ML20009B008

Environ Rept for Facility

ML20009B008
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	05/12/1981
From:	DAMES & MOORE
To:
Shared Package
ML20009B005	List: ML20009B004 ML20009B008
References
ENVR-810630, NUDOCS 8107140648
Download: ML20009B008 (24)

Text

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RFRR&

l ENVIRONMENTAL REPORT FOR THE j AFRRI-TRIGA REACTOR  !

FACILITY LICENSE R-84 .

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PREPARED BY DAMES AND MOORE, l

ENGINEER CONSULTANTS FOR DEFENS. JUCLEAH AGENCY ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE BETHESDA, MARYLAND 20014 D ADO O O O C PDR

O ENVIRONMENTAL REPORT FOR THE AFRRI-TRIGA REACTOR Submitted to:

The Armed Forces Radiobiology Research Institute National Naval Medical Center Bethesda, Maryland l

Submitted by:

DAMES & MOORE 7101 Wisconsin Avenue Suite 700 Bethesda, Maryland 20014 I

l l May 12,1981 l

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o Note: This Environmental Report is submitted in addition to the EnvironmentalImpact Appraisal Data already provided. Extensive reference must also be made to the Safety Analysis Report dated 12 May 1981.

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. CONTENTS

1.0 INTRODUCTION

1 2.0 ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE 1 2.1 AFRRI SITE 1 2.2 AFRRICOMPLEX 1 2.3 AFRRI REACTOR FACILITY 2 2.4 AFRRI-TRIGA MARK-F REACTOR 3 3.0 ENVIRONMENTAL EFFECTS OF AFRR1 REACTOR FACILITY 4 3.1 THERMAL EFFLUENTS 4 3.2 RADIOACTIVE GASEOUS EFFLUENTS 4 3.3 7 LIQUID RADIOACTIVE WASTES 3.4 SOLID RADIOACTIVE WASTES 7 3.5 ENVIRONMENTAL SAMPLING 8 4.0 ENVIRONMENTAL EFFECTS OF ACCIDENTS 8 4.1 UNAVOIDABLE EFFECTS OF FACILITY

CONSTRUCTION AND OPERATION 8 4.2 LONG-TERM EFFECTS OF FACILITY CONSTRUCTION AND OPERATION 8 l

4.3 COST AND BENEFITS OF FACILITY AND ALTERNATIVES 8 REFERENCES 9 l

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. LIST OF TABLES f

Table M 1 Summary of Gaseous Radioeffluent,1 Jan 71 to 30 June 80: Total Release--Radionuclide(s) 10 2 Dose Assessment Based Upon Annual Radionuclide Release 11 3 Personnel Monitoring 12 4 Collective Doses (REM-Person) from 1973 through 1978 13 5 Inplant Thermoluminescent Dosimeters 14 6 Low Background Film Dosimeter 15 7 Environmental Surveillance Perimeter Monitoring Results (Film Dosimeters)in Unrestricted Areas 16 8 Environmental Film Daimeters: 1971-1980 Summary 17 9 Liquid Radioactive Waste 18 10 Solid Radioactive Waste 19 11

. ENVIRONMENTAL REPORT FOR THE ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE TRIGA MARK-F REACTOR

1.0 INTRODUCTION

As required by the National Environmental Policy Act of 1969 (NEPA), the U.S. Nuclear Regulatory Commission must consider environmental aspects of proposed Commission actions. This Environmental Report has been prepared in accordance with 10 CFR Part 51 to aid the Commission in complying with NEPA in connection with the Commission's licensing activities. This Environmental Report is part of the application for NRC relicensing of Facility License No. R-84 for the Armed Forces Radiobiology Research Institute (AFRRI) TRIGA Mr rk-F research reactor as required by 20 CFR Part 50.30. The Environmental Report considers the environmental effects that can be attributed to the operation of the TRIGA Mark-F reactor as well as other pertinent areas.

2.0 ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE AFRRI is a tri-service military organization under the Defense Nuclear Agency. The mission of AFRRI is to conduct scientific research in the field of radiobiology and related radiation cesearch essential to the support of the Department of Defense (DOD).

2.1 AFRRI SITE l- The AFRRI site is located on the grounds of the National Naval Medical Center, Bethesda, Maryland. The Medical Center is located approximately 3 miles north of the Washington, D.C.-Maryland line. The AFRRI site is located on a moderate slope, declining northward toward a narrow creek valley. The terrain l

' surrounding AFRRI is rolling with elevations ranging from 230 to 320 feet above

! sea level.

2.2 AFRRI COMPLEX The AFRRI complex includes six separate primary buildings arranged in an interconnected complex. The principal radiation facilities housed within AFRRI i are the TRIGA reactor facility, the 50-Mev electron linear accelerator facility,

. the 500-KCi Cobalt-60 facility, and the Standards Laboratory, which contains a f 1 L

. theratron and X-ray unit. In addition to these facilities, AFRRI also houses research laboratories, a hot cell, a radiochemistry lab, an animal clinical research facility, office space, and related support areas.

2.3 AFRRI REACTOR FACILITY The reactor facility, which includes the AFRRI-TRIGA Mark-F reactor and its associated equipment, is housed in a single building of reinforced concrete. This building is one of two separate buidings that are designated as Building #42. A description of the reactor building may be found in the Final Safety Analysis Report.I There are no exterior conduits, pipelines, electrical or mechanical structures, or transmission lines attached to the reactor building other than utility service facilities which are similar to those required for the rest of the AFRR1 complex.

These utility service facilities are similar to those required by other research laboratories.

The reactor building venti.ation system is independent of the ventilation systems serving the rest of the AFRRI complex. Ambient air enters the reactor building through two air supply fans. The air circulates through the reactor

, building, passes through roughing and absolute filters, and is subsequently exhaust-ed to the atmosphere via the AFRRI stack. The ventilation filters provide removal of particulate matter greater thm 0.3 microns in diameter and are maintained at a minimum efficiency of 99.9 perceat. The AFRRI stack releases the air exhausted from the reactor building ventilation system as well as from other ventilation emission systems in the AFRRI complex. The stack release point is approximately 35 feet above the roof of the reactor building and a minimum of 18 feet above the highest building in the AFRRI complex. The reactor building and ventilation system are further described in the FSAR.

Heat dissipation for the AFRRI-TRIGA reactor is accomplished by the reactor water coolant systems. These systems include the primary cooling system, the secondary cooling system (with a 1.5 MW(t) heat exchanger and wet mechanical draft cooling tower), a water makeup system for the primary cooling system, and a water purification system for the primary cooling system. The cooling towers are located on the roof of the AFRRI complex. The towers, with total dimensions of approximately 18 x 32 x 19 feet, are similar to cooling towers assoc.ated with the air conditioning systems of large office buildings. Makeup water for the secondary 2

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. cooling system consists of raw industrial water which is readily available from the local water system. The reactor water systems are described further in the FSAR.I Although no radioactive wastes are generated during normal reactor opera-tions, a liquid waste disposal system is available as a means of controlling the release of radioactive liquid waste from the AFRRI complex to the peblic sanitary sewer system. The liquid radioactive waste is divided into three categories: "very hot," " hot," and " warm." The "very hot" radioactive waste is usually too highly radioactive to be diluted and discharged into the sanitary sewer, hence it must be shipped out in a tank truck for disposal at an NRC-licensed burial ground. The

" hot" liquid radioactive waste subsystem collects effluents from the areas at AFRRI in which high level radioactive activation or coritamination may occur.-

Finally, the " warm" liquid radioactive waste subsystem collects effluents from those areas in AFR'll in which low-level radiaactive activation or contamination may occur. All three liquid radioactive waste systems utilize holdup tanks. The liquid radioactive viaste subsystems are further described in the FSAR.I l

2.4 AFRRI-TRIGA MARK-F REA'CTOR The AFRRI-TRIGA Mark-F Reactor, originally developed and installed by the General Atomics Division of the General Dynamics Corporation, is utilized for biomedical research and radioisotope production in support of AFRRI's radiobiology research mission, as well as irradiations of electrical components for DOD systems.

In addition, when scheduling permits, other out-of-house experiments are occasionally performed. For example, in the past, the AFRRI reacto has been used in support of Federal criminal investigations for the FBI, studies to character-ize transient radiation effects on electronics for Harry Diamond Laboratory and Westinghouse under DOD contract, and artifact analysis for th<: Smithsonian Institute and National Gallery of Art."

The principal experimental facilities associated with the AFRRI-TRIGA l

reactor are Exposure Room 1, Exposure Room 2, the Pneumatic Transfer System, l

j and the In-Core Experiment Tube (CET). Experiment; may also be conducted in j the reactor tank (with or without beam tubes), but these facilities or modes are not normally used. The AFRRI-TRIGA reactor and its associated exposure facilities are further described in the Final Safety Analysis Report.I l

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. The AFRRI reactor operates at steady state power levels up to : MW (thermal) and in a pulsing mode with step reactivity insertions up to a maximum of 2.8% Ak/k.3 Operation of the reactor will generally never exceed a 5-day week, 8-hour day, or about 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> per year." Based on historical data," the total reactor burnup has been less than 400.2 MW-hr for the period June 1964 to October 1980. Historical data" also indicate that the average annual burnup, since 1968 is 26.5 MW-hr/yr, while the average based upon cumulative burnup since 1967 is 30.77 MW-hr/yr. Using the standard 5-day work week, 8-hour day, and burnup rates suggested for a standard 40-hour work week, on the average, 15.44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> / week is allocated for operative runtime in support of approved experiments, 9.16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> / week allocated for setup time in support of approved experiment runs, 11.44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> / week allocated for maintenance, and approximately 3.96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> / week for training, administrWn, etc."

3.0 ENVIRONMENTAL EFFECTS OF AFRRI REACTOR FACILITY 3.1 THERMAL EFFLUENTS The AFRRI Reactor operates at a maximum' thermal power output of 1 MW in the steady state mode. The environmental effects of thermal effluents created at this power level are negligible. During prolonged operations at the upper range of l power levels, the secondary cooling system is activated and the waste heat is rejected to the atmosphere through the facility's mechanical draf t wet cooling tower, located on the roof cf the AFRRI complex. The efficiency of this cooling I

tower is largely determined by the temperature and humidity of the outside air. In l June 1980, the tower was enclosed and the H2 O supply was chemically treated to reduce losses. The tower now operates much like a condensor, with only nominal H O losses of approximately 50 gallons per week or about 2,600 gallons per year.

2 Prior to June 1980, H O losses were in the order of 125 to 250 gallons per week or 2

about 6,500-13,000 gallons per year.2 As of June 1980, fog plumes are essentially

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nonexistent, and prior to that date, plumes were evident but not extensive. The FSARI includes more information about the AFRRI reactor cooling system and thermal effluents.

3.2 RADIOACTIVE GASEOUS EFFLUENTS l

Gaseous radioactive effluents released by AFRRI from the reactor and other j

AFRRI facility operations must conform to the requirements of 10 CFR Parts 20.101 through 20.106.

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. Radioactive gaseous effluents released due to AFRRI facility operations include: N 16 and Ar"I, generatN by the AFRRI-TRIGA Mark-F reactor, and released to the environment from the reactor building ventilation system through the AFRRI stack; N I3 and O I3 generated as a result of the 50 MeV electron linear accelerator (LINAC); and 1 125 and Xe I33 generated as a result of operations in the radioisotope and nuclear medicine laboratories.

Table 1 presents a summary of the gaseous radionuclides released on an annual basis from January 1,1971, to June 30, 1980, while Table 2 presents the results of dose assessment calculations obtained via the annual radionuclide releases given in Table 1. Xe I33 and 1 125 environmental doses are less than 10 percent of the Ar"I, NI3,and OI3 doses2 , and hence were not evaluated in great detail (Table 2). For more information, see the FSAR.I The maximum permissible annual dose for all radioactive gaseous effluents released to unrestricted areas which could be occupied by individuals is 500 milliroentgens (mR) for gamma radiation as specified in 10 CFR Part 20. However, every effort should be made to maintain radiation exposures and releases of radioactive materials to unrestricted areas to levels that are as low as is reasonably achievable (ALARA). Design objectives for nuclear " power" reactors have been established in 10 CFR Part 50, Appendix I, to meet ALARA. The AFRRI dose assessments for Ar"I, which makes up the majority of AFRRI's gaseous radioactive effluents, are a factor of three below the design objective of 10 mR/ year for gamma radiation given in Appendix I of 10 CFR Part 50.I'3 The radiation monitoring systems associated with reactor operations at AFRRI are provided and maintained as a means of ensuring compliance with radiation limits established under 10 CFR Part 20. The AFRRI monitoring systems consist of remote area monitors (RAM's), continuous air monitors (CAM's), cooling l

water monitors, AFRRI perimeter monitors, personnel moaltors, and stack gas and

! particulate monitors. The RAM's, placed in various areas of the reactor building utilize scintillation detectors which measure gamma radiation. The CAM's utilized j

in the reactor room, exposure rooms, and prep area provide continuous air sampling and monitoring (gross beta-gamma activity) primarily of airborne particulate matter. The stack particulate and gas monitoring systems measure the -

gamma activity emitted by radioactive particulates and the activity of gases a f, radioactive nuclides, respectively, that are exhausted through the AFRRI stack.

Perimeter monitoring at AFRRI consists of a large number of stations, each 5

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. equipped with a thermoluminescent dosimeter (TLD) which detects X-ray and gamma radiation. AFRRI personnel and visitors are assigned personal dosimeters which assess whole body, extremity, and internal doses. The radiation monitoring systems utilized by AFRRI are discussed in greater detail in Section 3.6 of the Safety Analysis Report.I Table 3 lists the annual summary from 1971-1979, of the highest radiation doses received by individuals at the AFRRI reactor facility. The highest exposure (whole body, extremity, or internal) received by any individual is well below the limits specified in 10 CFR Part 20.101. Table 4 lists data tabulated for collective doses (person-rem) from 1973 thruugh 1978. Given the active civilian and noncivilian population of AFRRI, the collective individual doses are well below the permissible dose leve'.s specified in 10 CFR Part 20.101.

A survey of in-plant,thermoluminescent dosimeters (Table 5) and low background film dosimveYs (Table 6), for specific locations within the AFRRI reactor room and facilities, indicate that the net dose and high total readings are in compliance with 10 CFR Part 20.101. Perimeter monitoring results (film dosimeters) in unrestricted areas from 1971 to 1979 (Table 7) show that the radiation field caused by the AFRRI-TRIGA Mark-F Reactor is negligible relative to the allowable exposures given in 10 CFR Part 20.105. A summary of environ-

. mental film dosimetry data representing possible reactor-produced radioeffluent doses to the environment from 1971 to 1980 is given in Table 8. Even with individual dosimeter uncertainties of 8 millirem, the readings are well below the allowable doses given in 10 CFR Part 20.105.

During 1 M"/(t) steady state operatien, the gamma radiation levels directly above the reactor pool and at the reactor pool chain were measured to be 200 mR/hr and 14 mR/h espectively.I The amount of N 16 released to the 16 environment is negligible due to the time involved for N bubbles generated in core to reach the surface of the reactor pool (#42 seconds) and the time involved in transporting air from the reactor room to the exhaust stack (#3-4 minutes) relative to the rapid decay (7.14 second half-life) of N16, Ar0I, the gaseous ei!!uent of primary concern released through the AFRRI stack to the environment, was measured to be slightly less than 19 Curies during all of calendar year 1979. This amount of Ar 4I was larger than the toil Ar 4I release during any year since 1971 (see Table 1). Tnis maximum in annual Ar"I release totals was due to the number of reactor operations and the types of experiments performed during 1979. Based on the present experimental facility operational 6

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- configuration and anticipated acactor use, it is expected that the total amount of Ar"I released during any year will be no more than that released during 1979 (#20 Curies)I and certainly no more than twice that released during 1979 (#40 Curies).

Based on this conservative value of 40 Curies of Ar 01 released in one year, the maximum integrated air dose in an unrestricted area would be 1.9 millirads for the entire year.I Similarly, the consequences from the Design Basis Accidents of a fuel element drop accident or a fuel clad failure accident were determined te be minimal.I The maximum calculated whole-body dose was less than 2 mrad beyond 25 meters from the AFRRI facility.2 The maximum calculated thyroid dose was less than 57 mrad beyond 25 meters from the AFRRI facility.2 Doses from these postulated accidrats to individuals beyond the boundary of the National Naval Medical Center site would be significantly less than 1 mrad.2 These calculated doses are wer. below the permissible levels given in 10 CFR Part 20.106, and hence the operation of the AFRRI reactor would not represent an undue risk to the health and safety of the operational personnel or the general public.

3.3 LIQUID RADIOACTIVE WASTES Although thera are no liquid radioactive wastes generated by normal reactor operations, a liquid radioactive waste handling and disposal system is provided for temporary holding, primarily to provide a means of controlling the release of radioactive liquid wastes from the AFRRI complex to the public sanitary sewer system. Table 9 lists the total amount of radioactivity released to the sanitary sewer sysum from 1971 to 1979. The amounts of gross alpha, beta, and gamma activities released are within the requirements c 10 CFR Part 20, Section 20.303.

I See the FSAR for more information.

3.4 SOLID RADIOACTIVE WASTES Low-level solid radioactive wastes from reactor operations (1971-1980),

including laboratory wastes such as glassware, paper, plastics, scintillation vials, disposable gloves, and radioactive animal ccreasses, constitute a volume of one to five 55-gallon drums with less than 1 mci per year, containing essentially all short-liveJ, radionuclides (i.e., Na24, Mn N , Cu64),3 Reactor demineralizer resins and particulate filters are changed at intervals of 6 to 18 months, and are disposed of as solid waste. Typical activities observed in these materials are given in Table 10.

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. 3.5 ENVIRONMENTAL SAMPLING

, Environmental samples are taken quarterly of water, soll, and vegetation.

All sample results have been below action levels specified in AFRRI Health Physics Procedure 2-5 and, in fact, generally are indistinguishable from normal environ-mental background activity levels.0 4.0 ENVIRONMENTAL EFFECTS OF ACCIDENTS Accidents ranging from failure of experiments to the largest core damage and fission product release considered plausible would result in doses of only a small fraction of 10 CFR Part 20 guidelines and are considered negligible with respect to the environment. (See Chapter 6.0 of the FSAR.I) 4.1 UNAVOIDABLE EFFECTS OF FACILITY CONSTRUCTION AND OPERATION The unavoidable effects of construction and operation involve the materials used in construction that cannot be recovered and the fissionable material used in the reactor. No adverse impact on the environment is expected from either of the unavoidable effects.

4.2 LONG-TERM EFFECTS OF FACILITY CONSTRUCTION AND OPERATION

. The long-term effects of a research facility such as AFRRI are considered to be beneficial through contributions to scientific and medical knowledge. This is especially true in view of the relatively low capital cost involved and the minimal impact on the environment associated with such facilities.

4.3 COST AND BENEFITS OF FACILITY AND ALTERNATIVES The value of the AFRRI reactor, associated equipment, and the console, together with all other instrumentation and maintenance tools and supplies, is estimated at $3 million (1972-year dollars)." The benefits of this facility are in the field of biomedical research in support of national defense. The facility provides additional data and findings in the scientific and medical fields for international use. Some of the activities conducted at the AFRRI reactor facility could be accomplished using particle accelerators or other radioactive sources; however, these alternatives are more costly and less efficient, and cannet totally replace the existing capabilities associated with this facility. There is no reasonable alterna-tive to the AFRRI reactor for conducting the broad spectrum of research conducted.

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. REFERENCES

1. AFRRI Reactor Facility Safety Analysis Report, May 1981.

1. Ibid., Chapter 6, " Safety Analysis."

3. Amendment #17 to the Technical Specification, Facility License No. R-84 for AFRRI-TRIGA Mark-F Reactor, Docket No. 50-170.

4. Maj. Ronald R. Smoker, U.S.A., Personal Communcation, " Environmental Impact Analyses," February 13,1981.

5. AFRRI Environmentai impact Appraisal Data; Defense Nuclear Agency, Armed Forces Radiobiological Research Institute, Bethesda, Maryland.

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a TABLE 1 Summary of Gaseous Radioeffluent,1 Jan 71 to 30 June 80:

Total Release--Radionuclide(s)

Ar-41 N-13,0-15 1-125 Xe-133 Source of Activity: Reactor LINAC Other Other Released activity (mci): 1971 26,900 1,460 0 0

" " 1972 11,040 3,760 <1 120

" " 1973 11,310 3,850 0 1,380

" " l'//4 16,690 20,740 0 40

" " li '5 7,190 20,180 <1 340

" " 1976 2,750 1,040 0 2,100

" " 1977 2,370 640 <1 1,590

" " 1978 9,410 15,840 <1 340

" " 1979 18,930 0 <1 1,280 t

" a 1980(hy) 1,940 5 <1 260 e

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. TABLE 2 Dose Assessment Based Upon Annual Radionuclide Release Radio-nuclide 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 i

Ar-41 Ci/s: 8.5E-7 3.5E- 7 3.6E-7 5.3E-7 2.3E-7 8.7 E-8 7.5E-8 3.0E-7 6.0E-7 1.2E-7 Ar-41 mR/h: 3.5E-6 1.4E-6 1.5E-6 2.2E-6 9.3E-7 3.6E-7 3.l E-7 1.2E-6 2.5E-6 5.lE-7 Ar-41 mrem: 0.031 0.012 0.013 0.019 0.008 0.003 0.003 0.011 0.022 .002 N,0 Ci/s: 4.6E-8 1.2 E-7 1.2 E-7 6.5E-7 6.4 E-7 3.3E-8 2.0E-8 5.0E-7 0 1.6E-10 N,0 mR/h: 2.0E-7 5.2E-7 5.2 E-7 2.8E-6 2.8 E-6 1.4E-7 8.6E-8 2.2 E-6 0 7.E-10 N,0 mrem: 0.002 0.005 0.005 0.024 0.024 0.002 0.001 0.019 0 10-5

TABLE 3 Personnel Monitoring Annual Highest Exposure Interr.al Sun mary Whole Body Extremity Thyroid (Year) Dose (mrem) (mrem) 1-125 (nCi) 1971 1,644 -- --

1973 2,261 -- --

1975 568 -- --

1977 473 -- --

1978 384 7,038 30 1979 127 3,779 38 l

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a TABLE 4 Collective Doses (REM-Person) from 1973 through 1978 (1) Rad Physics Division Year Total Dose (REM-Person) 1973 .042 1974 .337 1975 .344 1976 .733 1977 .852 1978 .972 (2) Nuclear Medicine Division Year Total Dose (REM-Person) 1973 11.433

- 1974 8.324 1975 2.248 1976 1.653

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1977 .970 1978 1.775 (3) Sources Division Year Total Dose (REM-Person) 1973 .691 1974 .244 1975 .970 1976 .078 1977 .248 1978 .677 13

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TABLE 5 Inplant Thermoluminescent Dosimeters

, Net Dose (Background subtracted)

Year Location" (mrem) 1978 B1 30 3201 20 1124 20 1979 Area 1101 52 1

l "See Section 3 of AFRRI Reactor Safety Analysis Report for location description.

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TABLE 6 Low Background Film Dosimeter High Total Year Readings Year Location (mrem) 1978 PN (north end of reactor pool) 170 Kl (KLYSTRONS) 271 K2 (Modulator Building) 168 NMI (Gamma Camera, Room 1491) 450 NMB (Hood Radiopharn.scy, Room 1411) 690 a

1979 Reactor Building 926 b

Nuclear Medicine 1,723 c

Modulator Building 196 I

• North end of reactor pool, reflects large activation workload, b

Wall of 1413, adjacent to generator storage.

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! Extrapolated to outside high dose of 13 mrem.

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TABLE 7 Environmental Surveillance Perimeter Monitoring Results (Film Dosimeters) in Unrestricted Areas Total Yearly Annual Maximum Average Doses Summary Net Yearly per Station a

(Year) Location Dose (mrem) (mrem) 1971 (Co-4) 26 1.4 1973 Co-4 13 1.67 1975 (8- A) 14 2.44 1977 ID 14 3.3 1978 ID 10 1.5

- 1979 -- 13" 5.I b "See Section 3.0 of AFRRI Reactor Safety Analysis Report lor locations of peri-meter monitors.

b Resulted primarily from a number of high (6 to 8 millirem) readings in one seven-week exposure period; did not correlate with reactor use patterns and appeared to be an artifact.

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TABLE 8 Environmental Film Dosimeters: 1971-1980 Summary (all doses in millirem):

Year Envir. Dosimeter Avg.* Highest Dosimeter Reading

• 1971 1.4 8 1972 7.7 16 1973 1.7 12 1974 2.2 10 1975 2.4 14 1976 0.3 13 1977 3.3 20 1978 1.5 30 r

1979 5.1 9 1980(hy) -2.5

• All are net readings, with background station doses (!oc.:.ted miles from AFRRI) subtracted. Individual dosimeter readings have 2a uncertainties of 8 millirem.

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. TAbtE 9 Liquid Radioactive Waste Total Radioactivity Released To Sanitary Sewage System Gross Beta Gross Alpha Gross Gamma Tritium Year Total mci mci mci mci 1971 -- 143.6 i2.8 5.4 i1.1 -- --

1973 <0.004 ci 87 el 828 2.5 1975 <l.2 147.9 3.7 0.81 i l.7 -956 524 --

millicuries 1977 <4 millicuries -- -- -- --

, 1978 <33 millicuries 595.4 11.9 1.11 i1.46 3,188 463 --

(70% by USUHS) ,

1979 90 millicuries 829 19 0.7 0.8 2,850 1,290 --

including USUHS i

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__ ._=--. - - . _ _ - _ _ - . _ - . - .. - - _ ... - . . - . . . - .- . . . . . . . - . ..

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, .-- TABLE 10 Solid Radioactive Waste 1

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! Total Radioactivity -

Shipped i Year (millicuries activity) j 1971 150

. 1973 93.7 1

1975 155.4 1977 S'4. 5 1978 615 I 1979 237.8 4

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