Text

Rocketdyne Div Environ Monitoring & Facility Effluent Annual Rept for 1988
	ML20236E510
Person / Time
Site:	07000025
Issue date:	05/31/1989
From:	Tuttle R; ROCKWELL INTERNATIONAL CORP.
To:	;
Shared Package
ML19311A788	List: ML19311A787; ML19311A789; ML20236E479; ML20236E482; ML20236E487; ML20236E492; ML20236E495; ML20236E498; ML20236E502; ML20236E505; ML20236E510;
References
	RI-RD89-139, NUDOCS 8906050301
	Download: ML20236E510 (83)
	v • d • e

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Rl/RD89-139 APPENDIX B TO RI/RD 39 339 ESG-82 33 ROCKETDYNE DIVISION ENVIRONMENTAL MONITORING AND FACILITY EFFLUENT ANNUAL REPORT DE SOTO AND SANTA SUSANA FIELD LABORATORIES SITES 1988 I

., o RockwellInternational Rocketdyne Division ADOt'ofoook,5 PR PDC

l l

Rl/RD89-139

)

i ROCKETDYNE DIVISION ENVIRONMENTAL MONITORING l

AND FACILITY EFFLUENT ANNUAL REPORT DE SOTO AND SANTA SUSANA FIELD LABORATORIES SITES.,

i 1988 By J. D. Moore

'.l APPROVED:

b R.J.iTUTTLE Manager Radiation and Nuclear Safety RockwellInternational Rocketdyne Diviolon ano a Pa k, Cal fo nia 91303 J

o ISSUED: May 1989

CONTENTS Page I.

Introduction......................................................

1 II. Sammary and Evaluation of Environmental Monitoring Results........

11 III.

Environmental Monitoring Results..................................

15 A.

Radioactive Materials--1988...................................

15 B.

Nonradioactive Materials -1988................................

30 IV.

Environmental Monitoring Program..................................

33 A.

Description...................................................

33 B.

Sampling and Sample Preparation...............................

43 1.

So11.....................................................

43 2.

Hater.....................................................

41 3.

Ambient Air....................

44 C.

Counting and Calibration......................................

44 D.

Nonradioactive Materials......................................

46 V.

Ef fl uent Moni tori ng Program........................................

49 A.

Treatment and Handling................

49 B.

Facility Descriptions.........................................

51 1.

De Soto Site..............................................

51 2.

Santa Susana Fi eld Laboratori es Si te......................

51 3.

Canoga Site...............................................

52 C.

Estimation of General Population Dose Attributable to Rocketdyne Operations--1988...................................

52 Appendices A.

Comparison of Environmental Radioactivity Data for 1988 with Previous Years................................................

61 B.

Environmental Monitoring Program Quality Control..................

68 C.

California Regional Water Quality Control Board Criteria for Discharging Nonradioactive Constituents from Rocketdyne Division, SSFL.........................................

70 D.

Bibliography......................................................

71 E.

Ex t e rna l' Di s t ri buti on.............................................

73 F.

Alternative Units for Radiological Data...........................

75 G.

Additional Environmental Information..............................

76 RI/RD89-139 iii l.

TABLES Page 1.

Soil Radioactivity Data--1988.....................................

16 2.

Soil Plutonium Radioactivity Data--1988...........................

16 3.

Supply Water Radioactivity Data--1988.............................

18 4.

SSFL Site Retention Pond, Site Runoff, and Well Water Radioactivity Data--1988..........................................

20 5.

Ambient Air Radioactivity Data--1988..............................

25 6.

De Soto, SSFL, and Canoga Sites--Ambient Radiation Dosimetry Data--1988........................................................

28 7.

Nonradioactive Constituents in Wastewater Discharged to Uncontrolled Areas--1988..........................................

31 8.

Sampling Location Description.....................................

38 9.

Lowe r Li mi t s o f Det e c t i on.........................................

45 10.

Atmospheric Effluents to Uncontrolled Areas--1988.................

50 11.

Annual Averaged Plume Concentrations of Atmospheric Emissions--1988...................................................

57 12.

Estimated Dose to the Public in the Vicinity of Rocketdyne Facilities--1988..................................................

58 13.

Population Dose Estimates for Atmospheric Emissions from SSFL Facilities--1988.............................................

60 b

RI/RD88-139 iv

FIGURES Page 1.

Rocketdyne Division--De Soto Site..................................

3 e

2.

Rocketdyne Division--Santa Susana Field Laboratories Site.........

4 3.

Map of Santa Susana Field Laboratories Site facilities............

5 4.

Map of General Los Ang el es Area...................................

6 5.

Weekly, Monthly, and Annual Averaged Long-Lived Airborne Radio-activity at the De Soto and Santa Susana fic1d Laboratories Sites--1988.......................................................

27 6.

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

34 7.

Map of De Soto Complex and Vicinity Sampling Stations.............

35 8.

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

36 9.

Map of Canoga Site TLD Locations..................................

37 10.

Santa Susana Field Laboratories Site-Centered Demography to 8 km..............................................................

54 11.

Santa Susana Field Laboratories Site-Centered Demography to 16 km.............................................................

55 12.

Santa Susana Field Laboratories Site-Centered Demography to 56 80 km............

O RI/RD88-139 v

I.

INTRODUCTION Environmental and facility effluent radioactivity monitoring at the Rocketdyne Division of Rockwell International is performed by the Radiation and Nuclear Safety Group of the Health, Safety, and Environment Department.

Soil and surface water are routinely sampled to a distance of 16 km from divi-sion sites. Groundwater from Santa Susana Field Laboratories (SSFL) supply water wells and other test wells is periodically sampled to measure radio-activity. Continuous ambient air sampling and direct radiation monitc-by thermoluminescent dosimetry are performed at several on-site and off-site locations for measuring airborne radioactivity concentrations and site ambient radiation levels.

Radioactivity in effluents discharged to the atmosphere from nuclear facilities is continually sampled and monitored to assure that These amounts released to uncontrolled areas are below appropriate limits.

procedures also help identify processes that may require additional engineer-In addition, ing safeguards to minimize radioactivity in such discharges.

selected nonradioactive chemical constituent concentrations in surface water discharged to uncontrolled areas are measured.

The environmental radioactivity reported herein is attributed to natural

~

sources and to residual fallout of radioactive material from past atmospheric testing of nuclear devices.

Work in nuclear energy research and development in what has become the In Rocketdyne Division of Rockwell International Corporation began in 1946.

addition to a broad spectrum of conventional programs in rocket propulsion, spa:e utilization, and national defense, Rocketdyne is working on the design, development, and testing of components and systems for central station nuclear power plants, the decladding of irradiated nuclear fuel, and the decontamina-tic and decommissioning of facilities.

Nuclear research programs licensed by the State of California are con-ducted at the De Soto site (Figure 1) in the Building 104 Applied Nuclear Technology laboratories and in the Gamma Irradiation Facility.

The De Soto RI/RD89-139 1

location is typical of the San.Fernando Valley floor at an altitude of 875 ft above sea-level. Nuclear research programs licensed by the State of California are conducted there in the Building 104 Applied Nuclear Research laboratories and in the Gamma Irradiation Facility (containing approximately 60 137 35 kCi of Co and 570 kCi of Cs).

The Santa Susana Field Laboratories (SSFL) site (Figure 2) occupies 2,668

~ acres located in the Simi Hills of Ventura County, approximately 30 miles northwest of downtown Los Angeles.

The SSFL site is situated on rugged ter-rain which typifies mountain areas of recent geological age.

A sandstone bed-rock unit called the upper cretaceous Chatsworth formation underlies this area. The site may be described as an irregular plateau sprinkled with out-croppings above the more level patches and with peripheral eroded ravines.

Elevations of the site vary from 1650 to 2250 ft above sea level.

The surface mantle consists of unconsolidated gravel, sand, silt, and clay.

Both Depart-ment of Energy (DOE) and Rockwell International owned facilities, shown in Figure 3, share the Area IV portion of this site. The SSFL site also contains facilities in which nuclear operations licensed by the U.S. Nuclear Regulatory Commission and the State are conducted.

The licensed facilities include (1) the Rockwell International Hot Laboratory (RIHL) (Building 020). (2) sev-eral X-ray and radioisotope industrial radiography inspection facilities, and (3) a radiation instrument calibration laboratory.

The DOE facility is the Radioactive Material Disposal Facility which receives, processes, and packages radioactive wastes for disposal at authorized DOE disposal cites.

At the Canoga site, the predominate use of radiation is in industrial radiography for quality control inspection of rocket engine components. Other uses involve research and development.

The location of these sites in relation to nearby communities is shown in Figure 4.

Surrounding the De Soto complex is light industry, other commercial establishments, apartment buildings, and single-family houses.

Bare land sur-rounds most of the SSFL site, with occasional cattle grazing on the southern portion and some orchard farming at the eastern boundary.

No significant RI/RD89-139 2

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1 agricultural land.use exists within 30 km of the SSFL site. With the excep-tion of the Pacific Ocean about 20 km south, no recreational body of water of noteworthy' size is located in the surrounding area. Four major reservoirs providing domestic water to the Los Angeles area,are located within 50 km of SSFL. However, the closest is more.than 16 km away. -Hithin the SSFL site is an 82-acre government-optioned area where Depart-ment of Energy (DOE) contract acti.vities are conducted. Most of the work is performed by the nonnuclear Energy Technology Engineering Center (ETEC). The major operational nuclear installation within the DOE-optioned area is the Radioactive Material Disposal Facility (RMDF). This facility is used for ~ torage of irradiated fuel and for packaging radioactive wastes resulting from s decommissioning and fuel decladding operations. Radioactive water is evapo-rated and the sludge is dried and disposed as packaged dry waste together with other dry wastes at a DOE disposal site. Licensed programs conducted during 1988 were limited to maintenance and decontamination of the RIHL which was used for nuclear reactor fuel decladding and reactor syste:n component examination. The basic policy.for the control of radiological and chemical hazards l requires that adequate containment of such materials be provided through engineering controls and that facility effluent releases and' external radia-l tion levels be reduced to a minimum through rigid operational controls. The environmental monitoring program implements some safety procedural effective-ness and monitors the engineering safeguards incorporated into facility de-signs. Except for plutonium, specific radionuclides in environmental samples are not routinely identified because of the extremely low radioactivity levels normally' detected. Gross alpha and beta radiation analyses are performed on all other environmental samples. Based upon comparison with current analyti-cal results and the historical data, any significant increase in radioactivity levels would be easily detected. This is assured by attention to the maximum Value. measured for each sample. type throughout the year. Identification of noticeably elevated radioactivity would lead to further analyses and RI/RD89-139 7

investigation. Relatively few different radionuclides are involved in opera-tions conducted on site. Facility eff1 cent sample filters for 1988 were com-posited for specific radiochemistry analysis. Occasional gamma-spectral analyses of bulk samples such as soil, water, and ambient air sample collection filters confirm that the major radionuclides present are normally those of the naturally occurring thorium and uranium 40 decay chains, plus other natural radionuclides such as the primordial g, 7 and Be produced by cosmic ray interactions in the atmosphere. In addition to environmental monitoring, work area air and atmospheric effluents are continuously monitored or sampled, as appropriate. This directly measures the effectiveness of engineering controls and allows reme-dial action to be taken before a significant release of hazardous material can occur. Environmental sampling stations located within the De Soto and SSFL Area IV boundaries are referred to as "on-site" stations; those located out-side these boundaries, or relatively distant from any nuclear facilities, are referred to as "off-site" stations. The De Soto and SSFL locations are sam-pled quarterly to determine the concentration of radioactivity in typical sur-face soil. Soil is also sampled on-site (SSFL) and off-site semiannually for plutonium analysis. Similar off-site environmental samples, except for pluto-nium analysis, are also obtained quarterly. Water samples are obtained monthly at both De Soto and SSFL from supply water sources, retention ponds, and also from deep and shallow wells on a seasonal frequency. Continuous ambient air sampling provides information concerning long-lived airborne par-ticulate radioactivity. On-site ambient radiation monitoring using thermolu-minescent dosimetry (TLD) measures environmental radiation levels at the Canoga, De Soto, and SSFL sites and also at several off-site locations. Nonradioactive wastes discharged to uncontrolled areas are limited to liquids released to sanitary sewage systems and to surface water drainage sys- -l tems. No intentional releases of any liquid pollutants are made to uncon-trolled areas. Sanitary sewage from all facilities at the SSFL site is RI/RD89-139 8

l treated at on-site sewage plants. The outfall from the plant for Area IV flows into retention pond R-2A, located toward the southern boundary of the SSFL site. The surface water drainage system of SSFL, which is composed of catch ponds and open drainage ditches, also drains to retention pond R-2A. Hater from the pond may be reclaimed as industrial process water or released, s as necessary, off-site into Bell Creek, a tributary of the Los Angeles River. The pond water is sampled monthly for radioactivity. It is also sampled at discharge for both radioactive and nonradic4 active pollutants as required by the discharge permit (NPDES CA0001309) issued to Rocketdyne Division by the California Regional Water Quality Control Board. In addition, an automatic water sampler takes samples from the discharge stream channel (Bell Creek) whenever water is present. Section II of this report summarizes and discusses monitoring and sam-pling methods and describes possible sources of radioactivity. Results of environmental monitoring for 1988 are presented and evaluated in Section III. Part A deals with radioactive materials and reports gross alpha and beta radi-oactivity and also plutonium isotopes in soil. Tha maximum value determined for each type or analysis is reported in the tables and shows no significant elevation over the averaged values. Measurements of radionuclides components' in atmospheric emissions provide the basis for oose commitment calculations. Part B discusses results of monitoring nonradioactive materials. The sampling and analytical methods used in the environmental monitoring program for radio-active materials are described in Section IV. Treatment and handling of effluents is described in Section V. This section also provides facility descriptions and estimates the general population dose attributable to Rocket-dyne operations. A comparison of 1988 radioactivity results with the results from previous years appears in Appendix A. Appendix B provides a summary of the Environmental Monitoring Program Quality Control. Appendix C shows regu-latory limits on nonradioactive pollutants in water released from the site. References are listed in Appendix 0. The external distribution of this report comprises Appendix E, and a table of alternative units for radiological data ~ is shown in Appendix F. Additional environmental information of concern to DOE is presented in Appendix G. 0256Y/sjv RI/RD89-139 9

3 II.

SUMMARY

AND EVALUATION OF ENVIRONMENTAL MONITORING RESULTS Except as noted below, all radioactivity levels observed in environmental samples for 1988 are close to radioactivity levels measured during recent years and listed in the previous issues of this report. Local environmental radioactivity levels have decreased and been generally constant during the past several years. These levels are produced by natural and man-made radio-nuclides. They have revealed the presence of falleut from past atmospheric testing of nuclear devices and from the Chernobyl reactor accident. Present levels are due mainly to primordial natural radionuclides. The results of this environmental monitoring indicate that there are no significant sources of unnatural radioactive material in the vicinity of the Rocketdyne sites. Additionally, identical results obtained from on-site and off-site samples provide supporting evidence that nuclear operations at Rock-etdyne have not contributed to general environmental radioactivity. The atmospheric discharge of radioactive materials provides the only potentially significant exposure pathways to the general public resulting from Rocketdyne nuclear operations. The only exposure pathways to people are via whole body external exposure, inhalation exposure to released materials, and direct radiation exposure. All liquid radioactive wastes are processed for disposu' at DOE disposal sites. Liquid radioactive wastes are not released into the environment and do not constitute an exposure pathway. The maximum individual annual exposures estimated for persons at the site boundary and also at the residence nearest the SSFL site are small when com-pared with natural radiation and with all applicable guidelines. Inhalation exposure estimates were derived from AIRDOS-EPA calculated concentrations at the boundary and the nearest residence and the dose conversion factors approp-riate for radionuclides identified in the effluent from each nuclear facil-ity. Dose conversion factors for all atmospheric effluents were taken from DOE /EH-0071, " Internal Dose Conversion Factors for Calculation of Dose to the Public." This inhalation exposure estimate is the sum of contributions calcu-lated for the measured releases from each facility. Exposures by other modes l-of the airborne pathway are considered to be negligibly small compared to the RI/RD89-139 11 ____________l

inhalation mode. The external radiation exposure estimates at the naximum cxposed boundary location and at the nearest residence are based on results for site ambient radiation dosimeters and also for several facility workplace r'adiation dosimeters. The unshielded external annual exposure resulting from operations conducted at the RMDF is estimated to be about 40 mR at the nearest j boundary-line location and less than 0.1 mR for the nearest residence. The boundary-line exposure is conservative in that the rugged terrain at the site boundary nearest the RMDF precludes anything more than the rare and temporary presence of any person at that location. These values were determined by calculating the unattenuated exposure expected at the boundary and nearest l residence on the basis of the highest annual result for area dosimeters in place around the facility. For the nearest residence, radiation attenuation J by the air lowers direct radiation to practically nonexistent levels. In most cases. intervening irregular rock formations and hills completely shield off-site locations from the radiation sources. Only natural background radiation inherent to the residence location would be present. Boundary-line direct radiation exposu,res for the State of California and U.S. NRC-licensed opera-tions at other Rocketdyne nuclear facilities were well below 10 mR for the year. Similarly for the De Soto site, internal dose estimates at the boundary and at the nearest residence do rot differ significantly from zero. Esti-mates of the external radiation exposure at the De Soto boundary (less than j 0.01 0.01 mR) and at the nearest residence (less than 0.01 0.01 mR) are based on the difference between the single highest on-site TLD measurement and the average of off-site measurements. The difference is more likely the 1 result of random variability in the measurements than from actual radiation exposure. Supply water at the SSFL site is sampled monthly at two locations. This supply consists of water from deep wells site-blended with potable water from the Ventura County Water District 17. In addition, shallow groundwater is periodically sampled at a standpipe adjacent to the basement level of a de-activated reactor test facility (Building 059). These samples are evaluated RI/RD89-1,39 12

for any transfer of activation product radioactivity from the underground reactor test vault containment into the surrounding soil. None has been detected. Therefore, these analyses serve as a measure of radioactivity naturally present in the groundwater. Deep well water samples are also evaluated to determine any impact of Rocketdyne Division nuclear operations on the deep groundwater system underlying SSFL. Quality assurance measures incorporated into the environmental monitoring program include participation in DOE-sponsored programs such as the Environ-mental Dosimeter Intercomparison Program and the DOE Environmental Measure-ments Laboratory Quality Assessment Program (EML-QAP). In 1988, Environmental Monitoring participated in two EHL-QAP sample analysis sets (QAP XXVIII and XXIX). Analysis of the QAP results indicates that accuracy in measuring radioactivity in the sample media provided for the intercomparison has improved. In addition to participation in these programs, laboratory analyses of split and 1' sicate samples are routinely evaluated for the reproducibility of sample radioactivity measurements of water and soil gross radioactivity. Control charts of counting system radiation response are maintained. These data are periodically evaluated to determine the correlation between sample i sets and trends in background. RI/RD89-139 13

= u III. ENVIRONMENTAL HONITORING RESULTS r i-A. RADI0 ACTIVE MATERIALS--1988 The average' radioactivity concentrations in local soil, surface and groundwater, and in ambient air for 1988 are presented in Tables 1 through 6. The presentation of data' in the tables includes the annually averaged data. for' each sample type and the maximum radioactivity level detected for a single sample.from the annual set. The single sample is reported because of its significance in indicating the occurrence of a major episode or an area-wide incident of radioactive material deposition. Except :for soil, sup-ply water, and air samples, none of the maximum observed values, which gener-ally occurred randomly during the year, show a great increase over the annually averaged values beyond inherent variability. (Refer to Tables 1 through 6.) The ambient air sampling data show no greatly increasing or -decreasing trends for the year and can be described as generally constant, with some increase in airborne radioactivity occurring through the third and fourth quarters. The results of the gross radioactivity measurements in soil (Table 1) show no significant difference between on-site and off-site samples. To achieve much higher detection sensitivity for plutonium than gross alpha measurements can provide, soil samples are collected and sent to an independent testing laboratory for specific plutonium analysis. This analysis is ' performed by leaching individual soil samples with acid, then treating the leachate chemically to separate and concentrate any plutonium present. In this way, minute quantities of plutonium, such as those distributed globally _by testing of nuclear weapons, can be detected and quantitatively measured by alpha spectroscopy. The results are shown in Table 2. Alpha spectroscopy 239Pu + 240Pu, predominantly from weapons tests. . permits identification of and= 238Pu, partly from the destructive reentry of a Transit satellite over the Indian Ocean in April 1964. RI/RD89-139 15 i i

TABLE 1 SOIL RADIOACTIVITY DATA--1988 L Gross Radioactivity l I (pCi/g) l Number Maximum Observed of Annual Average Value Value* and Area Activity Samples and Dispersion Month Observed On-site Alpha 48 29.1 6.2 53.6 (quarterly) (October) Beta 48 26.0 2 2.8 31.4 (October) Off-site Alpha 48 25.6 2 6.2 39.6 (quarterly) (October) Beta 48 24.4 2.7 29.6 (April) Pond R-2A Alpha 4 28.7 2 3.6 33.6 mud No. 55 (January) Beta 4 24.7 0.8 25.4 (January) Bell Creek Alpha 4 22.0 7.5 33.2 upper stream (October) bed soil Be tt, 4 23.9 1.5 25.1 No. 62 (December)

Maximum value observed for single sample.

TABLE 2 S0IL PLUT0NIUM RADIOACTIVITY DATA--1988 29 June 1988 Survey Results 1 December 1988 Survey Results 238 239Pu + 240Pu Pu 238 239Pu + 240Pu Sample Pu Location (pCi/g) (pCi/g) (pCi/g) (pCi/g) S-56 0.0004 0.0002 0.0008 0.0002 0 0.0001 0.0012 0.0002 S-57 0 0.0001 0.0039 0.0005 0 0.0001 0.0032 0.0005 S-58 0.0004 0.0001 0.0022 1 0.0003 0 0.0001 0.0033 1 0.0004 S-59 0.0001 0.0001 0.0031 0.0004 0.0002 0.0001 0.0069 0.0008 S-60 0.0001 0.0001 0.0029 0.0004 0 0.0001 0.0032 0.0004 S-61* 0.0004 0.0002 0.0003 0.0002 0 0.0001 0.0001 0.0001

0ff-site location RI/RD89-139 16

For comparison with these results, published data from soil tests in nearby Burbank, California in 1970-71 show a plutonium concentration of. 239 240 approximately 0.002 pCi/g for Pu + Pu and approximately 238 0.00006 pCi /g - for Pu. ~ The data in Table 2 show no significant increases ~in on-site soil plutonium relative to the Burbank values and no significant variation in soil plutonium concentrations for the 1988 sample sets. The detected gross radioactivity in soil is due to various naturally occurring radionuclides present in the environment, to radioactive fallout of dispersed nuclear weapons materials, and fission product radioactivity pro-duced by past ' atmospheric tests of nuclear weapons. No atmospheric nuclear weapons tests were announced during 1988. Naturally occurring radionuclides include Be, 40g, 87Rb, Sm, and the uranium and thorium series (in-7 I47 cluding radon and daughters). The radionuclides composition of local area 40 surface soil has been. determined to be predominantly K, natural thorium, and natural uranium, both in secular equilibrium with daughter nuclides, with 137 less than 11 fission-produced radionuclides, principally Cs and Sr. -Radioactivity in aged fallout consists primarily of the fission produced -90Sr 90y, Cs, and Pm, and also U and Pu. Gamma spec-137 I47 239 trometric analysis of composited ambient air sr.mples collected during 1988 7 detected the cosmogenic radionuclides Be, plus additional natural radio- ~ nuclides of terrestrial origin, the natural uranium and thorium series, and 40 40 K. Relative amounts of these radionuclides were approximately 73% g, 7 25% Be, and the remainder due to the natural uranium series and natural 7 therium series. The value for Be is representative for the mixture only. at the time of measurement since the physical half-life is extremely short com-pared with those of the other radionuclides detected. Supply water is sampled monthly at De Soto and at two widely separated i SSFL site locations / The average supply water radioactivity concentration for each site is presented.in Table 3. Supply water used at De Soto is supplied by the Los Angeles Department of Hater and Power. Supply water used at the j h. SSFL site is obtained partly from the Ventura County Hater District No.17, 1 which also supplies nearby communities, and from local well water. Two l i RI/RD89-139 17 J

TABLE'3 . SUPPLY HATER RADI0 ACTIVITY DATA--1988 Gross Radioactivity (10 '> pCi/mi) Number Maximuin Value* of Average'Value and Month Area Activity Samples and Dispersion Observed De'Soto Alpha 12 3.80 i 1.42 6.57 (monthly) (April) Beta 12 4.10 0.43 5.16 (March) SSFL Alpha 24 5.40 1 3.34 13.81 (monthly) (June) Beta 24 3.93 0.84 5.80 (June)

Maximum value observed for single sample, on-site water ' wells (wells 5 and 13) were operated during FY 1988 to reduce the consumption of the Ventura County water.

The well water proportion in the blend averaged about 67% for the year, for a total well water consumption of about.2.7 x 105,3 (7.1 x 107 gal). A shallow standpipe, connected to a French drain at foundation level, is being used for sampling of groundwater adjacent to the underground reactor-test vault. (This standpipe was installed during a construction modification to.a currently deactivated Space Nuclear Auxiliary Power, SNAP, reactor test facility.) Hater in the standpipe is periodically sampled for the purpose of oetecting any transfer of activation product radioactivity from the contain-ment to the outside environment. Radioactivity in seven samples taken during 1988 averaged 1.2 x 10-8 Ci/mi' beta with no alpha activity detected. 60 Gamma spectrometric analysis, with a minimum detection limit for Co of about 5 x 10-7 pCi/ml, has not identified any specific unnatural radio-nuclides in the water; thus, the observed activity is attributed to dissolved radioelement of natural origin in the soil bed. 18

l A recent hydrogeologic study at SSFL describes two groundwater systems at the site: a shallow,. unconfined system in the alluvial surface mantle' of the . Burro Flats area and along the major drainage channels, and a deeper ground-water system in the fractured Chatsworth sandstone. Alluvium along the major surface. drainage systems may store and transmit groundwater to the underlying Chatsworth fermation through fractures. Hater levels in the alluvium respond -to recharge resulting from surface flows and may vary considerably between wet and dry periods. The alluvium, composed of a heterogeneous mixture of gravel, sand, silt, and clay, has estimated hydraulic conductivities' rangi.ng from 0.1-2 to 1000 gal / day /ft, i The Chatsworth formation is composed of well-consolidated, massively bed-ded: sandstones with interbedded layers of siltstone and claystone. The layer may be as thick as 6,000 ft at the SSFL site. The direction of groundwater flow in the formation is probably radially off-site toward the surroundia lowlands and is probably controlled by fracture zones. The hydrogeologic environment at the SSFL site is a dynamic system. ~ Groundwater is' recharged at, the site, moves through the aquifers, and dis-- charges to the surface or to other aquifers down-gradient of the site. The groundwater system is recharged by precipitation and by unlined ponds and drainage channels. Because of the meager rainfall in the area and the. rela-tively.large. variability in annual precipitation, groundwater recharge may vary greatly from year to year. Specific pathways of possible contaminant transport are difficult to predict on the basis of on-site well data. The most likely pathways are along fracture zones that trend off-site. i As discussed earlier, surface waters discharged from SSFL facilities and. the sewage plant outfall drain southward into Rocketdyne retention pond R-2A. g When the pond is full, the water may be discharged into Bell Creek, a tribu-tary of the Los Angeles River in the San Fernando Valley, Los Angeles County. . Average radioactivity concentrations in retention pond R-2A, upper Bell Creek, and test well samples are presented in Table 4. s i RI/RD89-139 19 l 1 a

TABLE 4 SSFL SITE RETENTION PONO, SITE RUN0FF,. ID WELL WATER RADI0 ACTIVITY DATA 1988 (Sheet 1 of 4) Gross Radioacti ity Concentration f x 10 U pCi/ml) Percent of Samples Number Annual Average Maximum Valuea With of Value and Month Activ{ty Area Activity Samples and Dispersion Observed <LLD Pond No. 6 Alpha 12 2.04 1.03 4.48 100 (Monthly) (September) Beta 12 4.18 2 0.70 5.56 0 (October) Pond No. 12 Alpha 12 4.47 ! 2.11 8.47 92 (R-2A) (Monthly) (September) Beta 12 4.51 0.91 6.49 0 (September) Upper Bell Creek Alpha 8 3.67 2.36 8.92 75 No.17 (Seasonal) (December) Beta 8 4.31 0.85 5.59 0 (December) Well WS-4A Alpha 3 5.54 2.33 6.Bs 100 (Seasonal) (March) l Beta 3 4.35 0.12 4.48 0 (June) Well WS-5 Alpha 12 3.47 3.07 8.95 83 (Seasonal) (August) 4 l Beta 12 4.27 0.93 6.21 0 (August) Well WS-6 Alpha 3 6.78 1.48 7.83 50 (Seasonal) (March) ] Beta 3 5.02 0.56 5.63 0 (December) - 2 I .l Well WS-7 Alpha 2 9.16 3 6.84 14.00 50 (Seasonal) (June) -1 1 Beta 2 5.75 2 1.15 6.56 0 ,1 (June) ) 1 RI/RD89-139 j 20

TABLE 4 SSFL SITE RETENTION POND, SITE RUNOFF, AND WELL WATER RADIOACTIVITY DATA 1988 (Sheet 2 of 4) Gross Radioacti ity Concentration (x10-U pCi/ml) Percent of Sampl es Number Annual Average Maximum Valuea With of Value and Month Activgty Area Activity Samples and Dispersion Observed <LLO Well WS-8 Alpha 4 7.95 2.66 10.60 25 (Seasonal) (March) Beta 4 3.68 1.65 6.10 0 (December) Well WS-9 Alpha 3 9.67 1.56 10.82 0 (Seasonal) (June) Beta 3 4.60 0.22 4.76 0 (Deceter) Well WS-9A Alpha 1 4.40 4.40 100 (Seasonal) (December) Beta 1 3.37 3.37 0 (December) Well WS-il Alpha (Seasonal) Well ou'. of service Beta Well WS-12 Alpha 2 6.38 5.62 10.35 50 (Seasonal) (June) Beta 2 5.42 0.19 5.53 0 (June) Well WS-13 Alpha 12 4.62 L21 8.54 83 (Seasonal) (October) Beta 12 4.09 0.75 5.78 0 (June) y RI/RD89-139 21 "r

l i k l TABLE 4 -j k SSFL SITE RETENTION POND, SITE RUNOFF, AND WELL WATER RADIOACTIVITY DATA 1988 j (Sheet 3 of 4) Gross Radioacti itj Concentration (x 10 pCi/ml) Percent of j Sampl es Number Annual Average Maximum Valuea With of Value and Month Activ{ty Area Activity Samples and Dispersion Observed <LLD Well WS-14 Alpha 2 10.44 0.01 10.45 0 (Seasonal) (December) Beta 2 4.61 0.30 4.82 0 (December) Well 05-1 Alpha 3 5.50 3.23 7.77 33 (Seasonal) (March) j Beta 3 4.20 0.95 5.19 0 (September) Well 05-2 Alpha 3 6.40 2 2.29 9.01 66 (Seasonal) (December) Beta 3 2.96 1.23 4.23 0 (September) Well 0S-5 Alpha 3 7.53 7.39 15.11 66 (Seasonal) (September) Beta 3 4.20 0.41 4.46 0 (September) Well 05-8 Alpha 2 3.52 3.31 5.86 100 (Seasonal) (December) Beta 2 3.60 1.39 4.59 0 (December) Well 05-10 Alpha 1 4.87 4.87 100 (Seasonal) (Decunber) Beta 1 1,55 1.55 0 (December) 9 RI/RD89-139 22

TABLE 4 SSFL SITE RETENTION POND, SITE RUNOFF, AND WELL WATER RADIOACTIVITY DATA 1988 (Sheet 4 of 4) Gross Radioacti ity Concentration (x 10- pCi/ml) 4 Percent of Samples Number Annual Average Maximum Value" With of Value and Month Activity Area Activity Samples and Dispersion Observed <LL0b Well 05-13 Alpha (Seasonal) Dry well--no sample Beta Well 05-15 Alpha 1 11.87 11.87 100 (Seasonal) (December) Beta 1 6.63 6.63 0 (December) Well 05-16 Alpha 2 11.06 3 7.18 16.13 50 (Seasonal) (June) Beta 2 4.90 0.88 5.52 0 (March) Well R'-20 Alpha 1 2.29 2.29 100 (Seasonal) (December) Beta 1 0 50 0.50 100 (December) Well RS-21 Alpha l 14.60 14.60 0 (Seasonal) (March) Beta 1 1.75 1.75 0 (March) Well RS-22 Al pha 2 11.56 2 8.32 17.45 50 (Seasonal) (March) Beta 2 2.01 2 0.53 2.38 0 (September) aMaximum value observed for single sample, blower limit of detection: Approximately 0.4 x 10-9 pCi/mi alpha; 1.10 x 10-9 pCi/ml beta for water. W RI/RD89-139 23

l1 y Comparison of the radioactivity concentrations in water from the ponds with.that of. the supply water shows no significant-differences in either alpha ~ or beta activity. Similarly, comparisons between on-site and off-site soil samples and'those of upper Bell Creek stream bed show no significant 1-differences, l The' SSFL site. surface water and the ambient air radioactivity concentra-1 L tion guide values selected for each site are the most restrictive limits for L those radionuclides currently in use at Rocketdyne facilities and should not be taken to indicate the identification of these radionuclides in the sam-ples. ' Radioactivity concentration guide values are those concentration limits adopted by the Nuclear Regulatory Commission (NRC) and the State of California as maximum permissible concentration (HPC) values for uncontrolled areas. These values are established in 10 CFR 20 and California Administrative Code Title 17. These MPCs are consistent with the derived air concentration (DAC) and drinking water guidelines presented in draft DOE Order 5400.XX-(03/31/87). The MPC values are dependent on the radionuclides and its behavior as a soluble or an insoluble material. For comparison with results of environmental and effluent monitoring, the single lowest MPC valut for the various radionuclides present is selected rather than a derived MPC for the mixture. Accordingly, for SSFL site surface water, the guide values of 5 x 10-6 Ci/ml alpha ~ 239Pu and 3 x 10-7 pCi/ml beta activity corres-activity corresponding to 90 ponding to Sr are used. Ambient air sampling for long-lived particulate alpha and beta radioac-tivity is performed continuously by automatic sequential samplers located at De Soto and SSFL. Air is drawn through glass fiber filters, which are ana-1 lyzed for retained long-lived radioactivity after a minimum 120-h decay period that eliminates naturally occurring short-lived particulate radioactivity (most radon daughters). The average concentrations of ambient air alpha and beta radioactivity for 1988 are presented for the various sampler locations in Table 5. The guide va'lue of 6 x 10-I4 pCi/ml for SSFL site ambient air alpha activity is due to work with unencapsulated plutonium. The value of 3 x RI/RD89-139 24 ___.____.-___._____.m_________________.-____J

TABLE 5 AMBIENT AIR RA010 ACTIVITY OATA--1988 Gross Radioactivity Concegrations--Femtocuries per m3 (10-pCi/ml) Number Annual Average Maximum Valuea Percent Percent of value and Oate of Less Than Area Activity samples and Dispersion Observed Guideb LLO De soto Alpha 680 2.4 2.6 15.0 (04/03) 0.08 96 (2 locations) Beta 34.1 21.8 108.6 (10/24) 0.01 48 ssFL Area IV Alpha 1696 1.9 2.7 17.3 (08/10) 3.2 98 (5 locations) Beta 31.0 2 20.4 134.4 (01/04) 0.10 55 ssFL sewage Alpha 355 2.2 2.7 11.2 (09/07) 3.7 99 treatment plant Beta 31.5 ! 19.0 94.6 (12/14) 0.11 50 ssFL control Alpha 346 1.9 2 2.7 10.9 (09/07) 3.2 98 center Beta 31.1 19.3 99.8 (10/16) 0.10 56 All locations Alpha 3077 2.1 2.7 Beta 31.7 20.4 aMaximum value observed for single sample. bGuide De soto site:143 x 10-12 pCi/ml alpha 3 x 10-10 pCi/ml beta; 10 CFR 20 Appendix B, CAC 17. ssFL site: 6 x 10-pCi/ml alpha, 3 x 10-II pCi/ml beta; 10 CFR 20 Appendix B, CAC 17, 00E Order ~ 5480.1A. cLLD - 9.1 x 10-15 pCi/ml alpha; 3.8 x 10-14 pCi/ml beta. 90 10-II pCi/ml for beta activity is due to the presence of Sr in fission products in irradiated nuclear fuel at the SSFL site. The guide value of 3 x 10~ pCi/ml for De Soto ambient air alpha activity is due to prior work with unencapsulated depleted uranium. The guide value of 3 x 10-10 Ci/ml 60 is for Co, for which the ambient air beta activity guide is appropriate since it is the most restrictive limit for any beta-emitting radionuclides in use at De Soto. Guide value percentages are not presented for soil data, since none have been established. Figure 5 is a graph of the weekly averaged long-lived alpha and beta ambient air radioactivity concentrations for De Soto and SSFL during 1988. The daily data were mathematically smoothed in a moving weekly average of ~ daily data for the year. The average alpha and beta radioactivity concentra-tions for each month are indicated by horizontal bars. The graph shows an ? abrupt decrease in airborne radioactivity during March and April which is a l RI/RD89-139 25 L ......._i

l result of the movement of a series of intense rain storms into the Southern i California area. By the end of June, activity returned to previous levels and continued to be generally constant or slightly increasing during the remainder of 1988. The activity detected in ambient air is attributed to naturally i occurring radioactive materials and possibly to aged fission products from past atmospheric tests of nuclear devices. Radionuclides detected in air ~ 7 40 samples collected during 1988 include Be and K plus several naturally occurring radionuclides from the uranium and thorium series. While the data for air-borne alpha activity are nearly all below the minimum detection level for a single sample, averaging values from nine daily air samples over seven con-secutive days and over calendar months reveal the long-term behavior of this activity. Monitoring of ambient radiation is performed with TLDs. Each dosimeter set uses two calcium fluoride (CaF :Mn) low background, bulb-type chip dosi-2 meters. The dosimeter sets are placed at locations on or naar the perimeters of the De Soto, SSFL, and Canoga sites. Each dosimeter, sealed in a light-proof energy compensation shield, is installed in a sealed piastic container mounted about 1 m above ground at each location. The dosimeters are exchanged and evaluated quarterly. During the year, 27 on-site TLD monitoring locations were used. Five additional dosimeter sets, placed at locations up to 10 miles ~ from the sites, are similarly evaluated to determim the local area off-site ambient radiation level, which averaged 9 pR/h for 1988. Table 6 presents the quarterly and annual radiation exposures, the equivalent absolute and altitude-adjusted annual exposures, and exposure rates determined for each dosimeter location. During the third quarter of 1988, TLD exposure data was somewhat higher than expected for the on-site and off-site dosimeters. The higher results were noted for both off-site and on-site dosimeters. It was concluded that the values were affected by an intermittently malfunctioning shutter in the e RI/RD89-139 26

5 D 1 E B D D E 1 T V d AC A l I r D l N j V l O I \\ N o S Y l i AD l da N O l R D l T e C n E R l O r R o U 1 b C r C 1 it O A L i P E d L l S e A v F l iL N R I L I A 1 G n g A E R 1 1 U o A L / A L 1 d v l e AC g p O l a L r y L e l l U i v f l J v l A A A a T H l u E P n B L I N U n A I J A I d n 4 I a I YA y ,3 l M l V l h t A ~ n ( l o M l R I P y A l 1 k e L 1 e I W R I A I M 5 r I e Q I ur Y I g B i I E F F I 1 i I N A 1 A J ^ 2 3 4 -o 0 0 1 3 1 ,U 5e29 g l !fl

i TABLE 6 DE SOTO, SSFL, AND CANOGA SITES--AMBIENT RADIATION 00SIMETRY DATA--1988 Equivalent Quarterly Exposure Exposure at (mR) Annual 1000-ft ASL TLD Exposure Location Q-1 Q-2 Q-3 Q-4 (mR) (mR) (pR/h) De Soto DS-1 20 -23 27 20 90 91 10 DS-2 21 21 22 16 80 82 9 DS-3 20 23 27 ' 17 87 90 10 DS-4 .19 18 27 20 84 85 10 DS-5 20 15 20 15 70 71 8 DS-6 23 16 33 15 87 88 10 DS-7 23 1E 37 19 95 96 11 DS-8 19 10 31 15 75 78 9 Mean value 21 18 28 17 84 85 10 ~I5FL SS-1 21 22 31 20 94 82 9 SS-2 26 22 30 23 101 89 10 SS-3 21 20 27 18 86 74 8 SS-4 18 29 29 22 98 85 10 SS-5 21 21 29 27 98 84 10 SS-6 25 19 29 21 94 82 9 SS-7 27 14 31 14 86 73 8 SS-8 26 12 41 18 97 84 10 SS-9 29 20 32 21 102 90 10 SS-10 24 18 31 20 93 81 9 SS-11 33 26 39 39 137 126 14 SS-12 32 25 41 31 129 118 13 SS-13 25 19 32 29 105 94 11 Mean value 25 21 32 23 102 89 10 Canoga CA-1 22 11 24 12 69 72 8 CA-2 19 13 31 13 76 78 9 CA-3 23 14 24 13 74 75 9-CA-4 24 13 25 15 77 79 9 CA-5 19 7 43 8 77 79 9 CA-6 17 14 34 13 78 79 9 Hean value 21 12 30 12 75 77 9 Of f-si te OS-1 29 18 25 13 85 88 10 0S-2 18 12 21 13 64 62 7 OS-3 18 21 25 18 82 84 10 OS-4 21 16 25 13 75 73 8 0S-5 22 16 27 16 81 81 9 Mean value 22 17 25 15 77 78 9 RI/RD89-139 28 l

n dosimeter. reader, which artificially increase the results. The data reported for 1988 include a correction for self-irradiation as recommended by the U.S. e- . DOE-Environmental Measurements Laboratory. This correction tends to reduce j, the exposure estimates. Improvements in dosimeter calibration methods, field deployment, and storage conditions continue to be implemented. Table 61 shows that radiation exposures and equivalent annual exposure rates monitored-on-site. are nearly identical to levels monitored at 'the five- - widely separated off-site locations. These data reflect natural background radiation from cosmic radiation, radionuclides in the soil, radon and thoron .in the atmosphere, and local radioactive fallout. Locally, the natural back-ground-radiation level as measured by these dosimeters is about 100 mR/yr. The small variability observed in the data is attributed to differences in elevation and. geologic conditions at the various dosimeter locations. The altitude range.for the dosimeter locations is from about 850-ft ASL (above sea level) at the Canoga facility to a maximum of about 1900-ft ASL at SSFL. When normalized to a specific altitude by adjusting the measured value (using an altitude adjustment factor equal to 15 mR/1000-ft elevation difference), derived radiation exposures for all locations are essentially identical. The. 1988' averaged total exposure values adjusted to 1000-ft ASL are 85 8 mR for ~ De Soto, 89 216 mR for the SSFL site, 77 i 3 mR for the Canoga site, and 78 10 mR for the off-site control dosimeters. Supplementary measurements of ambient radiation levels with high-pressure ion chamber (HPIC) monitors are made at two locations at the, SSFL site. The HPIC values for 1988 were equivalent to annual exposures of 109 mR for the Building 207 monitor and 97 mR for the Building 363 monitor. These values are in good agreement with results for nearby TLD locations for the year. The Radiologic Health Section of the State of California Department of Health Services provides packages containing calcium sulfate (CaSO ) dosi-4 meters for independent monitoring of radiation levels in this area. These dosimeters 'are placed in field deployment containers used for the bulb dosi-meters. The State dosimeters. are returned to the Radiologic Health. Section RI/RD89-139 29 m

I l for evaluation by their vendor laboratory. Data for these TLDs, placed at eight Rocketdyne dosimeter locations, both on-site and off-site, were not available from the State for inclusion in this report. B. NONRADI0 ACTIVE tiATERIALS--1988 Processed wastewater and most of the collected surface runoff discharged from the SSFL site flows to Rocketdyne retention pond R-2A. Water samples from the pond are analyzed for various constituents, as required by the Regional Water Quality Control Board, for each discharge to Bell Canyon. Such discharges are normally done only as a result of excessive rainfall runoff. During a relatively dry 1988, only 11 off-site discharges from pond R-2A occurred. Water is discharged to Bell Canyon under NPDES Permit No. CA0001309. The allowable limits of this permit are listed in Appendix C. (In addition, five discharges were made from Perimeter Pond, which does not receive any water from Area IV.) The results of the pond R-2A water analyses for each discharge during 1988 are presented in Table 7 and are compared with the dis-charge limits established by the NPDES Permit. During the discharge of Sep-tember 22, the analytical results showed an excess of sulfate, above the ~ allowable limit. This was presumed to have resulted from cooling water dis-charged from the Sodium Component Test Installation (SCTI). e RI/RD89-139 30

r iL 6 8 4 6 8 5 3 6 5 e 5 b 2 9, n t a e l 1 4 8 7 v u 0 0 3 o s 5 0 0 2 5 3 0 N e 8 2 4 0 0 R 5 1 1 9 2 1 5 0 0 0 t 0 i ) 2 3 7 3 7 7 0 0 4 m% 0 0 ~ i ( 4 9 6 3 6 6 0 0 4 1 L 6 4 5 2 6 6 6 0 8 r 8 e 8 5 9 t t 4 6, 1 0 6 8, 1 n l 1 4 2 e u 0 0 0 3 9 0 7 7 v s 0 6 6 0 S o e 1 4 7 1 0 A N R 6 1 1 2 8 13 0 1 0 0 0 E R o A t 1 3 t 2 4 1 3 0 0 0 A 2 i ) l 2 im% D t ( 0 8 10 3 7 0 3 3 0 0 0 r L 9 6 3 6 1 2 4 8 6 1 l e 2 0 R )2 b 8, R 1 m t 4 d - e l 4 4 T n 1 N oW t u 9 3 2 1 7 2 0 0 8 3 O P p _ s 5 0 3 9 0 0 e 8 1 3 2 0 1 1 1 0. 0 0 0 C n e. R N o Umi S o t r 0 a t f 1 t i ) 9 7 3 1 0 0 0 S m% d U 0 i ( 3 8 9 6 0 0 0 e Grle 2 L 3 g 2 0 1 2 2 2 0 0 9 E 1 2 R ap l 2 6 3, A hn i t H a) r l c 8 3 9 C S2 p u 2 2 2 s S A _ s 7 8 8 3 3 i I f e 3 2 8 6 0 5 3 3 0 0 0 0 i D D do R e E r R t1 e I t a t 3 0 B t l ct A aide 2 im% 7 0 0 0 0 0 0 A e 9 i ) w 3 0 0 I W ( 3 0 6 3 0 0 0 0 4 e t nh L 3 2 2 1 2 4 2 6 2 9 t 1 IS y 5 ( r 1 4 s AaWe a _. t 1 1, 0 7 W t u l 4 2 1 a r u 1 0 3 8 5 3 2 r N D b _. s 0 4 2 0 o I e e 2 0 8 5 0 2 0 f 4 n F. R 3 3 1 7 3 3 3 0 0 0 5 o s 1 t N k t 0 3 0 0 l ~ m% E e 6 r l ( 1 4. 3 3 0 0 1 i) u 1U e l 0 3 sl y __ iL 3 1 2 1 1 2 10 0 s 1 0 3 3 0 4 5 e 1 C 6 9 R 15 r 1 4 4, 1 N l a _. l 4 2 1 12 i t 5 1 1 O e u s C B n y u 1 0 0 8 6 4 s 0 a 3 2 . 0 0 l L J e 0 2 2 0 5 8 0 a V R 3 7 8 4 0 4 1 0 n 1 A 1C( ) A ) 3 1 t 0 m / ( 0 g A m f R ( ) ) f N ) 1 1 o O s 1 / / n h N d / g ) g u t i g m 1 m r n l m ( / ( ) i e o ( g ) l 3 d u s s m e S l m t s d ( n A a ( d d ) d i e ) t i B f ) i t e 1 ) r M n e t i l s v / 1 l o s U / o m ( ) i n g / o s a 1 g ) n a u l o lo m g s ) e ( l m 1 h s u r l m e 1 r ( / c t ( o C s ( d s ( l / g y g n d v i e e b g t e m l a l e l d e d a m d d i t n e ( n i d ( a t l t e l d i n d a f m a f u c a a s l r a e l a i o o i f n i e r a o f p t 5 b t l l s t 0 l r l B R S p R E R R u r s r, T C S S S B O l F t H i t l i o h u u e 0 iu o e a s e , @o>e " w-

t 3 2 0 3 7 0 0 i ) m% 1 3 3 8 2 i ( 3 8 9 3 6 0 0 L 2 8 ( 1 2 0 0 0 0 1 1 r 8 6 e b t 2, 1 7 4 4 n l 8 0 e u 5 0 0 7 3 9 2 1 e e 2 1 8 3 0. 5 1 2 0 c s 0 9 1 8 D R 2 2 5 2 2 2 0 0 0 0 8 9 1 t 3 0 0 im% 0 7 7 0 0 ) 1 1 ( 2 1 0 3 0 5 2 iL 2 16 1 3 4 1 0 4 2 A 1 8 1 1 0 L r 2 2 R e 1 1 o A t t t 1 1 n l D e u 1 1 4 1 0 A 0 0 1 3 9 8 E c s 0 . 6 2 1 l2 e e 1 4 3 1 0 6 0 0 0 l - D R 2 2 5 4 2 2 5 0 R) 0 2 R 1 d t 3 0 1WonW im% 6 0 3 7 ) 5 3 3 0 6 f P C n 1 ( 0 4 4 3 0 0 0 4 0 U io iL 6 4 4 5 7 6 4 0 Nm r ot e 4, 13 r 0 a t t 0 1 1 8, 3 f 1 t n l 4 3 S e u 1 1 0 2 8 4 1 4 d U c s 6 3 e 2 . 6 5 . 0 0 6 0 7 F e e e 1 6 3 0 0 0 Ggl D R 5 6 1 3 1 2 0 r R ap A hn H a) t c 3 0 C s2 im% 1 3 0 0 0 4 0 0 ) 1 7 s S 1 3 0 8 f ( 4 3 8. 7 IiD iL 5 8 3 3 5 3 6 2 3 7 6 D do r e e 6 E r I R t2 t 8 0, e a n t B l t l ct e l 4 4 1 A a 4 A ie c u 1 0 0 3 Wwde e s 0 5 1 0. 6 5 3 0 1 e 6 L nh D e 2 2 1 t 0 I IS R 5 1 1 8 9 6 0 0 0 s S ( a awe W t t a 2 i ) 1 r 1 3 3 3 0 0 0 1 8 0 0 0 N D 2 m% 0 o i( 3 9 8 3 0 I f n r L 5 7 3 1 6< 5 3 4 5 5 o e s 0 N 0, t b 1Llk n t 2 e e l 1U e v u 1 4 9 u 0 0 1 2 8 1 s r o s 5 15 l R 10 19 1 5 0 1 5 3 0 e C N e 1 R 0 5 1 1 4 3 5 0 0 0 s Nil O e s ) C B ) Ely 3 1 m / a ( V g l n l A m f ( ) ) f C( ) 1 1 o A s 1 / / n h 0 d g u D1 t i / g ) g m 1 m r m ( / ( ) i n l A e o ( g ) l m R u s s m e S l 3 d N t s d ( n A a ( d O i d ) d i ) i B f N t e 1 ) i lo s u / o ( ) i m l e ) 1 r M n e t s v / 1 l n l g / o s a l g ) m a u l o o m g s ) m 1 h s c r l e ( C s ( m d ic 1 r ( / c t ( o s ( / g y g n d v e e b g t e m id i t n c ( d id i n d a f m a f l a l e l d e d a m d ( a t l t e l n u c a a s r a e i a r l o l u e 0 u l o e u H i t le i a f p t 5 i o o is r b f n i e n s t 0 l r u r t l u a s o h T C S S S B iO l F B R S p R t R R* hheL w* wto

IV. ENVIRONMENTAL MONITORING PROGRAM A. DESCRIPTION The environmental monitoring program was initiated in 1952 at Rocket-dyne's predecessor company, which was then located in Downey, California. At that time, a program of soil and vegetation sample collection and analysis was begun to study environmental effects from the nuclear research and develop-ment conducted there. This program was designed with the primary purpose of adequately surveying environmental radioactivity to ensure that company nuc-lear operations would not contribute significantly to local radioactivity. Any program changes have reflected this primary objective. Environmental sampling was subsequently extended to the then proposed Sodium Reactor Experi-ment (SRE) site in the Simi Hills in May 1954. Sampling was also begun in the Burro Flats area, southwest of SRE, where other nuclear installations were planned and are currently in operation. The Downey area survey was terminated when nuclear activities were relocated to Canoga Park in 1955. After review of the needs and results of the environmental monitoring program in 1986, sam-pling of vegetation for radioactivity analysis was terminated and soil sam-pling frequency was reduced to quarterly. This was based upon reviews of the sampling program aro the nuclear operations being conducted at the site. The reduced nuclear operations and the historical data led to the conclusion that quarterly sampling was adeauate to confirm releases of radioactivity identi-fied by other monitoring methods. Although the reduction in the number of on-site soil samples taken annually is significant, the number of off-site soil samples taken annually remains the same. lable A-1 shows that the 1988 aver-aged values for soil activity compares well with values for prior year 3. 1 Locations of sampling stations are shown in Figures 6 through 9 and listed in Table 8. l i ] RI/RD89-139 33

g t R 3 1 .Oj <O c 2 c 0 E 34 g O N l$ DS T A D O G N SE T OK A A EI NR G D L AA O lOL'S CP R w i E C N OL I E A WH IL T E D O( D O A t C N S W7 S E ghO O G R E S L r A \\' J S \\ A \\ B A \\ \\ L l \\ A \\ C \\ mI \\ c I I I l g I \\ [k" \\ Y N h T O Y N Y,M Y T U [ N F M."" N ^ O A/ g D OU C C M S O R I; - C E P A L A D R E U T rl gILE U G X 4 ET T N I N A L FS E S S ( IH AS V E I LA A I O 1 R NE L AR M SO UT R SA ~ U Y AR O 5 E TO ~ G L NB A ~ L AA 4 A SL V I y f MI S E 3 K L S A A O C D S 2 N A f N S U 1 O H / O_ T l / 1 / / b E yoc t o g

1 I1l1l 1 R 3 R 2 0 E 3 L 4 PM R A E S ft Y R s 5 D E E 2 I n N V A L 2 t T o E A 1 G i S C O N 1 lt I t E S m D E L a D B O L M t S T A S h g p\\ n 6, i l p l" ma S k y t in ic A ,lII ,.8Ed I i R N V E E M b 1 e@ F H d M F U O - T P n L H A a P D E P R 5 e O t N f # I!mm M a-i S rg o I t 8a* o S e D fo p a M 7 e A rug i ( F i N I "h?C*

t e4 %? 8 5!' O o z g !!!* A. !! i i . Ei s \\ Le s, =g 6 ,8#5 5 \\ GOQe ? m ee- \\ \\h h \\4!h'1 n N % f f[ e l '!!!( df q ,5 4 _i \\~

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\\.. = ' ( \\ c.,g j sEJ u s z-v_f r o-- f ~ m q a 'g \\:A k.ji N!, - 'B i \\ d"- A g N4 4 - {......- m \\ b 's E .E" \\- \\ ,Y \\ 7 l N, ,/ 's / RI/RD89-139 36 l l _ ____________________._________j

VANOWEN SLVD sums -m 1 g PARKING ' BLDG 004 ~ BLDG l BLDG OES 043 c 2 l co a 5 t I SECURITY U q CONTROL CENTER C I t L_ g 9 j--Z 4 BLDG 001 5 ]=5 La -2 a BLDG 037 s k i g l [~~] } PARKING PARKING HEOP6IT ~ ~ is== LEGEND TLD DOSIMETER D5074-1 Figure 9. Map of Canoga Site TLD Locations 9 R1/RD89-139 37

l TABLE 8 SAMPLING LOCATION DESCRIPTION i 1-(Sheet 1 of 5) Frequency of Station Location Sampling

I S-1 SSFL Site, Building 143, southeast side (Q) l S-2 SSFL Site, Building 003, east side (Q)

S-3 SSFL Site, Building 064, north parking area (Q) S-4 SSFL Site, Building 020, at west fence (Q) S-5 SSFL Site, Building 363, east parking area (Q) S-6 SSFL Site, Interim Retention Pond, south side (Q) S-10 SSFL Site Access Road, at upper mobile home park entrance (Q) S-12 SSFL Site, Building 093, at driveway (Q) S-13 SSFL Site, above SRE Retention Pond (0) S-14 SSFL Site, Building 028, upper parking area (Q) S-19 SSFL Site Entrance, Woolsey Canyon (Q) S-24 De Soto Site, Building 104, east side (0) S-25 De Soto Avenue and Plummer Street, southeast corner (Q) S-26 Mason Avenue and Nordhoff Street, southeast corner (Q) S-27 De Soto Avenue and Parthenia Street, northeast corner (Q) S-28 Canoga Avenue and Nordhoff Street, northwest corner (Q) S-31 Simi Valley, Alamo Avenue and Sycamore Road, southeast (Q) corner S-40 Agoura - Kanan Road and Ventura Freeway at Frontage Road (Q) S-41 Calabasas - Parkway Calabasas and Ventura Freeway at Frontage Road (Q) S-42 SSFL Site, Building 886, at former sodium disposal facility gate (Q) S-47 Chatsworth Reservoir Site North Boundary at north gate (Q) S-51 SSFL Site, Building 029, at driveway (Q) S-52 SSFL Site, Burro Flats Drainage Control Sump, G Street and 17th Street (Q) S-53 SSFL Site, Pond R-2A (Q) m RI/RD89-139 38

l TABLE 8 SAMPLING LOCATION CCSCRIPTION (Sheet 2 of 5) Frequency of Station Location Sampling

S-55 SSFL Site, Pond R-2A (Pond Bottom Mud), north side (0)

S-Sf-3SFL Site, F Street and 24th Street (S) S-Si 3SFL Site, J Street, south of Building 055 exhaust stack (S) S-58 SSFL Site, Building 353, south of road (S) S-59 SSFL Site, Test Area STL-4, entrance, west side (S) S-60 SSFL Site, Pond R-2A, northwest side (S) S-61 Simi Valley, east end of Alamo Avenue (S) S-62 SSFL Site, near south boundary, Bell Creek Heir, Hell 9 (Q) H-6 SSFL Site Interim Retention Pond, south side (M) H-7 SSFL Site Domestic Water, Building 003, washroom faucet (M) H-11 SSFL Site Domestic Hater, Building 363, washroom faucet (M) H-12 SSFL Site, Pond R-2A, north side (M) ~ H-13 De Soto Site, Building 104, washroom faucet (M) H-17 SSFL Site, Pond R-2A, discharge to Bell Creek (Seasonal) A-1 De Soto Site, Building 102 roof (D) A-2 De Soto Site, Building 104 roof (D) A-3 SSFL Site,,8uilding 100, east side (D) A-4 SSFL Site, Building 011, west side (D) A-5 SSFL Site, Building 600, Sewage Treatment Plant, north side (D) A-6 SSFL Site, Building 207, Security Control Center, north side (D) A-7 SSFL Site, Building 093, west side (D) A-8 SSFL Site, Building 163, Box Shop at east side (D) A-9 SSFL Site, Building 363, west side (D) A-10 SSFL Site, Building 100, east side day sampler (168 h) W F.I/RD89-139 39 i la

TABLE 8 SAMPLING LOCATION DESCRIPTION (Sheet 3 of 5) Frequency of Station Location Sampling

Qn-Site--De Soto - Ambient Radiation Dosimeter Locations (TLD)

DS-1 De Soto Site, south of Block House (Q) DS-2 De Soto Site, northwest corner of Building 101 (State of California TLD Location Number 2) (Q) DS-3 De Soto Site, southeast corner of Building 102 (Q) DS-4 De Soto Site, northeast corner of SPEL II Laboratory Building 113 (Q) DS-5 De Soto Site, northeast corner of Building 102 (Q) 05-6 De Soto Site, east boundary, southeast corner of Build-ing 105 (State of California TLD Location Number 1) (Q) DS-7 De Soto Site, north of Building 106 -(Q) DS-8 De Soto Site Guard Post 4, southwest corner of Building 101 (State of California TLD Location Number 7) (Q) On-Site--SSFL - Ambient Radiation Dositneter Locations (TLD) SS-1 SSFL Site, west of emergency trailer, Building 114 (Q) SS-2 SSFL Site, SRE Retention Pond (Q) SS-3 SSFL Site, Electric Substation 719 on boundary fence (State of California TLD Location Number 3) (Q) SS-4 SSFL Site, west boundary on H Street (Q) SS-5 SSFL Site, southwest boundary at property line gate (Q) SS-6 SSFL Site, northeast corner of Buiiaing 353 (State of California TLD Location Number 4) (Q) SS-7 SSFL Site, Building 363, north side on HPIC monitor (State of California TLD Location Number 8) (Q) SS-8 SSFL Site, Souium Disposal Facility north boundary (Q) SS-9 SSFL Site, Radioactive Materials Disposal Facility, northeast boundary at Building 133 (Q) SS-10 SSFL Site, Building 600, Sewage Treatment Plant (Q) SS-11 SSFL Site, RMDF northwest property line boundary (Q) (State of California TLD Location Nuicher 9) SS-12 SSFL Site, RMDF northsest property line boundary (Q) SS-13 SSFL Site, RMDF northwest property line bc idary (Q) RI/RD89-139 40

TABLE 8 SAMPLING LOCATION DESCRIPTION (Sheet 4 of 5) Frequency of Station Location Sampling

a On-Site--Canoaa - Ambient Radiation Dosimeter Locations (TLD)

CA-1 Canoga Site, northeast corner of Building 038 CA-2 Canoga Site, southwest corner of Building 002 CA-3 Canoga Site, south of Building 001 near street entrance CA-4 Canoga Site, east of Building 009 on boundary fence CA-5 Canoga Site, east of Building 037 on boundary fence CA-6 Canoga Site, southeast corner of Building 037 Off-Site (TLD1 OS-1 Off-site, Northridge, approximately Oakdala Avenue and Lassen Street (State of California TLD Location Number 5) (Q) OS-2 Off-site, Simi Valley, approximately Tapo Canyon and Halnut Streets (Q) OS-3 Off-site, San Fernando Valley, Northridge, approximately Plummer Street and Vanalden Avenue (Q) 0S-4 Off-site, Simi Valley, approximately Tapo Canyon and Halnut Streets (Q) 0S-5 Off-site, Simi Valley, approximately east Los Angeles Avenue and Stow Street (State of California TLD Location Number 6) (Q) HPI-l High-Pressure Ion Chamber (HPIC) Ambient Radiation Monitor at Building 207, north side (C) HPI-2 High-Pressure Ion Chamber (HPIC) Ambient Radiation Monitor at Building 363, north side (C) Codes: Samole Tvoe

Freauency Location S Soil 0 Daily CA Canoga H Hater M Monthly DS De Soto A Air 0 Quarterly SS SSFL TLD Thermoluminescent S Semiannual OS Offsite Dosimeter C Continuous O

RI/RD89-139 41 i

TABLE 8 SAMPLING LOCATION DESCRIPTION (Sheet 5 of 5) SSFL SITE GROUNDWATER SAMPLING STATIONS DEEP AND SHALL0H TEST AND PRODUCTION HELLS (Sampled Quarterly or Seasonally Depending on Groundwater Recharge) Hell Description of General Location HS-4A On-site: On north boundary HS-5 On-site: 1500 ft from southeast boundary HS-6 On-site: 2500 ft from north boundary HS-7 On-site: 550 ft from north boundary HS-8 On-site: 300 ft east of Silvernale Reservoir HS-9 On-site: 1500 ft east of Silvernale Reservoir NS-9A On-site: 1000 ft south of Pond R-2A in drainage channel HS-11 On-site: 2500 ft from northwest boundary HS-12 On-site: 800 ft from north boundary NS-13 On-site: 200 ft from north boundary HS-14 On-site: On northeast boundary OS-1 Off-site: 1350 ft from site north boundary 05-2 Off-site: 1750 ft from site northwest boundary 0S-5 Off-site: 1100 ft from site northwest boundary OS-8 Off-site: 1750 ft from site north boundary (Spring) OS-10 Off-site: 4250 ft from site north boundary OS-13 Off-site: 900 ft from site east boundary 0S-15 Of f-si te: 2900 ft from site northeast boundary OS-16 Off-site: 800 ft from s te northeast coundary i RS-20 On-site: 4400 ft from east boundary RS-21 On-site: 860 ft from north boundary RS-22 On-site: 1000 ft from north boundary HS SSFL on-site water supply well (drilled before 1960) OS Off-site water well for groundwater monitoring RS SSFL on-site shallow zone groundwater monitoring well. .) RI/RD89-139 l 42

1 B. SAMPLING AND SAMPLE PREPARATION 1. SAi_1 Soil is analyzed 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 monitored for increases beyond the natural variability of this background. For most radionuclides, gross alpha and beta radioactivity measurements are adequate for this purpose. Chemically specific analyses are performed for plutonium to provide improved sensitivity. Surface soil types available for sampling range from decomposed granite to clay and loam. Samples are taken from the upper 1 cm of undisturbed ground surface for gross radioactivity analysis and to a depth of 5 cm for plutonium analysis. The soil samples are packaged in paper containers and returned to the laboratory for analysis. Sample soil preparation for gross radioactivity determination. consists of transferring samples to Pyrex beakers and drying them in a muffle furnace at about 500*C for 8 h. After cooling, the soil is sieved to obtain uniform par-ticle size. Two-gram aliquots of the sieved soil are weighed into stainless-steel planchets. The soil is wetted in the planchet with alcohol, evenly dis-tributed to obtain uniform sample thickness, dried, and counted for alpha and beta radiation. Soil plutonium analysis is performed using a chemically specific method by a certified independent testing laboratory according to the guidelines specified in the U.S. NRC Regulatory Guide 4.5 titled " Measurements of Radio-l nuclides in the Environment--Sampling and Analysis of Plutonium in Soil." l I RI/RD89-139 43

2. Water Surface and supply water samples are obtained monthly at the De Soto and SSFL sites and from upper Bell Creek during periods of off-site discharge. 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 crystallizing dishes at about 90*C. The residual dissolved solids are redissolved into distilled water with dilute nitric acid, transferred to planchets, dried under heat lamps, and counteG for alpha and beta radiation. 3. Ambient Air Air sampling is performed continually at De Soto and SSFL with air samp-1ers operating on 24-h sampling cycles. Airborne particulate radioactivity is collected on glass fiber filters which arc automatically changed daily at the end of each sampling period (midnight). The samples are counted for alpha and beta radiation following a minimum 120-h decay period. The volume of a typi-3 cal daily ambient air sample is about 25 m, C. COUNTING AND CALIBRATION Environmental soil, water, and ambient air samples are counted for alpha and beta radiation w'.th a low-background gas flow proportional counting sys-tem. The system is capable of simultaneously counting both alpha and beta radiation. The sample-detector configuration provides a nearly 2tr geometry. The thin-window detector is continually p :rged with argcn/ methane counting gas. A preset time mode of operation is used for all samples. The lower lim-its of detection shown in Table 9 are those for a single sample determined by using typical values for counting time, system efficiencies for detecting alpha and beta radiation, background count rates (approximately 0.05 cpm alpha and 1.0 cpm beta), and sample size. These limits of detectability, for single samples, are calculated according to U.S. NRC Reguiatory Guide 4.16, and assure a 957. probability that the measured activity would be identified as "above background." RI/RD89-139 44

TABLE 9 LOWER LIMITS OF DETECTION (LLDs) Sample Activity Soil Alpha (3.2 1.8) 10-6 pCi/g (118.4 1 66.6 Bq/kg) ~ Beta (3.7 2.0) 10-7 pCi/g (136.9 74 Bq/kg) Hater Alpha (4.0 1.9) 10-10 pCi/ml (0.0148 0.007 Bq/1) Beta (1.1 1.2) 10-9 pCi/ml (0.0407 1 0.044 Bq/1) Air Alpha (9.1 2.4) 10-15 pCi/ml (0.0003 1 0.0001 Bq/m3) Beta (3.8 1.4) 10-14 pCi/ml (0.0013 0.0004 Bq/m3) 99Tc, 36Cl, Counting system efficiencies are determined routinely with 230 235 239 40 Th, U, and Pu standard sources and with K, in the, form of standard reagent-grade kcl, which is used to simulate soil, and with soil con-taining known amounts of highly enriched uranium. The activities of the standard sources are traceable to the National Institute of Standards and Technology (NIST, formerly NBS). Self-absorption standards for beta counting are made by dividing sieved kcl into samples that increase in mass by 200-mg increments, from 100 to 3000 mg. The samples are placed in planchets of the type used for environ-mental samples and are counted. The ratio of sample activity to the observed net count rate for each sample is plotted as a function of sample mass and a smooth curve is drawn through these points. The correction factor (ratio) corresponding to the mass of environmental samples is then obtained from the graph. The product of the correction factor and the net sample count rate yields the sample activity (dpm). This method has been proven usable by applying it to various-sized aliquots of uniformly mixed environmental samples and observing that the resultant specific activities fell within the expected statistical counting error, showing the absence of any systematic bias. Since the observed radioactivity in environmental samples primarily results from natural sources and is at low concentrations, constituent radio-nuclides are not identified for each sample. However, cellected samples are RI/RDB9-139 45

composited for gamma spectrometry of accumulated sample materials. The detec-tion of significant levels of radioactivity would lead to an investigation of the radioactive material involved, the sources, and possible causes. D. NONRADI0 ACTIVE MATERIALS The Rocketdyne Division of Rockwell International Corporation has filed a Report of Haste Discharge with the California Regional Water Quality Control Board and has been granted a Na'_lonal Pollutant Discharge Elimination System permit to discharge wastewater, pursuant to Section 402 of the Federal Water Pollution Control Act. The permit, NPDES No. CA0001309, which became effec-tive 27 September 1976, was renewed with minor changes effec 61ve 17 September 1984. This permit covers discharge of overflow and storm runoff from water reclamation retention ponds into Bell Creek. Discharge generally occurs only during and immediately after periods of heavy rainfall or during extended per-iods of rocket engine testing that release large amounts o# cooling water to the ponds. Only one of the retention ponds receives influent from the nuclear oper-ating areas (Area IV) of the SSFL site. It is identified as retention pond R-2A, Water Sample Station H-12 in Table 8. The influent includes sewage treatment plant outfall and surface runoff water. Grab-type water samples taken at the re+ i pond prior to a dis-charge are analyzed by a California State certifiet _alytical testing labora-tory for nonradioactive chemical constituents and for radioactivity. Appen-dix C lists specific constituents which are analyzed, as well as their respec-tive limitations in discharged wastewater. Hastewater originating from facil-ities located throughout the SSFL site is collected at the retention pond. The point of origin of small amounts of most nonradioactive constituents nor-mally found in wastewater is difficult to determine. If excessiv6 amounts of any of these materials were found in wastewater, their origin could be deter-mined from the knowledge of facility operations involving their use. RI/RD89-139 46 l l

In addition to the wastewater discharge limitations, atmospheric pollu-tant discharge limitations ware imposed by the Ventura County Air Pollution Control District (APCD) Permit 0271 on two natural-gas / oil-fired sodium heaters operated by ETEC. The limitations for 1988 are 1.50 tons /yr for reat-tive organic compounds,131.13 ton /yr for oxides of nitrogen, 3.05 tons /yr for O particulate 0.60 tons /yr for oxides of sulfur, and 40.51 tons /yr for carbon monoxide. No operations resulted in emissions exceeding these limits. These limits were increased for 1988 due to planned increases in operation of gas-fired boilers for component testing and for a new power generation facility which was brought into service during the year. The increased limits reflect anticipated increased demand and do not reflect actual release increases. The decrease in the limit for oxides of sulfur occurred because the use of fuel oil during the year was not planned. There were no draft or final Environmental Impact Statements or Reports, site assessments, or remedial action reports produced during 1988. Addition-ally, there were no actions taken by local authorities relative to CERCLA / SARA activities or Notices of Violation. ~ RI/RD89-139 47 E

V. EFFLUENT MONITORING PROGRAM Effluents that may contain radioactive material are generated at the Rocketdyne Division facilities as the result of operations performed under contract to DOE, under NRC Special Nuclear Materials License SNM-21, and under O the State of California Radioactive Material Licens+ 0015-70. The specific facilities are identified as Buildings 020 and 021-022 at SSFL, and Build-ing 104 at the De Soto complex. A. TREATMENT AND HANDLING The oniy release of radioactivity to uncontrolled areas is by way of dis-charge to the atmosphere. No contaminated liquids are discharged to unre-stricted areas. The level of radioactivity contained in all atmospheric effluents is reduced to the. lowest practical value by passing the effluents through certi-fled high-efficiency particulate air (HEPA) filters. The effluents are sam-pied for particulate radioactive materials by means of continuously operating stack exhaust samplers at the point of release. In addition, stack monitors ~ installed at Buildings 020 and 021-022 provide automatic alarm capability in the event of the release of gaseous or particulate activity from Building 020 and particulate activity from Buildings 021-022. The HEPA filters used for filtering atmospheric effluents are at least 99.97% efficient for particles 0.3 pm in diameter. Particle filtration efficiency increases for particles above and below this size. The average concentration and total radioactivity in atmospheric efflu- - ents to uncontrolled areas are shown in Table 10. The effectiveness of the air cleaning systems is evident from the fact that the atmospheric effluents are less radioactive than is the ambient air. The total shows that no signif-icant quantities of radioactivity were released in 1988. 1 l i l RI/RD89-139 l 49 1

l I l' ,re G 3 36 t 231 0 002 i P 000 0 005 l M 000 0 000 i l 000 00000 l im F 3 4 r D 0 m 8 0 e M 0 / 627 7 4 1 0 03 p i 68832 0 000 R 0, C s 2 0 F 02606000000 e 2 0 0 i 0 0 0 r 0 9, 7 0 1 7 7 u 01 2, 92 3 8 01 r 1 0001 1 c L 0 3 3

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a 4 7 84 7 000 000 o 4 F 4 5 2 00 3 01 22 04 L. e 52000000000 r 5 I " Y c 01 000000000 i m e o s 1 t a r 2 2 08 e a 441 360 000 t l e 662 500 000 r e " Y e R 001 01 000000 vno 6 1 6 1 c a 8 0 0 0 0 C 00 0 0 0 o P 00 0 0 0 T M 00 0 0 0 000 00000 8 c 8 i 9 8 b 1 L 3 4 0 a 0 m 0 2 0 t l 0 / 88 4890 0 0 i l 90 223 0 0 0 L 0 0 F 61 000000000 is S R 0, i C A h R 2 0 0 t 0 A 0 7, 81 1 6 0 n 01 3, 1 18 r 31 1 1 3 3

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a 2 358 3 000000 i D L 8 33 E F 0 0 1 3 03 I. e 041 01 000000 - n L S 4 00 3 09 O I "Y o I S 1 2000000000 i R t a 1 N e 3 t O s 2 1 0 n C a r 0 0 0 e N e a 54 02 60 0 0 s U l " e 8 4 1 0 0 0 e 1 1 r e Y R 20000000000 p 0 1 4 f a-o 5 60 285 1 1 N C 00 9 00 y 1 L P 00 00 0 - t U M 00 1000 0 - i r I 000 00000 a I I h l c L c ~ r C a 3 1 r I e 0 m 0. o R s 0 / 2 82 67 3 1 0 f t e 0, 2 1 2 57 00 0 i H R C r P 0 F 02000000000. te 5 4 0 0 0 0 1 0 e m 8 8 8 M 1 01 4, 91 2 6 3 4 / r 2 00 022 - 3 3 3 6 1 2 9 D. i a 91 958 000000 I 1 A o 16 1 2 c o l C 5 83 00 e 54000000000 t 00 2 1 i S l pY. .b 0 01 000000000 - u s c e _ e 1 D e t r ue E s 1 I a/ r 5 2 0 n p R lei a 7 3 3 4 3 0 0 0 i A C e t s 1 e pY 3 0091 00 0 s e R O0000000000 ei r - eu s t r e s c r n a d oo e e e - dt i m t u y l e n c l / c - n e mo f i f s u if i c c d ie n i t ct u c d s r y - ea d 5 b e ~ n e u b u nI. ut d i v c c e e r u d w l c o0 l n e r e - d e p o s c s . i s n h1 mf m i b a u o a t o im e x l s a l t e ot r m d e o r1 vi e t u e r 0 n a m m n m s y 9 y -, sb t i 3 u e3 i 3 a nl m3 cm3 x m3 e t m gn l e / mo n/ mu / ml i u 0 n os u r i / v oi/n i / e v i 4 iie i r / rtu l e Ci cCi Ci r f w f C r f C d F C t t 8 9 - r al f o f i c* 0 t 1 4 5 8 2 2. ctv 0 3 3. u ra e f o f y el a a ga ina t a a7 4 Y h a ah a roh aih a _ / 7 23 3 3 - - c n e e pt e rpt ei p t v pt. f mm0 m3 - 2 2 2 mm o ee et el e ptl eil e ou u6 u1 m - - - u u - ch t t l ii i u mmmii-y nt uu ab a v ab aab t ab _ n n m a gr c el st t miu u u n n - l o ii s si s s nt s s a s s t l sl n u niii oo Cy l x x s s xsl s sins s s s a ya a oi on n nt t . a l o o) oo or aool eool o o. mrt b r sl a a a u u r p r r0 r r re ur r pcr r a r r _ i e oot e or r rl l - u ;i t BP C S C P U UUPP t et p p1 GG pt nGG mnGG t G G s - a tl p p1 pe n ao o A A( AmA Sc l . N ou E

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l 1 l I The isotopic composition of the radioactivity deposited on the nuclear facility exhaust air sampling filters, composited for the year, is presented in Table 10. The table shows that the majority of the collected activity is caused by naturally occurring elements. The beryllium-7 collected on the RIHL filter is attributed to its presence in bypass air taken into the main exhaust system. The presence of-polonium-210 is also a result of natural occurring elrments in the uranium-238 decay chain. Materials used in operations con-ducted at the SSFL site are responsible for the fission / activation product radioactivity. The laboratory LLD for the composited filters was converted to an equivalent annual release and is shown in the table as LLD, pCi/ year. B. FACILITY DESCRIPTION 1. De Soto Site a. Buildina 104--California State Licensed Activities Operations at Building 104 that may generate radioactive effluents con-sist of research studies in applied physics and physical chemistry. Only atmospheric effluents are released from the building to uncontrolled areas. 60 137 Major quantities of radionuclides present are limited to Co and Cs in encapsulated form. 2. Santa Sttsana Field Laboratories _ Site a. Buildina 020--NRC and California State Licensed Activitiel Operations at Building 020 that may generate radioactive effluents con-sist of hot cell examination and decladding of irradiated nuclear fuels and examination of reactor components. Only atmospheric effluents are released from the building to uncontrolled areas. The discharge may contain radioac-tive gases as well as particulate material depending on the operations being 4 RI/RD89-139 51 b

performed and the history of the irrad hted fuel or other material. No radio-active liquid waste is released from the facility. Prior radioactive material handled in unencapsulated form in this facility included the following radio-137 nuclides: U, Pu, as constituents in the various fuel materials; and Cs, I47 90Sr, 85Kr, and Pm as mixed fission products. b. fly.i_1dingi_021 and 022--DOE Contract Activities Operations at Buildings 021 and 022 that may generate radioactive efflu-ents consist of the processing, packaging, and temporary storage of liquid and dry radioactive waste material for disposal. Only atmospheric effluents are released from the building to uncontrolled areas. No radioactive liquid waste is released from the facility. Nuclear fuel material handled in encapsulated 137Cs, 90Sr, I or unencapsulated form contains ' uranium and plutonium plus i 85 I Kr, and Pm as mixed fission products. i i 3. Cmga_ Site a. S_eyvatal Maior Manufacturing Facilities Engaged in DOD and NASA Activities Other than product quality assurance inspection by X-ray and source radiography techniques, and also some limited State-licensed research work requiring the incidental use of small quantities of radioactive materials, no nuclear activities are conducted at the Canoga complex. C. ESTIMATION OF GENERAL POPULATION DOSE ATTRIBUTABLE TO ROCKETDYNE OPERATIONS--1988 The Los Angeles basin is a semiarid regior. whose climate is controlled primarily by the semipermanent Pacific high-pressure cell that extends from Hawaii to the Southern California coast. The seasonal changes in the position of this cell greatly influence the weather conditions in this area. During the summer months, the high-pressure cell is displaced to the north. This ~ results in mostly clear skies with little precipitation. During the winter, RI/RD89-139 52

the cell moves sufficiently southward to allow some Pacific lows' with their associated frontal systems to move into the area. This produces light to moderate precipitation with northerly and northwesterly winds. The release of airborrt material at De Soto for summer season weather conditions would generally be under a subsidence inversion into an atmosphere that is typical of slight neutral to lapse conditions. Nocturnal cooling inversions, although present, are relatively shallow. During the summer, a subsidence inversion is present almost every day. The base and top of this inversion usually lie below the elevation of the SSFL site. Thus, any atmos-pheric release from the SSFL site under this condition would result in Pasquill Type D lofting diffusion conditions above the inversion ar.d consider-able atmospheric dispersion, prior to any diffusion through the inversion into the Simi or San Fernando Valleys. In the winter season, the Pacific high-pressure cell shifts to the south and the subsidence inversion is-usually absent. The surface airflow is then dominated by frontal activity moving easterly through the area, resulting in high-pressure systems in the Great Basin region. Frontal passages +hrough the area during winter are generally accompanied by rainfall. Diffusion characteristics are highly variable depending on the location of the front. Generally, a light to moderate south-westerly wind precedes these frontal passages, introducing a strong onshore flow of marine air and producing lapse rates that are slightly unstable. Wind speeds increase as the frontal systems approach, enhancing diffusion. The diffusion characteristics of the frontal passage are lapse conditions with light to moderate northerly winds. Locally, average wind speeds for the vari-ous stability categories range from 0 to about 4.4 m/s with the greatest fre-quency occurring for winds from the north to northwest sectors. Figures 10 through 12 show local population distribution estimates that were projected i for 1986, based on the 1980 federal census and on direct observation of nearby residential areas around the S$FL site and out to 80 km for 16 sCctors. The downwind concentration of radioactive material edissions to the atmosphere during 1988 from each of the three major Rocketdyne nuclear facili-ties has been calculated with the AIRD05-EPA computer code using site-specific RI/RD89-139 53 i

j. t \\ \\ \\ \\ \\ \\ \\ am f / \\j \\ % wu 1 l M l "" W-L "'I / j VALLEY p [ 3' \\ idOb6 2760 / I O I 4279 0 sANgrgsusANA l l 308' i3si 0 0 ,, no,3 rare 0 10 50 Se / io aso tiri f p 0 O O O O is a0

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"f: I I l' \\ !? \\ \\ n \\ \\ \\ n \\ \\ / SANT A SUSANA MOUNTAINS 101 38 \\ ,/ /N 14174 I g y { g, 3306 3 681 50131 'I , VALLEY \\ bf '~ 21 1397 CHATSWORTH l O 8471 115433 THOUSAND 1 8687 OAKS CANOGA l 25 l PARK l )152365 41543 5747 55 3697 \\ l VENTURA COUNTY LOS ANGELES COUNTY ,/ f / 19125 / / WOODLAND

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f 12602 100 / 1 889 / / 'N SANT A MONICA MOUNTAINS / / SCALE D 1 2 3 4 5 MILES 0 1 2 3 4 5 6 7 8 KILOMETERS D4302 8 Figure 11. Santa Susana Field t. laboratories Site-Centered Demography to 16 km RI/RD89-139 55

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-Y g'4?; (., PACIFIC OCE AN h 1 i SCALE O to 20 30 40 50 MILES fl 10 ?O 30 40 50 60 70 80 KILOMETERS D4302-9 Figure 12. Santa Susana Field Laboratories Site-Centered Demography to 80 km (heavily populated areas are shown by shading) RI/RD89-139 56

i input data including local area windspeed, directional frequency, and stabil-ity plus facility-specific data such as stack heights and exhaust air velocity. The radioactivity concentrations at the site boundary location nearest 4 to each release point and at the nearest residence for each nuclear facility 9 are shown in Table 11, and both internal and external radiation dose estimates are given in Table 12. The internal dose calculations in Table 12 assume a I constant unsheltered exposure, adjusted for wind direction frequency, through-out the year and therefore considerably overestimate the actual annual-averaged doses at the nearest boundary and nearest residence. The external dose calculations assume that differences in TLD readings represent true differences in local exposure. These differences are extrapolated to the boundary and nearest residence using an inverse square distance relation from an assumed source of radiation. The estimated doses are far below the applicable limits of DOE, EPA, NRC, and the State of California. TABLE 11 ANNUAL AVERAGED PLUME CONCENTRATIONS 0F ATMOSPHERIC EMISSIONS--1988 Downwind Concentration ~ Release Distance (m) to (10-18 Ci/ml) Rate Facility (Ci/ year) Boundary Residence Boundary Residence 80 km B/104 9.4 x 10-7 187 E 315 SH 0.07 0.02 0.004 B/020 3.8 x 10-6 302 NH 1900 SE 0.20 0.04 0.0006 B/022 4.1 x 10-6 118 NH 2300 SE 0.05 0.03 0.0007 Except for the nearest boundary line exposure for the Radioactive Materi-als Disposal Facility (RMDF), the estimated off-site doses are extremely low compared to the maximum permissible exposures recommended for the general pop-ulation in the vicinity of DOE facilities. The effective dose equivalent for any member of the public, for all pathways, shall not exceed 500 mrem /yr for occasional exposures, and 100 mrem /yr for prolonged periods of exposure. For E RI/RD89-139 57 L

- i 1llII s 2 3 l I 4 l 1 3 3 3 0 0 e 1 I I I 1 I 1 1 1 1 1 88 1 c ) n 0 0 0 0 0 0 0 0 0 0 0 0 0 0 F e 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D d M i x x x x x x x 0 000 00 x x x x x x x R s 0 1 4 802 9 62 2 4 5 5 5 ( e R 2 1 5 1 57 4 1 1 3 3 1 4 4 4 2 ) 0 m e 1 r 2 2 2 l 0 3 1 I 3 3 3 0 ( 0 1 1 I 1 1 1 I I 1 1 1 2 2 4 / y 8 T r 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 a 1 1 1 1 1 1 1 1 1 1 1 1 1 1 9 L d 1 F n x x x x x x x x x x x x x x 5 u 81 41 60000 0 02 2 3 6 0 0 0 0 1 5 o S B E 2 1 2 1 1 8 3 3 66 2 4 44 I T I L 3 3 2 2 4 2 3 4 4 4 2 1 I e 1 1 1 1 I 1 1 1 1 1 1 9 9 1 C c A n 0 0 0 0 0 0 0 0 0 0 0 0 0 0 F ) e 1 1 1 1 1 1 1 1 1 1 1 1 1 1 L d E H i x x x x x x x 0 0 0 0 00 x x x x x x x N I s 96 4 4 1 1 3 1 2 2 2 5 3 1 Y R e D ( R T 2 1 2 2 2 1 1 666 7 2 2 2 E 0 K 2 C 0 O / 2 3 1 1 3 2 3 3 3 3 I R T 1 1 1 1 1 1 I 1 1 1 I 668 y F L r 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O F a 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 5 d 1 Y 5 n x x x x x x x 0 00 0 0 0 x x x x x x x T u 3 7 5 3 3 3 1 1 2 6 66 6 E I o 1 L N B B I 1 61 1 1 7 7 3 3 3 3 5 5 5 A C T I V E 4 4 2 5 1 3 4 4 4 l T c 3 9 9 I H e 1 1 1 9 1 1 1 1 1 4 n 0 0 0 0 0 0 0 0 0 0' 0 0 0 N 0 e 1 1 1 1 1 1 1 1 1 1 1 1 1 I 1 d i x x x x x x x 0 0 0 0 0 0 x x x x 0 x x C g s I n e 0 1 64 2 43 5 5 5 4 4 4 L i R B d 63 62 6 2 7 1 1 1 2 2 2 U l P iu E B H 3 3 1 4 0 2 4 4 4 0 T o 1 1 1 9I 1 1 1 1 I 8 8 1 t y O o r 0 0 0 0 0 0 0 0 0 0 0 00 T S a 1 1 1 1 1 1 1 1 1 1 1 1 1 d E e n x x x x x x x 0 0 0 0 0 0 x x x x 0 x x S D u O o 5 3 9 96 0 0 0 0 2 0 0 0 D B 2 1 2 92 1 3 666 1 1 1 D E TA y y e M d - d s I of o o T B eb t d S e n v E d n w e ed e e d S o a o n l el l n e - M g r s i ot o a o t t r r e t h t h vi a n e O a c s Wi wit m e r m a e m u a yi l u y f t I r y m e qi d t a s a e r s s nL e a o v ed o s v o w n d u l ah i L d w ci aB ei m p h s t o i s y n s a e c nh t eR u j x t d s b s o r e e u n r al + i t r c s el q 1 E a a a g r e e n e m e c ml a a y e ot l a e / P n ed n y n vd l y r n o aI mP - f d c ot Y o r e uh oii ph d at mL e 0 eh oI 6 rG B R L T B L K S T A P S S UR r5 r W T S 52 i i iA A D 0 + xC$$b$ ( lllI l'

the air pathway only, the limits are 25 mrem /yr for whole body doses, and 75 mrem /yr for any organ doses. The RMDF boundary to the north of the facil-ity received an estimated " property line" exposure of.40 mrem for the year. s. However, this does not constitute a dose to the general public since it lies within an isolated area without direct public access. No members of the general public were present at the site boundary during any significant por-tion of the year. The maximum estimated internal and external exposures to an individual for 1988 at the De Soto and SSFL site boundaries and also at the nearest residence are shown in Table 12. Estimated internal radiation doses due to atmospheric emission of radioactive materials from De Soto and the SSFL nuclear facilities are several orders of magnitude below the radiation stan-dards and are far below doses from internal exposure to natural radioactivity in air. The external exposures, above background, are based on the greatest expo-sure adjusted to a constant altitude (1000-ft ASL) measured by a single dosi-meter compared with average adjusted off-site measurements. The mean adjusted value for five off-site dosimeters was 78 mR with a maximum annually obierved Q value for a single location of 88 mR. Boundary dose estimates assume 100%- occupancy, whereas the actual presence of persons at the boundary is rare or ~ nonexistent. These data indicate that the derived values, except for the RMDF, do not differ significantly from zero, as shown by the uncertainties being near the reported value, but result from assumptions in the analysis. The general population person-rem dose estimates are calculated from the demographic distribution and the sector total inhalation intake (person-pCi/ year) generated by AIRDOS-EPA. This code uses release rate, wind speed, wind direction and frequency, inversion, lapse, and effective stack height param-eters as input data. Population dose estimates centered on the SSFL site are presented in Table 13. Inhalation is the only potentially significant expo-sure pathway likely to exist. The doses reported for SSFL site emissions are summed for all release points and nuclides. 0256Y/ljm O RI/RD89-139 59

1ABLE 13 POPULATION DOSE ESIIMAILS FOR A1MOSPHERIC EMISSIONS FROM SSFL FACIL111ES -1988 22.S. Dose to Receptor Population Segment (person-rem) Oegree ~~ Sector 0-8 km 8-16 km 16-32 km 32-48 km 48-64 km 64-80 km Total N 6.6 x 10 1.8 x 10' 1.7 x 10 2.8 x 10~ 3.0 x 10~ 2.5 x 10 8.6 x 10 NNW 3.0 x 10 8.0 x 10~ 1.5 x 10~ 0 0 3.7 x 10' 3.2 x 10~ NW 7.8 x 10 0 4.4 x 10~ 0 S 6 x 10~ 1.2 x 10' 8.3 x 10~ WNW 1.1 x 10~ 1.5 x 10~ 9.G x 10 8.0 x 10' 8.0 x 10~ 0 1.4 x 10 W 0 6.7 x 10~ 2.2 x 10~ 3.2 x 10 1.2 x 10~ 0 1.3 x 10- -9 -6 -6 -1 -8 4 l W5W ?.4 x 10 2.9 x 10 2.3 x 10 3.0 x 10 S.6 x 10 0 S.6 x 10 l SW S.3 x 10 1.0 x 10 3.2 x 10~ 0 0 0 1.0 x 10 1 55W 7.6 x 10~ 7.3 x 10 2.3 x 10~ 0 0 0 1.7 x 10 6 5 3.0 x 10~ 1.5 x 10 3.1 x 10~ 0 0 0 1.8 x 10 SSE 1.0 x 10 1.4 x 10~ 3.4 x 10~ 0 0 0 1.4 x 10 l 8 -6 -6 -6 -S 4 -S SE 1.8 x 10 2.6 x 10 S.3 x 10 6.7 x 10 1.5 x 10 4.6 x 10 3.4 x 10 .6 -6 -6 -5 -5 -5 -5 f.SL 1.8 x 10 S.7 x 10 7.2 x 10 3.8 x 10 2.7 x 10 1.8 x 10 9.7 x 10 E 1.2 x 10' B.4 x 10 1.4 x 10 1.1 x 10 1.1 x 10' 7.0 x 10" 5.2 x 10 [NE 2.2 x 10' 2.4 x 10 6.1 x 10 7.6 x 10 8.9 x 10 1.1 x 10 9.5 x 10 NE 1.4 x 10 2.4 x 10 9.1 x 10~ 2.2 x 10' 7.2 x'10~ 7.2 x 10~ 2.1 x 10~ -6 NNE 3.1 x 10 ' 3.8 x 10 1.8 x 10 2.7 x 10 8.5 x 10~ 3.9 x 10~ 5.7 x 10~ lotal 3.7 x 10~ 2.7 x 10 4.4 x 10 6.2 x 10 S.4 x 10 3.1 x 10~ 2.5 x 10 Average individual dose 3.2 x 10 ran for the 80 km radius area total population. 0756Y/ljm 1 l RI/RD89-139 60

APPENDIX A COMPARISON OF ENVIRONMENTAL RADI0 ACTIVITY DATA FOR 1988 WITH PREVIOUS YEARS This~ section compares environmental monitoring results for the calendar year 1988 with previous annual data. The data presented in Tables A-1 through A-4 summarize past annual aver-age radioactivity concentrations. These data show the effects of both the short-lived and long-l';ved radioactive fallout from nuclear weapons tests and the 1986 Chernobyl accident superimposed on the natural radioactivity inherent in the various sample types. The data shown for gross alpha activity in samples that are generally-thick compared to the range of the alpha particles represent a marked change from earlier reports in the manner of calculating and reporting them. This change' reflects the gradual redirection of the monitoring program from moni-toring to measurement. Previously, alpha count data had been converted to alpha activity concentrations by using an efficiency factor for a thin electroplated source, and the results were monitored for changes from prior values. This resul'ted in artificially low numerical values for the alpha . activity in several sample media. Starting with the 1984 report-the alpha . activity concentrations for these media are reported based on an efficiency factor derived from a sample with distributed alpha activity that is thick relative to the alpha particle range. For monitoring purposes, this has no effect. However, the values reported more closely represent the actual alpha activity existing in the environment. In calculating the average concentra-tion values, all values, including negative values, are included. This method of uncensored data averaging, recommended by DOE /EP-0023, affords a better estimate of the central value and dispersion of the data. All limits of error reported in the tables are for one standard deviation (1 sigma). Usually, ( these show the dispersion.of the measured values about the mean. These two l changes in data interpretation result in noticeable differences in the data RI/RD89-139 61

shown in the historical comparisons. It must be recognized that these dif-ferences do not reflect changes in environmental radioactivity but merely result from the evolution of the monitoring program. Over the long period that the environmental program has been in opera-tion, 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 occurs in 1971. This increase, which is observed in both the on-site and the off-site samples, resulted from use of an improved counting system with a thinner sample configuration. The thinner sample increased the sensitivity of the detector to alpha-emitting radionuclides, which resulted in a higher j measured specific sample activity. Similarly, prior to 1971, tctal activity in ambient air was measured, combining both alpha and beta activity. In 1971, measurements were begun that allowed separate identification of these two types of radiation. In 1984, recalibration of the alpha counting method for thick samples was achieved, resulting in determination of the absolute alpha activity in these samples rather than the relative values previously used for monitoring purposes. Comparison of the values for 1988 as determined by the relative method with those for prior years shows no significant difference. In late 1985, a new automatic low-background gas flow proportional counting system was placed in operation for counting most environmental sam-ples. The new system was used for all sample types that were analyzed during 1988. Gamma spectroscopy is performed with a high-purity germanium detector (HPGe) coupled to a multichannel analyzer (MCA) with programmable radionuclides libraries and efficiency calibrations. O RI/RD89-139 62

TABLE A-1 SOIL RADI0 ACTIVITY DATA--1969 THROUGH 1988 On-site Average Off-site Average (pCi/g) (pCi/g) Number of Number of Year Samples Alpha Beta Samples Alpha Beta 1988* 48 29.1 26 48 25.6 24 1987* 48 27.1 25 48 25.7 24 1986* 48 26.7 26 48 25.1 25 1985* 144 25.2 24 48 26.3 24 1984* 144 25.8 24 48 26.2 23 1983 144 0.61 24 48 0.59 23 1982 144 0.69 25 48 0.68 23 1981 144 0.69 25 48 0.64 23 1980 144 0.60 24 48 0.58 23 1979 144 0.64 25 48 0.50 23 1978 144 0.63 24 48 0.51 24 1977 144 0.56 24 48 0.53 23 1976 144 0.56 25 48 0.56 24 1975 144 0.60 25 48 0.58 24 1974 144 0.60 25 48 0.54 24 1973 144 0.57 25 48 0.51 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

The change in alpha activity after 1983 is the result of an improved calibration method that provides a true measure of alpha activity in thick samples rather than the relative values used previously. This is discussed in detail in Section III, Part A.

Values for 1988 using the prior method would be 0.83 for the on-site average and 0.73 for the off-site average. 0256Y/ljm RI/RD89-139 63

l TABLE A-2 SSFL SITE SUPPLY HATER RADI0 ACTIVITY DATA-- 1969 THROUGH 1988 l Number of Average Alpha Average Beta Year Samples (10-9 pCi/ml) (10-9 pCi/ml) l 1988* 24 5.40 3.9 1987* 24 5.10 3.6 1986* 24 6.55 3.6 1985* 24 2.05 2.8 1984* 24 3.53 2.9 1983 24 0.12 3.0 1982 24 0.14 3.0 1981 24 0.24 2.8 1980 24 0.22 2.4 1979 24 0.23 2.8 1978 24 0.26 3.0 1977 24 0.25 2.5 1976 24 0.25 2.0 1975 24 0.24 2.3 1974 24 0.24 2.7 1973 24 0.26 3.4 1972 24 0.22 3.7 1971 24 0.28 4.9 1970 24 0.18 5.3 1969 24 0.11 5.0

The change in alpha activity after 1983 is the result of an improved calibration method that provides a true measure of alpha activity in thick samples rather than the relative values used previously. This is discussed in detail in Section III, Part A.

The value for 1988 using the prior method would be 0.38. 0256Y/ljm J RI/RD89-139 64

!.. O L E TABLE A-3 ROCKETDYNE DIVISION RETENTION POND RADI0 ACTIVITY DATA--1969 THROUGH 1988 o h l Interim Retention Final Retention Pond Pond Hater R-2A Hater 6 12 i Average Average Number (10-9 pCi/ml) Number (10-9 pC1/ml) of of Year Samples Alpha Beta Samples Alpha Beta 198B' 12 2.04 4.2 12 4.47 4.5 1987* 12 1.75 4.7 12 2 78 4.4 1986* 12 2.51 2.9 12 4.18 3.6 1985* 12 2.06 3.5 12 3.07 3.5 ~1984* 12 2,07 4.6 12 0.15 4.2 1983 12 0.12 3.6 12 0.13 4.4 1982 12 0.17 3.9 12 0.11 3.9 1981 12 <0.23 4.3 12 <0.25 5.2 1980 12 <0.22 2.9 12 <0.22 3.9 1979 12 <0.25 3.1 12 <0.23 4.5 1978 12 <0.25 4.3 12 <0.25 4.6 1977 12 <0.24 4.3 12 <0.25 5.2 1976 12 <0.24 4.3 12 <0.28 4.4 1975 12 <0.24 4.2 12 <0.31 4.5 1974 12 <0.22 4.2 12 <0.21 4.5 1973 12 <0.23 4.5 12 (0.37 5.6 1972 12 0.22 5.3 12 0.22 5.5 1971 12 0.18 6.2 12 0.16 6.4 1970 12 0.15 6.9 12 0.12 7.4 1969 12 0.07 5.9 11 0.10 5.7

The change in alpha activity after 1983 is the result of an improved calibration method that provides a true measure of alpha activity in thick samples rather than the relative' values used previously.. Values for 1988 using the prior method would be as follows:

Interim retention pond: 0.14 Final retention pond: 0.28 0256Y/1jm i RI/RDB9-139 1 I 65 \\ l

TABLE A-4 AM8IENT AIR RADI0 ACTIVITY CONCENTRATION DATA--1969 TH20VGH 1988 DeSo{oAverage SSFL Average (10- 2 pCi/ml) (10-12 pCi/ml) Number of Number of Year Samples Alpha Beta Samples Alpha Beta 1988 680 0.0024 0.034 2397 0.0020 0.031 1987 690 0.0019 0.027 2460 0.0019 0.027 1986 687 0.0029 0.058 2415 0.0028 0.061 1985 544 0.0026 0.044 2450 0.0020 0.040 1984 712 0.0019 0.027 2461 0.0014 0.024 1983 644 0.0024 0.026 2328 0.0010 0.023 1982 727 0.0017 0.026 2347 0.0013 0.022 1981 704 0.0069 0.12 2518 0.0068 0.12 1980 685 0.0065 0.039 2342 0.0064 0.035 1979 697 0.0066 0.021 2519 0.0065 0.020 1978 713 0.0084 0.091 2402 0.0072 0.088 1977 729 0.0066 0.17 2438 0.0066 0.17 1976 719 0.0067 0.096 2520 0.0065 0.11 1975 709 0.0063 0.076 2450 0.0060 0.073 1974 663 0.0056 0.16 2477 0.0057 0.16 1973 715 0.0075 0.041 2311 0.0072 0.038 1972 708 0.0085 0.14 2430 0.0086 0.14 1971* 730 0.0087 0.30 2476 0.0086 0.33 1970 668 0.34 2434 0.36 l i 1969 687 0.27 2364 0.26

Ambient air alpha radioactivity values were included in the beta values and not reported separately prior to 1971.

0256Y/ljm RI/RD89-139 66

The ' ambient radiation monitoring results show a continuing long-term variation that had been apparent in previous years but is unrelated to opera-r tions on-site. Independent measurements and intercomparisons support the' val-ues measured by the bulb-type dosimeters. With the exception of apparent L. changes resulting from improvements in analytical methods and interpretation of the data, the soil, vegetation, water, and air' radioactivity results are notably constant over the past 20 years. In particular, environmental radio-activity-data for De Soto show no reduction in the measured levels below those that had been observed during the fuel fabrication operations that were dis-continted in 1982 confirming that those levels represent natural radioactivity. For a11' types of samples, the data indicate that there is no concen-trated local source of unnatural radioactivity in the environment. Also, the similarity between on-site and off-site results further indicates that Rocket-dyne operations contribute essentially nothing to general environmental radioactivity. P A O RI/RD89-139 67

k-PENDIX B ENVIRONMENTAL MONITORING PROGRAM OUALITY CONTROL This appendix describes the quality assurance (QA) elements that are incorporated into the Rocketdyne progt to ensure that data produced are as meaningful as possible. PROCEDURES Procedures followed include: sample selection; sample collection; pack-aging, shipment, and handling of samples for off-site analysis; sample prepar-ation and analysis; the use of radioactive reference standards; calibration h.ethods and instrument QA; and data evaluation and reporting. RECORDS Records generally cover the following processes: field sample collection and laboratory ' identification coding; sample preparation method; radioactivity measurements (counting) of samples, instrument backgrounds, and analytical blanks; and data reduction and verification. Quality control records for laboratory counting systems include the results of measurements of radioactive check sources, calibration sources, backgrounds, and blanks, as well as a complete record of all maintenance and service. Records relating to overall laboratory performance include the results of analysis of quality control samples such as analytical duplicates, interlabor-atory cross-check samples and other quality control analyses; use of standard (radioactive) reference materials to prepare working standards; and calibra-tion of analytical balances. l RI/RD89-139 68

The following specific elements of quality control are used for the Rocketdyne program: 1) Reagent Quality -Reagent-grade chemicals and certified grade counting gas used. 2) Laboratory Ventilation--Room air supply is controlled to mini-mize temperature variance and dust incursion. 3) Laboratory Contamination--Periodic laboratory contamination surveys for fixed and removable surface contamination are per-formed. Areas are cleaned routinely and decontaminated when necessary. 4) Control Charts--Background and reference source control charts for counting equipment are maintained to evaluate stability and response characteristics. 5) Laboratory Intercomparisons--Rocketdyne partic' pates in the DOE-EHL-QAP, and in the DOE Environmental Dositc&ter Inter-comparison Project. 6) Duplicate Samples--Duplicate samples are obtained monthly at randomly selected environmental sampling locations. Analytical data are statistically evaluated to determine the correlation coefficients for each media type for the annual sample set. 7) Calibration Standards--Counting standard radioactivity values are traceable to the National Institute of Standards and Tech-nology primary standards. m 9 RI/RD89-139 69

~, APPENDIX C CALIFORNIA REGIONAL HATER QUALITY CONTROL BOARD CRITERIA FOR DISCHARGING NONRADI0 ACTIVE CONSTITUENTS FROM ROCKETDYNE DIVISION, SSFL l The discharge of an effluent in excess of the limits given in Table C-1 is prohibited. TABLE C-1 NPDES NO. CA00-01309, ORDER 84-85, EFFECTIVE 17 SEPTEMBER 1984 Discharge Rate Concentration Limit ' (ib/ day)a (mg/ liter) 30-Day Constituent Average Maximum Total dissolved solids 1,267,680 950 Chloride 200,160 150 Sulfate 400,320 300 b Suspended solids 66,720 b Settleable solids B00 26,690 30 5 Oil and grease 13,350 15 Chromium 6.67 Fluoride 1,340 1.0 Boron 1,340 1.0 Residual chlorine 0.1 Surfactants (as HBAS) 667 0.5 pH 6.0 to 9.0 a 6 Based on a total waste flow of 160 x 10 gal / day. Not applicable to discharges containing rainfall runoff during or imme-diately after periods of rainfall. E RI/RD89-139 70 _-________ _ L

ie'f APPENDIX D 1 8 BIBLIOGRAPHY - c, 1. DOE Order 5484.1, " Environmental Protection, Safety, and Health P otec-tion Information. Reporting Requirements" (7 January 1987) 2. DOE Order 5480.lA,'" Radiation Standards for Protection of the Public in the v'cinity of DOE Facilities" (3 September 1985) 3. 00E/EP-0023, "A Guide for: Environmental Radiological Surveillance at U.S. Department of Energy Installations" 4. Code of Federal Regulations, Title 10 Part 20 (10 CFR 20), " Standards for Protection Against Radiation" 5. California Radiation Control Reaulatioqi, California Administrative Code, Title 17, Public Health 6. California Regional. Water-Quality Control-Board, Los Angeles Region, Order No. 84-85, NPDES No. CA0001309 (Effective 17 September 1984) 7. R. E. Moore, 1979. "AIRDOS-EPA:.A Computerized Methodology for Estimat-ing Environmental Con;entrations and Doses to Man from Airborne Releases of. Radionuclides," ORNL-5532 8. AI-76-21, "En'tircamental Impact Assessment of Operations at Atomics International Under Special Nuclear Materials License No. SNM-21" (30 April 1976) 9. ESG-82-32 Supplement to AI-76-21, " Environmental Assessment of Opera-tions at Energy Systems Group of Rockwell International Under Special Nuclear Materials License SNM-21" (1982 Supplement to AI-76-21, 25 August 1982)

10. NUREG-1077, " Environmental Impact Appraisal for Renewal of Special Nuc-lear Material License No. SNM-21" (June 1984) 11.

U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, " Environmental Impact Appraisal of the Atomics International -(AI) Commercial Nuclear Fuel Fabrication Facilities Canoga Park and Chatsworth, California" (September 1977)

12. -ESG-DOE-13288, " Environmental Analysis of Decommissioned Facilities at Santa Susana Field Laboratory" 13.

J. D. Moore " Radiological Environmental Monitoring Program," N00105P000001, Rocketdyne Division, Rockwell International (9 July 1984) P, RI/RD89-139 1 71 A

14. J. D. Moore, " Radiological Environmental Monitoring Program Sampling Pro-cedures, Analysis Procedures, and Radioactivity Measurement Methods," N001DWP000008, Rocketdyne Division, Rockwell International (9 July 1984) 15. J. D. Moore, " Radiological Environmental Monitoring Program Quality Assurance," N001DWPC00009, Rocketdyne Division, Rockwell International (25 September 1984) 16. " Investigation of Hydrogeologic Conditions - Santa Susana Field'Labora-tory, Ventura County, California," Hargis & Associates, Inc., Tucson, Arizona (22 February 1985) 17. HASL-300, EML Procedures Manual 2nd Edition, Environmental Measurements Laboratory, U.S. Department of Energy

18. DOE /EH-0071, " Internal Dose Conversion Factors for Calculation of Dose to the Public," July 1988 C

RI/RD89-139 72

i APPENDIX E EXTERNAL DISTRIBUTION q Copies U.S. Department of Energy. EH-23 1 1000 Independence Avenue Washington, D.C. 20585 U.S. Department of Energy 1 Environmental Measurements Laboratory New York, NY 10014 County of Ventura 1 Fire Protection District l, Hazardous Material Section 395 Willis Avenue Camarillo, CA 93010-U.S. Environmental Protection Agency 1 Regional Radiat'lon Representative, Region IX 215 Fremont Street San Francisco, CA 94105 California State Department of Health Services 1 Radiologic Health Branch 714 "P" Street Sacramento, CA 95201 Los Angeles County Health Department i Occupational Health and Radiation Management Los Angeles, CA 90007 County of Ventura 1 Resource Management Agency Ventura, CA 93009 U.S. Department of Energy, ESQA 20 1333 Broadway Oakland, CA 94612 Rocky Flats Plant 1 Health, Safety, and Environment Golden, Colorado 80402-0464 Q u RI/RD89-139 73 ________________a

Copies California Regional Water Quality Control Board 1 Region 7 73-271 Highway ill, Suite 21 Palm Desert, CA 92260 U.S. Department of Energy 1 Office of Operational Safety, EP-?; Technical Information Center 1000 Independence Avenue Washington, D.C. 20585 U.S. Nuclear Regulatory Commission 3 Office for Analysis and Evaluation of Operational Data Washington, D.C. 20555 U.S. Nuclear Regulatory Commission 1 Office of Radiation. Safety and Safeguards Region V 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596-5368 California State Department of Health Services 1 Environmental Radiation Surveillance Unit 1449 West Temple Street, Room 222 Los Angeles, CA 90026 California State Department of Health Services 1 Toxic Substances Control Division Radiological Monitoring 2151 Berkeley Way, Annex 7 Berkeley, CA 94704 I i i o i RI/RD89-139 74 k.. S

APPENDIX F ALTERNATIVE UNITS FOR RADIOLOGICAL DATA Conversion In Non-SI In SI Factor From Units Units Non-SI to SI Unitsa Activity concentrations (envi-ronmental) 3 3 Airborne particulate and gas pCi/m Bq/m 3.70E 02 Liquids (water, milk, etc.) pCi/R Bq/2 3.70E - 02 Solids (soil, sediment, vegetation, foodstuff, etc.) pCi/g Bq/kg 3.70E - 05 Activity concentrations (effluent) Gas (air) (pCi/m2)b Bq/m 3.70E + 10 3 Liquid (pCi/m2)b Bq/A 3.70E + 07 Exposure rate (environment) R/h C/kg h 2.58E - 04 Absorbed dose _ mrad Gy 1.00E - 05 Dose equivalent mrem Sv 1.00E - 05 Dose equivalent rate (commitment) mrem / year Sv/ year 1.00E - 05 aTo convert non-SI units to SI units, multiply the non-SI units by the conversion factor. bAdopted because of established convention and use in maximum permissible concentration (MPC) tabulations. RI/RD89-139 75

APPENDIX G ADDITIONAL ENVIRONMENTAL INFORMATION This appendix presents additional information genera', y related to non-radiological environmental concerns for DOE operations on the governmen optioned land in Area IV at SSFL. In May 1988 a major environmental survey was conducted by a team of experts established by the DOE Office of Environment, Safety, and Health. This survey found iio environmental problems that represent an immediate threat to human life. A few areas were identified with possible contamination by hazardous or radioactive materials. The results of this survey are reported-in detail in DOE /EH/0EV-33-P, " Environmental Survey Preliminary Report--DOE Activities at Santa Susana Field Laboratories, Ventura County, California-- l February 1989." Steps to remedy the findings of this survey have been pro-l posed to DOE-SAN. i A groundwater monitoring program has been established at the SSFL site. ) This has been accomplished by the construction of a total of 82 on-site shal-low zone wells, sampling subsurface soils at over 150 locations, and routine i periodic sampling of groundwater from 49 shallow zone wells. Surface water j sampling has been done as aeded. These data have been summarized in numerous i reports. Shallow groundwater conditions do not occur in most of Area IV. Of eight shallow zone wells constructed in Area IV, groundwater was encountered consistently in only two wells. l A RCRA Part B permit application was submitted for sodium and similar waste material treatment at Building T/133. This application is under review l by the California Department of Health Services. Sodi"m combustion is contin-l uing under the existing permit with the concurrence of the Department of Health Services and the U.S. EPA. A release of sodium hydroxide solution from the sodium treatment facility was reported to the Department of Health Scr-d vices on Septem5er 23, 1988. Approximately 5 gal of a dilute solution of 9 RI/RD89-139 76 i l l c _ __ _ ____ _ ______________ _____________.____ _ j

sodiura hydroxide was released to the ground. Contaminated soil and associated hardware were recovered and disposed of as hazardous waste. A disdiarge exceedance occurred on September 22, 1988, from the R-2A retention pond. Monitoring indicated sulfate levels of 332 ppm, which exceeded Rocketdyne's NPDES discharge permit limit of b ppm. The high sul-fate level was attributed to operations at the Sodium Component Test Installa-tion (SCTI) in which blowdown water from cooling towers was concentrated up to four times the influent sulfate concentration due to evaporation. The plant shifted to water supplied by Ventura County District 17, which reduced the sulfate concentration to permitted levels. A major effort was begun in June 1988 to eliminate the risk of soil con-tamination by radioactive materials at Building T/059. This involved removal and disposal at a DOE radioactive waste disposal site of the activated sand and much of an activated vacuum duct in the Pipe Chase Room. Groundwater had leaked into this room and became contaminated. Out-leakape was prevented by pumping water out and evaporating the water at the RMDF. Sludge from the evaporation process was disposed at a DOE radioactive material disposal site. On August 3, 1988, ETEC operations were reviewed by an inspector from the Ventura County Air Pollution Control District. There were no adverse findings. A Spill Prevention and Control Countermeasure (SPCC) plan was started in 1988. The U.S EPA requires the preparation of an SPCC plan by those facili-ties which, because of their location, could rea.sonably be expected to dis-charge oil in harmful quantities into or upon navigable waters. The SPCC plan for SSFL facilities, including ETEC facilities, is currently under review for updating purposes by Rocketdyne Division. Additional comments provided by the Ventura County Health Department have been included into the plan and will be submitted to ine county by June 1989. An undergound storage tank program has been implemented at Rocketdyne o Division within the guidelines of California Assembly Bills 2013 and 1362 and under the direction of the State Water Resources Control Board. The bills RI/RD89-139 77

require all owners of underground tanks to register them with the Control Board and also requires the ank owners to install a leak detection system on all existing tanks. For the new tank installations, secondary containment of the tank and piping are' to be installed in addition to the leak detection sys-tem. Any underground tank abandonment requires a permit to remove and clear the tank and also to check the underlying soil for past leakage. The Ventbra County Environmental Health Department is the local regu' story agency respon-sible for enforcement of these requ',rements. A Rocketdyne procedure outlined in the Environmental Control Manual defines and assigns specific responsibilities relative to the use, storage, identification, transportation, handling, disposal, and inspection of sources of PCB bearing materials. The Rocketdyne PCB control program is based on the requirements of the U.S. EPA CFh Title'40, Part 61 regulations. Asbestos control at Rocketdyne is conducted under the requirements of Titles.29, 40, and 49 of the Code of Federal Regulations, in addition to any state or local regulations that apply to any asbestos abatement program. Several steps in managing an asbestos program have been incorporated into facility renovation and demolition. These generally include assessment or identification of asbestos-containing materials (ACM), abatement activities such as worker protection and surveillance, and clearance requirements such as cleanup and disposal. Within Area IV, approximately 75% of the buildings have been surveyed and materials in question have been analyzed for asbestos. Where required, asbestos abatement will occur when renovation or demolition projects are identified. C C RI/RD89-139 78

h j'ljo/J?9 U U&%g) " " ~ ~ !y)v '91 \\ t =, 4th b ' gngggzq j g USHRQ Rocketdyne Division g. \\ \\ ef ernational Corporation OCkWell j$T }3b3 T y l g % 198, ~. 6633 Canoga Avenue g InternadOn8 -[ SS* i m Ja Park, Califomia 91304 ~~ s-/ et ISW t" ggss 77 O gML SECHON Telex: 698478 Mu 8 on 000KEI M RoCKETDYN CNPK \\ g ru s w May 25, 1989 In reply refer to 89RC06668 Leland C. Rouse, Chief Fuel Cycle Safety Branch ~ ~ ' Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Application for Renewal of License No. SNM-21 Docket 70-25 issued to the Rocketdyne Division of Rockwell International Corporation

Reference:

1. NRC Letter, Leland C. Rouse to Attn: Dr. M.E. Remley, dated March 8, 1989. 2. RI Letter, M.E. Remley to Leland C. Rouse, " Application for Amendment to License _[ )/ No. SNM-21", dated December 19, 1988. sQ/

Dear Mr. Rouse:

The subject License, as revised by Amendment 2 (reference 1) expires June 30, 1989. In accordance with TITLE 10, Code of Federe.1 Regulations, Part 70, Section 70.33, we are submitting this application for a 10 year renewal not less than thirty days prior to expiration of the current license. Therefore, in accordance with this section, our current license shall not expire until the application for a renewal has been finally determined by the Commission. Environmental data and information to support the renewal application are provided as required by 10 CFR Part 51. In accordance with Section 170.31 of 10 CFR 170, we have enclosed our check for $150 to cover the application fee for the requested renewal. Six copies o the applicat' ion are provided as required by 10 CFR 70.21 (a) (2;. In accordance with the requirements of 10 CFR 70.22, we are submitting __ the f c11 swing--Ett~5Hments to the ---[--------* application: Lg __.__. Check No. Eh 7g_, _, j-g) nam;tter.. A mount.--

*" ~

Fee Category..- M - ------ gl{ Typt of ft* - fl}~I4 'f-- ~ l ~17 ~ ~ ~ \\ Dat Check Rcc'd. J-- 25545 O a ComNc c ---]_-] g g.QIOS f. Y.---- ~- 1

[ JL L r~N. Rockwell = v) International I ( 89RC06668 25 May, 1989 Page 2 ( A, Updated organization charts and resumes of key Rocketdyne secsonnel. (2) An updated Health and Safety Report containing supporting information for the application; ESG-82-33 revised May 19, 1989". " Health and Safety Sections for Renewal Application of the Special Nuclear Materials License SNM-21, Docket 70-25 issued to Rocketdyne Division of Rockwell International". This document follows the guidance in the " Standard Format and Content for the Health and Safety Sections of Renewal Applications for Uranium Fuel Fabrica. ion Plants". The portions that have been changed are noted by bars in the right hand margin. This document contains as appendices the 1988 Rockwell International Annual Report (A), the 1997 and 1988 Annual [] Environmental Monitoring and Facility Effluent Reports (B), ('j the Criticality Studies for Fuel Handling (C), and the 1986, 1987 and 1988 Annual Reviews of Radiological Controls (D). (3) Revised Material Controls

Report,

" Fundamental Material Controls for Special Nuclear Materials" RI/RD 86-190, April 15, 1989 issue. Changes are indicated by bars in the right hand margins. (4) A supplement to RI/RD B6-190 "Special Nuclear Material Control 1 program for Actinide Burner Program (TRUMP-S)" issued May 10, 1989. (5) Updated " Physical Security Plan for the Protection of Moderate Strategic Quantities of Special Nuclear Material at the Hot Laboratories of the Rocketdyne Division of Rockwell International ESG-80-17, May 19, 1989 issue. Changes are indicated by bars in the right hand margins. (6) A. supplement to the previously submitted env.ironmental assessments AI 76-21 and ESG-82-32, " Environmental Assessment of Operations at Rocketdyne Division of Rockwell International Under Special Nuclear Materials License No. SNM-21" RI/RD 89-180 issued May 19, 1989. O

1 I u..* JL i A Rockwell l l i International I - (,/ 89RC06668 25 May, 1989 -Page 3. (7) Updated '" Decontamination Plan for Rocketdyne Facilities Licensed Under Special Nuclear Material License SNM-21" AI-78-10, May 19, 1989 issue. As identified in the application, other materials have been included by reference, most notable of which is RI/RD 88-206 the "On-Site Radiological Contingency Plan for Rockwell International Operations Licensed Under Special Nuclear Material License No. SNM-21". This application for renewal does not include any increase in the scope of licensed activities. The possession limits have not been changed except to clarify that the renewed license should cover only up to, but not including, formula quantities of U-235 and Pu. If you have any questions or require additional information please call me at-(818) 718-3462. ['N Very truly yours, -rf R. T. Lancet, Director Nuclear Safety and Licensing Enclosures - 1. License Renewal Application (6 copies)

2. Check in the Amount of $150.00 1

o O _ _ - _ - _ - _ - _ _ _ _ _ _ _ _ - _ _ _ _ _}}

ML20236E510

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ML20236E510

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Dear Mr. Rouse:

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