ML20076B007

Energy Sys Group Environ Monitoring & Facility Effluent Annual Rept,1978

ML20076B007
Person / Time
Site:	05000375
Issue date:	04/30/1979
From:	Johari Moore ROCKWELL INTERNATIONAL CORP.
To:
Shared Package
ML20076B003	List: ML20076A996 ML20076B005 ML20076B007
References
ESG-79-7, NUDOCS 7905080517
Download: ML20076B007 (57)

Text

._

ESG-79 7 ENERGY SYSTEMS GROUP ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT 1978 fp Rockweiiinternationai Energy Systems Group 8900 De Soto Avenue Canoga Park, California 91304 e

79050805

ESG 79-7 k

ENERGY SYSTEMS GROUP ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT 1978 O

BY J. D. MOOR E APPROVED  %"S-R. TUTTLE Manager Radiation and Nuclear Safety 9

RockwellInternational u Energy Systems Group 8900 De Soto Avenue Canoga Park, California 91304 ISSUED: APRIL 1979

. CONTENTS i

Page Abstract . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 I. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 II. Environmental Monitoring Summary Results . . . . . . . . . . . . . 19

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A. Radioactive Materials - 1978 . . . . . . . . . . . . . . . . . 19 B. Nonradioactive Materials - 1978 ............... 27 III. Environmental Monitoring Program . . . . . . . . . . . . . . . . . 29 A. General Description ..................... 29 B. Sampling and Sample Preparation ............... 29

1. Soil . . . . . . . . . . . . . . . . . . . . . . . . . . . 29

2. Vegetation . . . . . . . . . . . . . . . . . . . . . . . . 35 h 3. Water .......................... 35

4. Ambient Air ....................... 37 C. Counting and Calibration . . . . . . . . . . . . . . . . . . . 37 D. Nonradioactive Materials . . . . . . . . . . . . . . . . . . . 38 IV. Effluent Monitoring Program ................... 41 A. Treatment and Handling . . . . . . . . . . . . . . . . . . . . 41 B. Energy Systems Group Facility Descriptions . . . . . . . . . . 43

1. De Soto Site . . . . . . . . . . . . . . . . . . . . . . . 43

2. Santa Susana Field Laboratories Site . . . . . . . . . . . 44 C. Estimation of General Population Dose . . . . . . . . . . . . . 45 Appendices h A. Comparison of Environmental Radioactivity Data for 1978 with Previous Years . . . . . . . . . . . . . . . . . . . 49 B. California Regional Water Quality Control Board Criteria for Discharging Nonradioactive Constituents from Rocketdyne Division, SSFL .................. 55 C. References . . . . . . . . . . . . . . . . . . . . . . . . . . 57 D. External Distribution .................... 57 ESG-79-7 3

TABLES .

Page 1- A. Soil Radioactivity Data -- 1978 . . . . . . . . . . . . . . . . . . 18 1-B. Soil Plutonium Radioactivity Data - 1978 . . . . . . . . . . . . . 18

2. Vegetation Radioactivity Data -- 1978 . . . . . . . . . . . . . . . 20

3. SSFL Site -- Domestic Water Radioactivity Data - 1978 . . . . . . . 21

4. Bell Creek and Rocketdyne Site Retention Pond Radioactivity Data -- 1978 .................... 22

5. Ambient Air Radioactivity Data - 1978 .............. 24

6. De Soto and SSFL Sites -- Ambient Radiation Dosimetry Data - 1978 ........................... 25

7. Nonradioactive Constituents and Tritium in Wastewater Discharged to Unrestricted Areas -- 1978 ............. 26

8. Sample Station Locations . . . . . . . . . . . . . . . . . . . . . 32

9. Minimum Radioactivity Detection Limits (MDL) . . . . . . . . . . . 38

10. Atmospherically Discharged Effluent Released to Unrestricted Areas -- 1978 .................... 40

11. Liquid Effluent Discharged to Sanitary Sewer -- 1978 ....... 42

12. Surface Wind Conditions ..................... 45

13. Downwind Concentration of Gaseous Effluents -- 1978 . . . . . . . . 46

14. Population Dose Estimates for Atmospheric Discharged Effluents ............................ 47 A-1. Soil Radioactivity Data - 1957 Through 1978 ........... 50 A-2. Vegetation Radioactivity Data -- 1957 Through 1978 ........ 51 A-3. SSFL Site Domestic Water Radioactivity Data --

1957 Through 1978 ........................ 52 A-4. Bell Creek and Rocketdyne Division Retention Pond Radioactivity Data -- 1966 Through 1978 . . . . . . . . . . . . . . 53 A-5. Ambient Air Radioactivity Concentration Data --

1957 Through 1978 ........................ 54 B-1. NPDES No. CA00-01309, Effective September 27, 1976 ....... 55 t

ESG-79-7 4

FIGURES Page

1. Energy Systems 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 . . . . . . . . . . . . . . . . . . 15

5. Map of Canoga Park, Simi Valley, Agoura and Calabasas Sampling Stations . . . . . . . . . . . . . . . . . . . . . . . . . 28

6. Map of De Soto Site and Vicinity Sampling Stations ........ 30

7. Map of Santa Susana Field Laboratories Site Sampling Stations . . . 31

8. Daily Averaged Long-Lived Airborne Radioactivity at the De Soto and Santa Susana Field Laboratories Site - 1978 . . . . . . 36 0

9 ESG-79-7 5

ABSTRACT Environmental and facility effluent radioactivity monitoring at the Energy Systems Group (ESG) of Rockwell International (California operations) is performed by the Radiation and Nuclear Safety Group of the Health, Safety and Radiation Services Depart-ment. Soil, vegetation, and surface water are routinely sampled to a distance of 10 miles from ESG sites. Continuous ambient air sampling and also monitoring by thermoluminescent dosimetry are performed on-site for measuring airborne radioactivity concentra-tions and site ambient radiation levels. Radioactivity in ef-fluents discharged to the atmosphere from ESG facilities is con-tinuously sampled and monitored to ensure that levels released to unrestricted areas are within appropriate limits, and to identify processes which may require additional engineering safeguards to minimize radioactivity levels in such effluents. In addition, selected nonradioactive constituent concentrations in surface water discharged to unrestricted areas are determined. This report summarizes and discusses monitoring results for 1978.

The random variations observed in the environmental monitor-ing data indicate that no local source of unnatural radioactive material exists in the environs. Additionally, the similarity between on-site and off-site results further indicates that the contribution to general environmental radioactivity due to opera-tions at the 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.

ESG-79-7 6

1. INTRODUCTION The Energy Systems Group (ESG) of Rockwell International Corporation has been engaged in atomic energy research and development since 1946. The ESG is currently working on the design, development, fabrication, and testing of compo-nents 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) Prograni. Other programs include the development and fabri-cation of systems for stack gas S0 2 control, gasification and liquefaction of coal, and solid and liquid waste disposal.

The Group's administration, scientific research, and manufacturing facili-ties (Figure 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 of the Group's nuclear programs, under licenses issued by the Nuclear Regulatory Commission (4RC) and the State of California, are conducted here. These include: (1) Building 001 containing uranium fuel production facilities, and (2) Building 004 containing analytical chemistry laboratories, and a gamma irradiation facility. The 290-acre Santa Susana Field Laboratories site (SSFL), Figure 2, is located in the Simi Hills of Ventura County, approximately 29 miles northwest of downtown Los Angeles. The SSFL site is situated in rugged terrain typical of mountain areas of recent geological age. 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 scil on sandstone. Both Department of Energy (DOE) and ESG owned facilities share this site shown in Figure 3. The SSFL also contain facilities in which nuclear operations licensed by NRC and the State, are conducted. The licensed facilities include: (1) the Rockwell Inter-national Hot Laboratory (RIHL), Building 020; (2) the Nuclear Materials Develop-ment Facility (NMDF), Building 055; (3) a neutron radiography facility contain-ing the L-85 nuclear examination and research reactor, Building 093; and (4) several X-radiography inspection facilities. The location of these sites, in relation to nearby conmunities, is shown in Figure 4.

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ROCKWE LL/ GOVT. 4C 003 EXCESS EO JIPMENT STOR AGE GOVT. 7F 383 ROCKWELL 60 005 ENVIRONMENTAL SYSTEMS ROCKWELL 4D 453 ROCKWELL 60 006 SODIUM LABORATORY GOVT. 7D 457 ROCKWELL 6E 007 SODIUM STOR AGE GOVT. 8D 459 ROCKWELL 6E 008 F LAMMABLE MATERenL STOR AGE GOVT. 7F 461' ROCKWELL 9G 009 ENGINEERING DEVELOPMENT FACILITY GOVT. 8F 462 GOVT. 7D 010 D&D GOVT. 8F 463 ROCKWELL 6F 011 MANUFACTURING SUPPORT SHOP ROCKWELL 8G 473 GOVT. 70 012 TOOL CRIB - ETEC OPERATIONS GOVT. 7F 482 GOVT. 7D 013 THERMAL TRANSIENT FACILITY GOVT. 7F 483 GOVT. 3C 014 SODIUM STOR AGE BUILCING GOVT. 7F 484 ROCKWELL 7G 015 SUPPLEIMNTARY STORAGE BUILDING GOVT. 7F 485 GOVT. 70 019 ETEC CONSTRUCTION STAGING GOVT. 7F 486 ROCKWELL 8G 020 ENERGY SYSTEMS GROUP HOT LABOR ATORY GOVT. 487' GOVT. 6C 021 RADIOACTIVE WASTE, DECONTAMINATION AND PACKAGING BUILDING COVT. 488 GOVT. 6C 022 RADIOACTIVE WASTE STOR AGE VAULT BUILDING ROCKWELL 6F 500 GOVT. SD 023 LIQUID METALS CHEMISTRY LABOR ATORY ROCKWELL SE 501 GOVT. 60 024 DEVELOPMENT TEST BUILDING ROCKWELL 7E 502 GOVT. 6D 025 ETEC INSTRUMENTATION & INVENTORY STORAGE ROCKWELL 9G 509 i GOVT. 6E 026 SMALL COMPONENT TEST LOOP CONTROL BUILDING ROCKWELL 2B 511 GOVT. 60 027 ETEC QUALITY ASSURANCE GOVT. 3C 513

' GOVT. 60 028 LMFBR FUEL SAFETY ROCKWELL 8G 520 GOVT. 3D 029 SODIUM STOR AGE ROCKWELL SC 523 GOVT. 4C 030 SITE PURCHASING OF FICE ROCKWELL 5D 536

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GOVT. SD 032 ETEC GENERAL TEST GOVT. EF 538 GOVT. SC 034 R/A W ACTE OFFICE BUILDING ROCKWELL 7G 573 GOVT. SD 036 ETEC OPERATIONS ROCKWELL 28 583 GOVT. 7E 038 ETEC ADMINISTRATION ROCKWELL 5F 600 GOVT. 7E 039 OFFICE BUILDING ROCKWELL 6E 606 ROCKWELL 2C 040 FACILITIES AND INDJSTRIAL ENGINEERING ROCKWELL 6F 611 GOVT. SC 041 STOR AGE BUILDING ROCKWELL 6F 612 GOVT. 5D 042 LMFBR TEST GOVT. 7C 614 GOVT. 6C 044 RMDF CLEAN SHOP ROCKWELL 6E 616 ROCKWELL 4C 046 MATERIALOFFICE ANNEX GOVT. 6C 621 ROCKWELL 6E 048 PDU INSTRUMENTATION BUILDING ROCKWELL 2B 623 GOVT. 50 049 PDV CONTROL ROOM GOVT. 8E 626 ROCKWELL 8G 055 PLUTONIUM FACILITY ROCKWELL 4C 633 GOVT. 7E 057 ETEC LABORATORY GOVT. SD 636 GOVT. 80 059 LARGE LEAK TEST RlG GOVT. 4C 641 GOVT. 7E 062 ETEC INSTRUMENTATION GOVT. SC 654 GOVT. 30 064 SOURCE AND SPECIAL NUCLEAR MATERIAL STORAGE GOVT. 7E 656 GOVT. 7E 065 ETEC CHEMISTRY LABOR ATORY GOVT. GOVT. 6C 664 7E 066 INSTRUMENTATION REPAIR AND CALIBRATION BUILDING ETEC ROCKWELL GOVT. 6C 665 4C 074 STOR AGE BUILDING GOVT. 6C 075 GOVT. 4C 633 CONTAMINATED EQUIPMENT STORAGE BUILDING GOVT. 6C 608 g ROCKWELL 4C 083 CONTROL BUILDING - NEUTRON R ADIOGRAPHY BUILDING ROCKWELL GOVT. 4C 693 4C 093 NEUTRON RADIOGRAPHY BUILDING ROCKWELL 9F 100 GOVT. 48 695 ADVANCED FUELS LABORATORY ROCKWELL 10J 701 ROCKWELL 58 114 DECON TRAILER ROCKWELL SC 133 ROCKWELL 10J 702 SODIUM BURN FACILITY GOVT. BE 704 ROCKWELL 4B 143 SODIUM REACTOR EXPERIMENT- D&D GOVT. 8G 155 CONTROL CENTER ROCKWELL 6E 705 ROCKWELL 48 163 BOX SHOP ROCKWELL 6E 7 06 ROCKWELL 6F ROCKWELL 9G 709 171 X RAY BUILDING ROCKWELL 6F ROCKWELL 6F 711 172 X-R AY BUILDING ROCKWELL BH 172 GOVT. 70 713 GAMMAGRAPH BUILDING GOVT. 7D 719 ROCKWELL 48 183 FIRE PUMP BUILDING - D&D ROCKWELL 10G 3*4 ROCKWELL 80 720 LARGE LEAK INJECTOR DEVICE (LLID) TEST CONTROL BUILDING GOVT. 7D 726 GOVT. 28 J20 FUEL O!L CONTROL BUILDING ROCKWELL GOVT. 6D 727 3C 333 TIME CLOCK BUILDING ROCKWELL 7G 343 ROCKWELL 10G 730 TIME CLOCK BUILDING GOVT. 2A 731 ROCKWELL 7H 353 RESEARCH AND DEVELOPMENT LABORATORY BUILDING GOVT. 6E 354 GOVT. 6E 735 CONTROL ELEMENT TEST STRUCTURE GOVT. SD 742 GOVT. 7D 355 SCTI SUPPORT BUILDING GOVT. 70 356 GOVT. 48 753 SODIUM COMPONENT TEST INSTALLATION ROCKWELL 8G 755 GOVT. 7D 357 ETEC PUMP BEARING TEST FACILITY CONTROL BUILDING GOVT. 6E 358 GOVT. 7D 756 SCTl SUPPORT BUILDING GOVT. GOVT. 8E 757 7E 359 COMPRESSOR BUILDING GOVT. GOVT. 8D 759 7E 360 CHEMICAL STORAGE BUILDING ROCKWELL 8H 363 GOVT. 7F 762 RESEARCH AND DEVELOPMENT LABORATORY BUILDING GOVT. 3C 763 ROCKWELL 7G 373 DEVELOPMENT TEST BUILDING GOVT. GOVT. 48 773 l 7G 374 TEST LOOP ENCLOSURE GOVT. 8F 780 l g ROCKWELL 8G 375 CONTROL SHELTER BUILDING SCE 3C 783

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I ETEC CONSTRUCTION STAGING ROCKWELL 9F 800 ELECTRNAL SUBSTATION l STG. NEUTRON RADIOGR APHY STORAGE ROCKWELL 7E 805 PUMP BEARING TEST STRUCTURE TIME CLOCK BUILDING ROCKWELL 11G 814 LARGE LEAK INJECTOR DEVICE UNINTERRUPTIBLE POWER SUPPLY ROCKWELL 6E 816 RECOMBINER CANOPY MOTOR GENERATOR BUILDING SODIUM PUMP TEST FACILITY ROCKWELL SD 836 TIME CLOCK BUILDING CHCF GOVT. 7H 854 TEST STRUCTURE ROCKWELL 7H 863 HYDRAULIC TEST LOOP HYDR AULIC TEST INSTRUMENTATION BUILDING ROCKWELL 8G 873 HYDRAULIC TEST LABOR ATORY GOVERNMENT PROJECT OFFICES ETEC OFFICE COMPLEX ROCKWELL 7F 883 ELECTRICAL SUBSTATION REST ROOM - TRAILER ROCKWELL 10F 885 PISTON RANGE ETEC OFFICE COMPLEX ROCKWELL 11G 886 SODIUM DISPOSAL FACILITY ETEC OFFICE COMPLEX GOVT. 60 924 ELECTRICAL SUBSTATION ETEC OFFICE COMPLEX BOWL MEA REST ROOM TRAILER ROCKWELL H 13 306 PUMP HOUSE NO.1 COMPRESSED GAS BOTTLE STOR AGE DOCK ROCKWELL H -12 307 PUMP HOUSE NO. 2 PARKING LOT G 12 CONTROL CENTER PARKING LOT ROCKWELL 308 qOCKWELL G -13 320 POWER CONTROL PARKING LOT H 12 ROCKWELL 334 V.T.S. - 3 OPERATIONS AND WORKSHOP PARKING LOT H 12 ROCKWELL 391 V.T.S. - 3 WOR KSHOP PARKlNG LOT PARKING LOT PARKING LOT ROCKWELL ROCKWELL H 12 G 12 393 401 PLUME STUDY BLDG.

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ROCKWEL L H 12 405 STEAM PLANT BLDG.

PARKING LOT ROCKWELL G 13 416 ELECTRICAL BLDG. j PARKING LOT ROCKWELL G 13 PRE *EST - BOWL 437 PARKING LOT ROCKWELL F 11 964 SEWAGE TREATMENT PLANT BLDG.

CONSERVATION STORAGE YARD SECAGE TREATMENT PLANT HYDROGEN RECOMBINER TEST PAINT SPR AY BOOTH STORAGE BUILDING DRAINAGE SUMP COOLING TOWER RADIOACTIVE ACCOUNTABLE WASTE STORAGE Bb.LDING GUARD POST NO.1 ETEC INVENTORY STOR AGE RE ACTOR COOLING WATER PAD GUARD POST RECEIVING & STORAGE BUILDING INTERIM RADIOACTIVE WASTE - D&D SCTI COOLING TOWER LOW LEVEL RADIOACTIVE WASTE PROCESSING RMDF OXIDATION FACILITY ELECTRICAL SUBSTATION I AUMILI ARY SKl0 BUILDING i ELECTRICAL SUBSTATION NO.1 \

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STOR AGE SHED 1.5M FUEL OIL STOR AGE TANK I 86K FUEL OIL STORAGE DAY TANK ELECTRICAL SUBSTATION PRIMARY FlLL TANK VAULT-D&D ELECTRICAL SUBSTATION ELECTRICAL SUBSTATION i ELECTRICAL SUBSTATION Figure 3. Map of Santa Susana {

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ELECTRICAL SUBSTATION Facilities DR AINAGE CONTROL DAM ELECTRICAL SUBSTATION (Sheet 2 of 2) i E LECTRICAL SUBSTATION ESG-79-7 f 13 i

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i F. um ~.f#dN-W-", ,p, 1@$ M @l1$ o M.5 7 .4 % N T MM . v ~h. ~-iL,U Figure 4. Map of General Los Angeles Area (Reproduced by permission of Automobile Club of Southern California)

Also included within the SSFL site is an 82-acre Government-optioned area where DOE-contract activities are conducted, primarily by the non-nuclear Energy Technology Engineering Center (ETEC). The major operational nuclear installation within the optioned area is the Radiodctive Material Disposal Facility (RMDF),

Buildings 021 and 022. This facility is used for processing wastes generated as a result of the D&D Program, begun in 1975. Several deactivated nuclear reactor l and support facilities, all within the optioned area, are affected by the D&D program. Currently involved are several facilities used for Systems for Nuclear Auxiliary Power (SNAP) reactor test op2 rations, Buildings 010, 024, and 059, and the SRE, Building 143. There is no fitsile material located at any of these facilities.

Licensed programs conducted during 1978 included: (1) commercial operation of the L-85 reactor for central station 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 development of processes for fabrication of advanced fuels.

The basic policy for control of radiological and toxicological hazards at ESG requires that through engineering controls adequate containment of such mate-rials be provided, and through rigid operational controls, that facility effluent releases and external radiation levels are reduced to a minimum. The environ-mental monitoring program provides a measure of the effectiveness of the Group safety procedures and of the engineering safeguards incorporated into facility designs. Specific radionuclides in facility effluent or environmental samples, although not routinely identified due to the extremely low radioactivity levels normally detected, may be identified by analytical or radiochemistry techniques if significantly increased radioactivity levels were observed.

In addition to environmental monitoring, work area air and atmospherically discharged effluents 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 l can occur.

ESG-79-7 16

Environmental sampling stations that are located within the boundaries of ESG sites are referred to as "on-site" stations; those located within a 10-mile radius of the sites are referred to as "off-site" stations. The on-site environs of the De Soto and SSFL sites are sampled monthly to determine the e.oncentration of radioactivity in typical surface soil, vegetation, and water. Soil is also sampled on site semiannually, for plutonium analysis. Similar off-site environ-mental samples, except for plutonium analysis, are obtained quarterly. Continu-ous on-site and off-site ambient air sampling provides information concerning long-lived airborne particulate radioactivity. A site ambient radiation monitor-ing program, utilizing thermoluminescent dosimetry (TLD), begun in 1971, was expanded during 1978.

Nonradioactive wastes released 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.

Liquid wastes generated at the De Soto site are discharged into the city sewage system. This effluent is sampled for determination of radioactivity. Sanitary sewage from all DOE and ESG facilities at the SSFL site is treated at an on-site sewage plant. The plant effluent drains into a retention pond, located on the adjoining Rocketdyne Division site. The surface water drainage system of the SSFL is composed of catch ponds and open drainage ditches leading to the Rocket-dyne retention pond. This pond also receives the ESG site sewage plant effluent.

Water from the pond 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 was also monitored at discharge for tritium,and for nonradioactive 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 1978. A com-parison of 1978 radioactivity results with previous years appears in Appendix A.

ESG-79-7 17

TABLE 1-A S0Il RADI0 ACTIVITY DATA - 1978 Gross Radioactivity (pCi/g) l Area Activity Sa ples Maximum Annual Average Value Observed (95% Confidence Level) Value*

-7 a 144 (6.3 1.5)10 9.9 x 10 -7 On Site 8 144 (2.4 0.09) 10-5 4.8 x 10 -5 a 48 -7 -7 (5.1 1.4) 10 10.0 x 10 Off Site B 48 (2.4 0.09) 10-5 3.4 x 10 -5

• Maximum value observed for single sample TABLE 1-B S0Il PLUT0NIUM RADI0 ACTIVITY DATA - 1978 Sample June 8,1978 Survey Results December 13, 1978 Survey Results 238 p3239 + Pu240 238 Pu Pu Pu239 + Pu240 (pCi/g) (pCi/g) (pCf/g) (pCi/g)

S-56 -9 -9 -9

(-2.90 2.3) 10 (1.04 2.3) 10 *

(9.05 3.61 10 S-57 -9 -9

(-2.13 2.2) 10 (1.14 2.2) 10 *

(6.21 3.5)10-9 S-58 -9 -9

(-3.59 2.3) 10 (1.46 3.0) 10 *

(5.54 2.8) 10-9 S-59 -9 -9 -9

(-3.61 2.3) 10 (3.10 3.4) 10 (1.22 2.4) 10 (5.98 2.8) 10-9 S-60 (-2.17 3.2) 10-9 -9 -9 (3.35 3.9) 10-9 (-3.66 1.7) 10 (8.28 4.4) 10 Note: Minus (-) indicates sample value less than reagent blank.

• Result significantly less than the minimum detection level.

I ESG-78-7 18 1

l. .

II. ENVIRONMENTAL MONITORING

SUMMARY

RESULTS A. RADI0 ACTIVE MATERIALS -- 1978 The sampling and analytic methods used in the environmental monitoring pro-gram for radioactive materials are described in Section III.

The average radioactivity concentrations in local soil, vegetation, surface water, and in ambient air for 1978 are presented in Tables 1 through 5. In cal-culating the averaged concentration value for the tables, those individual sam-ples having radioactivity levels less than their minimum detection levels (MDL) are assumed to have a concentration equal to the MDL. This method of data aver-aging, required by DOE Manual Chapter 0513, affords a significant level of con-servatism in the data, as evident in the tables, in that most radioactivity con-centrations are reported as "less than" (<) values. Thus, for measurements in which some 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. Except fcr ambient air radioactivity, none of the maximum observed values, which occurred randomly dur-ing the year, show a great increase over the average values beyond natural vari-ability. The air sample data reflect March and December atmospheric nuclear device detonations which resulted in marked but transient inc eases in local airborne radioactivity levels.

The results reported in Tables 1-A and 2 show no significant difference be-tween on-site and off-site samples. Table 1-B shows no significant variations in soil plutonium concentrations for the 1978 sample sets. The detected activity is due to a variety of naturally occurring radionuclides, and to radioactive fallout resulting from dispersal of nuclear weapons materials and fission products by atmospheric testing. Naturally occurring radionuclides include Be , K 40 , Rb O7 ,

147 Sm , and the uranium and thorium series (including the inert gas radon and its radioactivedaughters). Radioactivity from fallout consists primarily of the fission products Sr90 , y90 , Cs 137 , and Pm I47 , and also U 235 and Pu 239 ,

ESG-78-7 19

TABLE 2 VEGETATION RADI0 ACTIVITY DATA - 1978 Gross Radioactivity (pCi/9)

Area Activity Dry Weight Ash Samp1es Annual Average Annual Average Value Maximum Value 0 rv d (95% Confidence Level) e

-8 -7 a 144 (<5.8 4.1) 10 (<2.4 1.7) 10 9.6 x 10 -7

-5 -4 8 144 (2.6 0.05) 10 (1.66 0.03)10 3.19 x 10 -4

-8 -7 a 48 (<6.6 4.4) 10 (<2.4 1.6) 10 6.6 x 10 -7 Off Site

-5 -4 8 48 (3.3 0.07) 10 (1.43 0.03) 10 2.41 x 10 -4

• Maximum value observed for single sample 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. Conversion to the domestic water supply was completed during 1969. Two on-site water wells were operated during 1978 to reduce consumption of Ventury County domestic water as a conservation measure due to local drought conditions. The well water proportion in the blend aver-aged about 38% for the year for a total well water consumption of approximately 6

6.3 x 10 gal. Pressure for the water system is provided by elevated storage tanks.

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 a retention pond on Rocketdyne property. When full, the pond may be drained into Bell Creek, a tributary of ESG-79-7 20

TABLE 3 SSFL SITE - DOMESTIC WATER RADI0 ACTIVITY DATA - 1978 Gross Radioactivity Area Activity No. (pCi/mt)

Samples Maximum

• Average Value Observed (95% Confidence Level)

-10 ESG-SSFL a 24 (<2.6 2.8) 10 4.4 x 10 -10

-9 8 24 (3.0 0.8) 10 3.6 x 10 -9

• Maximum value observed for single sample 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-O tion 66-49 of September 21, 1966, a sampling station for evaluating environ-mental radioactivity in Bell Canyon was established in 1966. It is located approximately 2.5 miles downstream from the southern Rockwell International Corporation boundary. 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.

Comparison of the radioactivity 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 concentra-tion Guide values selected for each site are the most restrictive limits for those radionuclides currently in use at ESG facilities. The identity of all such radionuclides is known, irrespective of concentration. Accordingly, for SSFL site surface water, the Guide value of 5 x 10 -6 Ci/mta and 3 x 10-7 pCi/mtS, for Pu 239 and for Sr90, respectively, is appropriate. The correspond-ingly most restrictive Guide value for De Soto site wastewater radioactivity discharged to the sanitary sewage system, a controlled area, is 8 x 10-4 pCi/mta and 1 x 10 -3 pCi/mtB for U 235 and Co 60 , respectively. These values are established in 10 CFR 20, California Administrative Code Title 17, and DOE Manual Chapter 0524.

ESG-79-7 21

TABLE 4 BELL CREEK AND ROCKETDYNE SITE RETENTION POND RADI0 ACTIVITY DATA - 1978 Gross Radioactivity Concentration Area Activity 3 pjes Average Value Maximum *

% of (95% Observe.1 Guidet Confidence Level) Value Bell Creek a 12 (4.2 1.3) 10-7 7.4 x 10 -7 NA Mud No. 54

-5 (pCi/g) 8 12 (2.3 0.08) 10 2.7 x 10 -5 NA

-7 Pond R-2A a 12 (6.5 1.6) 10 9.0 x 10 -7 NA Mud No. 55 (pCi/g) -5 -5 0 12 (2.5 0.09) 10 2.8 x 10 NA k -7 V ta n a 12 (<2.6 1.7) 10 5.1 x 10 -7 NA

-4 Ci/ ash) S 12 (1.56 0.03) 10 2.14 x 10 -4 NA Bell Creek Vegetation a -8 -7 12 (<4.6 3.8) 10 1.0 x 10 NA No. 54 (pCi/g) -5 -5 B 12 (2.8 0.05) 10 4.4 x 10 NA dry weight)

-10 Bell Creek a 12 (<2.4 2.8) 10 <2.4 x 10 -10 <0.005 Water No. 16 (pCi/mt) 8 12 (2.5 0.8) 10-9 3.5 x 10 -9 0.8 Pond Water a -10 12 (<2.5 2.8) 10 3.5 x 10-10 <0.005 No. 6 (pCi/mt) 8 12 (4.3 0.8) 10-9 7.0 x 10 -9 1.4 S3FL Pond R-2A a -10 12 (<2.5 2.8)10 2.7 x 10-10 <0.005 Water No. 12

-9 (pCi/mt) 8 12 (4.6 0.8) 10 6.3 x 10 -9 1.5

• Maximum value observed for single sample.

tGuide: 5 x 10-6 pCi/mta, 3 x 10-7 pCi/mtS; 10 CFR 20 Appendix B, CAC 17, DOE Manual Chapter 0524.

NA - not applicable, no Guide value having been established.

ESG-79-7 22

The Guide value of 6 x 10 -14 pCi/mta for SSFL site ambient air radio-activity is due to work with unencapsulated plutonium. The Guide value of 3 x 10 -11 Ci/mtB for Sr 90 is due to the presence of fission products in irradi-ated nuclear fuel at the SSFL site. The Guide value of 3 x 10 -12 Ci/mta for De Soto site ambient air radioactivity is due to work with unencapsulated ura-nium (including depleted uranium). The Guide value of 3 x 10 -10 Ci/mtB for 60 Co for ambient air radioactivity 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 con-centration 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 the radon particulate daughters. The average concentrations of ambient air alpha and beta radioactivity are presented separately in Table 5.

Radioactivity levels observed in environmental samples for 1978, 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 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 continuing, although infrequent, foreign atmospheric nuclear tests continue to be occasionally ob-servable in daily ambient air radioactivity levels; however, the long-term effects on surface sample radioactivity levels are not discernible. The con-tinued relative constancy in current levels of environmental radioactivity is due primarily to the dominance of naturally occurring radionuclides in the envi-ronment and to the longer-life fission product radioactivity from fallout.

Site ambient radiation monitoring is performed with thermoluminescent dosimeters. Each dosimeter set contains two calcium fluoride (CaF M") IOW 2

background, bulb-type chip dosimeters. The dosimeter sets are placed at se-lected locations (Figures 6 and 7) on or near the perimeters of the De Soto and SSFL sites. Each dosimeter, sealed in a light-proof energy compensation shield, ESG-79-7 23

TABLE 5 AMBIENT AIR RADI0 ACTIVITY DATA - 1978 Maximum

• Site No. Averagefalue Observed  % of Activity Location Samples Value Guidet Confid ce Level) (daily)

De Soto a5 713 (<8.4 8.1) 10

-15 9.5 x 10 -14 <0.28 On Site (pCi/mt) 6** 713 (<9.1 1.7) 10

-14 1.4 x 10 -12 <0.030 SSFL a5 1724 (<7.2 7.9) 10

-15 2.1 x 10 -14 <12.0 On Site -14 -12 (pCi/mt) 6** 1724 (<8.8 1.7) 10 1.5 x 10 <0.29 SSFL Sewage Treatment a5 (<7.3 7.3) 10

-15 4.4 x 10 -14 <12.2 Plant 327

-14 Off Site B** (<8.4 1.6) 10 1.2 x 10 -12 <0.28 (pCi/mt)

-15 SSFL Control Center as (<7.1 7.3) 10 3.4 x 10 -14 <11.8 te E -14 j g g** (<8.9 1.6) 10 1.3 x 10 -12 <0.30

• Maximum value observed for single sample.

tGuide: De Soto site, 3 x 10-12 pCi/mta 3 x 10-10 pCi/mtS 10 CFR 20 Appendix B, SSFL site, 6 x 10-14 pCi/mta,3x10-1IpCi/mtB; 10 CFR 20 Appendix B, CAC 17, and DOE Manual Chapter 0524 SMDL = 6.0 x 10-15 uCi/mt - Individual daily samples with activity levels of 0 to 6.0 x 10-15 pCi/mt are recorded and averaged as 6.0 x 10-15 pCi/mt.

• • MDL = 1.2 x 10-14 pCi/mi - Individual daily samples with activity levels of 0 to 1.2 x 10-14 pCi/mt are recorded and averaged as 1.2 x 10-14 pCi/mt.

Indicated average values are upper limits, since some data were below the minimum detection levels. {

is installed in a polyethylene container which is mounted si meter above ground at each location. The dosimeters are exchanged and evaluated quarterly. There l 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 0.014 mrem /h for 1978. The average radiation dose rate and equivalent annual dose monitored at each dosimeter location are presented in Table 6.

ESG-79-7 24

TABLE 6 DE S0TO AND SSFL SITES - AMBIENT RADIATION DOSIMETRY DATA - 1978

^V*# ' Rate E"v 9 "t TCD Annual Dose re (mrem) 1 De Soto 0.016 140 2 De Soto 0.015 131 3 De Soto 0.014 123 4 De Soto 0.015 131 5 De Soto 0.015 131 6 De Soto 0.013* 114 7 De Soto 0.014 123 1 SSFL 0.017 149 2 SSFL 0.017 149 3 SSFL 0.017 149 4 SSFL 0.017 149 i

5 SSFL 0.011 96 6 SSFL 0.016 140 1 Off-Site Control 0.014 123 2 Off-Site Control 0.014 123 3 Off-Site Control 0.015 131

• Excludes second quarter data due to missing dosimeter.

tDosimeter partially shielded by water tank. Relocated to G 3600 exposure field beginning third quarter. Unshielded annual average dose rate is 0.014 mrem /h, equivalent to an annual dose of 123 mrem.

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 the natural background radiation compo-nent which exists as a consequence of cosmic radiation, radionuclides in the soil, and radon and thoron in the atmosphere, in addition to rad!cactive fallout from nuclear weapons tests. Locally, this is approximately 125 mrem / year. The small variability observed in the data is attributed to differences in elevation ESG-79-7 25

TABL( 7 it09RA0!GaCT]v[ (045TITU[%T5 A%D TRITip l4 kAiW4'[R D;5 CHARGE 0 ?O U%RESTE!CTED AR[A5 - 1978

( Analysis Results for hastewater ascharced from Pond R-2A to Bell Cree 6 on Gate ladicated - Saerle Station W-12)

January 5* Jan . ry 16* February 6* February 'li* March 1*

l Cons tituent s * ' '#

Result Res u l t Result * '# !

Resul t I# A $ul t I Guide fa de Guide G. ..a Guide Total Cissolved Solids (og/t) 225 23.7 217 72 .s 2 '? 29.6 147 15.5 107 11.3 Chloride (og/el 25 16.7 25 16 28 18.7 11 7. 3 4 7. 7 Sulfate (ag/t) 56 18.7 50 '6.7 63 21.0 28 9. 3 ,14 4.7 Suspended So11dsi (mget) 135 90.0 40 26.7 53 35.3 58 39.7 400 III.3 5ettleable So19dsi (at/t) 0. 2 66.7 0.1 <313 0.1 33.3 0. 3 100.0 0.6 200.0 800 (og/t) 65 108.3 3 5.0 9 15.0 6 1 1. 7 10.0 011 and Grease (ag/t) 2 13.3 2 13.3 s2 13.1 <1 6. 7 1 < 6. 7 Turbidity (TU) 85 - 32 39 53 -

165 -

Chromium (sq/ t) 0.011 110.0 0 003 30.0 0.006 6n 0 L . 00o 60.0 0.024 240.0 Fluoride (mg/t) 0,4 40.0 0. 3 31 0 03 30.0 0? 30.0 04 40.0 Boron (eg/t) 0.1 10.0 0.1 10 0 C1 P) 0 .. L 20.0 < 0. 2 -20.0 Residual Chlortee (eg/s) *0.05 50 0 0.02 20.0 < 0. 04 < 40. 0 J. 04 40 0 < . 04

. 410 Fetal Coltfore (Wm/100 mi) < 2. 2 9. 5 2. 2 9i 2.2 9. 5 < 2./ 95 16 0+ 69. 5 +

Sur f actants (mg/f ) < 0. 01 2. 0 0.006 1.2 0 01 2.0 -0/1 <2.0 a 01 <2.0 pH 7.5 7.6 2 3 7.6 7.6 4

Tritium * (Ji/cc) 1.1 10 1 37 1.1 x 10 0.37 <!-ln 10 ' n 3' " 1.1 a In -5 ,0.37 < l .1 x 10 < 0. 3 7 Rainfall (in.) 2 4 7 7 E 76 Estimated Ratefall R...off (gal) 8 4a 10 12a 10 6 = 10 2. 5 a 10 2.1 s 10 Release volume (gall 4a 10 6 1 /'

6m 10 _ 9a 10 g5 s' M

,,aro 10- m., 2r as e aro ,

• I nrii e Constituent s 1 of s c< t of 1 of 1 of Result sesult 4es =1 t Guide { "esult g gg vuide t Gu tde Total Dissolved Soltds (ag/ t) 4 73 40.8 32 6 34. 3 429 45.2 3R4 40.4 254 26.7 Chlorlde (eg/t) 50 33.3 76 50.7 61 417 44 29.3 26 17.3

%1f ate (eg/t) 93 31.0 f5 14.3 98 9 62 20.7 53 17.7 hspenced 5011651 (og/t) 25 16.7 63 45 3 ' 8. 7 44 29.3 100 66.7 Settleable Solids' (af/t) 0.1 33.3 0.1 < 3 3. 3 ' 0.1 < 3 3. 3 0.1 233.3 0.5 166.6 BJO (og/t) 5 8.3 to 3.6 3 7 l 11.7 6.0 1- 20.0 011 and Grease (sul/t)

'l 6. 7 1 61 i 6. 7 1 6. 7 <1 < 6. 7 s

Turbidity (TU) 14 -

55 - et 33 84 -

Chromium (*g/t) 0.039 390. 0 0.001 70 0 0.0 12 20.0 0.096 60,0 0. oor, 50.0 Fluuride (mg/t) 4. 9 490 0 1.0 100.0 1.1 110.0 0. 5 50.0 0.8 80.0 Boron (eg!!) 02 23.0 10.2 20 0 0. 3 30.0 0.2 210 G.2 < 20. 0 Residual Chlorlee (og/t} 0.1 100.0 0.04 40.0 ' O.04 410 0.04 40.0 0.04 < 40.0 Fecal Collform (wP4/100 st) hA 2. 2 95 16 69.5 2.2 - 9,5 <2.2 9. 5 Surfactants (mj/t) 0.02 40 0.03 60 0.N 8.0 0.03 6. 0 0.01 2.0 I pH 7.8 7.9 8.0 7.8 8.0 4

Trittue' ( Ct/cc) < 1.1 e 10 0.37 < 1.1 = 10 4 0.37 1.1 10 5

1 37 1.1 = 10 4 < 0. 37 < 1.1 x 10 4

< 0. 3 7 Rahfall ( te. ) 0.87 1.33 0 &' 0 65 1.23

1. 7 Estimated Rainfall Run of f (gal) 2.1 a 10 3. 2 s 10 2 10 1.4 10 7 7 4 s 10 Release volume (gal) 5.5 m ;0 5 5 6 3 , 33 5e 10 5 a 10 7 m if I 5eptember 5* No vembe r 11' moverM ?? Dareeer IP*

Cons tituents 1 of I o, * .-g g c, ~

Resul t gg Rewit gg Res ul t g, Pes It g, Total Dissolved solids (eg/t) 438 46.1 548 57.1 09 12.5 403 42.4 Chloride (og/A) 84 56.0 87 58.0 33 210 44 29.3 blfate (og/t) 115 38.3 183 61.0 au 26.7 R9 29.7 hspended Solidsl (eg/t) 16 10.7 18 17.0 e4. 7 tv 40 26.7 5ettleable Solidst (et/t) 03 100.0 0. 3 O cf). 0 0.1 < 1. 3 - 0.1 < 33. 3 BCD (ag/t) 5 8. 3 5 e.3 14 l3 3 $ 10.0 011 and Grease (ag/t) 1 < 6. 7 <1 s7 l' , i s1 6.7 Turbidi tt (TV) 7 -

10 62 34 Chro*tum tog /t) 0.003 30.0 0 005 50.0 009 L. 0.008 80.0 Fluoride (ag/t) 1.0 100.0 0. 8 2. 0 0.5 50.0 0. 5 50.0 acron (og/t) 0. 2 20.0 0. 3 I 30 0 0. I ' 11 0 0.2 M.0 Residual Chlortee (eg/t) 0.02 = 20. 0 0 04 4; s 10.04 . (0. 0 < 0. 04 s40 J Fecal Colifore (MP4/100 mt) 2.2 9. 5 2,2 9. 5 22 9. 5 52 40.0 Surfectants (,uj/t) 0.12 pH 82 24.0 0.07 is.O 0. d6 i2.0 0.11 - [l26. 0 7.8 - 8. 5 8.1 Tritlu=* (uCI/cc) < 1.1 x 10-5 0.37 < l.1 a 104 k 0 37 ' 1.1 y 10 ' ' -ca' < 1.1 x Ic d

0.37 Ratnf all (ie.) 1.0 0.96 1.49 1.06 7 7 Estimated Rafnf all Runoff (cal) 3 10 2. 3 a 10 3 m 10 I

2.5 a 15 Reiease Wolume (gal) 6 6 1.1 a 10 2.9 s 10 7,, {. 1. 6 x 11.*

kA = *ot Avatleble; analysts not requested or not performed. '

• Rainfall related discharge.

t = Tritium etnismm detec tion 1 tatt: (1.1 e 1.1) 10-5 ut< f,t ,

t = hot applicable to discharges containtne rainfa'l runoff o.. inq or t Tsiately a#ter periods of rainfall.

ESG-79-7 26

1 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

.: jose to' the general population or to individuals in uncontrolled areas resulted from ESG operations.

B. NONRADI0 ACTIVE MATERIALS - 1978 Processed wastewater and most collected surface runoff discharged from the SSFL site drains to Retention Pond R-2A, operated by Rocketdyne. Water samples are taken from the pond and analyzed for various constituents, as required by ,

the Regional Water Quality Control Board, and for tritium as required by NRC License - 5NM-21, for each discharge to Bell Canyon. The discharges are nor-nally required only as a result of excessive rainfall run-off. During such -

releases, the NPDES concentration limits for turbidity, and suspended and settleable solids do not apply. The results of analyses for each discharge for 1978, all of which were rainfall-related discharges, are presented in Table 7.

O ESG-79-7 27 1

1 1

9

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T APO CANYON

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t SsMsVALLEY

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AGOURA p SOlt AND VE GE Y AtlON

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0041319C Figure 5. Map of Canoga Park, Simi Valley, Agoura ,

and Calabasas Sampling Stations

- e 9

lli. 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 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 the Group 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 en-vironmental radioactivity. The locations of sampling stations are shown in Fig-O- ures 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 weapons, a general background level of radioactivity exists. The data are moni-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 takc' from the top 1/2-in. layer of und sturbed ground surface for gross radioactivity analysis and to a depth of 5 cm for plu-tonium analysis. The soil samples are packaged in plastic containers, and re-turned to the laboratory for analysis.

Sample preparation for gross radioactivity determination consists of trans-ferring the soils to Pyrex beakers, and drying in a muffle furnace at %5000C for 8 h. After cooling, the soil is sieved to obtain uniform particle size. Two-gram aliquots of the sieved soil are weighed, and transferred to copper planchets.

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

Plutonium in soil analysis is performed according to the guidelines specified in ESG-79-7 29

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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, Below Sodium Cleaning Facility at SRE Pond ll 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 17th Street SV-53 Rocketdyne Site Pond R-2A Spillway, Head of Bell Canyon SV-54 Bell Crecx 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 S - Soil Sample Station ESG-79-7 32

TABLE 8 SAMPLE STATION LOCATIONS (Sheet 2 of 3)

Station 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 O 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 G TLD-2 De Soto Site, West Boundary TLD-3 De Soto Site, Guard Post No. 1, Bldg. 201 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 TLD-1 SSFL Site, Bldg. 114 S -- Soil Sample Station W - Water Sample Station A -- Air Sampler Station TLD - Thermoluminescent Dosimeter Location ESG-79-7 33

TABLE 8 SAMPLE 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, Water Tank No. 701 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 lk ESG-79-7 34

U. S. NRC Regulatory Guide 4.5 titled " Measurements of Radionuclides in the Environment-Sampling and Analysis of Plutonium in Soil."

2. Vegetation The analysis of vegetation is performed as an adjunct to the soil analysis and is done to determine the uptake of radioactivity by plants. These plants do not contribute to the human food chain, nor is there significant agriculture or grazing in the inmediate 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 leaves.

Vegetation 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.

O Vegetation samples are first washed with tap water to remove foreign matter, and then thoroughly rinsed with distilled water. Washed vegetation is dried in l tared beakers at 1000C for 24 h for dry weight determination, then ashed in a muffle furnace at 15000C for 8 h, producing a completely burned ash. One-gram aliquots of pulverized ash from each beaker are weighed, and transferred to copper planchets. The vegetation ash is wetted in the planchet with alcohol, evenly dis-tributed to obtain unifonn sample thickness, dried, and counted for alpha and beta radiation. The dry / ash weight ratio is used for the determination of the equiva-lent dry weight gross radioactivity concentration value.

3. Water Surface and domestic supply water samples are obtained monthly at the SSFL site 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-tallizing dishes at %900C. The residual salts are redissolved into distilled water, transferred to copper planchets, dried under heat lamps, and counted for alpha and beta radiation.

ESG-79-7 35

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De Soto and Santa Susana Field Laboratories Sites - 1978 e

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4. Ambient Air Air sampling is performed continuously at tne De Soto and SSFL sites with automatic 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 to eliminate radon particulate daughters. 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 1978. The average beta concentration for each month is also indicated by horizontal bars.

The graph shows two prominent peaks occurring during the year, a moderate spring increase in concentration and subsequent decreasing levels through the year's end.

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 system, capable of the simultaneous counting of both alpha and net beta radiation.

The sample-detector configuration provides a nearly 2Tr 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 count rates (approximately 0.05 cpm a and 1.0 cpm 8) and sample size. For the table, the minimum statis-tically significant amount of radioactivity, irrespective of sample configuration, is taken as that amount equal in count rate to three ti,nes the standard deviation of the system background count rate.

Counting system efficiencies are determined routinely with Ra-D+E+F (with alpha absorber), Cl 36 , Th 30 ,U 35 , and Pu 239 standard sources, and with K40, in the form of standard reagent grade kcl, which is used to simulate soil and vegeta-tion samples. Self-absorption standards are made by dividing sieved kcl into samples, increasing in mass by 200-mg increments, from 100 to 3000 mg. Thi. sam-ples are placed in copper planchets, of the type used for environmental samples, ESG-79-7 37

TABLE 9 I

MINIMUM RADI0 ACTIVITY DETECTION LIMITS (MDL)

Sample Activity Minimum Detection Limits *

-8 gjjy a (5.8 6.9) 10 Soil

-7 8 (2.3 2.3) 10 Ci/g a -7 pCi/g ash (1.2 1.4) 10

-7 8 (3.7 3.6) 10 Ci/g ash a -10 pCi/mt (2.3 2.8) 10 Water

-10 8 (6.2 6.1) 10 Ci/mt a -15 (6.0 7.2) 10 Ci/mL Air

-14 pCi/mt 8 (1.2 1.2) 10

• 95% Confidence Level and counted. The ratio of sample activity to the observed net count rate for each sample is plotted as a function of sample weight. The correction factor (ratio) corresponding to sample weight may be 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 proved usable by applying it to various-sized aliquots of uniformly mixed environmental samples and observing that the resultant specific activities fall within the expected statistical counting error.

Since the observed radioactivity in environmental samples results primarily from natural and weapons-testing sources, and is at such low concentrations, an effort is not made to identify individual radionuclides. The detection of sig-nificant levels of radioactivity would lead to an investigation of the radio-active material involved, the sources and possible causes.

D. NONRADI0 ACTIVE MATERIALS Rockwell International Corporation, Rocketdyne Division, has filed a Report l of Waste Discharge with the California Regional Water Quality Control Board, and ESG-79-7 38

~

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 September 27, 1976, and supersedes all previously held permits for wastewater discharge from the Rocketdyne Division SSFL. Discharge of overflow and storm runoff only is permitted into Bell Creek from water reclamation retention ponds. Discharge generally occurs only during and immediately after periods of heavy rainfall or during extended periods of rocket engire testing.

Only one of the retention ponds receives influent directly from the ESG SSFL site. It is identified as retention pond R-2A, Water Sample Station W-12 in Table 8. The influent includes sewage treatment plant effluent and surface runoff water. Grab-type water samples, taken at the retention pond prior to a discharge, are analyzed for non-radioactive chemical constituents by a Cali-O fornia State certified analytical testing laboratory and for tritium. The spe-cific constituents analyzed for, and their respective limitations in discharged wastewater, are presented in Appendix B. Wastewater originating from facilities located throughout the SSFL site is composited in the reto tion pond. Therefore, the point of origin of nonradioactive constituents found in wastewater is im-possible to determine.

O ESG-79-7 39

3 .. .

TABLE 10 ATM0 SPHERICALLY DISCHARGED EFFLUENT RELEASED TO UNRESTRICTED AREAS - 1978 Approximate Approximate Annual

• Sampling Period Total Point of Effluent Activity Minimum Average Maximum Radio-Building Release Volume Monitored Detection Concentration Observed Activity Limit Concentration Released (ft )

3 (pCi/mt) (U II*E) (pCi/mt) (Ci) 10 a 1.7 x 10 <1.8 x 10

1. 1.4 x 10 -13 <1.6 x 10 -5 001 Stack Exit 2.3 x 10 8 5.4 x 10 -16 <5.8 x 10 -15 3.8 x 10 -I4 <5.0 x 10 -6 004 Stack Exit 3.4 x 10 10 a 2.7 x 10 -16 <6.8 x 10 -16 4.7 x 10 -15 <6.5 x 10 -7 y 8 9.2 x 10 -16 <4.5 x 10 -15 4.6 x 10 -14 <4.3 x 10 -6 a 0.9 x 10-16 <4.0 x 10~IO 1.8 x 10 -15 <1.3 x 10 -7 020 Stack Exit 1.1 x 10 10 8 3.0 x 10'16 1.4 x 10 -13 1.0 x 10 -12 5.9 x 10 -5 021- 10 a 2.1 x 10 -16 <3.2 x 10 -16 8.3 x 10 -16 <1.0 x 10-7 Stack Exit 1.2 x 10 022 8 7.0 x 10-16 3.5 x 10 -14 2.5 x 10 -13 <1.1 x 10 -5 055 Stack Exit 8.0 x 10 9 a 2.4 x 10 -16 <3.5 x 10 -16 9.7 x 10 -16 <8.1 x 10 -8 Total <9.6 x 10 -5 Annual average ambient air a <7.5 x 10-15

<8.8 x 10 -14 radioactivity concentration - 1978 8

• Effluent radioactivity is generally less than ambient air radioactivity. If released concentra-tions were at the ambient air radioactivity concentrations, a total of 2.4 x 10-4 Ci would be ,

released, which value is 2.5 times greater than the actual release. ,

IV. EFFLUENT MONITORING PROGRAM Effluents which may contain radioactive material are generated at ESG facilities as the result of operations performed under contract to DOE, under NRC Special Nuclear Materials License SNM-21, ard under State of California Radioactive Material License 0015-59. 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 effluents. No contaminated liquids are discharged to unrestricted areas.

() The level of radioactivity contained in all atmospherically discharged effluents is reduced to the lowest practicable values by passing the effluents through certified, high efficiency particulate air (HEPA) filters. These ef-fluents are sampled for particulate radioactive materials by means of continuous stack exhaust samplers at the point of release. In addition, stack monitors installed at Buildings 020 and 055 provide automatic alarm capability in the event of the release of gaseous activity from Building 020 or particulate activ-ity from Building 055. The HEPA filters used for filtering gaseous effluents are 99.97% efficient for particles of 0.3-pm diameter. Particle filtration efficiency increases above and below this size.

The average concentration and total radioactivity in gaseous effluent re-G leased to unrestricted areas is shownThe ineffectiveness Table 10.of the air cleaning systems is evident from the fact that in most cases, the gaseous efflu-ent released is less radioactive than the ambient air, which is indicative that there are not radioactivity releases during normal facility operations.

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.

Liquid wastes are discharged from Building 001 following analysis on a volume basis only. There is no continuous flow. Building 004 liquid chemical wastes are released to a proportional sampler installation which retains an aliquot ESG-79-7 41

i .

TABLE 11 LIQUID EFFLUENT DISCHARGED TO SANITARY SEWER - 1978 Approximate Annual Total

. . Approximate Maximum ,,

80ilding Point of Effluent Activity "L

. Average Radioactivity Release Volume Monitored Concentration Concentration Released j (pCi/mt) (pCi/mt)

(gal) (pCi/mt) (Ci) a 1.2 x 10

-9 1.5 x 10

-7 3.7 x 10 -7 2.3 x 10 -5 001 Retention 40,500 l Tank -9 -7 -7 -5 6 4.1 x 10 1.1 x 10 3.3 x 10 1.7 x 10 l

-8 1.2 x 10 -9 <2.1 x 10 1.5 x 10 -7

~0

, Propor- a <8.0 x 10 N e 004 tional 1,039,600 0 Sampler B 4.1 x 10 ~9 7.8 x 10 -8 1.4 x 10 ~0 3.1 x 10 -4 020* -

0 - - - - -

021 - 022* -

0 - - - - -

055* 0 - - - - -

• All liquid radioactive wastes are solidified and land buried as dry waste.

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t each. time a fixed volume is released to the sanitary sewage system. No radio-active liquid effluents are released from the Santa Susana Buildings 020, 021, 022, or 055, except as controlled liquid radioactive waste solidified for land burial. The average concentration and total radioactivity in liquid effluents discharged is shown in Table 11.

B. ENERGY SYSTEMS GROUP FACILITY DESCRIPTIONS

1. De Soto Site

a. Building 001 - NRC and California State Licensed Activities Operations at Building 001 which may generate radioactive effluents consist of production operations associated with the manufacture of enriched uranium fuel elements. Only atmospherically discharged effluents are released from the build-ing to uncontrolled 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 234 U ,U 5 ,U , and U 238 . No significant quantities of these radionuclides were released.

b. Building 004 - NRC and California State Licensed Activities Operations at Building 004 which may generate radioactive effluents consist 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 effluents are released from the building to uncontrolled areas.

1. Liquid laboratory wastes are released to a proportional sampler installation which retains an aliquot of wastewater each time a fixed volume is released to the facility sanitary sewage system. The aliquots are composited and analyzed for radioactivity. Nuclear fuel material handled in unencapsulated form in this facility contains the uranium isotopes U 234 ,U 235 ,U 36 , and U 38 Major quan- .

tities of other radionuclides in encapsulated form include Co60 and Pm 147 No .

significant quantities of these radionuclides were released. The monitoring of De Soto site sewage effluent for tritium commenced during December 1977 and con-tinues on the basis of a monthly analysis of a daily composited sample of total facility effluent collected at the discharge point into the municipal sewerage.

ESG-79-7 43

2. Santa Susana Field Laboratories Site

a. Building 020 - NRC and California State Licensed Activities Operations at Building 020 which may generate radioactive effluents consist of hot cell examination of irradiated nuclear fuels and reactor components. Only atmospherically discharged effluents are released from the building to uncon-trolled areas. The effluent may contain particulate material, as well as radio-active gases, depending on the operations being performed and the history of the irradiated fuel and other material. The chemical form of such materials may be U metal, U02 , 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 90 fuel materials; and Cs 137 , Sr , Kr85, and Pm 147 as mixed fission products. No significant quantities of these radionuclides were released.

b. Buildings 021 and 022 - DOE Contract Activities Operations at Buildings 021 and 022 which may generate radioactive effluents consist of the processing, packaging, and temporary storage of liquid and dry radioactive waste material for disposal. Only atmospherically discharged ef-fluents are released from the building to uncontrolled areas. No radioactive liquid waste is released from the facility. Nuclear fuel material handled in 234 35 encapsulated or unencapsulated form contains the uranium isotopes U ,U ,

236 U ,U 38 , plus Cs 137 , Sr 90 , and Pm 147 as mixed fission products. No signifi-cant quantities of these radionuclides were released. &

W

c. Building 055 - NRC and California State Licensed Activities Operations at Building 055 which may generate radioactive effluents consist of fabrication of plutonium and plutonium-uranium fuel pins. Only atmospheri-cally discharged effluents 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) 234 contain the following radionuclides: U ,U 35 ,U 236 ,U 238 , Pu 238 , Pu 239 ,

240 241 241 Pu , Pu , and Am . No significant quantities of these radionuclides were released.

ESG-79-7 44

l*

C. ESTIMATION OF GENERAL POPULATION DOSE 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. Although nocturnal cool-ing inversions are present they are relatively shallow in extent. During the summer season the subsidence inversion is present almost every day. The base and top of this inversion for the most part lie below the elevation of the SSFL site. Thus, any atmospheric release under this condition from the SSFL site would result in Pasquill 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 for

) the most part is missing. The surface air flow is dominated by frontal activity moving through the area or to the east. Frontal passages through the area during this season are generally accompanied by precipitation. Diffusion characteris-tics are highly variable depending upon the frontal location. Generally, a light to moderate southwesterly wind precedes these frontal passages introducing strong onshore flow of marine air, and lapse rates are slight neutral to lapse. Wind speeds increase with the approach of the frontal systems, enhancing diffusion.

The diffusion characteristics of the frontal passage are lapse conditions with light to moderate northerly winds. A summary of surface wind conditions for the local area is presented in Table 12.

ll TABLE 12 SURFACE WIND CONDITIONS Summer Winter Prevailing afternoon direction WNW NW Prevailing early morning direction ESE ESE Average daytime speed 8 mph 6 mph Average nighttime speed 3 mph 3 mph ESG-79-7 45

l .

The population distributions around the De Soto and SSFL sites used to esti-mate population doses in this section are based on the 1970 census data projected for 1980. The projections were based on an average growth rate of 5.17%/yr for this area. For population distribution at distances >5 miles out to 50 miles, a single distribution centered on 34014'25" north and 118039'00" west is used.

This location is between the two ESG sites which are % miles apart. This popu-lation distribution is also based on the 1970 census data, with the 1980 projec-tion based on the average growth rate of 5.17 %/yr.

The calculated downwind concentration of radioactive material discharged during 1978 from each of the four major ESG nuclear facilities is presented in Table 13. The Type B stability parameter coefficients and a mean wind speed of 2.2 m/s were used for the calculations.

TABLE 13 DOWNWIND CONCENTRATION OF GASE0US EFFLUENTS - 1978 Facility 0 Meters to Type 8 Stability py ) Type 8 stablitty l'i)

(Ct/s) x Downutnd 4Ct/ce")

Boundary Eesidence Boundary Residence 80 km Boundary Residence 80 km* Boundary Residence PO km B/001 6.7 a 10'I 3 110 m 7,g , gg41 171 SW 18 27 6800 12 17 2000 4.5 m 10-16 2.1 a 10-16 B/020 1. 9 a 10 42 305 W 1900 SE 50 290 6800 34 340 2000 1.6 s 10-16 2.7 a 10-18 2.0 a 10'N 8/022 3.5 ; 10*I3 350 W 2300 SE 55 310 6800 38 500 2000 2.4 a 10*II 3.3 m 10'I' 3.7 a 10 I B/055 2.6 a 10-15 430 W 1930 SE 68 260 6800 42 300 2000 1.3 a 10'I' 4.8 a 10'2I 2.7 a 10'I3

$eCs 1 yc e r The general population man-rem dose estimates calculated from demography data and the concentrations calculated for atmospherically discharged effiuent data are presented in Table 14.

It should be noted that these estimates assume level surrounding terrain and ignore the effect of the mountains that completely encircle the sites at distances of about 10 km. The air turbulence and changes in elevation associated with actual terrain would result in much lower concen-trations than those calculated.

~

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 bene, and 1.5 rem / year for the lung for an individual, and are one-third of ESG-79-7 46

TABLE 14 POPULATION DOSE ESTIMATES FOR ATM0 SPHERIC DISCHARGED EFFLUENTS Dose to Receptor Population Segment (rnan-rem)

Sector 0-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total N-NNE 0.0099 0.0000 0.0002 0.0000 0.0000 0.0000 0.010 NNE-NE 0.013 0.0000 0.0001 0.0000 0.0004 0.0000 0.014 NE-ENE 0.59 0.10 0.0008 0.0000 0.0000 0.0000 0.69 ENE-E 0.58 0.18 0.0016 0.0005 0.0002 0.0001 0.76 E-ESE 1.2 0.21 0.0026 0.0024 0.0014 0.0007 1.4 ESE-SE 1.4 0.11 0.0019 0.0029 0.0018 0.0008 1.5 SE-SSE 1.2 0.57 0.0008 0.0003 0.0005 0.0000 1.8 SSE-S 1.2 0.062 0.0000 0.0000 0.0000 0.0000 1.3

() S-SSW SSW-SW 0.0016 0.005 0.0000 0.0001 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.002 0.005 SW-WSW 0.0037 0.0000 0.0002 0.0000 0.0000 0.0000 0.004 WSW-W 0.031 0.0000 0.0001 0.0002 0.0002 0.0000 0.032 W-WNW 0.19 0.0008 0.0000 0.0001 0.0000 0.0000 0.19 WNW-NW 0.50 0.0001 0.0000 0.0000 0.0000 0.0000 0.5 NW-NNW 0.19 0.0000 0.0000 0.0000 0.0000 0.0000 0.19 NNW-N 0.0099 0.0000 0.0000 0.0000 0.0000 0.0000 0.010 7.1 1.2 0.0086 0.0064 0.0045 0.0016 8.4 ,

1. Average rem / man dose = 0.00001 rem for the 80 km segment average population.

G 2. Total 80 km man-rem dose estimate from naturally occurring airborne radioactivity dose to the lung of no.1 rem / year = 1,300,000 man-rem for the 80 km segment average population these values for the general population. From Table 14, it may be seen that the highest segment dose integral is for the 0-8 km se' gment equivalent to an average dose / man-year of 0.48 mrem equivalent to 0.096% of the maximum permissible expo-sure for an individual and 0.28% of the general population recommer.ded average exposure. Thus, atmospheric discharges from ESG nuclear facilities have resulted in estimated radiation doses which are a small fraction of the recommended limits. Doses due to internal deposition of natural radioactivity in air are s50 to 100 mrem per year.

ESG-79-7 47

APPENDIX A COMPARISON OF ENVIRONMENTAL RADIOACTIVITY DATA FOR 1978 WITH PREVIOUS YE ARS This section compares environmental monitoring results for the calendar year 1978 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 effective data. In some cases this is readily apparent in the data. For example, in Table A-1, a small but abrupt increase in the alpha activity reported for soil is seen to occur in 1971. This increase is observed in both the on-site and the off-site samples and resulted from use of an improved counting system with a thinner sample configuration. The thinner sample increases the sensitivity of the detector to alpha-emitting radionuclides in the sample, thus producing a higher measured specific activity.

Similarly, prior to 1971, gross activity in ambient air was measured, in-cluding both alpha and beta activity. In 1971, measurements were begun which allowed separate identification of these two types of activity.

The types of random variations observed in the data indicate that there is no local source of unnatural radioactivity in the environment. Also, the sim-ilarity between on-site and off-site results further indicate that the contribu-tion to general environmental radioactivity due to operations at ESG is essen-tially nonexistent.

ESG-79-7 49

?

TABLE A-1 S0ll RADI0 ACTIVITY DATA - 1957 THROUGH 1978 On Site-Average Off Sitg - Average (10-6 pCi/g) (10-0 uCi/g)

Year Number Number

" O " 6 Samples Samples 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 g

1975 144 0.60 25 48 0.58 24 W 1974 144 0.60 25 48 0.54 24 1973 144 0.57 25 48 0.51 24 1972 144 0.56 25 48 0.57 24 1971 144 0.55 25 48 0.53 23 1970 144 0.47 27 48 0.48 25 1969 144 0.42 27 48 0.42 25 1968 144 0.47 26 48 0.48 26 1967 144 0.42 28 48 0.39 24 1966 144 0.41 29 48 0.44 25 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-79-7 50

TABLE A-2 VEGETATION RADI0 ACTIVITY DATA - 1957 THROUGH 1978 On Sige -- Average Off-Sgte-Average (10- pCi/g ash) (10- pCi/g ash)

Year Number Number Samples " O " 0 Samples 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 48 <0.27 141 0 1973 144 <0.24 152 155 48 <0.24 142 1972 144 0.23 145 48 0.36 125 1971 144 0.24 165 48 0.31 132 1970 144 O.33 159 48 0.30 142 1969 144 0.40 165 48 0.36 144 1068 144 0.51 158 48 0.51 205 1967 144 0.62 286 48 0.39 413 1966 144 0.37 169 48 0.37 123 1965 144 0.56 162 142 0.61 138 1964 154 0.50 211 293 0.51 181 1963 156 0.44 465 456 0.37 388 0 1962 147 0.45 500 453 0.44 406 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 ESG-79-7 51

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

1957 THROUGH 1978 Number Average a Average B Year (10-9 pCi/mt) (10-9 pCi/mt)

Samples 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 j l 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 1.0 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 ESG-79-7 52

TABLE A-4 BELL CREEK AND ROCKETDYNE DIVISION RETENTION POND RADI0 ACTIVITY DATA - 1966 THROUGH 1978 Saaples Bell Creek Mud Bell Creek Vegetation Bell Creek Water Interim Retention Final Retention Pond Pond Water R-2A Water 54 54 16 6 12 l

Average Average Avera ge Average Avera ge l (10-6 Cig) (10-6 Ci/g ash) 3,"Oies -9 pCi/mt) No -9 pCi/mt) (10-9 pC1/m2)

Year 3,' jes 3,pj,3 (10 (10 jes 3, ies 3, a 8 a 8 a 6 a 8 a 8 m 1978 12 0.42 23. 12 <0.26 156. 12 <0.24 2.5 12 <0.25 4.3 12 <0.25 4.6 l

$ 1977 12 0.29 22. 12 <0.19 155. 12 <0.24 1.8 12 <0.24 4.3 12 <0.25 5.2

$h 19/6 1975 12 0.38 0.29 23.

22.

12 <0.17

<0.19 164. 12 <0.25

<0.22 2.2 2.4 12 <0.24 4.3

<0.24 4.2 12 <0.28

<0.31 4.4 4.5 4 12 12 123. 12 12 12 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 0.23 165. 12 0.15 3.7 12 0.15 6.9 12 0.12 7.4 l 1969 12 0.35 27. 12 0.28 166. 12 0.04 4.0 12 0.07 5.9 11 0.10 5.7 l 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 m

TABLE A-5 ,

AMBIENT AIR RADI0 ACTIVITY CONCENTRATION DATA -

1957 THROUGH 1978 DeSoto Site Average SSFL Site Averages (10-12 pCi/mt) (10-12 pCi/mt)

Year Number Number

" O " 6 Samples Samples 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 5 Includes Rocketdyne Site Air Sampler Data ESG-79-7 54

APPENDIX B CALIFORNIA REGIONAL WATER QUALITY CONTROL EOARD CRITERIA FOR , n DISCHARGING NONRADIOACTIVE CONSTITUENTS FROM ROCKETDYNE DIVISION, SSFL The discharge of an effluent in excess of the following limits given in Table B-1 is prohibited.

~

T/SLE B-1 NPDES NO. CA00-01309, EFFECTIVE SEPTEMBER 27, 1976 Discharge Rate Concentration Limit (lb/ day) (mg/A)

Constituent 30-day 30-day Maximum Average Average Total Dissolved Solids 1,267,680 -

950 Chloride 200,160 -

'150 Sul fate 400,320 -

300 Suspended Solids

• 66,720 50 150 Settleable Solids * -

0.1 0.3 BOD 200C 26,690 20 60 Oil and Grease 13,350 10 . - 16 Chromium 6.67 0.005 0.01 Fluoride 1,340 -

1.0 Boron 1,340 -

1.0 p Residual Chlorine - -

0.1 Fecal Coliform (MPN/100 mt) - - 23:0 Surfactants (as MBAS) 667 -

0.5 pH F.0-9.0

• Not applicable to discharges containing rainfall runoff during or inmediately after periods of rainfall. ,

s l

1 ESG-79-7 55 .

APPENDIX C REFERENCES

1. 00E 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 Ccde, Title 17, Public Health

5. ' alifornia C 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 y 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 6

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 2

l 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. Environmental Healt< Department, Ventura County, California

4. U.S. Department of 5,aergy, San Francisco Operations Office

5. U.S. Nuclear Regulatory Comission, Division of Reactor Licensing

6. Cordon Facer, Division of Military Applications, DOE

7. Agdrew 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-79-7 57

i RockwellInternational Energy Systems Group 8900 DeSoto Avenue

• Canoga Park, California 91304 I

i

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