclear devices and to naturally occurring airborne radioactive materials.

! C. COUNTING AND CALIBRATION

. Environmental soil, vegetation, water, and ambient air samples are counted for alpha and beta radiation with a low-background gas flow proportional counting

- ESG-83-17 37

1ai giiiiliiiii;iiiii;eiiiii .iiijiiii tr iiiiiiiiiil liiiiiiiiiiiliiiiiiiiii

_~ LOCAL RAINFALL OCCURRED ON DAYS INDICATED BY DOT 2

~

BETA

- ~

~' AVG. #

y #~ , ____

1

~ DL M J- y- en g 1&2 _

~

10-2

~

L

~

$ ALPHA O -

U E r b -

-? d m E b Y1__

W 1

4g j h $$..

t 8 o ,g3 = --

_ 9_[

41' k '

_  : Y i,A l --

W-y- .- tw3 1 y 30-4 iiis iliiiii h) i d i,liiiiilisivilitisilit isi liinisliiiiiiiiiinlei niiliiar i 104 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT Nov DEC Figure 8. Daily Averaged Long-Lived Airborne Radioactivity at the De Soto and Santa Susana Field Laboratories Sites - 1982

system. The system is capable of simultaneously counting both alpha and net beta radiation. The sample-detector configuration provides a nearly 27r 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

' levels shown in Table 10 were determined by using typical values for counting time, system efficiencies for detecting alpha and beta radiation, background count rates (approximately 0.05 cpm a and 1.0 cpm S), and sample size. For the table, the minimum statistically significant amount of radioactivity, irrespec-tive of sample configuration, is taken as that amount equal in count rate to three times the standard deviation of the ' system background count rate.

TABLE 10 MINIMUM RADI0 ACTIVITY DETECTION LEVELS (MDLs)

Sample Activity Minimum Detection Level Soil a (5.8 3.4)10-8 Ci/g

1. (2.3 1.2) 10-7 Ci/g Vegetation a (1.2 0.7) 10-7 pCi/g ash

1. (3.6 2 1.8) 10-7 Ci/g ash Water a (2.3 1.4) 10-10 Ci/ml

1. (6.4 3.2)10-10 Ci/ml Air a (6.4 2 3.8) 10-15 Ci/ml S (1.3 0.6) 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, which 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 are counted. The ratio of sample activity to the observed net count rate for each sample is plotted as a function of canie weight. The correction ESG-83-17 39

factor (ratio) corresponding to sample weight is obtained from the graph. The product of the correction factor 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 statistial counting error. .

Since the observed radioactivity in environmental samples results primarily from natural and weapons-testing sources, and is at such low concentrations, no effort is normally made to identify individual radionuclides. The detection of significant levels of radioactivity would lead to an investigation of the radio-active material involved, the sources, and the possible causes.

D. NONRADI0 ACTIVE MATERIALS The Rocketdyne Division of Rockwell International Corporation has filed a Report of Waste Discharge with the California Regional Water Quality Control Board and has been granted a National Pollutant Discharge Elimination System permit to discharge wastewater, pursuant to Section 402 of the Federal Water Pollution Control Act. The permit, NPDES No. CA0001309, became effective on 27 September 1976 and supersedes all previously held permits for wastewater discharge from the Rocketdyne Division, SSFL'. This permit covers discharge of overflow and storm runoff from water reclamation retention ponds into Bell Creek. Discharge generally occurs only during and immediately after periods of heavy rainfall or during extended periods of rocket engine testing.

Only one of the retention ponds receives influent from the ESG-SSFL site.

l It is identified as retention pond R-2A, Water Sample Station W-12 in Table 9.

The influent includes sewage treatment plant outfall and surface runoff water.

l Grab-type water samples, taken at the retention pond prior to a discharge, are analyzed for nonradioactive chemical constituents and for radioactivity by a California ' State certified analytical testing laboratory. The specific con-stituents 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 .

ESG 17 .

40

. .. . _ _ _ _ _ _ - _ _ _ __ m .

of origin of nonradioactive constituents nomally found in wastewater is impos-sible to determine; however, in the event of excessive amounts of any of these

. materials in wastewater, the origin could be detemined from the knowledge of facility operations involving their use. Ten offsite discharges of wistewater

, from Pond R-2A occurred during 1982.

't i

. ESG-83-17 41

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 0015-70. The specific facilities are identified 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 emissions is reduced to the lowest values by passing the emissions through certified, high-efficiency partitculate air (HEPA) filters. These emissions are sampled for particulate radioactive materials by means of continuously operating stack exhaust samplers at the points of release. In addition, stack monitors installed at Buildings 020 and 055 provide automatic alarm capability in the event of the release of gaseous or particulate activity from Building 020 and particulate activity from Build-ing 055. The HEPA filters used for filtering gaseous emissions are at least 99.97% efficient for particles of 0.3-Um diameter. Particle filtration effi-ciency increases for particles above and below this size.

The average concentration and total radioactivity in gaseous emissions to unrestricted areas are shown in Table 11. The effectiveness of the air cleaning systems is evident from the fact that, in most cases, the gaseous emissions are less radioactive than is ambient air. The table shows that no significant quantities of radioactivity were released in 1982.

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-83-17 43

TABLE 11 ATMOSPHERIC EMISSIONS TO UNRESTRICTE0 AREAS - 1982 Sampling Percent Approximate Period Total of Approximate Minimum Annual Maximum Radio- Samples Emissions Detection Average Observed activity Percent With Volume Activity Level Concentration Concentration Released of Activity Building a (f t3) Monitored ( Ci/ml) ( Ci/ml) ( Ci/ml) (C1) Guide < MDL 001 1.4 x 10 10 a 1.6 x 10-10 3.0 x 10-15 1.5 x 10-I4 1.2 x 10-6 0.10 35 De Sot

1. 5.4 x 10-16 2.4 x 10-15 1.7 x 10-14 9.4 x 10-7 0.0008 33 004 2.4 x 10 10 a 2.1 x 10-16 3.4 x 10-16 2.5 x 10-15 2.4 x 10-7 0.01 46 De Soto S 7. 2 x 10-16 1.5 x 10-15 1.3 x 10-14 1.1 x 10-6 0.0005 43 020 1.0 x 10 10 a 0.9 x 10-16 1.0 x 10-16 4.4 x 10-16 3.1 x 10-8 0.16 68 Sbfl g A 3.0 x 10-16 4.7 x 10-I4 9.0 x 10-13 1.4 x 10-5 0.16 0 m

$ 021-022 1.2 x 10 10 a 0. 9 x 10- 16 6.8 x 10-16 1.9 x 10-16 2.4 x 10-8 1.13 82 q SSFL S 3.0 x 10-16 1.8 x 10-15 4.4 x 10-15 6.1 x 10-7 0.006 0 055 7.0 x 10 9 a 2.9 x 10 16 1.1 x 10-16 7.6 x 10-16 2.3 x 10-8 0.18 84 SSFL

1. 9.6 x 10-16 5.2 x 10-15 1.7 x 10-14 1.0 x'10-6 0.17 0 Annual average ambient air radio- a activity concentra- 2.0 x 10-15 Total 1.9 x 10-5 g

tionb ( Ci/ml) - 4.0 x 10-14 1982 a

Assuming all radioactivity detgted is from ESG operatgns.

Guide: De Soto site: 3 x 10- Ci/ml alpha, 3 x 10 11 Ci/ml beta; 10 CFR g Appendix B.

SSFL site: 6 x 10-74 Ci/ml alpha, 3 x 10- Ci/ml beta, 3 x 10- pCi/ml beta (055 only);

b 10 CFR 20 Appendix B, CAC-17, and DOE Order 5480.1 Chapter XI.

Averaged result for 7-day (202 m3) De Soto continuous air sampler.

Note: All release points are at the stack exit.

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 peri-odically samples and composites aliquots of the tank contents prior to each dis-

. 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 solidified for land burial. The average concentration and total radioactivity in effluents dis-charged are shown in Table 12.

B. ENERGY SYSTEMS GROUP FACILITY DESCRIPTIONS

1. De Soto Site

a. Building 001 - NRC and California State Licensed Activities Operations at Building 001 that may generate radioactive effluents consist of production operations associated with the manufacture of enriched uranium fuel elements. Only atmospheric emissions are released from the building to uncon-trolled areas. Following analysis for radioactivity concentration, liquid wastes are released to the sanitary sewage system, 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 U 234 ,g 235 ,

236 238 U , and U ,

b. Building 004 - NRC and California State Licensed Activities Operations at Building 004 that may generate radioactive effluents consist of research studies in physical chemistry, and the chemical analysis of small quantities of fuel materials, usually limited to a few grams. Only atmospheric emissions are released from the building to uncontrolled areas. Liquid labora-tory wastes are released to an interim retention tank installation. Aliquots

. ESG-83-17 45

TABLE 12 LIQUID EFFLUENT DISCHARGED TO SANITARY SEWER - 1982 Sample Total Approximate Annual Maximum Radio-Effluent Approximate Avera9e Observed. activity Percent Point of Volume Activity MDL Concentration Concentration Released of b

, Building Release (gal) Monitored (pCi/ml) (Ci/ml) ( Ci/ml) (C1) Guide 001 Retention 25,500 a 1.0 x 10-9 3.2 x 10-7 9.8 x 10-7 3.1 x 10-5 0.027 tank

1. 3.7 x 10-9 2.4 x 10-7 8.0 x 10-7 2.3 x 10-5 0.024 c

m 004 Flow 690,000 a 1.1.x 10-9 5.9 x 10-8 7.0 x 10-8 7.4 x 10-5 0.006 sampler S 3.7 x 10-9 3.2 x 10-7 1.6 x 10-7 2.8 x 10-4 0.032

• 4' O a 020 -

0 - - - - - -

a

! 021-022 -

0 - - - - - -

a 055 -

0 - - - - - -

a All liquid radigactive wastes are solidified and land buried as dry waste Guide: 9 x 10- C1/ml alpha, 1 x 10- pCi/ml beta; 10 CFR 20 Appendix B, CAC-17 c

Percent of samples <MDL: 30.4% alpha activity, 18.8% beta activity

~

from the tank ~ are composited and analyzed for radioactivity. Nuclear fuel mate-rial bandled in unencapsulated form in this facility contains the uranium iso-

, .. topes U 234

,U 235 ,U 236 , and U 238 Major quantities of other radionuclides in encapsulated form include Co 60 and'Pml47 . No significant quantities of these radionuclides were released.

2. - Santa Susana Field Laboratories Site

a. Building 020 - NRC and California State Lirdrsed Activities-

, Operations at Building 020 that may generate radioactive effluents consist of hot cell examination of irradiated nuclear fuels and reactor components.

On'ly atmospheric emissions are released from the building to uncontrolled areas.

The discharge may contain particulate material, as well as radioactive gases, depending on the operations being performed and the history of.the irradiated fuel _ or other material. No radioactive liquid waste is released from the facility.

I Ra'd ioactive material handled in unencapsulated form in this. facility includes the following radionuclides: Th, U, Pu, as constituents in the various fuel materials; and Cs 137 , Sr90, Kr85, and Pm I47 as mixed fission products.

b. ^ Buildings 021 and 022 - DOE Contract Activities Operations at Buildings 021 and 022 that may generate. radioactive effluents consist o'f the processing, packaging, and temporary storage of liquid and dry radioactive waste material for disposal. Only atmospheric emissions are released from the building to uncontrolled areas. No radioactive liquid waste is released from the facility. Nuclear fuel material handled in encapsulated or unencapsu-lated' form contains the uranium isotopes U and Pu, plus Cs 137 , 3790, and Pm 147

~

as mixed fission products.

f~

h

_, ESG-83-17 47

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 atraospheric 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) l contain the following radionuclides: U plus Pu 238 , Pu 239 , Pu 240 , Pu 241 ,and i

241 Am ,

C. ESTIMATION OF GENERAL POPULATION DOSE ATTRIBUTABLE TO ESG OPERATIONS - 1982 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 neutral 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 D lofting diffusion conditions above the inversion and considerable atmospheric dispersion, prior to any diffusion 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 l 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 precipitation. Diffusion characteristics are highly variable depending on the

! location of the front. Generally, a light to moderate southwesterly wind precedes these frontal passages, introducing a strong onshore flow of marine air and lapse rates that are slightly unstable. Wind speeds increase as the frontal systems approach, enhancing diffusion. The diffusion characteristics of the

. ESG-83-17 -

48

frontal 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 frequency occurring for winds from the north to northwest sectors. Local population distribution estimates for 1981,

. based on the 1980 federal census, for areas surrounding the De Soto and SSFL sites and out to 80 km for 16 sectors are shown in Tables 13 and 14.

The downwind concentration of radioactive material emissions to the atmos-phere during 1982 from each of the four major ESG nuclear facilities has been calculated with the AIRDOS-EPA computer code using site-specific input data.

To determine the nearest site boundary and nearest residence maximum radio-activity concentrations, a mean wind speed of 2.2 m/s for each stability class was selected to evaluate the plume centerline (maximum) concentrations toward the sector in which those locations lie. The 80-km concentration is not direc-tion specific but is given for comparison with the nearby concentration values.

These are shown in Table 15.

The general population man-rem dose estimates are calculated from the demo-graphic distribution and the sector total inhalation intake (man-pCi/ year) generated by AIRDOS-EPA, which uses release rate, wind speed, wind direction and frequency, inversion, lapse, and effective stack height parameters as input data. Population dose estimates are presented in Tables 16 and 17 for the De Soto and SSFL sites. The exposure mode is by inhalation with lung the critical organ for U and Pu, and bone for Sr90 The doses reported for SSFL site emissions are summed for all release points and nuclides.

. ESG-83-17 49

~

TABLE 13 DES (340f0SITEDEMOGRAPHY-1981 13'54"N, 118 35'12"W)

Centered Azimuth 0

Direction 22.5 Toward Sector (deg) 0-1.6 km 1.6-3.2 km 3.2-4.8 km 4.8-6.4 km 6.4-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total i

N O- 0 527 -3.437 8 0 2,483 31,112 5,718 738 2,444 46,467 NNE 22-1/2 1,407 4 ,36 0 4,542 4,550 10.388 5,022 22,207 6,734 25,388 42,248 126,846 NE 45 126 3,616 4,391 3,181 10,563 64,364 18,639 5,383 21,750 6,932 138,945

.Q ENE 67-1/2 0 0 7.26 3 4,551 7,499 107,317 87,278 3,078 271 552 217,809

? E 90 2,701 4,204 6,088 8,807 13,290 111.190 277,042 470,238 492.682 368.758 1,755,000

$$ ESE 112-1/2 1.4 30 2,455 7, 16 9 9.837 11,371 78,493 478,488 1,151,795 811,774 852,309 3,405.121 h SE 135 1.324 4,045 8.717 10,886 16,600 35,573 410.956 795,894 773,769 229,030 2,286,794 SSE 157-1/2 929 7.681 9,530 2,543 8,131 6,519 87.880 0 55,599 0 178,812

, S 180 0 5.744 3,743 2,309 5,549 17,658 7,554 0 0 0 42,557 SSW 202-1/2 4.384 3,778 7,330 9,866 9.330 15,514 4,905 0 0 0 55.107 SW 225 3.697 2,633 6,863 3,614 9,768 3.139 27,213 969 0 0 57,896 WSW 247-1/2 0 5.295 1,189 4,232 4 0 82,022 39,794 136,563 0 269,099 W 270 0 0 897 51 0 26,335 38,145 49,946 84,637 34.472 234,483 WNW 292-1/2 0 2,106 0 0 564 26.119 809 12,534 1,887 1.556 45,575 NW 315 0- 7,561 0 0 0 97 1,565 0 241 1,987 11.451 NNW 337-1/2 0 2.861 2,004 392 0 414 16,387 4.449 280 288 27,075 Total 15.998 56,866 73,163 64.827 103,057 500,237 1,592,202 2,546,532 2,405,579 1,540,576 8.899.037

+

8 . , ,

1 TABLE 14 SANTA SUSANA FIELD gLABORATORIESgSITE DEMOGRAPHY - 1981 (34 13'50"N, 118 32'45"W)

Centered Azimuth

. Di rection 22.5* Toward Sector (deg) 0-1.6 km 1.6-3.2 km 3.2-4.8 km 4.8-6.4 km 6.4-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total .{

N 0 0 0 2,436 3,597 7.682 97 16,387 '4,449 730 89 35,467

l. NME 22-1/2 0 0 0 8,350 2,468 41 33,977 8,274 3,815 24,562 '81,487 '

m. NE 45 0 1,209 0 564 0 26,411 9,844 4,270 53,563 106,253 l m 392 l

T) ENE 67-1/2 0 0 0 51 883 45,597 264,064 58,027 10 '1,219 369,851

$$' E- 90 0 0 0 2,107 5,661 111,226 405,120 '522,360 692,884 581,012 2,320,370 '

. ESE 112-1/2 0 0 0 548 8,346 '53,282 138,131 1,189,218 1,180,366 1,015.060 3,584,951  ;

SE 135 0 0 0 0 0 18,022 80,026 177,617 515,221 '200,041 990,927

! SSE 157-1/2 0 0 0 113 3,025 0 5,183 0 0 0 8,321 S 180 0 0 0 0 0 '8,876 .4,134 0 0 0 13.010 SSW 202-1/2 0 0 0 ~ 4.396 0 10,474 6.638 0 0 ~0 21,508 l SW '225 0 0 0 0 0 15,395 1,125 0 0 0 16 ,520 WSW 247-1/2 0 0 0 0 0 38,005 58,298 135,222 3,195 0 234,720 W 270. 0 0 0 0 0 3,982 28,824 77,255 42,697 13,212 165,970 WNW 292-1/2 0 0 2,914- 3,145 14.747 3,237 7,%4 12,288 18,433 .0 62,728 NW 315 0 0 4,093 13,753 4,001 0 7,861 0 241 618 30,567 NNW 337-1/2 0 0 0 6.144 3,257 607 1.565 0 0 .2,186 13,759 Total 0 1,209 '9,443 42,768 50,070 309,233 1,085,708 2,194,554 2.461,862 1,901,502 8,056,409 i

TABLE 15 MAXIMUM D0WNWIND PLUME CENTERLINE CONCENTRATIONS OF GASEOUS EMISSIONS - 1982 Release 3 Distance (m) to Downwind Concentration ( C1/cm )a Rate .

Facility (Ci/ year) Boundary Residence Boundary Residence 80 km B/001 2.1 x 10-6 110 W 171 SW 1. 7 x 10-17 1.9 x 10-17 6.1 x 10-20 B/020 1.4 x 10-5 305 NW 1900 SE 1.9 x 10-17 9.9 x 10-18 3.4 x 10-19 B/022 6.3 x 10-7 350 NW 2300 SE 2.7 x 10-19' 2.3 x 10-19 1.3 x 10-20 B/055 1.2xlb-6 400 NW 1830 SE 3.4 x 10-18 1.0 x 10-18 2.6'x 10-20 a

Assume li = 2.2 m/s average wind speed, constant direction, full year.

The offsite doses are extremely low compared with the maximum permissible exposures recommended for the general population. These maximum permissible values are 3 Rem / year for bone and 1.5 Rem / year for the lung for an individual.

The general population values are one-third of the individual exposures. The maximum possible individual dose for 1982 at the De Soto boundary is calculated to be 0.1 mrem and is 0.03 mrem at the Santa Susana site boundary. These values are less than 0.02% of the permissible level of radiation in unrestricted areas of 500 mrem per year as specified in 10 CFR 20.105, CAC-17 Section 30268, and DOE Order 5480.1, Chapter XI, Part 4.b. Estimated radiation doses due to atmos-pheric emission of radioactivity from ESG facilities are a small fraction of the recommended limits and are far below doses due to internal deposition of natural radioactivity in air, which is approximately 50 to 100 mrem / year.

ESG-83-17 ,

52

TABLE 16 POPULATION DOSE ESTIMATES FOR ATMOSPHERIC EMISSIONS

)

FROM THE DE S0TO FACILITY - 1982 g

Dose to Receptor Population Segmerit (man-Rem)

Sector 0-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total N 5.8 x 10-4 7.2 x 10-5 4.1 x 10-4 4.8 x 10-5 4.6 x 10-6 -1.2 x 10-5 1.2 x 10-3 NNW 5.9 x 10-4 7.4 x 10-6 1.3 x 10-4 2.3 x 10-5 1.1 x 10-6 8.6 x 10-7 7.5 x 10-4 NW 1.1 x 10-3 1.7 x 10-6 1.2 x 10-5 0 9.1 x 10-7 5.9 x.10-6 1.1 x 10-3 WNW 6.3 x 10-4 9.2 x 10-4 1.3 x 10-5 1.3 x 10-4 1.4 x 10-5 9.2 x 10-6 1.7 x 10-3 W 9.2 x 10 -5 5.8 x 10-4 3.8 x 10-4 3.2 x 10-4 4.0 x 10-4 1.3 x 10-4 1.9 x 10 WSW 1.4 x 10-3 0 4.4 x 10-4 1.4 x 10-4 3.4 x 10-4 0 2.3 x 10-3

O SW 1.4 x 10 -3 2.8 x 10-5 1.2 x 10-4 2.6 x 10-6 0 0 1.6 x 10-3 ui c$ SSW 2.0 x 10-3 1.5 x 10-4 2.2 x 10-5 0 0 0 2.2 x 10-3

$ S 1.7 x 10-3 3.6 x 10-4 7.2 x 10-5 0 0 0 2.1 x 10-3 SSE 3.5 x 10-3 1.6 x 10-4 9.6 x 10-4 0 2.8 x 10-4 0 4.9 x 10-3 SE 3.8 x 10-3 8.2 x 10-4 4.4 x 10-3 5.4 x 10-3 3.8 x 10-3 8.8 x 10-4 1.9 x 10-2 ESE 2.4 x 10-3 1.4 x 10-3 4.0 x 10-3 6.1 x 10-3 3.2 x 10-3 2.6 x 10-3 2.0 x 10-2

-3 E 2.2 x 10-3 1.4 x 10 1.6 x 10-3 1.8 x 10-3 1.4 x 10-3 7.9 x 10-4 9.2 x 10-3 ENE 5.5 x 10-4 9.5 x 10-4 3.6 x 10-4 8.1 x 10-6 5.2 x 10-7 8.3 x 10-7 1.9 x 10-3 NE 1.0 x 10-3 7.8 x 10-4 1.0 x 10-4 1.9 x 10-5 5.7 x 10-5 1.4 x 10-5 2.0 x 10-3 NNE 2.1 x 10-3 8.9 x 10-5 1.8 x 10-4 3.5 x 10-5 9.6 x 10-5 1.2 x 10-4 2.6 x 10-3 Total 2.5 x 10-2 7.7 x 10-3 1.3 x 10-2 1.4 x 10-2 9.6 x 10-3 4.6 x 10-3 1.2 x 10-1 Notes:

1. Average individual dose = 1.3 x 10-8 Rem for the total population of 80-km radius area.

2. Total 80-km radius man-Rem dose estimate from naturally occurring airborne radioactivity dose to the lung of %0.1 Rem / year = 1,000,000 (1.0 x 106) man-Rem.

TABLE 17 POPULATION DOSE ESTIMATES FOR ATMOSPHERIC EMISSIONS FROM SSFL FACILITIES - 1982 g Dose to Receptor Population Segment (man-Rem)

Sector 0-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total N 3.7 x 10-5 8.8 x 10-8 6.4 x 10-6 1.1 x 10-6 1.3 x 10-7 1.2 x 10-8 4.5 x 10-5 NNW 1.5 x 10-5 3.4 x 10-7 4.6 x 10-7 0 0 1.8 x 10-7 1.6 x 10-5 NW 4.1 x 10-5 0 2.1 x 10-6 0 2.9 x 10-8 5.8 x 10-8 4.3 x 10-5 WNW 6.7 x 10 -5 3.9 x 10-6 4.4 x 10-6 -4.4 x 10-6 4.8 x 10-6 0 8.4 x 10-5 W 0 2.9 x 10-6 9.9 x 10-6 1.7 x 10-5 6.8 x 10-6 6.7 x 10-6 4.3 x 10-5 h NSW 3.2 x 10-5 2.3 x 10-5 2.4 x 10-5 3.7 x 10-7 0 0 7.9 x 10-5 Eb SW 1.4 x 10-5 0 0 0 0 0 1.4 x 10-5 b SSW 1.5 x 10-5 0 0 0 0 0 1.5 x 10-5 S 5.0 x 10-5 0 0 0 0 0 5.0 x 10-5 SSE 2.8 x 10-5 0 0 0 0 <

0 2.8 x 10-5 SE 1.8 x 10 -5 0 0 0 0 0 1.8 x 10-5 ESE 1.4 x 10-4 1.1 x 10-4 1.4 x 10-4 3.6 x 10-5 0 0 4.3 x 10-4 E 2.0 x 10-4 4.8 x 10-4 2.2 x 10 -4 1.2 x 10-4 0 0 1.0 x 10-3 3.4 x 10 -4 -4 ENE 1.4 x 10 8.6 x 10-5 4.6 x 10-5 0 0 6.1 x 10-4 NE 2.7 x 10-4 9.0 x 10-5 1.7 x 10-9 1.3 x 10-7 0 0 3.6 x 10-4 NNE 3.5 x 10-5 5.2 x 10-6 1.0 x 10-6 9.6 x 10-6 0 0 5.1 x 10-5 Total 1.3 x 10-3 8.6 x 10-4 4.9 x 10-4 2.3 x 10-4 1.2 x 10-5 7.0 x 10-6 2.9 x 10-3 Average individual dose = 3.6 x 10-10 Rem for the 80-km radius area total population.

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APPENDIX A COMPARIS0N OF ENVIRONMENTAL RADI0 ACTIVITY DATA FOR 1982 WITH PREVIOUS YEARS This section compares environmental monitoring results for calendar year 1982 with previous annual data.

The data presented in Tables A-1 through A-5 summarize 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 onsite and the off-site samples, resulted from use of an improved counting system with a thinner sample configuration. The thinner sample increases the sensitivity of the detec-tor to alpha-emitting radionuclides in the sample, thus producing a higher mea-sured 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.

For all types of samples, the data indicate that there is no concentrated local source of unnatural radioactivity in the environment. Also, the similarity l between onsite and offsite results further indicates that ESG operations contrib-ute essentially nothing to general environmental radioactivity.

. ESG-83-17 55

TABLE A-1 S0Il RADI0 ACTIVITY DATA - 1963 THROUGH 1982 Onsite Average Offsite Average (10-6 pCi/g) (10-6 pCi/g)

Number of Number of Year Samples a 6 Samples a 6 1982 144 0.69 25 48 0.68 23 1981 144 0.69 25 48 0.64 23 1980 144 0.60 24 48 0.58 23 '

1979 144 0.64 25 48 0.50 23 1978 144 0.63 24 48 0.51 24 1977 144 0.56 24 48 0.53 23 1976 144 0.56 25 48 0.56 24 1975 144 0.60 25 48 0.58 24 1974 144 0.60 25 48 0.54 24 1973 144 0.57 25 48 0.51 24 1972 144 0.56 25 48 0.57 24 1971 144 0.55 25 48 0.53 23 1970 144 0.47 27 48 0.48 25 l 1969 144 0.42 27 48 0.42 25 l 1968 144 0.47 26 48 0.48 26 1967 144 0.42 28 48 0.39 24 1966 144 0.41 29 48 0.44 25 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 l

ESG-83-17 56

. TABLE A-2 VEGETATION RADI0 ACTIVITY DATA - 1963 THROUGH 1982 Onsite Average Offsite Average (10-6 pCi/g ash). (10-6 pCi/ gash)

Number of Number of Year Samples a 8 Samples a 8 1982 144 0.16 140 48 0.17 130 1981 144 <0.20 137 48 <0.21 129 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 144 0.33 159 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 l 1966 144 0.37 169 48 0.37 123 1965 144 0.56 16 2 142 0.61 138 1964 154 0.50 211 293 0.51 181 1963 156 0.44 465 456 0.37 388

. ESG-83-17 57

TABLE A-3 SSFL SITE DOMESTIC WATER RADI0 ACTIVITY DATA -

1963 THROUGH 1982 Number of Average a Average 8 Year Samples (10-9 pCi/ml) (10-9pCi/ml) 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 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 ESG-83-17 '

58

. ~ _ -

4 TABLE A-4 BELL CREEK AND ROCKETDYNE DIVISION RETENTION POND RADI0 ACTIVITY DATA - 1966 THROUGH 1982 Samples Interim Retention Final Retention Pond Bell Creek Mud Bell Creek Vegetation Bell Creek Water Pond Water R-2A Water 54 54 16. 6 12 Average Average Average Average Avera9e Number (10-6 pC1/g) Ntsnber (10-6 pCi/g ash) Number (10-9 pCi/ml) Number (10-9 pC1/ml) Number (10-9 pCi/ml) of of of of of Year Samples a 8 Samples a B Samples a 8 Samples a 8 Sagles a 8 1982 12 0.64 25. 12 0.08 160. 12 0.03 3.3 12 0.17 3.9 12 0.11 3.9 1981 12 0.58 24. 12 <0.13 10 3. 12 <0.23 3.8 12 <0.23 4.2 12 <0.25 5.2 rn 1980 12 0.51 23. 12 <0.18 150. 12 <0.22 2.9 12 <0.22 2.9 12 <0.22 3.9 m

p 1979 12 0.46 23. 12 <0.26 136. 12 <0.23 3.2 12 <0.25 3.1 12 <0.23 4.5 e

$ 1978 12 0.42 23. 12 <0.26 156, 12 <0.24 2.5 12 <0.25 4.3 12 <0.25 4.6 1

1977 12 0.29 22. 12 <0.19 155. 12 <0.24 1.8 12 <0.24 4.3 12 <0.25 5.2 1976 12 0.38 23. 12 <0.17 164. 12 <0.25 2.2 12 <0.24 4.3 12 <0.28 4.4 t 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 5.6 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 16 5 . 12 0.15 3.7 12 0.15 6.9 12 0.12 7.4 1%9 12 0. 35 27. 12 0.28 166, 12 0.04 4.0 12 0.07 5.9 11 0.10 5.7 1968 11 0.32 24. l'1 0.39 170. 8 0.05 4.6 11 0.23 8.1 12 0.33 7.7

1%7 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

TABLE A-5 AMBIENT AIR RADI0 ACTIVITY CONCENTRATION DATA - .

1963 THROUGH 1982 De Soto Site Average SSFL Site Average a (10-12pCi/ml) (10-12pCi/ml).

Number of Number of Year Samples a 8 Samples a B 1982 727 0.0017 0.026 2347 0.0013 0.022 i

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 l

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 b

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 l 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 -

c 1963 l 360 -

6.6 292 -

4.7 a

Includes Rocketdyne Site Air Sampler Data Ambient air alpha radioactivity values were included in the beta values l

c and not reported separately prior to 1971 i

Insufficient data .

~

ESG-83-17 60

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 27 SEPTEMBER 1976 Discharge Rate Concentration Limit (1b/ day) (mg/ liter) 30-day 30-day Constituent Average Average Maximum Total dissolved solids 1,267,680 -

950 Chloride 200,160 -

150 Sulfate 400,320 -

' 300 a

Suspended solids 66,720 50 150 a

Settleable solids -

0.1 0.3 B00 26,690 20 60 5

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 ml) - -

23.0 Surfactants (as MBAS) 667 -

0.5 pH 6.0-9.0 a

Not applicable to discharges containing rainfall runoff during or immediately after periods of rainfall.

ESG-83-17 61

APPENDIX C REFERENCES

1. DOE Order 5484.1

2. DOE Order 5480.1

3. Code of Federal Regulations, Title 10, Part 20

4. California Radiation Control Regulations, California Administrative Code, Title 17, Public Health

5. California Regional Water Quality Control Board, Los Angeles Region, Order No.74-379, NPDES No. CA0001309, Effective 27 September 1976

6. AIRD0S-EPA: A Computerized Methodology for Estimating Environmental Concentrations and Doses to Man from Airborne Releases of Radionuclides, ORNL-5532

7. Estimates of Internal Dose Equivalent to 22 Target Organs for Radio-nuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, Volume III, ORNL/NUREG/TM-190 APPENDIX D EXTERNAL DISTRIBUTION l

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 g

4. U.S'. Department of Energy, San Francisco Operations Office

5. U.S. Nuclear Regulatory Commission, Division of Peactor Licensing

6. Gordon Facer, Division of Military Applications, DOE

7. Andrew J. Pressesky, Reactor Research and Development, DOE

8. James Miller, Divsion of Biomedical and Environmental Research, DOE

9. D0E-Headquarters Library, Attention: Charles Sherman ESG-83-17 63-

I i

l Rockwell International j Energy Systems Group 8900 DeSoto Avenue Canoga Park, California 91304

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