ML19305E693

Environ Monitoring & Facility Effluent Annual Rept,1979.

ML19305E693
Person / Time
Site:	05000375
Issue date:	04/25/1980
From:	Johari Moore, Tuttle R EMVROCIE, ROCKWELL INTERNATIONAL CORP.
To:
Shared Package
ML19305E683	List: ML19305E682 ML19305E686 ML19305E693
References
ESG-80-7, ESG80-7, NUDOCS 8005200274
Download: ML19305E693 (57)

Text

_

ESG-80-7 O SooO.co;LW v

ENERGY SYSTEMS GROUP ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT 1979 BY J. D. MOOR E APPROVED: ,

4 R. J. TUTTLE Manager

)

Radiation and Nuclear Safety RockwellInternational sw Energy Systems Group 8900 De Soto Avenue Canoga Park, California 91034 ISSUED: APRll 25,1980 l

CONTENTS

, Page A b s t ra c t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6

. I. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 II. Environmental Monitoring Summary Results . . . . . . . . . . . . . 19 A. Radioactive Material s -- 1979 . . . . . . . . . . . . . . . . . 19

, B. Nonradioactive Materials - 1979 ............... 27 III. Environmental Monitoring Program . . . . . . . . ......... 25 A. General Description ..................... .3 B. Sampling and Sample Preparation ............... 29

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

2. Vegetation . . . . . . . . . . . . . . . . . . . . . . . . 35

3. Water .......................... 35

4. Ambient Air ....................... 37 C. Counting and Calibration . . . . . . . . . . . . . . . . . . . 37 D. Nonradioacti ve Ma terials . . . . . . . . . . . . . . . . . . . 38 IV. Effluent Monitoring Program ................... 41 A. Tre a tme n t a nd Han dl i n g . . . . . . . . . . . . . . . . . . . . 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 A. Comparison of Environmental Radioactivity Data f ar 1979 with Previous Years . . . . . . . . . . . . . . . . . . . 49 B. California Regional Water Quality Control Board Criteria for Discharging Nonradioactive Constituents from Rocketdyne Division, SSFL .................. 55 C. R e fe r e n c e s . . . . . . . . . . . . . . . . . . . . . . . . . . 57

. D. External Distribution .................... 57 ESG-80-7 3

TABLES Page 1-A. Soi l Ra di oa c ti vi ty Da ta - 1979 . . . . . . . . . . . . . . . . . 18 1-B. Soil Plutonium Radioactivity Data - 1979 . . . . . . . . . . . . 18

2. Vegetation Radioactivity Data - 1979 . . . . . . . . . . . . . . 20

3. SSFL Site - Domestic Water Radioactivity Data - 1979 . . . . . . 21

4. Bell Creek and Rocketdyne Site Retention Pond Radioactivity Data - 1979 ................... 22

5. Ambient Air Radioactivity Data - 1979 ............. 24

6. De Soto and SSFL Sites - Ambient Radiation Dosimetry Data - 1979 .......................... 25

7. Nonradioactive Constituents and Tritium in Wastewater Discharged to Unrestricted Areas - 1979 ............ 26

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

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

10. Atmospherically Discharged Effluent Released to Unrestricted Areas - 1979 ................... 40

11. Liquid Effluent Discharged to Sanitary Sewer - 1979 ...... 42

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

13. Downwind Concentration of Gaseous Effluents - 1979 . . . . . . . 46

14. Population Dose Estimates for Atmospheric Discharged Effluents ........................... 47 A- 1. Soil Radioactivity Data - 1957 Through 1979 .......... 50 A-2. Vegetation Radioactivity Data - 1957 Through 1979 ....... 51 l A-3. SSFL Site Domestic Water Radioactivity Data -

52 1957 Through 1979 .......................

A-4. Bell Creek and Rocketdyne Division Retention Pond Radioactivity Data - 1966 Through 1979 . . . . . . . . . . . . . 53 A-5. Ambient Air Radioactivity Concentration Data -

1957 Through 1979 ....................... 54 B- 1. NPDES No. CA00-01309, Effective September 27, 1976 . . . . . . . 55 ESG-80-7 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 Sampl i ng Sta ti ons . . . . . . . . . . . . . . . . . . . . . . . . . 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 - 1979 . . . . . . 36 e

S ESG-80-7 5

o 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, 3afety 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 radiation nonitoring 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 sumnarizes and discusses monitoring results for 1979.

The random variations observed in the ensironmental 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.

S ESG-80-7 6

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1. INTRODUCTION

. The Energy Systems Group (ESG) of Rockwell International Corporation has been engaged in nuclear energy research.and development since 1946. 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) Program. Other programs include the development and fabri-cation of systems for stack gas S02 control, production of gaseous and liquid fuels from coal, and solar and ocean thermal energy development.

The administration, scientific research, and manufacturing facilities (Figure 1) are located in Canoga Park, California, approximately 23 miles nort'1-west of downtown Los Angeles. The site is level, typical of the San Fernand Valley floor. Certain nuclear programs, under licenses issued by the Nuclear Regula'.ory Commission (NRC) 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 facil-ity. The 290-acre Santa Susana Field Laboratories site (SSFL), Figure 2, is located in the Simi Hills of Ventura County, approximately 23 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 l

irregular plateau sprinkled with outcroppings above the more level patches and l 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 (D0E) and ESG owned facilities share this site, shown in Figure 3. The SSFL also contains facilities in which nuclear operations licensed by NRC and the State, are conducted. The licensed facilities include:

(1) the Rockwell International Hot Laboratory (RIHL), Building 020; (2) the Nuclear Materials Development Facility (NMDF), Building 055; (3) a neutron radio-

- graphy facility containing the L-85 nuclear examination and research reactor, Building 093; and (4) sereral X-radiography inspection facilities. The location of these sites, in relation to nearby communities, is shown in Figure 4.

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ESG-80 7 11 b

BUILDING OWNED ZONE NUMBER DESCRIPTION OWNED ZONE ROCKWE LL/ GOVT. 4C 003 EXCESS EQUIPMENT STORAGE GOVT. 7F

. t ROCKWELL 60 005 ENVIRONMENTAL SYSTEMS ROCKWELL 4D l GOVT. 70 ROCKWELL 60 006 SODIUM LABORATORY k ROCKWELL 6E 007 SODIUM STOR AGE GOVT. 8D E

ROCKWELL 6E 008 FLAMMABLE MATERIAL STORAGE GOVT. 7F ROCKWELL 9G 009 ENGINEERING DEVELOPMENT FACILITY GOVT. 8F GOVT. 70 010 D&D GOVT. 8F ROCKWELL 6F 011 MANUF ACTURING SUPPORT SHOP ROCKWFLL 8G GOVT. 70 012 TOOL CRIB - ETEC OPERATIONS GOVT. 7F GOVT. 7D 013 THERMAL TRANSIENT FACILITY GOVT. 7F GOVT. 3C 014 SODIUM STOR AGk BUILDING GOVT. 7F RCCKWELL 7G 015 SbPPLEMENTARY STORAGE BUILDING GOVT. 7F GOVT. 70 019 ETEC CONSTRUCTION STAGING GOVT. IF ROCKWELL 8G 020 ENERGY SYSTEMS GROUP HOT LABOR ATORY GOVT.

GOVT. 6C 021 RADIOACTIVE WASTE. DECONTAMINATION AND PACKAGING BUILDING GOVT.

GOVT. 6C 022 RADIOACTIVE WASTE STOR AGE VAULT BUILDING ROCKWELL 6F GOVT. SD 023 LIQUID METALS CHEMISTRY LABOR ATORY ROCKWELL SE GOVT. 6D 024 DEVELOPMENT TEST BUILDING ROCKWELL 7E GOVT. 60 025 ETEC INSTRUMENTATION & INVENTORY STORAGE ROCKWELL 9G GOVT. 6E 026 SMALL COILPONENT TEST LOOP CONTROL BUILDING ROCKWELL 2B GOVT. 60 027 ETEC QUALITY ASSURANCE GOVT. 3C GOVT. 60 028 LMFBR FUEL SAFETY ROCKWELL 8G GOVT. 3D 029 SODIUM STOR AGE ROCKWELL SC GOVT. 4C 030 SITE PURCHASING OF FICE ROCKWELL SD GOVT. 50 032 ETEC GENE RAL TEST GOVT. 6F GOVT. SC 034 R/A WASTE OFFICE BUILDING ROCKWELL 7G GOVT. SD 036 ETEC OPER ATIONS ROCKWELL 28 GOVT. 7E 038 ETEC ADMINISTRATION ROCKWELL 5F GOVT. 7E 039 OFFICE BUILDING ROCKWELL 6E ROCKWELL 2C 040 FACILITIES AND INDUSTRIAL ENGINEERING ROCKWELL 6F GOVT. SC 041 STOR AGE BUILDING ROCKWELL 6F GOVT. 50 042 LMFBR TEST GOVT. 7C GOVT. 6C 044 RMDF CLEAN SHOP ROCKWELL 6E ROCKWELL 4C 046 MATERIAL OFFICE ANNEX GOVT. 6C ROCKWELL 6E 048 PDU INSTRUMENTATION BUILDING ROCKWELL 2B GOVT. 50 049 PDV CONTROL ROOM GOVT. 8E ROCKWELL 8G 055 PLUTONIUM FACILITY ROCKWELL 4C GOVT. 7E 057 ETEC LABORATORY GOVT. SD GOVT. 80 059 LARGE LEAK TEST RIG GOVT. 4C GOVT. 7E 062 ETEC INSTRUMENTATION GOVT. SC GOVT. 30 064 SOURCE AND SPECIAL NUCLEAR MATERIAL STORAGE GOVT. 7E GOVT. 7E 065 ETEC CHEMISTRY LABORATORY GOVT. 6C GOVT. 7E 066 INSTRUMENTATION REPAIR AND CALIBRATION BUILDING ETEC GOVT. 6C ROCKWELL 4C 074 STOR AGE BUILDING GOVT. 4C GOVT. 6C 075 CONTAMINATED EQUIPMENT STORAGE BUILDING GOVT. 6C ROCKWELL 4C 083 CONTROL BUILDING - NEUTRON RADIOGR APHY BUILDING GOVT. 4C ROCKWELL 4C 093 NEUTRON RADIOGRAPHY BUILDING GOVT. 4B ROCKWELL 9F 100 ADVANCED FUELS LABORATORY ROCKWELL 10J ROCKWELL SB 114 DECON TRAILER ROCKWELL 10J ROCKWELL SC 133 SODIUM BURN FACILITY GOVT. 6E ROCKWELL 4B 143 SODIUM REACTOR EXPERIMENT- D&D ROCKWELL 6E GOVT. 8G 155 CONTROL CENTER ROCKWELL 6E ROCKWELL 48 163 BOX SHOP ROCKWELL 9G ROCKWELL 6F 171 X-RAY BUILDING ROCKWELL 6F ROCKWELL 6F 172 X R AY BUILDING GOVT. 7D ROCKWELL 8H 173 GAMMAGRAPH BUILDING GOVT. 7D ROCKWELL 48 183 FIRE PUMP BUILDING - D&D ROCKWELL 8G ROCKWELL 10G 314 LARGE LEAK INJECTOR DEVICE (LLID) TEST CONTROL BUILDING GOVT. 7D GOVT. 2B 320 FUEL OIL CONTROL BUILDING GOVT. 6D ROCKWELL 3C 333 TIME CLOCK BUILDING ROCKWELL 10G ROCKWELL 7G 343 TIME CLOCK BUILDING GOVT. 2A ROCKWELL 7H 353 RESEARCH AND DEVELOPMENT LABORATORY BUILDING GOVT. 6E GOVT. 6E 354 CONTROL ELEMENT TEST STRUCTURE GOVT. SD GOVT. 7D 355 SCTI SUPPORT BUILDING GOVT. 4B

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GOVT. 7E 3C0 CHEMICAL STORAGE BUILDING GOVT. 7F ROCKWELL 8H 363 RESEARCH AND DEVELOPMENT LABORATORY BUILDING OOVT. 3C 4B ROCKWELL 7G 373 DEVELOPMENT TEST DUILDING GOVT.

d GOVT. 7G 374 TEST LOOP ENCLOSURE GOVT. 8F

ROCKWELL BG 375 CONTROL SHELTER BUILDING SCE 3C l

NILDING BUILDING DESCRIPTION OWNED 20NE NUMBER DESCRIPTION NUMBER 383 ETEC CONSTRUCTION STAGING ROCKWELL 9F 800 ELECTRICAL SUBSTATION 453 STG. NEUTRON R ADIOGR APHY STOR AGE ROCKWELL 7E 805 TIME CLOCK BUILDING 457 PUMP BEARING TEST STRUCTURE ROCKWELL 11G 814 LARGE LEAK INJECTOR DEVICE 459 UNINTERRUPTIBLE POWER SUPPLY ROCKWELL 6E 816 RECOMBINER CANOPY 461 MOTOR GENERATOR BUILDING ROCKWELL SD 836 TIME CLOCK BUILDING g 462 SODIUM PUMP TEST F ACILITY GOVT. 7H 854 TEST STRUCTURE 463 CHCF ROCKWELL 7H 863 HYDRAULIC TEST LOOP 473 HYDRAULIC TEST INSTRUMENT ATION BUILDING ROCKWELL 8G 873 HYDRAULIC TEST LABORATORY 482 GOVERNMENT PROJECT OF FICES ROCKWELL 7F 883 ELECTRICAL SUBSTATION 483 ETEC OFFICE COMPLEX RDCKWELL 10F 885 PISTON RANGE 484 REST ROOM - TRAILER ROCKWELL 11G 886 SODIUM DISPOSAL FACILITY 485 ETEC OFFICE COMPLEX GOVT. 60 924 ELECTRICAL SUBSTATION 486 ETEC OF FICE COMPLEX BOWL AREA 487 ET EC OF FICE COMPLEX ROCKWELL H 13 306 PUMP HOUSE NO.1 488 REST ROOM TRAILER ROCKWELL H 12 307 PUMP HOUSE NO. 2 500 COMPRESSED GAS BOTTLE STORAGE DOCK ROCKWELL G 12 308 CONTRCL CENTER 501 PARKING LOT ROCKWELL G.13 320 POWER CONTROL 502 PARKING LOT ROCKWELL H -12 334 V.T.S. - 3 OPERATIONS AND WORKSHOP 509 PARKING LOT ROCKWELL H 12 3S1 V.T.S. - 3 WOR KSHOP 511 PARKING LOT ROCKWELL H 12 393 PLUME STUDY BLDG.

513 PARKING LOT ROCKWELL G 12 401 INSTRUMENT AND WORKSHOP 520 PARKING LOT FMCKWELL H -12 405 STEAM PLANT BLDG.

523 PARKING LOT

. .OC KWE LL G 13 416 ELECTRICAL BLDG.

536 PARKING LOT ROCKWELL G -13 437 PRE. TEST - BOWL 538 PARKING LOT ROCKWELL F -11 964 SEWAGE TREATMENT PLANT BLDG.

573 PARKING LOT 583 CONSERVATION STORAGE YARD 600 SEWAGE TREATMENT PLANT COG HYDROGEN RECOMBINER TEST 611 PAINT SPR AY BOOTH 612 STORAGE BUILDING 614 DR AINAGE SUMP 616 COOLING TOWER 621 RADIOACTIVE ACCOUNTABLE WASTE STORAGE BUILDING 623 GU ARD POST NO.1 626 ETEC INVENTORY STORAGE 633 RE ACTOR COOLING WATER PAD 636 GUARD POST 641 RECEIVING & STORAGE BUILDING 654 INTERIM RADIOACTIVE WASTE - D&D 656 SCTl COOLING TOWER 664 LOW LEVEL R ADIOACTIVE WASTE PROCESSING 665 RMD5 OXIDATION FACILITY 683 E LECTRICAL SUBSTATlON 688 AUX LI ARY SKID BUILDING 693 ELECTRICAL SUBSTATION NO.1 6% COLD TR AP VAULT (SRE) - D&D 701 WATER TANK (DEER FLATS) 702 WATER TANK (DEER FLATS) 704 ELECT RICAL SUBSTATION 705 E LECTRICAL SUBSTATION 706 ELECTRICAL SUBSTATION 709 E LECTRICAL SUBSTATION 711 ELECTRICAL SUBSTATION 713 ELECTRICAL SUBSTATION 719 ELECTRICAL SUBSTATION 730 ELECTRICAL SUBSYATION 726 ELECTRIC AL SUBSTATION 727 ELECTRICAL SUBSTATION 730 STOR AGE SHED 731 1.5M FUEL OIL STOR AGE TANK 735 86K FUEL OIL STORAGE DAY TANK 743 ELECTRICAL SUBSTATION 753 PRIMARY FILL T ANK VAULT - D&D 755 ELECTRICAL SUBSTATION 756 ELECTRICAL SUBSTATION Figure 3. Map of Santa Susana f 757 759 E LECTRICAL SUBSTATION ELECTRICAL SUBSTATION Field laboratories Site 763 ELECTRICAL SUBSTATION Facilities ,

763 773 ELECTRICAL SUBSTATION DR AIN AGE CONTROL DAM (Sheet 2 of 2) 780 ELECTR? CAL SUBSTATION ESG-80 -7 783 E LECTRICAL SUBSTATION 13

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Figure 4. Map of General Los Angeles Area (Reproduced by pennission 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 Radioactive Material Disposal Facility (RMDF), -

Buildings 021 and 022. This facility is used for packaging of 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 va D&D Program. Currently involved are several facilities that had been used for SNAP, Systems for Nuclear Auxiliary Power, reactor test operations, Buildings 010, 024, and 059, and the SRE, Building 143. There is no fissile material located at any of these facilities.

Licensed programs conducted during 1979 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 saurces; 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 chemical 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, are not routinely identified due to the extremely low radioactivity levels normally detected, but would be identified by analytical or radiochemistry techniques if significantly increased radioactivity levels were observed.

In addition to environmental monitori;.g, 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 can occur.

ESG-80-7 16 l

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 concentration 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, measures radiation levels in the environs of both the De Soto and SSFL sites.

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 ccmposed 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 raclaimed 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 radioactive and nonradioactive pollutants by Rocketdyne Division as required by discharge permits issued to Rocketdyne by the California Regional Water Quality Control Board. I This report summarizes environmental monitoring results for 1979. A com- j parison of 1979 radioactivity results with previous years appears in Appendix A.

1 e

l ESG-80-7 17

TABLE 1-A S0Il RADI0 ACTIVITY DATA - 1979 Gross Radioactivity N

(pCi/g)

Area Activity Sampies Annual Average Value Max gbseved 9

(95% Confidence Level) Month Observed

-7 a 144 (6.4 1.5) 10 10.9 x 10-7 On Site (June)

-5 8 144 (2.5 0.1) 10 9.7 x 10-5 (November) a 48

-7 8.1 x 10-7 (5.0 1.4) 10 Off Site (January),5

-5 8 48 (2.3 0.1) 10 2.9 x 10 (January)

• Maximum value observ>;d for single sample TABLE 1-B S0IL PLUT0NIUM RADI0 ACTIVITY DATA - 1979 J

June 23, 1979 Survey Resuits December 17, 1979 Survey Results Sample Location 238 238 Pu Pu239+ Pu 240 Pu Pu239+ Pu 240 (pCi/g) (pCi/q) (uCi/a) (uCi/a) 9 S-56 (,1. 4 12.7)10-9 (9.9 3.9) 1T (-0.6 2.2) 10-9 ( 6.0 3.5) 10-9 S-57 (1.5 i 3.0)10-9 (2.5 2.4) 10-9 (-1.9 2.0) 10-9 ( 4.5 3.0) 10 '

! S-58 (-1.1 2.1)10-9 (2.2 2.2) 10-9 ( 3.3 5.3) 10-9 (18.9 i 8.7) 10-9 S-59 (-2. 0 i 1.9)10-9 (4.2 3.1) 10-9 ( 2.3 4.5) 10-9 (18.6 8.0) 10-9' S-60 (-2. 8 i 1.9)10-9 (0.3 i 1.6) 10-9 ( 0.2 -9 l 2.9) 10-9 ( 3.3. 3.1) 10 Note: Minus (-) indicates sample value less than reagent blank.

ESG-80-7 18 N . . ._ _

11. ENVIRONMENTAL MONITORING

SUMMARY

RESULTS A. RADI0 ACTIVE MATERIALS - 1979 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 1979 are presented in Tables 1 through 5. In cal-culating the averaged concentration value for the tables, those individual sam-ples having radicactivity 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 Mancal 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 adioactivity detected for a single sample is reported because of its significance in indicating the existence of a major episode or area-wide location of radioactive material deposition. None of the maximum ob-served values, which occurred randomly during the year as shown in the tables, show a great increase over the average values beyond natural variability. The ambient air sampling data show no greatly increasing or decreasing trends for the year and can be described as generally constant levels with only very minor transient increases 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 1979 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 although no atmospheric tests in the northern hemisphere 7 40 were announced during 1979. Naturally occurring radionuclides include Be , g ,

Rb87, Sm 147 , and the uranium and thorium series (including the inert gas radon and its radioactive daughters). Radioactivity from fallout consists primarily of the fission pror'ucts Sr90 _ y90 , Cs 137 , and Pm 147 , and also U 235 and Pu 239 ,

ESG-80-7 19

TABLE 2 .

VEGETATION RADI0 ACTIVITY DATA - 1979 Gross Radioactivity -

(pCi/g)  % of Ash Area Activity 3,"Pj,3 Dry Weight Wt ity Annual Maximum Value* <MDL Average Annual Average Value and Month Value (95% Confidence level) Observed

-8 a 144 (<5.2 3.5) 10 (<2.4 1.6) 10~7 1.4 x 10-6 35 On Site (December 8 144 (2.6 2 0.04) 10-5 (1.39 1 0.02) 10~4 2.48x10}4 0 (May)

-8 8.6 x 10~7 35 m 48 (<6.3 1 4.4) 10 (<2.3 t 1.6) 10~7 Off Site -5 (April) 8 48 (3.0 0.04) 10 (1.34 2 0.02) 10-4 2.30 x 10,4 0 (July)

• 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. Two on-site water wells were operated during 1979 to reduce consumption of Ventura County domestic water. The well water proportion in the blend averaged about 69% for the year for a total well water 7

consumption of approximately 7.9 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-80-7 20

TABLE 3 SSFL SITE - DOMESTIC WATER RADI0 ACTIVITY DATA - 1979 Gross Radioactivity N. (pCi/mt)

. Area Activity Samples M mum

• Average Value Value and (95% Confidence Level) Month Observed ESG-SSFL a 24 (<2.3 2.7) 10-10 <2.3 x 10-10

-9 (100% <MDL) 8 24 (1.8 0.7) 10 3.9 x 10-9 (ilulyl

• 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-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 concentration  !

Guide values selected for each site are the most restrictive limits for those ~

radionuclides currently in use at ESG facilities. Radioactivity cancentration guide values are those concentration limits adopted by the Department of Energy, the Nuclear Regulatory Commission, and the State of California as maximum per-missible concentrations (MPC). The MPC values are dependent upon the radio-nuclide and its behavior as a soluble or an insoluble material. For comparison with results of the environmental and effluent monitoring, the lowest MPC value for the various radionuclides present is selected. Accordingly, for SSFL site surface water, the Guide value of 5 x 10 -6 pCi/mL alpha activity corresponding 90 to Pu 239 and 3 x 10-7 pCi/mt beta activity corresponding to Sr are appropriate.

ESG-80-7 21

TABLE 4 BELL CREEK AND ROCKETDYNE SITE RETENTION POND .

RADI0 ACTIVITY DATA - 1979 Gross Radioactivity Concentration Area Activity Sapies Avera e Value Maximum *

% of S mp es t

Obs ved Guide with tivity Confidenc Level) Mo Bell Crcex a 12 (4.6 x 1.3) 10-7 6.2 x 10~7 NA 0 Mud No. 54 (July)

(pCi/g) 8 12 (2.3 0.1) 10

-5 2.7 x 10 _3 NA 0 (April)

Pond R-2A a 12 (7.1 2 1.6) 10-7 1.1 x 10 -6 NA 0 Mud No. 55 (June)

(pCi/g) 8 12 (2.5 1 0.1) 10-5 3.3 x 10-5 NA 0 (March)

Bell Creek a 12 (<2.6 1.7) 10-7 7.6 x 10-7 NA 25 Vegetation (April)

No. 54 8 12 (1.36 0.02) 10-4 2.08 x 10-4 NA 0 (pC1/g ash) (November)

Bell Creek -8 Vegetation a 12 (<7.5 4.8) 10 3.3 x 10~7 NA 25 No. 54 (April)

(pCi/g) 8 12 (3.0 2 0.1) 10-5 7.2 x 10-5 NA 0 i dry weight (November)

-10 2.4 x 10-10 91.7 Bell Creek u 12 (<2.3 2 2.7)10 <0.005 Water No. 16 (July)

(pC1/mt)

-9 8.2 x 10~9 1.1 0 8 12 (3.2 1 0.9)'10 (August)

Pond Water a 12 (<2.5 2.8)10-IO 5.5 x 10-10 <0.005 91.7 No. 6 (May)

(pCi/mt) 8 12 - (3.1 0.8) 10~9 4.7 x 10~9 1.0 0 SSFL Pond R-2A a 12 (<2.3 2.7)10-10 jx10-10 <0.005' 91.7 Water No. 12 (November (uC1/mt) 8 12 (4.5 0.8) 10~9 1.0 x 10- 1.5 0 (September)

• Maximum value observed for single sample.

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

~

j NA - not applicable, ao Guide value having been established. -

ESG-80-7 22

l The correspondingly 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/mt alpha activity corresponding to U 235 and 1 x 10-3 pCi/mt beta activity corresponding to Co 60 These values are established in 10 CFR 20, Cali-fornia Ao.7inistrative Code Title 17, and DOE Manual Chapter 0524.

-14 pCi/m21or SSFL site ambient air alpha acti-The Gaide value of 6 x 10 vity is due '.o work with unencapsulated plutonium. The value of 3 x 10-11 pCi/mt for beta activity is due to the presence of Sr 90 in fission products in irradi-

-12 pCi/mL for ated nuclear fuel at the SSFL site. The Guide value of 3 x 10 De Soto ambient air alpha activity is due to work with unencapsulated uranium (including depleted uraniun). The Guide value of 3 x 10-10 pCi/mi is for Co 60 for which the ambient air beta activity Guide is appropriate since it is the most restrictive limit for beta-emitting radionuclides present at the De Soto site.

Guide value percentages are not presented for soil or vegetation data since no concentration Guide values have been established.

Ambient air sampling for long-lived particulate alpha and beta radioactivity is performed continuously with automatic sequcntial 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 naturally occurring short lived particulate radioactivity. The average con-centrations of ambient air alpha and beta radioactivity are presented separately in Table 5.

Radioactivity levels observed in environmental samples for 1979, reported in l l

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 atmos- i pheric testing of nuclear devices, have decreased, and have been generally con-stant during the past several years. The effects of foreign atmospheric nuclear tests continue to be occasionally observed in daily ambient radioactivity levels, although this effect was not readily discernible during 1979. The long-tenn effects of airborne radioactivity on surface sample radioactivity levels are also not discernible in recent years. The continuing relative constancy in environ- j mental radioactivity levels is due primarily to the dominance of naturally occur-ring radionuclides in the environment and to the longer-life fission product radioactivity from aged fallout.

ESG-80-7 23

TABLE 5 AMBIENT AIR RADI0 ACTIVITY DATA - 1979 ,

"'  % of Samples Site Acticity No. Average Value  % of Loc 4 tion Samples (95% t with Activity 0 ate Guide ConfidenceLevel) <MDL er e De Soto a E

702 (<6.6 7.8) 10

-15 4.5 x 10 -14 <0.28 88.6 On Site ,, (06/28)

(pCi/mt) 8 702 (<2.1 1.3)10-I4 1.0 x 10-13 <0.030 36.7 (02/25) 5 -15 4.0 x 10-14 <12.0 91.0 SSFL a 1793 (<6.5 7.6) 10 On Site .,

-I4 (04/19 (pCi/mt) 8 1792 (<2.1 1 1.3) 10 1.1 x 10-13 <0.29 38.3 (03/07)

SSFL Sewage Treatment a 0

(<6.2 7.4) 10-15 2.0 x 10-14 <12.2 92.0 ant .. 362

~14 (09/29) '13 <0.28 Off Site 8 (<2.0 1.3) 10 1.1 x 10 41.4 (pCi/mt) (02/25)

SSFL Control a 5

(<6.2 2 8.4) 10-15 3.4 x 10-I4 <11.8 90.6 Center .. 364 (08/31)

Off Site 8 (<1.8 1.5) 10-14 1.0 x 10-13 <0.30 49.4 (pCi/mt) (03/06)

• Maximum value observed for sin le sample.

tGuide: De Soto site, 3 x 10-1 pCi/mta, 3 x 10 -10 pCi/mtB; 10 CFR 20 Appendix B, SSFL site, 6 x 10-14 pCi/mta, 3 x 10-11 pCi/mtB; 10 CFR 20 Appendix B, CAC 17, and DOE Manual Chapter 5MDL

=6.1x10g24pCi/mt - Individual daily samples with activity levels of 0 to 6.1 x :D-15 pCi/mt are recorded and averaged as 6.1 x 10-15 pCi/mt'

• • MDL = 1.2 x 10-14 pCi/mL - Individual daily samples with activity le/els of 0 to 1.2 x 10-14 pCi/mt are recorded and averaged as 1.2 x 10-14 pCi/mt. Indicated acerage values are upper limits, since some data were below the minimum detection levels.

Site ambient radiation monitoring is performed with thermoluminescent dosi-meters. Each dosimeter contains two calcium fluoride (CaF 2:Mn) low background, bulb-type chip dosimeters. The dosimeter sets are placed at selected locations (Figure 6 and 7) on or near the perimeters of the De Soto and SSFL sites. Each dosimeter, sealed in a light-proof compensation shield, is installed in a poly- -

ethylene container which is mounted si meter above ground at each location. The dosimeters are exchanged and evaluated quarterly. There were 13 on-site TLD ESG-80-7 24

l 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 0.015 mrem /h for 1979. The average radiation dose rate and equivalent annual

- dose monitored at each dosimeter location are presented in Table 6.

TABLE 6 DE S0TO AND SSFL SITES - AMBIENT RADIATION D0SIMETRY DATA - 1979 Aver D Rate E9 V "t TCD Annua 1 Dose (mrem) 1 De Soto 0.016 140 2 De Soto 0.015 131 3 De Soto 0.014 123 4 De Soto 0.016 140 5 De Soto 0.016 140 6 De Soto 0.017* 149 7 De Soto 0.016t 140 1 SSFL 0.017 149 2 SSFL 0.018 158 3 SSFL 0.022 193 4 SSFL 0.021 184 5 SSFL 0.016 140 6 SSFL 0.016 140 1 Off-Site Control 0.014 123 2 Off-Site Control 0.016 140 3 Off-Site Control 0.015 131

• Excludes first quarter data due to missing dosimeter.

~

tExcludes second quarter data due to missing dosimeter.

ESG-80-7 25

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

TA8LE 7 4 n0htA010 ACTIVE C0mSTITUECTS CJe TalTIC 14 isASTrisATER 015CMaarl0 TO UNRE5talCTio AREAS - 1979

- (Analysis Results for usstemater Otscharged from Pond R-2A to Bell Creek on Date Indicated - 5aspie Station M-12)

• January $* January 15* January 31' February 14*

• " I"" I '# I '# I I '#

I tesul t Result Result Result Guide i Gutde Guide Guide Total Dissolved Solfes (ag/4) 283 - 29.8 328 34.5 160 16.8 339 35.7 j ' Chieride (ag/t) 31 20.7 35 23.3 16 10.7 31 20.7 Sulfate (ag/t) 41 20.3 138 46.0 33 11.0 71 23.7 Suspended Solfds' (ms/t) 80.0 101 67.3 16 10.7 34 22.7

!.- 132 0.2 66.7 0.1 33.3 <0.1 < 33.3 0.1 33.3

! 5ettlea61e Solidsl(at/t) -

' 800 (mg/t) 7 11.7 6 10.0 2 3.3 5 8. 3 011 and Grease (og/t) 1.2 8.0 1.2 8.0 1 6.7 1 6.7 Tur61dity (TU) 46 - 74 -

14 -

32 -

Chromium (eg/t) 0.015 150.0 0.016 160.0 0.003 30.0 0.006 60.0 Fluoride (mg/t) 0. 3 J0.0 0.4 40.0 0.2 20.0 0.4 40.0 j

Borce (mg/t) 40.2 <20.0 <0. 2 <20.0 <0.1 < 10.0 0.1 10.0 Residual Chlorine (mg/t) <0.04 <40.0 <0.04 < 40.0 <0.04 540.0 <0.04 <40.0 Fecal Collform (MP4/100 m,1) <2.2 <9.5 <2.2 < 9. 5

• 2. 2 < 9. 5 M- -

Surfactants (ag/t) 0.09 0.04 0.08 0.06 i

p .82 8.0 78 84

< 1.1 8 10-5 <0.37 <l.1 a 10-5 ,0.37 41.1 x 10-5 .g,37 .g,3 , 30-5 <0. 37 Tritium' (uCf /st) 3.7 2.2 2.0 1.5 i Ratafall Jin.)

4.8 s 10#

7 I

Estimated Rainfall Runoff (gal) 8.9 a 10 5.2 a 10 3.6 u 10 6

telease volume (gal) 1.5 a 10 6

2.0 m to' l.3 a 106 1.2 a 10 k February 21* March 1* March 14* March 27 Constituents Result I

g [d Result Eesult h' Result Total Dissolved Solids (ag/t) 331 34.8 378 39.8 462 48.6 287 30.2 Chloride (ag/t) 36 24.0 J1 20.7 54 36.0 25 16.7 Sulfate (ag/t) 69 23.0 104 34.7 103 34.3 55 18.3 i

Suspended SolidsI (ag/1) 153 102.0 31 20.7 13 8.7 94 62.7 f 0.2 66.7 5ettleatie Solids' (at/t) <0.1 < 33.3 <0.1 < 33. 3 <0.1 < 33.3 j 6.7 800 (ag/t) 4 6.7 4 6.7 6 10.0 4 i

4 011 and Grease (ag/t) <l <6.7 0.6 4.0 1 6.7 2 13.3 Turbietty (TU) 42 - 26 - 4 - 88 -

Chromium (ag/s) 0.006 60.0 0.011 110.0 0.004 40.0 0.016 160.0 Fluoride (pg/t) 05 50.0 0.4 40.0 0.4 40.0 0.8 80.0 f 20,0 0.08 8.0 Boron (ag/t) 0.2 0.2 20.0 <0.1 < 10.0 l

1. esidual Chlorine (eg/t) <0.04 440.0 0.07 70.0 < 0.04 <40.0 <0. 04 <40.0 j

2 Fecal Celtform (MPN/100 ot) <2.2 <9.5 < 2. 2 <9.5 16 69.5 NA -

4 Surfactants (ag/t) 0.02 <0.01 0.04 0.02

) pH 8.0 7.8 8.3 8.1 4 <0.37 Tritivat (uC1/at) <1.1 x 10-5 <0. 37 <1.1 a 10-5 <0. 37 <1.1 a 10'I =0.37 <1.1 a 10 l Rainfall (In.) 2. 3 0.7 1.4 3.3

1. I I

! Estimated Rainfall Aunoff (gal) 5.4 a 10 1.8 a 10' 3.4 a 10 7.9 a 10 6 5 6 Release Voluse (gal) 1.3 a 10 3,3 , gg6 8.0 a 10 1.1 a 10 April !? October 23' noveseer 8* Deceamer 21*

Result h' Result h*[ Result ' h* Result Total Olssolved Solids (mg/t) 435 45.8 604 63.6 445 46.8 608 64.0 Chloride (ag/s) - 51 34.0 75 50.0 62 4 .32 76 50.7 Sulfate (mg/t) 111 37.0 174 58.0 132 44.0 170 $6.7 Suspended Sollos8 (ag/t) 18 12.0 6 4.0 165 1R 0 32 21.3 j

f <0.1 < 33. 3 <0.1 < 3L 3 <0.1 < 33. 3 5ettleable (Solids' (at/t) <0.1 < 33. 3 11.7 12 20.0 4 6,7 I 800 (ag/4) 8 13.3 7 011 and Grease (ag/t) <1 e6.7 2 13.3 <1 <6. 7 <1 <6.7 Tertidity (Til) 3 - 7 -

130 17 Chromium (eg/t) 0.003 30.0 0.004 40.0 0.014 140.0 ' O.004 ' 40.0 Fluoride (og/t) 0.3 30.0 0.7 70.0 0.7 70.0 1.0 100.0 Soron (og/t) 0.2 20.0 0.3 30.0 0.3 30.0 0.2 20.0 .

Residual Chlorine (ag/t) <0.004 < 4.0 <0.04 <40.0 <0. 04 c40.0 0.04 <40.0 Fecal Collform (wit /100 mt) n4 -

<2.2 < 9. 5 <!.2 <9.5 2.2 ' 9.5 Surfactants (ms/t) 0.03 0.04 0.03 0.01 pH 8.8 8.] 8.8 8.4 NA RA fritf um' (uCl/st) '1.1 a 10-5 <0.

• 7 4A Rainfall (in.) ' 0 0.5 1.2 1.0 Estimated Rainfall Runoff (gat) 0 1.2 a 10 2.9 a 10 2.4 x 10I telease Volume (tal) 1.5 a '0 ' 5 2.4 a 10 6 g,, , gg 6 1.8 a 106 f

.nA

• not Avatlettet analysts not requested ce not perforwed.

• Rainfall related discharge.

t e Trittum minimum detection Ilmit: (1.1 e 1.1) 10-5 uti/mt.

i

' l

• Not applicable to dischar9es containte) rainfall runoff during or issuedtately after periods of ratafall.

Note: Pond R 2 A capacity - 2.5 a 106 gal ESG-80-7 26.-

t

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j The table shows that radiation dose rates and equivalent annual doses mon 1-l tored on site are nearly identical to levels monitored at three widely separated

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i 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 radioactive fallout from nuclear weapons tests. Locally, this is approximately 135 mrem / year. The small variability observed in the data is attributed to differences in elevation and geologic conditions at the various dosimeter locations. Since the data for the on-site and off-site locations are nearly identical, no measurable radiation dose to the general population or to individuals in uncontrolled areas resulted from ESG operations.

B. NONRADI0 ACTIVE MATERIALS - 1979 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 for each dischcrge to Bell Canyon.

Tritium monitoring of discharged waste water was permanently discontinued during the fourth quarter of 1979 in conformance with a condition permitting this action in NRC License - SNM-21. The discharges are normally required only as a result of excessive rainfall run-off. During such releases, the NPDES permit concen-tration limits for turbidity, and for suspended and settleable solids do r.ot apply. The results of analyses for each discharge for 1979, most all of which were rainfall-related discharges, are presented in Table 7.

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00 41319D Figure 5. Map of Canoga Park, Simi Valley, Agoura and Calabasas Sampling Stations

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 proposeo 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-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 taken from the top 1/2-in. layer of undisturbed 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-l 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-80-7 29

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TABLE 8 SAMPLE STATION LOCATIONS (Sheet 1 of 3) ,

Station Location

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SV-1 SSFL Site, Bldg. 143 SV-2 SSFL Site, Bldg. 143 Perimeter Drainage System SV-3 SSFL Site, Bldg. 064 SV-4 SSFL Site, Bldg. 020 SV-5 SSFL Site, Bldg. 363 SV-6 Rocketdyne Site Interim Retention Pond SV-10 SSFL Site Access Road SV-12 SSFL Site, Bldg. 093 (L-85 Reactor)

SV-13 SSFL Site, at SRE Water Retention Pond SV-14 SSFL Site, Bldg. 028 SV-19 SSFL Site Entrance, Woolsey Canyon SV-24 De Soto Site, Bldg. 004 SV-25 De Soto Avenue and Plummer Street SV-26 Mason Avenue and Nordhoff Street SV-27 De Soto Avenue and Parthenia Street SV-28 Canoga Avenue and Nordhoff Street SV-31 Simi Valley, Alamo Avenue and Sycamore Road SV-40 Agoura -- Kanan Road and Ventura Freeway SV-41 Calabasas --Parkway Calabasas and Ventura Freeway SV-42 SSFL Site, Bldg. 886 SV-47 Chatsworth Reservoir North Boundary SV-51 SSFL Site, Bldg. 029 SV-52 SSFL Site, Burro Flats Drainage Control Pond, G Street and 17th Street SV-53 Rocketdyne Site Pond R-2A Spillway, Head of Bell Canyon SV-54 Bell Creek S-55 Rocketdyne Site Retention Pond R-2A (Pond Bottom Mud)

S-56 SSFL Site, F Street and 24th Street .

SV -- Soil and Vegetation Sample Station S - Soil Sample Station ESG-80-7 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 W-16 Bell Creek A-1 De Soto Site, Bldg. 001 Roof A-2 De Soto Sif ', Bldg. 004 Roof A-3 SSFL Site, Bldg. 009, West Side A-4 SSFL Site, Bldg. 011, West Side A-5 Rocketdyne Site, Bldg. 600, North Side A-6 Rocketdyne Site, Bldg. 207, North Side A-7 SSFL Site, Bldg. 074, South Side A-8 SSFL Site, Bldg. 143, West Side A-9 SSFL Site, Bldg. 363, West Side TLD-1 De Soto Site, South of Bldg.102 TLD-2 De Soto Site, West Boundary TLD-3 De Soto Site, Guard Post No.1, Bldg. 201 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 i

TLD - Thermoluminescent Dosimeter ' .ication l

l ESG-80-7 l 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, at Southwest Boundary TLD-6 SSFL Site, Bldg. 854 TLD-1 Off Site, Northridge TLD-2 Off Site, Simi Valley TLD-3 Off Site, Northridge TLD -- Thermoluminescent Dosimeter Location O

l ESG-80-7 34

U.S. NRC Regulatory GuiA 4.5 titled " Measurements of Radionuclides in the Environment-Sampling and Analysis of Plutonium in Soil" by a certified inde-

~

pendent testing laboratory.

2. Vegetation O

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 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 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 c t analyzed.

Vegetation samples are first washed with tap water to remove foreign matter, and then thoroughly rinsed with distilled water. Washed vegetation is dried in tared beakers at 1000C for 24 h for dry weight determination, then ashed in a  ;

muffle furnace at %5000C 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 uniform 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-80-7 35

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3 JAN FEB MAR APR MAY JUNE JULY AUG SEPT OCT NOV DEC Figure 8. Daily Averaged Long-Lived Airborne Radioactivity at the De Soto and Santa Susana Field Laboratories Sites - 1979

4. Ambient Air l

Air sampling is performed continuously at the De Soto and SSFL sites with automatic air samplers, operating on 24-h sampling cycles. Airborne particulate j radioactivity is collected on Type HV-70 filter media, which are automatically l 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 3

) a typical daily ambient air sample is approximately 25 m ,

Figure 8 is a graph of the dally averaged long-lived alpha and beta ambient '

air radioactivity concentrations for the De Soto and SSFL sites during 1979. The l average beta concentration for each month is also indicated by horizontal bars.

! The graph shows that no prominent peaks occurred during the year, and that radio-activity concentrations were essentially constant through the year.

C. COUNTING AND CALIBRATION i

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.

1 The sample-detector configuration provides a nearly 2n geometry. The thin-window detector is continually purged with methane counting gas. A preset time mode of i operation is used for all samples. The minimum detection limits shown in Table 9

) were determinea 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, .

j is taken as that amount equal in count rate to three times the standard deviation j of the system background count rate.

! Counting system efficiencies are determined routinely with Ra-D+E+F (with alpha absorber), Cl 6 , Th 230 ,U 235 , and Pu 239 standard sources, and with K40, in f~ the form of standard reagent grade kcl, which is used to simulate soil and vegeta- l

! tion-samples. Self-absorption standards are made by dividing sieved KC1 into  !

f* 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, l

i ESG-80-7

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TABLE 9 MINIMUM RADI0 ACTIVITY DETECTION LIMITS (MDL)

Sample Activity Minimum Detection Limits Soil a 5.7 x 10-8 uCi/g B 2.3 x 10-7 pCi/g Vegetation a 1.1 x 10 -7 pCi/g ash 8 3.6 x 10 -7 pCi/g ash

-10 pCi/mt Water a 2.3 x 10 8 6.3 x 10-10 uCi/mL Air a 6.1 x 10-15 pCi/mt

]

6 1.2 x 10-14 pCi/mL 1

j 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 c'orrection 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 of Waste Discharge with the California Regional Water Quality Control Board, and ESG-80-7 i 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 engine 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 and for radioac-tivity by a California State certified analytical testing laboratory. The specific l constituents analyzed for, and their respective limitations in discharged waste-water, are presented in Appendix B. Wastewater originating from facilities located throughout the SSFL site is composited in the retention pond. The point of origin of nonradioactive constituents normally found in wastewater is impossible to deter-mine; however, in the event of excessive amounts of any of these materials in wastewater, the origin may be determined from the knowledge of facility oper-ations involving their use. A total of twelve off-site discharges of wastewater from Pond R-2A occurred durinq 1979.

1 1

ESG-G0-7 39

TABLE 10 ATM0 SPHERICALLY DISCHARGED EFFLUENT RELEASED TO UNRESTRICTED AREAS - 1979 Approximate ** "9 * *  % of Approximate " *"*

Annual Maximum Radio-Effluent Activity Average 1 of i Samples Building Volume Monitored c on Concentration Guide with Activity j Con on Re s (ft3) (pCi/mt) (pCi/mt) '"

(LCi/mt) (Ci) 001 2.5 x 10 10 a 1.7 x 10-16 <2.9 x 10-I4 2.8 x 10-13 <2.1 x 10-5 <0.99 41.7 8 5.a x 10-16 <8.1 x 10-15 5.8 x 10-I4 <5.8 x 10-6 <0.003 45.8

-15 004 3.3 x 10 10 a 3.5 x 10-16 <1.2 x 10 5.2 x 10-15 <1.1 x 10-6 <0.04 41.3 0 <6.1 x 10-15 1.3 x 10-13 <5.7 x 10-6 <0.002 49.3 10.7 x 10-16

$ 020 1.5 x 10 10 a 0.9 x 10-16 <4.2 x 10-16 1.1 x 10-15 <1.8 x 10-7 <0.70 4.2 O SSFL 1.0 x 10 -I*- 4.0 x 10-13 4.4 x 10-5 0.34 B 2.9 x 10-16 0 021- 1.1 x 10 10 a 2.0 x 10 -16 <2.6 x 10-16 5.9 x 10 -16 <3.5 x 10-8 <0.45 75.0 022 0 <8.4 x 10-15 3.9 x 10-I4 <2.7 x 10-6 <0.03 8.3 SSFL 6.4 x 10-16 6.1 x 109

-I 055 a 2.8 x 10-16 <3.1 x 10-16 1.1 x 10 <5.3 x 10-8 <0.51 86.0 8 8.2 x 10-16 <1.2 x 10-15 9.2 x 10-15 <2.1 x 10-7 <0.04 50.0 Annual average ambient air Total <8.1 x 10-5 radioactivity concentration - 1979 -

a < 6.4 x 10-15 B < 2.0 x 10-14 tGuide: De Soto site, 3 x 1n-12 pCi/mt alpha, 3 x 10-10 pCi/mt beta,10 C SSFL site, 6 x 10-14 pCi/mt alpha. 3 x 10-11 pCi/mtbeta,3x10g20AppendixB. pCi/mi beta (055 only); 10 CFR 20 Appendix B, CAC-17, and DOE Manual Chapter 0524.

Note: All release points are at the Stack Exit

+ , .

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, and under State of California Radioactive Material License 0015-70. The specific facilities are identified as Buildings 001 and ON 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 or particulate activity from Building 020 and particulate activity from Building 055. The HEPA filters used for filtering gaseous effluents are 99.97% efficient for particles of 0.3-pm diameter. Parti-cle filtration efficiency increases for particles above and below this size.

The average concentration and total radioactivity in gaseous effluent re-leased to unrestricted areas is shown in Table 10. The effectiveness 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. The table shows that no significant quantities of radioactivity was released for 1979.

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 for radioactivity concentration. There is no continuous flow. Building 004 chemical wastes are released to a proportional sampler installation which retains an aliquot each ESG-80-7 41

TABLE 11 LIQUID EFFLUENT DISCHARGED TO SANITARY SEWER - 1979 Sample Approximate . Annual Total Approximate N*I*"" Radioactivity Building Point of Effluent Activity "L

Average  % of t Release Volume Monitored Concentrat, ion Concentration Released Guide (pCi/mt) (pCi/mti (gal) (pCi/mt) (Ci)

-5 Retention a 1.2 x 10

-9 1.5 x 10 -7 1.2 x 10-6 3.0 x 10 0.02 001 54,000

-9 Ci Tank 8 3.7 x 10 1.1 x 10 -7 6.5 x 10-7 2.2 x 10-5 0.01 o

1.2 x 10 -9 5

gh Propor-1*641*000 a <1.1 x 10-8 7.0 x 10-8 <6.9 x 10-5 <0.001 a

004 tional 5 Sampler B 3.7 x 10-9 <3.1 x 10-8 1.4 x 10- <1.9 x 10-4 <0.003 020* -

0 - - - - -

021 - 022* -

0 - - - - -

055* -

0 - - - - -

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

tGuide: 8 x 10-4 pC1/mE alpha',1 x 10-3 pCi/ hit beta; 10 CFR 20 Appendix B, CAC-17 5% of samples <MDI.: 56.9% alpha activity, 11.8% beta activity

time a fixed volume is released to the sanitary sewage system. No radioactive liquid effluents are released from the Santa Susana Buildings 020, 021, 022, or 055. Liquid rddioactive waste generated at SSFL is solidified for land burial.

The average concentration and total radioactivity in 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 el ements. 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 U

234 ,U 235 ,U 236 , and U 238 ,

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.

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

,U 235 ,U 236 , and U 234 38 facility contains the uranium isotopes U . Major quan-tities of other radionuclides in encapsulated form include Co 60 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 con-

~

tinued on the basis of a monthly analysis of a daily composited sample of total facility effluent collected at the point of discharge into the municipal sewerage until the first calendar quarter of 1979 when it was terminated in accordance with the NRC license.

ESG-80-7

( 43 l l

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 137 , Sr 90

, Kr85, and PmI47 as mixed fission products.

fuel materials; and Cs

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 ,U 235 encapsulated or unencapsulated form contains the uranium isotopes U ,

U 236 ,U 2?8

, plus Cs 137 , Sr90, and Pm 147 as mixed fission products.

c. Builairg 055 - NRC and California State Licensed Activities Operations at Building 055 which may generate radioactive effluents consist of fabrication of depleted uranium carbide fuel pellets. 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 ,U 235 ,U 236 ,U 238 , Pu238, Pu239 contain the following radionuclides: U , ,

240 , Pu241, and Am241 Pu ,

t ESG-80-7 44 l

C. ESTIMATION OF GENERAL POPULATION DOSE Release of airborne material at the De Soto site for suaner 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 sumer 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 i 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.

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 1

ESG-80-7

. 45

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. Fo population distribution at distances >5 miles out to 50 miles, a single distribution centered on 34 14'25" north and 118 39'00" wcit is used.

This location i<, 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 1979 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 00WhWIND CONCENTRATION OF GASE0US EFFLUENTS - 1979 3

0 Meters to Type B Stability (cy) Type B 5tability(c,) v Downwind (utt/cm ')

Fact)Ity IU#II Boundary Rasidecce Bounda ry Residence 80 km Bounda ry Residence 80 km* Bounda ry Residence 80 km 6

8/001 8.4 m 10-I3 110 W 171 SW 18 27 6800 12 la 10 5.6 a 10-16 2.5 a 10-16 1.8 m 10-23 6

8/070 1.4 a 10-12 305 W 1900 SE 50 290 6800 33 350 10 1.2 x 10-16 2.0 m 10-18 3.0 a 10-23 6

8/022 8.8 a 10*I* 350 m 2300 SE 55 310 6800 38 500 10 6.1 x 10-18 8.2 m 10-20 1.9 x 10-24 B/055 8.4 a 10-15 400 m 1830 SE 68 260 6900 44 320 10 6

4.1 a 10 M 1.5 m 10-20 1.8 a 10-25 As ~= aea in . co t di e o full year The general population man-rem dose estimates calculated from demography data and the concentrations calculated for atmospherically discharged effluent 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-l trations than those calculated. -

l l The off-site doses are extremely low compared to the maximum permissible i

! exposures recomended for the general population. These values are 3 rem / year .

for bone, and 1.5 rem / year for the lung for an individual, and are one-third of ESG-80-7 46

I l

! TABLE 14 POPULATION DOSE ESTIMATES FOR ATMOSPHERIC DISCHARGED EFFLUENTS Dose to Receptor Population Segment - Man-rem 0-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total l N-NNE 2.6E-4 1.3E-7 2.5E-6 4.4E-8 2.4E-8 9.8E-9 2.6E-4 NNE-NE 3.4E-4 1.5E-7 1.8E-6 5.4E-8 1.6E-7 1.3E-7 3.4E-4 NE-ENE 1.6E-2 ~ 3E-5 1.2E-5 4.8E-8 6.8E-9 1.6E-8 1.6E-2 ENE-E 1.5E-2 6.1E-5 2.3E-5 3.5E-6 9.0E-7 2.7E-7 1.5E-2 E-ESE 3.1E-2 7.0E-5 3.7E-5 1.8E-5 6.3E-6 2.0E-6 3.1E-2 ESE-SE 3.6E-2 3.5E-5 2.8E-5 2.3E-E 7.9E-6 2.2E-6 3.6E-2 SE-SSE 3.2E-2 1.9E-5 1.0E-5 2.6E-6 2.1E-6 1.4E-7 3.2E-2 SSE-S 3.1E-2 2.2E-6 6.0E-7 0 1.6E-9 0 3.1E-2 S-SSW 4.2E-5 1.6E-6 2.5t-7 0 0 0 4.4E-5 SSW-SW 1.3E-4 2.3E-6 6.7E-7 0 0 0 1.3E-4  ;

SW-WSW 9.8E-5 8.5E-7 3.5E-6 1.6E-7 5.6E-8 0 1.0E-4 WSW-W 8.2E-4 1.6E-6 1.8E-6 1.5E-6 9.5E-7 1.3E-9 8.2E-4 NW-WNW 4.9E-3 2.8E-5 6.8E-7 4.9E-7 1.8E-7 3.7E-9 4.9E-3 WNW-NW 1.3E-2 2.6E-6 7.8E-7 3.3E-9 1.3E-9 3.1E-10 1.3E-2 NW-NNW 5.0E ' 6.2E-8 4.6E-8 1.6E-9 4.0E-10 4.7E-9 5.0E-3 NNW-N 2.6E-( 3.0E-8 2.4E-7 7.0E-9 2.3E-9 9.4E-11 2.6E-4 I

1.9E-1 2.6E-4 1.2E-4 4.9E-5 1.9E-5 4.8E-6 1.9E-1 l

1. Average rem / man dose = 1.5E-8 rem for the 80 km segment average population.

2. Total 80 km man-rem dose estimate from naturaily occurring airborne radioactivity dose to the lung of 40.1 rem / year = 1,300,000 man-rem for the 80 km radius area population.

these values for the general population. From Table 14, it may be seen that the highest total segment dose is for the 0-8 km segment equivalent to an average dose / man-year of 0.0008 mrem equivalent to 0.00005% of the maximum permissible exposure for an individual and 0.00016% of the general population recommended average exposure. Estimated radiation doses due to atmospheric discharges 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 are s50 to 100 mrem per year.

ESG-80-7 47

l l

APPENDIX .A COMPARISON OF ENVIRONMENTAL RADIOACTIVY DATA FOR 1979 WITH PREVIOUS YEARS This section compares environmental monitoring results for the calendar year 1979 with previous annual data.

The data presented in Tables A-1 through A-5 sumuarize 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.

4 ESG-80-7 49

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TABLE A-1 .

S0IL RADI0 ACTIVITY DATA - 1957 THROUGH 1979 Off Site - Average On Sige-Average (10- pCi/g) (10-6 pCi/g) 1 Year -

1 Number Number

" 8 " 8 Samples Samples 1979 144 0.64 25 48 0.50 23 1978 144 0.63 24 48 0.51 24 1917 144 0.56 24 48 0.53 23 1976 144 0.56 25 48 0.56 24 1975 144 0.60 25 48 0.58 24 1974 144 0.60 25 48 0.54 24 1973 144 0.57 25 48 0.51 24 1972 144 0.56 25 48 0.57 24 1971 144 0.55 25 48 0.53 23 1970 144 0.47 27 48 0.48 25 1969 144 0.42 27 48 0.42 25 1968 144 0.47 26 48 0.48 26 1967 144 0.42 28 48 0.39 24 1966 144 0.41 29 48 0.44 25 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-80-7 50

TALLE A-2 VEGETATION RADI0 ACTIVITY DATA -- 1957 THROUGH 1979 On Site - Average Off-Sjte - Average (10-6 pCi/g ash) (10- pCi/g ash)

Year Number Number

" " 0 Samples Sanples 1979 144 <0.24 139 48 <0.23 134 1978 144 <0.24 166 48 <0.24 143 1977 6 144 <0.22 162 48 <0.21 142 1976 144 <0.19 170 48 <0.22 147 1975 144 <0.21 155 48 <d". 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 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 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-80-7 51

TABLE A-3 .

SSFL SITE DOMESTIC WATER RADI0 ACTIVITY DATA -

1957 THROUGH 1979 Number Av Av Year Samples (10grageaUCi/mt)(10 grage gpCi/mt) 1979 24 <0.23 2.8 1978 24 (0.26 3.0 1977 24 <0.25 2.5 1976 24 <0.25 2.0 1975 24 <0.24 2.3 1974 24 <0.24 2.7 1973 24 <0.26 3.4 1972 24 0.22 3.7 1971 24 0.28 4.9 1970 24 0.18 5.3 1969 24 0.11 5.0 1968 24 0.16 5.0 1967 24 0.13 6.1 1966 24 0.13 4.6 1965 24 0.22 6.0 1964 23 0.18 5.3 1963 24 0.18 7.0 1962 24 0.21 12.0 1961 24 0.08 2.9 1960 22 0.08 1.9 1959 18 0.08 1.6 _

1958 13 0.16 4.7

(

1957 17 13.0 ,

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ESG-80-7 l

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TABLE A-4 BELL CREEK AND ROCKETDYNE DIVISION RETENTION POND RADI0 ACTIVITY DATA - 1966 THROUGH 1979 Sanples Bell Creek Vegetation Bell Cmk Water Interim Retention Final R e a Pond Bell C ek Mud 6 12 Average Average Average Average Average (10~9 pC1/mt) No (1b~0 pCi/9) "

(10-6 pCi/g ash) *j,3 (10~9 pCi/mt) (10 2C1/m2)

Year.33,pj,3 Sa les 3 5 5es 3,np ,,

a 8 a S a 8 a 8 a 8 1979 12 0.46 23. 12 <0.26 136. 12 <0.23 3.2 12 <0.25 3.1 12 <0.23 4.5 1978 12 0.42 23. 12 <0.26 156. 12 <0.24 2.5 12 <0.25 4.3 12 <0.25 4.6 m

$ 1977 4.2 0.29 22. 12 <0.19 155. 12 <0.24 1.8 12 <0.24 4.3 12 <0.25 5.2 ci.b 1976 H 0.38 23. 12 <0.17 164. 12 <0.25 2.2 12 <0.24 4.3 12 <0.28 4.4 w o 4.2 4.5 1975 '2 0.29 22. 12 <0.19 123. 12 <0.22 2.4 12 <0.24 12 <0.31 4 4.2 4.5 1974 12 0.32 22. 12 <0.16 142. 12 <0.21 2.5 12 <0.22 12 <0.21 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 1069 12 0.35 27. 12 0.28 166. 12 0.04 4.0 12 0.07 5.9 11 0.10 5.7 1%8 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 1%6 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 -

1957 THROUGH 1979 ,

0 SSFL Site Average DeSoto p2ite Average (10 pCi/mt)

( 10- uCi/mt) .

Year Number Number

" O " 0 Samples Samples 1979 697 <0.0066 <0. 0,21 2519 <0.0065 <0.020 1978 713 <0.0084 <0.091 2402 <0.0072 <0.088 1977 729 <0.0066 <0.17 2438 <0.0066 <0.17 1976 719 <0.0067 <0.096 2520 <0.0065 <0.11 1975 709 <0.0063 <0.076 2450 <0.0060 <0.073 1974 663 <0.0056 <0.16 2477 <0.0057 <0.16 1973 715 <0.0075 <0.041 2311 <0.0072 <0.038 1972 708 0.0085 0.14 2430 0.0086 0.14 1971* 730 0.0087 0.30 2476 0.0086 0.33 1970 668 --

0.34 2434 --

0.36 1969 687 -

0.27 2364 --

. 0.26 1968 650 -

0.32 2157 -

0.32 1967 712 --

0.39 2400 -

0.41 1966 706 --

0.18 2205 --

0.17 l 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 l not reported separately prior to 1971 l

tInsufficient data '

l 5 Includes Rocketdyne Site Air Sampler Data ESG-80-7 54

APPENDIX B CAllFORNI A REGIONAL WATER QUALITY CONTROL BOARD CRITERI A FOR

- 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.

TABLE B-1 NPDES NO. CA00-01309, EFFECTIVE SEPTEMBER 27, 1976 Discharge Rate Concentration Limit (1b/ day) (mg/t)

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

950 Chloride 200,160 -

150 Sulfate 400,320 -

300 Suspended Solids

• 66,720 50 150 Settleable Solids * -

0.1 0.3 B0D 200C 26,690 20 60 Oil and Grease 13,350 10 15 Chromium 6.67 0.005 0.01 Fluoride 1,340 -

1.0 Boron 1,340 -

1.0 Residual Chlorine - -

0.1 Fecal Coliform (MPN/100 mt) - - 23.0 Surfactants (as MBAS) 667 -

0.5 pH 6.0-9.0

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

O ESG-80-7 55

APPENDIX C REFERENCES

, 1. DOE Manual Chapter 0513

2. DOE Manual Chapter 0524, Appendix

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

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

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

6. Meteorology and Atomic Energy - 1968, TID 24190

7. Report of Committee II on Permissible Dose for Internal Radiation (1959),

ICRP Publication 2

8. Deposition and Retention Models for Internal Dosimetry of the Human Respiratory Tract, ICRP Committee II Task Group on Lung Dynamics

9. Document TI #N001TI000-046 titled " Method of Estimating General Population Radiation Dose Attributable to Atmospheric Discharge of Radioactivity from ESG Nuclear Facilities," J. D. Moore 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. Resources Management Agency, County of Ventura, California

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

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

6. Gordon Facer, Division of Military Applications, DOE

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

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

9. D0E-Headquarters Library, Attention: Charles Sherman I

ESG-80-7 l

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