Text

Vol I to Savannah River Plant Environ Annual Rept for 1987
	ML20154C330
Person / Time
Site:	Vogtle
Issue date:	12/31/1987
From:	Burckhalter L, Mikol S, Todd J; E.I. DU PONT DE NEMOURS & CO., INC.
To:	;
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FRACTIONS AND MULTIPLES OF UNITS Decimal Multiple Equivalent Prefix Symbol 10' 1,000,000 mega-M 8

10 1,000 kilo-k 10' 100 hecto-h 10 10 deka-da 10" 0.1 deci-d 10

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m 3.28 ft ml 1.61 km km 0.G21 mi Ib 0.4536 kg kg 2.205 lb liq qt - U.S.

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m' 10.764 ft' mi' 2.59 km km' O.386 mi' 2

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mci /mi' O.386 mCLknf(nCi/nf) mCLkm' 2.59 mCl/mi' d/m 0.450 pCi pCl 2.22 6m nCi 1 x 10' pCl pCi 1 x 10'*

nCl d/mt 0.45x10*

pCVcc pCVcc 2.22 x 10' d/mt i

d/mit' O.01256 mci /mi' mCVmi' 79.6-

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Cl/cc(air) pCi/cc(air) 10

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'1 mCLkm' DISCLAIMER This report was prepared as an account of work sponsored by an agency c' onited States Government. Neither the United States Government nor any agency t'

.or any of their i

employees, makes any warranty, express or implied, or assur

< legal liability or responsibility for the accuracy, completeness, or usefulness of enformation, apparatus, product, or process disclosed, or represents that its uss woule infringe privately owned rights. Reference herein to any specific commercial product, c-ss, or service by the trade name, trademark, manufacturer, or otherwise, does not nec

ly constitute or imply its endorsement, recommendation, or favoring by the United St

'3 oven ment or any agency thereof. The views and opinions of authors expressed herei not ecessarily state or i

reflect those of the United States Government or any agency ths. sr.

l

DPSPU-88-30-1 Volume I Text U.S. DEPARTMENT OF ENERGY SAVANNAH RIVER PLANT ENVIRONMENTAL REPORT Annual Report for 1987 By Sue C. Mikol Laurie T. Burckhalter James L. Todd i

Donna K. Martin Prepared for the United States Department of Energy by the IIcalth Protection Department of E. I. du Pont de Nemours & Co.

Savannah River Plant, Aiken, South Carolina

ACKNOWLEDGMENTS The authors acknowledge with appreciation the efforts of a number ofindividuals and groups who contributed technical data and reviewed the draft report. The authors express gratitude to the following groups:

Environmental Monitoring Group, IIealth Protection Department, SRP Environment and Energy Department, SRP Power Technology Departmem, SRP Custodians of Groundwater Monitoring Sites Environmental Sciences Division, SRL Environmental Transport Division, SRL Savannah River Ecology Laboratory Savannah River Forest Station Department of Energy Academy of Natural Sciences of Philadelphia The authors arc indebted to the following individuals who were instrumentalin the preparation and review of the report:

S. P. Boynton C. L. Cummins E. M. Heath J. D. HefTner R. L. Kump W. L. Marter A. S. Morrison W. M. Fay, Exploration'Sof1 ware M. R. Rainer, Exploration Software M. A. Ilarper, Exploration Software J. E. Till, Radiological Assessments Corporation G. G. Killough, Radiological Assessments Corporation j

Special thanks go to R. A. Childers, Information Industries, Inc., for editing and preparing the copy for publication and to the Publications Group at SRP.

1

Contents Contents.

......i Abbreviations and Acronyms.

.. v Abstract................

.. vii Preface..

..... ix Executive Summary..............................

........ x i 1.

Introduction and Program Overview.....

........1 S U M M A RY......................

.....1 DESCRIPTION OF TIIE SRP SITE AND FACILITIES..

.... 1 OVERVIEW OF ENVIRONMENTAL PROGRAMS.

..4 Environmental Monitoring and Regulatory Compliance.....

..4 Environmental Research.

.................6 PROGRAM REVIEWS.

.6 External Review of Nonradiological Monitoring Program....

.6 DOE-Headquarters Environmental Survey......

..7 Environmental Advisory Committee.........

...7 1987 HIGHLIGHTS.

..8 2.

Air Monitoring Program......

.9 SU MM ARY..............

.9 RADIOACTIVE MONITORING..

....... 9 Atmospheric Emissions...

........9 Summary of 1987 Atmospheric Releases and Concentrations................. 14 Offsite Radiation Doses from Atmospheric Releases.......

.15 Environmenta1 Gamma Radiation.......

... 15 NONRADIOACTIVE MONITORING....

.......... 17 Atmospheric Emissions.

.17 Ambient Air Quality...

. 18 1987 HIGHLIGHTS...

.. 19 3.

Surface Water Monitoring Program.........

..........21 S U M M ARY.................

..........21 RADIOACTIVE MONITORING.

........ 21 Savannah River.......

...... 21 SRP Streams............

........ 2 3 Seepage Basins.........

.26 Inventory of Tritium Released........................

...... 2 8 Summary of 1987 Liquid Releases and Concentrations...

...............30 OrTsite Radiation Doses From Liquid Releases.......

..........................31 NONRADIOACTIVE MONITORING.............................

... 32 Liquid Efiluent Monitoring (NPDES)..

...32 Savr.nnah Riyer....

............ 3 3 Academy of Natural Sciences of Philadelphia River Qus!ity Surveys............34 SRP Streams.

............ 3 6 River and Stream Temperature Surveys............

............................36 19 8 7 H IG H LI G H T S.......................................................

....... 3 8 i

[il

l l

l I

4.

Groundwater Monitoring Program.......

...........................39 SU M M ARY..................

....... 3 9 1

...w...................

DESCRIPTION OF h1ONITORING PROGRAh!..................

39 CHANGES IN TIIE PROORAh! DURING 1987...........

...................39 I IYD RO G E O LO GY AT S RP................................................................... 4 0 i

RADIOACTIVE MONITORING.

.. 41 Applicable Stan dard s.......................................

.. 41 Se p a ratio n s Ar e a s..................

....................41 i

Reaetor Areas..........

...............45 General Areas...........

.........................................,............49 0ther Sites...

....................................................50 NONRADIOACTIVE AfONITORING.....

... 50 Applicable Standards.............

...........................50 S e pa ra ti o n s Area s.............................................

.50 Reactor Arsas...............

.......................53 General Areas.....

......... 55 Other Sites...............

..........................................................57 1987 HIGHLIGHTS.........................

........ 5 8 5.

Food and Drinking Water.........

... 59 S U MM ARY..............

.................................................................59 RAD 10 ACTIVE MONITORING.....

... 59 M ilk.................

......... 5 9 Food.........................................

..................................59 Drinking Water.........

.60 NONRADIOACTIVE MONITO RING............................................... 61 Drinking Water......

.................61 1987 HIGHLIGHTS.

.....................................................63 6.

Wildlife Mo ni to ri n g.............................................................. 65 SUMM ARY.......

... 65 RADIO ACTIVE M ONITORING............................................................ 65 i

Fi sh an d S ea food...................................................................... 65 D e e r an d I I o gs..................................................................

...........67 Furbearers...

......................69 Ducks.........................................

............................,..............69 Turties....

................................70 NONRADIOACTIVE MONITORING........................

....... 7 0 Fi sh................

..................................................70 D e e r....................

................................................70 1987 HIGHLIGHTS..

...........71 7.

Rainwa ter, Soll, Sediment, and Vegetation.................................. 73 SUMM ARY..........

... 73 RADIO ACTIVE M ONITO RING.................................................................. 73 Rain water..............

............. 7 3 Soil...............................

.........................................................74 j

Sedim ent..............

...................................................75 Vegeta tion......................................................................................75 198 7 H IGH LIG HTS..................................

..............................77

[..j i

J

8.

Special Surveys / Unusual Occurrences..................................... 79 S U M M A RY....................

......... 7 9 RAD 10 LO GICAL S U RVEYS......................................

.....................79 Tritium in th e E n ron m e n t.................................................................... 7 9 Tritium Releases.....

................................80 Other Radionuclide Iuleases.

........ 8 2 Special Study of Tritium Concentrations in Drinking Water....

............82 hieasurements ofI.129 in Groundwater and Surface Water......

.................82 Savannah River Swamp Survey....

............. 8 3 Special Creek Plantation Weh Survey..........

.,... 84 Low. Level Gamma Analysis of River Water......................

.....................84 Comprehensive Surveys at the Beaufort. Jasper and Port Wentworth Water Tr*

'lants.......

............ 84 Special 2 e Radon Study................

.......................................88 Environte

.ta Exchan ge.................

............. 8 9 Special Fe

.e Creek S urvey.....................

. 89 Surveys Monitoring Wells in Separations Areas Waste Managen a Facilities..........

........................90 NONRADJOuOGICAL SURVEYS..

....... 90 Monitoring for Pesticides, Herbicides, and Polychlorinated Biphenyls.......... 9 0 S p ill s..............................

......... 91 1987 H I GHLI GHTS......................-.........

........................91 9.

Methods for Calculating Offsite Radiation Doses................ 93

SUMMARY

..................................................................................93 DEFINITION OF RADIATION DOSE COMMITMENT.....

.....................93 APPLICADLE DOSE STANDARDS..

. 94 INTE RNAL DO S E FACTORS................................................

...............94 Organ.S pecific D o se Faeto rs....................................................

...... 9 4 Efrective Dose Equivalent...........

.....................95 RELATIVE EFFECTS OF DIFFERENT CHEMICAL FORMS OF TRITIUM IN TH E ATM OS PH ERE.............................................................. 95 CALCULATIONAL MODEIE.....

.. 95 Modeling the Dispersion of Radioactive Releases to the Atmosphere........... 96 Modeling the Dilution and Transport of Radioactivity Released to Surrounding Streams.

........................98 1987 HIGHLIGHTS.......

...... 99

10. Sample Collection and Analytical Procedures.................. 101

SUMMARY

.101 INTRODUCTION....................

............ 101 RADIOLOGICAL PROCEDURES.....................

...... 102 NONRADIOLOGICAL PROCEDURES.,..

....... 107 19 8 7 H I G H LI G HT S.................................................

.................. 110

11. Data Analysis and Quality Assurance......................................111

SUMMARY

....... 111 INTRO D U CTI O N............................................................................ 1 11 LOWER LIMITS OF DETECTION (LLDS) OF RADIOACTIVITY.......................111

[iii)

QUALITY CONTROL OF RADIOLOGICAL MONITORING PROGRAMS...........113 QUALITY CONTROL OF NONRADIOLOGICAL MONITORING PROGRAMS..

................................................................114 Amblent Air Quality...............

...................................114 Liquid Efilue n ts.................................................................................... 114 S tre am and Rive r Wate r Q uality................................................................ 114 G roun d w a te r...........................................

...............................117 INTERNAL REVIEW OF SRP QA/QC PROGRAMS....

........ 118 1 9 8 7 H I G H LI G HT S......................................... >............................................ 1 19

12. Environmental Management and Research Programs........... 121

SUMMARY

.121 SAVANNAH RIVER PLANT ENVIRONMENTAL MANAGEMENT PROGRAMS...

............ 121 Environmental Implementation Plan..................

..........................121 Environmental Audits and Appraisals........

.121 Responses to Superfund Amendments and Reauthorization Act, Title III.......

.. 122 Operations Under Hazardous Waste RCRA Part B Permit..............

..122 Environmental Awarenessffraining Programs..................

..122 Preparation of NEPA Documentation for SRP/SRL Activities..............

.123 Preparation of Environmental Impact Statements....

..... 123 SRL ENVIRONMENTALMANAGEMENT AND RESEARCH PROGRAMS..........

.......................123 Special Studies for Determining the Dispersion and Efrect of SRP Pollutants......

........ 123 Activities to Aid Compliance with Pollution Abatement Regulations............

........... 12 7 Activities to Meet Permit or Environmental Impact Statement Requiremen ts................

..............................................................129 Waste Management and Groundwater Protection....

...........................131 NATIONAL ENVIRONMENTAL RESEARCH PARK PROGRAM...................134 SAVANNAH RIVER ECOLOGY LABORATORY PROGRAMS............................135 Division of B iogeochemical Ecology.................................................

..... 135 Division of Stress and Wildlife Ecology........................

....... 136 Division of Wetlands Ecology......

................................................... 140 U. S. FOREST SERVICE SAVANNAH RIVER FOREST STATION PROGRAMS..

.......................142 Fore st Ma n a ge m e n t............................................................... 14 2 Forest Management Research......

......... 14 4 1987 HIGHLIGHTS.......

........................145 References........

.........................151 G l o s s a ry..............................

.155 Appendix A: Listing of Environmental Monitoring Reports....................157 Appendix B: Groundwater Monitoring Sites.......................................... 161 Appendix C: Environmental Permits, Orders and Notices.......................173

[iv)

ABBREVIATIONS AND ACRONYVIS ACWS Alternate Cooling Water System IGB Indian Grave Branch ANSP Academy of Natural Sciences of IT International Technology Corporation Philadelphia ITAS IT Analytical Services APHA American Public Health Association LANDSAT Land Resources Observatory Satellite BDC Beaver Dam Creek LEPC local emergency planning commission BG Burial Ground LETF Liquid Elliuent Treatment Facility BP biomass production LLD lower limit of detection BWHP Backwash Holding Pond LSC liquid scintillation counter CAAC Clean Air Act Code L3R Lower Three Runs Creek CCWS Comprehensive Cooling Water Study MCL maximum contaminant level CERCLA Comprehensive Environmental MDC Minimum Detectable Concentration Response, Compensation and Liability MSDS Material Safety Data Sheet Act (Superfund)

MSS multispectral scanner CL confidence level MTP Memorandum-to-File CSRA Central Savannah River Area NBS National Bureau of Standards DCG Derived Concentration Guide NCRP National Council on Radiation DEL deleted version Protection and Measurements DM Dry Monitoring (Wells)

NEPA National Environmental Policy Act DOE Department of Energy NERP National Environmental Research DWPF Defense Waste Processing Facility Park EA Environmental Assessment NESHAPS National Emission Standards for ECS Environmental and Chemical Services Hazardous Air Pollutants E&E Environment and Energy Department NPDES National Pollutant Discharge (SRP)

Elimination System EEI Envirodyne Engineers, Inc.

NRC Nuclear Regulatory Commission EID environmental information document PB Pen Branch EIP Environmental Implementation Plan PCB polychlorinated biphenyl EIS Environmental Impact Statement PHA pulse height analysis EML Environmental Measurements POC point-of-compliance Laboratory (DOE)

QA quality assurance EOC Emergency Operating Center QAD Quality Assurance Division (EPA)

EPA Environmental Protection Agency QAP Quality Assessment Program (DOE)

ETF Efiluent Treatment Facility QC quality control ETI Environmental Testing, Inc.

RCRA Resource Conservation and ETP Efiluent Treatment Plant Recovery Act FDA Food and Drug Administration RFI RCRA facility investigation FEIS Final Environmental Impact RWHP Raw Water Holding Pond Statement SARA Superfund Amendments and FMC Four Mile Creek Reauthorization Act GDNR Georgia Department of Natural SBL stable boundary layer Resources SCB standing crop biomass GIS Geographie Information System SCCP South Carolina Coastal Plain HEP Habitat Evaluation Procedures SCDHEC South Carolina Department of Health HP Health Protection Department (SRP) and Environmental Control HPGe high purity germanium SEFES Southeastern Forest HQ Headquarters (DOE)

Experiment Station ICRP International Commission on SMCC Subsurface Microbiological Culture Radiological Protection Collection IDMS isotope dilution mass spectrometric SREL Savannah River Ecology Laboratory (v]

SRFS Savannah River Forest Station SRL Savannah River Laboratory SRP Savannah River Plant STABLE Stable Atmospheric Boundary Layer Experiment SWMU solid waste management unit TB Tims Branch TLD thermoluminescent dosimeter TRAC Tracking Radioactive Atmosphere Contaminants TSP total suspended particulates TSS total suspended solids TRU transuranic USFS U. S. Forest Service USFWS U. S. Fish and Wildlife Service USGS U. S. Geological Survey U3R Upper Three Runs Creek VOC volatile organic compound WCAL Weather Center Analysis Laboratory WIND Weather Information and Display WSCTF Waste Site Closure Task Force

[vi]

ARSTRACT In 1987, as in previous years, the radiological These radiation doses from SRP operations are impact of Savannah River Plant operations on small when compared to the dose from natural public health was insignificant. The maximum radiation, which averages 295 mrem (2.95 mSv) radiation dose commitment to a hypothetical per year [NCRP87]. The largest part of this individual on the SRP boundary from 1987 SRP natural dose is 200 mrem (2.00 mSv) from natural atmospheric releases of radioactive materials was radon gas in homes. The maximum dose from SRP 0.6 millirem (mrem)(0.006 mSv). To obtain the atmospheric releases of 0.6 mrem is only 0.2% of maximum dose, an individual would have had to the average annual dose from natural radiation.

reside on the SRP boundary at the location of highest dose for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day,365 days per This 1987 report contains monitoring data from year.The average radiation dose commitment to routine radiological and nonradiological environ-the hypothetical individual on the SRP boundary mental surveillance activities, summaries of envi-was 0.3 mrem (0.003 mSv).

ronmental protection programs in progress, a summary of National Environmental Policy Act The maximum radiation dose commitment to an (NEPA) activities, and a listing of environmental individual downriver of SRP who consumed permits issued by regulatory agencies and their Savannah River water was 0.1 mrem at both the status. The environmental surveillance activities Cherokee Hill water treatment plant at Port at and in the vicinity of SRP comprise one of the Wentworth, GA (near Savannah) and the most comprehensive and extensive environmental Beaufort-Jasper water treatment plant near monitoring programs in the United States.

Beaufort, SC. This assumes the individual drinks two liters (approximately one half gallon) of water each day,365 days per year.

[vii)

PREFACE The purpose of this report is to provide informa-activities were published and issued to the public, tion to the public about the impact of SRP opera-was initiated in 1959. Dual reporting of SRP tions on the public and the environment. This environmental monitoring activities continued report, U. S. Department of Energy Savannah until 1985 when data from both onsite and offsite River Plant Environmental Report for 1987, surveillance programs were merged into a single describes environmental surveillance and moni-publication. In 1985, the report expanded to two toring activities conducted at and around the volumes. A listing of past onsite and offsite Savannah River Plant (SRP) during the calendar reports is presented in Appendix A.

year 1987. The SRP Environmental Report is published annually and is widely distributed to The scope of the environmental monitoring government officials, U. S. Congressmen, universi-program at SRP has increased significantly ties, and other interested parties. Copies of the during the years since plant startup. The change report are placed in public reading rooms. Prepa-is reflected in annual reports. Prior to the mid-ration and publication of the report is mandated 1970s, the reports contained primarily radiologi-by Order DOE 5484.1, with a publication deadline cal monitoring data. Beginning in the mid-1970s, of May of the following year.

the reports included increased amounts of nonra-diological monitoring data as those programs The objectives of this report are to:

increased. The nonradiological monitoring pro-gram is now as extensive as the radiological i

+ provide detailed information about the SRP monitoring program.

site and environmental monitoring activities,

+ report 1987 monitoring data for the SRP and Volume I of the report summarizes environmental surrounding environs, surveillance and monitoring activities at SRP and

+ provide radiation dose estimates for contains key figures and summary tables. Volume surrounding populations and describe how II contains figures (maps and diagrams) and the estimates are derived, detailed monitoring data tables.

+ summarize all significant environmental activities at SRP in one report, Previous reports were categorized by radioactive

+ provide a historical document for reference and nonradioactive monitoring with subdivisions and trending, by media (air, water, etc.). The format of the 1987

+ show trend analyses, when possible, to report has been reversed: monitoring programs indicate increases and decreases in are presented first by media type and then subdi.

concentrations and/or discharges, vided by type of monitoring.

Ensuring the radiation safety of the public in the The 1987 report is written for a broad audience j

vicinity of SRP was a foremost consideration in with a variety of environmental interests. Readers I

the design of the plant and has continued to be a may selectively read different sections of the primary objective during the 33 years of SRP op-report according to their specific interests. The erations. An extensive environmental surveillance abstract gives an overall picture of what the program has been maintained continuously since report contains, while the executive summary i

1951 (before SRP startup) to determine the provides a short digest of the entire report. A brief concentrations of radionuclides in the environ-summary is presented at the beginning of each ment of the plant. Data generated by the onsite chapter, and highlights appear at the end of the surveillance program have been recorded in SRP chapter. More detailed information is found in the documents since 1951. A public report,in which chapters.

data from offsite environmental monitoring

[ix]

1 EXECUTIVE

SUMMARY

The environmental surveillance activities at and this report, the individual's lifetime is assumed to in the vicinity of the Savannah River Plant extend 50 years beyond the time of exposure.

comprise one of the most comprehensive and extensive environmental monitoring programs in The terms, dose and dose commitment, are some-the United States. This 1987 report contains times used interchangeably in this report. The monitoring data from routine radiological and dose commitment to an individual is usually nonradiological environmental surveillance expressed in units of millirem (abbreviated activities, summaries of environmental protection "mrem") or millisievert (abbreviated "mSv")

programs in progress, a summary of National (1 mrem = 1/1000 rem; 1 mSv = 1/1000 Sv; Environmental Policy Act (NEPA) activities, and a 1 Sv = 100 rem).

listing of environmental permits issued by regula-tory agencies and their status. The report consists Population dose commitment is the sum ofindivid-of two volumes. Text, major figures, and summary ual dose commitments in a population group and data tables are presented in Volume I; Volume II is expressed in units of person. rem (person-is comprised of figures and comprehensive data sievert). For example,if each person in a popula-tables. The purpose of this report is to provide tion of 1,000 receives a dose commitment of 1 rem information to the public about the impact of SRP (0.01 Sv), the population dose commitment would operations on the public and the environment.

be 1,000 person. rem (10 person Sv).

SRP occupies a large area of approximately 300 Applicable Dose Standards square miles along the Savannah River, princi-pally in Aiken and Barnwell Counties of South The DOE radiation standards for the protection of Carolina. SRP's primary function is the produc-the public in the vicinity of SRP are given in tion of plutonium, tritium, and other special Order DOE 5480.1 A. These standards are based nuclear materials for national defense, for other on recommendations of the International Commis-governmental uses, and for some civilian pur-sion on Radiological Protection (ICRP) and the poses. SRP is operated for the Department of National Council on Radiation Protection and Energy (DOE) by E. I. du Pont de Nemours & Co.

Measurements (NCRP).

In 1985, a draft DOE order was issued that ASSESSMENT OF RADIOLOGICAL IMPACT contained revised interim standards incorporating OF SRP OPERATIONS ON TIIE PUBLIC the recommendations and dose models contained in ICRP Publications 26 and 30 (ICRP77, Radiation Dose Tenns ICRP79]. (The previous standards had been based on ICRP Publications 2 and 10 [ICRP59, ICRP68].

As used in this report, the term dose normally The previous guides were based on a maximum means "effective dose equivalent." It is defined by annual dose of 500 mrem (5 mSv) to an ofis*te the International Commission on Radiological individual. The draft DOE order changed tha Protection [ICRP77, ICRP791 as "the sum of the maximum allowable ofTsite dose to 100 mrem (1 external dose equivalent plus the committed dose mSv). The revised interim standards, which also equivalents to specific organs of the body, times a include Environmental Protection Agency (EPA) weighting factor appropriate for each organ." The limits for the atmospheric pathways contained in term dose commitment, as it is applied to an 40 CFR 61, Subpart II [ EPA 85}, are given in Table individual, means

committed efTective dose ES-1 p. xii.

equivalent," which is a measure of the amount of radiation dose received by the individual over a EPA drinking water standards which apply at lifetime as a result of exposure to all radiation downriver water treatment plants are based on an pathways during the year being considered. In annual whole body dose of 4 mrem (0.04 mSv)

[xi)

Table ES-1. DOE Revised Interim Radiation Dose Limits All Pathways. The effective dose equivalent for any member of the public from all routine DOE opera-tions* (natural background and medical exposures excluded) shall not exceed the values given below:

Effective dose equivalent

mrem / year (mSv/ year)

Occasional annual exposures 500 (5)

Prolonged period of exposure

100 (1)

No individual organ shall receive a committed dose equivalent of 5 rem / year (50 mSv/ year) or greater.

1 Air Pathway Only (Limits of 40 CFR 61, Subpart H)

Dose equivalent mrem / year (mSv/ year)

Whole body dose 25 (0.25)

Any organ 75 (0.75)

Liquid Pathway Only (Limits of 40 CFR 141 [ Drinking Water])

Dose equivalent mrem / year (mSv/ year)

Whole body dose 4

(0.04)

"Routine DOE operations

means normal planned operations and does not include additional planned or unplanne~d releases.

EfTective dose equivalent is expressed in rem (or mrem) with the corresponding value in Sv (or mSv)in parentheses.

For the purpose of these standards, a prolonged exposure is one that lasts, or is predicted to last, longer than 5 years.

from the annual consumption of two liters of mechanisms for atmospheric and liquid releases water per day [ EPA 75, EPA 87]. Periodically in this and known major pathways of exposure to man.

l report, radioactivity concentrations are compared Environmental measurements of tritium oxide with EPA drinking water standard concentra.

released from production areas in small quantities tions. While this is a convenient reference, it are used to verify atmospheric dispersion in the should be noted that the current EPA standard transport models [Ma841.

concentrations for tritium (20,000 pCi/L) and "Sr (8 pCi/L) correspond to a whole body dose less Dose Commitment from than 4 mrem. EPA is considering a change to Atmospheric Releases these concentrations to reflect the actual 4 mrem dose [ EPA 86].

The maximum radiation dose commitment to a hypothetical individual on the SRP boundary from Calculational Models 1987 SRP atmospheric releases of radioactive materials was 0.6 mrem (0.006 mSv). The 0.6 With few exceptions, most of the radioactive mrem (0.006 mSv) is 0.6% of the DOE guide of 100 materials released from SRP are of such low mrem /yr (1 mSv) for a prolonged exposure to an concentrations that when dispersed in the envi.

individualin the public zone. The assumptions ronment they are not detectable by conventional used in calculating the maximum public zone dose monitoring procedures. Therefore, radiation doses commitment are conservative; that is, they tend to to offbite populations are calculated with overestimate the dose commitment. Therefore,it mathematical models that use known transport is very lilrely that the actual maximum individual

[xii]

O

dose commitment was less than 0.6 mrem (0.006 The Cherokee Hill water treatment plant at Port mSv). This maximum individual dose commitment Wentworth, GA (near Savannah) provides water from SRP operations was approximately 0.2% of for industrial and manufacturing purposes. The the average dose of 295 mrem (2.95 mSv) per year 20,000 consumers of this water are primarily received in the vicinity of SRP from natural adults working in industrial facilities. The radiation. The radiation dose commitment to the Beaufort-Jasper Counties, SC, water treatment average individual at the plant perimeter was 0.3 plant provides water to 50,000 consumers of all mrem (0.003 mSv), which is 0.1% of the average ages living in Beaufort and Jasper Counties, SC.

dose of 295 mrem (2.95 mSv) from natural radia-Approximately 94% of the radiation dose at the tion sources.

water treatment plants from SRP operations is due to tritium.

The population dose commitment from SRP atmospheric releases to the 555,100 people who The radiation dose commitment to an individual live within 50 miles (80 km) of the center of the downriver of SRP who consumed Savannah River plant was 29 person rem (0.29 person Sv) with an water at a maximum rate of two liters a day was average dose of 0.00005 rem (0.0000005 Sv) per 0.1 mrem (0.001 mSv) at both the Cherokee Hill person. During 1987, this same population re-water treatment plant at Port Wentworth, GA, ceived an estimated annual radiation dose of and the Beaufort-Jasper water treatment plant.

164,000 person rem from natural radiation and an The dose commitment for an individual consum-additional dose of 29,400 person rem from medical ing the water at an average rate of one liter per procedures. Most of the natural radiation dose day was 0.05 mrem (0.0005 mSv) for Beaufort-comes from radon in homes. The individual Jasper and 0.06 mrem (0.0006 mSv) for Port radiation dose from natural radioactivity, medical Wentworth, procedures, and consumer products averages 360 mrem per person, which is 7200 times the dose The dose commitment to a hypothetical individual from SRP operations.

who could receive the highest offsite doses from releases of radioactivity from SRP to the Savan-Releases of tritium account for ~50% of the ofTsite nah River was 0.9 mrem (0.009 mSv). This maxi-population dose from SRP atmospherie releases.

mum individual would consume an average Tritium from SRP is released in two forms to the amount of water and a large amount of fish from atmosphere. The HT or elemental gas form is not the riverjust downriver from SRP and would also readily absorbed in the human body while the spend many hours in shoreline activities, swim-HTO or oxide form (tritiated water)is readily ming, and boating. This dose commitment of 0.9 assimilated. The dose from the elemental form is mrem is only 0.3% of the annual dose commitment therefore significantly less than from the oxide of 295 mrem (2.95 mSv) received from natural form. (The dose per unit ofintake is 25,000 times radiation sources.

less for elemental tritium than for tritium oxide.)

The population dose commitment from liquid Before 1985, all tritium released from SRP to the releases in 1987 was 6 person-rem (0.06 person-atmosphere was considered to be in the oxide form Sv). The dose commitments from the water because the methodology to distinguish between consumption pathway (Beaufort-Jasper and Port the two forms had not been perfected to the extent Wentworth) occur to discrete population groups; that reliable continuous measurements could be however, the dose commitments from other made. Techniques to measure the two forms of exposure path ways (i.e., fish and shellfish con-tritium were perfected in 1985. Measurements of sumption and recreational activities) occur to a the forms of tritium in 1987 showed that approxi-diffuse population that cannot be described as mately 54% of the tritum released to the atmos-being in a specific geographical location.

phere from SRP was in the elemental form.

Perspective Dose Commitment from Liquid Releases These radiation doses from SRP operations are Consumption of water from the two water treat-small when compared to the dose from natural ment plants on the Savannah River below SRP radiation, which averages 295 mrem (2.95 mSv) also contributes to the offsite dose commitment.

per year [NCRP87al. The largest part of this

[xiiil

natural dose is 200 mrem (2.00 mSv) from natural commitment from SRP releases (29 person-rem radon gas in homes. The maximum dose from SRP from atmospheric releases and 6 person-rem from atmospheric releases of 0.6 mrem (0.006 mSv)is liquid releases)is compared with annual popula-only 0.2% of the average dose from natural radia-tion dose from natural and medical sources in tion. Fig. ES-1 below graphically shows the Table ES-2. Even though the SRP contribution to sources of an individual's radiation dose, the per-population dose commitment is very small(0.02%

centage each source contributes, and SRP's of that from natural sources), SRP has a continu-maximum atmospheric contribution from releases.

ing program to improve operating techniques and Table ES-2 (shown as ES-1 in Volume II) summa-to develop new technology directed toward reduc-rizes the individual and population doses from ing releases of radioactive materials to the SRP and from other sources.

environment.

The popciation dose commitment (person rem)

The radiation dose the public receives from from SRP releases can be compared with the nuclear operations at SRP can be viewed from population doses from natural radioactivity (cos-several perspectives. From the viewpoint of mic radiation, terrestrial radioactivity, internal regulatory standards, the maximum radiation radioactivity, and radon in homes) and medical dose to consumers of water treated by the Port radiation exposure. The 1987 population dose Wentworth and Beaufort-Jasper water treatment otna sources SRP Contributon 12 =em

-, f o e mwn s

)

O

~

sa m an x~

Natural

~

295 m em Fig ES 1. Sources of radiation dose vs. SItI"s contribution

[xiv]

Table ES 2. INDMDUAL AND POPULATION DOSES - 1987 Calculated Calculated Individual Population Population dose, Location / Source Dose. mrema Ez.g cerson-rem

SRP Boundarv Averaoe Maximum SRP Atmospheric Releases 0.26 0.65*

SRP Liquid Releases 0.93*

Within 80 km of SRP Dose From Atmospheric Releases 0.058 555,100 29.3 Water Treatment Plants Downstream of SRP Using Water From Beaufort-Jasper Treatment Plant 0.05 0.11 51,000 2.5 Using Water From Port Wentworth Treatment Plant 0.06 0.11 20,000 1.1 River Fish atx1 Recreation Consuming River Fish 555,100 2.3 Recreation 555,100

<0.1 SRP Releases Total 35.3 Other Sources Annual Dose mrem Poo. Dose. Derson-rem Natural Radicadivitva Cosmic Radiation 27 Extemal Terrestrial 28 Internal Terrestrial 40 Radon in Homes 200 555,100(within 80km) 164,000 71,000(water plants) 20,900 Subtotal (Naturafi 295 185,000 Medical Radiation

53 555,100(within 80km) 29,400 71,000(water plants) 3,800 Subtetal(Medicaf) 53 33,200 Consumer Products 10 555,100 (within 80km) 5,600 71,000 (water plants) 700 Subtetal(Consumer Products) 10 6,300 Weapons Test Fallout

<1.0 555,000(within 80km) 600 71,000(water plants) 100 Subtotal (Weapons Tests)

<1.0 700 Other

< 1.0 555,000 (within 80km) 600 71,000 (water plants) 100 Subtotal (Other)

<1.0 700 Other Sources Total 360 225,000

Committed effectiw dose equivalent

Based on a hypotheucal individual with maximum dietary habits located on the phnt perimeter at locations of highest exposure. No such indmdualis luiown to exist

Based on a hypothetical indivdual with maximum dietary habits who Eyes on the shore of the Savannah River. No such individual is known to exist.

Based on atmospheric dspersion of SRP releases as desenbod in Table 2-2 (Vol. II).

Average values for the United States.

' Dose is prorated over the U. S. population. This is a means of arriving at an average dose, wNch when multiplied by the population size, produces an estimate of population exposure. It does not mean that enry member of the population receiwd a radabon exposure from these sources.

Not applicable.

[xvJ

plants was 2.5% of the EPA standard. In compari-Statistical errors are not presented with data son to the EPA standard pertaining to atmos-shown in Volume I but are included in the com-pheric releases, the maximum individual dose at prehensive data tables in Volume II.

the SRP perimeter was 2.4% of the EPA limit.

Compared to the exposure from natural radiation Air Monitoring (average is about 300 mrem / year in the SRP area),

the dose contributed by SRP operations is mini-Extensive monitoring for radioactivity in air is seule. Even the variation in the natural radiation performed at six onplant stations,13 plant pe-dose in this area far exceeds the maximum ofTsite rimeter stations,12 stations at the 25-mile radius dose resulting from the Savannah River Plant. In of SRP, and four stations at the 100-mile radius.

the context of the recommendations of the Na-The small amount of particulate alpha and beta-tional Committee on Radiation Protection gamma radioactivity released to the atmosphere

[NCRP 87b], any radiation dose less than 1 mrem from SRP facilities is generally obscured in the (0.01 mSv) per year is so low that further efTort to area surrounding SRP by worldwide fallout.

reduce radiation exposure to the individualis Tritium, the only radionuclide of plant origin i

unwarranted.

routinely detected in offsite air, showed a decreas-ing trend with distance from the site. The average OVERVIEW OF 1987 tritium concentration at the plant perimeter was 81 pCi/m. compared to 25 pCi/m at the 25 mile 8

8 MONITORING RESULTS radius and 3.9 pCi/m* at the 100-mile radius. The Magnitude of Program average onsite tritium concentration was 8

1,000 pCi/m.

The environmental monitoring program conducted at SRP is one of the largest and most comprehen.

Continuous measurements of the intensity of sive in the United States. A total of 177,000 gamma radiation levels at 350 locations at and analyses (89,000 radiological and 88,000 nonradi-around SRP were made with thermoluminescent ological) were performed in 1987. In addition, over dosimeters (TLDs). In the unlikely event of a 1.6 million nonradioactive measurements were significant unplanned release of radioactivity, made at ambient air quality monitoring stations these TLDs would provide a quick and reliable and over 460,000 water quality readings were method to determine external gamma radiation made in Beaver Dam Creek and Steel Creek.

doses to population groups within an 8,000-square-mile area in the vicinity of SRP. Signifi-i While the radiological monitoring program has cant variability in environmental radiation is seen continued to experience some growth from year to from one location to the other because of variable year, the most pronounced growth has occurred in radioactivity in soil, rocks, and building material, j

the nonradiological program. This program began As observed in previous years, there were no j

expanding in the mid 1970s and has continued to significant differences in 1987 between measure-escalate so that it is now ns large as the radiologi-ments taken at the site boundary and those taken cal pregram. The major growth has occurred in as far as 100 miles away from SRP.

groundwater monitoring.

Atmospheric emissions of sulfur dioxide, oxides of Presentation of Units nitrogen, and total suspended particulates from the five onsite coal. fired power plants were within It is intended to use the most practical units of applicable standards in 1987. All SRP stacks met measure when presenting data in this report.

the 40% opacity standard at all times except for Most data are presented in picoeuries per the 291 F stack, which occasionally exceeded the liter (pCi/L) or picoeuries per gram (pCi/g).

standard. A number of renovations are under way

[1 pCi = 10 is Ci (curie).] Fractions and multiples to ensure 100% compliance by the 291.F stack.

of units are shown on the inside front cover of this The quality of air at SRP was monitored at report. In some cases, data are presented in severallocations around the site that measure femtocuries (fCi). [1 (Ci = Igis Ci.] A few data are total suspended particulates, sulfur dioxide,

^

presented in attocuries (aCi). [1 aCi = 10" Ci.]

oxides of nitrogen, and ozone. The states of South Tritium concentrations are usually expressed in Carolina and Georgia performed additional picoeuries per milliliter (pCi/mL) but are some-ambient air monitoring. All SRP monitoring times shown in pCi/L. [1pCi/mL = 1,000 pCi/L.)

results were within state standards.

[xvi]

Surface Water Monitoring A comparison of the amount of tritium released from SRP facilities in 1987 with the amount of The Savannah River and all plant streams located tritium measured in transport in SRP streams on the SRP site are continuously sampled to and in the Savannah River continued to show monitor radioactivity released in emuent water relatively good agreement. Sources of tritium in from SRP facilities. Radioactivity in the liquid liquid emuents include direct releases from plant effluents is diluted by stream water, reactor heat facilities (20% in 1987 compared with 26% in exchanger cooling water, and Savannah River 1986) and migration of tritium from the Burial water. In 1987, no measurable differences were Ground, F, H, and P. Area seepage basins, and detected between upriver and downriver alpha K-Area Containment Basin (80% in 1987 com-and nonvolatile beta concentrations in the Savan-pared with 74% in 1986).

nah River. The release of tritium accounted for greater than 99% of the total radioactivity intro.

SRP liquid emuents are regulated by the South duced into the Savannah River from SRP activi-Carolina Department of Health and Environ-ties during 1987. After dilution by SRP streams mental Control (SCDlIEC) under the National and the Savannah River, tritium concentrations Pollutant Discharge Elimination System averaged 3.3 pCi/mL in the river below SRP at (NPDES). In 1987,68 active, permitted outfalls liighway 301 compared to 3.9 pCi/mL in 1986.

were monitored. SRP had a 99.7% NPDES compli.

The only radionuclide ether than tritium detected ance rate in 1987, compared to a 99.4% compli-in river water by routine analytical techniques ance rate in 1986. Only 18 of the 6,560 analyses was "Sr in trace quantities, performed exceeded permitlimits.

Using a special low-level analysis technique, the The Savannah River is extensivelv monitored for Savannah River Laboratory (SRL) detected 2"Cs chemicals, physical properties, as.. metals.

both upriver and downriver of SRP. In 1987, the Chemical and biological quality standards for the i

average "Cs concentrations determined by this Savannah River are specified in the requirements 1

technique were 0.010 pCi/L upriver and 0.057 of the state of South Carolina for Class B streams.

pCi/L downriver of SRP. The difference between All indications are that SRP operations do not the upriver and downriver concentrations is at.

have a deleterious effect on the Savannah River tributed to releases from SRP operations. The aquatic environment.

maximum "Cs concentration detected was 2,000 1

times less than the EPA drinking water standard The Division of Environmental Research of the of 200 pCi/L.

Academy of Natural Sciences of Philadelphia (ANSP) continued surveys of the aquatic environ.

Located approximately 20 miles from SRP, the ment and water quality of the Savannah River.

Edisto River is minimally affected by SRP opera-Studies in 1987 included diatometer studies, tions and is sampled for radioactivity as a meas.

aquatic insect surveys, and algal and aquatic ure for comparison to concentrations in SRP macrophyte surveys. In addition, a comprehensive streams. The maximum radioactivity concentra-survey was conducted in the Savannah River tions detected in the Edisto River in 1987 were 1.5 in the vicinity of the Vogtle 1 Nuclear pCi/L alpha,2.9 pCi/L nonvolatile beta, and 940 Power Plant, i

pCi/L (0.9 pCi/mL) tritium.

Extensive monitoring of SRP streams indicates The primary SRP stream with the highest concen-that, except for temperature in Pen Branch, the tration of radionuclides in 1987 was Four Mile water quality is not adversely affected by SRP Creek (FMC), which receives efiluents from F-and operations. Temperature prome surveys were II Separations Areas, C Reactor Area (although conducted at the mouths and upriver of Beaver C Reactor was not operating in 1987) and migra-Dam Creek and Steel Creek as part of a compre-tien from F-and II-Separations Areas seepage hensive study of the thermal effects of SRP basins and the Solid Waste Storage Facility operations upon the waters of the state of South (Burial Ground). Alpha and nonvolatile beta con.

Carolina as stated in consent order 84 4 W be-centrations in FMC were elevated with maximum tween SCDilEC and DOE. Temperature measure-activities of 15 and 140 pCi/L, respectively.

ments in both Beaver Dam Creek and Steel Creek j

Tritium concentrations were also elevated with a exceeded the ambient river temperatures but were maximum concentration of 3,300 pCi/mL.

within the consent order limits.

[xviil

Groundwater Monitoring Environmental Monitoring of I

Other Media SRP monitors groundwater quality to identify any contamination that may occur as a result of plant Air and water are the principal dispersal media operations. The purposes of monitoring groundwa-for SRP radioactive releases. However, the SRP ter are:

environmental surveillance program also includes samples representing other segments of the

+ to identify sources of contamination as soon environment that may be affected by these re-as possible leases or that might provide pathways of radiation

+ to measure concentrations of contaminants exposure to people.

that may enter groundwater, and

+ to provide data that can be used to design any Concentrations of radioactivity routinely detected needed cleanup projects.

in milk, food, drinking water, wildlife, rainwater, soil, sediment, and vegetation in 1987 were within The SRP Health Protection Department main-ranges observed during the last several years.

tains the primary responsibility for installing Except for tritium, the concentrations observed monitoring wells, and for collecting and analyzing were similar to those reported by other agencies groundwater samples.

in parts of the country not affected by SRP opera-tions (EPA 82, EPA 83]. Therefore, the occasional Monitoring of groundwater for radioactivity began trace amounts of radioactivity detected in thoe in 1957. Monitoring of groundwater for possible samples are attributed to worldwide fallout from chemical or nonradioactive contaminants began atmospheric nuclear weapons tests. Tritium, i

in 1975.

when present, is attributed to SRP operations.

i Approximately 75 waste sites, operating facilities, Annual hunts are conducted at SRP to contrcl the and spill sites have mor-itoring wells. About 800 deer and hog populations and to reduce animal-wells were monitored in 1987, and around 100 vehicle accidents. All animals are monitored for new monitoring wells are being added to the radioactivity before being released to the hunters, monitoring system each year. Many of these wells The 1987 hunts yielded 606 deer and 123 hogs, as have been installed to comply with environmental compared with 944 deer and 127 hogs regulations.

in 1986.

Groundwater in the M. Fuel Fabrication Area was Concentrations of t"Cs in the deer and hogs were i

found to be contaminated with metal degreasing withl-re.ngea observed over the last several solvents in 1981. Followup sampling indicated years. Consumption of the meat from these trichloroethylene and tetrachloroethylene (chio o-animals presents no radiation hazard. For ex-carbons)in Wells 20A and 53A in the A Admini-ample, an adult consuming all of the meat (12 kg) stration Area. Upon confirmation of the presence from the deer with the maximum "Cs concentra-5 of chlorocarbons, these drinking water wells were tion (45 pCi/g) would receive a 50-year radiation shut down and drinking water was supplied from dose commitment of 27 mrem (0.27 mSv)or 9% of Well 82A. New drinking water supply wells 112-G the average local resident's annual dose from and 113.G were placed in service in late 1986.

naturally occurring radiation. Average "Cs 5

concentrations in SRP deer and ofTsite deer were 5 No confirmed positive concentrations of chlorocar-and 9 pCi/g, respectively.

bons were detected in drinking water samples from the A Administration /M Fuel Preparation Areas or in other drinking water supplies at SRP Special Surveys and Studies in 1987. Occasionallow concentrations of trichlo-roethylene and tetrachloroethylene continued to Special radiological surveys were conducted in the be detected at the wellhead of Well 31A. The environment when short-term tritium releases maximums for 1987 were 13 pg/L and 4pgL occurred on three occasions in 1987. The maxi-respectively. Process water wells 20A and 53A mum calculated dose to an individual at the site continued to show elevated chlorocarbon analysis boundary from the largest release was 0.02 mrem l

results. The maximum concentration was 123 (0.0002 mSv) when 172,000 Ci of tritium was pg/L of trichloroethylene.

released to the atmosphere on July 31,1987.

fxviill

)

Special surveys were conducted on two other conducted at the Beaufort-Jasper and Port occasions in 1987 when short term radioactivity Wentworth water treatment plants following the releases occurred. An estimated 1.5 Ci of mixed 1985 startup of L-Reactor. The surveys were radionuclides were inadvertently released to conducted quarterly beginning in June 1986, and Upper Three Runs Creek on January 1,1987. The ending in April 1987. Surveys were conducted to maximum alpha and nonvolatile beta concentra-meet environmental impact statement require-tions in Upper Three Runs Creek in 1987 (which ments and to determine if the L-Reactor startup were due to this release) were 1.5 and 2.6 pCi/L, impacted the water treatment plants below SRP.

respectively. These concentrations are within the Similar surveys were conducted in 1983 to provide ranges of radioactivity observed in the Edisto baseline data of environmental conditions prior to River. On November 24,1987,1 Ci of 8'Cs and 33 L-Reactor startup in October 1985. In addition to mci of 88dCs were released to the atmosphere from radioactivity measurements, water quality meas-an H-Area facility.The maximum 287Cs concentra-urements were also performed. Monitoring results tions detected onplant and at the plant perimeter showed no significant impact to the water treat-were 0.70 and 0.79 pCUm, respectively. The ment plants from L-Reactor startup.

8 maximum concentration of 0.79 pCi/m detected 8

at the site boundary was 0.2% of the DCG Special Atmospheric Radon Study. An atmos-for88'Cs.

pheric radon study conducted at SRP and at residences in the region indicated doses from Savannah River Swamp Survey. Monitoring of radon were equivalent to those in other areas of five square miles of swamp bordering the Savan-the United States. Acccrding to the study, the nah River below the SRP boundary continued to annual average efTective dose equivalent to indicate radioactivity (previously identified as "Co residents in the Savannah River region from and '8'Cs) above natural background levels. The radon exposure probably lies between 100 and 300 ofTsite swamp area is uninhabited and inacces.

mrem / year. A comprehensive assessment of sible except for possible occasional hunting or radiation exposure of the U. S. population re-fishing. A comprehensive survey along 10 sam-ported by the National Council on Radiation pling trails that traverse the swamp was con-Protection and Measurements (NCRP)in 1987 ducted in 1985 before the startup of L-Reactor.

estimated the radon contribution at 200 Cursory surveys performed in 1986 and 1987 mrem / year [NCRP87al.

indicated the following radiological conditions:

Spills. A site wide procedure requires prompt

+

Gamma radiation measurements were within reporting of oil and chemical spills to a spill ranges observed in previous years. The coordinator who ensures spills are reported to the maximum radiation measurement was Department of Energy (DOE), Environmental 0.94 mR/ day.

Protection Agency (EPA), and South Carolina

+

Radionuclide concentrations in soil and Department of Health and Environmental Control i

vegetation samples were within ranges (SCDHEC) as appropriate to satisfy agulatory observed in previous data.

requirements. In 1987, there were 145 spills

+

Concentrations ofi87Cs in fish collected from reported to the spill coordinator. Most of these two lakes near the swamp trails were within were minor spills of petroleum products. None of ranges observed in previous years, the spills were reportable under the Comprehen-sive Environmental Response, Compensation and Special Creek Plantation Well Survey. Wells Liability Act (CERCLA). SRP has not had a on the ofTsite Creek Plantation below SRP were CERCLA reportable spill in ever two years.

sampled and analyzed for radioactivity in 1987 to confirm these wells have not been impacted by ENVIRONMENTAL 51ANAGEMENT AND SRP operations. All results were below EPA RESEARCH PROGRAMS drinking water standards and were within ranges observed for other offsite drinking water wells A wide variety of environmental manegement and routinely sampled.

research programs are conducted at the SRP site each year by the Savannah River Plant (SRP),

Comprehensive Surveys at the Beaufort-Savannah River Laboratory (SRL), Savannah Jasper and Port Wentworth Water Treat.

River Ecology Laboratory (SREL), and the Savan-ment Plants. Comprehensive surveys were nah River Forest Station (SRFS). Summaries of lxix]

programs conducted during 1987 are included in install a recirculating cooling tower for K Area.

Chapter 12 of this report. Highlights of a few of The Record of Decision was issued on February the programs are discussed in the succeeding 12,1988, and recommended installation of the paragra.phs, tower.)

Savannah River Plant Environmental Savannah River Laboratory Environmental Management Programs Management and Research Programs Environmental Audits and Appraisals. From Comprehensive Cooling Water Study. The the third quarter of 1986 into 1987, the Environ-Comprehensive Cooling Water Study (CCWS) was mental Protection Agency (EPA) conducted the initiated in 1983 to evaluate environmental effects largest environmental audit ever at SRP. This associated with SRP cooling water withdrawals audit, known as a multimedia audit, encompassed and discharges, and to determine the significance seven areas: hazardous waste (RCRA), solid of these effects on the onsite and downriver waste management units (SWMUs), wastewater environments. The CCWS was published in (NPDES), drinking water, groundwater, toxic October 1987. Some observations discussed in the substances, and air quality. No major problems report include the following:

were found; there were 98 minor administrative findings which SRP corrected during and after the

+ The water quality of onsite streams at SRP audit.

has been influenced primarily by the elevated temperatures and flow rates As part of a commitment to Congress to perform a associated with reactor operation.

baseline environmental survey of all DOE facili-ties, the Department of Energy Headquarters

+ In the vicinity of SRP, the Savannah River (IIQ) conducted a comprehensive environmental contains an abundant, diverse fish population.

survey at SRP in January 1987.

There is no evidence that river populations are adversely afTected by SRP cooling water Operations Under Hazardous Waste RCRA discharges.

Part B Permit. On September 30,1987, SCDilEC issued to SRP a RCRA Part B Permit

+ Reactor operations have no adverse impact on for operation of the liazardous Waste Storage the Par Pond system.

Facilities (Buildings 709-G,709 2G,709-4G, and 710 U) and post-closure maintenance of the M.

+ Four threatened or endangered species use Area Settling Basin and vicinity (overflow ditch, areas that could be affected by SRP cooling seep area, and Lost Lake). The EPA issued the water withdrawal or release.

federal portion of the permit covering the require-nents of 3004 (u) and 3005 (h) of the 1984 RCRA Amendments. This portion of the permit identified Waste Management and Groundwater 65 solid waste management units at SRP that will Protection Envimnmental Impact Statement require a RCRA Facility Investigation (RFI).

(EIS). An environmental impact statement (EIS) on waste management activities for groundwater Preparation of EnvironmentalImpact protection at the SRP was issued in December Statements. During 1987, the following two 1987. Seventy seven waste sites at 45 distinct environmental impact statements (EISs) were geographical locations around SRP were analyzed issued:

for impacts on human health and the ecology resulting from postulated closure actions.The Waste Afanagement Activities for the Protection of results of the environmental analysis of waste Groundwater at the Savannah River Plant, DOF2 disposal sites at SRP indicate that the risk to EIS 0120, December 1987. (The Record of Deci.

human health and the ecology is quite lovr. For sion was issued in March 1988.)

many sites, no remedial action is needed. For others, backfilling and capping the waste site Alternative Cooling Water Systems, SRP, LOFJ provides the required protection. At one site and EIS 0121, October 1987. (The Record of Decision possibly two, removal of the waste may be re-was delayed until early 1988 pending a decision quired to reduce the calculaten risk to the human on an EPA and SCDilEC recommendation to population.

[xx]

l National Environmental Research 1985. In 1986, wood storks foraged on the ponds Park Program for over two months, and 97 storks were counted feeding at one time; this number increased to 150 During 1987, approximately 15 NERP program in 1987. The patterns of numbers of storks at the research projects were conducted at the SRP. The ponds suggest that the artificial ponds do indeed site was surveyed for plants listed by state or present appropriate foraging habitat.

federal agencies as endangered, threatened, or of special concern. Other scientists surveyed soil U. S. Forest Service Savannah Ri,er Forest organisms, shallow pond protozoa, stream insects, Station Programs and forest vines. In 1987, NERP sponsored an SRP meeting at which scientists from across the Timber cut during 1987 brought the Federal country learned about opportunities to study Government nearly $2.3 million for 27 million microorganisms found in the sedimentary rocks board feet. Pine seedlings were planted on over hundreds of feet beneath the SRP.

2,200 acres during FY 1987.

Savannah River Ecology Southern bald eagles returned to SRP to nest in Laborato.y Programs 1987. For the second year, two eaglets were raised to fledging.

Wood Storks at Kathwood Artificial Forag-ing Ponds. When the Department of Energy In an efTort to reduce genetic inbreeding, two red (DOE) decided to restart the L-Reactor, there was cockaded woodpecker chicks were removed from a concern that reactor cooling water would increase nest at Francis Marion Forest, transported to the water level in the Steel Creek delta and make SRP, and substituted for two chicks of the same this area unavailable to wood storks that nest in a age in an SRP nest. The SRP chicks were then rookery near Millen, GA, and fly to the SRP to placed i t the nest at Francis Marion Forest. All of feed on fish. (In 1984, the U. S. Fish and Wildlife the swapped chicks were accepted and reared by Services classified the wood stork population as their foster parents. In 1987, all three pairs of red endangered.) To replace the potentially lost cockaded woodpeckers at SRP nested successfully.

foraging habitat, DOE created ponds at the site of They produced seven fledgings, increasing the Kathwood Lake on the National Audubon known SRP population to 14 birds.

Society's Silver BlufT Plantation Sanctuary in I

I l

f P

l l

i i

[xxi)

1 Introduction and Program Overview

(

h

SUMMARY

- An overview of the environmental monitoring program at Savannah River Plant (SRP) is given in this introductory chapter, along with a description of the SRP site and f acilities. SRP occupies approximately 100 square miles along the Savannah River in a predominantly rural section of South Carolina, principally in /nen and Bamwell Counties.

SRP's primary function is the production of p!utonium, tritium, and other special nuclear mate-rials for national def ense, otr,er governtnental uses, and some civilian purposes. Major

(

ooerating f aci!! ties include three nuclear reactors, a fuel target f abrication plant, a naval fuel materials facility, two chemical separations plants, and the Savannah River Laboratory (SRL),

which is a pro;ess development laboratory that supports production operations. Exclusion of the public from the plant site (except for controlled public hunts for deer and hogs) creates a refuge for many terrestrial and aquatic animals. The extensive environmental program at SRP encompasses both radioactive and nonradioactive monitoring. The program intensively i

surveys a 2,000-square mile area in the immediate vicinity of SRP and analyzes representa-tive samples collected from an additional 30,000-square-mile area. Both radiological and nonradiological analyses are carried out for air, surface water, groundwatar, drinking water, sediment, and fish, in addition, radiological analyses are carried out on samples of milk, food, i

wildlife, rainwater. soils, and vegetation. SRP streams and the Savannah River are exten-sively monitored for chemicals, metals, organics and numerous other constituents and physical properties. Drinking water is analyzed for total coliform, residual chlorine, and a variety of chemicals, including chlorocarbons. River and stream water and sediment are analyzed for pesticides, herbicides, and polychionnated biphenyls (PCBs). In addition to the monitoring programs, a significant amount of environmental research is conducted each year at SRP by organizations that include SRL, the Savannah River Ecology Laboratory (Univer-t- 'of Georgia), and the Savannah River Forest Station.

DESCRIPTION OF THE SRP SITE AND The climate is mild, with an average frost-free sea-FACILITIES son of approximately 246 days. The annual average rainfall at SRP is about 48 inches and is fairly evenly The Savannah River Plant (SRP) occupies an area of distributed throughnut the year. The SRP and sur-approximately 300 square miles along the Savan.

rounding area are described in more detailin "I'he nah River, principally in Aiken and Barnwell Coun.

Savannah River Plant Environment"[Du84].

ties of South Carolina. Most of the plant's environs are rural. Average population density in the coun-SRP's primary function is the production of pluto-ties surrounding SRP ranges from 23 to 560 people nium, tritium, and other special nuclear materials per square mile with the largest concentration in the for national defense, for %er governmental uses, Augusta, GA metropolitan area, which has a popu-and for some civilian purposes. Major operating fa-lation greater than 250,000. The countryside is cilities in 1987 included three nuclear reactors, a predominantly forested. Farming is diversified; the fuel and target fabrication plant, a naval fuel mate-main crops are cotton, soybeans, corn, and small rials facility, two chemical separations piants, and grains. Production of beef cattle continues to the Savannah River Laboratory (SRL), a process de-expand.

velopment laboratory which supports production

2 SAVANNAH RIVER PLANT - Environmental Report for 1987 operations. Many other facilities necessary to sup-Iteactor produced products are recovered in the port operations are located on the SRP site. The chemical separations areas. Plutonium 238, "Pu, heavy water production plant, which began opera-and uranium are separated from each other and i

tion in 1953, was shut down in Ifol. The three from fission products by complex chemical proc.

operating reactors are the P, K, and L-Reactors. L.

esses. These areas also have facilities for purifica-Reactor was restarted in Octcher 1985 after an tion and packaging of tritium and for storage of extensive upgrade. A fourth reactor, C Reactor, op-fission product wastes. SRP production areas and erated until 1986, when it was sh ut down for repairs.

eOluent streams are shown on the facing page in l

The fifth reactor, R Reactor, was permanently shut Fig.1 1.

down in 1964. Reactors and separations plants are located n ear th e center of the site; oth er facilities are A major facility is currently under construction on located near the perimeter.

the SRP site. The Defense Waste Processing Facility (DWPF) will immobilize high level radioactive Nuclear fuels and targets, together with other reac-waste in a solid, unleachable glass. The facility will tor components, are manufactured in the fuel and be the first ofits type in the nation.

target fabrication facility. The reactors at SRP are fueled with uranium, moderated and cooled by An other process waste facility u nder con st ruction at heavy water circulated in a closed system through SRP is tiie F/II Efiluent Treatment Facility (ETF).

heat exchangers. Water from the Savannah River The FTF will treat wastewater generated by the and Par Pond, a manmade cooling water im-chemical separations facilities before it is dis-pound men t covering 2,640 ac res, is used a s a coolant charged to the Savannah River via Upper Three in the heat exchannrv Runs Creck. The wastewater is currently dis-charged to seepage basins. Operation of the facility 13ecause heat.

cooling water does not pass is expected tu begin in late 1988.

directly throui.,

actors, it is not subject to direct neutron acta ation. The heat exchanger cool-Construction of a Naval Renetor Fuel Materials ing water from P Reactor is r(turned to Par Pond, Facility to produce nuclear fuel for the U.S. Navy some of w hich ove rflows to IAwer Th ree Run s Creek.

was completed in 1986 and the facility is undergoing L-and K Reactors use Savannah River water as startup tests.

heat exchanger coolant. The water is discharged via difTerent waterways. L Reactor heat exchanger Exclusion of the public from the plant site creates a cooling water is discharged to L Lake, which over-refuge for many terrestrial and aquatic animals.

flows to Steel Creek. K Reactor heat exchanger The deer population is limited by controlled public cooling water is discharged to Pen Branch.

hunts to prevent range deterioration end to mini-mize deer / vehicle acci.

dents. More than 700 JG]

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1. Introduction and Program Overview 3

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4 SAVANNAH RIVER PLANT - Environmental Report for 1981 ducted at the site that are funded by the Department both radioactive and nonradioactive monitoring. A of Energy (DOE), approximately 15 research proj.

total of 177,000 analyses (89,000 radiological and ects were conducted at the SRP site under the NERP 88,000 nonradiological) were performed in 1987. In program in 1987, addition, over 1.6 million nonradioactive measure-ments were made at ambient air quality monitoring The U.S. Forest Service has planted over 99 million stations and over 460,000 water quality readings pine seedlings on nearly 91,000 acres of the plant were taken from monitors in Beaver Dam Creek and site since 1952. Significant quantities ofpine, hard-Steel Creek. hf onitoring programs are coordinated wood saw timber, and pulpwood have been har-by the IIealth Protection (IIP) Department at SRP.

vested during this same period.

Regulatory compliance is coordinated by the Envi-ronment and Energy (E & E) Department at SRP.

Research programs are conducted by the Savannah OVERVIEW OF ENVIRON 51 ENTAL River Laboratory (SRL) and the Savannah River PROGRA31S Ecology Laboratory (SREL).

Environmental 5fonitoring and Hegulatory E & E is responsible for the oversight and coordina-Compliance tion of site programs to protect the environment and ensure regulatory compliance. A etaTornearly 30 The environmental monitoring program at SRP is professionals in engineering, chemistry, geology, one of the largest and most comprehensive in the biology, toxicology, and health physics provides United States. Extensive programs are conducted in support to the site environmental programs.

Hadiological Programs Departments Involved a

Environmental Stonitoring Health Protection Dept (Air, Surface Water, Groundwater, Food, Drinking Water, Wildlife, Rainwater, Soil, Sediment, Vegetation)

Nonradiological Pmgrams Departments Involved 5

Air hionitoring Health Protection Dept Environment and Energy Dept Operating Depts a

Water Quality hfonitoring Health Protection Dept Laboratories Dept Environment and Energy Dept u

Drinking Water Health Prottetion Dept Power Technology Dept Environment and Energy Dept a

Surface Water Afonitoring IIcalth Protection Dept (NPDES)

Environment & Energy Dept Operating Depts a

Groundwater h!onitoring Health Protection Dept (Nonregulatory &

Environment & Energy Dept Regulatory)

Operating Depts SRL Interim Waste Technology Div

1. Introduction and Program Overview 5

Each year, extensive radioactive monitoring is per-g formed in a 2,000-square mile area in the immedi-7 4

ate vicinity of SRP and representative samples are

,5 collected from an additional 30,000-square mile area. In this 30,000-square mile area, many difTor.

ent types of samples are collected routinely and ana-

.O' lyzed for radioactivity. The radioactive monitoring program generated approximately 23,800 samples and 89,000 analyses in 1987. Approximately t

504,000 samples A 1,859,000 analyses have been generated since the program began in 1951. Types of a

p samples collected and analyzed for radioactivity are shown at the bottom of the page.

Wildlife is monitored The nonradioactive ambient air monitoring pro-gram is coordinated by IIP, and routme operation of Monitoring programs at SRP and departments in-the program is contracted to an offsite company.

volved are shown on the facing page.

Onsite stations house instruments which monitor for sulfur dioxide, oxides of nitrogen, ozone, and The IIealth Protection Department performs most total suspended particulates. Over 1.6 million radiological and nonregulatory water quality analy-measurements were made in 19S7.

ses. IIP facilities include sample receiving areas, ra-diochemical preparation laboratories, nonradio.

SRP has monitored site stream wastewater dis-chemical analytical laboratories, and radionnalyti-charges and their efTects on Savannah River water cal counting rooms. NeeFy 30 laboratory analysts quality since the early 1960s.The inhouse nonregu-and technicians collect, prepare, and analyze envi-latory water quality program, conducted by the ronmental samples. In addition to the laboratory su-llealth Protection Department, monitors plant pervisors who supervise sample collection, prepara-streams and the Savannah River for chemicals, tion, and analysis, a staffof over 15 professionals in metals, and organics. Six to 33 constituents are ana-biology, enemistry, geology, health physics, and lyzed at each sample location. The SRP Laborato-computer science provides technical support to the ries Department performs coliform bacteria analy-monitoring program. A large portion of the ses for this program. Each year, approximately 200 regulatory monitoring programs is contracted to samples are collected and 5,500 analyses per-commercial laboratories.

formed. In addition, water quality parameters are Types of Samples Analyzed in the Itadioactive Monitoring Program Air Wildlife Thermoluminescent Dosimeters fish Surface Water crabs and oysters rivers deer and hogs streams furbearers seepage basins (i.e., oppossums, foxes, raccoons)

Groundwater turtles Milk ducks Food (i.e., eggs, chickens, Itainwater meats, fruits, grain s, Soll collards)

Sediment Drinking Water Vegetation

6 SAVANNAH RIVER PLANT - Environmental Report for 1987 measured in Steel Creek and Beaver Dam Creek to comply with consent order 84-4.W between the Types of Samples Analyzed in the South Carolina Department ofIIcalth and Environ.

Nonradiological hionitoring Programs mental Control (SCDilEC) and the DOE. Tempera-ture and dissolved oxygen measurements are taken Air daily in Steel Creek, and readings for temperature, Surface Water conductivity, pli, oxidation / reduction potential. and Rivers dissolved oxygen are made every five minutes in Streams Beaver Dam Creek. In 1987, over 460,000 measure-Seepage Basins ments were made.

Groundwater Drinking Water Analyses for the regulatory National Pollutant Dis-Sediment charge Elimination System (NPDES) liquid efiluent Rivers monitoring program coordinated by IIP are con-Streams tracted to commercial laboratories certified by Fish SCDREC. IIP handles sample collection and ad-ministraticn of analytical contracts. E & E reviews and reports data to SCDiiEC via the DOE. Approxi-Environmental Research mately 6,600 routine analyses were performed on 68 active outfalls in 1987. An additional 10,000 analy-A significant amount of environmental research is ses were performed for NPDES permit renewal.

conducted each ycar at S RP. 31any of th ese activities are described in Chapter 12 of this report. Groups Sample collection, laboratory analysis, and data involved in these efforts include the following:

handling for the groundwater monitoring program (nonregulatory and regulatory) are contracted to E Savannah River Laboratory ofTsite companies. Contracts are administered by Environmental Sciences Division llP. E & E reviews and reports groundwater data to Environmental Transport Division SCDIIEC to fullfill regulatory requirements. Ap-Interim Waste Technology Division proximately 61,000 analyses of groundwater were E Savannah River Ecology Laboratory performed in 1987.

(University of GA)

Drinking water analyses for residual chlorine and a variety of chemicals are subcontracted to offsite laboratories by the Power Technology Department-PROGRA51 REVIEWS Total coliform analysis of drinking water is per-formed onsite by the Laboratories Department.

External Review of Nonradiological Chlorocarbon analyses are performed on duplicate hionitoring Program drinking water samples by both the Laboratories Department and an offsitelaboratory. E & E reviews At the IIealth Protection Department's request, and reports the regulatory required data to International Technology Corporation (IT) per-SCDilEC via DOE. Approximately 4,200 analyses formed a comprehensive review of the SRP nonradi-were performed on drinking water in 1987.

ological environmental monitoring program during the fcurth quarter of 1986. A similar audit of the River and stream water and sediment are analyzed radiolngical program s was repot ted in the 1986 SRP for pesticides, herbicides, and polychlorinated Environmental Report (Ze87]. Five areas were au-biphenyls (PCBs) by an offsite laboratory. There dited: (1) surface and ground water quality sam-were 576 analyses performed in 1987, la addition, pling;(2) air quality sampling;(3) well installation; mercury analyses in fish are normally conducted (4) laboratory analysis; and (5) biological studies.

each year. Types of routine samples analyzed in the Each area was separately audited. Written nonradiological monitoring programs are shown in checklists developed by IT were followed during the the table at the top right hand column ofthepage, audit.

1 1

1. Introduction and Program Overview 7

The general objective of the audit was to evaluate grams. The report also identified several areas procedures and the efTectiveness of their implemen-where the programs could be strengthened to im-tation, to evaluate work areas and activities, to prove quality.

review documentation, and to recommend methods to improve the program. The scope of the audit in-The major recommendations pertained to written cluded the following:

plans for monitoring objectives and criteria of each monitoring program. These plans will document E subcontractor capability and performance why monitoring is performed and provide technical E field operations, records, and precedures justification. Other methods to improve the quality E laboratory testing and records of programs include chain of-custody and minor E equipment calibration and records modifications to procedures.

E identification and control of samples E numerical analyses and designs DOE Headquarters Environmental Survey 5 information reporting E record control and retention In 1987, DOE performed a comprehensive environ.

E personnel training

ntal survey at SFP to identify environmental problems and areas.I associated environmental The analyticallaboratories were audited according risk. The multimedia survey was conducted on the to requirements of the IT Analytical Services (ITAS)

SRP site in two phases. During the first phase from Quality Assurance Manual and appropriate SRP January 5-23,1987, the survey team developed a QA procedures. Items examined by the auditor in-sampling and analysis plan to assist in further as.

cluded availability and implementation of approved sessing certain of the environmental problems iden-laboratory procedures, equipment calibration and tified during the visit. The second phase was con-records, control and storage of samples, QC sample ducted from September 14-December 17,1987. The program, performance documentation and check-preliminary report from the first phase was pub-ing, and nonconformance documentation. Two Du lished in August 1987 and included 65 findings, Pont laboratories and five subcontractor laborato-none of which identified any environmental prob-ries were audited:

1 ems at SRP that represent an immediate threat to human health or the environment.When analyses of 5 Du Pont Lab 772 D (SRP) samples collected during phase two are completed, E Du Pont Lab 735 A(SRP) the results will be incorporated into an SRP Envi.

E Environmental and Chemical Services, Inc.

ronmental Survey Interim Report, which will reflect (New Ellenton, SC) the final determinations of the SRP survey.

E Environmental Testing, Inc. (Charlotte, NC)

E Envirodyne Engineers, Inc. (St. Louis, MO)

Environmental Advisory Committee E Academy of Natural Sciences (Philadelphia, PA)

E Zedek Corporation (Durham, NC)

A e mmittee composed of four consultants meets quarterly to review SRP/SRL environmental pro.

The audit findings and recommendations were grams and make recommendations. The four con-documented in a report issued in December 1986.

sultants are nationally recognized experts in their The report evaluated the programs as technically respective fields of biology, ecology, hydrogeology, strong and presented a favorable view of the pro-and health phys,cs.

i 1

I 8 SAVANNAH RIVER PLANT - Environmental Report for 1987

=

1987 HIGHLIGHTS E The Defense Waste Processing Facility (DWPF), a major f acility that will immobilize high-level radioactive waste in a solid, unleachable glass, is under construction on the SRP site. The facility will be the first of its type in the nation.

5 The F/H Elfluent Treatment Facility (ETF), another process waste f acility under construc-tion on the SRP site and expected to be in operation in 1988, will treat wastewater gener-ated by the chemical separations facilities before it is discharged to the Savannah River via Upper Three Runs Creek.

E Approximately 15 research projects were conducted at the SRP site under the National Environmental Research Park (NERP) program in 1987.

E The environmental monitoring program expanded with 69,000 radiological and 88,000 nonradiological analyses performed in 1987.

E Approximate!y 6,600 routine analyses were pt rformed on 68 active outf alls for the reguta-tory National Pollutant Discharge Elimination System (NPDES) liquid effluent monitoring program during 1987; an additional 10,000 analyses were performed for NPDES permit renewal.

E During 1987, approximately 61,000 analyses were performed for the groundwater moni-toring program. This is twice the number performed in 1986.

E Drinking water analyses for 1987 totaled approximately 4,200.

E River and stream sediment were sampled for pesticides, herbicides, and polychlorinated biphenyls (PCBs): 576 analyses were performed during 1987.

5 An audit of the nonradiological programs evaluated them to be technically strong.

E DOE conducted a comprehensive multimedia survey in 1987. The preliminary report included 65 findings, none of which identified any environmental problems at SRP that represent a threat to human health or the environment.

)

2 Air Monitoring ' Program

(

)

SUMMARY

- Results of radiological and nonradiological rnonitoring of atmospheric emis-sions, environmental gamma radiation measurements made with TLDs, and ambient air quality measurements of total suspended particulates, sulfur dioxide, oxides of nitregen, and ozone are presented in this chapter. Airbome radioactive materials are measured by analysis of filter papers, charcoal filters, and tritium desiccants located at monitoring stations on the site, around the plant perimeter, and at distances of 25 and 100 miles. The major gamma-emitting radionuclide routinely detected in air was naturally occurring 78e. The offsite radiation dose cornmitments from radioactivity released to the atmosphere from SRP facilit'es during normal cperat;ons were celculated for individuals closest to the plant site by potential path-ways, and for populations out to a distance of 80 km (50 miles) from the center of the site.

Tha highest potential dose commitment from atmespheric releases of radioactivity to a hypo-thetical person at the plant boundary was 0.6 mrem which is 0.2% of the annual dose com-mitment of 295 mrem (2.95 mSv) received from natural radiation sources. Atmospheric emis-sions from the five coal fPed power plants located at SRP that bumed a total of 452,980 tons of coalin 1987 were within applicable standards. A comparison of data from SRP ambient air monitoring stations with Georgia and South Carolina standards clearfy shows that air quality in the SRP area is good and well within the EPA standards.

N

)

RADIOACTIVE MONITORING fallout. Distant air monitoring station s are shown in Fig. 2 2, Vol. II.

Atmospheric Emissions Airborne radioactive materials are measured by Description of Monitoring Program. Concen-analysis of filter papers, charcoal filters, and tritium trations of radioactive materials in the air are desiccants placed at the monitoring stations for measured at six monitoring stations on the plant specified periods. The filter papers and charcoal site,13 monitoring stations around the plant filters remain in pbce for one week; the tritium perimeter, and 12 stations at distances of approxi-desiceants are changed every two weeks.

mately 2f miles from the center of the plant (called "25-mile radius" stations). The stations at the plant perimeter and the 25. mile radius stations are Applicable Standards. The guides for con-spaced to permit contin uous monitoring within each centrations of radionuclides in air are given in 30 degree sector. This spacing enhances the proba-Chapter XI of order DOE 5480.1A (Rev. 8/5/85).

bility of detecting a significant release of airborne These guides are based on recommendations in radioactivity from SRP regardless of win d direction.

Publications 26 and 30 of the International Air filters are collected weekly for analysis (see Commission on Radiological Protection [lCRP77; Chapter 10). The locations of the air monitoring sta-ICRP 79].

tions are shown in Fig. 2-1, on p.10.

The guides are designated as Derived Con.

Additional air monitoring stations located at Savan-centration Guides (DCGs).The DCGror a radionu-nah and Macon, GA, and at Columbia and Green-clide is defined as the air concentration of that ville, SC ("100-mile radius" stations), are so distant radionuclide that willgive a 50-year dose commit-from SRP that the effect of SRP operations at these ment of 100 mrem ifbreathed continuously for one locations is negligible. They serve as reference year.The DCGs for radionuclides released to the points for determining background radioactivity atmosphcre from SRP are listed in Table 2-1 at levels from natural sources and from worldwide the top of p.11.

10 SAVANNAH RIVER PLANT - Environmental Report for 1987

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Fig. 21. Continuous Air Monitoring Stations and Public Water Sample Locations The revised DOE interim standards aiso include the contribution of particulate radioactivity from re-EPA National Emission Standards for liazardous leases at SRP was not detectable at any of the site Air Pollutants (NESIIAPS): Standards for Radionu-clides (40 C1'R 61), which apply to federal facilities.

Average activity concentration (fCi/m')*

The NES!!APS Standards state that radioactive air emissions shall not reult in a whole body dose of Location Alpha lieta greater than 25 mrem / year to any member of the Onplant 1.1 28 public.

Plant Perimeter 1.0 17 25 Mile Radius 1.0 16 Monitoring Itesults. Atmospheric monitoring 100 Mile Radius 1.2 15 results are presented in Table 2 1, Vol II. The small 1,000 fcum'.1 pcum'

2. Air Monitoring Program 11 Table 21. DOE Derived Concentration Guides for Air (pCi/nt)*

H3 100,000 Nb-95 3,000 Ce 141 1,000 C 14 6,000 Ru 103 2,000 C+ 144 30 Co-58 2,000 Ru 106 30 U 235 0.1 Co 60 80 1-129 70 U 238 0.1 Kr-85m 100,000 1131 400 Pu 238 0.03 Kr-85 300,000 Xo-131m 400,000 Pu 239 0.02 Kr-87 20,000 Xe 133 300,000 Am 241 0.02 Kr 88 20,000 Cs 134 200 Cm 242 0.7 Sr-89 300 Xe-135 100,000 Am 243 0.02 Sr 90 9

Cs 137 400 Cm 244 0.04

Department of Energy draft order 5480.1A(Chapter XI) for soluble forms.

boundary monitoring stations. Tritium was the only testing of nuclear weapons by nonparticipants in radionuelide of plant origin that was routinely de-the 1962 atmospheric testing moratorium, tected in offsite air. The concentrations of all par-ticulate radioactivity and tritium were only small Some increase in nonvolatile beta in air has also l

percentages of the DCGs for air, generally occurred at alllocations in the spring as a l

result of the mixing of the stratosphere with the tro-1 The small amount of particulate alpha and beta-posphere. This phenomenon is generally observed gamma radioactivity released to the atmosphere, between January and June dependingon prevailing j

primarily from the F.and H. Separations Area facili-meteorological eonditions.

i i

ties, is generally obscured in the area surrounding SRP by worldwide fallout levels. The plant perime.

The major gamma-emitting radionuclide routinely ter, 25-mile radius, and 100-mile-radius sample detected in air was ?Be, which is naturally formed by groups had essentially the same average particulate the interaction of cosmic rays with oxygen and alpha and nonvolatile beta concentrations as shown nitrogen in the upper atmosphere. In 1987, concen-in the table at the bottom right column on p.10.

trations of naturally occurring 'Be ranged from 1.6 8

to 1,400 IUi/m.

These results indicate a slightly higher nonvolatile beta average for the "onplant"location group but are No significant difference was noted between aver-within ranges observed in previous years.The maxi-age measurements of plutonium in air at the site mum onplant alpha concentration of 3.7 fCi/m oc-boundary and offsite locations as shown in the fol-8 curred at A Area, and the maximum onplant non-lowing table:

volatile beta concentration of 290 fCi/m occurred at 8

H Area. Both maximum values were detected in Average plutonium concentrations November 1987.

(aC1/m P in the SRP vicinity 8

j Location Pu 238 Pu 239 The historical influence of fallout from weapons tests on particulate nonvolatile beta activity in air is Onplant 28 11 shown in Fig. 2-2 on p.12. Elevated nonvolatile beta Plant Perimeter 0.31 1.3 concentrations were observed at alllocations after 254 tile Radius 0.31 1.0 l

atmospheric testing was resumed in the United 1004 file Radius 0.70 1.5 States in September 1961, and after atmospheric 8

8

' 1,000,000 aCi/m = 1 pCi/m

12 SAVANNAH RIVER PLANT - Environmental Report for 1987

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2. Air Monitoring Program 13 TABLE 2 2.1987 RADIOACTIVE ATMOSPHERIC TABLE 2 3. AVERAGE INDIVIDUAL DOSES AT RELEASES AND CONCENTRATIONS THE PLANT PERIMETER FROM ATMOSPHERIC RELEASES Calculated Avg. Conc.

Curies Released at at Plant Perimeter, Bv Pathway Nuclide Emission Source pC1'm2 Avg. Individual Percent of Gases and Vapors:

Pathway Dose mrema Total Dose 4

H 3 (oxide) 2.70E+05 8.1 E+01 4-3 (elemental) 3.20E+05 9.6E+01 Plume 9.54E 02 36.18 H 3 (total) 5.90E+05 1.8E+02 Ground 1.77E 02 6.71 C-14 4.10E+01 1.2E-02 inhalation 6.72E-02 25.48 Ar 41 8.77E+04 1.4E+01 Vegetation 5.32E 02 20.17 Kr 85m 1.69E+03 3.9E-01 Mak 1.49E-02 5.65 Kr-85 3.95E+05 1.2E+02 Meat 1.53E 02 5.80 Kr 87 1.16E+ 03 1.4E 01 Kr 88 2.01 E+03 4.0E 01 Total 2.64E-01 Xe 133 5.32E+03 1.6E+00 Xe 135 3.48E+03 9.2E-01 Bv RadionucHde I-129 7.20E 02 2.0E-05 l131 1.26E 02 3.4E 06

g g

g Particulates:

Radionuclide Dose. mrema Total Dose Co-60 1.30 E-05 3.6E-09 Se 75

<4.00E 04

<1.1 E-08 Gases and Vapors:

Sr 89,90 1.35E-03 3.7E 07 H3 1.08E-01 40.91 Zr 95 1.67E 03 4.6E 07 C-14 6.85E-03 2.59 Nb-95 3.29E-03 9.0E-07 Ar-41 8.75E-02 33.14 Ru 103 1.37E-03 3.7E-07 Kr, Xe isotopes 7.91 E-03 3.00 Ru 106 4.53E-02 1.2E 05 l-129 1.75E-02 6.63 Cs 134 2.20E-03 6.0E-07 1131 3.54E-05 0.01 Cs 137 1.07E+ 00 2.9E-04 Ce 141 6.00E-06 1.6E-09 a W ak s:

Ce 144 3.15E-02 8.6E-06 Ru-106 1.46E 03 0.55 Os 185

<7.00E-05

<1.9E 08 Cs437 2.82E42 10.68 Total U 8.52E 03 2.3E 06 235,238 2.66E43 1.01 Pu-238 1.96E 03 5.4 E-07 238 2.07E43 0.78 Pu 239 4.07E 04 1.1 E-07 Cm 242,244 2.04E-04 5.6E-08 j

A 24L243 6

Am-241,243 3.22E 04 8.8E-08 Cm 242,244 1.51 E-04 0.06 Total 2.64E-01 liigher values were detected at the onsite monitor-

Committed effective dose equivaient.

ing stations near the F and II Separations Areas.

Concentrations of"8Pu ranged up to 220 aCi/m and 5

"'Pu ranged up to 93 aCi/m at these locations.

8 Average tritium concentrations SRP released tritium was detected at ofTsite moni.

In the SRP vicinity

]

toring stations and shows a decreasing trend with distance from the site as shown in the table at right:

Location Tritium (pCi/m')

J Onsite tritium oxide concentrations in air ranged Onplant 1,000 8

from 6.5 to 7,200 pCUm. The maximum value was Plant Perimeter 81 detected at the II-Area monitoring station.

25-Mile Radius 25 100-Mile Radius 9.9 4

14 SAVANNAH RIVER PLANT - Environmental Report for 1987 l

TABLE 2 4. MAXIMUM INDIVIDUAL DOSES AT THE PLANT PERIMETER FROM ATMOSPHERIC RELEASES By Pathway Averace Consumotion Maximum Consumotion Maximum individual Percent 0!

Maximum individual Percent 0f Pathway Dose. mrema Total Dose Dose. mrem

Total Dose Plume 1.70E-01 37.98 1.70E 01 26.34 Ground 2.90E-02 6.48 2.90E-02 4.49 inhalation 1.11 E-01 24.80 1.11E 01 17.20 i

Vegetation 8.77E-02 19.59 2.35E 01 36.42 MJk 2.47E-02 5.52 7.03E 02 10.89 i

Meat 2.52E-02 5.63 3.00E-02 4.65 l

Total 4.48E-01 6.45E 01 By Radionuclide Averaoe Consumotion Maximum Consumotion Maximum Individual Percent Of MaximumIndividual Percent Of Radionuclide Dose mrema Total Dose Dose. mrem

Total Dose Gases and Vapors:

H3 1.79E-01 39.96 2.85E-01 44.16 C 14 1.13E-02 2.52 2.74E 02 4.25 Ar-41 1.57E-01 35.05 1.57E-01 24.33 Kr,Xe isotopes 1.36E-02 3.04 1.36E 02 2.11 l-129 2.88 E-02 6.43 7.39E 02 11.45 l-131 5.82E-05 0.01 1.30E 04 0.02 Particulates:

Ru 106 2.39 E-03 0.53 3.04E-03 0.47 Cs 137 4.62E-02 10.31 7.41 E-02 11.48 U 235.238 4.40E-03 0.98 5.21E 03 0.81 Pu-238 3.43E-03 0.77 3.71 E-03 0.57 Pu 239 7.90E-04 0.18 8.56E-04 0.13 Am 241.243 7.67E 04 0.17 1.03E-03 0.16 Cm 242.244 2.50E-04 0.06 3.34E 04 0.05 Total 4.48E 01 6.45E-01

Committed effective dose equivalent.

Summary of 1987 Atmospheric Heleases of the releases and also contribute most of the and Concentrations ofTsite dose.

Radioactivity released to the atmosphere from SRP Tritium is the only radionuclide ofSRP origin which facilities during normal operations is monitored at is detected routinely in ofTsite air. The maximum the source of release for all atmospheric efiluents.

concentration of tritium oxide measured at the plant Releases of radioactive materials to the atmosphere perimeter in 1987 was 286,000 pCi/m due to the 8

in 1987 are shown in Table 2 2 on p.13(also in tritium release which occurred on July 31,1987 (see Vol. II). Gases an d vapors are the major constituents Chapter 8). Tritium cor.centrations were also

2. Air Monitoring Program 15 Offsite Radiation Doses from TABLE 2 5.80 KM POPULATION DOSE 1987 ATMOSPHERIC RELEASES Offsite radiation dose commitments from atmos-By Pathway pheric releases during 1987 were calculated for individuals closest to the plant site and for cumula-Population Dose Percent of tive population dose out to a distance of 80 km (50 Pathway oerson rema Total Dose miles) from the center of the site using meteorologi-cal data for the period 1982 through 1986. Table 2-Plume 4.17E+00 14.25 3 on p.13 (also in Vol. II) shows the calculated dose Ground 4.18 E+00 14.29 commitments to the average individual at the plant inhalation 8.64E +00 29.53 perim ete r by pathway. Dose com mitments, based on Vegetation 8.48E+00 28.98 annual releases, were calculated for persons with MJk 2.06E+00 7.04 normal living habits residing at 320 locations equi.

Meat 1.73 E+00 5.91 distantly spaced along the plant perimeter. These d se commitments were then averaged over the 320 Total 2.93E+01 locations to give the values in Table 2-3.

Bv Radionuclide The dose commitment of 0.3 mrem (0.003 mSv) to Population Dose Percent of the average individual was 0.09% of the normal Radionuclide eerson-rem

Total Dose average dose of about 295 mrem (2.95 mSv) from natural radiation sources in the Central Savannah Gases and Vapors:

River Area INCRP87a].

H3 1.50E+01 51.28 C 14 9.79E-01 3.35 Table 2-4 on p.14 (also in Vol. II) shows the dose by Ar-41 3.63E+00 12.41 pathway to a hypotheticalindividuallocated at the Kr,Xe isotopes 5.37E-01 1.84 plant perimeter at the point of maximum exposure.

1-129 2.62E+00 8.96 With an assumed average dietary intake,the dose to I-131 8.56E 03 0.03 this individual is 0.4 mrem (0.004 mSv). If the maximum in take of ali types of food (milk, ment, an d Particulates:

vegetables) is assumed, the dose is 0.6 mrem Ru-106 1.42 E-01 0.49 (0.006 mSv) which is 2.4% of the NESHAPS stan-dard of 25 mrem / year to a member of the public.

25238 01 Pu 238 2.57E-01 0.88 Pu 239 5.92E-02 0.20 Doses were calculated for individuals within 80 km Am 241-243 5.89E-02 0.20 (50 miles) of the SRP site at normal places of resi-Cm 242,244 1.92E 02 0.07 dence, and the individual doses were summed to obtain the population doses shown in Table 2 5 (also Total 2.93E+01 in Vol. II). The population dose commitment calcu-lated in this manner for the population of 550,000 Commced effective dose equivalent.

within 80 km of the plant site in 1987 was 29.3 a

person rem (0.29 person-Sv).This dose is equivalent to an average dose of 0.05 mrem (0.0005 mSv) and is calculated using computer codes and standard me.

0.02% of the dose of 295 mrem received annually by teorological dispersion equations [USNRC73). The the 80-km radius population from natural radiation average concentration of tritium oxide measured at sources.

plant perimeter monitoring stations was 81 pCi/m,

8 which is the same as the calculated value shown in Environmental Gamma Radiation Table 2-2 on p.13. Thus, it appears that the caleu-lated concentrations in the table are a reasonable Continuous measurements of the intensity of estimation of the offsite efTect of releases of radioac.

gamma radiation levels at and around SRP were tive materials.

made with thermoluminescent dosimeters (TLDs).

16 SAVANNAH RIVER PLANT - Environmental Report for 1987 In the unlikely event of a significant unplanned with 1986 results. Summaries of all TLD results radioactivity release, these 350 monitoring stations are presented in Tables 2 6 and 2 7 of Vol. II, and lo-would provide a quick and reliable method to deter-cations are shown in Figs. 2-4 and 2 5, Vol. II.

mine external gamma radiation doses to population groups within an 8,000 square mile area in the Radiation levels above background were detected at vicinity of SRP, Five Panasonic TLDs are placed at the fencea around operating facilities. The maxi-each station with a 90 day collection cycle. The mum was 1.6 mIVday around 11 Area which reflected TLDs are placed at stations up to a 100 mile radius radiation from process equipment or work being per-from SRP. The number of stations and their loca, formed inside the area. The F-Area Separations tions are shown in the table below:

maximum was 0.55 mIVday.

No. of Location TLD Stations Plant Perimeter Radioactivity Stations. In ad-dition to the monitoring stations described on p. 9, Onplant 100 there are 12 plant perimeter stations which monitor Plant Perimeter 174 gamma radiation levels and tritium concentrations.

SC Cities and Towns 48 These stations supplement the plant's emergency GA Cities and Towns 30 response capability by continuously measuring and periodically reporting gamma radiation levels and Changes to 1987 51onitoring Program. During tritium concentrations from each 30' sector around 1987, the environmental TLD program changed SRP. The gamma monitors are capable of detecting from using SRP-designed TLDs to using Panasonic.

radiation levels from 10 pinr to 1,0001%r. The 901 TLDs (described in Chapter 8). Both types of tritium ion chambers can detect tritium concentra.

TLDs were used through the third quarter of 1987, tions from 1 x 10 *pCi/mL to 1 x 10 a pCUmL.

with a complete conversion to the Panasonic TLDs in the fourth quarter.

The monitors are housed in temperature-controlled buildings. Using a U.S. Geological Survey satellite hionitoring Results. Environmental gamma ra-telemetry system, each monitoring station trans-diation fields vary significantly from one location to mits data at least once per day. Should an emer-another because ofdifferences in the terrestrial and gency occur, th e monitors can be set to transmit data I

cosmic compon ents of the natural background radia-at six minute intervals. The data are transmitted to tion. The difTerences are influenced by the decay the WIND (Weather INformation and Display) sys-products ofradium and thorium in the soil. The table tem computers an d integrated into the overall emer-below provides a comparison of 1987 TLD results gency response system.

i Comparison of 1987 TLD Gamma Radiation Measurements with 1986 Results 51aximum 511nimum Average No. of (mIUyr)

(mluyr)

(mIUyr)

Identification Locations 1986 1987 1986 1987 1986 1987 Plant Perimeter Stations Air Sampling Locations 13 84 135 47 47 73 73 1 Mile Intervals 79 106 135 29 40 44 69 254 tile Radius 12 84 113 47 51 58 77 10041ile Radius 4

204 124 40 62 84 95 Cities and Towns (South Carolina and Georgia)

Inside Buildings 62 803' 219 37 47 113 113 Outside Buildings 62 226 164 33 47 100 102 j

l Result of one unexplainably high value at the inside location in Columbia, SC *Shandore Other measurements during the year at this location were within normal ranges.

2. Air Monitoring Program 17 hionitoring Results. Atmospheric Capacity of emissions of sulfur dioxide, oxides of

?

No. of Each Boiler nitrogen, and total suspended particu.

I Power Plant Location Boilers 10" Btu /hr Input lates from power plants at SRP were within applicable standards in 1987.

A Administration Area 2

71.7 Compliance with the sulfur dioxide D-Powerhouse Area 4

396 (SO,) emissions standard at power li-Separations Area 3

71.7 plants is determined by analysis of th e J

K Reactor Area 2

194.5 coal received.The sulfur content ofcoal P-Reactor Area 2

194.5 burned at SRP in 1987 averaged 1.0%,

which yielded an average of 1.73 lb SO/108 Blu input. This is 49% of the South Carolina standard.

NONRADIOACTIVE 310NITO~ RING The day-to-day control of total suspended particu-Atmospheric Emissions lates and oxides of nitrogen is maintained by use of opacity meters in all SRP powerhouse stacks.These Description of hfonitoring Program. Five coal-measurements indicated that SRP boilers were fired power plants located at SRP burned a total of within limits more than 99% of the time in 1987.

452,980 ton s of coal in 1987. The location. number of boilers and capacity of each boiler for each of these Compliance with standards for oxides of nitrogen plants are listed in the table above.

and total suspended particulates is determined by

[

periodic air compliance tests conducted every two l

The four D Powerhouse Area boilers use pulverized years by specialists in air emissions testing under coal; all of the other boilers are stoker fed. The D-contracts issued by SRP. All SRP boilers were within Powerhouse also burns waste oll. The content of the compliance limits during the latest series of tests coal delivered to the site for burning is determined conducted in the second half of 1987.

by analyses for sulfur, carbon, ash, water and Btu output.

A new regulation limiting opacity of oxides of nitro-gen went into efTect in February 1986. As indicated There are six other onsite process stacks with major in the table at the bottom of the page, the new stan.

l emissions of nonradioactive materials. They in-dard is 20%, except for stacks that existed before

)

clude th ree 313-51 stacks and one 32141 stack in the January 1,1986, and powerhouse stacks built before hi Fuel Fabrication Area and the two 291 stacks in February 11,1971; these existing stacks are subject the F. and H-Separations Arcas.

to a 40% opacitylimit. AllSRP process stacks,includ-ing the four 30041 stacks and 291 F and H stacks, Applicable Standards. Nonradioactive at-are subject to the 40% limit. In 1987, all stacks met i

mospheric emissions from SRP stacks are regulated the 40% opacity requirement except for the 291 F l

by permits issued by the South Carolina Depart-stack, which oecasionally exceeded the limit. Rework ment of Health and Environmental Control of the deteriorating acid abc.orption column in 291 F (SCDHEC). Air Emissions Standards are listed stack reduced the opacity of the stack to borderline

below, compliance. A number of programs (including a multi million dollar absorber column contro1 project) are being pursued to ensure that theopacityis below40% on alloc.

Sulfur dioxide 3.5 IW108 Btu m.put easions. The absorber column Total suspended particulates 0.6 IW108 Btu input project is scheduled for comple.

Opacity 40%*

tion in December 1989.

j i

Applicable for process stacks in existence prior to January 1,1986' In December 1987, SCDHEC and powerhouse stacks built before February 11,1971, when these conducted an compliance inspec-standards beconw effective. For stacks that came on line after tion of all permitted air emission these dates, the standard is 20%.

sources. All emissions were within applicable standards.

\\

18 SAVANNAH RIVER PLANT - Environmental Report for 1987 ticulates, sulfur dioxide, oxides of nitrogen, and ozone.The operation of these stations is consistent with requirements of the EPA and SCDilEC. Addi-

?

i

=

l

'D*

tion al monito ring of ambient air quality near SRP is W-performed by the states ofSouth Carolina and Geor-gin as part of the network associated with the Clean g

Air Act Amendments of 1970.

y l

Chan ges in 1987 hionitoring Pmgram. Changes m the 1987 monitoring program were as follows:

E Two ambient monitoring stations were discon-tinued on June 30,1987, bringing the total number of monitoring stations to four. The two stations,614 37G and 614-36G, were ye discontinued as the result of a technical 5g reevaluation of the program.

==

..?

E Existing samplers for total suspended par-r" ticulates were modified by installing FM size l

g l

selective inlets. These inlets allow only par-ticulates of 10p and smaller to impact the filter paper.

E During the second quarter, barometers were Ambient air monitor mstalled m all air momtoring stations to i

I Ambient Air Quality make current barometric data available throughout the day.

j Description of Monitoring Program.The qual.

E Data management computer sonware was up.

ity of air at SRP is monitored at several locations graded to provide automatic creation of data-l around the site that measure total suspended par.

base space for the upcoming year.

I I

Air Quality Standard I

South SitP Percent

Carolina

Georgia Maximum Standard Sulfur dioxide ( g'm )

8 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1300*

1300 146 11 4

j 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 365' 365 53 14 Annual 80 80 6

8 i

Total suspended

]

particulates ( g/m')

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 250 150 120 80 Annual geometric

{

inean 60 75 38 63 j

Ozone (ppm)

I 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.12d 0.12 0.100 83 l

Nitrogen dioxide (pg'm$)

I Annual 100 100 7

7 l

i

Compared to the most restrictive standard, j

Lead, carbon monoxide and gaseous fluorides are not monitored twauw the potential relea* is insignificant compared to the standard.

' Not to be exceeded more than once a year.

Not to be exceeded more than one day a year.

4 4

1 l

2. Air Monitoring Program 19 Applicable Standards. Georgia and South Caro-2-6, Vol. II, and monitoring data are presented in lina air quality standards are shown in &c compari.

Table 2 8, Vol 11.

son table on the bottom of p.18.

The late st available ai r quality mea sure ments of th e MonitoringIlesults. Listed in the same table is a South Carolina and Georgia network monitored by comparison of monitoring data from the SRP ambi-the states in the vicinity of SRP are presented in ent air monitoring stations with Georgia and South Tables 2-9 and 2 10 of Vol II. The measurements in-Carolina stande ds, dicate that the air quality near SRP is good and well within the EPA standards.

The locations of the SRP monitoring stations and an alyses performed at each station are shown in Fig.

1987 HIGHLIGHTS E Onsite tritium concentrations in air ranged from 6.5 to 7,200 pCi/m2. The maximum value was detected at the H-Area monitoring station. Tritium was the only radionuclide of plant origin routinely detected offsite in air.

E No significant difference was noted between average measurements of plutonium in air at the site boundary and offsite. The highest values were detected onsite near the F and H Separations Areas, but were within ranges observed in previous years.

E The maximum dose commitment to a hypotheticalindividual at the SRP boundary from atmospheric releases was 0.6 mrem (0.006 mSv), or 0.2% of the normal average dose of about 295 mrem (2.95 mSv) from natural radiation sources. The average dose commit-ment to a hypothetical individual at the SRP boundary from atmospheric releases was 0.3 mrem (0.003 mSv), or 0.09% of the normal average dose from natural radiation sources.

E Continuous measurements from 350 monitoring stations provide a quick and reliable method to determine external gamma radiation doses to population groups within an 8,000-square mile area in the vicinity of SRP, E The 12-station plant perimeter radioactivity monitoring system is capable of continuously measuring gamma radiation from 10 pR/hr to 1,000 R/hr, and tritium levels from 1 x 104 pCi/mL to 1 x 10-2 pCi/mL E The sulfur content of coal burned at SRP in 1987 averaged 1.0%, which yielded an average of 1.73 lb SO/10' Btu input. This is 49% of the South Carolina standard.

E Two ambient air rnonitoring stations were discontinued on June 30,1987, bringing the total number of monitoring Stations to fout.

3 Surface Water Monitoring Program SUMM ARY - This chapter describes the radioactive and nonradioactive monitoring of surf ace waters on and around SRP, summarizes the results of these surveys, and compares l

the results to the applicable standards. The Savannah River and all streams located on the SRP site are continuously sampled to monitor radioactivity released in effluent water from SRP f acilities. This comprehensive program consists of monitoring at 35 SRP stream loca-tions and six Savannah River locations for alpha, nonvolatile beta, tritium, and a variety of i

specific radionuclides. Water samples from seepage basins in the F, H, P, K, L, and C Areas, l

which generally reflect concentrations observed in the wastewater released to the basins, were also monitored. Liquid releases and concentrations of radioactive materials, including an inventory of tritium released, are summarized, and offsite radiation doses from these liquid releases are calculated. The highest potential dose commitment from releases of radioactivity from SRP to the Savannah River to a hypotheticalindividualis 0.9 mrem (0.009 mSv), which is 0.3% of the annual dose Commitment of 295 mrem (2.95 mSv) received from natural radiation sources. Surf ace water is monitored nonradiologically for chemicals, metals, tem-perature, and other physical and biological properties. Operational effluents f rom SPP f acilities discharge through 68 active point source outf alls under a SCDHEC permit. River quality surveys conducted by the Academy of Natural Sciences of Philadelphia are described, and results of river and stream temperature profile surveys are reported.

1L J

ltADIOACTIVE MONITORING Applicable Standards. DOE derived concentra-tion guides (DCGs) for surface water apply to SRP Savannah Itiver releases to the Savannah River (Table 31 on p. 23).

EPA drinking water standards apply at the down.

Description of Monitoring Program. The rivcr water treatment plants.

Savannah River is continuously sampled with pad-dlewheel samplers at strategic locations above, ad-Monitoring Results. In 19S7, no measurable dif-jacent to, and below SRP in order to monitor radio-ferences were detected between upriver and down-activity released to the Savannah River via SRP river alpha and beta concentrations in the Savan-streams.The river sampling locations are presented nah River. Alpha and nonvolatile beta concentra-in Fig. 3-1 on p. 22 (also in Vol. II). River flow is tions in river water samples at stetions R-2 (upriver) measured with United States Geological Survey and R 10 (downriver) were determined in both dis-(USGS) flow recorders at sampling stadons R 2 solved and suspended portions of the samples. Aver-above SRP and R-10 below SRP. The sampling age concentrations of alpha activity were near or program consisted of six samplinglocations in 1987.

less than the minimum detectable concentration of approximately 0.3 pCi/L. Maximum nonvolatile The continuous river paddlewheel samples are beta concentrations for 1987 (excluding tritium) generally collected weekly for analyses of alpha, ranged from 0.88 to 4.1 pCi/L, compared to a range nonvolatile beta, tritium, and a variety of s pecific ra-of 1.3 to 6.0 pCi/L in 1986. River monitoring data are dionuclides. The frequency and type of analysis presented in Table 31, Vol. II.

varies from location tolocation and isbased upon the potential quantity and type of radioactivity likely to The release of tritium accounted for more than 994 be present. The sample locations and frequencies of of the total radioactivity introduced into the Savan-analysis change from time to time to accommodate nah River from SRP activities during 1987. Fig. 3 2 changes in SRP operations and variations in radio-on p. 23(alsoin Vol. II) shows tritium releases at the logical conditions.

source for the years 1983 through 1987. Tritium

22 SAVANNAH RIVER PLANT - Environmental Report for 1987

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c Fig. 31. Stream and river sample locations

I l

3. Surface Water Monitoring Program 23 measured in tran sport in the river w as Table 31. DOE Derived Concentration Guides For 26,145 Ci in 1987, compared to 22,120 Surface Water (pCi/L)*

Ci m 1986. The average river flow in 1987 was about 10,328 ft%ee, which is II 3 2,000,000 Cs 134 2,000 146"c of the 19S6 flow rate of 7,070 ft%ec. ARer dilution by SRP streams C-14 70,000 Cs-137 3,000 j

and the Savannah River, tritium con-Co-58 40,000 Ce 141 50,000 centrations m 1987 averaged 3.3 pCi/

mLin the river below SRP at Ilighway Co-60 5,000 Ce 144 7,000 301 compared to 3.9 pCi/mL in 1986.

Sr 89 20,000 U 235 600 j

The higher river flow rate in 1987 ae-I counts for the fact that the average Sr 90 1,000 U 238 600 j

tritium concentration in the river in Zr 95 40,000 Pu-238 40 i

19S7 was lower than in 19S6 even l

though the amount of tritium released Nb-95 60,000 Pu 239 30 i

to the river was greater.

Ru 103 50,000 Am 241 30 Savannah River water is routinely Ru-106 6,000 Cm 242 1,000 l

monitored for gamma emitting radi-I-129 500 Am-243 30 onuclides by concentrating the radio-activity in about 20 liters of water on I131 3,000 Crn 244 60 ion exch ange column s. lon column s are counted directly for gamma emitters and then chemically analyzed for radi-Department of Energy draft order DOE 5480.XX for i

j ostrontium. The only radionuelide soluble forms.

other than tritium detected in river water by routine analytical techniques i

was *'Sr in trace quantities. Routine m g-analytical techniques are described in

(/

i _,

Chapter 10. Other radionuclides may

! 7/jV be detected by ultra-low level analysis y

V j

a l

techniques.

rw F////.

i The quantity mea sured in transport in F/,

/ V I

the river was 2 2 Ci of *~Sr in 1957.This l

amount of *Sr corresponds to concen-m

/:

/

J trations in the river below SRP that

/'

'M/4 are indistinguishable from worldwide d

1 fallout levels of

Sr detected upriver of jm SRP. The average concentrations of l

Sr both upriver and downriver ofSRP were less than the minimum detect-

,y a w, able concentration of 0.3 pCil(aver.

ages of data include zeros for observa-tions below lower limits of detection y

i I

and negative values that sometimes result from instrument background m

~

corrections; see Chapter 11).

i j

SRP Streams no i.e im

,m, Description of Monitming Pro-gram. All streams Isated on the Fig.3 2. Tritium releases at source SRPsite are contino,asly sampled at

l 24 SAVANNAll It1VEll PLANT - Environmental lleport ART dioactivity in stream water, b.

Idition, offsite surface water was sampled to pro-vide background data Ii.e., data from com-

'( '[ > N parable waterways that are unhkely to

?g have been significantly influenced by SitP operationd. A good indication of back-t ground radioactivity concentrations in oil,-

site surface water similar to SitP strearns is provided by radioactis ity meas u reme nt s in the Edisto liiver, a small river that is similar in many characteri tics to SltP streams. The masimum concentrations i

detected in the Edisto Itiver during !!h7 7y @ N@ s-page.

j'We-are show n in Table 3 2 at the bottom of the Stonitoring Ilesults. Stream nwnitoring data are pre ented in Table 3-2, Vol.11.The use of background values and Drgs pro-vide refere n ce s for evalua ting st re a m d ata.

Savan nah Itiver Table 3 3 at the bottom of the facing page presents masimum, average, and mini-strategic location s to monitor radioactivity released mum radioactivity values for plant streams and the in eflluent water from SitP facilities. This compre.

Edisto ltiver. Direct liquid tritium relea es to plant hensive program consists of monitoring at 35 pitP streams for the year 1%3 through 1%7 are repre-stream localicns. Stream sample locations are pre-sented in the top right colu mn of p 25 in Fig. a.3 < also sented in Fig. 31. At mostlocations stream flow s are in Vol.1D.

determined with L'SGS 11uw recorders. Sampling is maintained on all major streams near Itcad A Tims Branch (Till received etiluents from the 51-(lligh w ay 125), a convenien t monitoring location be.

Fuel Fabrication Area and SitL SitL releases were fore the streams exit.he SRP site.

negligible. The St. Area eflluent contained small quantities of uranium. The aserage alpha and non.

The continuous samples are generally collected vcdatile beta concentrations in the 51 Area efiluent weekly for analyses of alpha, nonvolatile beta, trit.

w ere 3 3 and 7.2 pri. L, respectively. St. Area re-ium and numerous specific radionuclides. The leases to Tli tiow downstream and enter l?pper analyses vary in frequency and type from one loca.

Three Ituns Creek it'altt Average alpha and non.

tion to another and are generally based upon the volatde beta concentrations in TH, before entering potential quantity end type of radioactivity. The U3R, were 0 41 and 1 A pct L, re. pectively. These sample locations and frequencies of analyses are concentrations are within the ranges ob erved in sometimes changed in accordance with changes in control samples from the Edisto ltiver.

SRP operations and variations in radiological l

conditions.

Table 3 2. Background Radioactivity Levels in Changes in 19871*rogram. During 5f arch Offsite Streams' 19s7, a continuoua sampler was installed in 1

Crouch Branch to monitor stormwater runctT Maumum concentrabon in 10%,

Radiation t pe (pC t 1.)

from the northeast side of the ll+,eparations i

Area. Crouch Branch is a tributary of l?pper Alpha 15 Three Runs Creek (see Fig 31).

Non.claMe beta 29 Applicable Standards. The DOE IX?Gs (Table 311 apply at the site boundary, which is pated on meassents tven n t"e f d sta R or a the b,avannah River. IK,G,s, how es er, are rea Pu4 y b SRP s' m sonable refert nces for ganging the impact of ra-

)

1 2,

---_,,c-_....

.m

3. Surface Water Monitoring Program 25 Upper Three Runs Creek (U3R) also receives storm.

water runoff from parts of the F-and II. Separations Areas. During January 1987, elevated alpha and nonvolatile beta concentrations were detected in samples from U3R at Road C. These concentrations were attributed to a solvent release that occurred when a solvent sump area in the II Separations a <=

Area overCowed. The maximum concentrations of 5

5OL alpha and nonvolatile beta for 1987 in U3R (due to this release) were 1.5 and 2.6 pCi/L, respectively.

These concentrations are within the ranges ob.

served in the Edisto River.

Bea rer Dam Creek (B DC) received efnuen ts from the heavy water rework and laboratory facilities in 400-D Area. Tritium oxide was the principal radionu-e clide released. Tritium concentrations in BDC ranged to a maximum of 360 pCUmL. The average tritium concentration in BDC for 19S7 was 19 Fig.3 3. Direct tritium releases to streams pCUmL. Average alpha and nonvolatile beta concen-excluding scepage basin migration trations in BDC for 1987 were 0.08 and 1.9 pCUL respectively, within the ranges observed in the Tritium concentrations in F51C ranged to a maxi-Edisto River, mum of 5,200 pCi/mL at F51-1C which contains releases from Il-Separations Area. This maximum Four Mile Creek (F31C) received efDuents from fuel concentration, which occurred in February 1987, reprocessing facilities in the F and li-Separations was attributed to a release from the tritium facili-Areas and from the C-Reactor Area. C Reactor was ties. A thermal diffusion column wall failed, con-not in operation in 1987 and released only 3.8 Ci of taminating process cooling water that was subse-t ritiu m in liquid efiluent relea ses for the entire year.

quently released to F51C. This event resulted in a Four 51ile Creek also ceceived tritium and "Sr mi-release of 156 Ci of tritium to F5tC.

grating from the F-and II Separations Area seepage basins and the Solid Waste Storage Facility (Burial The maximum of the averaged concentration s at the Groun d).

F5tC sampling points was 2,400 pCi/mL After dilu-Table 3-3. Radioactivity In Plant Stream Water AIch a (DCiO Nonvotatile Beta f oCI'L)

Tritium f oCi'mL)

Locationa Mn Min Ayg Mn Mjn Ayg Mu Min Ayg Tims Branch 1.7

-0.08 0.37 4.6 0 85 1.6 2.8 0.38 1.1 Upper Three Runs 1.7 0.00 0.56 11 0.58 3.0 3.3 1.6 2.4 Beaver Dam Creek 0.54

-0.23 0.08 3.4 0.42 1.9 360

-0.01 19 Four Mile Creek 15

-0.16 0.72 140 8.7 35 3,300 34 1,020 Indian Grave Branch 0.41 0.00 0.18 1.8

-0.26 0.82 9,600 62 5.371 Pen Branch 0.38

-0.08 0.07 2.8 0.49 1.6 66 7.9 13 Steel Creek 0 69

-0.08 0.16 11 0.95 5.1 70 1.6 26 Lower Three Runs 0.91

-0.16 0.09 7.1 0.58 4.1 12 0.77 6.6 Control Edisto River 1.5 0.00 0.51 2.9

-0.06 1.0 0.94 -0.42 0.41 l

'Does not include emuent samphng pnts.

i

26 SAVANNAH RIVER PLANT - Environmental Report for 1987 Steel Creek 31onitoring Data 1985 1980 1987 Analysis Stax Avg 51ax Avg Stax Avg Alpha, pCi/L 0.69 0.14 0.78 0.15 0.41 0.10 Nonvolatile Beta, pCL/L 8.9 4.0 6.3 2.4 3.5 2.0 Tritium, pCUmL 17 8.6 4.7 2.5 4.5 2.8 Sr 89,90, pCUL 0.04 0.33 0.75 0.13 0.51 0.11 Cs 134,137, pCUL 9.3 3.5 3.7 0.87 3.2 0.32 tion by other water in F51C, the average concentra-nonvolatile beta, and 4.1 pCi/mL of tritium. These tion of tritium in F51C before entering the river concentrations for 19S7 were essentially unchanged (Road A) was 590 pCi/mL.

from 1986.

Indian Grace Branch (IGB) receives tritium migra-There were no radioactive releases from TNX Area.

tion from the K Reactor containment basin. IGB Radioactivity concentrations in the TNX Area out-dows into Pen Branch (PB) which also receives heat falls were at or near background ranges.

exchanger cooling water from K-Reactor Area. The maximum tritium concentration was 9,600 pCUmL Scepage liasins at samplin g location IG B-21, which is downgradient from the containment basin, ARer dilution, the Description of 31onitoring Program. Seepage maximum tritium concentration measured in PB basins are shallow, earthen excavations used to at Road A was 66 pCi/mL. Alpha and nonvolatile receive wa stewate r containin g low con ce nt ration s or beta concentrations in PB at Road A were at or near chemicals and radionuelides. The wastewater seeps background ranges, downward through the sides and door of a basin to Steel Creek received radioactive releases from the w

migration of tritium from P Reactor Area seepage basin and from emuents from L-Reactor Area. These C

releases enter L Lake, which overnows to Steel Creek near Road A. 51ost radionuclide concentra-tions in Steel Creek below L Lake represent notable decreases from their 1955 levels. The decreases likely resulted from the inereased 0cw of river water used in L Reactor. Staximum and average concen-3 trations for Steel Creek are presented in the table at jg the top of the page.

Par Pond receives P Reactor heat exchanger cooling water and other eMuents from P Area. Par Pond also e

receives all storm sewer outfalls from the de-activated R Area and from a few storm sewers from P Area.The average concentrations detected in Par Pond water in 1987 were 0.32 pCi/L of alpha,5.9 pCUL of nonvolatile beta, and 9.3 pCi/mL of g

tritium.

r

=

The overCow from Par Pond goes to Lower Three Runs Creek (L3R) Sf aximum concentrations in Fig. 3-4. Tritium migration from L3R at Road A were 0.23 pCi/L of alpha,5.7 pCUL of seepage basins

. ~ -.

3. Surface Water Monitoring Program 27 the shallow groundwater. ARer mixing with the 51easured migration of tritium in 1987 was 2,760 Ci groundwater it generally flows slowly in a horizon-from F Area seepage basins (56% increase from tal direction, eventually outcropping into a surface 1986),6,150 Ci from Il Area seepage basin 4 and the stream. Daring its slow travel through the soil, the Solid Waste Storage Facility (18% increase from wastewater loses some ofits contaminants by pre.

1986), and 5,630 Ci from the other ll Area seepa;e cipitation, filtration, adsorption, ion exchange, and basins (24% decrease from 1986),

radioactive decay (StS31.

The quantity of tritium migrating from all seepage Water samples from seepage basins loevted in F,11, basins to SRP streams was 18,266 Ciin 1987, com.

P, K, L, and C Areas generally reneet concentrations pared with 20,627 Ci in 1986, an 11% deercase. The observed in the wastewater released to the basins.

tritium migrating from seepage basin represents The settling basin at 300 51 Area was taken out of 80% of the total SRP tritium released to streams.

service in July 1985, when the Liquid Efiluent Treatment Facility (LETF) was placed in operation.

The amount of *Sr migration was 0.19 Ci from F-Wastewater is released to Tims Branch aRer treat.

Area seepage basins and 0.08 Ci from Il Area seep-ment in the LETF The results of seepage basin age basins. Cesium 137 migration,ifit occurs, can-sample analyses are presented in Table 3 3, Vol. II, not be measured because of the deorption of"'Cs in an d the seepage ba sin location s are shown in variou s the stream bed from previously released "'Cs.

figures in Vol.11. Fig. 3-4 at the bottom of p. 26 (and Desorption is calculated by subtracting the F-and in Vol.11) shows tritium migration from scepage ba-Il-Separations Area contributions (sampling loca-sins for the years 1983 through 1987, tio'is F513, F51 1C, F51 1B) from the total curies of

"'Cs at F51 A7. On Stay 1,1987, F311B showed 511gration of Radioactivity from F and ll Area elevated nonvolatile beta and "'Cs concentrations.

Seepage Basins and K Area Containment This sampling point receives stormwater runoff Hasin. Tritium was the only radionuclide detected from the II-Waste 51anagement Facilities and the migrating from the K Area containment basin to 28811 Ash liasin, and water from the Il Area pow.

Pen Branch. Weekly Cow tr.casurements combined erhouse. Yhe "'Cs concentration in this sample was with tritium concentrations measured in Indian 1.0 pCUmL. Sample points downstream of F31-1B Grave Branch (a tributary of Pen Branch) indicated did not show elevated "'Cs concentrations. Since migration of 3,600 Ciin 1987. This quantity repre.

this result affects the transport calculation, it was sents a 414 decrease from 1986. This migration is assumed that the "'Cs was deposited in the stream subsequently diluted by heat exchanger cooling bed. Cesium-137 was not detected in the efiluent water from K Reactor Area before entering the (llP-52) from Il-Separations Area, and thus this

river, release was nwst likelv due to stormwater runoff j

from a contammated area. Steasurements of radio-51igration of radioactivity from F and ll Separa-activity in transport at sample points on Four Stile tions Area seepage basins was measured with con.

Creek indicate an estimated desorption of 0.02Ci tinuous samplers and Gow recorders in Four Stile of "'C s.

Creek. Graundwater from the F-Separation Area seepage basin s outcrops into Four 51ile Creek (FS!C)

Stigration of radionuclides from seepage basins is between sampling locations F51-3A, F51-2B, and presented in Table 3-4, Vol. IL Radioactivity in F51.A7. Stost of the II Area seepage basin outcrop-transport at sample points on Four Stile Creek and ping from basins 1 through 3 occursbetween F51-1C desorption of"'Cs from Four Stile Creek are shown and F5128. Flow measurements at F512B were in Table 3-5, Vol. II.

estimated from F512,because beaver dams periodi-cally backed up the water near F512B, causing false 51igration from P and C Area Scepage Danins, flow measurements. Additional outcropping from Liquid purges from the P. and C Reactor area disas-Il-Area seepage basin 4 and the Solid Waste Storage sembly basins have been released to their respective Facility occurs between F51-3 and F513A. The ra-seepage basins since 1978. Purge water is released dioactivity from these two sources mixes, and radio-to the seepage basins so that a significant part of the activity from the two sources cannot be distin-tritium can decay before the water outcrops to sur-guished. Four Stile Creek sample locations are face streams and flows to the Savannah River. The shown in Fig. 3-1 (also in Vol. II).

delaying action of the ha. ins reduces the dose that

i 1

28 SAVANNAH RIVER PLANT - Environmental Report for 1987 users of water from downriver treatment plants Inventory of Tritium Heleased receive from SRP tritium releases.

A comparison of the amount of tritium released from During the period between 1970 and 1978, disas-SRP facilities in 1987 with the amount of tritium sembly basin purge water was released to SRP measured in transport in SRP streams and in the streams, but the seepage basin s had been previously Savannah River continued to show relatively good used for purging the disassembly basins (from the agreement. Point-of release measurements are cal-1950s to 1970). The earlier experience with scepage culated from known concentrations contributed to basins indicated that the extent of radioactive decay the streams. Stream transport is measured at the during the holdup was suMcient to recommend their last sampling point before entry into the river.

reinstatement in the P and C Areas.

Results showed that point of release and stream transport measurements agreed within 9% and that Equipment was installed at locations downgradient the point of release measurements were less than from each basin to measure tritium migration from the river transport measurements by 16%. The the P and C-Area seepage basins. Results from cau;,e of small differenres is due to statistical uncer-paddlewheel samplers installed on Twin Lakes and tainties associated with measurements. Tritium Castor Creek at C Area indicated no measurable tri-inventory in the streams and in the Savannah tium that could be attributed to migration from the River is summarized in Table 3 6, Vol. II, C-Area seepage basin in 1987. Results from a pad.

diewheel sampler installed on Steel Creek, above L Sources of tritium in liquid emuents include direct Lake, indicated 130 Ci of tritium migrating from the releases from plant facilitie (20% in 1987 compared P Area seepage basin during 1987.

with 26% in 1986) and migration of tritium from the 15o

+ Relea ses

- - Transport in Streams j

-*- Transport in rher I

J l

100 -

e I

3 8

1 5

So -

i t

l 1

l i

o 1960 1965 197o 1975 1980 1985 1987 Year Fig. 3 5. Tritium balanee summary 19601987

.i

L 2

3. Surface Water Monitoring Program 2D trations in streams ar.d the river were not available.

The minimum detectable concentration for the vi-brating reed electrometer, used at that time, was f

1,000 pCi/ml. Liquid scintillation counters, devel.

oped in the late 1950s, made low level measure.

ments practical (the minimum detectable concen-I tration is now 1 pCUmL).

llllqll19 SRP began routine use ofliquid scintillation count.

.I W

ing in 1959 and made river and stream measure-

/

mentsbeginningin thelast halforthatyear During j'

/

some of the early years (1960-106 t), noticeable dif.

0

/

fewnees occurred between releases and the amount t

of tritium measured in streams and the river.This discrepancy led to additional efUuent monitoring Liquid scintillation counter pomts where small amounts of tritium were re-Burial Ground, F, II, and P-Area seepage basins, leased (miscellaneous reactor releases), and the and K-Area Containment Basin (807t in 1987 com.

measurement ofleakage from reactorheat exchang-pared with 74% in 19S6). Migration occurs when ers to accomplish further sampling redements, tritium released to the seepage basins in previous years reaches SRP streams via groundwater out-As shown in Fig. 3-5, tritium releases to the Saum-cropping into the streams, nah River have decreased signincandy since 1964, when the maximum tritium releases occurred.

Relatively good agreement in the inventory of trit.

Process control improvements that have led to this lum measured at three locations (the point of re-decrease are:

lease, plant Streams before entry into the river, and the river below SRP) has been achieved each year a Change from continuous pur, of reactor since the statistics have been compiled (1960) as aran disassembly basins to peuvdie purges shown in Fig. 3 5 at the bottom of p. 2S (also in Vol.

in the Inte 1960s, allowinglonger holdup

!!). A tritium inventory summary from 1960 to 1987 time for decay, some evaporation, and a i

is presented in Table 3 7 of Vol. II.

larger inventory of tritium in the basi.o.

E Development of equipment and techniques Before 1959, low level measurement techniques to flush and contain tritium bearing nee..ed for routine measurements of tritium concen.

moderator present on fuel and target 1

TABLE 3-4.1987 RADIOACTIVE LIQUID RELEASES AND CONCENTRATIONS ll Curies Released Below SRPa Be auf ort-Jas cer*

Port Wentworth

At Emission Conc.

Conc.

Nuchde turgg pCi'mL pCemL LC!'mL H3

. 9E+04' 3.3 E-06' 2 2E-06' 2.3 E-06' l

Sr 90 4.0E 01 5 EE 10' 3 SE 11 4.CE-11 1129 2.2E 02 3.2E 12 2.1E 12 2.2E 12 1

I Cs 137 3 3E 01 3.CE 11' 3.7E 11 3.8E 11 i

U 235,238 5 SE 03 8 CE 13 5.3E 13 5 5E-13 Pu 239 1.8 E-02 2.6E 12 11E 12 1.6E 12

Savannah Rrver just downriver from SRP.

Beaufort-Jasper drinking water.

Port Wentwodh drinking water.

' includes releases to streams and groundwater mgraton from seepage basins.

Measured concentratons. All other concentrations were calculated using models that were verd.ed using i

i tntium measurements, i

1 1

30 SAVANNAH RIVER PLANT - Environmental Report for 1987 TABLE 3 5. MAXIMUM INDIVIDUAL radioactive material to liquid effluents.The average c ncentrations ofradioactive materialsin water are DOSES - LlOUID RELEASES shown at three locations, i.e. just below SRP after By Pathway complete mixing,in Beaufort-Jasper drinking wa-ter, and in Port Wentworth drinking water (both Maximum Individuala Percent of drinking water plants are approximately 100 miles downriver fr m SRP).

Pathway mrem

Total Dose majo% oMe concen tradons shown in Tame 3-Fish 8.48E-01 90.96 4 are calculated, rather than measured; the calcu.

Water 8.34E-02 8.95 Shoreline 8.68E-04 0.09 lated values are based on dilution of radioactivity Swimming 1.64E-06 0.00 entering the Savannah River with a known flow rate Boating 4.91 E-06 0.00 of water. However, measured concentrations are shown in those cases where the radionuclides are Total 9.32E-01 measurable by conventional analytical techniques.

Bv Radionuclide As shown in Table 3-4, the maximum concentrations occur in the Savannah River just below SRP. Trit-Maximum Individuala Percent of ium was the radionuclide having the highest offsite Radionuclide mrema Total Dose concentration.

H-3 8.32E-02 8.93 TABLE 3-6. INDIVIDUAL DOSES FROM PUBLIC 29 WATER SUPPLIES AT BEAUFORT-JASPER Cs 137 8.37E-01 89.81 U 235.238 8.01 E-05 0.01 Pu-239 5.54E-04 0.06 Averace Consumotion Total 9.32E-01 Ir:dividual Percent of Radionuclide Dose. mrema Total Dose Hypothetical person just downstream of SRP.There a

are no known persons who meet the hypothetical H3 5.13E-02 94.48 situation.

Sr-90 1.83E-03 3.37

Committed effective dose equivalent.

1-129 2.20E4 0.41 Cs 137 6.79E-04 1.25 U 235,238 4.51 E-05 0.08 housings during discharge from the reactor.

Total 5.43E-02 E Diversion of periodic disassembly basin purges from streams to seepage basins in Maximum Consumotion P and C Areas in 1978, allowing some radioactive decay of tritium before migra-Individual Percent of tion to streams via groundwater.

Radionuclide Rose. mrema Total Dose In addition, releases were reduced by the shutdown H-3 1.01 E-01 94.37 Sr90 3.61 E-03 3.37 of R-and I Area reactors in 1964 and 1968, respec-1-129 4.33E-04 0.40 tively.

Cs 137 1.34E-03 1.25 U 235,238 8.88E-05 0.08 Summary of 1987 Liqu.d Releases and i

Pu 239 5.50E-04 0.51 Concentrations Total 1.07E-01 Releases ofradioactive materials to the river m 1987 are shown in Table 3-4 on p. 29 (shown as Table 3-8

. Committeo effective dose equivaient.

in Vol. II). Tritium constitutes the major release of

~

3. Surface Water Monitoring Program 31 consume their entire daily intake of water from TABLE 3-7. INDIVIDUAL DOSES FROM water supplied by the Beaufort 4 asper and Port PUBLIC WATER SUPPLIES Wentworth water treatment plants, respectively.

AT PORT WENTWORTH The dose commitments for averege water consump-tion were 0.05 mrem (0.0005 mSv) for Beaufort.

Averaae Consumotion Jasper and 0.06 mrem (0.0006 mSv) for Port Wentworth; the dose commitments for maximum Individual Percent of water consumption rates for both Beaufort-Jasper Radionuclide Dose. mrema Total Dose and Port Wentworth were 0.1 mrem (0.001 mSv).

Doses for maximum water consumption are in.

H-3 5.36 E-02 94.38 cluded for comparison with the EPA standard for Sr-90 1.91 E-03 3.36 public water supplies of 4 mrem to the body or any I129 2.30E 04 0.41 organ. EPA standards are based on a maximized Cs-137 7.10E-04 1.25 water consumption of two liters per day.

U-235,238 4.71 E-05 0.08 Pu-239 2.92E-04 0.51 Population dose commitments from liquid releases of radioactivity in 1987 are shown by exposure Total 5.68E-02 pathway in Table 3 8 below (shown as Table 3-12 in Vol. II). Dose commitments from the water con-Maximum Consumotion sumption pathway (BeaufortJasper and Port Wentworth) occur to discrete population groups; Individual Percent of Radionuclide Dose. mrema Total Den TABLE 3-8. POPULATION DOSE FROM H3 1.06E-01 94.40 Sr 90 3.77E 03 3.36 LIQUID RELEASES l129 4.54E-04 0.40 Bv Pathway Cs-137 1.40E 03 1.25 U 235.238 9.30E-05 0.08 Population Dose Percent of Pu 239 5.76E 04 0.51 Pathway cerson-rema Tots! Dose Total 1.12E 01 Sport F;sh 2.22E+00 37.26 Cml. Fish 9.38E-02 1.57 Committed effective dose equivalent.

Beaufort 4 asper 2.51 E+00 42.12 a

Port Wentworth 1.13E+00 18.96 Offsite Radiation Doses from Liquid Weleases Salt Water Invert.

5.28E-05 0.00 Recreation River 4.72E-03 0.08 Table 3-5 on the facing page (shown as Table Total 5.96E+00 3-9 in Vol. II) shows the calculated dose commit-ments to a hypotheticalindividual who could receive By Radionuclide the highest ofTsite doses from releases of radioactiv-ity from SRE to the Savannah River. The maximum individualis described as a person who consumes an Population Dose Percent of average amount of water and a large amount of fish

.Radionuclide eerson rem' Total Dose i

from the riverjust downriver from SRP.'f his person H3 3.45E+00 57.89 i

also spends many hours m shorehne activities' Sr-90 1.43E-01 2.40 swimming, and boating. The highest potential dose 1-129 1.60E-02 0.27 commitment was 0.9 mrem (0.009 mSv). This dose Cs 137 2.32E+00 38.93 commitment is only 0.3% of the annual dose commit-U 235,238 3.06E 03 0.05 ment of 295 mrem (2.95 mSv) received from natural Pu-239 1.91 E-02 0.32 radiation sources.

Tota' 5.96E+00 Table 3 6 on p.30 andTable 3 7 at the top ofthe page (shown as Tables 3-10 and 311 in Vol. II) show Committed effective dose ecuivalent.

a calculated dose commitments to individuals who

32 SAVANNAH RIVER PLANT - Environmental Report for 1987 TABLE 3-9. POTENTIAL DOSES FROM grams sem as a backup to outfali monitoring to en-IRRIGATION PATHWAY sure that maten,als that could adversely affect the environment are detected if released.

Effective Dose Eauivalent Maximum Individual Liquid Effluent Monitoring (NPDES)

Food Tvoe m re m Description of Monitoring Program. Measure.

Vegetation 1.74 E-01 ments of physical properties and concentrations of Leafy Veg.

2.14E-02 chemicals and metals in SRP emuents are regulated MJk 7.76E-02 by SCDHEC under the National Pollutant Dis-Meat 2A3E42 charge Elimination System (NPDES). The NPDES program at SRP included monitoring at 68 active Total 2.97E-01 outfalls in 1987. In addition, new permits were requested for the F-Area EmuentTreatment Facil-ity (ETF) Holding Basin, the H-Area ETF Holding however, the dose commitments from other expo.

Basin, and the new Fuel Production Facility, sure pathways (i.e., fish and shellfish consumption and recreational activities) occur to a diffuse popu-Changes in 1987 Monitoring Program. Updates lation that cannot be described as beingin a specific on existing permits included the following:

geographical location. As shown in Table 3-8, the population dose commitment from liquid releases E Request for deletion of Biochemical was 6.0 person-rem (0.06 person Sv).

Oxygen Demand (BOD)(5-day) for K-Reactor Cooling Water Outfall; Radiation dose commitments are not routinely cal-culated for the irrigation exposure pathway because a mercury limit added for TNX there is no known use of Savannah River water for Emuent Treatment Facility; farm irrigation downstream of SRP. But capability for calculating offsite dose from the irrigation food a frequency change from weekly to pathways has been developed to provide potential monthly for Power Sanitary dose from irr'gation for informatinn purpoe>es. Po-Waste Treatment; tential doses from the irrigation pathway are shown above in Table 3 9 (shown as Table 3-13 in Vol. II).

M frequency change from monthly to annually for Par Pond stormwater.

The maximum individual dose commitment from j

the irrigation pathway was 0.3 mrem (0.003 mSv).

Applicable Standards. Standards applicable to This dose value is one-third of the maximum individ-nonradioactive materials and physical properties in ual dose of 0.9 mrem (0.009 mSv) calculated for all SRP wastewater discharges are contained in SRP's other pathways (fish consumption, water consump-NPDES permit administered by SCDH EC. Monitor-tion, and recreation).

ing requirements and standards can be found in permit SC 0000175 [SCDHEC85].

NONRADIOACTIVE MONITORING 1

Surface water is monitored for nonradioactive No.of No. of materials at emuent outfalls from site facilities.

Analysis Exceptions Outfalls at locations along the six site streams, and at three locations in the Savannah River. Opera.

Total Nonfilterable tional emuents from SRP facilities discharge Residue 6

6 through 68 active SCDHEC-per3itted, point Fecal Coliform 3

3 source outfalls. These outfalls are monitored to pH 7

6 eneu e a pplicable permitlimits are met. SRP also Oil and Grease 2

2 maintains an extensive network of stormwater outfalls. The stream and river monitoring pro-Totals 18 17

1

3. Surface Water Monitoring Program 33 Savannah River Description of Monitoring Program. The Savannah River is extensively monitored for chem-i icals, metals, and physical and biological properties.

l

~

Monitoring of the river above and below the site pro-i vides a means of determining concentrations of pol-3.h

[

lutants that may be discharged by ofTsite industrial 1

p/ 3(7 *p facilities upriver of SRP. Measurements confirm 1

s i~

- n, Tp that the impact ofSRP operations is minimal. Allin-3 gya." l4 dications are that SRP operations do not have a 4-1~'..

,5 [ '.V N,

3. '

'.~E

k< g#,

deleterious effect on the Savannah River aquatic

+ -

environment.

l

^

5',

Applicable Standards. Chemical and biological y

. f.

quality standards for the Savannah River are speci-I j.

4,

.y $

fled in the requirements of the State of South Caro-

r..

7*.

= '

' y -

lina for Class B streams, which are: *Frerhwaters

'd dm

. g ar*

suitable for secondary contact recreation and as a ip C.y y 7 source for drinking water supply after conventional y,

1 treatment in accordance with requirements of the

.7 Department (SCDilEC). Suitable for fishing, sur-e -

4'

~

vival, and propagation of fish, and other fauna and fiora. Suitable also for industrial and agricultural NPDES outfall uses"[SCDH EC81]. Specifications c re summarized Monitoring Results. NPDES outfalllocationt are in the table at the bottom of the page.

listed in Table 3-14, Vol. II, and a summary of moni-toring results is presented in Table 3-15,Vol. H. SRP had a 99.7% NPDES compliance rate in 1987, as Monitoring Results. A comparison of Savannah compared to a 99.4% compliance rate in 1986. Only River water quality analyses upriver and downriver 18 of the 6,560 analyses performed exceeded permit of SRP showed no significant differences except for limits. Listed at the bottom of p. 32 is a summary of fecal coliform. Fecal coliform levels were higher the 18 limits exceeded.

upriver of SRP than downriver. The average of the South Carolina Water Quality Standards (for Class B Waters)

Fecal Coliform. (The count is) not to exceed a geometric mean of 1000 colonies /100 mL based on five consecutive samples during any 30-day period; not to exceed 2000 colonies /100 mL in more than 20% of the samples examined during such period.

pH. Range between 6.0 and 8.5, except that specified waters may range from pli 5.0 to 8.5 due to natural conditions.

Temperature. Shall not exceed a weekly average temperature of 90 degrees F (32.2 degrees C) aRer adequate mixing as a result of heated liquids, nor shall a weekly average temperature rise of more than 5 degrees F (2.8 degrees C) above temperatures existing under natural conditions be allowed as l

a result of the discharge of heated liquids unless an appropriate temperature criterion or mixing zone has been established.

Dissolve <i Oxygen. Daily average not less than 5.0 mg/ liter with a low of 4.0 mg/L, except that specified waters may have an average of 4 mg/L due to natural conditions.

l 34 SAVANNAH RIVER PLANT - Environmer tal Report fe 1987 monthly geometric mean of fecal colift rm h5 [3 -

g*

g g

measurements was 600 colonies /100 mL

~~

s upriver and 196 colonied100 mL down-f river of SRP.The decrease is attributed to f'

removal of fecal coliform by the heating of 7

river water as it is passed through SRP

,e p reactor heat exchangers before it is re-

~

^

turned to the river. Savannah River water E

v s

quality data are presented in Tables 3-16

/'

and 3-17 of Vol. II. Samplinglocatior.s are

~

.S shown in Fig. 3-6 on the facing page (also

~~

in Vol. II).

k f

~}

Academy of Natural Sciences yS W

of Philadelphia - River Quality Surveys Changing diatom slides Description of 51onitoring Program.The Divi-In rivers adversely afTected by poHution, the number sicn of Environmental Research of the Academy of of species is teduced in varying s moun ts correspond-Natural Sciences of Philadelphia (ANSP), under ing to the degree of pollution. The less tolerant contract to Du Pont, has carried out continuing sur-species are eliminated, while the more tolerant spe-veys of th e aquatic environ ment and water quality of cies become dominant. While the total population the Savannah River upriver (Station 1) and down-may increase in size in a polluted river, the number river (Station 6) from SRP since 1951. Survey loca-of different species will be reduced. A summary of tions are shown in Fig. 3-7, Vol. II. These studies the results of the diatometer studies conducted in were expanded in 1982 to include Station 5, below 1987 by ANSP will be issued in 1988.

Steel Creek. The purpose of these studies is to determine the effect, if any, of SRP efiluent dis-Quarterly surveys of aquatic insects were also con-charges on general river health.

ducted by ANSP in 1987, during h! arch, June, Sep-tember, and November. In addition, algal and Three types of studies have been undertaken:

aquatic macrophyte surveys were conducted during the first (hf arch) and fourth (November) msect trap collection periods, and fish were collected during the E detailed surveys (every four years): these third (September) insect collection period. Data surveys study algae and rooted aquatic plants, from these continuous cursory surveys constitute a protozoa, macroinvertebrates, in sects, fish, chronological characterization of biological condi-and water chemistry; tions in the vicinity of the SRP. Results of the 1987 E continuous cursory studies of aquatic life cursory surveys will be issued during 1988.

(quarterly): these studies focus on algae, insects, and fish; Studies of the Savannah River in 1987 included a 1

E continuous surveys of diatom communi.

September comprehensive survey of the river in the tics (semi-monthly).

vicinity of Vogtle Nuclear Power Plant, which be-came operational in 1987. These studies encom-51onitoring Results. Diatometers are positioned passed protozoa, algae, rooted aquatic plants and in the river at three locations (one above and two macrophytes, non. insect macroinvertebrates, in-below the SRP site).They provide continuous moni-sects, fish and water chemistry. Stations surveyed toring of the efTects of SRP efliuents on diatoms, one were located above (reference) and below (impact) major group of river organisms. The diatometers the Vogtle Plant site discharge. Results of this study contain glass slides on which diatoms accumulate.

will be compared to resu'ts of previous preopera-The slides were replaced every two weeks and sent tional haseline studies conducted by ANSP in 1985 to ANSP for diatom community anc. lysis.

and 1986, and will be issued as a report in 1988.

g c; g

3. Surface Water Monitoring Program 35 U3R w

-278 Ea A

U3R at C Road F M

b E

g McQueen Branch k

c '

DWPF Crouch Pond 8 h

H

^

785 F

-- - Pond U3R c4 C

E Road A

(

FMA7 g

y

-Z- -Z^Z" R2 g*

P L

2 400-0 K

8 Eff 6

L u.

4 L3R PATT M 6

w.,

6815G PB3 f

6p g

/

9s#'g #

SC Road A O

e

(

t South 5

4 Carolina

^E R

S h

L3R at Tabernacle Chure I

0 2

4 6

8 odA Kilometers S Water Quality Sampling Locations R10 E Fecal Coliform Sampli g Locations Georgia Fig. 3 0. Water quality sampling locations i

l....

\\

36 SAVANNAH RIVER PLANT - Environmental Report for 1987 SRP Streams charged heated water to Four Mile Creek, was out of service in 1986 and 1987.

Description of Monitoring Program. SRP streams are extensively monitored for chemicals, During 1987, fecal coliform counts increased in metals, and physical and biological properties. The Pen Branch at Road A. The maximum count stream monitoring program helps en sure that mate-was 14,000 colonies /100 mL, cnd the geometric rials are not inadvertently released from sources mean was 684 colonies /100 mL.The K Area sanitary other than routine release points. Five principal outfall, upstream of the sample point, did not show streams traverse the SRP site and a sixth stream, elevated counts. The laboratory noticed a red over-Beaver Dam Creek, contains primarily water from growth on the Pen Branch samples that interfered the D Area powerhouse. D Area also has heavy-with the analysis. As a result, the analytical proce-water rework facilities and a process controllabora-dure was changed to another El A approved proce-tory.The streams receive varying amounts ofwaste-dure. At this time, the cause of the elevated counts water and rainwater runofifrom SRP facilities.

has not been determined.

In addition to SRP monitoring, SCDHEC collects Except for temperature and fecal coliform in Pen monthly samples from Tims Branch near Road C, Branch, all stream analyses were generally within Upper Three Runs Creek at Road A, Four Mile the South Carolina standards for a Class B stream.

Creek at Road A 7, and Steel Creek at Road A.

Stream water quality data are sammarized in Duplicate samples are collected at these locations Tables 3-17 and 3-18 in Vol. II, and sampling loca-for analysis at SRP.

tions are shown in Fig. 3 6 (also in Vol. II).

Applicable Standards. South Carolina water River and Stream Temperature Surveys quality standards for Class B waters apply to SRP streams (shown on p. 33).

Description of Monitoring Program. Tempera-ture profile surveys are conducted on the Savannah Monitoring Results. Analyses of SRP stream River and SRP streams as part of a comprehensive samples and measurements in the streams indicate study of the thermal efTects of SRP operations upon that, except for temperature in Pen Branch, the the waters of the state ofSouth Carolina as stated in water quality is not adversely affected by SRP op-consent order 84-4-W between SCDIIEC and DOE.

erations. This stream receives heated water from K-Reactor Area.The heated water from L-and P-Reac-Measurements in the creek mouths are taken at 2-tor Areas is cooled by L Lake and Par Pond, respec-ft. intervals across the creeks. At each of these inter-tively. The C-Reactor Area, which formerly dis-vals, stream temperatures are measured at 1 ft.

Temperature Data Maximum Consent Order Daily Temperature Maximum Allowable Above Ambient Above Ambient Mnnth Location

('C)

March Steel Creek 2.6 16.6 Beaver Dam Creek 9.9 17.5 May Steel Creek 2.0 16.6 Beaver Dam Creek 5.8 17.5 Sept.

Steel Creek 2.2 16.6 Beaver Dam Creek 4.4 17.5 Dec.

Steel Creek 0.0 16.6 Beaver Dam Creek 10.0 17.5 J

3. Surface Water Monitoring Program 37 depth intervals from the surface to the bottom. River ating. Temperature measurements in both Beaver measurements are taken at 10-20 ft intervals from Dam Creek and Steel Creek exceeded the ambient the South Carolina bank to the Georgia bank. At river temperatures but were within the consent each of these intervals, temperature measurements order limits shown at the bottom of p. 36.

are taken at one-ft. depth intervals from the surface to the bottom.

Data from this survey, together with past data, indicated that subsurface river temperature meas-The reference ambient temperature for the river and urements would also be significantly less than the the streams is determined from a temperature pro-limits setby consent order 84-4-W,which states that file 100 yards above the point where the first heated "the temperature should not exceed 2.8 C' above SRP efiluent (Beaver Dam Creek) enters the river.

ambient at the edge of 25% of the cross sectional area In addition to the temperature profile surveys con-and over 33% of the surface area."Therefore, addi.

ducted by SRP, the USGS has established continu-tional measurements for p ume definition in the l

ous monitoring stations for temperature measure-Savannah River were not necessary.

ments at the mouth of each SRP stream.

The elevated temperatures in Pen Branch men-Monitoring Results. During 1987, quarterly tem-tioned in a previous section are not reported in this perature profile surveys were made in the mouths survey. The mouth of Pen Branch is poorly defined and upriver of Beaver Dam Creek and Steel Creek, swamp area and was not monitored under this Surveys were not made in the mouth and downriver program.

cf Four Mile Creek, because C-Reactor was not oper-i 1

4 i

w.-+,

-,,-6,--,m--4.,. -

-,-,-y

.-+w-7 y+,--,---yy,-,,-,,

--=- -

-,-.e---w e,-

p-

,-e.-,.-y

-s-----

.,-.-,--,-,,-,,y,-

,m,--,,---w re-.

-w_,--

--p-,.

38 SAVANNAH RIVER PLANT - Environmental Report for 1987 1987 HIGHLIGHTS E in 1987, no measurable differences were detected between upriver and downriver alpha and beta concentrations in the dissolved or suspended portions of Savannah River samples.

E In 1987, tritium measured in transport in the Savannah River was 26,145 Cl, compared to 22,120 Clin 1986. After dilution by streams and the Savannah River, tritium concentra-tions in 1987 averaged 3.3 pCi/mL in the river below SRP at Highway 301, compared to 3.9 pCi/mL in 1986.

E Radioactivity in plant streams reflected contributions from SRP operations. Alpha, beta, and tritium concentrations in plant streams were comparable to values observed in past years.

k Most radionuclide concentrations in Steel Creek below L Lake represent notable decreases from their 1985 levels.

5 The quantity of tritium migrating from all seepage basins to SRP streams was 18,266 Ci in 1987, compared with 20,627 Ciin 1986, an 11% decrease. The tritium migrating from seepage basins represents 80% of the total SRP tritium released to streams, and direct release of tritium from plant facilities accounts for the remaining 20%.

5 The maximum radiation dose comnitment to an individual downriver of SRP who con-sumed Savannah River water was 0.1 mrem, or 0.03% of the average annual radiation dose from natural sources. The population dose commitment from liquid reicases of radioactivity was 6 person. rom (0.06 person-Sv).

E SRP had a 99.7% NPDES compliance rate in 1987, as compared to a 99.4% compliance rate in 1986. Only 18 of 6,560 analyses performed exceeded permit limits.

E Except for temperature and fecal coliform in Pen Branch, all stream analyses were within the South Carolina standards for a Class D stream.

1

4 Groundwater Monitoring Program r

3

SUMMARY

- This chapter examines the results of groundwater monitoring of both radioac-tive and nonradioactive constituents at the Savannah River Plant (SRP). In addition the hycrogeology of the area is described, and geologic terminology applicable to the SRP vicinity is given. The current groundwater monitoring program uses sev2ral programs already in operaticn. These programs are managed by the SRP Health Protection Depadment, which has radioactive and nonradioactive monitoring programs; the SRP Raw Materials Engineering and Technology Department, which monitors for volatile organics in the A and M Areas of the site; and 'he Interim Waste Technology Division of the Savannah River Laboratory, which monitors selected wells within the Burial Ground. For both radioactive and nonradioactive constituents, drinking water standards were used as a convenient reference for comparison.

In this chapter, activities of gross alpha,"Sr, tritium, and total radium are reponed for wells having levels higher than the drinking water standards. In addition, wells with nonradioactive constituent levels above their respective federal primary drinking water standards are identified.

(

)

DESCRIPTION OF MONITORING Landfill.The scope of monitoring expanded rapidly, PROGRA31 and Ue nonradioactive groundwater monitoring program was established in 1982. Most of the wells The operating policy at the Savannah River Plant is are sampled by pumping, and the analyses are j

to prevent or minimize degradation of natural conducted by contract laboratories. All wells are resources and to take restorative action should such sampled quarterly for field measurements of pil, degradation occur. The purpose of the groundwater temperature, conductivity, and water level. Other monitoring program is to detect and quantify any analyses are performed according to the sampling der,radation in groundwater quality at the Savan-schedule, which is generated using criteria that nah River Plant. The program also supports re-include applicable regulatory requirements, previ-search efTorts and performs leak monitoring at se-ous analytical results, potential constituents, and lec;cd sites.

ongoing research.

The current groundwater momoring program at Two other organizations momtor the groundwater.

SRP ia a combination of several programs. The SRP The SRP Raw Materials Engineering and Technol-Health Protection Department conducted both a ogy D(partment monitors for volatile organics in A radioactive monitoring program and a nonradioac-and M Areas, and the Interim Waste Technology tive monitoring program. The radioactit c monitor.

Division of the Savannah River Laboratory moni.

ing program began in the early 1950s and has tors selected wells within the Burial Grounds.

primarily monitored for gross alpha and nonvolatile beta activities and tritium concentrations at se-A description of each site and its hydrology and a lected sites. The samples are collected by either listing of the sources and types of materials known pumping or bailing wells, and the analyses are to exist at the site are presented in Appendix B.

conducted by the Ilealth Protection Department's laboratory at the SRP site.

CHANGES IN THE PROGRA31 DURING 1987 Groundwater monitoring for nonradioactive mate-Three new well series were constructed in 1987.

rials began in 1975 with four wells at the Sanitary Four MCB Series wells were installed around the

40 SAVANNAH RIVER PLANT - Environmental Report for 1987 l

Miscellaneous Chemical Basin, three RSF Series Upper Middle Eocene Stage: Upper Claibornian wells wei, installed around the kaolinite diked Lisbon or Santee equivalents are generally marine areas of R. Area Reactor Seepage Basin s l and 3, and formations oflow permeability. Provisionally these th ree ZBG Series wells were con structed in Z Area to units are assigned to the Santee Formation with a serve as background monitoring wells.

McBean sandy micritic member; a Warley Ilill sandy, often glauconitie, member; and a basal Caw-Fifty nine new wells were added to existing well Caw glauconitic and/or lignitic shale member. The I

series in 1987. Seven additional DCB wells were Caw-Caw member has been called "the green clay" constructed around the D-Area Coal Pile RunofT in SRP hydrologic writings.

Containment Basin. At the F Area Seepage Basins, Upper Eocene Stage: The lower portion, the Dry 30 Resource Conservation and Recovery Act(RCRA)

Branch Formation, comprises near shore sands, point-of compliancewells wereinstalled.These FSB clays,and oyster-shell bearinglimestones. A persis-cluster wells are screened in the water-table, tent clay in this formation is the "tan clay" of SRP McBean, and Upper Congaree aquifers. In S Area hydrologic literature. The Irwinton Sand member one additional background well was constructed, overlies the tan clay. The upper portion, the "ro-an d two RS E wells were added to the R-Area Reactor bacco Road Formation," is predominantly clayey Seepage Basins monitoring network. Nineteen sands with a few clean sands or clays. These two plume definition wells were added to the MSB well formations make up the Barnwell Group. In some series.

SRP literature the Jacksonian Dry Branch Forma-tion has been included in the "McBean Formation."

Severalions were added for analysis during 1987 to Post-Jacksonian Sediments: Gravels, clays, and determine all of the major ions present in the arkosic sands of fluvial origin cap many interfluye groundwater. The added analyses are calcium, po.

areas of the SRP region and are included in an tassium, magnesium, silica, and phosphate.

informal stratigraphic unit called the"upland unit."

These gravels, together with a reticulate-mottled IIYDROGEOLOGY AT SRP "B" soil horizon, were mapped as the "Hawthorn Formation" in early SRP area publications.

The Savannah River Plant is located in the Upper Flood Plain Deposits:These deposits are signifi-Atlantic Coastal Plain, approximately 30 km south-cant but generally occur along the Savannah River i

east of the Fall Line separating the Piedmont and and its major tributaries.

Coastal Plain provinces. The SRP is on the Aiken Plateau, a comparatively Dat surface that slopes A generalized view of these formations is shown in southeastward but is dissected by several tributar-Fig. 4 1 in Vol. H.The two aquifers in the Cretaceous t

i les to the Savannah River. The SRP stratigraphy Formations arc used separately and in combination comprises about 300 m of unconsolidated sands, to nbtain yields of greater than 1,000 gal / min in clayey sands, and sandy c'/s, which in turn are properly designed and constructed wells. The lower underlain by dense crystalhne metamorphic rc.ck or middle Eocen e Section also con tains san ds th atyield consolidated red mudstone. The geologic terminol-a few hundred gallons per minute in many location s.

i ogy applicable to the SRP vicinity is as follows:

Apart from these aquifers, most of the rest of the Coastal Plain sediments transmit water on a local Cretaceous System: Cape Fear, Middendcrf, scale but do not yield water to wells in su0icient Black Creek, and Steel Creek member of Pee Dee quantity to be classiGed as primary aquifers. A few formations (formerly all called Tuscaloosa Forma-excavated wells and some low yield drilled wells tion). Sands in the lower and upper part of this exist in the shallow formations; thus, these forma-section are important water producers.

tions could marginally be classined as aquifers.The Paleocene Series: Ellenton, Williamsburg, and connning beds retard the interchange of water be-unnamed formations. Very few clean sands occur in tween formations but do not totally prevent it-this nart of the section, whien constitutes a regional a9 aitard.

The direction ofgroundwater movement is governed Lower Middle Eocene Stage: Lower Claibornian largely by the depth ofincision of the creeks that rock s are generally sandy an d are ca pable ofproduc-dissect the Aiken Plateau. Small creek valleys gov-ing several hundred gallons of water per minute to ern the groundwater Dow directions in the shallow good wells. The name Congaree Formation is gener-sediments. The valleys of major tributaries to the ally applied.

Savannah River govern flow direction in the

4. Groundwater Monitoring Program 41 sediments ofintermediate depth, and the flow in the Table 41. Drinking Water Standards deep sediments is governed by the valley of the

( Cl/L) For Radioactive Constituents

Savannah River. Groundwater m, the Cretaceous Formations flows toward the Savannah River, and Gross alpha 15 that in the Lower Middle Eocene flows toward Upper Three Runs Creek or the Savannah River, Total ra dium 5

depending on its location. In several locations, dis.

Strontium-90 8

section by creek valleys creates groundwater subunits or islands in some formations.

Tntium 20,000 In the northwest part of SRP, groundwater head

CFR (Code of Federal Regulations).1987. National decreases with depth, providing the potential for l'rimary Drinking Water Regulations,40 CFR 141.

recharge from the surface to penetrate to the deeper formations. However,in the vicinity of the valleys of Upper Three Runs Creek and the Savannah River, summary ofmaximum constituentlevels in ground-the water levels above the Paleocene confining units water.

are drawn down by natural discharge to a greater extent than those in the deeper formations. Thus, Separations Areas there is a head reversal so that the vertical ground-water gradients in the central part of SRP are Maximum levels of radioactive constituents found upward.

in selected well series that are representative of groundwater monitoring in the separations areas Water levels in wells sam pling th e Cretaceous sands are summarized in Table 4-2 on p. 42. The higher do not respond quickly to rainfall; however, a long-than expected levels of radium at several sites are term relationship probably exists between water under investigation, level and recharge by rainfall. Water levels have fallen to a degree that cannot be totally correlated Solid Waste Storage Facilities.The Solid Waste with rainfall during the past severalyears. Pu mping Storage Facilities (Burial Grounds) are monitored for irrigation in Allendale and Barnwell Counties has increased greatly durir.g this period. In addi-tion, the pumping at SRP has also increased during this period. The head reversal near the central part of the plant has not disappeared due to the falling water levels, but it has decreased.

ItADIOACTIVE MONITORING f

]

i Applicable Standards k

i Analytical results ofgroundwater from onsite moni-

,y 9

u -

toring wells are compared with federal drinking

. 9;

/

water standards in this report. Although drinking

. ;t Tv ',

water standards do not apply to monitoring wells,

.['

they are a convenient reference for comparison. For p ".

3 et

~

8 1*

radioactive constituents the National Primary Drinking Water Regulations (CFR,1987) lists stan-

,;f-J j......

r (Table 4 1 at the top right hand column of the page).

A

~

yi 3' ~ "Q dard s for gross alpha, total radium, *)Sr, and tritium p -#

.n

~

%e

A

~ 'i.

Only wells with constituents above their respective R

drinking water standards are discussed in the fol-

[

h

~

J,ggiij;;, [S lowing sections. Tables 4-2 through 4-4 summarize

/

P radioactive results from selected well series that are representative of groundwater monitoring in the various areas. Table 4 26 in Vol.Il gives a complete Wells monitor Hurial Ground perimeter

42 SAVANNAH RIVER PLANT - Environmental Report for 1987 TABLE 4 2. MAXIMUM RADIOACTIVITIES IN SELECTED SEPARATIONS AREA WELLS Burial Grounds Constituent DWS/ units LB.GJ (MGA)

(MGC)

(MGE)

Gross Alpha 15 pCi/L 7

9.7 7

4 Nonvol. Beta NA 748 82 3,700 1,430 Tritium 20 pCi/mL 902,000 482,000 20,900,000 9,930,000 l

F Area Seepage Ganyon Seepage Tank Basins Building Basins Farm Constituent DWS/ units LEl (FCA)

(FSB)

LEIfl Gross Alpha 15 pCi/L 192 1,530 1,850 59.4 Nonvol. Beta NA 2,420 2,230 9,960 34,600

)

Radium 5 pCi/L 120 155 Strontium-90 8 pCi/L 231 13.7 Tritium 20 pCi/mL 67,200 482 67,200 282 H Area Seepage Canyon Seepage Tank Basins Building Basins Farm Constituent DWS/ units RJ1 (HCA)

(HSB) di1El Gross Alpha 15 pCi/L 46.6 5.2 711 7.37 Nonvol. Beta NA 14,200 16.7 9,150 73.2 Radium 5 pCi/L 4.9 48.6 Strontium-90 8 pCl/L 6.4 Tritium 20 pCi/mL 37,600 204 89,600 173 S and Z Areas S Area Z Area Constituent DWS/ units (SBG)

(ZBG)

Gross Alpha 15 pCi/L 3.2 2.0 Nonvol. Beta NA 10.4 3.4 Radium 5 pCl/L 1.3 1.1 Tritium 20 pCi/mL 23.2 16.5 DWS = Drinking water standard (EPA) by wells along the perimeter fence line, within the maximum nonvolatile beta activity was 9.61 pCi/L fence, and outside the perimeter north of the 643 7G in well BG 52. Tritium concentrations were above Burial Ground (Fig. 4-2, Vol. II). Results of the the drinking water standard in all but four of these groundwater monitoring are presented in Table 4 1, wells, with most of the concentrations less than 50 Vol. II.

pCi/mL.

The perimeter is monitored by wells BG 26 through Since 1978, high tritium concentrations have been i

BG 67. The maximum gross alpha activity levelin found in two areas of the perimeter. A tritium plume these wells was 3.66 pCi/L in well BG 32, and the has been migrating to the southwest from the south-

4. Groundwater Monitoring Program 43 west end of the original Burial Ground (643-G) southeastern end of 643 7G in well BG 408GR.

toward Four Mile Creek. The elevated tritium con-Elevated tritium (up to 902,000 pCi/mL) was de-centrations have in the past extended from well BG tected near the nnrthern fence in well BG 822GR. A 53 through BG 58. These wells are downgradient of single excursion of nonvolatile beta (748pCi/L) was the western third of the 643-G Burial Ground.The reported in well BG 822GR.

tritium concentrations in these wells have varied widely from year to year, with the maximum value F Area. Nine facilities in F Area are monitored by generally occurring in well BG 56 and occasionally groundwater wells; the F-Area A Line, the F-Area in BG 54. In 1987, the highest tritium concentration Acid / Caustic Basin, the F Area Burning / Rubble recorded for this plume (53,900 pCi/mL) was found Pits, the F-Area Canyon Building, the F Area Coal in well BG 56. The 1987 tritium concentration in Pile RunofrContain ment Basin, the F-Area Seepage well BG 56 is similar to the 1986 concentration but Basins, the Old F-Area Seepage Basin, the F-Area is higher than the concentrations observed from Tank Farm, and the Naval Fuels Facility back-1976 through 1985. The tritium concentrations in ground wells. The groundwater monitoring results wells BG 53,54,57, and 58 declined in 1987. These from F Area are presented in Tables 4-2 and 4-3, wells are at the margins of the plume.

Vol. II.

Another plume of tritium has been migrating to the The F-Area A Line and the F. Area Canyon Building northwest from the north end of the Burial Ground are monitored by the wells of the FAL and FCA addition (643-7G) toward Upper Three Runs Creek.

series (Fig. 4-3, Vol II). Wells FAL 1, FAL 2, and This plume extends from perimeter wells BG 33 FCA 2D are between the southeast end of the Can-through BG 35. Wells BG 68 through BG 90 were yon Building and the A-Line Building. Of these wells l

installed north of the perimeter fenee to monitor this only FCA 2D showed elevated levels of radionu-plume. Most of these wells had elevated tritium clides, with activities up to 1,530 pCi/L for gross concentrations, with a maximum of 18,000 pCi/mL alpha,2,230 pCi/L for nonvolatile beta,13.7 pCi/L detected in well BG 77. The leading edge of this for

Sr,34.1 pCi/mL for tritium, and 56.5 pCi/L for plume is apparently near wells BG 77,79, and 83.

total radium. The values for these constituents The tritium concentrations in most of these wells declined in this well in the fourth quarter. In the changed during 1987, generally decreasing in wells past, alpha and gamma spectroscopy analyses of to the south and generally increasingin wells to samples from well FCA 2D indicated that the radio-the north, activity was due primarily to "U, with some "U and decay daughters. IIigh nitrate levels from this The 70 wells of the MGA, MGC, MGE, MGG, and well indicate the source of this activity is uranyl MGI series monitor the groundwater beneath the nitrate. If the contamination resulted from uranyl i

643.G Burial Ground for gross alpha and nonvola-nitrate, a likely source would be the A Line Build-tile beta activities and for tritium. As in 1986, the ing, which processes uranium in the uranyl nitrate maximum activity levels for gross alpha (618 pCi/L) form. The remaining wells of the FCA series had and nonvolatile beta (12,600 pCi/L) were found in utivities of up to 51.2 pCi/L gross alpha,48.4 pCi/L well MGG 21. Elevated tritium concentrations were nonvolatile beta,120 pCi/L total radium, and 482 found in all wells, with the highest values recorded pCi/mL tritium.

for wells MGC 5 (20,900,000 pCi/mL), MGE 3 (9,930,000 pCi!mL), MGG 13 (6,690,000 pCi/mL),

The F-Area Acid / Caustic Basin is monitored by the MGG 34 (118,000,000 pCi/mL), and MGG 21D wells of the FAC series (Fig. 4-4, Vol. II). Wells FAC (4,410,000 pCi/mL). The maximum value recorded 1 and 2 were dry during 1987. Upgradient well FAC for well MGG 34 is considered spurious because it is 3 had the highest levels of gross alpha (36.5 pCi/L),

two orders of magnitude higher than any of the nonvolatile beta (38.4 pCi/L), and total radium other results from preceding and succeding quar-(23.1 pCi/L).

terly analysis of the well.

The F Area Burning / Rubble Pits are monitored by Twenty-one wells of the BG series within the Burial the FBP wells (Fig. 4 5, Vol. II). The only elevated Ground (identifled with numbers in previous an-radioactive constituents reported for waters from nual reports) monitor the groundwater beneath the these wells were nonvolatile beta (up to 98.2 pCi/L) 643 7G Burial Ground. Clevated tritium concentra-in upgradient well FBP 1A and an excursion of tions (up to 114,000 pCi/mL) were deted at the radium (6.3 pCi/L)in well FBP 4.

44 SAVANNAH, RIVER PLANT - Environmental Report for 1987 The F-Area Coal Pile Runoff Containment Basin The F Area Naval Fuels Facility (Fig. 4-3, Vol. II)is is monitored by the FCB wells (Fig. 4 6, Vol. II).

monitored by wells NBG 1 through 5. Wells NBG 1 The only measurement of radioactivity above and 2 had tritium levels in excess of the drinking drinking water standards was a total radium water standard. The highest 1987 tritium concen-activity of 6.7 pCi/L in downgradient well tration (897 pCi/mL), recorded for well NBG 2, j

FCB 3.

rcpresents an increase from 1986, when all tritium concentrations were under 250 pCi/mL Well NBG 2 The F Area Seepage Basins are monitored by the also contained elevated nonvolatile beta activity in wells of the F and FSB series (Fig. 4 7, Vol. II). All of 1987 (26.5 pCi/L), a level similar to the one recorded the F series wells and most of the FSB series wells there in 1986.

i had elevated tritium concentrations. Tritium and nonvohtile beta activities were elevated in all zones H Area. Five facilities in H Area are monitored by monitored except the lower portion of the Congaree groundwater wells: the II Area Canyon Building, Formation. The highest tritium values (67,200 the H-Area Coal Pile Runoff Containment Basin,

[

pCi/mL) were found in wells F 10 and FSB 78. Well the H Area Retention Basins, the II-Area Seepage F 10 is located adjacent to Basin 3 and monitors the Basins, and the II-Area Tank Farm. Tables 4-4 and perched water zone.Well FSB 78 monitors the water 4-5inVol.IlshowtheII Areagroundwatermonitor-table downgradient of Basin 3. Well F 10 also con-ing results, i

tained "Sr activity of 231 pCi/L. The highest non-volatile beta value was 9,960 pCi/L in well FSB 92D.

The H-Area Canyou Building is monitored by the Wells with elevated gross alpha activity (up to 1,850 four wells of the IICA series (Fig. 4-10, Vol. II).

pCi/L) were F 10,15,16, and 18A and FSB 77,78, Tritium concentrations (up to 204 pCi/mL) were 78C, 79, 79 C, 87 D, 88D, 89D, 90D, 91 D, 92 D, 94 C, above the drinking water standard in all four wells, i

97D,98C,98D, and 99D. Total radium activities (up and nonvolatile beta activity (up to 16.7 pCi/L) was to 155 pCi/L) were detected at levels above the elevated in wells IICA 1 and 2.

drinking water standard in wells FSB 77,78,780, 79, 79C, 87 D, 89 D, 90D, 910, 91 D, 92D, 97 D, 98C, The H Area Coal Pile Runoff Containment Basin is and 99D.

monitored by wells in the IICB series (Fig. 4-11, Vol.

II). Results from all of the wells showed elevated The Old F Area Scepage Basin is monitored by the levels of tritium. The highest concentration (42.8 FNB well series (Fig. 4 8, Vol. II). Downgradient pCi/mL) was recorded at upgradient well IICB 3.

well FN B 2 had the highest radioactivity levels with Well IICB 2 contained elevated gross alpha activi.

maximums of 61.4 pCi/L for gross alpha,701 pCi/L ties (27.7 pCi/L) and elevated nonvolatile beta ac-for nonvolatile beta,9.5 pCi/L for total radium, and tivities(34.9 pCi/L).The total radium activity in this 657 pCi/mL for tritium. Sidegradient wells FNB 1 well was equal to the drinking water standard.

and 3 had elevated levels of tritium activity, and These 1987 concentrations are considerably lower FNB 3 had elevated nonvolatile beta and total ra-than those recorded in 1986.

dium activities.

The wells monitoring the H Area Retention Basins The water table at the F Area Tank Farm is moni-are the llR3 and HR8 series (Fig. 4-12, Vol. II).

l tored by the 27 wells of the NF series (Fig. 4-9, Vol.

Results for 1987 indicate that virtually no change in II). Elevated nonvolatile beta activity was found in the concentrations in any of the wells has occurred wells NF 3 th rough 12,19,20,21,9.4A,25A,26, and since they were sampled in 1985. Well HR814,

27. Well NF 6 had the maximum nonvolatile beta which is downgradient from the old retention basin, value (34,600 pCi/L), the highest tritium concentra-was the only well with elevated gross alpha (44.6 tion (282 pCi/mL), and the highest elevated gross pCi/L), nonvolatile beta (21.4 pCi/L), and total ra-alpha value (39.4 pCi/L) at the site. All of the values dium (13.3 pCi/L) results. Tritium concentrations in NF 6 represent increases from 1986 levels. The exceeded the drinking water standard in all wells source of the elevated values in wells NF 5 through except HR814. The maximum tritium concentra-7 is a spill that occurred in 1961 when Tank 8 was tion (70.3 pCi/mL) was found in sidegradient well overfilled. Tritium was above the drinking water IIR811. Of the remaining wells, the second highest standard in wells MF 5,6,7,11,12,19,24A,25A, tritium value (54 pCi/mL) was in upgradient well i

26, and 27.

HR313.

4. Groundwater Monitoring Program 45 The H. Area Seepage Basins are monitored by the Z n nd ZW Wells.The Z and ZW wells were installed wells of the 11 and IISB series (Fig. 4-13, Vol. II).

in the separations areas (Fig. 416, Vol. II) as pie.

Most of the water table wells and wells monitoring zometers. Monitoring results from these wells are the lower Dry Branch Formation had elevated non-presented in Table 4 8, Vol. II. Gross alpha and volatile beta activities and tritium concentrations nonvolatile beta activities were not elevated in the that exceeded the drinking water standard. The ZW wells except for 12.8 pCi/L of nonvolatile beta maximum tritium concentration was found in well activity reported for well ZW 7. Tritium concentra-ti ns in excess of the drinking water standard were IISB 86D (89,600 pCi/mL). The highest nonvolatile o

beta activity (14,200 pCi/L) occurred in well II 6, found in wells Z 3, Z 15, ZW 2, and ZW 5 through 10.

which is at the edge of Basin 2. Gross alpha activities The highest tritium value found in these wells (282 were elevated in some of the water-table wells, with pCi/mL) was at well Z 3, which is approximately 150 the maximum value of 711 pCi/L recorded in well m east of the F-Area Seepage Basins. The other wells IISB 68. Total radium activity was elevated in sev-with elevated tritium levels are in or around the F.

eral of the water-table wells, with a maximum re-or II-area operating fence lines. Tritium decreased ported concentration of 48.6 pCi/L in well IISB 69.

from 1986 levels in wells Z3, ZW 2, and ZW 5.

Well IISB 84Ais screened in the upper portion of the Congaree Formation and had elevated ievels of all of Reactor Areas the measured radioactive constituents.

Maximum levels of radioactive constituents occur.

The H Area Tank Farm is monitored by the wells of ringin selected well series that are representative of the IITF series (Fig. 4-14, Vol. II). Elevated levels of groundwater monitoring in the reactor areas are nonvolatile beta activity were detected in wells IITF summarized in Table 4 3 on p. 46.

I through 6, 9, and 27 and 241 II. The highest nonvolatile beta activity (73.2 pCi/L) was found in C Area.The following locations, shown in Fig. 4-17, well IITF 5. This represents a decrease from the Vol. II, are monitored by groundwater wells: the 1986 maximum of 190 pCi/L in the same well.

C Area Burning / Rubble Pit, the C-Area Coal Pile Tritium concentrations were above the drinking RunofT Containment Basin, the C-Area Disassem-water standard for all of the wells except IITF 7,19, bly Basin, and the C-Area Reactor Seepage Basins.

27,28,31, and 32. As in 1986, well 24111 had the The monitoring results from these wells are pre-highest tritium concentration in the area (635 sented in Tables 4 9 and 4-10, Vol. II.

pCi/mL). The next highest tritium value (173 pCi/

mL) was found in well llTF 25 and represents a sub.

The C-Area Reactor Seepage Basins are monitored stantial increase from the 1986 maximum for this by the wells of the CSB series, all of which had well. Significant decreasesin maximum tritium con-tritium levels ebove the drinking water standard.

centrations from 1986 levels were seen in wells IITF The 1987 tritium concentrations in these wells were 1,6, and 12. Otherwise, tritium levels were similar similar to those of past years. Wells CSB 3A,4 A, and to those in 1986. Gross alpha activities were not ele.

5A, which are downgradient from Basins 1 and 2, vated in the wells monitoring this site.

had the highest tritium levels measured in the series (up to 120,000 pCi/mL). Overall, the tritium S Area. S Area and the Defense Waste Processing concentrations in the C-Area 1.eactor Seepage Ba.

Facility are monitored by the SBG well series (Fig.

sins wells declined during 1987. Well CSB 6A had 4-15, Vol. II). Analytical results from these wells are one excursion (6.3 pCi/L) of total radium.

presented in Table 4 6, Vol. II. Tritium levels above the drinking water standard were detected in well Elevated ievels of tritium were found in wells CRP 1 SBG 1, with a maximum concentration of 23.2 and 2, which are upgradient and sidegradient, re-pCi/mL.

spectively, of the C Area Burning / Rubble Pit. The maximum tritium value recorded for these wells Z Area. Z Area is monitored by wells in the ZBG was 294 pCi/mL in CRP 2.

series. These background wells are the only wells that have been installed in Z Area to date. Table Elevated levels of tritium were detected in both of 4 7 in Vol. II gives the monitoring results from these the wells (CDB 1 and 2) monitoring the C Area wells. Ne radioactive constituents were detected Disassembly Basin. The maximum concentration of above dnnking water standards.

368 pCi/mL occurred in well CDB 2.

-- ~

46 SAVANNAH RIVER PLANT - Environmental Report for 1987 TABLE 4-3. MAXIMUM RADIOACTIVITIES IN SELECTED REACTOR AREA WELLS C Area Coal Pile Burning /

Reactor Rudi Disassembly Rubble Seepage Basin Basin Pit Baains

(. LS)

(CDB)

(CEEl (CSB)

Const4uent DWS/ units Q

Gross Alpha 15 pCi/L 1.4 5.4

<3.0 18 Nonvol. Beta NA 2.8 18.7 11.0 5.4 Radium 5 pCl,t 0.8 2.7 0.9 4.3 Tritium 20 pCVmL 10.5 368 167 120,000 K Area Acid /

Reactor Caustic Disassembly Retention Soopage Basin Basin Basin Basin Const tue-1 DWStunos (EAQ1

{ED3]

{EBE1 (KSB)

Gross Alpha 15 pCi,t 42.2 18.3 6.6 1.45 Nonvol. Beta NA 3.1 27.fi 96.5 2.8 Radium 5 pCi,t 5.3 5.0 2.6 0.7 Tntium 20 pCi/mL 12.5 4,380 238,000 1,120 L Area Acid /

Burning /

Reactor Caustic Disassembly Rubble Seepage Basin Basin Prt Basin Consttuent DWS/unds IMQ)

(LDB)

LLBEJ LLSDA Gross Alpha 15 pCi/L 2.2

<3.0 1.6

<3.0 Nonvol. Beta NA S.0 3.0 4.0 2.7 Radium 5 pCi,1 0.9 1.2 1.1

<1.0 Tritium 20 pCi/mL 17.0 5.10 3.79 1,290 P Area Acid /

Burning /

Reactor Caustic Disassembly Rubble Seepage Basin Basin Pd Basin Const4uent DWSiunits (EAQ1

{E03)

(EBEl

{E.SB) l Gross Alpha 15 pCit

<3.0 4.2 5.2 1.54 Nonvol. Beta NA 3.0 1.8 7.6 13.7 Radium 5 pCist

< 1.0 0.9 1.8 1.3 Tritium 20 pCi/mL 12.9 342 82.9 272,000 R Area Acid /

Burning /

Reactor Reactor Caustic Rubble Seepage Seepage Basin Pas Basins Basins Const4uent DWS/unds (BAQ)

{BBEl (RSD)

IBSf]

Gross Alpha 15 pCi/L 6.1

<3.0 10.5 8.3 Nonvol. Beta NA 3.0 3.4 4,460 11.5 Radium 5 pCi/L 1.0

< 1.0 1.6 Tritium 20 pCi/mL 4.60 3.57 6.78 20.4

4. Groundwater Monitoring Program 47 R

K-Area Acid / Caustic Basin monitor-ing well KAC 1 contained elevated j (

{f'y 1s gross alpha levels up to 42.2 pCi/L and

[p i

elevated total radium levels up to 5.3 rg pCi/L.

@[.1

+(

At the K.Arca Ash Basin, wells KAB 1, 1;

,g, 2, and 4 contained elevated levels of i

' t-nonvolatile beta activity. The highest j

. M <*

8, concentration (35.8 pCUL) ivas re-y ';h ported for well KAB 1. Wells KAB 3 T

I

%g and 4 contained elevated total radium

.y

{

4 g

activities, with the highest concentra-H' tion (13.6 pCi/L) found in well KAB 4

%gghq*A (

.y

'g,;

and the concentration in well KAB 3 equal to the drinking water standard.

^ - U. -6 ' ?

Wells KAB 2 and 4 contained elevated

[

'J gross alpha activities, with the highest

^

~

4 * =. j-j 77.] jg4 [ i' value (36.4 pCi/L) recorded for up-c

[r[

[

gradient well KAB 2. Elevated calcium g) 8

~I-p and conductivity val.2es mdicate that welli, KAB 2 arsd 4 may be afTected by leaching of well grout.

o. - -. _ _

Groundwater from wells KCB 2 and 3, Installing surface easing for well which monitor the K Area Coal Pile K Area. Seve n facilities have groundwater monitor-Runo/TContainment Basin, contained elevated lev-ing wells installed: the K Area Acid' Caustic Basin, els of radioactive constituents. Well KCB 3 con-the K-Area Ash Basin, the K-Area Burning / Rubble tained elevated gross alpha activities up to 32.8 pCi/

Pit, the K-Area Coal Pile Ranoff Containment Ba-L, nonvolatile beta activity at 27.0 pCUL, total ra-sin, the K Area Disassembly Basin, the K-Area dium activity up to 14.5 pCUL, and tritium activity Reactor Seepage Basin, and the K Area Retention at 27.4 pCi/mL. Well KCB 2 had elevated tritium Basin. The locations of these facilities are shown in concentrations (34.5 pCi/mL) only.

Fig. 418, Vol. II, and the groundwater monitoring results are given in Tables 4-11 and 4-12, Vol. II.

Elevated tridum concentrations were detected in all the K-Area Reactor Seepage Basin wells. The high-The five wells of series KRB monitoring the K. Area est value (1,120 pCi/mL) was recorded for upgradi-Rctention Basin contained elevated tritium concen-ent well KSB 1. The 1987 tritium concentrations in trations. The maximum concentration for well KRB wells KSB 3 and 4A increased somewhat from their 1 was 252 pCi/mL. Measurements from the other 1986 levels.

wells were above 7,000 pCi/mL, with a maximum concentration of 238,000 pCi/mLin upgradient well KRB 8. Elevated nonvolatile beta activity (up to 91.0 L Area. Groundwater monitoring wells have pCi/L) was recorded for well KRB 15.

been installed at the following sites: the L Area Acid / Caustic Basin, the I Area Burning / Rubble Pit, The three wells of series KDB, which monitor the K-the I Area Disassembly Basin, the L-Area Oil and Arca Disassembly Basin, had elevated levels of trit-Chemical Basin, and the L-Area Reactor Scepage ium. The highest tritium value (4,380 pCi/mL) was Basin (Fig. 419, Vol. II). Table 4-13 in Vol. Il recorded in sidegradient well KDB 1. Sidegradient presents the groundwater monitoring results from well KDB 3 also contained elevated activities of these wells for 1987.

gross alpha (18.3 pCi/L) and nonvolatile beta (27.6 pCi/L) Total radium activity (5.0 pCi/L) was equal At the L-Area Oiland Chemical Basin, wells LCO 1 to the drinking water standard.

and 4 had elevated tritium concentrations and I

48 SAVANNAH RIVER PLANT - Environmental Report for 1987 nonvolatile beta activities similar to those that have other wells were generally above 50,000 pCi/mL, been recorded since 1985. For 1987, the maximum and the highest value (272,000 pCi/mL) occurred in values for tritium (1,040 pCi/mL) and nonvolatile well PSB 1A.These 1987 concentrations are similar beta (79.8 pCi/L) were from well LCO 1.

to those recorded in past years.

At the L-Area Reactor Seepage Basin, wells LSB 1 At the P Area Burning / Rubble Pit, results from and 4 had elevated tritium concentrations up to wells PRP 1A and 3 showed elevated levels of trit-1,290 pCi/mL (in upgradient well LSB 4). These ium. The highest tritium value recorded (82.9 1987 concentrations represent an increase from the pCi/mL) was for well PRP 1A. The tritium concen-1986 maximum concentration of 207 pCi/mL The tration in well PRP 3 was equal to the drinking elevated levels of these constituents are probably water standard.

related to the reactivation of L Reactor in 1985.

Both wells monitoring the P-Area Disassernbly Ba-P Area. Five sites are monitored by groundwater sin (PDB 2 and 3) had elevated ievels of tritium. The wells (Fig. 4 20, Vol. II): the P Area Acid / Caustic highest tritium value (342 pCi/mL) was recorded for Basin, the P Area Burning / Rubble Pit, the P-Area well PDB 2.

Coal Pile RunofT Containment Basin, the P. Area Disassembly Basin, and the P Area Reactar Seep-R Area.The R. Area Acid / Caustic Basin,the R Area 1

age Basins.The groundwater monitoring results are Burning / Rubble Pits, and the R-Area Reactor Seep-shown in Tables 414 and 4-15, Vol. II.

age Basins are monitored by groundwater wells.

Tables 4-16 and 4-17 in Vol.11 contain the monitor-All wells monitoring the P. Area Reactor Seepage ing data from these wells.

l Basins contained elevated tritium concentrations.

Most of the tritium values recorded for wells PSB 4A Nonvolatile beta activity was elevated in wells and 5A were below 500 pCi/mL. The values in the monitoring the R Area Reactor Seepage Basins (Fig.

TABLE 4-4. MAXIMUM RADIOACTIVITIES IN SELECTED GENERAL AREA WELLS A/M Areas Metals SRL Misc.

M Area Burning Seepage Chemical Settling Pit Basins Basin Basin Constituent DWS' units (ABP)

(ASB)

(MCB)

(MSB)

Gross Alpha 15 pCi/L 1.9 5.7 3.1 259 Nonvol. Bela NA 3.0 6.2 4.9 166 Radium 5 pCl/L 4.6 5.3 1.3 121 Tritium 20 pCi/mL 2.3 25.1 2.4 8.8 Miscellaneous Areas Fire Dept.

Training Sanitary Facility Landfill Constituent DWS/uniti (CSO)

(LFW)

Gross Alpha 15 pCl/L

<3.0 28.6 Nonvol. Beta NA

<2.0 23.4 Radium 5 pCi/L

<10 6.7 Tritium 20 pCi/mL 11.1 96.1 i

4. Groundwater Monitoring Program 4_9 4-21, Vol. II). Elevated levels were found in wells activity (up to 47 7 pCi/L) was elevated in wells MSB RSD 1 through 2C,4 through 8,10,11, and RSE 1A, 90,11F,120,13B, and 17A.

3A through 7,11,12,13, and 19. The highest non-volatile beta value (14,000 pCi/L) and the only ele-The ASB series wells monitor the Savanncn River vated gross alpha value (30.1 pCi/L) were found in Laboratory (SRL) Seepage Basina. Total radium well RSE 6. This well is adjacent to Basin 1 and is levels above the drinking water standard occurred within the perimeter of the kaolinite dike. Most of in wells ASB 2A (5.2 pCi/L) and ASB 3A (5.3 pCi/L).

the nonvolatile beta contamination in this area is Tritium levels up to 25.1 pCi/mL were observed in probably due to "Sr from fuel element failure in well ASB 80, which is approximately 120 m from the 1957. The elevated nonvolatile beta values are simi-SRL Seepage Basins and adjacent to the A-001 lar to those recorded in past years. A single excur-outfall.

sion of tritium (20.4 pCi/mL) was reported for well RSF1.

Central Shops. The following sites have ground-water monitoring wells installed: th e Central Shops General Areas Burning / Rubble Pits, the Central Shops IIy-drofluoric Acid Snill Area, the Fire Department Table 4-4 on the facing page summarizes maximum TrainingFacility, h Ford BuildingSeepage Basin, activity levels of radioactive con stituents in selected and the llazardou Waste Storage Facility (Fig.

well series that that are representative of ground-4-24, Vol. II). Table 4 19 in Vol. II shows the analyti-water monitoring in the general areas.

cal results from these wells. No elevated levels of ra-dioactive constituents were detected in this area.

A/M Area. Ten sites, as shown in Figs. 4 22 and 4 23, Vol. II, have groundwater monitoring wells:

CMP Pits. The only radioactive constituent ele-the A Area Background Well, the A-Area Burning /

vated at the CMP Pits (Fig. 4-25, Vol. II) was non.

Rubble Pits, the A Area Coal Pile RunofTContain-volatile beta in well CMP 15B, with concentrations ment Basin, the A Area Metals Burning Pit, the M-up to 20.4 pCi/L (Table 4-20, Vol. II).

Area Settling Basin and Lost Lake, the Metallurgi-cal Laboratory Seepage Basin, the Miscellaneous D Area. The D-Area Burning / Rubble Pits, the D-l Chemical Basin, the Motor Shop Oil Basin, the Area Coal Pile Runoff Containment Basin, and the l

Savannah River Laboratory (SRL) Seepage Basins, D Area Oil Disposal Basin are monitored by ground-and the Silverton Road Wastt Site. The analytical water wells, as shown in Figs. 4-26 and 4-27, Vol. It results from the monitoring wells for these sites are The groundwater monitoring results from these presented in Table 4-18, Vol. II.

wells are presented in Table 4 21, Vol. IL At the A Area Coal Pile RunoffContainment Basin, The only elevated radioactive constituents detected well ACB 4A had elevated levels of total radium up in this area were in the DCB wells, which monitor to 7.9 pCi/L.

the D-Area Coal Pile Runoff Containment Basin.

Elevated gross alpha activities (up to 92.1 pCi/L)

Wells MSB 1A through 8A are adjacent to the M-were reported in wells DCB 1A,6, and 11. Elevated Area Settling Basin and Lost Ioke. Total radium nonvolatile be+a activities (up to 85.2 pCi/L) were activity higher than the drinking water standard reported in wells DCB 6,10, and 11. Elevated total was detected (up to 29.2 pCi/L)in wells MSB 2A,3A, radium activities (up to 21.3 pCi/L) were reported in 4A, and 8A. Gross alpha activity was above the wells I A,6, and 10. The on'y well with an elevated drinking water standard in wells MSB 3A,4 A, and tritium concentration w a r, well DCB 12 8A (up to 97.2 pCi/L). Nonvolatile beta activity was (216 pCi/mL).

elevated in wells MSB 3A,4A,5A, and 8A (up to 157 pCi/L).

Sanitary Landfill. The Sanitary Landfill is moni-tored by the LFW series wells (Fig. 4 28, Vol. II).The The remaining MSB wells are used as plume defini-monitoring data for these wells are presented in tion wells, some of which were analyzed for radioae.

Table 4-22, Vol. IL Elevated tritium concentrations tive constituents. Total radium activity (up to 121 (up to 96.1 pCi/mL) were detected in wells LFW 6,7, pCi/L) was elevated in wells MSB 9C,11C,11F,17B, 8,18, and 38. Elevated activities for gross alpha and 29D. Gross alpha activity (up to 136 pCi/L) was (28.6 pCi/L), for nonvolatile beta (23.4 pCi/L), and elevated in wells MSB 9C and 11F. Nonvolatile beta for total radium levels (6.7 pCi/L) were reported for

50 SAVANNAH RIVER PLANT - Environmental Report for 1987 well LFW 7. A single elevated nonvolatile beta value ing separations areas is included in Tables 4 6 of 11 pCi/L was reported for well LFW 25.

through 4 9.

TNX Area. Two seepage basins have groundwater F Area. Eight facilities in F Area are monitored by monitoring wells: the Old TNX Seepage Basin and groundwater wells: the F-Area A Line, the F-Area the New TNX Seepage Basin. Fig. 4-29 in Vol. II, Aci& Caustic Basin, the F-Area Burning / Rubble shows the location of the basins and their monitor-Pits, the F-Area Canyon Building, the F-Area Coal ing wells; Table 4 23, Vol. II, gives the monitoring Pile RunofTContainment Basin,the F-Area Seepage data from these wells.

Basins, the Old F Area Seepage Basin, and the Naval Fuels Background Wells. The groundwater Old TNX Scepage Basin wells XSB 2,4, and 5A monitoring results from F Area are presented in contained elevated gross alpha activity and non.

Table 4-3, Vol. II.

volatile beta activity. Wells XSB 2 and 4 also con-tained elevated total radium activities. The highest The F Area A Line and F Area Canyon Building are values for gross alpha (125 pCi/L) and total radium monitored oy the FAL and FCA wells, respectively (95 pCi/L) were recorded in upgradient well XSB 2.

(Fig. 4-3, Vol. II). Elevated concentrations of trichlo-The highest value for nonvolatile beta (153 pCi/L) roethylene were reported in the water of both FAL was found in well XSB 4.

wells (up to 0.037 mg/L). Well FCA 2D, between the two buildings, had elevated conductivity, low pII, Other Sites and elevated levels of cadmium (up to 0.022 mg/L),

lead (u p to 0.110 mg/L), nitrate (up to 173 mg/L), and One analysis of total radium activity (5.9 pCi/L) that trichloroethylene (up to 0.570 mg/L). Nitrate (up to exceeded the drinking water standard was reported 11.1 mg/L) was above the drinking water standard for well BRD 3 monitoring the Road A Chemical in wells FCA 9D and 16D.Trichloroethylene concen-Basin (Fig. 4 30, Vol. II). No elevated levels of radioactivity were detected in the GBW 1 well at the Hawthorne Fire Tower. Table 4-24, Vol. II, M

presents monitoring data for these wells.

NONILADIOACTIVE MONITOllING J

Applicable Standards Analytical results of groundwater monitoring are compared to federal primary drinking water stan-

[

. Y.

dards in this report. Although drinking water

l t,' MMQ g._ w

%[MD~ ok. 9 N

)I standards do not apply to monitoring wells, they j~'

are a convenient reference for comparison. Only

% k*t

+ -

wells with constituent levels above their respec-N(.,

tive drinking water standards are discussed in the M-AO '

e d

following section. Table 4-5 on the facing pagc lists M;A S,

O 3-A.-

the standards for this comparison and the refer-N ence for each standard. Tables 4 6 through 4 9 M.

fi-9" presen t a sampling of non radioactive results from h

hh1 selected well series that are representative of groundwater monitoring in the various areas.

N, Table 4 26 in Vol. Il gives a complete summary of L

maximum constituent levels in groundwater.

,Q

l' Separations Areas

--2 A sampling of maximum levels of nonradioactive con stituents found in selected well series monitor-Thirty wells were installed in F Area in 1987 l

___-,__m

. _. _ ~

4. Groundwater Monitoring Program 51 At the F Area Coal Pile Table 4-5. Federal Primary Drinking Water Standards for Runoff Containment Ba-Nonradioactive Constituents sin (Fig. 4-6, Vol.10, lead concentrationsin excess of An alvte Leni lhlita Referencea the drinking water stan-Arsenic 0.05 mg/L CFR,1987 dard were detected in up-Barium 1.0 mg/L CFR,1987 gradient well FCB 1. The Cadmium 0.01 mg/L CFR,1987 maximum lead concentra-Chromium 0.05 mg/L CFR,1987 tion in this well was 0.163 Fluoride 4

mg/L CFR,1987 mg/L. The elevated pH, Lead 0.05 mg/L CFR,1987 conductivity, and calcium Mercury 0.002 mg/L CFR,1987 concentrations reported Nitrate (as N) 10 mg/L CFR,1987 for this well indicate that Selenium 0.01 mg/L CFR,1987 ithasbeen affectedby well Silver 0.05 mg/L CFR,1987 grout leaching Endrin 0.0002 mg/L CFR,1987 2,4-D 0.1 mg/L CFR,1987 The F-Area Seepage Ba-Lindane 0.004 mg/L CFR,1987 sins are monitored by the Methoxychlor 0.1 mg/L CFR,1987 wells of the FSB series Silvex 0.01 mg/L CFR,1987 (pig. 4 7, Vol. II). Nonra-Toxaphene 0.005 mg/L CFR,1987 dioactive constituents Benzene 0.005 mg/L EPA,1987 with concentrations de-Carbon Tetrachloride 0.005 mg/L EPA,1987 tected above drinking wa.

Chloroform

0.1 mg/L CFR,1987 ter standards in these Trichloroethylene 0.005 mg/L EPA,1987 wells were nitrate, lead, 1,1,1 TCE 0.2 mg/L EPA,1987 and cadmium, with iso-lated cases of barium and trichloroethylene. Nitrate

The level for trihalomethanes is set at 100 pg'w/L. Because no bromated was the pervasive con-methanes have been detected in SRP ground ater,liealth Protection taminant, occurring at has made the assumption that most of the trihalomethanes elevated levels (up to 472 present in plant water are chloroform.

mg/L)in most of the wells

CFR (Code of Federal Reguhtiens),1987. National Primary Drinking above the green clay. Ni-Water Regulations, 40 CFR 141.

trate was also present in wells FSB 78B and 97A in EPA (U.S. Environmental Protection Agency),1987. NationalPrimary the upper portion of the Drinking Water Regulations; Volatile Synthetic Organic Chemicals, U.S. Environmental Protection Agency, Federal Register, Congaree Formation. Ele-July 8,1987, pp. 25690 25717.

vated conductivity was found in the waters with elevated nitrate levels.

trations were elevated in wells FCA 16A and 16D, Lead (up to 0.169 mg/L) was elevated in wells FSB with a maximum reported concentration of 76,78,78C,79,79C,87D, and 92D. Cadmium (up to 0.323 mg/L.

0.071 mg/L) was elevated in wells FSB 78,78C,790, 87D,92D, and 980. Trichloroethylene (0.51 mg/L)

At the F. Area Burning / Rubble Pits (Fig. 4 5, Vol.

was above the drinking water standard in well FSB II), elevated levels of nitrate (up to 16.9 mg/L) and 109D. Barium levels (up to 8.96 mg/L) were above trichloroethylene (up to 0.053 mg/L) were reported the drinking water standard in wells FSB 91D,92D, in upgradient well FBP 1 A and downgradient well and 96C, possibly as a result of well construction.

FBP 2A. Well FBP 2A also had elevated levels of Isolated excursions of arsenic (0.192 mg/L) and sele-carbon tetrachloride (up to 0.15 mg/L)and tetrachlo-nium (0.02 mg/L) were recorded for well FSB 91D.

roethylene. One elevated lead value (0.072 mg/L)

No nonradioactive constituents with concentrations was reported in sidegradient well FBP 3A.

above drinking water standards were detected in

52 SAVANNAH RIVER PLANT - Environmental Report for 1987 TABLE 4-6. A SAMPLING OF MAXIMUM NONRADIOACTIVE CONSTITUENT CtYlCENTRATIONS (MG/L)IN SELECTED SEEPAGE BASIN WELLS F Area H Area K-Reactor M-Area Seepage Seepage Seepago Settling DWS Basins Basins Basin Basin Constituent (mdL)

(FSB)

(HSB)

(KSB)

(MSB)

Cadmium 0.01 0.071 0.007

<0.002 0.002 Lead 0.05 0.169 0.027

<0.006 0.072 Mercury 0.002 0.0020 0.0082

<0.0002

<0.0002 NO (as N) 10 472 118 1.84 238 3

Endrin 0.0002

<0.0001 0.0005 Triciene 0.005 0.051

<0.005 125 the wells monitoring the lower portion of the Conga-above its drinking water standard in the groundwa-ree Formation.

ter at the Il Area Canyon Building (Fig. 4 10, Vol.

II). Tetrachloroethylene was also detected in The FNB wells monitor the Old F Area Seepage this well.

Basin (Fig. 4-8, Vol. II). Elevated levels of trichlo-roethylene (up to 0.099 mg/L) were reported in Results from sidegradient well llCB 2 monitoring downgradient wells FNB 1 and 2. Elevated nitrate the II-Area Coal Pile Runoff Containment Basin levels (up to 31.1 mg/L), elevated conductivity (up to (Fig. 4-11, Vol. II) showed a lead concentration 320 pmhor/cm), and low pil(3.4 to 4.3) were reported (0.054 mg/L) above its drinking water standard. The in downgradient well FNB 2 and downgradient well conductivity (240 to 2,080 pmhos/em) and sulfate FNB 3. One elevated lead value (0.052 mg/L) was concentrations (150 to 760 mg/L) were elevated and reported for well FNB 2.

variable in this well during 1987, as they were in 1986.

Three wells (NBG 1,2, and 3) monitoring th e r Area Naest Fuels Facility (Fig. 4-3, Vol. II) contained Of the llR3 and IIR8 series wells, which monitor the elevated levels of trichloroethylene. The highest II. Area Retention Basins (Fig. 4-12, Vol. II), only trichloroethylene concentration (0.059 mg/L) was well IIR814 had elevated levels of nonradioactive recorded for well NBG 1. Well NBG 2 contained constituents. This well is downgradient of the old concentrations of nitrate up to 31.7 mg/L.

retention basin and had elevated conductivity (380 to 420 pmhos/cm) and nitrate concentrations (up to At the F Area Tank Farm (Fig. 4 9, Vol. II) nitrate 38.7 mg/L).

concentrations above the drinking water standard were detected in wells WF 6 (12.2 mg/L), WF 25A (120 mg/L), and WP 26 (42.6 mg/L). Elevated pli The II Area Scepage Basins are monitored for and conductivity in wells WP 12 and 21 indicate nonradioactive constituents in groundwater by the that these wells have been afTected by well grout IIS B well series (Fig. 4 13, Vol. II). Nitrate (up to 118 1 caching.

mg/L) was the most common nonradioactive con-stituent detected above the drinking water standard II Area.The II Area Canyon Building, the II Area at this site. Wells llSB 67,68,69,71,83D,84D, and Coal Pile RunofT Containment Basin, the II Area 86D, which are screened in the water table, and Retention Basins, the II Area Tank Farm, and the wells llSB 68C and 86C, which are screened in the II Area Seepage Basins have groundwater monitor-lower portion of the Dry Branch Formation, had ing wells. Table 4 5 in Vol.11 shows the II Area elevated nitrate levels. Water-table wells llSB 67 groundwater monitoring results.

and 83D h ad mercu ry levels (up to 0.0082 mg/L) that exceeded the drinking water standard. Well llSB Trichloroethylene (up to 0.008 mg/L) in well llCA 4 84A is screened in the upper portion of the Congaree was the only nonradioactive constituent detected Formation and had elevated levels ornitrate.

4. Groundwater Monitoring Program 53 TABLE 4 7. A SAMPLING OF MAXIMUM NONRADIOA3 NE CONSTITUENT CONCENTRATIONS (MG/L)IN SELECTED COAL PILE RUNOFF BASIN WELLS F-Area C-Area P-Area A-Area D-Area Coal Coal Coal Coal Coal Pile Pile Pile Pile Pile Runoff Runoff Runoff Runoff Runoff DWS Basin Basin Basin Basin Basin Constituent (ma'L)

(FCB)

(CCB)

(PCB)

(ACB)

(DCB)

Cadmium 0.01

<0.002

<0.002 0.012

<0.002 0.032 Lead 0.05 0.163 0.015 0.062 0.020 0.310 Mercury 0.002

<0.0002

<0.0002 0.0009 0.0009 NO (as N) 10 1.97 1.37 0.53 1.50 2.15 3

Endrin 0.0002

<0.0001

<0.005

<0.001 0.034 Triciene 0.005 Water samples from the IITF series wells at the H.

Containment Basin, the C-Area Disassembly Basin, Area Tank Farm (Fig. 413, Vol. II) were analyzed and the C-Area Reactor Seepage Basins. The moni-for sodium and nitrate in the third and fourth toring results from these wells are presented in quarters ofl987. An elevated sodium concentration Table 4 10, Vol. II.

(460 mg/L) was found in a sample from well llTF 8, but this result is questionable because of the low At the C-Area Disassembly Basin, results from well conductivity result for the sample. The nitrate con-CDB 1 showed one elevated measurement oflead centration (25 mg/L)in well llTF 22 was above the (0.076 mg/L).

drinking water standard.

Elevated trichloroethylene levels, up to 5.2 mg/L in S Area. Analytical results from the S. Area Back-well CRP 3, were reported for wells CRP 1,3, and 4, ground Wells (Fig. 4-15, Vol. II) are presen ted on the which monitor the C-Area Burning / Rubble Pit, facing page in Table 4 6, Vol. II. Trichloroethylene Water from well CRP 3 had high pli, conductivity, (0.111 mg/L)in well SBG 4 was the only nonradioac-and high calcium concentrations, indicating the tive constituent level above th e drinking water stan-efTects ofleaching of well grout. Elevated lead levels I

dard that was detected in the groundwater. Low (up to 0.418 mg/L) and elevated chromium levels (up levels of mercury were detected in well SBG 1, but to 0.108 mg/L) were also reported for this well.

they did not exceed the drinking water standard.

The CSB wells, which monitor the C Area Scepage Z Area.The Z-Area Background Wells are the only Basins, had elevated trichloroethylene concentra.

wells that have been installed in Z Area to date.

tions. Well CSB 4A had the maximum trichloroeth-Table 47 in Vol. II gives the monitoring results from ylene concentration (0.330 mg/L), which is similar to these wells. No constituents were detected above the maximum value recorded in 1986. Well CSB 5A the drinking water standards.

had one elevated tetrachloroethylene result (0.203 mg/L). Upgradient well CSB 1A contained elevated Reactor Areas chromium concentrations (up to 0.066 mg/L) and one elevated lead concentration (0.199 mg/L). liigh A sampling of maximum levels of nonradioactive pli, conductivity, and calcium concentrations in the constituents found in selected well series monitor.

water from wells CSB 1A,5A, and 6A indicate that ing reactor areas is included in Tables 4 6 these wells have been affected by well grout through 4 9.

leaching.

C Area. The following locations are monitored by K Area. Seven facilities have groundwater monitor-groundwater wells (Fig. 417, Vol. II): the C-Area ing wells installed: the K Area Acid / Caustic Basin, Burning / Rubble Pit, the C-Area Coal Pile Runoff the K Area Ash Basin, the K Area Burning / Rubble

54 SAVANNAH RIVER PLANT - Environmental Report for 1987 TABLE 4 8. A SAMPLING OF MAXIMUM NONRADIOACTIVE CONSTITUENT CONCENTRATIONS (MG/L)IN SELECTED MISCELLANEOUS WELLS Central Shops H Area Hazardous Naval Canyon Waste Sanitary DWS Fuels Building Z Area Storage Landfill Constituent (ma'L)

IfplG1 (HCA)

(ZBG)

(HWS)

(LFW)

Cadmium 0.01

<0.002

<0.002 0.021 Lead 0.05 0.038 0.013 0.010 0.007 0.022 Mercury 0.002 0.0003

<0.0002

<0.0002 0.0005 NO (as N) 10 31,7 1.69 1.75 0.90 1.95 3

Endrin 0.0002

<0.0001

<0.00005 Trictene 0.005 0.059 0.008

<0.005 0.044 Pit, the K Area Coal Pile Runoff Containment Bri-Lead concentrations in excess of the drinking water i

sin, the K-Area Disassembly Basin, the K Area standard were reported in wells KRB 1,8, and 13, i

Reactor Seepage Basin, and the K Area Retention monitorin g th e K-Area Retention Basin. Th e high est Basin. The locations of these facilities are given in lead concentration (0.189 mg/L) was detected in well Fig. 418, Vol. II, and the groundwater monitoring KRB 1.

results are given in Table 4-12, Vol. II.

The KAC wells monitor the K Area Acid / Caustic L Area. Groundwater monitoring wells have been Basin. No nonradioactive constituents with levels installed around the following sites: the L Area above drinking water standards were detected in Aci& Caustic Basin, the L-Area Burning / Rubble Pit, these wells; however, elevated levels of sulfate and the L-Area Disassembly Basin, the L-Area Oil and TDS and elevated conductivity were observed in Chemical Basin, and the L-Area Reactor Seepage downgradient well KAC 1 and to a lesser extent in Basin (Fig. 4-19, Vol. ID, Table 413 in Vol. II wells KAC 2 and 3.

presents the groundwater monitoring results from these wells for 1987.

At the K Area Burning / Rubble Pit, sidegradient well KRP 1 and upgradient well KRP 2 contained Elevated levels of tetrachloroethylene were found concentrations of lead in excess of the drinking in wells LAC 1, 2, and 3 monitoring the L-Area water standard. The highest lead concentration Acid / Caustic Basin. Trichloroethylene levels were (0.099 mg/L) was reported for well KRP 1. Down-above the drinking water standard in all of the gradient well KRP 4 contained elevated trichlo-L Area Aci& Caustic Basin wells,with a maximum roethylene levels (up to 0.043 mg/L).

value of 0.124 mg/L, which occurred in well IAC 2.

No nonradioactive constituents with levels above drinking water standards were detected in the KCB At the L Area Burning / Rubble Pit, well LRP 2 wells monitoring the K Area Coal Pile Runoff Con-contained elevated lead concentrations up to 0.061 tainment Basin. Downgradient well KCB 3 and to a mg/L.

lesser extent well KCB 4 had elevated conductivity levels.

L Area Disassembly Basin wells LDB 1 and 2 con-tained lead levels above the drinking water stan-Well KDB 1, which monitors the K Area Disassem.

dard, although these levels were substantiallylower bly Basin, contained elevated lead concentrations than ihnse recorded for 1986. The 1987 maximum up to 0.142 mg/L. Well KDB 3 had elevated 1cvels of lead concentration (0.160 mg/L) was found in well calciu m and conductivity, possibly indicating leach-LDB 1. In 1986 the maximum lead concentration ing of well grout was 0.718 mg/L.

l

)

4. Groundwater Monitoring Program 55 LArea Oil and Chemical Basin well LCO 4 had age Basins are monitored by groundwater wells.

chated levels oflead and mercury that exceeded Table 417 in Vol. II contains the monitoring data the levels of these constituents found in this wellin from these wells.

1955 and 1986. The 1987 maximum lead value (6069 mg/L) exceeded the drinking water standard; At the R-Area Reactor Scepage Basins (Fig. 4-21, the 1987 maximum mercury value (0.002 mg/L) was Vol. II), five wells (RSE 24 and 25 and RSF 1,2, and qual to the drinking water standard. Well LCO 3

3) were monitared for nonradioactive constituents.

had elevated trichloroethylen e concentration s, up to One nitrate concentration (12.7 mg/L) above the 0.015 mg/L. The trichloroethylene levels in well drinking water standard was detected in well RSE LCO 3 sre possibly attributable to the influence of

25. Iligh pli and conductivity and hica calcium the nearby L-Area Acid / Caustic Basin because of the concentrations in the water from well RS F lindicate presence of trichloroethylene in wells monitoring that it was affected by the leaching of well grout, that upgradient facility. Tetrachloroethylene was detected in wells LCO 2,3, and 4.

General Areas P Area. Five sites (Fig. 4 20, Vol. II) are monitored by groundwater wells: the P-Area Acid / Caustic A sampling of maximum levels of nonradioactive Basin, the P. Area Burning / Rubble Pit, the P-Area constituents found in selected well series monitor-Coa! Pile Runoff Containment Basin, the P Area ing general areas is included in Tables 4 6 Disassembly Basin, and the P-Area Reactor Seep-through 4-9.

age Basin s.The groundwater monitoring results are shown in Table 4-15, Vol. II.

A/M Area. Ten sites, as shown in Figs. 4 22 and 4-23, Vol. II, have groundwater monitoring wells:

At the P Area Burning / Rubble Pit, sidegradient the A. Area Background Well, the A Area well PRP 3 had a single excursion oflead (0.065 Burning / Rubble Pits, the A Area Coal Pile Runoff mg/L) and elevated ievels of tetrachloroethylene (up ContainmentBasin,the A AreaMetalsBurningPit, to 0.043 mg/L), trichloroethylene (up to 0.252 mg/L),

the M Area Settling Basin, the Metallurgical Lab and 1,1,1 TCE (up to 0.494 mg/L).

Seepage Basin, the Miscellaneous Chemical Basin, the Motor Shop Oil Basin, the Savannah River Well PCB 3A, downgradient from the P Area Coal Laboratory (SRL) Seepage Basins, an d th e Silverton Pile Runoff Containment Basin, had single excur-Road Waste Site. The analytical results from the sions of cadmium (0.012 mg/L), lead (0.062 mg/L),

monitoring wells are presented in Table 418, and selenium (0.011 mg/L) above their respective Vol. II.

drinking water standards. This well also had ele-vated conductivity (952 to l,450 pmhos/cm), calcium Trichloroethylene levels up to 0.006 mg/L were (59.4 mg/L), and sulfate concentrations (up to detected in the A Area Bqckground Well(ABW 1),

831 mg/L).

but these elevated levels may be due to contamina-tion from the A 001 outfall, which is upgradient Lead concentrations in excess of the drinking water from the well site. All other constituents were below standard were reported in well PDB 3, which moni-drinking water standards.

Lors the P. Area Disassembly Basin. The highest concentration reported was 0103 mg/L.

At the A Area Metals Burning Pit, trichloroethylene levels above the drinking water standard were re-Four wells monitoring the P-Area Reactor Seepage ported in wells ABP 2A,3, and 4. The maximum Basins (PSB 3A,4 A,5A, and 6A) contained elevated concentration of 0.088 mg/L was reported in well lead levels. The highest lead value reported was ABP 3. Tetrachloroethylene was detected in the 0.077 mg/L in well PSB 4 A. The elevated lead levels wells at this site.

may be attributable to the P Area Coal Pile Runoff Containment Basin, which is upgradient of the At the A Area Burning / Rubble Pits, trichloroeth-seepage basin. This well also contained on e elevated ylene was elevated in wells ARP 1A and 3, with a nitrate level (13.7 mg/L).

maximum 1987 value of 0.248 mg/L in upgradient well ARP 3, representing an increase from the 1986 R Area.The R Area Acid / Caustic Basin,the R Area maximum of 0.067 mg/L. Well ARP 3 also showed a Burning / Rubble Pits, and the R Area Reactor Seep-single tetrachloroethylene excursion.

56 SAVANNAH RIVER PLANT - Environmental Report for 1987 TABLE 4 9. A SAMPLING OF MAXIMUM NONRADIOACTIVE CONSTITUENT CONCENTRATIONS (MG/L)IN SELECTED ACID CAUSTIC BASIN WELLS F-Area K Area L Area P-Area R Area Acid / Caustic Acid / Caustic Acid / Caustic Acid / Caustic Acid / Caustic DWS Basin Basin Basin Basin Basin Constituent Imp'll (FAC)

(KAC)

LLAC)

(PAC)

(RAC)

Cadmium 0.01 0.002 0.004 0.002 0.002 0.002 Lead 0.05 0.029 0.012 0.029 0.006 0.044 Mercury 0.002 0.0002 0.0004 0.0002 0.0002 0.0002 NO (as N) 10 0.20 0.63 1.22 1.23 3.76 3

Endrin 0.0002 Trictene 0.005 0.005 0.124 At the 3fotor Shop Oil Basin, well AOB 1 contained Seepage Basins. liigher concentrations of trichlo-up to 0.112 mg/L of trichloroethylene. These ele-roethylene (up to ;.i.2 mg/L) and concentrations of l

va ted levels of trichloroethylene may originate from tetrachloroethylene (up to 0.146 mg/L) were de-the nearby A 014 outfall, although the outfall is tected in three welb(ASB 8,8B, and CC) downgradi.

j sidegradient of the basin. Tetrachloroethylene was ent from the A 001 outfall and approxirnately 120 m detected in the wells at this site.

from the seepage basins.

j Wells MSB 1A through 4A are adjacent to the Concentrations of two organic compounds were ele-Af-Area Settling Basin, and wells 5A through 8A are vated in the SRW wells monitoring the Silverton near Lost Lake. These wells are the designated Road Waste Site. Wells SRW 5, 6, 7, 8, and 11 RCRA point-of compliance (POC) monitoring wells contained carbon tetrachloride levels above the for the M Area Hazardous Waste Management drinking water standard (u p to 0.011 mg/L).Trichlo-Facility. Wells MSB 3A and 4A were the most af-roethylene levels (up to 0.011 mg/L) were above the fected at the site. Trichloroethylene (up to 125 drinking water standard in wells SRW 6,7,8,11, mg/L), tetrachloroethylene (up to 271 mg/L), and and 16A.

nitrate (up to 238 mg/L) were the most common con-taminants. Levels of carbon tetrachloride (up to Central Shops. The following sites have ground.

0.072 mg'L), chromium (up to 0.056 mg/L),1,1,1-water monitoring wells: the Central Shops trichloroethane (up to 0.589 mg/L), and chloroform Burning / Rubble Pits, the Central Shops liy-(up to 0.3 mg/L) were also reported above the drink-drofluoric Acid Spill Area, the Fire Department ing water standards. Elevated ievels oflead, nitrate, Training Facility (previously called the Central trichloroethylene, tetrachloroethylene, and chloro-Shops Burnable Oil Basin), the Ford Building Seep-form were reported in some of the POC wells, age Basin, and the Hazardous Waste Storage Facil.

ity (Fig. 4 24, Vol. II). Table 4-19 in Vol.11 shows the Trichloroethylene (up to 0.058 mg/L) was the only analytical results from these wells.

constituent above the drinking wate. standard de-tected in the AMB wells monitoring the 3fetallurgi-In well CSA 4, monitoring the Hydrofluoric Acid cal Laboratory Seepage Basin.

Spill Area, cadmium was detected at a concentra-tion equal to the drinking water standard.

Elevated trichloroethylene levels (up to 0.129 mg/L) we re detected in the MCB wells at the 3fiscellaneous Chemical Basin.

CMP Pits. The CMP Pits (Fig. 4-25, Vol. II) are monitored by tlie wells of the CMP series (Table Trichloroethylene (up to 0.096 mg/L) was detected 4 20, Vol. II). The only nonradioactive constituents above the drinking water standard in wells ASB 4 with elevated levels were trichloroethylene in well and 5A adjacent to the Savannah River Laboratory CMP 13 (up to 0.009 mg/L), elevated carbon tetra-m

- - - - - - - ^ - " - ^ -

^~

4. Groundwater Monitoring Program 57 i

chloride results in wells C51P 13 (0.007 mg/

L) and C51P 14B (0.009 mg/L), and a single s

excursion for lead (0.272 mg'L) in well g

C51P 11.

1 t

P J,

e, h.

D Area.The D Area Burning / Rubble Pits,

~

X

U f

the D-Area Coal Pile Runoff Containment

/ ;'

Basin, and the D-Area Oil Disposal Basin F

4 4

- I are monitored by groundwater wells, as shown in Figs. 4-26 and 4-27, Vol. IL The

.~

groundwater monitoring results from these

~

wells are presented in Table 4-21, Vol. IL

'w f

At the D Area Burning l Rubble Pits, one V

trichloroethylene analysis from well DBP 4 4

was equal to the drinking water standard.

W,' '

jgp t y

's_

The DCB well series monitors the D-Area Coc

Pile Runoff Containment Basin. 51ost of tne wells had elevated sulfate concentra-

.. i t

.i tions, elevated conductivity, and low pII.

~3 Con stituen ts with levels above th e drinking water standards were cadmium in weils Stetals analysis on groundwater samples DCB 1A and 11 (up to 0.032 mg/L), chromium in contained lead and nitrate levels in excess of their wells DCB 6,10, and 11(up to 0.488 mg/L), fluoride respective drinking water standards. The highest in well DCB 6 (4.50 mg/L), lead in well DCB 1A values for nitrate (220 mg/L) and lead (5.0 mg/L)

(0.310 mg/L), and trichloroethylene in wells DCB I A were found in upgradient well XSB 2. Elevated and 3A (up to 0.034 mg'L).

mercury levels were found in wells XSB 2 and 4. Well XSB 4 contained the highest mercury concentration Sanitary Landfill. The data for the LFW wells, (0.0123 mg/L). Elevated trichloroethylene concen-which monitor the Sanitary Landfill (Fig. 4 28, trations were found in all wells monitoring the Old Vol. ID, are presented in Table 4 22, Vol. IL Trichlo-TNX Seepage Basin. Upgradient well XSB 2 con-roethylene levels (up to 0.044 mg/L) were reported tained the highest trichloroethylene concentration above the drinking water standard in wells LFW 7, (0.593 mg/L) and an excursion of carbon tetrachlo-8,17,36,37, and 38. Similarly, tetrachloroethylene ride (0.017 mg/L).

levels (up to o.655 mg/L) were reported in wells LFW 21, 3S, and 39. Elevated cadmium results (up to The New TNXSeepage Basi.: monitoring well YSB 0.021 mg'L) were reported in wells LFW 6,17, and 4A had a single excursion of nitrate (11.7 mg/L) 26, and elevated chromium results were reported for above the drinking water standard, wells LFW 8 and 17.

Other Sites TNX Area. Two seepage basins have groundwater monitoring wells: the Old TNX Seepage Basin and The only nonradioactive constituent with elevated the New TNX Seepage Basin. Fig. 4 29 in Vol. Il concentrations found in the groundwater at the shows the location of the basins and their monitor-Road A Chemic d Basin (Fig. 4 30, Vol. II) was lead ing wells; Table 4 23, Vol. II, gives the monitoring (up to 0.155 mg/L)in well BRD 3. No elevated levels data from these wells.

of nonradioactive constituents were found in the GBW 1 background well at the Hau thorne Fire The Old TNX Secpage Basin is monitored by the Tower. Table 4 24, Vol. II, presents monitoring data XSB well series. Four wells (XSB 1,2,4, and 5A) for these wells.

I

58 SAVANNAH RIVER PLANT - Environmental Report for 1987 1987 HIGHLIGHTS E Three new well series were constructed around the P8iscellaneous Chemical Basin, around the kaolinite diked area of R-Area Reactor Scepage Basins 1 and 3, and in the Z Area.

E Fifty nine new wells were added to existing well series during 1987, M Thirty RCRA point-of-compliance welis were installed at the F-Area Seepage Basins and analyzed for EPA Appendix IX constituents.

j u Of allwells monitored on the SRP site,the highest activity levels of tritiumwere measuredin the MGA through MGl well series monitoring the groundwaMr beneath the original Burial Ground.

5 A wel'in the F-Area Tank Farm had the maximum nonvolatile bela value (34,623 pCi/L) for the SRP site, while a well at the F-Area Seepage Basins had the highest gross alpha activity, 1,850 pCi/L.

M No nonradioactive constituents were detected above drinking wa'er standards in the Z Atea, In the Central Shops Area,in the A, C, and K-Area Coal Runoff Basins,in the K Area Ash Basin,in the F eactor seepage basins for K and L Areas,in the acid / caustic basins in P F K, and R Areas,in the D-Area Oil Disposal Basin, or in the buming' rubble pits of R Area.

5 Food and Drinking Water

(

h

SUMMARY

- The results of the monitoring programs for m!!k food, and drinking water, along with a description of each of the monitoring programs, are conbined in this chapter.

Drinking water supplies from 22 onsite facilities and 14 surrounding ; owns were sampled and analyzed for radioactive and nonradioactive constituents. The radiological analyses included gross alpha, nonvolatile beta, and tritium. The nonradiologica: analysas included residual chlorine, chlorocarbons, total coliform, and various water quality parameters. The guidelines recommended by the South Carolina Department of Health and Environmental Control (SCDHEC) and by the U.S. EPA are used as standards for nonradiological monitoring at SRP. The radiological monitoring of milk for O'Cs, "'t, tritium, and "Sr, and of f arm products for tritium, "Sr, U/Pu (nonspecific), and N"Pu, indicated concentrations of radioactivity certesponding to an insignificant radiation dose.

RADIOACTIVE 510NITORING 1987 had less than minimum detectable "'I concen-trations. Because of its short physical halflife (8 51 ilk days), "il is not generally detectcd, er. cept shortly after tests of nuclear weapons or in th:. wake of Description of 51onitoring Program. Routine events such as the Chernobyl reactor accident.

samples of milk are taken from production at five There were no announced atmospheric nuclear dairies within a 25 mile radius of SRP and from weapons tests or other major nuclear eventsin 1987.

locally-produced inventories of a major local dis-tributor. Milk samples are analyzed for "'Cs, "21, Cesium 137 eoncentrations in milk ranged fromless tritium, and "Sr. Sampling locations are shown in than 2 to 8 pCi/L with an average concentration ef 2 Fig. 5 1, Vol. II.

pCi/L. These data from 1987 are in agreement with data from previous years. Concentrations cf"'Cs in Monitoring Results. Monitoring data for 1987 are milk from the SRP area are within the ranges presented in Table 5-1, Vol. II. Tritium in milk is reported by the EPA for the southeastern United attributed to releases from SRP. During 1987, trit-States and are attributed to worldwide fallent from ium concentrations in routine individual milk weapons tests.

samples ranged from less than 0.03 to 4.0 pCUmL with an average of 0.6 pCi/mL These very small Fool tritium concentrations in milk uo not correspond to significant rmliation doses. For example, the 50-Description of Monitoring Program. Farm year dose commitment from drinking one halfliter products representing the food cattgories ofleafy of milk per day for a year with a 1 pCi/mL tritium vegetables, fruit. grain, poultry, eggs, and meat are con:entration is approximately 0.01 mrem (0.0001 collected at 14 localities in the six counties sur-mSv). This dose is 0.003% of the average Central rounding SRP. Six locations are near the plant Savannah River Area (CSRA) individual's annual perimeter and eight are at a distance of approxi.

dose from maurally occurring radioactivity.

mately 25 miles. Food samples are ana!yzed for gamma-emitting radionuclides, tritium, *Sr, U/Pu Concentrations of"Sr in milk ranged from 2 to 14 (non-specific), and ""Pu. Food sample locations pCUL with an average concentration of 7 pCi% and are shown in Fig. 5-2, Vol. II.

were within ranges observed in previous years. One milk sample collected in 1987 showed an "'I concen-Monitoring Results. Food radioactivity monitor-tration of 3.7 pCUL, which was within ranges ob-ing data are presented in Table 5-2, Vol. II. Concen-served in previousyears except 1986.The maximum trations of gamma emitting radionuclides in foods "il concen' ration of 11 pCUL dectected in milk in were generally near or less than the minimum May 1986 reflected contribution from the Chernobyl detectable concentrations. Concentrations of "K accident. All other milk samples collected during varied from less than detectable concentrations to

60 SAVANNAH RIVER PLANT - Environmental Report for 1987 6.9 pCi/g and were within ranges normally observed plant is used primarily for industrial and manufac-in food and vegetation. Cesium-137 concentrations turing purposes in an 6dustrial complex near were near cr below minimum detectable concentra-Savannah, GA. It has a consumer population of tions. Themaximum "?Cs concentration was 0.08 about 20,000 people who are primarily adults work-pCi/g in eggs, ing in industrial facilities. The Beaufort-Jasper water treatment plant near liardeeville, SC, has Strontium.90 concentrations were within the been in operation since 1965. It serves a consumer rar'ges observed in past years. The maximum in population of cpproximately 50,000 people who live 1987 was 0.63 pCi/g in pork, compared to a maxi-in Beaufort and Juper Counties, mum in 1986 of 0.36 pCi/g in collards. U/Pu concen-trations were at or below minimum detectable con-Raw and dnished water treatment plant samples l

centratic9s. Concentrations of"Pu in food ranged from these two plants and from a water treatment from 0.04 to 0.54 (CVg. Plutonium.239 concentra-plant in North Augusta, SC, are collected daily by tions in food ranged from 0.01 to 0.76 fCi/g. All treatment plant personnel and composited for plutonium results were within values seen in previ-monthly analyses by SRP.The North Augusta water ous years. Plutonium and "Sr in food result primar-treatment plant is upriver of SRP and provides a ily from worldwide fallout that has accumulated in con trol for the analyses.These samples are a nalyzed the soil, for gross alpha, nonvolatile beta, and indum con-centrations.

)

Tritium concentrations in free water obtained from freeze. drying the food ranged from 0.28 to 4.3 Monitoring iksults. Drinking water radioactivity pCi/mL and were within ranges routinely detected monitoring data for 1987 at e presented in Table 5-3, in food and vegetation. The maximu m concentration Vol. II. Alpha and nonvolatile beta concentrations in was observed in fruits and collards.

drinking water collected onsite and from sm round-ing towns were within ranges r.tiributed to natu-The radiation dose from eating foods with these rally occurring radium and thorium. Studies con-levels of radioactivity is a small fraction of the dose ducted in South Carolina to determine levels of from naturel sources of radioactivity. For example, naturally occurring radionuclides in drinking water if a person consumed collards at a maximum con.

have indicated radium concentrations of over M i

aumption rate of 64 kg/ year (140 IUyr), the 50-year pCi/L [ mis 0). EPA maximum contaminant levels whole body dose commitment would be 0.8 mrem (MCL) are 5 pCi/L combine 3 *Ra and"Ra, and 15 e

(0.008 mSv) for "Sr (average 0.1pCi/g)and 0.008 pQiL gross alpha activity (excluding radon and mrem (0.00008 mSv) for tritium (average 2 pCi/g).

uranium).

The sum is equal to 0.3% of the average CSRA individual's annual dose from naturally occurring Small but measurable concentrations of tritium radioactivity, were detected occasionally in drinking water samples collected in operating areas.The maximum onsite tritium cancentration of 6 pCi/mL was 30% of i

Drinking Water the EPA drinking water standard. A special study conducted in 1987 indicated that trace levels of Descriptionof Monitoring Prograrn. Drinking tritiam detected in onsite drinking water samples water supplies from 22 onsite facilities and 14 are introduced aRer sample collection and do not surrounding towns are sampled and analyzed for reflect contamination in the aquifer. Cnapter 8 dis-l l

gross alpha, nonvolatile beta, and tritium. Public cusses the study in more detail.

drinking water locations are shown in Fig. 2-1, Vol. II.

The maximum tritium concentration.n drinking i

water supplies from surrounding townt, was 0.9 Two water treatment plants downriver from SRP pCi/mL, which is 5% ef the EPA d rinking water sts.n-I i

supply treated Savannah River water to customers dard. Tritium, when present in water supplies that in Beaufort and Jasper Counties, SC, and Port use surfacewater, is attributed to SRP releasea and Wentworth, GA (Fig. 5-3, Vol. II). The Ch erok ee lfill global fallout. The measurable tritium concentra-water treatment plant at Port Wentworth has been tions in surface water result from exchange of trit-treating Savannah River water during the entire ium from SRPatmospheric releases with hydrogen period ofoperation of SRP. Treated water from this in rainwater and surface water.

i l

J

l

5. Food and Drinking Water 61 Analytical data from water treatment plants are the EPA drinking water standard for tritium (20 shown in Table 5-3, Vol. II. Alpha concentrations at pCi/mL).

all three water treatment plants were less than the minimum detectable concentration of approxi-NONRADIOACTIVE MONITORING mately 0.5 pCi/L. The maximum nonvolatile beta concentrations in Anished water from the three Drinking Water plants ranged from 1.9 to 2.4 pCi/L. ihese concen-trations were within the ranges observed in water Description of Monitoring Program. Drinking from the Edisto River, which is approximately 20 wats.r at SRP is supplied primarily by deep wells miles from SRP and is negligibly innuenced by SRP that draw water from the Black Creek Middendorf

)

onerations. The maximum nonvolatile beta concen-Formations (formerly called the Tuscaloosa Aqui-tration in water collected from the Edisto River fer). The Savannah Itiver is used for drinking water during 1987 was 2.9 pCi/L(Chapter 3).These results in 400-D Aren. The drinking water is generally 1

for alpha and nonvolatile beta activity con 6rm that treated with chlorine to ensure that no harmful SRP operations have no signincant impact on down-coliform bacteria are present-river concentrations. The only measurable SRP impact is from tritium. The maximum tritium con-Samples from drinking water supplies are routinely l

centration in Saished water from both the Beaufort-analyzed for residual chlorine and total coliform.

Jasper and Port Wentworth treatment piants in The sampling frequency depends upon the potential 1987 wa. 3.3 pCi/mL with an average concentration for contamination and the amount of use. In addi-of 2.3 pCi/mL. The average concentration is 12% of tion, the primary supplies are analyzed annually for a comprehensivelist ofchemicals and other water quality parame-ters.

Drinking wateris also monitored

~

for chlorocarbons. Groundwater x

in the vicinity of M-Fuel Fabrica-4 tion Area was found to be con-taminated with metaldegreasing solvents in 1981. Followup sam-pling indicated t. hat trichloro-y' ethylene and tetrachloroeth-g ylene (chlorocarbons) were pres-entinWells20Aand53A nthe A-Administration Area. These wells, which supplied both drink-g s

ing water and process water for the A Admimstration and M-4 5-I Fuel Fabrication Areas, were

% ?("

^l '

shut down, and drinking water was supplied from Well 82A, which was free orchlorocarbons.

~

'( -

Use of drinking water from Well M

source of drinking water, was 31A, which served as a backup

+

O also discontinued in 1983 be-

{y,. '

W-cause of the occasional presence gI k..

of low concentrations of chloro-w carbons. The drinking water and I

i

,?

process water systems were then

+ $+b sepa-aied, and water from Wells 20A and 53A was restricted to

~

Sampling drinking water process water applications. A 1

~ - -

+

62 SAVANNAH RIVER PLANT - Environmental Report for 1987 dense-bed activated charcoal filter system was in-For other constituents, the "National Interim Pri-stalled on A Administration /51 Fuel Fabrication mary Drinking Water Regulations

apply [ EPA 76].

Areas drinHng water supplies in 1985. This action permitted the reactivation of Well 31A as a backup For chlorocarbons, the EPA drinking water stand-source of drinking water. In December 1986, the ard for tetrachloroethylene is 10 pg/L (parts per charcoal filter system was removed from service, billion, ppb). The proposed EPA standards for and Well 31 A is being converted to a process water trichloroethylene of 5 pg/L (ppb) and 1,1,1 trichlo-well. New drinking water supply wells (112-and roethane of 200 pg/L (ppb) have not yet been 113-G),approximately one and one halfmiles cast of adopted. Table 5-1 at the bottom of the page the A-Administration Area, respectively, were summarizes the drinking water standards.

placed in service in late 1986. No chlorocarbons have been detected in water from these wells. No chloro.

Stonitoring Hesults. 51onitoring data show tha' carbons have ever been detected in drinking water residual chlorine concentrations were within ex-systems.

pected ranges in 1987. Elevated total coliform

~

counts were detected in domestic water samples in D Area (5! arch 1987),TNX Area (April 1987),and K Applicable Standards. SCDHEC maximum con.

Area (September 1987). The elevated counts in D taminant levels and recommended guidelines are and TNX Areas were due to the use of unsterile used to ensure safe drinking water at SRP. The rec.

sample containers. Residual chlorine levels were ommended guidelines call for a minimum of 0.2 part sufficient to keep the coliform counts less than per million (ppm) chlorine at all parts of the water 1 colony /100 mL in these samples. The elevated system. The maximum contaminant concentration coliform count in K Area was detected in a sample

~

limit for total coliform is a monthly avernge not taken afler a water line repair was completed.This greater than 1 colony /100 mL or an individual result sink was not returned to service until two consecu-not greater tl.an 4 colonies /100 mL in two consecu.

tive resamplings showed less than 1 colony /100 mL tive samples.

total coliform. Analytical results are presented in Table 5-4, Vol. II.

For total tribalomethanes, the standard is less than 100 pg/L for community drinking water supplies.

Concentrations of chemicals, metals, and organics Although SRP drinking water supplies are not clas.

were within applicable standards except for total sified as community drinking wate r supplies and are iron, total manganese, turbidity, color, and pH at a nnt required to meet this standa:d, SRP policy is to few locations. Nine of the 15 samples had elevated meet the requirement.

total iron concentretions. These elevated iron con-Table 5-1. Drinking Water Standards for Nonradiological Contaminants" total coliform either monthly average s 1 colony /100 mL or S 4 colonics/100 mL in 2 consecutive samples total trihalomethanes < 100 g1 tetrachloroethylene

< 10 pg'L' trichloroethylene

< 5 pg'Ld 1,1,1-trichloroethane < 200 pg/Ld SCDiiEC. recommended guidelines call for a minimum of 0.2 ppm chlorine at all parts of the water system.

i For constituents not shown, the NationalInterim Primary Drinking Water Regulations apply [ EPA 761 t

EPA standard.

Proposed EPA standard - not yet adopted.

d

5. Food and Drinking Water 63 centrations are attributed to natural sources.Three drinking water supplies at SRP showed no con-of the 15 samples had a low pil, with the minimum Grmed chloroca bons.

being 4.63 in an II Area sample. No health hazard exists from drinking water with these levels. Andy-Occasionallow concentrations of trichloroethylene sis results are summarized in Table 5 5, Vol. II.

and tdrachloroethylene continued to be detected at the wellhead of Well 31 A. The maximums for 1987 No confirmed positive concentrations of tetrachlo-were 13 pg/L and 4 pg/L, respectively. Process water roethylene, trichloroethylsne or 1,1,1 trichlo.

wells 20A and 53A continued to show elevated chlo-roethane were detected in monthly analyses of rocarbon concentrations.The maximum concentra-

)

drinking water for the A Administration /M Fuel tion was 123 pg/L of trichloroethylene. Monitoring Preparation areas in 1987.The new 112 and 113-G results are presented in Tables 5 6 and 5 7,Vol. II.

Wells have also shown no conGrmed chlorocarbon Well locations are shown in Fig. 5-4, Vol. II, concentrations. Semi annual analyses of other 1987 HIGHLIGHTS E Tritium concentrations in milk were similar to 1986 values, ranging from less than 0.03 to 4.0 pCVmL, with an average of 0.6 pCumL.

E Strontium-90 concentrations in milk ranged from 2 to 14 pCVL, with an average concen-tration of 7 pCVL, which is somewhat higher than 1986, but within ranges observed in past years.

E Plutonium-238 and "Pu conc 3ntrations in foods were detected with maximum values of 0.54 and 0.76 fCVg, respectis ety. Plutonium and strontium in food rest.it mainly from worldwide fallout that has accumulated in soil.

E Alpha and nonvolatile beta concentrations in drinking water from onsite and surrounding towns were within ranges attributed to naturally occurring radium and thorium.

E in drinking water supplies, the maxirnum onsite tritium concentration of 6 pCVmL was 30% of the U.S. EPA drinking water standard, while the maximum tritiurr, concentration from surrounding towns was 0.9 pCUmL.

E Concentration of chemicals, metals, and organics in drin6 ;ng water were within applicable standards, except for total iron, total manganese, turbidity, color, and pH at a few locations.

E No confirmed positive concentrations of chlorocarbons were detected in drinking water from the A'M Areas in 1987. Process water wells 20A and 53A continued to show ele-vated chlorocarbon levels, the maximum concentration being 123 po'L of trichloroethylene.

j

6 Wildlife Monitoring

SUMMARY

-The results of the radic?ogical monitoring of fish and seafood, deer and hogs, furbearert, ducks, and turtles, and the nortradiological monitoring of deer and hogs for metals are presented, along with a short description of each of the monitoring programs. A total of 155 Savannah River fish and 220 fish caught in SRP streams, ponds, and swamp areas were analyzed for gamma, alpha, and nonvolatile beta concentrations. Of the Savannah River fish, only 11 had concentrations greater than 1 pCi/g of "7Cs. Crabs and oysters caught at the rnouth of the Savannah River were analyzed for alpha, beta, and gamma enitting radionuclides. The annual hunts on the SRP reservation yielded 606 deer and 123 hogs in 1987. Maximum concentrations of "7Cs, *l, tritium, and "Sr found in deer and hogs were similar to results from previous years, with the consumption of the meat resulting in an insignificant radiation dose. Con-centrations of gross alpha and beta, tritium, and "Sr in 22 furbearers trapped in 1987 were within expected ranges. Only two of 689 turtles trapped in 1987 had elevated readings with a G M detector (Thyac).

RADIOACTIVE 310NITORING Fig. 5-3, Vol. II. htore comprehensive fish monitor-ing data for 1987 are presented in Table 6 1, Vol. II.

Fish and Seafood A summary with comparisons of u?Cs data to those from earlieryears is presented in Table 6 2, Vol. II.

Description of Stonitoring Program. Savannah River fish are routinely trapped upriver of SRP, Of the 155 river fish analyzed for gamma-emitting adjacent to SRP, and downriver of SRP. Additional radionuclides,96 contained measurable concentra-fish are caught in the mouth of the Savannah River tion s of "Cs. Except for 11 fish,2"Cs concentrations (river miles 0-8). Fish are also collected from plant were less than i pCilg. The maximum "'Cs concen-streams and ponds and from Thurmond Irke (for-tration in these 11 fish was 2.2 pCi/g in a bream merly Clarks Hill).Thurmond Lake fish are used ca caught in Thurmond Lake. The radiation dose from controls because the lake is upriver of SRP.

eating fish with these "Cs concentrations is small.

8 For example, the 50 year dose commitment from Seafoods (crabs and oysters) are collected from the eating fish for a year (11.3 kglyear average mouth of the Savannah River near Savannah, GA, consumption) with the maximum '"Cs concentra-andanalyzedforgamma, alpha,andbeta emitting tion of 2.2 pCi/g would be 1.2 mrem (0.012 mSv),

radionuclides.

which is 0.8% of the average Central Savannah River Area (CSRA) individual's annual dose from Afonitoring Results. In 1987, a total of 155 indi-naturally occurring radioactivity, vidual fish from the Savannah River and Thurmond Lake were analyzed for gamma emitting radionu.

Of the 32 river fish analyzed for gross alpha and clides. Cesium-137 was the only man made gamma-nonvolatile beta emitting radionuclides, eight con-emitting radionuclide detected. A total of32 individ-tained measurable quantities ofalpha and all 32 fish ual fish from the Savannah River were analyzed for contained measurable quantities of nonvolatile gross alph a-and beta-emitting radionuclides. Table beta. The maximum concentrations for alpha and 6-1 at the top of p. 66 summarizes the maximuni nonvolatile beta were 0.3 and 33 pCi/g, respectialy, concentrations of alpha and beta activity and '"Cs and were detected in a perch caught downriver of found in fish caught near and on the SRP site and in SRP at sampling station R-10. The average alpha seafood caught near the Savannah River mouth, and nonvolatile beta concentrations were within Savannah River sampling locations are shown in ranges observed during 1986. The maximum beta

66 SAVANNAH RIVER PLANT - Environmental Report for 1987 Table 61. Radioactivity in Fish and Seafood Caught on and near SHP Site' Maximum concentration (pCl/g)

Gross Nonvolatile alpha beta "7Cs Savannah River fish 0.3(32) 33 (32) 2.2*(155)

Crabs' O.75 (20) 5.9(20) 0.17 (20)

Fish from SRP streams, ponds, and swamps 1.4 (106) 190(106) 213'(220)

Numbers in parentheses indicate numbers of specimens analyzed.

Caught in Thurmond Lake, the control locatiort An individual eatint,11.3 kg of fish (an sverage year's consumption) with this level of *Cs would receive 1.2 mrem (0.012 mSv) or 0.4% of the annual dose to an average CSRA resident from natura!!y occurring I

radioactivity.

Caught at the mouth of the Savannah River.

The maximum occurred in a bass taken from Pond B. Fish in Pond B ar.rt Par Pond are isolated from pubGc access, and no migratory pathway exists to anow movement of these fish to the Savannah River.

value, while greater than the 1986 maximum, was The highest "'Cs concentration in fish caught in within range 3 normally observed in fish from Four SRP ponds was 213 pCi/g detected in a bass from Mile Creek.

Pond B. Cesium 137 concentrations in all fish from Pond B wer e higher than other onsite location s with Crabs and oysters caught at the mouth of the Savan.

an average of 91 pCi/g. Pond B is located along the nah River were analyzed for gamma emitting radi-efiluent canal from R Area to Par Pond. The R.

onuclides. Cesium-137 was detected in five of the 20 Reactor efiluents were discharged through this 1

crabs collected with a maximum concentration of canal from the late 1950s to 1964 when R Reactor 0.17 pCi/g. Cesium 137 was not detected in the operation was permanently discontinued. During oysters. These data are consistent with analytical this time, releases from R Area were approximately results from previous years.

170 Ci of utCs.

i i

Of the 16 crabs analyzed for alpha-and nonvolatile Cesium-137 concentrations in Par Pond fish were l

beta emitting radionuclides, three had measurable also elevated with a maximum of 7 pCi/g detected in quantities of alpha and 13 had measurable quanti-a bream. Par Pond receives reactor heat exchanger ties of nonvolatile beta. The maximum concentra-cooling water from P Area. Releases of radioactivity tions of alpha and nonvolatile beta in the crabs were from this source consist of only small amounts of 0.75 and 5.92 pCi/g, while the average concentra.

tritium. No measurable "'Cs is released via this tions were 0.18 and 2.4 pCitg, respectively. Alpha route into Par Pond. Almost all of the utCs in Par and nonvolatile beta concentrations above the lower Pond was released from R Area before R Reactor limit ofdetection were not detected in the oysters. In was shut down in 1964.

previous years, crabs and oysters were not analyzed for alpha and beta emitting radionuclides.

Access to SRP streams and ponds is restricted, and no use of fish for food is allowed. Fish in Pond B and A total of 220 fish were caught in SRP streams, Par Pond are isolated from public access, and no mi.

)

ponds, and swamp areas. Cesium 137 was the only gratory pathway exists to allow movement of the j

man made gamma emitting radionuclide detected pond fish to the Savannah River.

in the fish. The maximum concentration of"'Cs in a stream fish was 9 pCi'g in a catfish collected from Concentration s of"'Cs genert.lly decreased in plant 4

Four Mile Creek.

stream and pond fish between 1971 and 1979. Since

.---r-s-r

,--,,,w,

---m.

-w ww-

--r---

7,y-.-

r-

_ _ _. _ _ _ = _ _

G. Wildlife Monitoring 67 1979, concentrations of'"Cs in fish have remained centration of 11 pCi/g and an average of 3 pCi/

fairly constant.

g. The 1986 maximum '"Cs concentrations in deer and hogs were 29 pCi/g and 21 pCi'g, respectively.

A total of l06 fish trapped in SRP streams and ponds Table 6 2 (at the top of p 68) presents maximum were analyzed for gross alpha and beta. Gross alpha concentration; of t"Cs. *l, tritium, and *Sr found in concentrations ranged from a maximum of 1.4 deer and hogs taken in hunts on the SRP reservation pCi!g to less than detectable concentrations. The in 1987. A summary ofmonitoring data is presented maximum gross beta concentration was 190 pCi/g in Table 6 3, Vol. II, and the minimum was 0.81 pCi'g. The maximum alpha concentration was detected in a crappie All dec-and hog results were within ranges ob-j caught in Upper Three Runs Creek, and the maxi-served over the last several years, and consumption j

mum beta concentration was detected in a bass from of the meat from these animals presents no radia-Pond B. Gross alpha and beta radioactivity data in tion hazard. For example, edible meat from the deer fish are presented in Table 6-1, Vol. II.

with the highest '"Cs concentration (45 pCi/g) weighed about 12 kg and contained approximately Deer and Hogs 0.55 uCi of'"Cs. An adult consuming all of this meat would receive a 50-year radiation dose commitment Description of Monitoring Program. Annual of 27 mrem (0.27 mSv) or 9% of the average CSRA hunts are conducted at SRP to control the plant deer resident's annual dose from naturally occurring and hog populations and to reduce animal-vehicle radioactivity.

accidents. All animals are monitored for radioactiv-ity with portable sodium iodide (Nal) detectors be-Five deer collected from a controlled hunting camp fore they are relea sed to the h un ters. The 1987 hunts located on the South Carolina Coastal Plain (SCCP) yielded 606 deer and 123 hogs, as compared with 944 about 65 miles from SRP had an average '"Cs con-deer and 127 hogs in 1986.

centration of 9 pCi'g, while 606 deer collected on SRP had an average concentration of 5 pCi'g. The Monitoring Results. In deer, the maximum '"Cs SRP maximum concentration of45 pCilg was higher field measurement was 45 pCi'g ofmuscle tissue and than the 15 pCi'g maximum detected in the deer the average was 5 pCi'g. Measurements in hogs from the controlled camp on the SCCP.The higher were somewhat lower with a maximum "Cs con.

SRP maximum may reflect some uptake of '"Cs Y

l'

-l t-

Qf r,(

L.

1 y

p.

o Fish in Par Pond are monitored for radioactivity

~

P 68 SAVANNAH RIVER PLANT - Environmental Report for 1987 Table 6 2. Radioactivity in Deer and Hogs Kllied in Hunts on SRP Site

Maximum concentration i

Cs

'"I Tritium "Sr (pCi/g)

(pCilg)

(pCl/mL)

(pCilg) 1 Deer 45'(606) 168(24) 6458(3) 120'(5)

Hogs 11 (123) 15' (4)

Numbers in parentheses indicate numbers of specimens analyzed, Consumption of the meat of this deer would lead to a 50-year dose commitment of 27 mrom (0.27 mSv) from "'Cs.

Thyroid.

Consumption of the meat of this deer would lead to a 50 year dose commitment of 0.02 3

mrem (0.0002 mSv) f rom tritium.

Bone.

from SRP operations or it may reflect difTerences in obtained by freeze-drying the tissue.The 1986 maxi.

the diets of the deer.The higher number may be due mum tritium concentration in deer was 38 pCi/mL.

to the larger sample size of th e SRP deer. A compari.

Consumption of the deer with the higher tritium son of SRP and SCCP deer "Cs concentrations since concentrations presents no radiation hazard. For 5

1968 has shown significant year to year variations example, meat consamed from the deer with the in both maximum and average concentrations, as highest tritium concentration (645 pCi/mL) would shown in Table 6-4, Vol. II.

result in a 50. year dose commitment of 0.02 mrem (0.0002 mSv), based on a total deer weight of 52 kg Tissue samples were collected from 36 deer and 14 containing 0.33 pCi of tritium.This dose is 0.007% of hogs to verify the field measurements and to deter-the average CSRA individual's annual dose from mine whether other radionuclides were present.

naturally occurring radioactivity. Tritium concen.

i Statistical analysis of field measurements of 1"Cs, trations in deer are presented in Table 6 7, Vol. II.

compared to laboratory measurements, indicated l

good agreement and supported the field monitoring Tistue and bone samples from five deer and four results. Gamma analysis of the laboratory samples hogs were analyzed for "Sr. As expected, concentra-detected only "Cs and normal levels of naturally tions for*Sr (which is a bone seeker) were higher in 3

occurring"K. A comparison of field and laboratory the bone samples than in the tissue samples. The j

2"Cs measurements in the deer and hogs is pre-concentrations in tissue were near or less than the sented in Table 6-5, Vol. II.

minimum detectable value of 0.8 pCi/g. The coneen-trations in bone ranged from 6 to 120 pCi/g. The In addition to the "Cs laboratory analyses in deer maximum 1987 concentration of 120 pCi/g was in i

8 and hog flesh, flesh samples from 20 deer were the bone of a deer;in 1986, the maximum "Sr con-analyzed for 58'I, and bone samples from 24 deer centration in deer bone was 130 pCi/g. The 1937 were analyzed for "Cs. All the flesh samples had maximum"Sr concentration in the bone of a hog was 5

less than detectable concentrations of 88'I, except for 15 pCi/g. Strontium 90 analysis was not performed one sample with an *! concentration of 3 pCi/g.

in previous years on hog samples. These data are Cesium 137 concentrations in the bone samples presented in Table 6-8, Voi. II.

ranged from less than 0.2 to 3.5 pCi/g.Th ese data a re presented in Table 6-6, Vol. II.

Tissue and thyroid samples were collected from 24 deer and sent to the Departmeat of Physiology and i

Analyses of tissue from three deer and one hog for Biophysics, University of Tennessee, Memphis, for i

tritium showed greatly varying concentrations analysis.The tissue samples were analyzed for "Cs, i

ranging from 9 to 645 pCi/mL in the free water and the thyroids were analyzed for "I and '"Cs.

2 1

i

I G. Wildlife Monitoring 69 Concentrations of'"Cs in the tissue samples ranged River swamp near Creek Plantation. Counting of from less than 1 to 12 pCi'g and showed reason-the animals for gamma emitters indicated low con-ably good agreement with the SRP field mea-centrations of" Cs.The maximum concentration of surements. Iodine-129 concentrations in the thy-5"Cs was 3 pCUg in an opossum from a location be-roids ranged from 0.1 to 16 pCi'g, with an average of tween Par Pond and Pond B. If this opossum left the 3 pCi/g. These values for 1987 are similar to the SRP site and were used for food, the 50-year radia-average of 2 pCi/g and the range of 0.02 to 15 pCi/g tion dose commitment to an individual who con-detected in 1986. Concentrations of 5"Cs in the sumed all edible portion s (total weight 3.1 kg) would thyroids ranged from 0.2 to 6 pCi/g, with an be 0.47 mrem (0.005 mSv) or 0.2% of the average average of 2 pCi/g. These data are presented in CSRA individual's annual dose from naturally oc.

Table 6 9, Vol. H.

curring radioactivity.The average '"Cs concentra-tion for all furbearers was 1.2 pCilg. Animal moni-Furbearers toring results are presented in Table 6-10, Vol. II.

9 g gp A total of 84 beavers were trapped during 1987.

is.. H '.9 L 't

H :1:

{

', f' ' L c ' 4} M,

V Field rnonitoring was performed on 53 of these I

t animals. In addition to field monitoring, bone and I

\\,'

~

a flesh samples from four beavers were analyzed for concentrations of gross alpha and beta activity and

{

tritium, "Sr, and gamma emitting radionuclides.

- ri~

Cesium 137 and naturally occurring "K and were the only gamma emitters detected. Data from these ki analyses are summarized in Table 6-11, Vol. II.

3

\\

j Ducks

't ! 0' O & 'f.

s. I-h. -

~

r$ -

Description of 51onitoring Program. Ducks are

~~

~

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routinely trapped at Par Pond and counted whole for Opossum trapped for analysis gamma-emitting radionuclides.

j Description of Afonitoring Program. The SRP 51 nitoring liesults, in 1987, a total of 13 ducks site is closed to outside hunters except for the con-were trapped at Par Pond. Cesium 137 was the only trolled hunts for deer and hogs. Therefore, furbear-gamma emittma radionuclide detected. The may,-

l ers (referred to in previous reports as terrestrial ani-nmm e neentration of "Cs detected was 2.7 pCi'g m mals) are not a likely source of food to the surround-a h rned grebe. The horned grebe is not a preferred ing population. Furbearing animals such as foxes, table fare of waterfowl hunters. However, if th,s i

raccoons, and opossums are trapped and analyzed horned grebe left the SRP site and were used for for gamma. emitting radionuclides.

fwd, the 50-year radiation dose commitment to an The U.S. Forest Service administers a Du Pont j

contract for the trapping ofbeavers in selected areas within the SRP perimeter. The purpose of the trap-m *0

. g-.

I ping is to reduce the beaver paulation in particular A.-

areas of SRP and thereby to minimize dam building activities that result in flood damage to timber stands, primary and secondary roads, and railroad i

beds. Beavers are monitored with a G-31 detector (Thyac) and disposed ofin the SRP sanitary landfill.

A few of the beavers are submitted for laboratory 3

j analysis of radionuclides.

~

f w:

j 5fonitoring Results. During 1987,22 furbearers

{

(not including beavers) were trapped along 10 l

transects across the SRP site and in the Savannah Ducks are routinely monitored

[

70 SAVANNAH RIVER PLANT - Environmental Report for 1987 individual who consumed the duck (total weight annual basis. Since 1975, analyses have been per.

604 g) would be 0.07 mrem (0.001 mSv) or 0.02% of formed on individual fish.

the average CSRA individual's annual dose from naturally occurring radioactivity. All of the ducks The concentrations of mercury are determined in monitored contained "?Cs concentrations within the desh of fish taken from onsite and ofTsite loca-ranges observed ia previousycars. Duck monitoring tions. The fish analyzed represent a random selec.

data are presented in Table 6-12, Vol.11.

tion of the Osh that were caught in traps. These analyses are performed to assess the uptake of mer.

Turtles cury that is assumed to come principally from previ-ous releases from industries upriver of SRP. The Dese:intion of Monitoring Program. As part of mercury concentrations detected in onsite Osh re-an ongoing study conducted by SHEL to learn more ficct mercury in the Savannah River water that has about turtles' migratory behavior, specimens are been used as cooling water in site facilities and sub-trapped on site and ofTsite, surveyed for radioactivity sequently pumped into SRP streams and lakes.

with a G-M detector (Thyac), aged, and sexed.

Turtles collected from sites where no turtles had Applicable Standards. The Food and Drug Ad-been previously collected and those with field radia-ministration (FDA) has established an action level tion measuremem.c above levels previously detected of 1.0 pg lig'g for a daily intake of mercury in edible in turtles from those specific locations are submitted fish. For this reason,it is more appropriate to com-for laboratory analysis to datermine the origin of ra-pare average concentrations to the action level dioactivity.

rather than maximum concentrations.

Monitoring Results. A total of 689 turtles, mainly Monitoring Results. Because of the startup of a pondsliders and eastern mud turtles, were trapped new laboratory facility,it was not possible to per.

in 1987. Only two of the 6S9 turdes trapped had form mercury analyses in fish during 1987. This pro.

elevated Thyac readings. Both were pondsliders gram will be resumed in 1988. Maximum results in captured onsite; one was capturus at Twin Lakes past years have indicated no significant accumula-near C Reactor, and the other, found crossing the tion of mercury in Osh.

road in the 700 Area, very likely inhabited the 700 Area basins at one time.

Deer None of the turtles trapped ofTsite showed detect.

Description of Monitoring Program. As part of able levels of radioactivity. These ofTsite turtles a special study, tissue samples were taken from the were taken from nearby private ponds in the Green muscle, spleen, liver, and kidney of a nu mbe r ofdeer Pond Church area, near the SRP boundary. No and hogs killed during SRP deer hunts in 1986.

)

turtles were submitted for laboratory analysis in These samples were analyzed for cadmium, chro-1987, because analytical data compiled from previ-mium, lead, and mercury in 1987.

ous years were judged to be sufficient.

Monitoring Results. Tissue samples from a total NONRADIOACTIVE MONITORING of 70 deer and three hogs were analyzed offsite for cadmium, chromium, kad, and mercury. The high.

Fish est metal concentrations, thoso of cadmium in the kidneys, ranged from less than 0.13 to 42 mg/kg.

Description of Monitoring Program. Mercury All the other metal concentrations found in muscle, has been detected in river and stream fish since spleen, liver, and kidney ranged from less than de-analyses were begun in 1971. Initially, individual tectable concentrations to 7 mg/kg. Additional fish Desh samples were analyzed. In 1972, fish samples will be obtained in.1988 for followup analy-samples were analyzed quarterly by composites of sis and data comparison. A summary of the metal bass, bream, and catfish. Analyses by species com-concentrations in deer and hog tissues is presented posites continued from 1973 to 1975 but on a semi-in Table 6-13, Vol. II.

6. Wildlife Monitoring 71 1987 HIGHLIGHTS E The 50 year dose commitment from eating fish for a year (11.3 kg'yr) with the maximum "7Cs concentration of 2.2 pCilg (detected in a fish from Thurmond Lake) would be 1.2 mrem, or 0.8% of the average annual dose f rom naturally occurring radioactivity.

E Fish trapped in SRP streams and ponds had gross alpha concentrations reging from less than detectable levels to a maximum of 1.4 pCi/g, and beta concentrations ranging from 0.81 to 190 pCL'g.

E An adult consuming all the edible meat from the deer with the highest "7Cs concentration (45 pCilg) would receive a 50-year dose commitment of 27 mrem, or 9% of the average annual dose from naturally occurring radioactivity. Average "7Cs concentrations in SRP deer and offsite deer were 5 and 9 pCi!O, respectively.

E in 1987, the maximum "Sr concentration in the bone of a deer was 120 pCi'g, compaied to the 1986 maximum of 130 pCL'g.

E in the 13 ducks analyzed, "7Cs concentrations were within ranges observed in previous years, with a maximum of 2.7 pCilg in a homed grebe, 1

j

7 Rainwater, Soil, Sediment, and Vegetation

SUMMARY

-This chapter presents the results of the radiological monitoring of rainwater, soil, sediments, and vegetation from locations on and around the SRP site. Sampling protocol varied from quarterly analyses of rainwater obtained at the plant perimeter and at four 100-mile radius stations, to soil sampling around the two separations areas and at the plant boundary, to the annual collection of sediment samples at six locations on the Savannah River and at nine SRP stream locations. Measurable quantities of alpha, nonvolatile beta, "Sr *Cs, and naturally occurring Be were detected in rainwater samples during the year.

7 The concentrations of radionuclides in soil varied significantly among locations because of differences in rainf all patterns and the mechanics of transport in different types of soil. Con-centrations of radioactivity in river and stream sediments were similar to results from previous years with the exception of one stream "Pu concentration, which was slightly higher. Vegeta-tion samples, collected at the plant perimeter,25-mile radius, and 100 mile radius, had alpha, nonvolatile beta, and tritium concentrations that were approximately the same as those seen in 1986.

ItADIOACTIVE 510NITOllING analyses of rainwater were discontinued at all sta-tions except Darkhorse and Barnwell Gate at the Itainwater plant perimeter, Olar at the 25 mile radius (see Fig.

21, Vol. ID and quarterly analyses of samples ob-Description of 51onitoring Program. Small tained at the four 100 mile radius stations. Rain-quantities of worldwide fallout that remain in the water samples at alllocations are collected and held atmosphere are deposited on the earth in rainwater, until the Darkhorse and Barnwell Gate analyses are The quantity deposited each year has decreased complete. Samples from the other air monitoring significantly since the 1960s and is now near or less stations are available for analysis should the need than the minimum detectable quantity, occur. The rainwater monitoring program was re-duced because levels of worldwide fallout from pre-On occasions such as the Chernobyl accident or vious nuclear weapons testa have decreased to such other unusual occurrences associated with radioae-an extent that monitoring at a large number of tivity, the fallout in rainwater becomes more signifi-stations is no longer considered necessary for ade-cant, because radionuclides in rainwater may pro-quate coverage.

vide a principal source ofdose to persons through th e grass to cow to milk to person pathway. Continuous 51onitoring Ilesults. 51easurable quantities of measurements at a few stations are sufficient to alpha, nonvolatile beta,"*Sr,"'Cs, and naturally identify these events when they occur.

occurring Te were detected in rainwater samples during the year. Quantities of radioactivity de-As a part ofits monitoring program for worldwide posited in rainwater are presented in Table 71, fallout and emission s from the plant, SRP maintain s Vol. II.

a network of sampling stations for rainwater. Loca-tions of the stations, sampling frequencies, and Alpha concentrations in rainwater were approxi.

methods of analysis are described in Chapter 10 mately the same as in 1986 with a maximum alpha deposition of 42 pCUm at II Aree. Nor olatile beta 2

Changes in 1987 51onitoring Program. No activitydepositedin rainwater ranged.' rom 516 to changes in the monitoring program occurred be-2,755 pCUm'. The maximum onplant nonvolatile tween 1986 and 1987. In 1986, routine monthly beta deposition was 1,624 pCi/m' at the !! Separa.

74 SAVANNAH RIVER PLANT - Environmental Report for 1987 of the quantity of radioactivity deposited from the atmosphere. Samples are collected from each of M[ ?Yih*

the four quadrants around the two separations areas and at the SitP boundary.Two controlloca-

.(.

"a tions approximately 100 miles from SitP are also 79, sampled.

[_

'))~

Monitoring Ilesults. The concentrations of radionuclides in soil vary signiGenntly among locations because of difTerences in rainfall pat-ly terns and the mechanics of transport in different a-p types of soil. Rates of migration in soil also vary

[

signiGeantly from one radionuclide to another.

, h For example, strontium tends to migrate th ough d

..~

j soil more freely than cesium or plutonium. The chemical separation of radionuclides in soil 3-samples in the laboratory is complicated by the nonhomogeneity of the soil and difficulty in strip-

[

ping ions from the soil. Individual measurements 4

f of radionuclides ia soil samples may not be repre-sentative oflarge areas. Averaged concentrations of multiple samples provide a better measure of

"."Clide c neentrations. Radioactivity llain pan collects rainwater samples concentrations m soil for 1987 are presented m i

tions Area. The average nonvolatile beta deposited Table 7-2, Vol. II. Deposition of radioactivity on soil, j

at the plant perimeter stations was 869 pCi/m.The calculatedin mCilm from the sample concentra-2 2

maximum deposition of 2,755 pCL/m was observed tions in Table 7 2,is presented in Table 7-3,Vol. II.

2 at the 100-mile radius station in Macon, GA.

A yearly summary of deposition values is shown in Table 7-4, Vol. II.

The deposition of"'Cs in rainwater ranged from less than the lower limit of detection to 590 pCi/m. The Strontium-90 concentrations in soil ranged from 2

maximum *Cs deposition was at the Olar station at less than minimum detectable concentrations to the 25 mile tadiu' O.61 pCi'g around F and 11 Areas, to 0.03 pCilg at the site boundary, and to 0.02 pCi'g at the 100 mile The depositi. of 2"Pu in rainwater ranged from less radius. These *Sr concentrations are similar to con-1 than the le er limit ofdetection to 1.1 pCi'm ; depo-cen trations observed over the last several years and 2

sition of' ?u ranged from the lower limit of detec-result primarily from worldwide fallout from nu-tion to 1 Ci/m'. These values are slightly higher clear weapons tests.

than the oberved in 1986.

Cesium 137 concentrations ranged from 0.12 to 1.0 Beryllium-7 concentrations ranged from 2,100 to pCL'g around F Area and 0.48 to 2.0 pCi/g around 11 2

13,000 pCi/m. Deposition of"*Sr due to worldwide Area. The 2.0 pCi/g result likely redects releases fallout ranged from less than the lower limit of from 11 Area. Concentrations of"'Cs at the plant pe-detection to 41 pCi/m. All mi results were less than timeter and 100-mile radius ranged from C 33 to 2

the minimum detectable concentration. Tritium 0.93 pCi'g. OfTsite data nte consistent w ith previou s concentrations in rainwater as eraged 4.6 pCi/ml at years and are within the concentrations observed the plant perimeter and 0.13 pCL/mL at the 100-mile from worldwide fallout.

1 radius. The maximum tritium concentration in plant perimeter rainwater was 65 pCi/mL Plutonium concentrations in soil samples around the separations areas are somewhat greater than Soll those detected at the plant perimeter, renecting F-and ll Separations Area releases. Cumulative at-Description of Monitoring Program. Soil mospheric plutonium releases from the separations samples from uncultivated area s provide a mca sure areas have totaled 0.7 Ci 2*Pu and 3.0 Ci "Pu i

. ~

~

7 Rainwater, Soil, Sediment, and Vegetation 75

?

through 1987. The largest part of these releases mum was 0.99 pCi/g. Concentrations of naturally l

occurred in earlier years of SRP operation. Releases occurring "K were within ranges observed in previ-for 1987 were 2.0 mci of *Pu and 0.27 mci of *Pu.

ous years with a maximum of 17 pCi/g.

Ranges of mPu concentrations in soil were 0.016-0.073 pCUgin F Area,0.012-0.051 pCi/ gin 11 The maximum "Sr concentration in river sediment Area,0.003-0.021 pCi/g at the plant perimeter, for 1987 was 0.06 pCi/g, as compared to a maximum and below minimum detection limits at the 100-of0.05 pCi/ gin 1986.Th e maximum concentration of j

mile radius stations. For "Pu, the ranges were "Pu was 0.027 pCi/g. Plutonium-238 concentra-O.006-0.094 pCi/ gin F Area,0.040-0.072 pCi/g in 11 tions were less than the minimum detectable activ-Area, and 0.013-0.021 pCi/g at the plant perimeter; ity for the analysis.

a maximum contentration of 0.02 pCi/g was re-ported at the 100-mile-radius stations. Most concen-In atream sediments, the maximum concentrations trations of "Pu and "Pu detected at the SRP detected were 16 pCi/g of"K,32 pCi/g of"'Cs,1.8 boundary and 100-mile-radius sampling locations pCi/g of"Co,0.98 pCi/g of SSr,0.66 pCi/g of"Pu, were near or less than minimum detectable concen.

and 0.23 pCi/g of"Pu. Stream sediment results trations, and all concentrations at those locations reflect contributions of radioactivity from SRP ro-were within the ranges observed during previous leases and are similar to results from previous years

years, with the exception of"Pu concentrations. In past

{

years, maximum "Pu concentrations of around 0.2 The quantity of *Sr, "'Cs, and 5 *Pu deposited in pCi/g have been detected at Four Mile Creek sam-i soil was calculated using soil density, sample vol-pl:nglocation A-7A, as compared to the higher 1987 t

ume, and the measured radionuclide concentrati. i maximum of 0.66 pCi/g.The exact point at which a i

in soil. Results for 1987 were greater than ranges sample is collected in the stream may vary at a

{

observed over the last several years. This effect is sampling location from year to year, and the higher l

due to a calculational correction: a 5-em depth factor "Pu concentration may be due to collecting the was used in previous years instead of the correct 8-sample at a slightly different place than in previous 1

cm depth.

years, i

i Sediment Vegetation l

Description of Monitoring Program. Sediment samples have been collected annually at six loca-Description of Monitoring Program. Radioac.

tions on the Savannah River above, adjacent to, and tive contamination of growing plants may result below SRP since 1975 and at nine plant stream loca-from sorption of radioactive materials from the soil j

tions since 1977. The samples are collected at loca-or from radioactivity deposited from the atmos-tions where maximum accumulation of radioactiv-phere. Grass is analyzed routinely for radioactivity; l

ity in the river and stream beds is expected. Col-Bermuda is used ifit is available, because ofits im-l lection techniques are designed to obtain samples portanee as a pasture grass for dairy herds and year-l from the top 8 cm of sediment in areas where fine round availability. Grass also provides an early sediment has accumulated Therefore, the samples indication of fallout because of the relatively large are not representative of the entire stream bed.

surface area of the grass blades exposed to the air.

Sediment is analyzed for gamma. emitting radionu.

clides, *S r. and * *Pu.

Vegetation samples are collected on the general j

plant aite and at the plant perimeter,25 mile radius, i

Monitoring Results. Analytical results for 1987 and 100 mile radius. Onsite samples are also col-and a summary since 1975 for both river and stream lected around seepage and retention basins and in sediment samples are presented in Table 7-5, and around the Solid Waste Storage Facility (Ilurial Vol. II. Concentrations of radioactivity in river sed-Ground).

I iments were within the ranges detected from world-wide fallout. Potassium-40, a naturally occurring Monitoring Results. Radioactivity in vegetation radionuclide, and "'Cs were the only gamma-data are presented in Table 7 6, Vol. II. Alpha emitting radionuelides detected in river sediment, concentrations for vegetation collected at the plant i

The maximum 1987 "'Cs concentration detected in perimeter,25, and 100 mile radius Imations were 1

the river sedimer.t was 0.62 pCUg; the 1986 maxi.

near or less than the minimum detectable concen'.

i l

i 70 SAVANNAH RIVER PLANT - Environmental Report for 1987 maximum concentrations were 0.37 pCUg alpha and 23 pCi/g nonvolatile beta at Il Separations Area.

Tritium concentrations in free water obtained from i

I f"

freeze-drying F-and II-Area vegetation were gener-I h, ally higher than those observed at the SRP perime-a g gre j'i ter and ofTsite and reflect SRP releases. The maxi-l I

mum tritium concentration in routine samples from

}%,'.k

b.*

F and 11 Areas was 380 pCi/mL. The maximum 2[

tritium concentration in onsite vegetation from a 9

tritium rclease occurring on July 31,1987, was

}

i 5,760 pCi/mL (the July tritium release is described I

3 in Chapter 8). Concentrations of gamma-emitting radionuclides and "Sr in onsite vegetation were I

'i l

within ranges observed in plant perimeter and off-J

^N site vegetation.

D Vegetation samples were collected around seepage and retention basins located near reactor and sepa-rations areas. Samples from four to eight locations Counting for alpha emitting radionuclides outside the fence of each basin were composited for alpha, nonvolatile beta, and "*Sr analyses. Alpha i

tration of approximately 0.2 pCUg. The maximum and nonvolatile beta concentrations were near lev-alpha concentration detected in vegetation was 0.5 els observed ofTsite with maximums of 0.13 and 49 pCi/g in a sample from the plant perimeter. Beta pCUg respectively. The maximum concentration of concentrations showed a relatively wide variation:

"*Sr was 13 pCi/g at II-Separations Area seepage from 9 to 35 pCUg at the plant perimeter, from 4 basin. These data indicate good control of radio-to 25 pCi/g at the 25-mile radius, and from 11 to 28 activity within the basins. Seepage and retention pCUg at the 100 mile radius. These difTerences are basin vegetation monitodng results are presented l

attributed to variations in worldwide fallout in Table 7 7, Vol. IL patterns.

Vegetation samples were collected inside the Solid j

Naturally occurring 'De and "K were the major Waste Storage Facility (643-G and 7G) to deter.

j contributors to the beta gamma activity in vegeta-mine whether significant uptake of radioactivity by i

tion. Maximum concentrations of "?Cs detected at vegetation from buried waste has occurred. Vegeta-the plant perimeter and 100-mile radius were 0.56 tion was collected from a relatively large area at 51 l

and 0.25 pCi/g respectively. A maximum "*Sr con-locations inside the Solid Waste Storage Facility con tration of1.7 pCUg was detected at both the plant (Burial Ground) and composited by location for an l

perimeter and 25 mile radius. These values are annual analysis. This collection method provides j

within ranges observed in previous years.

coverage of a large part of the facility,yet keeps the j

number of samples to a minimum. The samples were l

The average tritium concentration in the free water analyzed for alpha, nonvolatile beta, and gamma-4 obtained from freeze drying vegetation collected at emitting radionuclides. Sample location s a re shown the plant perimeter was 8.6 pCUmL compared to 1.4 in Fig. 71, Vol. II and data are presented in Table pCi/mL at 25-mile-radius station s and 0.9 pCUmL at 7-8, Vol.11. The only radioactivity above ambient l

100-mile-radius stations. Average concentrations levels was detected in vegetation from locations 9A, i

for 1987 are approximately the same as those seen in 11 and 12. The maximum concentrations were 7.6 1

1986.

pCUg alpha,6,006 pCi/g nonvolatile beta, and 37 pCUg of"'Cs. Locations 5 and 10 have a history of Analyses of vegetation from two locations around F contaminated vegetation. In 1965, contaminated and 11 Areas rhowed alpha concentrations approxi.

vegetation with cor.:entrations of up to 7.4x10' i

mately twice as high as those detected ofTsite and pCUg of"*Sr was found near locations 9 and 10.

nonvolatile beta concentrations within the range Soil eore samples at that time indicated up to 7.7x10'

]

observed at the SRP perimeter and offsite. The pCUg of nonvolatile beta (primarily "*Sr) within 2

)

i

7. Rainwatgn Soil, Sediment, and Vegetation 77 fl of the surface of the ground. The area has been (naturally occurring radionuclides) were also de-cleared of vegetation and treated with a herbicide tected. These surveys indicata control practices at several times.

the Solid Waste Storage Facility have ocen gener-ally efTective in preventing the spread of contan,ina-Vegetation samples were also collected quarterly tion from the facility, and vegetation sampling is an around the outside of.he Solid Waste Storage Facil-efTective method of detecting the release of very ity (Burial Ground) feaees. Th e maximum alpha and small quantities of radioactivity. Vegetation sam-nonvolatile beta concintrations were 0.46 and 21 pling locations outside the Solid Waste Storage pCUg respectively. A maximum mCs concentration Facility are shown in Fig. 7 2, Vol. II, and monitor-of 5.2 pCUg was detected at BG 10. Both 'Be and "K ing data are presented in Table 7 9, Vol. II.

1987 HIGHLIGHTS E Tritium concentrations in rainwater averaged 4.6 pCi/mL at the plant perimeter. The maximum tritium concentration in plant perimeter rainwater (85 pCi/mL) represents 4% of the Derived Concentration Guide (DCG) for water.

E Concentrations of *Cs in s00 at the plant perimeter and 100 rrite radius ranged from 0.93

!: 0.33 pCi'g, consistent with data from previous years.

E in river sediment, the maximum 1987 *Cs concentration (0.62 pCi/g) was lower than the 1986 maximum of 0.99 pCilg. The maximum "Sr concentration in river sediment in 1987 was 0.06 pCi/g, as compared to a maximum of 0.05 pCilg in 1986. The SPu concentration in sediment at one location was three times higher than the 1986 maximum concentration.

E Alpha concentrations in vegetation collected at the plant perimeter,25 mile, and 100 mile-radius locations were near or less than the minimum detectable concentrations of approxi-mately 0.2 pCilg.

E Radioactivity concentrations in vegetation collected around basins of the reactor and separations areas and around the outside of the Burial Ground were near offsite levels,in-dicating good control of radioactivity within the basins.

l l

l I

l

8 Special Surveys /Enusual Occurrences

SUMMARY

- TNs chapter fowses on special radiological surveys of tritium and radionu-clide tcleases by atmospheric and liquid pathways that have occurred during 1987, along with surveys of various areas around the SRP site, including the Savannah River swamp. In addition, a comprehensive survey of the intake and discharge systems of the Beaufort Jasper and Port Wentworth water treatment plants was conducted, and the results of analyzing sediment, vegetation, and water sampfes for gross alpha and nonvolatile beta activity and for tritium, strontium, plutonium, and gamma-emitting radionuclides are presented. An atmos-pheric radon study made at SRP and at residences in the region of the plant indicated that doses from radon were equivalent to those in other areas of the U.S. Other topics discussed include a low level gamma analysis technique for detecting *Cs in Savannah River water; an environmental data exchange among SRP, SRL, DOE, Georgia Power Company, Georgia Department of Natural Resources, and SCDHEC; the results of a Four Mile Creek Gurvey undertaken before initiation of a sampling program by SREL: and survcys of dry monitoring wells in both the F and H-Separations Areas waste management facilities, and in offsite Creek Plantation wells. The chapter also contains a section on the nonradiological monitoring of water and sediments for pesticides, herbicides, and polychlorinated biphenyls, and a icport y on oil and chemical spills in 1987.

y ItADIOLOGICAL SUltVEYS approximately one half as much tritium oxide is absorbed through the skin as is absorbed in the Tritium in the Environment lungs by inhalation [USNRC791. The halflife for biological removal of tritium oxide from the body is Tritium may be present in a variety of chemical approximately 10 days.

forms including oxide (IITO, T,0), elemental (IIT, T,), or as tritium labeled organics. Because of its Both tritium oxide and elemental tritium are re-chemical similarity to a water molecule, tritium leased to the atmosphere during routine operation or oxide is more readily assimilated into environ-the tritium facilities. The reactor facilities also re-mental media and human tissues than either the lease tritium, but this tritium is primarily in the elemental or organic form. The organic forms oxide form. Because hydrogen in tritium oxide read-represent less than 1% of the tritium releases ily exchanges with hydrogen in other materials from SRP.

(such as water), low-level concentrations are rou-tinely detected in the SRP environment. The aver.

Tritium has a physical half life of 12 years. The low age atmospheric tritium release from all facilities in energy beta particle emitted by tritium during decay 1987 was approximately 1,570 Ci per day and repre-will penetrate only 0.013 cm of human tissue. As an sented a 31% increase compared tc 1986. liow ever, elemental gas, tritium it nearl/ biologically inert the total amount of tritium oxide released was simi-and constitutes relatively little hazard. The weak lar to the 1986 value. Tritium oxide comprised ap-beta particle is completely attenuated by the inert proximately 44% of the total amount of tritium external skin layer (epidertris) and because only released to the atmosphere in 1987.

0.004% of elemental tritium inhaled is converted to the oxide and retained in the body [NCRP791.

All of the tritium released to the river or streamt is in oxide form. The average liquid release of tritium Almost all of the oxide form (water vapor) inhaled is from all plant sources in 1987 w1s approximately 62 absorbed in the lungs and enters the body water Ci per riay compared to approsimately 60 Ci per day pool, thereby exposing all body tissues, in addition, in 1986.

l l

80 SAVANNAH RIVER PLANT - Environmental Report for 1987

\\

Special environmental surveys were conducted minutes. The lined area indicates the region where when short. term tritiu n releases occurred on three the cloud

broke up" due to nearby thunderstorms.

1 occasions in 1987.The purpose of the surveys was to Sampling locations and tritium concentrations for

)

determine whether the releases carried a significant those samples within the plume path are presented risk of detriment to the public health or to the offsite in Tables 81 and 8 2, Vol. II.

j environment.

The tritium concentrations in surface watcr and Tritium Releases vegetation were similar to previous releases of this magnitude. The maximum tritium concentrations Atmospheric Tritium Release on July 31,1087.

detected in vegetation were 5,760 pCi/m L at NPDES l

Approximately 172,000 Ci of tritium was released to site H-004 near II Area,4,690 pCi/mL at the plant the atmosphere on July 31,1987, from the H Area perimeter, and 8 pCUmL at a location 25 miles from l

tritiura facilities as a resur af a line break during a the plant perimeter. The maximum vegetation con-maintenance operation [KuS7]. Approximately 3%

centration in the samples collected by SCDilEC was of the tritium released was in the oxide form (HTO) 2,069 pCi/mL. This vahie compares we!! with SRP J

and W% was elernental tritium (HT). The maximu m measurements from sampling locations 104 calculated dose to an individual at the site boundary through 108, which ranged in concentration from this release wa< 0 02 mrem (0.0002 mSv).

between 22 and 2,190 pCi/mL.Samplinglocations 104 through 108 were within two miles of the l

At the time of the incident wind direction was SCDilEC locations. Tritium mncentrations in sur-initially toward the east, then shifted toward the face water ranged frern a maximum concentration of north northeast. The TRAC (Tracking Radic<tive 48 pCi/mL at the plant perimeter to 4.0 pCUmL at Atmospherie Contaminants) van, SRL's mobile the 25 mile radius.

laboratory, responded to the release and obtained measurements along the path of the plume. Sam-The maximum ofTsite tritium oxide concentrations pling teams obtained air concentration n casure-detected in air were 286,000 pUi/m HTO at the 8

ments on the day of the release. Vegetation and plant boundary and 45,100 pCi/m'llTO at approxi-surface water samples were cellected at locations mately 20 miles downwind.

onsite, along the plant perimeter, and along a 15 and 25-mile radius in the path of the plume. Stilk Liquid Tritium Releases. On February 15,1987, samples were collected from offsite dairies. South a thermal diffusion column failure in an Il Area Carolina Department of Health and Environmental tritium facility caused water contaminated with Control (SCDHEC) collected vegetation samples tritium to enter the process cooling water system offsite. Fig. 8-1 on p. 81 (also in Vol. II) shows the and subsequently to be released to Four Mih Creek.

movement of the tritium cloud as predicted by the The maximum tritium concentration detected it.

WIND system. The circles on th e figu re indicate pufr Four Mile Creek after the failure was 5,200 pCUmL, l

positions and the width of the release every 60 at sampling location FM 1C. The average concen-1 tration detected in Four Mile Creek during c,2 j q,,

1 C+

!i

, 4 1986 was 70 pCUm L. Th e process cooling water was diverted to the seepage basin on February I

Q N

15, 1987; however, the tritium level in the k

ellluent did not return to normal until mid-m i

g March. The total release to Four Mile Creek i

j due to this release was 156 Ci.

J J-

)

Elevated concentrations of tritium were de-I tected in water samples collected from the 400-y D Area process sewer on May 11,1987. Subse.

quent laboratory analyses indicated 433 Ci of O

I tritium was released to Beaver Dam Creek from May 5 to May 12,1987. Investigation revealed that the release occurred on May 10, 1987, during startup of a *00 D heavy water 1

SitL's TRAC van rework facility.

I i

8. Special Surveys / Unusual Occurrences 81 GD "r

n

/

Wagenei, Nn I

Aiken

/

Neeses

/

%ringfield

< -/

9 New Ellenton Williston M

/

k BIscky;;;g i

\\

Deninstk F

H 321 C

P j\\

~f Barnweig k

L j

0 i

IE' E*I\\Iovement of tritium cloud as predicted by WIND system

82 SAVANNAH RIVER PLANT - Environmental Report for 1987 Other Radionuclide Helcases by sensitive environmental radiometric methods.

The study confirms low levels of tritium detected II Area Solvent Helease. On January 1,1987, by routine analysis of drinking water samples are overCow of a solvent sump area resulted in elevated introduced aner the water is drawn from the aqui-concentrations of gross alpha beta radioactivity in fer. The tritium may be introduced into the water Upper Three Runs Creek. Special samples were samples during chemical treatment or through collected along the release path of H 004 outfall, S.

exposure to atmospheric tritium during aeration.

Area Settling Basin, Crouch Branch, Upper Three Runs Creek, and the Savannah River, successively.

Dupliente drinking water samples were collected in An estimated 1.5 Ci of mixed radionuclides were specially prepa red bottles from P, K, L, and 11 Areas.

released through the storm sewer to the 11004 In the first two weeks of sampling, water was taken outfall. The relea se for the period from December N, from drinking water fountains. In the next two 1986 to January 2,1987, was 3 mci alpha and 8 mci weeks, water was collected directly from the well nonvolatile beta activity to Upper Three Runs head. The SRL Environmental Radiometries labora-Creek. During the period from January 2 to January tory analyzed the samples in low level tritium facili-13,1987, the release of radioactivity decreased to 2 ties and determined tritium concentrations by pro.

mci alpha and 7 mci nonvolatile beta. Gamma portional counting of the hydrogen gas generated analysis yielded background results for Upper from the water. The SRP Environmental hionitor.

Three Runs Creek.

ing laboratory analyzed duplicate samples in its routine facilities u sing distillation and liquid scintil-The majority of the activity released was retained in lation counting, the S. Area Settling Basin sediment. The primary gamma-emitting radionuelides detected were *Ru, Concentrations or minimum detectable amounts "Ru,"Zr, and "Nb with a maximum concentration are shown in Table 8-3,Vol. II. Results from the SRP of 181 pCi/g of *Ru.

Environmental Stonitoring laboratory indicated low level contamination of the water samples dur-H Area Atmospheric "'Cs Helease. On Novem-ing chemical treatment and aeration, as described ber 24,1987,1 Ci of"'Cs and 33 mci of *Cs were previously. SRL Environmental Radiometries re-releasedtotheatmospherefroman H Areaevapora-sults showed low but positive concentrations in four tor in the waste management facilities. The release of the water fountain samples. One of the samples resulted from a valve dange steam leak. Elevated collected directly from the well head and the control nonvolatile beta and cesium concentrations were sample taken from a well in Jackson, SC, showed detected at onplant and plant perimeter ambient air concentrations at the minimum detection level and monitoring stations. The maximum "'Cs concentra-do not reDeet contamination of the aquifer-tions detected onplant and at the plant perimeter 8

were 0.70 pCUm (at the onplant H Area monitoring Steasurements of '"I in Groundwater and station) and 0.79 pCUm (at the plant perimeter D.

Surface Water 8

Area monitoring station). The maximum concentra-tion of 0.79 pCUm was 0.2% of the DCG for "'Cs.

The Savannah River Laboratory has conducted a 8

Vegetation sample analysis showed elevated "'Cs study at irregular intervals since 1970 to determine

{

concentrations around 11 Area with a maximum F the "I content of groundwater and surface water at

)

8 17.6 pCi/g southeast of H Area. The H Area rain.

onplant and ofTplant locations (Ka87L hieasure-water sample did not show "'Cs concentrations ments were made by neutron activation analysis, above the lower limit of detection of 0.009 pCUmL Iodine 129 was detected in groundwater near the Burial Ground and near the seepage basins of the Special Study of Tritium Concentrations in Separations Areas. For reference, 3"I concentra-Drinking Water tions in the groundwater can be compared to the EPA drinking water standard. At a few locations, A special study was performed in 1987 to determine the concentrations exceeded both the existing and tritium concentrations in drinking water and well pending EPA drinking water standards of 1 and 100 water in several SRP operating areas. Analyses pCi/L, respectively. In surface water, Four h!ile show that no tritium contamination in the Black Creek was the only SRP stream found to transport Creek 51iddendorf Formations (formerly called the signineant51 to the Savannah River. Dilution by C.

Tuscaloosa Aquifer)is preser. at levels detectable Reactor discharge and the Savannah River reduced 1

8. Special Surveys / Unusual Occurrences 83 the ofiplant ml concentrations in river water to less Comprehensive surveys were made annually along than 1% of the existing EPA drinking water stan-the trails between 1974 and 1977.These comprehen-dard and less than 0.01% of the pending standard.

sive surveys included TLD gamma radiation meas-i urements and analysis of vegetation, soil, and Osh A quarterly sampling program for *1in Savannah samples. The frequency of comprehensive surveys River water upstream and downstream of SRP was was reduced to five-year intervals aRer 1977, be-reactivated in 1986 aRer Ove years of dormancy.

cause the surveys indicated no signi0eant changes Sam pling efwater at the two wate r treatment plan ts in radiological conditions. Interim monitoring was downriver of SRP is planned for 1988.

provided by annual TLD mea surements along the 10 transects. A routine comprehensive survey was con-Savannah ltiver Swamp Survey ducted in 1982. Another comprehensive survey was performed in 1985 during construction of L Lake.

Description of 51onitoring Program. The Cursory surveys were performed in 1986 and 1987.

Savannah River swamp between Steel Creek and Little llell Landing was contaminated with approx-imately 25 Ci of *Cs and less than 1 Ci of"Co in the Monitoring Results. During 1987, soil an d vegeta.

1960s. The contaminated swamp area extends be-tion samples were colkcted at three locations along yond the SRP site boundary to private property trails 1,5 and 10 in addition to the annualTLD mea-known as Creek Plantation.The offsite swamp area surements. Samples were collected to continue is uninhabited and inaccessible except for possible monitoring for any changes that may have resulted occasional hunting or Oshing.

from the restart ofL Reactor. Samples for 1987 were collected a s n ear as possible to th e location s sampled The source of the radioactivity was failed fuel ele.

in earlicr years. Monitoring data are presented in ments that leaked radioactivity into storage basin Tables 8-4 through 8 9, Vol. It water used to shield and evol irradiated fuel ele-i ments. Over time, portions of the fuel storage basin TLD gamma radiation measurements were made by water containing the WCs and "Co were discharged placing dosimeters one meter above the ground at to Steel Creek. The radioactivity settled in the previously identi0ed locations along the trail. The swamp during periods when Steel Creek Cowed dosimeters were collected for processing after an across the swamp before entering the river at Little exposure period of approximately 30 days.The 19S7 IIell Landing. The failed fuel elements were re-results ranged from 0.17 to 0.94 mR/ day and were in moved from P-Area fuel storage basins in 1970.

general agreement with data from previous years.

TLD radiation measurement data are presented in Ten sampling trails were established in the swamp Table 8 4, Vol. II.

l in 1974 in order that speciOc locations could be repetitively monitored to determine whether ra-TLD data collected during the 1986 survey were dioactivity in the swamp was migrating (Fig. 8 2, found to be unusual when compared with previous Vol.11).

years. A resurvey conducted during April 1987 con-Ormed that the original 1986 survey results were bi-ased by imp roper an alytical tech nique. Th ese resur.

.-)4

- se

=

vey data are also presented in Table 8-4, Vol. II.

U

't k'

l Soil core samples, collected at selected locations along trails 1,5, and 10, were analyzed for gamma-

'.'w emitters, *Sr, and "Pu. Analytical data are pre-f, sented in Tables 8-5 and 8 6, Vol.11. Cesium 137 g

was the only gamma-emitting radionuclide de-

\\

, J.@

tected. The concentrations of #Cs in soil were w ith-

,1 in ranges observed during the last severalyears and r

s:

9 d.

r-

_K showed a maximum of 178 pCUg. Strontium 90 concentrations m soil showed a maximum of 0.31

'w v

w.

^

)

'Y'

~*

pCUg and were within ranges obsernd in previous years.The maximum *Pu concentrationsin soil 1

Typical Savannah River swamp were 0.05 and 010 pCUg, respectively, and all l

l 1

- c

_,.,_.__-,.y._,,._----._-__._,__,,.,,,,,,,~,-%,_,,_..,.

-. - _ -_----.wv_.,. _ _, -. _.. _.

84 SAVANNAH RIVER PLANT - Environmental Report for 1987 Savannah River Area (CSRA)from naturally V

A occurnng radioactivity.

i#

Special Creek Plantation Well Survey

]

Wells on the Creek Plantation were sampled and analyzed for radioactivity during August g

y 4

1987. This study was conducted to confirm 6 -

these wells have not been impacted by SRP C

operation s. The results are presented in Table 8-10, Vol. II. All results were below E PA Drink-i ng Water standards and were within ranges 1

observed for other drinking water wells rou-4 tinely sampled.

Low Level Gamma Analysis of Iliver Water Monitoring for gamma emitting radionuclides Cesium 137 was detected by SRL both upriver 2*Pu concentrations were within ranges observed and downriver of SRP using a special low-level during the last several years. Concentrations of ra-analysis technique. The technique consists of sam-dionuelides in soil vary from sample to sample and pling large volumes of water and measuring the from year to year because of slight differences in radioactivity in a low background counting facility.

j sampling location and the non homogeneity of soil.

The continuous sampler typically processes 300 to 500 liters of water per week. Cesium 137 and "Co in Vegetation samples were also collected along Trails the water are selectively concentrated on ion ex-l 1,5 and 10 and analyzed for alpha-and gamma.

change material and counted for approximately 16 emitting radionuclides. Alpha concentrations were hours on an IIPGe detector in a low background 1

within the ranges observed in previous years and counting facility.The speciallow level u'Ca data are l

showed a maximum of 0.63 pCUg. Alpha data are presented in Table 8-11, Vol. II. A graph of all data l

presented in Table 8 7, Vol. II. The only gamma-collected since 1983 is shown on p. 85 in Fig. 8-2 emitting radionuclides detected in vegetation were (shown as Fig. 8 3, Vol. II).

u'Cs and naturally occurring "K. Cesium 137 con-centrations were within the ranges detected in pre-In 1987, "'Cs concentrations upriver of SRP (Shell vious surveys. The maximum "'Cs concentration BlufD averaged 0.010 pCUL. The downriver (Iligh-was 2.4 pCUg. Data am shown in table 8-8, Vol.11, way 301) concentrations averaged 0.057 pCi/L. The difference between the upriver and downriver con-Fish were collected from two of the three lakes in centrations is attributed to releases from SRP op.

close proximity to the swamp trails. Boggy Gut Lake erations. The maximum "'Cs concentration of 0.103 is n ormally sampled but wan dry in 1987. Concentra-pCi/L was 2,000 times less than the EPA drinking tions of WCs in the 10 fish analyzed were within water standard of 200 pCi/L Concentrations of ranges observed during previous years and are pre-

"Co were less than the minimum detectable con-sented in Table 8 9, Vol.11. The maximum "'Cs con-centration of 0.01 pCUL both upriver and downriver centration was 1.2 pCi/g in a bream from Cannuck of SRP.

Lake. The maximum concentration in the 27 fish from the River 2 controllocation upriver ofSRP was Comprehensive Surveys at the Beaufort-1.1 pCUg in a bream. The 50-year "'Cs dose com-Jasper and Port Wentworth Water mitment from eating fish for one year (163 kg Treatment Plants average consumption) collected from Cannuck i

Lake and Jacks Lake (maximum 1.2 pCUg) would Comprehensive surveys of the intake and discharge be 0.7 mrem (0.007 mSv) or 0.002% of the annual systems of the Beaufort-Jasper and Port Wentworth l

dose to an average resident of the Central water treatment plants (about 100 miles down-l

8. Special Surveys / Unusual Occurrences 85 CS-137 CONCENTRATIONS AT HIGHWAY 301 0.5-0.4-p 0. 3 -

lf

,0.2-I L

,&f1 g,gi hf

^'~

.0-i i

i

-r 01JAN83 01JAN84 310EC84 310EC85 310EC86-310EC87 YEAR CS-137 CONCENTRATIONS AT SHELL BLUFF 0.20-O.15 -

P C 0.10 -

/

L 0.05-f([h* 4

/

eo 310kC84 310kC85 310dC86 310kC87 OlJ N83 01J N84 YEAR Fig. 8 2. Iow level '"Cs concen! rations in the Savannah River stream from SRP) were conducted following the 1986, and ending in April 1987. Data from the first 1985 startup of L Reactor. Fig. 5-3 in Vol. Il shows three quarters of sampling were included in the the locations of the water treatment plants. The sur-1986 SRP Environmental Report (Ze87]. Complete veys were conducted quarterly beginning in June survey results are presented in this report.

86 SAVANNAH llIVElt PLANT - Environmental Iteport for 1987 Surveys were conducted to meet Environmental detected was 5,000 pCi/I,. This value is above the impact Statement requirements and to determine baseline maximum 002,300 pCi/I Tritium concen-whether the L lleactor startup afTected the water trations in the fourth quarter ranged from 740 to from treatment plants below SitP. Similar surveys 1,680 pCi/I,, lower than concentrations seen in the were conducted in 1983 to provide baseline data on Orst three quarters of the survey, llowever, these environ mr ntal eon ditions prior to lelleactor startu p results were consistent with lower levels also de-in October 1985. In addition to radioactivity meas-tected at the SitP ltiver 10 location (1,850 pCUL).

urements, water quality measurements were also Cesiu m concentrations were less than lower limit of performed. Monitoring results showed no signifi.

detection values. The 16 pCi/L beta and the 5,000 cant change to the water from the treatment plants pCUL tritium values appear to be spurious results, as a result of L Itenctor startup.

Twenty seven vegetation samples were collected lleaufort Jaspe.- Survey Samples consisted of from the Imnks of the canal along each transect and sediment cores, vegetation, water, fish, and turtles along the banks of the ItWilP and llWilPs. Vegeta-in the intake canal between the Savannah Iliver and tion monitoring data are presented in Table 813, the lleaufortJasper water treatment plant. Some Vol. l!. All sample results for vegetation are reported samples were also collected from the raw water in activity per gram of dry weight. Gross alpha holding pond (ItWilP) and the backwash holding concentrations in vegetation ranged from 0.01 to l.0 ponds (!!WIIP).

pCi/g which were near or less than the values de-tected in 1983 when the maximum was 1.6 pCUg.

The llWilP is a reservoir of approxin ately 0ve ncre, The only gamma emitting radionuclides detected th at su pplies feed water from the Savan nah Iliver to were "'Cs and naturally occurring "K. Maximum the water treatment plant. Water reaches the hohl.

concentrations of "K and "'Cs were 46 and 1.0 ing pond via an 18 mile longcanaland pipeline from pCUg, respectively, as compared to 1983 maximumn the river. At the water treatment plant, raw wateris of 65 and 1.5 pCi/g, respectively. Most samples had treated with alum to coagulate suspended solids.

"'Cs concentrations below the minimum detectable After coagulation and settling, the water is passed concentration range of 0.1 to 2.0 pCUg In samples through sand Olters to remove remaining Olterable analyzed for "Sr the maximum concentration de-solids. Itesidues from the coagulation process and tected was 1.4 pCUg.The maximum *Pu concentra, from sand 0lter back nushes are released to two hohl.

tion detected was 1.0 (Ui/g, and the maximum *Pu ing ponds (llWi!Ps). Figure 8-4, Vol. II, shows a concentration detected was 1.0 fUi/g.

diagram of the holding ponds at the lleaufort-Jasper treatment plant.

Sixty three sediment samples were collected at in-tervals along each transect and holding pond. The Fourteen transects across the canal were selected sediment cores ranged from three to 12 in. in depth for sampling. Water samples were collected at the in the canal ponds. Itadionetivity data for sediment approximate midpoint ofeach transect,one from the are presented in Table 8-14, Vol. II. All saliment itWilP and one from each of the llWiiPs. These sade results are in activity per gram ordry weight.

samples were analyzed for gross alpha and nonvola.

Gross alpha concentrations ranged from 0.2 to 5.7 tile beta a ctivity and tritiu m, stron tiu m, plutonium, pCUg. lleta concentrations ranged from 31 to 9.3 and gamma. emitting radionuclides. Itadionetivity pCUg. Alpha and beta analyses were not performed in water is presented in Table 812, Vol. II.

in 1983.

Cesium 137 was the only manmade gamma-emitting radionuclide detected. Its concen-Alpha concentrations in water ranged from less trations ranged from less than 0.03 to 3.5 pCUg.The than detectable concentrations to 4.5 pCUL. Non.

maximum concentration detected in 1983 was 2.0 vobtile beta concentrations ranged from 0.8 to 16 pCUg. Those concentrations above 1 pCUg, may re-pCUL. The maximum alpha and beta concentrations Dect some contribution from SI;P releases. Con-were higher than 1983 maximums of 0.88 and 4.3 centrations up to about 1 pCi/g are detected at lo-pCi/L, respectively, llowever, routine analysis of is not innueaced by SitP operations and are s

water from the lleaufort-Jasper plant indicated attnbuted to worldwide fallout from nuclear weap-normal ranges with a maximum of 0.73 and 4.7 pCU ons tests. Strontium 89,90 concentrations ranged L, respectively, during the same period as the 1986 from 0.1 tn 3.1 pCUg. Samplew were not analyzed for 1987 survey. The maximum tritium concentration

"*Sr in 1983. Concentrations of"l% detected in

8. Special SurVOys/ Unusual Occurrences 87 sediment ranged from less than detectable concen-the inlet line to the Port Wentworth water treat-trations to 34 fCUg.The maximum "Pu concentra-ment plant at Abercorn Creek and its pumping 2

tion detected in 1983 was 2.0 fCUg. Plutonium-239 station, at the plant settling basin, and near the contentrations ranged from 0.1 to 13 fCUg. The waste water discharge at St. Augustine Creek.

maximum "Pu concentration in 1983 was 8.0 fCUg, Water is supplied to the Port Wentworth water The higher 19861987 plutonium valuca may rep-treatment plant through a seven. mile long pipeline resent some contribution from SRP releases and from Abercorn Creek. Waste materials from the better quality of analytical techniques, treatment plant are discharged through a series of lines and ditches to a swampy area that drains to St.

Gamma rulse he mht analysis (PIIA) of 39 fish from Augustine Creek.

the canal and holding ponds showed detectable "?Cs in one fish sample from BWilPof 0.04 pCi/g. All 1983 Sixteen water samples were collected from the in-

"?Cs values for fish were less than the minimum takes and discharges for the treatment plant and detectable concentration. Fish data are presented in analyzed for gross alpha, nonvolatile beta, tritium, Table 815, Vol. II.

and gamma-emitting radionuclides. Water sample data are presented in Table 8-17, Vol. II. Gross al pha Twenty-one water samples were collected for water values ranged from less than minimum detectable quality analyses. These samples were analyzed for values to 3.9 pCi/L. In 1983, alpha values were less temperature, pil, dissolved oxygen, turbidity, con-than minimum detectable concentrations. Nonvola-ductivity and suspended solids. No noticeable tile beta concentrations ranged from 0.4 to 20 pCi/L, trends in the water quality were evident except that which is higher than the 1983 maximum beta con-turbidity and suspended solids we-slightly lower centration of 3.0 pCi/L. Tritium concentrations were than in 1983 and conductivity we, alightly higher similar to routine measurements at the treatment than in 1983. These data are prsented in Table plant and ranged from 1,320 to 4,500 pCUL. The 8-16. Vol. II.

1983 survey maximum was higher at 5,600 pCUL. Concentrations of all gamma emitting Port Wentworth Survey. Water, sed. ment, veg-radionucludes were less than the lower limit of etation, and aquatic specimens were collected near detection.

t g

8 k

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s

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. 65

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- A=y, m4 Collecting water samples

88 SAVANNAH IllVER PLANT - Environmental lleport for 1987 Sixteen vegetation samples were collected along the Conductivity has been erratic at these locations in banks ofAbercorn and St. Augustine creeks and the the past. Water quality data are presented in Table Port Wentworth settlingImsin. Vegetation monitor-8 21, Vol.11, ing results are presented m Table 818, Vol.11. All analyses are in acti/ity per gram of dry weight.

Special Atmospheric Itadon Study Gross alpha concentrations ranged from less than detectable concentrations to 0.5 pCi/g The alpha A study was conducted to(l) summarire the source, values are less than the 1983 maximums. Concen-dosimetry, and risk related to radon and radon trations of *Sr ranged from less than detectable progeny;(2) to review the results of radon me :sure-concentrations 100.7 pCUg, compared to a 1983 ment data collected by the %vannah Itiver Plant; maximum of 0.36 pCUg. Gamma analysis showed and (3) to recommend how radon monitoring data only naturally occurring "K (34 pCUg maximum) could be included in routine environmental reports and "'Cs (2.0 pCi'g maximum). These results com-to provide a comparison between risks from plant-pare favorably with 1983 values. Concentrations of generated radionuclides and those from naturally "Pu ranged from 0.1 to 10 IUi'g, while concentra-occurring radon.

tions of "Pu ranged from 0.01 to 2.0 IUUg. Pluto-nium analyses were not performed in 1983. Concen-From the period of September 1984 through 51 arch trations of" #Sr ranged from from less than detect-1985, several sets of atmospheric radon measure-able concentrations to 0.7 pCUg. This analysis was ments were made at various locations at the Savan-not performed in 1983.

nah Itiver Plant and in various homes throughout the local area. The purpose of these measurements Thirty.two sediment cores were collected from Aber-was:

corn Creek (at the mouth and pumping station), St.

Augustine Creek, and the plant settling basin. The B to improve the dennition of the natural cores were analyzed for concentrutions of alpha, background of radon and radon daughter nonvolatile beta,"Pu, "*Sr, and gamma emit-products in indoor locations at the Savan-ters. The cores ranged in depth from three to 10 nah lliver Plant and in the local area, inches. Sediment monitoring data are presented in Table 8-19, Vol.11. Gross alpha concentrations E to estimate the radiation dose associated ranged from less than detectable concentrations to with the levels of radon and radon daugh-1.3 pCVg. Nonvolatile beta concentrations ranged ters using reference dosimetric methods, from 2.3 to 15 pCUg. These analyses were not per-and formed in 1983. As in 1983,"'Cs and naturally oc-curring "K were the only gamma emitters detected 5 to describe an average radon and radon in sediment. Cesium 137 concentrations ranged daughter contribution to background from less than 0.05 to 9.0 pCUg. In 1983, the radiation dose, maximum "'Cs was 3.0 pCUg. Concentration s of"K ranged from 2 8 to 37 pCi/g. In 1983, the maximum Measurements of radon were made at the SitP and "K value was 14 pCi!g. Concentrations of "Pu at residences in the region of the plant using char-ranged from 0.20 to 57 (Ui/g, and "Pu concentra-coal canisters supplied by the Department of tions ranged from 0.04 to 261UUg Plutonium analy-Energy s Environmental Measurements 1.abora-ses were not performed in 1983.

tory. Data were collected over ditTerent periods to study seasonal variations in radon levels in build-Nine Osh from Abercorn Creek were analyzed for ings. Specine instructions to er ure uniformity of gamma.cmitting radionuelides. As in 1983, "'Cs sampling were issued with the t enisters.

concentrations were less than 1.0 pCUg. These data are presented in Table 8-20, Vol,11.

From this study, the geometric mean of etTective dose equivalent for continuous exposure in homes Water samples were analyzed for temperature, pli, during warm and cool weather is estimated to be 252 dissolved oxygen, turbidity, suspended solids, and and 415 mrerWyear, respectively. The annual aver-conductivity. All water quality measurements were age efTective dose equivalent to residents in the within ranges normally observed in the ris er except Savannah Itiver region from radon is estimated to for conductivity, which was higher at the plant lie bet w een 100 and 300 m rem' yea r. This estim ate is settling basin and St. Augustine Creek locations.

based on assumptions that individuals are not con-

8. Special Surveys / Unusual Occurrences 89 tinuously exposed to radon and that indoor radon from environmental radioactivity sampling. The concentrations vary seasonally. A comprehensivo exchange of sample results among the groups is in-assessment of radiation exposure of the U.S. popula-tended to provide an additional interlaboratory tion reported by the National Council on Radiation quality assurance (Q A) check, to in crease con fiden ce Protection and 51easurements (NCRP)in 1987 esti-in each group's monitoring pregram, to enhance mated the average radon dose to be 200 rnrem/ year public confidence in monitoring around SRP, and to

[NCRP87a).

provide a mechanism for timely communication of technical data.

This study of radon in homes near the Savannah River Plant and buildings on the plant lends signifi-Common samplinglocations and types were identi-cant insight into typical radon concentrations in the fled, and analytical schemes were selected. The region. Although this study does not represent a table below lists the samples chosen for the first comprehensive analysis of radon in the Savannah phase of data exchange scheduled for 1988.

River Plant area, these data along with the data reported by the South Carolina Department of Other types of samples such as vegetation, soil, and llealth and Environmental Control indicate that fish were identified as possible candidates for split levels of radon in the region are approximately sampling and parallel analysis among the partici-equivalent to the national average suggested by the pants in future data exchar.ges. The group agreed Environmental Protection Agency of 1 pCi/L. The on a quarterly reporting frequency, using a common dosimetry of radon is reviewed in ICRP Publication format for the data, which would be collated 32 [1CRP81].

and redistributed by participants on a rotational basis.

Environmental Data Exchange Special Four 5111e Creek Survey During 1987, representatives from South Carolina Department of Ilealth and Environmental Control Savannah River Ecology Laboratory (SREL) began (SCDiiEC), Georgia Departraent of Natural Re-sampling in the main Four Stile Creek (F31C) chan-sources (GDNR), Georgia Power Company, Depart-nel below C Area in 1987. SHEL requested a special ment of Energy (DOE), Savannah River Laboratory survey of the F51C work area to be completed before (SRL), and Savannah River Plant (SRP) met to initiation of their sampling activities. Data from this discuss mechanisms for routine exchange of data survey were used to assess potential exposures of Sample Type and location Analysis SAVANNAII RIVER:

gross alpha and beta, tritium, gamma emitting radionuclides Port Wentworth Water Treatment Plant Beaufort-Jasper Water Treatment Plant Ilighway 301 Bridge A31BIENT AIR 510NITORING:

gross alpha and beta, gamma-emitting radionuelides, radioiodine Waynesboro, GA Ilighway 21/167 TLDs:

gamma radiation S SRP locations Waynesboro, GA Columbia, M

90 SAVANNAH RIVER PLANT - Environmental Report for 1987 personnelin or near the stream to ionizing radia-measured in these four wells, all of which monitor tion and heavy metals.

diversion box #1.Seven DM wells were not surveyed because of water in the wells.

Radiation doses were calculated on the basis of assumptions and empirical measurements in the Radiation measurements were ande in an addi-vicinity of FMC. The maximum potential dose from tional 37 of 38 DM wells installed in a contaminated tritium exposure via inhalation and submersion for area near Tank 8 in the F Area waste management 25 weeks,40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months per week, was 2.07 mrem (0.021 facilities. Radiation levels measured in the Tank 8 l

mSv). A more realistic average dose from exposure wells denne the zone of major contamination, as via these two modes is 1.62 mrem (0.016 mSv). f LDs shown in Fig. 8-5, Vol. II. This contamination is wert, used to measure gamma radiation from FMC attributed to overfilling the tank in 1961. Radia-l sediments and along the stream bank. fLD meas-tion levels around Tank 8 remained high during l

urement data are shown in Table 8-22, Vol. II. The the 1987 survey. The maximum radiation level in average net dose from sediment (above background) the wells was 86 R/hr in RP-6 at a depth of 19 ft I

l would be 3.75 mrem (0.038 mSv) to an individual working in the creek 25 weeks (1,000 hours0 days 0 hours 0 weeks 0 months ). A more Fifteen of 16 DM wells in sersice in the II Separa-realistic dose of 3.3 mrem (0.033 mSv)is projected tions Area waste e nagement facilities were sur-by assuming that an individual divides his work veyed. IIDM wells showed no significant 1987 hours0.023 days 0.552 hours 0.00329 weeks 7.560535e-4 months between being in the creek and sampling changes from previous years, with the exception of along the creek bank.

IIDM wells 7 and 23. These wells showed back-ground radiation levels during 1987, while 1986 Results were less than lower limits of detection for radiation levels were greater than background.

l atmospheric *l and gamma-emitting radionuclides Radiation levels for dry wells in the F. and II.

in airborne particulates. In addition, water and Separations Area waste management facilities are sediment samples were collected by SREL from represented in Figs. 8-7 and 8 8, Vol. II.

I FMC at Road C down to Four Mile Delta. Samples were analyzed for tritium,"Sr,"fe, and "'Cs. Ra.

NONRADIOLOGICAL SURVEYS i

dioactivity monitoring data are presented in Table i

8 23,Vol. II. Samples were also analyzed for volatile Monitoring for Pesticides, Herbieldes, and organics, base / neutral and acid extractable com-Polychlorinated Hiphenyls pounds, pesticides and PC Bs, metals, and eyanide as shown in Table 8 24, Vol. II. The samples were ana.

Description of Monitoring Program. Water and lyzed by International Technology Corporation (IT),

sediment samples from seven site stream locations Oak Ridge,TN. A comparison of!T and SRPanalyti-were analyzed for 32 pesticides, herbicides, and cal results from common location s is shown in Table polychlorinated biphenyls (PCBs) during 1987. A 8-25, Vol. II.

listing of the 32 constituents and typical minimum detectable concentrations are shown in Table 8 26, Surveys of Dry Monitoring Wells in Vol. II. This program has been conducted since 1976 Separations Arean Waste Management to assess et,ncentrations of these materials in Facilities streams and the Savannah River, j

Profile radiation measurements were taken in dry Monitoring Results. Concentrations of all the l

monitoring (DM) wells in both the F. and II Separa-parameters analyzed in river and stream water and tions Areas waste management facilities. Figs. 8-5 sediment were less than the minimum detectable and 8-6 in Vol.11 show the location of the dry moni.

concentrations, except for the herbicide dicamba in toring wells. DM wells are two-inch diameter closed Four Mile Creek at Road A.The dicamba concentra-bottom steel cased wells that terminate above the tions in water and sediment samples were 2.0 pg/L wa ter table. Each well is cement grouted and capped and 36 pg/kg, respectively. There are no known i

to k eep surface water from leaking into the well. The drinking water standards for dicamba.

wells are located at points considered most vulner-able to leaks from piping which serves the storage Dicamba is not used at SRP, and its presence in SRP

tanks, stream s is attributed to ofTsite farming operations or i

upriver Savannah River water pumped to SRP fa-Four of 11 DM wells in the F Area facilities were cilities and then released to streams. Ahistory orde-surveyed in 1987. Background radiation levels were tectable pesticides, herbicides, and PCDs in SRP 1

l

8. Special Surveys / Unusual Occtirrences 91 stream water is presented in Table 8-27, Vol. II, and ment if the same spill were to go down a drain to a stream sediment in Table 8-28, Vol. II. Note that sewer line, it would be reportable. All chemical some detection limits have changed from year to releases to the atmosphere (e.g., chlorine gas) are year, partly because of sample m atrix in terferences.

considered spills for reporting purposes.

Spills The spill coordinator advises custodians on reme-dial action and helps determine whether a spill is Description of Monitoring Program, A site-reportable to the EPA and SCDilEC under guide-wide procedure requires prompt reporting of oil and lines of the Comprehensive Environmental Re.

chemical spills to a spill coordinator. The coordina-sponse, Compensation and Liability Act(CERCLA).

tor ensures that spills are r eported to the DOE, SPA, CERCLA is commonly called Superfund. A well.

and SCDilEC as appropriate to satisfy regulatory trained spill response team is on call to assist with requirements.

confiaement of spilled material.

A spillis defined as any unintentional discharge to Spills During 1987. In 1987, there were 145 spills th e environ men t. Environ men t is b roadly de fined as reported to the spill ec,ordinator. Most of these were any water, land, or ambient air. If a substance is minor spills ofpetroleum products. None ofthe spills spilled on a concrete floor inside a building, it is not were reporteble under CERCLA.

reportable because it does not reach the environ-1987 HIGHLIGHTS E The average e'mospheric tntium release from all facilities in 1987 was approximately 1,570 Ci per day and represented a 31% increase compared to 1966. However, the total amount of tritium oxide released was similar to the 1986 value. Tritium oxide comprised cpproximately 44% of the atmospheric tritium released in 1987.

5 The maximum calculated dose to an individual at the site boundary from an accidental release of 172,000 Ci of tritium in July w8s 0.02 mrem (0.0002 mSv).

E After an accidental release of 1 Ci of "7Cs and 33 mci of *Cs to the atmosphere from H Aren in November, the maximum concentration of 0.79 pCl/m' at the plant boundary was 0.2% of the DCG for O'Cs.

E Results of TLD gamma measurements and analysis of soil, vegetr. tion, and fish samples l

from the Savannah River swamp were within ranges observed in previous years.

{

E Water from offsite Creek Plantation wells had radioactivity levels below EPA drinking water standards and were well within ranges observed for other drinking water wells.

E A!pha concentrations in water intake from the intake canals to the Beaufort-Jasper and Port Wentworth water treatment plants ranged from less than detectable to 4.5 pCil, lower than the drinking water standard of 15 pCl/L.

E Concentrations of pesticides, herbicides, and polychlorinated biphenyls analyzed in river and stream water and sediments were less than the minimum detectable concentrations, i

except for the herbicide dicamba in Four Mile Creek at Road A. The elevated concentra-tions appear to be contributed to the river by upriver industrial operations since dicamba is not used at SRP.

E in 1987, there were 145 minor spills reported to the spill coordinator, but none were reportable under CERCLA.

i 9

j Methods for Calculating Offsite Radiation Doses

SUMMARY

-The methodology for calculating radiation doses to the population surrounding the SRP site is desenbed. Radiation dose terms, including dose commitment, population dose commitment, organ specific dose factors, and effective dose equivalent are detined, and applicable dose standards are given. The relative effects of the two chemical forms of tltium released to the ctmosphere from SRP operations are calculated separately in this report. Finally, the mathematical models used for calculating the SRP offsite doses are described. These radiation transport and exposure pathway models are necessary because l

conventional monitoring methods do not detect the very low concentrations of radioactive materlats dispersed in the atmosphere once they are released from SRP. These models are l

Implemented at SRP in three different computer programs: MAXIGASP, which calculates j

dose to off site individuals from atmospheric releases; POPGASP, which calculates popula-I tion doses from atmospheric releases: and LADTAP, which calculates doses to offsite individuals arid to the population f rom liquid releases.

This chapter discusses radiation dose terminology

[NCRP87al. Of this total dose, apfroximately 95 and describes how the ofTsite doses presented in mrem (0.95 mSv) is from natural radiation from Chapters 2 and 3 (and su mmarized in the Executive cosmic and terrestrial sources, and from naturally Summary) were calculated.

occurring radionuclides that have been taken into the human body; approximeely 200 mrem (2.00 DEFINITION OF ltADIATION DOSE mSv)is from the inhalation of natural radon gas in C051311T5fENT homes [NCRP87al. hiany indidduals also receive additional exposures from medical examinations or As used in this report, the term dose noriaally means treatments.

"efTective dose equivalent," as defined by the Inter-national Commission on Radiological Protection Population dose commitment is the sum ofindivid-

[lCRP77, ICRP79] and discussed in more detail fur-ual dose commitments in a population group and is ther in this chapter. The term dose commitment, as expressed in units of person-rem (person-sievert).

it is applied to an individual, means "committed For example,if each person in a population of 1,000 efTective dose equivalent," Sch is a measure of the receives a dose commitment of 1 rem (0.01 Sv), the amount of radiation dose received by the individual population dose co mmitmen t would be 1,000 person-over a lifetime as a result ofexposure to all radiation rem (10 person Sv).

pathways during the year being considered. In this report, the individual's lifeti me i s assumed to extend In this report, ofTsite doses that are given for SRP 50 years beyond the time of exposure.

releases of radicactive materials to the environ ment are for the individuals and population groups who The dose commitment to an individual is usually receive the maximum calculated dose commit-expressed in units of millirem (abbreviated "mrem")

ments. Table 9-1 in Vol.11 shows the demographic %

or millisievert (abbreviated "mSv") (1 mrem =

data used te calculate the doses for populations 1/1000 rem; 1 mSv = 1/1000 Sv; 1 Sv = 100 rem). To within an 80-km radius of the SRP and for pcpula-put these units in perspective, note that an individ-tions served by the Cherokee Ilill water treatment ual in the Central Savannah River Area (CSRA) plant at Port Wentworth,GA/near Savannah), and receives an average annual natural radiation dose of by the Beaufort-Jasper water treatment plant (near about 295 mrem (2.95 mSv) from natural radiation Beaufort, SC).

r 94 SAVANNAH RIVER PLANT - Environmental Report for 1987 l

Table 91. DOE Revised Interim Radiation Dose Limits All Pathways. The effective dose equivalent for any member of the public from all routine DOE operations * (natural background and medical exposures excluded) shall not exceed the values given below:

Effective dose equivalent

mrem / year (mSv/ year)

Occasional annual exposures 600 (5)

Prolonged period of exposure' 100 (1)

No individual organ shall receive a committed dose equivalent of 5 rem / year (50 mSv/ year) or greater.

Air Pathway Only (Limits of 40 CFR 61, Subpart H)

Dose equivalent mremtear (mSv/ year)

Whole body doso 25 (0.25)

Any organ 75 (0.75)

' Routine DOE operations" means normal planned operations and does not include additional planned or unplanned releases.

EITective dose equivalent is expressed in rem (or mrem) with the corresponding value in Sv(or mSv)in parentheses.

For the purpose of these standards, a prolonged exrosure is one that lasts, or is predicted to last, longer than 5 years.

The individual and population dose commitments limits for the atmospherie pathways contained in 40 for 1987 SRP releases, calculated by the methods CFR 61, Subpart 11 [ EPA 85), are given in Table described in this chapter, are compared with the 91 above.

average annual dose commitments from natural and medical sources in Table ES-2 in the Executive EPA drinking water standards which apply at i

Summary, downriver water treatment plants are based on an annual whole body dose of 4 mrem (0.04 mSv) from the annual consumption of two liters of water per APPLICABLE DOSE STANDARDS day [ EPA 75]. SRP dose estimates are based on similar criteria and can be compared with the EPA i

The DOE radiation standards for the protection of dose standard.

the public in the vicinity of the SRP are given in l

Order DOE 5480.1A. These standards are based on INTERNAL DOSE FACTORS recommendations of the International Commission s

on Radiological Protection (ICRP) and the National Organ Specific Dose Factors Council on Radiation Protection and Measurements (NCRP).

The internal radiation dose estimates presented in i

this report are ultimately derived from a set of In 1985, a draR DOE cider was issued that con-internal organ dose factors, which are based on the tained revised interim sumdards incorporating the methodology developed by the ICRP [lCRP79] and recommendations and dose models contained in have been calculated foi intake by inhalation and l

ICRP Publications 26 and 30 [ICRP77, ICRP79].

ingestion, for those racionuclides of interest in (The previous standards had been based on ICRP environ mental dosimet ry, and for approximately 20 j

Publications 2 and 10 [ICRP59, ICRP681.) These organs of the body. Each factor relates the intake of

~

revised interim standards, which also include EPA a unit quantity ofa radionuclide to the dose received i

I

O 0,Jtethods for Calculating Offsite Radiation Doses 95 by an organ during the 50 years following the la take.

RELATIVE EFFECTS OF DIFFERENT Their units typically are mrem /pCi(mSv/Bq). Multi-CHEMICAL FORMS OF TRITIUM IN plication of the dose factor by the number of pCi(Bq)

THE ATMOSPHERE of th e radionuclide tak en into th e body gives the dose to the organ in mrem (mSv).

Tritium released to the atmosphere from SRP opera-tions is primarily in two chemical forms: tritium Effective Dose Equivalent oxide (tritiated water vapor: TilO, T,0) and elemen-tal tritium (HT or T,). The effective dose equivalent Almost every intake of radioactive material into the factors for exposure to tritium in air differ by four human body involves the irradiation of more than orders ormagnitude for the two chemical forms; also, one organ or tissue, usually at different rates, and the two forms behave differently in the environ-the sensitivities of these organs or tissues to radia-ment. Therefore, releases of tritium to the atmos-tion differ from one another. It wa s to account for the phere must be identified by chemical form and the differing dose rates and radiosensitivities that the doses from the two chemical forms calculated ICRP adopted the concept of efTective dose equiva-separately.

Icnt. In calculating the effective dose equivalent, the dose to each organ or tissue is multiplied by a The dose calculations must also consider the differ-weighting factor, and the resulting products are ent ways in which tritium is biologically assimilated summed. Each weighting factor represents the ratio by the body. Tritium oxide is readily absorbed by the of the somatic and genetic risk resulting from the body when tritiated water vapor is inhaled or when irradiation of a specific organ or tissue to the total tritium oxide is ingested in drinking water or in food.

risk that would result from the uniform irradiation An individual exposed to airborne tritiated water of the whole body. Thus, efTective dose equivalent vapor normally absorbs about one-half as much trit-accounts for nonuniform irradiation of the body and ium through the skin as by inhalation [lCRP78);

also provides a common basis for comparing and thus the efrective dose equivalent factor correspond.

combining (adding) the doses from different inter-ing to intake by inhalation is increased by 50% to nally deposited radionuclides (which may cause account for the incremental uptake of tritium oxide different distributions of doses to difTerent organs) through the skin. Tritium oxide assimilated by the and the doses from external sources of radiation, body is assumed to be eliminated at the same rate as body water.

The organ specific internal dose factors are com-bined, by the process outlined above,into factors for Elemental tritium, on the other hand, is not effi-effective dose equivalent. Such a factor represents ciently assimilated by the human body. Of the ele-effective dose equivalent for 50 years fallowing the mental tritium gas inhaled, only about 0.004% is intake of a unit quantity of a radionuelide. It is converted to the oxide and retained as free water specific to the mode ofintake (inhalation or inges-

[NCRP79). The need for limiting exposure to ele-tion) and the radionuclide taken into the body; it is mental tritium in air is governed by the dose to the not specific to a particular organ or tissue, because lung as the airborne IIT gas passes through.

it represents a risk weighted average of the doses to all organs or tissues irradiated by the intake. Here-In this report, the releases of tritium to the atmos-after, unless a statement to the contrary is made, the phere are identified by chemical form.

term internal dose factor will refer to a 50-year committed effective dose equivalent factor.

CALCULATIONAL MODELS Because the current ICRP methodology is relatively new, only internal dose factors for adults are avail-With few exceptions, most of the radioactive materi-able at present. Age specific dose factors for infants als released from the SRP are of such low concentra-and edelescents probably will not become available tior,s that when dispersed in the environment they for severalyears. As an interi n p ocedure,the doses are not detectable by conventional monitoring pro-for all age groups are calculated with the adult dose cedures.Therefore, radiation doses to offsite popula-factors. But age specific intake rates of food and tions are calculated with mathematical models that water have been used in the dose calculations.

use known transport mechanisms for atmospheric These intake rates are shown in TaHes 9 2and9 3 and liquid releases and known major pathways of of Vol. II.

exposure to man. Environmental measurements of

96 SAVANNAH RIVER PLANT - Environmental Report for 1987 Dagt h m The Environmental Protection Agenty(EPA)requirestheuse orthe CAAC computer code (Clean Air Act oepoem Code, formerly AIRDOS. EPA) to i g calculate offsite doses from existing mna and proposed facilities in order to o

demonstrate compliance with the A,

_._e, National Emission Standards for llazardous Air Pollutants (NE-d Depo e m oaa o SIIAP). At SRP, the CAAC dose es-O M

5

timates are computed to show

%w 6

a NESIIAP compliance, but they are

$7 not included among the offsite dose ir estimates prepared for this report.

if The primary reason fornotadopting Inh

n m Anants

--en the CAAC methodologyisib eonser-vative approach to calculating doses from tritium oxide in food. The CAAC modelassumes that airborne i

tritium oxide at a given location is diluted with the atmospheric mois-ture, for which a generic specific Fig.D-1. Simplified pathways between radioactive materials humidity of 8 g H,0/m* is used by released to the atmosphere and man the code. It makes no provision for user input of a specific humidity tritium oxide that is released from production areas value appropriate for the particular site and season.

in small quantities are used to verify atmospheric Because of this parameter value, CAAC doses are dispersion in the transport models [hin84].

believed to be substantial overestimates for the humid SRP area. The h!AXIGASP and POPGASP The models used for calculating the SRP offsite codes incorporate a specific humidity parameter of doses are radiation transport and dose models devel-11 g H,O/m*, which was determined by a review of oped for the nuclear industry [USNRC71] to assess weather bureau records for Augusta, GA. Another the efreets of operations of licensed commercial conservative assumption of the CAAC methodology nuclear facilities. The models are implemented at is that the water content of foods reaches an equilib-SRP in the following computer programs:

rium content of tritium equal to the tritium content a m 8phric moisture, u hiAXIGASP: calculates maximum and aver-age doses to ofTsite individuals from atmos-Afodeling the Dispersion of Radioactive m

0 caleulates population doses from cleases to the Atmosphem atmospheric releases.

u LADTAP: calculates maximum and average Radioactive materials released to the atmosphere doses to ofTsite individuals and to the popula.

generally become involved in a complex series of tion from hquid releases, physical, ch emical, and biological processes. Some of these processes involve dilution, while others in.

MAXIGASP and POPGASP are SRL modified ver-volve physical or biological reconcentration, fol-sions of the Nuclear Regulatory Commission (NRC) lowed by transfer through various pathways to man, i

program called GASPAR The modifications are Figure 91 at the top of this page gives a simplified j

those needed to meet the requirements for input of representation of some of the pathways followed by l

specific SRP physical and biological data. The basic radioactive materials that are released to the atmos-calculations in the GASPAR program are not modi-phere and eventually reach man.

fled. LADTAP is an unmodified version of the NRC i

program of the same name. (For details on these Meteorological Data Hase. The transport of ra-environmental models and computer programs, see dioactive materials from SRP by the atmosphere is references [USNRC71), [Ec80], and [ sis 0].)

calculated on the basis of meteorological conditions l

i

9. Methods for Calculating Offsite Radiation Doses 97 measured continuously at seven onsite meteorologi.

The intakes of radioactivity by ofTsite populations cal towers and at a 1,200-ft television transmitting are emverted to dose commitment by use of the tower that is 30 km (18.8 miles) northwest of the geo-ICRP internal effective dose equivalent factors, metric center of the SRP. For this report, meteoro.

which as described previously, provide estimates of

%gical dispersion and deposition were calculated a 50 year dose commitment for intake of a unit from meteorological measurements made over a quantity of radioactivity. The term environmental five year period (1982-1986) collected at a meteoro.

dose commitment refers to population dose that is logical tower located near the center of the SRP site calculated to account for the persistence in t' e (II. Separations Area). (There meteorological data environment ofsome radioactive materials and thus are presented in Table 9-4 of Vol.11.)

for continued human exposure to external and inter-nal sources ofradiation that are due to the release or The meteorological measurements, which are ex.

operation under study. The calculated population pressed in terms of frequencies of wind speed, direc-doses in this report include an estimate of environ-tion, and atmospheric stability, are used to calculate mental dose commitment for a 100 year period fol.

the dispersive characteristics of the atmosphere, lowing the release of radioactivity.

l These dispersive characteristics are calculated by methods used in the nuclear industry [USNRC73] ts The Weather Information and Display (WIND) sys.

implemented in the computer program called tem is used to calculate offsite doses resulting from XOQD0Q [Sa77]. As noted above, the calculated unexpected releases from SRP. The assimilated (or dispersion is verified by envi-3,,, c y,,3,,

ronmental measurements of

,,3.

tritium oxide (Ma84]. Also, wreaxs measured annual average concentrat,ons of tritium ox-nets i

ide in the atmosphere are mos mars ->

compared with concentra.

SOL o

tions calculated with 3,3,3 XOQD0Q and are published sco m rs e

s, m,,,,,

9 ann tally in this report (see

,y,,,c, o, Chapter 2).

caou.%o 4

m v

~'-*

Dose Calculations for At-IN'A5

(

ms mospheric Releases. The UA E annual average concentra-

"'je%'."

u tion and deposition factors calculated with the XOQD0Q program, together with the measured annual releases of radioactivity to m3 the atmosphere, are used in t

nwis e

the MAXIGASP and POP-GASP prograirs, along with data on population distribu-y tion and production data for vegetable crops, milk, and meat,to calculate theintakes y

of radioactivity and exposure t,,,o l

to external radiation sources E was J

by offsite populations. The i

intakes are based on inhala-

,a sy m I

tion rates and consumption rates for food and water, as shown in Tables 91,9 2,9 5, Fig.9 2 Simplified pathways between radioactive materials re-and 9-6 of Vol. II, leased to the ground or to surface waters and man A

_=

t 98 SAVANNAH RIVER PLANT - Environmental Report for 1987 I

internal) dose estimates use the ICRP-30 50-year portant exposure pathways followed by radioactive dose commitment factors based on an active adult's materials released to liquid efiluents and eventually breathing rate. The models in the WIND system reachi;% man. In previous years, dose calculations which provide these individual dose estimates are for the irrigation water pathway were not included, PUFF /PLUh!E and 2DPUF. External doses from a because no use of river water for irrigation down-plume or pufi emitting gamma radiation are also river from SRP is known. However, because irriga.

calculated by PUFF /PLUh!E, tion along the river by a small farming operation is a possibility, potential doses via this pathway were 5fodeling the Dilution and Transport of calculated for 1987.

Endloactivity Released to Surrounding i

Streams Flow Rate Data. Dilution of radioactive materials in the river is based on continuous now rate meas-Radioactive materials released to SRP streams flow urements made attheSRP site. The average river to the Savannah River, and although many of the flow rate in 1987 was about 10,328 fWsee and radionuclides are measurable at the point ofrelease, represents 146% of the 1986 flow rate of 7,070 they are below the minimum detectable conc +ntra-fWsec. The flow rate varies annually, depending tions after dilution with river water. Only tritium on th e amount ofrainfallin the river watershed area oxide and trace amounts of *Sr and *Cs are rou-and the quantity of water released by Thurmond tinely detected in the river. Thus, to account for the Lake Dam (formerly Clarks Hill Dam).

offsite deses from all releases to the streams, it is necessary to employ an analytical model.

Dose Calculations for Stream Releases. Aver.

age river flow rates and measured annual releases of The radioactive materials released into the streams, radioactivity to the river are used in the LADTAP like those released to the atmosphere, become in.

program, along with data for population, sports and 1

volved in a complex series ofphysical, chemical, and commercial fish harvest [TuS3], community water biological processes. Some of these processes involve consumption, and recreational use of the river dilution, while others involve physical or biological

[Tu83b], to calculate offsite dose commitments.

reconcentration, followed by transfer through vari-Af any of the data used in these calculations, as well f

ous pathways to man Fig. 9 2 on p. 97 [ICRP65]is as human consumption rates for water and fish, are 4

a simplified representation of some of the more im-shown in Tables 91,9-3,9 5,9 6, and 9-7 of Vol. II.

i r

1 i

i 4

i 1

l

9. Methods for Calculating Offsite Radiation Doses 99 1987 HIGHLIGHTS E Internal dose factors for adults, which are the only intemal dose factors available at present that incorporate the new ICRP methodology, are used for calculating doses for all age groups. However, age-specific intake rates of food and water have been used in the dose calculations.

E NRC computer programs developed for the nuclear industry are used for calculating offsite doses to the public.

E Meteorological conditions are measured continuously at seven onsite meteorological towers ard at a 1,200 ft television transmitting tower located 30 km (18.8 miles) northwest of the geometric center of SRP.

5 The average river flow rate in 196/ of 10,328 ft'/sec was a rnore typical flow and represents a 46% increase in the flow rate since 1986. The 1986 flow was smaller due to reduced rainfall.

10 Sample Collection and Analytical Procedures SUMM ARY - Procedures for the collection, preparation, and analysis of environmental samples for both radioactive and nonradioactive constituents are described in detail.

The instruments and detector types for determining radionuclide concentrations in envi-ronmental samples, as well as the routine counting geometries for gamma spectrome-try, are outlined. For radiological analysis, air, streams, the Savannah River, the seep-age basins, groundwater, milk, drinking water, food, ralnwater, wildlif e, soils, sediments, and vegetation are sampled in clearly outlined procedures. Thermoluminescent dosime-ters are used to measure external radiation. For nonradiological analysis, four ambient air monitoring stations on the site measure sulfur dioxide, oxides of nitrogen, ozone, and total suspended particulates, in addition, water from streams and rivers, groundwater and drinking water, and soils and sediment are analyzed for physical properties such as alkalinity, conductivity, and temperature, and for nonradioactive constituents such as metals, pesticides, and volatile organics.

INTRODUCTION Geometry #1 Used for analyses of samples physically similar to This section describes sample collection and prepa-Dat 3 in.-dia air filters. All air filters are analyzed, ration procedures and the analytical techniques either individually or by collective composite, using used to determine concentrations of radionuclides this geometry All analyses of this type are per-in environmental samples. Listed below are formed on systems using SPECTRAN F software.

instruments and detector types used for these measurements:

Geometry #2 Used for analyses of samples physically similar to E Gas. flow proportional counters for alpha and 200 mL of water in a "standard" 500 mL 3.25-in. dia beta emitters polyethylene bottle. Air sample charcoal cartridges E Liquid scintillation counters (LSC) for low.

are also routinely analyzed in this geometry.

energy beta emitters E Semiconductor alpha spectrometers for isotope-Geometry #3 specific quantification of alpha emitters Used for analyses of samples physically similar to E liigh. purity germanium (IIPGe) detectors for 1 L of water in a "standard" 1 L polyethylene Mar-I high. resolution gamma quantification inelli beaker. Relatively n ew for SRP, this configura-E Sodium iodide [Nal(Tl)] detector for high-tion is becomirig the standard analysis geometry for efliciency detection of gamma emittars liquid environmental samples having low activities.

i Specific countiny geometrics or gamma spectrome-Geometry #5 try of ditTerent types of samples are required for Used for analyses of samples physically similar to accurate analysis. Standardized sources of radioac-500 mL of water in a "standard" 500-mL 3.25.in.-dia tivity with known gamma field characteristics are polyethylene bottle. This geometry was used for all used to calibrate the detection instruments; the direct mount liquid sample analyses prior to 1986.

j counting geometries correspond to the sizes and shapts of the standardized sources.

As new 11PGe detector systems are placed in service, many samples such as stream and river water, food.

A brief description of the routine "standard

count-stutTs, and groundwater that were analyzed in past ing geometries for gamma spectrometry follows:

years using only Geometry #5 (500 mL) will now use

102 SAVANNAH RIVER PLANT - Environmental Report for 1987 Geometry #3 (1000 mL). One such system, referred Alpha and beta en.itting radionuelides are deter-to as llPGe Detector #3, was used extensively in mined simultaneously by a direct gross count ofin-1987. At least one additional new system, IIPGe dividual particulate filters using a gas How propor-Detector #4, will be used in a similar conflguration tional counter. The weekly filters are then compos-in 1988.

ited monthly by location group (700 A, Burial Ground North, Burial Ground South,200-F,200 II, The following tables in Volume 11 present sample plant perimeter,25 mile radius, and 100-mile ra-media and counting data:

dius) and counted for gamma emitters on a high-purity germanium (IIPGe) detector. Afbir gamma Table 10-1 Sample Media Data counting, each filter in the composite groups is cut in Table 10-2 Gas Flow Proportional Counting Data half; one halfis used for strontium analysis and the Table 10-3 Liquid Scintillation Counting Data other for plutonium analysis.

Table 10-4 Alpha Spectrometer Counting Data Strontium 89,90 are leached from the filters with Additional tables in Volume 11 provide lower limits 8N (normal) nitric acid, precipitated with fuming of detection (LLD) for llPGe detectors and for se-nitric acid, scavenged with ferric hydroxide, precipi-lected sample types. Those tables are referenced in tated as the carbonate and transferred to a stainless Chapter 11.

steel planchet (holder) for counting on a gas.0ow proportional counter.

ItADIOLOGICAL PItOCEDUltES For N"Pu analysis, each filter composite is dry Air ashed and leached with acid. The solution is evapo-rated to dryness, dicolved in 7.2N nitric acid, and Particulate airborne radioactivity is sampled con-passed through an anion exchange resin. The ex-tinuously at each monitoring station by drawing air tracted plutonium is eluted from the resin column through a 2 in. dia. high-elliciency paper filter at with an ammonium iodide-hydrochloric acid solu-about 70 I/ min (2.5 fWmin). An auxiliary running tion, which is then evaporated to dryness. The resi-time meter and air flow meter record the volume of due is redissolved in a sulfate medium. Any pluto-air that passes through the filter and the total nium present in the sample is electrodeposited on a sampling time. Sample filters are collected weekly stainless steel disk and counted on a silicon surface from 35 monitoring stations for analyses.

barrier detector.

Samples for gaseous radioiodine are col-

-.. m a m W lected on cartridges containing 5% trieth-g u_ ~ ~ ~ w,

ylene diamine-(TEDA) impregnated char-coal. The charcoal cart ridges, located down.

line from the particulate filters, are col-2m, lected weekly. lodine-131 is measured by a

,45,,

direct count of the charcoal cartridge on an

-m IIPGe detector.

[. N I g,'"r,

,7-xise 1

Moisture is collected from the atmosphere

}_,

~

.a for determination of tritium oxide by draw-m-

'(y; ing air through a silica gel column at a

'm

"^

22 continuous rate of 150 ml/ min (0.005 fVmin).The column eontains non indicating i

silica gel and is backed up by an in line column ofindicating silica gel. The indicat-

,Gg ing silica gel changes color if moisture satu-rates the primary silica gel column during

~' -

'~'

the sampling period. These samples are

)

collected twice a month for analyses.

Air monitoring station

i

10. Sample Collection and Analytical Procedures 103 The non indicating silica gel is distilled using low heat to remove free water. The distillate, represent-

] TN ing the moisture content in the air sampled is sus-B

'g-pended in a liquid scintillation cocktail.The concen-

.,./

tration of tritium oxide in the moisture is deter-tration of tritium oxide in the air is calculated from 4'

mined by liquid scintillation counting. The concen-1

,f the tritium oxide in the atmospheric moisture and

' I the absolute humidity (moisture in the air) for the volume of air sampled.

s External Itadiation s

% p (g.. "

Thermoluminescent dosimeters (TLDs) are used to g

g

.1 measure external radiation. The SRP-designed TLD, which was used for many years, contains a calcium Ducride dysprosium (CaF) crystal posi-tioned behind a silver alter to measure dose from photons with energies above 100 kev. Energies below 100 kev are measured with lithium Ouoride w

~*

(LiF) TLDs positioned behind a paper alter. During 1986, a special study was conducted to compare the SRP-designed TLD with a new Panasonic 801 TLD.

Typteal TLD station The Panasonic dosimeter, which contains two cal-gla s wheel suspended on two pontoon s and anchored cium sulfate (CaSO) crystals and two lithium bo-in the stream. The wheel is turned by the stream rate (Li 8.Op crystals, was chosen for several rea-Dow. The sample is collected in a small cup or cups 2

sons. The more efTicient Panasonic system requires attached to the paddle. The cup containing the less labor, provides improved quality assurance, sample is emptied into a trough attached to the and is automated. Dosimeters of both types were sampler. The sample Dows e gravity from the exposed at selected Geld locations to verify that trough through a connecting tube into a poly-variable environmental conditions (rain, tempera-ethylene jug attached to the sampler. Samples are ture, humidity, and sunshine) would not adversely collected weekly.

affect the results of the Panasonic dosimeters.The Pana sonie test results were favorable. Fig.10 1, Vol.

Alpha and beta-emitting radionuclides are meas.

II, shows the relationship between the SRP and ured by a direct count of the residue remaining from Panasonic TLD measurements.

evaporation of a one liter water sample.The sample residue is transferred to a 2 in. stainless steel plan-SRP and Panasonic TLDs were used at sample chet. The planchet is named to remove volatile ma-locations during 1987 with a complete conversion to terial before being counted on a gas How propor-the Panasonic TLDs occurring by the fourth quar-tional counter. Gamma-emitting radionuclides are ter. The TLDs are annealed, placed in holders that determined by direct count of either a 500-mL or are then scaled in plastic bags, and mounted on a 1,000 mL aliquot of the sample on an llPGe stands one meter above the ground. They are col-

detector, lected quarterly and read to determine gamma radiation absorbed by the crystals. Calibration Alpha emitting radionuclides are extracted from a TLDs accompany each set of Geld TLDs to assure one liter sample with triisooctylamine (TIOA) in i

accurate measurements.

xylene. Uranium and plutonium are selectively stripped frrm the TIOA organic layer with 0.1N Strea ms hydrochloric acid, and the solution is evaporated to dryness. The residue is dissolved in SN nitric acid Plant streams are sampled continuously by paddle-and transferred to a stainless steel planchet for wheel samplers. Each sampler consists of a Plexi-counting on a gas Dow proportional counter.

I

- O

104 SAVANNAH RIVER PLANT - Environmental Report for 1987 Alpha and beta emitting radionuclides are measured by direct count of the residue remaining from evaporation of a one liter 4

=

sample aliquot on a planchet. The planchet is Gamed to remove volatile material before being counted on a gas Cow proportional counter.

fs g

Gamma emitting radionuclides are mens-g ured by passing approxi ~ately 20 liters of

~

the sample through a cation anion ion ex-s change colu mn to concentrate radionuclides present and thereby achieve increased ana-lytical sensitivity. The column is counted on 3

.w an llPGe detector. Radionuelides are then

.J > g / *C -

E;k

,3 eluted from the resin column with 3N nitric eL N

Y%,,-

acid, followed by 1 tN nitric acid for subse-quent analyses.

Paddlewbeel nampler Plutonium 238,239 are determm.ed from an Tritium is measured in a 3.0 mL undistilled aliquot aliquot of the cluate from the ion exchange column.

of the sample by liquid scintillation counting.

The analytical procedure is the same as th at used for air Glters.

For "*'Sr analysis, an aliquot of sample is evapo-rated to dryness. The sample is precipitated with Strontium 90 is recovered from an aliquot of the fuming nitric acid, scavenged with ferric hydroxide, column cluate, and the same procedure is used as precipitated as the carbonate and transferred to a that described for stream samples. Strontium 89,90 stainless steel planchet for counting on a gas now concentrations in the cluate are determined by the proportional counter.

same procedure used for stream samples.

For Sr analysis, an aliquot of the sample is evapo-Tritium concentration is determined by liquid scin-rated to dryness and the residue dissolved in 0.0SN tillation countingofa3.75 mLaliquo'.ofthedistilled hydrochloric acid. Yttrium 90 is stripped from the sam ple.

strontium using di 2 ethylhexyl phosphoric acid (llDEllP) in toluene. Equilibrium of *>Y is ap.

Seepage liasins pr. ached over a 15 day period, and then the short-lived 'T daughter is stripped once again. The yt-One liter grab samples are generally collected quar-trium is transferred to a stainless steel planchet and terly from the weepage basins. Analytical procedures counted in a gas Cow proportional counter. The are the same as for other surface water samples.

amount of Sr is calculated by relating the *T buildup to the original *Sr concentration.

Groundwater Cesium is selectively precipitated from the sample Most groundwater wells are sampled quarterly, by phosphotungstic acid. The precipitate is slurried Samples are removed from each well either by in ammonium hydroxide and transferred to a plan.

pumping a minimum of four well volumes before chet for countingin a gas Cow proportional counter.

collecting the samplc, or by lowering a weighted one-liter bailer into the well to collect the sample. Each Savannah Itiver dip sampled wellis equipped with a stainless steel bailer that remains at the well to prevent cross-The Savannah Itiver is sampled continuously by con tamination. The normal sa mple volume collected paddlewheel samplers equipped w;th 26 liter poly-for analysis is approximately two liters (or what can ethylene collection containers. Samples are col-be sampled if the water in the wellis less than two lected weekly.

liters).

I

10. Sample Collection and Analytical Procedures 105 Each monitoring well has a gravel packing in the monitoralpha andbeta-emittingradiont.ci desand screen zone which is beneath a bentonite seal and tritium. Some onplant samples are collected cement grout to the surface. The grout discourages monthly, while others are collected quarterly, leakage of shallow groundwater into the well. The OfTplant samples are collected semi annually.

top of the wellis either capped or sealed to prevent Samples are collected from faucets or drinking foun-introducing atmospheric water into the sauple, tain s.

All drinking water samples are analyzed annually for"Sr. Analytical procedures for drinking The analytical techniques are the same as described water are the same as those used for other water for stream and river sarnples, samples.

Milk Wildlife Fresh raw milk is collected from local dairies every Fish are caught in traps or by hook and line. Whole two weeks and analyzed for iodine, cesium, and trit.

fish are analyzed for gamma-emitting radionuclides ium Once per quarter the samples are also analyzed on a 9 x 9 in. Nal well detector or on an IIPGe for "Sr. Iodine 131 and *"'Cs concentrations are

detector, determined by direct count of a oneliter aliquot using an llPGe detector. Strontium and yttrium are Deer and hogs are monitored at the hunt site for scavenged from the milk by a cation exchange resin

'"Cs using 2 x 2 in. Nal detectors. The detectors are and put into solution in the chloride form. Using the calibrated so that '"Cs concentrations in aesh may same extraction described earlier for stream and be derived from the field measurements. Accuracy of river samples, "Sr is determined with r gas-flow the calibrations is verified by laboratory analyses of proportional counter. To determine tritium oxide approximately 5--10% of the deer. Laboratory concentration, the milk is distilled to reduce quench-samples are counted en an IIPGe detector. Flesh ing interferences and a 3.75 mL aliquot used for samples are collected randomly from deer during liquid scintillation counting, each hunt and analyzed for "Sr and tritium by the same procedures described earlier for other media.

Food Muscle tissue and thyroids are randomly collected from deer during each hunt and analyzed for "Cs 1

Local foods are obtained from farms located within and ml on either an llPGe or Nal detector.

a 25-mile radius of SRP. With the exception of grains, all foods are prepared as though for human consumption; i.e., peelings, seeds, and other ined-f ible parts are removed. Wheat, containing the whole grains only, and oats, containing both grains and husks, are processed unwashed. ARer removal of a portion of the original sample for tritium analysis, 2

the sample is dried and ashed. The residue is dis-solved in a }.ydrochloric acid solution, s

y,1 y h Gamma emitting radionuclides are determined by direct count on an llPGe detector. Plutonium-

,y..- h. N 238,239 are determined by the same procedure as Wg h

'w described for other media. Strontium 90 analysis of Ah a

the prepared solution is performed with the same 4

procedure used for water. Tritium is measured in f

(.

(

the free water obtained by freeze-drying a portion of J~

e Q

the original sample. The water is counted in a liquid

.V scintillation counter, pi,

*}y.

a f_..

Drinking Water p

a e

Drinking water is collected at onplant sampling Fish caught for analysis locations and in commumties surrounding SItP to

106 SAVANNAH RIVER PLANT - Environmental Report for 1987 Fu rbearing animals, in cluding racoon s, oppossums, methods. No correlation was seen between the re-foxes, and beavers, are trapped. All animals except sults obtained from the "wet

or "dry" pans and the beavers are counted whole for gamma emitting ra-routine rainfall collectior, pans. Given the qualita-dionuclides in a 9 x 9 in. Nal well detector or on an tive nature of deposition and rainfall analyses, it ilPGe detector, llcavers are monitored in the Geld was concluded that no correction factor should be with a portable Nal detector.

applied to routine rainfall analysis data as a result of this study.

Ducks are trappe.1 and counted whole for gamma-emitting radionuelides on a 9 x 0.in. Nal well detec.

Soil and Sediment tor or on an IIPGe detector.

At each sampling location,10 soil cores,8 cm deep, are taken in a straight line 30 cm apart. Soil cores liainwater are composited by location and analyzed for Sr,

Pu, and gamma emitting radionuclides. Sedi-lladioactivity deposited in rainwatei is determined ment collection techniques for streams and rivers from continuous samples that are collected for are designed to obtain samples from the top 8 cm of analysis every month. Itainwater is collected in sediment in areas where One sediment has accumu-metal pans that are 2 f1 square. At stations equipped lated.Therefore, the samples are not representative with ion exchange columns, the water passes of the entire stream bed.

through the column and into a polyethylenejug. At stations not equipped with ion exchange columns, Soil and sediment samples are dried, sieved, pu!ver-the water is simply collected in the pan and drained ized, and blended before unrlysis. For determina-directly into the jug.

tion ofgamma-emitting radionuclides, an aliquot of 6e pulverized soil is placed in a 500 mL plastic The ion exchange columns are counted directly for bottle and counted on an llPGe detector. Analysis gamma emitting radionuelides on an IIPGe de ec-of the soil and sediment for *Pu follows the same t

tor. The columns are then elated for alpha, beta, plu-procedure as described earlier for other media, tonium, and strontium determinations and ana-lyzed by the same procedures described earlier for For Sr, a portion of other media. Tritium concentrations are deter-the pulverired soil mined by analysis of the rainwater collected in the is leached with IN 3

jugs.

ammonium acetate

/y h,,

a and the solution The amount of each radionuclide deposited at a evaporated to dry-W station during the year is obtained by adding all ness. The residue is values that are greater than the minimum detect-dissolved in 0 08.V i

able concentration.

hydrochlorie acid

'g and the sample g

Analytical results are not corrected for dry deposi-analyzed by the

~

tion that may have escaped from or been deposited same method used d

in collection pans during periods of dry, windy for water.

w eathe r. A st udy, utiliz ing "we t' and

dry' collection pans, was conducted to determine the efTect of dry deposition on rainwater analysis results. The "wet" Vegetation and "dry" collection pan system consisted of two pans that had a cycling cover. The cover moved over Vegetation samples

\\'

the

wet" pan during periods of dry weather and are collected on-j y over the

dry" pan during periods of precipitation.

plant and within a The data confirrned that contribution or removal of 100 mile radius of

~.

material from the

wet" pan is extremely variable SitP They are j^ y Q and unpredictable. Di0iculties w ere encountered in taken quarterly at f

comparing results because of differences in sam-some locations, g

.g pling periods, collection techniques, and analy tical annually at others.

Core sampling

=__.-

i 1

i l

10. Sample Collection and Analytical Procedures 107

)

For gross determination of alpha. ond beta emitting the D Arealaboratory. Allsamplecollection,preser-

]

radionuclides, a portion of dried and ashed vegeta-vation and analyses procedures are in a-cordance tion is dissolved in nitric acid and transferred to a with EPA approved methods. A sampling of the ana.

planchet for counting in a gas flow proportional lytical methods used is shown in Table 10-1 shown

counter, on p.108.

l Gamma emitting radionuclides are determined by Plant streams and the Savannah Itiver are sampled counting dried vegetation in a standard geometry on continuously by paddlewheel samplers for metals I

an llPGe detector. Strontium 89,90 are determined analysis. Weekly samples are collected, preserved using the same procedure as described for other according to EPA procedure, and composited media. Tritium is measured by liquid scintillation monthly. Aliquots from the three months in each counting of water obtained by freeze-drying the quarter are combined to create a quarterly com-sample.

posite, which is analyzed by atomic absorption spectroscopy.

l NONitADIOLOGICAL PltOCEDUllES Because of short EPA recommended holding times Air and restrictive preservation requirements for para-meters such as total dissolved solids and chloride, Four ambient air monitoring stations on the site composited samples are not used for non metals house instruments to monitor for sulfur dioxide analyses. Grab samples are collected for non.

(SO,), oxides of nitrogen (NO,), ozone (0 ), and total metalparameters and analyzed according to EPA 3

suspended particulates (TSP). Instrumentation procedures.

used is as follows: Four NO, analyzers, two SO,ana-l lyzers, one 0, analyzer, and five TSP samplers (one hicasurements for pli, dissolved oxygen, conduc-TSP sampler at each station and an additional co-tivity, turbidity, and temperature are made at the located sampler). Sampling and analysis are per-sampling locations.

formed in accordance with EPA requirements and SCDilEC guidelines.

Groundwater NPDES Outfall Samples Samples of groundwater are collected according to procedures that are consistent with EPA and l

Samples from SitP outfalls regulated by SCDilEC SCDilEC methods. A pump installed in each well

)

under the National Pollutant Discharge Elimina-allows adequate purging before a sample is tion System (NPDES) are collected according to collected.

1l procedures consistent with EPA and SCDilEC l

methods.

Generally, four times the volume of water standing in the wellis purged to ensure that the sample is rep-l All samples except those for fecal coli-form analyses are analyzed by offsite 2,,

laboratories The fecal coliform analyses t-g.,. g

',,4

)

are performed by the on site laboratory in

, ;g,.. y. - %

,,4

[,. m,..

D Area because these analyses must be

.,o" g%

g %(

started within six hours of sample collec-

+,,[A-%[~

ll-

'f < J pg tion. Alllaboratories analyzing NPDES I

,pe, r

4 j

samples are certified by the EPA or the appropriate state regulatory agency.

l E

l Streams and Itiver

,y 4

e Laboratory analyses, except for fecal coliform, are performed in the SitP Envi-l ronmental $1onitoring laboratory. The fecal coliform analyses are performed in l

NPDES outfall l

108 SAVANNAH RIVER PLANT - Environmental Report for 1987 Table 101. Chemical Analyses and once r twice during the year for the constitu-Methods for Stream and River Samples sis requests are made in response to a special request, analysis for priority pollutants at se-Analysis Method

lected sanitary landfill wells was performed during 1987. Also du ring 1987,in anticipation of Non Metals issuance of RCRA Part H permits for F and II-Alkalinity EPA 310.1 Area Seepage Basins, Appendix IX analyses Total Solids, Volatile Solids, were performed on samples from F-Area Basin Fixed Residue, Suspended Solids, wells. Similar analyses on Il Area Basin wells Total Dissolved Solids EPA 160 are planned for 1988.

Chemical Oxygen Demand EPA 410.2 Chloride EPA 325.3 in 1987, Envirodyne Engineers, Inc., of St, Nitrate Nitrite Nitrogen EPA 253.2 Louis, $10, a certified offsite laboratory, per.

Sulfate EPA 375.4 formed all routine analyses using EPA.

Phosphate Phosphorus EPA 365.1 appmved procedures. A representative list of Ammonia Nitrogen EPA 350.1 analyses performed and methods used is shown in Table 10 2 on the facing page.

Aluminum EPA 202.2 Drinking Water Cadmium EPA 213.2 Calcium EPA 215.1 Drinking water at SRP is supplied primarily by Chromium EPA 218.2 deep wells that draw water from the Black Copper EPA 220.2 Creek bliddendorf Formations (formerly called Iron EPA 236.2 the Tuscaloosa Aquifer).There are 27 drinking l

Lead EPA 239.2 water systems at SRP.

Slagnesium EPA 242.1 hlanganese EPA 243.2 The 16 large drinking water systems are rou-hiereury EPA 245.1 tinely sampled by the SRP Power Technology Nickel EPA 249.2 Department and analyzed for pli, residual chlo-Sodium EPA 273.1 rine, and bacteria. The smaller systems (located at plant barricades) are not routinely analyred lardness Shi3 A for these parameters. All analyses are based on SCDilEC regulations, and the sample fre-

htethods from Ethods hr Chemical Analpes o/ Water quency is based on the number of people using and Wastes, USEPA, EPA 600'4 70q20(htarch 1979);

the system. Harricade wells are exempt from and Standard Methods for the Faamunation o/ Water mub.ne analysis because they serve only a few and Wastructer,15th Edition, APHA'AWWATPCP.

people, resentative of the groundwater, EPA recommended Three systems,in which polyphosphates are used to preservatives and sample handling procedures are treat the water, are sampled and analyzed daily for used during sample collection.

PO, residuals. Turbidity is measured daily in drink-ing water from a surface water treatment plant Field measurements are made quarterly at each located in D Area.

well for pil, temperature, conductivity, and water depth. A comprehensive chemical analysis is per-Annually, drinking water is analyzed for a compre-formed on every well every two years. At least once hensive list of chemicals. Samples are taken from a year, samples are analyzed for sitspected constitu-sample locations designated by SCDilEC.

ents (e.g., sulfate in wells near coal piles). The frequency of additional sampling for a constituent Soll and Sediment depends on concentration levels in the sample and on special requests to satisfy regulations. A com-Sediment samples are collected annually at seven puter program flags results that are above specific stream locations and two Savannah River locations.

limits. Samples with flagged results are analyred These samples were analyzed for 32 pesticides,

10. Sarnple Collection ancl Analytical Proceclures 109 herbicides, and polychlorinated Table 10 2. Chemleal Analyses and biphenyls (PClls) during 1987. This 51ethods for Groundwater Samples program, in conjunction with stream and river water sampling, has been Analysis hiethod' conducted since 1976 to assess concen-trations of these materials in SRP streams and in the Savannah River.

Conductivity EPA 120.1 Arsenic and Selenium EPA 270.3 A ne litergrab sample was collected at Silver and Lead EPA 200.0 each location. The samples were (Auto Analyzer Dameless) slopped to Envirodyne Engineers, Inc.

Barium, Cadmium, Chromium, (EEI), m St. leuis,510. eel analyzed Copper, iron, Lithium, the samples using EPA methods 608 blanganese, Sodium, Nickel, and 615.

Lead, Uranium, and Zine EPA 200.7 (plasma torch)

Chloride EPA 325.3 Cyanide EPA 335.2 Fluoride EPA 340.1 hiercury EPA 245.1 Volatile Organics EPA 624.0 (gas chromatograph hlass spectrophotometer) or EPA 601.0 (gas chromatograph)

Endrin, Lindane, hiethoxychlor, and Toxaphene EPA 603 Silvex and 2,4 D EPA 615

Methods from Methais for Chemical Analysis of Water and Wastes, USEPA, EPA-600/4 79 020 (March 1979) and Methods for Organic Chemical Analysis ofMu nicipal a nd industrial Wastewa.

ter, USEPA, EPA-600/4 82-057 (July t982).

110 SAVANNAII IIIVEll PLANT - Environmental Iteport for 1987 1987 HIGHLIGHTS E The standard analysis geometry for lquid environmental samples having low activities has changed to a new geometry ut,lizing a

standard"one liter polyethylene Marinelli beaker.

E Both SRP calcium fluoride dysprosium TLDs and Panasonic 801 TLDs, which contain calcium sulfate and lithium borate crystals, were used at sample locations during 1987 with a complete conversion to the Panasonic TLDs by tl.e fourth quarter.

E in 1987 Envirodyne Engineers, Inc., a certified offsite laboratory, portormed all routine groundwater and sediment anatyses using U.S. EPA approved procedures.

E Sediment samples, collected at seven stream locations and two Savannah River locations, were analyzed for 32 pesticides, herbicides, and polychlorinated biphenyls (PCBS) during 1987.

l l

t

{

1 l

11 Data Analysis and Quality Assurance SUMM ARY -This chapter describes the lower limits of detection (LLDs) of radioactivity in i

samples gathered at SRP and reviews the 1987 quahty assurance'quahty control (OAOC) l orograms for both the radiological and the nonradiological environmental monitoring pro-

)

grams. The OC program for radiological monitoring was penormed internally and continued to focus on the cabbration of the counting instruments, source and background counts, yield deterninations of radiochemical procedures, and replicate analyses to check precision. In 1987 a "bbnd samp.e program

was added to verify the maintenance of procedural controls, and SRP successfully participated in two interlaboratory quahty assurance programs con-i ducted by the Environmental Protection Agency and the Department of Energy. In general, SRP's analyses agreed with EPA and DOE values within 20% The responsibihty for the OC programs for nonradiological monitoring was shared by SRP and several outside contractors.

The ambient air qual;ty program was conducted by Zedek Corporation, which through quar-terly aud.ts and evaluations of the monitoring stations showed that SRP's gaseous anatyzers j

and total suspended particulate samplers performed satisf actorily. The liquid effluents pro-I gram was carried out by two contractors, Environmental Testing. Inc. (ETI) and Environmental and Chemical Services (ECS), each of which maintained internal quahty control programs;in f

add. tion, ECS, the major contractor, succcssfully participated in an EPA sponsored perform-l ance evaluation. The stream and river water quakty control program included an internal review of the SRP Environmental Monitoring methods;it also included replicate sample analyses by ECS and Envirodyne Engineers, Inc. (EEI). The groundwater program consisted of intercomparisons of sample analyses performed by four contractors (eel, ECS, Enwright i

Laboratories, and Weston Analytic) plus the establishment of a OA/OC program specifically for SRP samples by the primary contractor (EEI). Reviews of all these programs showed SRP l

to be in comphance with the various OA OC requirements during 1987.

INTitODUCTION In addition to the extensive monitoring program for radioactivity, SitP conducted a large monitoring The environmental monitoring program at SitP is program for nonradioactive chemicals, metals, and one of the largest and most comprehensive in the physical properties in 1957. Samples analyzed for l'nited State s. Ex ten sive p rogra m s are conduct ed in potential pollutants included those taken from SRP both radioactive and nonradioactive monitoring. A air, liquid emuents, surface water, and groundwa-total of 177,000 analyses (59,000 radiological and ter. The nonradioactive monitoring program gener-88,000 nonradiological) were performed in 1987.

ated approximately 88,000 analyses ir.19S7.

Each year, extensive radioactive monitoringis per.

LOWElt I.lMITS OF 1)ETECTION (1.Lih) formed in a 2,000 square mile area in the immedi.

OF ltADIOACTIVITY ate vicinity of SRP and representative samples are collected from an additional 30,000-square-mile in the analysis of samples gathered in the radioac-area. In this 30,000-square-mile area, many ditTer-tive monitoring programs, the estimated minimum ent types of samples are collected routinely and ana.

detcetchle concentration (MDC) for analyses refers lyzed for radioactivity. The radioactive monitoring to the amount of radioactivity that can be detected, program generated approximately 23,500 samples at the 954 confidence level, by the radiochemical and 89,000 analyses in 1987, analytical technique in use. Within the context of

112 SAVANNAH RIVER PLANT - Environmental Report for 1987 this report, the term loactlimit o[detretion (LLD) is used interchangeably with the MDC. This statistic can be innuenced by f

j such factors as counter eDiciency, prace.

l dure yield, length of ceunt, instrument

.1 background, sample geometry, sample vol-

'~

I ume and density, radioactive decay during

)

the interval between collection and analy-sis, and the number of radionuclides pres-ent in the sample.

i In 1956, SitP standardized the algorithm through which minimum sensitivities or l

LLDs for all ofits n uclea r cou nting system s are determined in order to conform with the industry standard formula listed below INCitPIS, NUltEGS t, llPSitS0]:

Gamma analysis uting APOGEE software i

An alyses of routine sam ples (othe r th a n milk and air k8 + 20hs = 2.71 + 4.65 s, charcoal cartridget, performed on the older datec-tors) using Canbarra's SPECTItAN-P gamma spec-I w here trum analysis software are based on spectra ac-I k = 1.6 5 (957 conGdence leveD, quired over a 3,000 second count interval as

= standard deviation of the background.

opposed to the otherwise standard 5,000 second s

cot.nt. This reduced counting interval elevats s the LLD (i.e., degrades the sensitivity) associated The resulting values listed in the LLD tables (see with each analysis, and theSPECTitAN P-<lerived 1

Vol. ID contain corrections for sample aliquot, LLDs are higher than the APOGEE-derived LLDs I

chemical yield, radioactive decay (where specified),

for equivalent geome tiievanalyses. LLDs for 11PGe

)

and detector e0iciency, although the uncertair,ty in systems using SPECTilAN P software are pre-i these factors is not always propagated.

sented in Table 11-5, Vol. Il l

LLDs for gamma spectrum analyses of individual it is important to distinguish the LLDs from the environmental samples, such as streams, food-uncertainty or error statistics that accompany stutTs, and groundwater, may vary signiGeantly analysis results. The LLD is an a priori thefore the because of the geometry of the sample during count-fact) estimate of a system's minimum detection ing. Specific geometries used are presented in Chap-capability, based on knowledge of its physical per-ter 10, "Sample Collection and Analytical Proce-formance characteristics and predetermined analy-dures " LLDs for certain sample types are listed in sin parameters.

Tables 11-1,112, and 113, Vol. IL LLDs may also vary because of differences in performance charae.

The uncertainty statistic (t) places an a posteriori terinics among the three primary counting systems (after the fact) con 6dence window around an actual used: a 25% Iteversed Electrode (*n type") closed-measurement value, or a collection of values. Gener.

end coaxial llPGe (high purity Ge) detector, a 301 ally, the errors on the analytical results are lower standard ('p type") closed-end coaxial detector, and than the LLD for a particular measurement.

a 359 standard t*p type") closed end coaxial detec-i i

tor. The LLD tables quoting values derived from Many of the concentrations of radioactive materials 1

Canberra Industries' APOGEE gamma spectrum in ambient environmental samples approach zero l

analysis software are all based on counts obtained and should statistically show a distribution around j

from the midrange "309 relative eniciency" detec-rero. When an instrument background is subtracted tor. Iloth the individual eRiciency and the resolution from an environmental measurement,it is possible parameters for the speci6c detector induence the to obtain n< t values less than the M DC or LLD. It in J

minimum sensitivity of the sample analysis. Lt.Ds also possible to obtain rero and negative values

{

j for llPGe systems using APOGEE software are (values les s th a n re ro). Note t h at ga mma spect ro me-I shown in Table 114, Vol. II.

try analytical results are usually not reported as

11. Data Analysis and Quality Assurance 113 activity concentration values, but as *less than" M calibration of counting instruments values representing the 95% con 6dence level LLD.

E source and background counts for all counting systems Analytical results less than the LLD or 51DC should E yield determinations of radiochemical not necessarily be interpreted as non detectable, procedurcs Values greater than one half the LLD can be inter.

E replicate analyses to check precision preted as probably indicating a positive analyte presence. In many cases, values less than one half Tne accuracy of the radioactivity measurements is the LLD,less than the accompanying error (!) sta.

established by use of standards traceable to the tistie, or even less than zero (negative) are reported National Bureau of Standards (NBS). llistories of (except for gamma spectrometry results). This prae-the performance of the counting instruments are tice is useful in evaluating a series of data and maintained in logbooks and computer Oles, provides a better estimate of the mean by averaging negative values with the zero and positive values.

The SRP Environmental h!onitoring Laboratory This approach allows all data to be reported and is began a "blind sample" program in 1987, After an useful in identifying trends and biases and in re6n-initial evaluation period, the blind sample program ing concentration boundary values. It may also re-was incorporated as a formal part of the QC effort, sult in improved analysis sensitivity.

Blind samples consist of water or air Ollers contain-ing known radionuclide activity levels that corre-In some tables the standard deviation is not caleu spond to typical levels found in routinely analyzed lated because of the small number of sample results samples. Whenever possible, the blind samples are (designated "insufUcient data"). When "plus-or-prepared from NBS traceable material or standard-minus" accompanies an individual result, such as ized against NBS material. The data are used to the maximum (h!AX) or minimum (511N), it repre-verify that procedural controls are maintained by sents the statistical counting uncertainty or error at the laboratory, the 95% con 6dence level, which in many cases ex-ceeds the net value of the sample. h1AX and hilN In addition to the internal quality control program, refer to the greatest and smallest concentrations SRP participated in two interlaboratory quality found in a single sample collected during the year.

assurance programs during 1987. One program is conducted by the Quality Assurance Division (QAD)

The average of all values obtained for a specine of the Environmental Protection Agency. The see-location or analysis also is usually accompanied by ond is the Quality Assessment Program (QAP) con.

a plus-or minus ( ) value, designated as the stan-ducted by the Department of En ergy Environmental dard deviation of the average at the 95% confidence hieasurements Laboratory (EhlL). Under both pro-level. It serves as an indicator of the deviation of grams, a variety of samples are sent to the partici.

concentrations encountered at that location. When pating laboratories at inte rvals th rough out th e year.

the average is given for groups oflocations, the plus-Sample results and SRP's performance in the QAD j

or minus value is the measure of the range of con-and QAP programs are presented in Tables 116 i

centrations found at alllocations.

and 11-7, VolIL LLD values quoted for gross alpha and nonvolatile The 20% indicator shown in the tables is a conven-beta results generally do not include correction for ient caeasure of overall relative performance but self absorption. Other analyses, such as those for cannot be used as a sole determinant for accuracy chemical cesium and *Sr, do include self-absorption and'or precision. SRP's participation in the inter.

factors within their derived procedural recovery laboratory comparison programs is based on the as-

factors, sumptions that the QAD and QAP samples are similar in activity level to routinely analyzed QUALITY CONTHOL OP HADIOLOGICAL samples and that they are analyzed for radionu.

i 510NITOlt1NG PROGRA51S clides included in the routine program. Where the true value of the comparison sample approachts the An internal quality control (QC) program for the SIDC (minimum detectable concentration) for the radiological monitoring programs is maintained by analysis, the associated statistical uncertainty of the routine checks listed at the top of the right the measurement at the 95% con 6dence level will hand column:

probably exceed the 20% range. In such cases, the i

=

i 114 SAVANNAH HIVER PLANT - Environmental Report for 1987 l

l routine analytical process is not designed to quan-Calibration of each of the analyzers is checked

{

tify the presence of those particular radionuclid. at quarterly using the appropriate calibration $;as. Of the speciGed activity levels. A more precise determi.

the 36 testa conducted in 1987,34 showed differ-nation of laboratory performance is adherence to encesless than 15% and two showed difTerences that established controllimits for the analysis, were in the 15 to 25% range. All gamus analyzers were therefore producing satisfactory data th rough-The SRP results were generally within 20% of the out the year, I

EPA or DOE values. Ilesults that fell outside of the i

120ere range were invcstigated,and corrective action The audit criterion for satisfactory calibration of the j

u as taken if needed, total suspended particulate samplers is a difference l

ofb7%. All of the samplers, including one co-located i

l control sampler, are audited on a quarterly basis. Of l

QUAtlTY CONTit0L OF the 22 tests conducted in 1987,19 showed a dif.

NONRAD10 LOGICAL MONIT0ltlNG ference of less than 7%. The three samplers that Pit 0 G itA M S showed a ditTerence greater than 7% were adjusted and recalibrated.

l Ambient Air Quality t

Individual results of the Zedek Corporation quar-l The ambient air quality monitom u program is terly audits are presented in Table 118, Vol.11.

conducted by Zedek Corporation, under contract to Du Pont. Quarterly QA audits are performed at the i

four SRP ambient air quality monitoring stations to Liquid Effluents

{

verify instrument calibration, accuracy, and per.

t formance. The stations are equipped with a total of SRP liquid An' samples are collected at the i

11 gaseous analyzers to monitor for sulfur dioxide, outfalls accou.

a the National Pollutant Din.

l oxides of nitrogen, and ozone and Ove samplers to charge Elimination System (NPDES) sampling monitor for total suspended particulates, in addi.

schedule approved by the South Carolina Depart.

l tion to the quarterly audits, daily zero and span ment of Ilealth and Environmental Control i

checks are performed on each analyrer.

(SCDilEC). The c01uent samples are collected by l

SRP personnel for onsite analyses for fecal roliform Results of the quarterly audits are evaluated by two and biochemical oxygen demand and offsite analy.

methods:(1)by a comparison of audit values and in-ses for other constituents. The prin ary ofTsite con-strument measurements at each audit point;and (2) tractors for this program in 1987 were Environ.

I by a linear regression analysis. The linear regres-mentalTesting,Inc.(ETD Charlotte,NC(Jan Feb sion analysis uses paired points (audit concentra-1987), and Environmental and Chemical Services tion and analyzer response) to generate the best (ECS), New Ellenton, SC (Mar. Dec 1987).

straight line that represents the sets of paired points. The difference determined by the slope of the ETI nnd ECS Progra ms. Hoth PTl and ECS main.

linear regression line and th e bias determined by the tain speelne analytical quality assurance programs intercept of the line are used to determine the status to ensure reliability of their analytical data. The of data quality and analyrer calibration.

established programs, based on their Q A manuals, cover the following topies:

The following ditTerence criteria are used for data E laboratory administrative control evaluation and corrective action for the gaseous E personnel qualineations

"" F* * ' "I E personnel training E procedural compliance Difference Conclusion Action E sample acquisition and custody documentation 4 15 %

satisfactory data E laboratory speci6 cation 15-254 satisfactory data recalibrate analyzer E instrument specineations, calibrations unsatisfactory data reenlibrate analyzer and maintenance

> 25'rr E analytical quality assurance

- - -. - ~ ~ - - - -

11. Data Analysis and Quality Assurance 115 ETI and ECS use their QA manuals in conjunction accuracy of the analysis is determined from the with Methods for the Chemical Analysis of Water spike results. Laboratory blanks (deionized water) and Wastes, EPA 600/4 79-020, and Standard are analyzed with each batch of sr,ples.

Methods for the Examination of Water and W' stewater,15th edition, American Public IIealth Known standards from the EPA or another reliable a

Association (APIIA),1980, to assure the quality of source are analyzed quarterly for each routine pa-the analytical data, rameter. Data verification procedures require that 20% of all calculated analytical values must be recal-ETI's quality assurance program includes the fol-culated by another analyst or supervisor. If any lowing specific items:

calculations are in error, the entire set must then be recalculated.

E standard curves prepared and verified daily; Performance Audits. In 1987, ECS participated 5 precision of each analysis determined daily in an EPA sponsored performance evaluation pro-using quality control charts; gram in which EPA provided samples spiked with E precision data reviewed and approved by known concentrations of the constituents ofinterest the laboratory director; to SRP as part of SRP's NPDES quality assurance E precision data outside of control limits program. The samples were forwarded to ECS for reviewed and signed by QA coordinator; analysis or trace metals (aluminum, cadmium, chro-E bias determined for at least 10% of the mium, copper, iron, lead, manganese, nickel and samples analyzed and plotted on zine), nutrients (nitrate nitrogen and total phospho-control charts; rus), biochemical oxygen demand, and miscellane-E bias data reviewed by the laboratory ous constituents such as pli, oil and grease, and total director; suspended solids.

E bias data outside of control limits reviewed and signed by QA coordinator.

All analytical results produced by ECS were within the EPA acceptable limits except for copper and ECS's quality assurance and control procedures, manganese, which were 4% and 2% above the upper described in their QA manual, include regularly acceptance limit, respectively. Operator notes from scheduled performance checks and calibrations to the day the samples were analyzed indicate that the ensure the reliability of measurements and the reproducibility ofresults from the atomic absorption following instrumentation checks:

spectrophotometer may not have been optimal. A summary of the EPA performance evaluation report E balances - daily performance checks using is presented in Table 11-9, Vol. II, known weights; e pli meters - daily intercalibrationQy Compliance Audits and Sampling. In 1987, obtaining a second reading on pli 7 buffer SCDiiEC performed eight NPDES compliance after adjusting the slope with a difTerent audits at SRP during seven monthly visits and cne buffer; comprehensive annual survey (in October).

E UV/ visible spectrophotometers - daily SCDilEC collected two series ofsamples from th e 68 preprogrammed performance checks; active NPDES sampling stations and SRP collected tolerance for all wavelength checks is duplicate samples from each series for comparison.

1.0 nm; E conductivity meters - monthly standard In addition to collecting samples for the NPDES-check; measured conductivity of the permit constituents, SCDilEC also collected standards should be within 5%.

samples at each location for dissolved oxygen and chlorine analyses during the annual audit. Of In addition to instrument tests, analytical perform-the 11 permit categories audited during October, ance checks are made in which 10% of all samples in SRP received a satisfactory ratingin 10. One permit a batch are replicated and precision of the analysis category-efiluent receiving water-was rated as is determined. Spikes (samples to which known con-unsatisfactory because two results out of 400 par-centrations of the standard solution are added) ameters analyzed were outside of permit limits represent another 10% ofeach batch ofsamples. The During 1987, SRP achieved an overall NPDES com-2

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116 SAVANNAH RIVER PLANT - Environmental Report for 1981 pliance rating of 99.7% (6,432 analy-l ses within permit limits out of 6,450 I

parameters analyzed).

y,

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.f, l4 Stream and Itiver Water Quality (j

i 1

h!ost stream and river water quality 6 '

@P W i T dl i p].

f 3 dl; analyses are performed by the SRP En-j vironmental 31onitoring Laboratory based on accepted methodology de-tailed in the EPA's 3fethods for the U

Chemical Analysis of Water and 6

Wa stes (EPA-600 4-79-020) and Handbook for Analytical Quality Con-tmlin Water and Wastewater Labora-tories (EPA 600-4-79 019), and in the APII A's Standard 3fethods for the Ex-amination of Water and Wastewater.

51easures taken as part of the quality y

control program are as follows:

E EPA approved analytical methods are used; E "spiked" samples with known

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analyte concentrations are i

analyzed with every run to determine accuracy; j,1 E 10% replicate analyses are k;

p performed to determine

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precision; j

E titrating solutions are routinely 5

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!s w m standardized; E sample chain-of custody is maintamed; Stream and river water analysis E data are veri 6ed before an analytical report Operating procedures define the frequency of rep-is issued.

lientes and spikes and of reagent standardization determinations. The procedures also provide in.

The quality control measures vary depending on the struction for using work sheets to record method type analysis. Speci6e QC procedures to ensure calibration and instrument settings.

accurate results have been established for each analysis.

The chain of custody form lists the preservatives to be used at the time of collection, methods of collec-As part of the quality assurance program, an annual tion and transport, the person collecting the sample, review verifying conformance oflaboratory operat-the time and date of collection, and which analyses ing procedures to approved EPA or standard meth-are required. When the samples are transferrtd to ods procedures is performed and formally docu-another person, verification signatures are required 4

mented. Also, Nils traceablestandard solutione.are by both the persons submitting and receiving the u sed whenever available to ndd to sam ples in kr.own sample. When the analy.,is is completed and the quantities to provide procedure yield determinn-sample is discarded, tho verification signature of the tions which are plotted on operational control limit analyst is required.

charts. Control chart acceptance limits are well de-Oned to provide an immediate evaluation of the Data verification is documented by authorized sig-accuracy and precision of each analytical method.

r atures on the operational work sheets. All calibra-

4

11. Data Analysis and Quality Assurance 117 tion information is verified, and control charts are E approach to analytical quality control in the reviewed to determine that the methods are within Envirodyne laboratory; control limits. Enh calculation determining sample E data handling and reporting; concentration is checked and approved. Data E experimental design for preliminary transfer to the final report is verified by signature estimate of precision and bias; approval.

E calibration and quality control procedures for the following instruments: atomic i

During the first two quarters of 1987, metals analy-absorption spectrophotometers, UVhisible -

ses of water quality samples were performed on spectrophotometers, Technicon auto replicate samples by certified offsite laboratories, analyzers, gas chromatographs, and gas Envi-onmental and Chemical Services (ECS) and chromatograph!' mass spectrometers; Envirodyne Engineers, Inc. (EEI). These inter-E preparation of reference standard solutions laboratory comparison data are presented in Table for gas chromatography; 11-10, Vol. II. Average concentrations from 1986 m chain-of-custody procedures; serve as appropriate reference values and are also E approved EPA f.est procedures.

shown in the table. The ECS and EEI results agree and compare favorably with the 1986 values.

The normal QNQC program consists of the follow-Groundwater ing established methods:

Sampling and analyses of groundwater are per-E applying recommended preswvation formed by contractors. Sampling, the addition of techniques and holding times; preserva.tives, and cham of custody procedures are E analyzing samples within the prescribed consistent with EPA recommended procedures.

daily calibration ofinstrumentation and Samples are analyzed withm recommended holdmg adhering to scheduled maintenance pro-amo intervals.

cedures for instruments and equipment;

" "I"E #8 ""*I 4"

During 1987, three quality control procedures con-th tinued to enhance the quality of the analyses.These

[ ]);d t n.

quality control procedures are listed below:

E The primary laboratory, Envirodyne Each lot of samples includes analysis of a blank. a Engineers Inc. (EEI), analyzed 10% of the duplicate sample, and a spiked method blank or samples m duplicate

check standard (an aliquot of deionized water forti-f ed with known concentrations of the material of ub ted to a secor d I r tory, E viron-interest).

mental and Chemical Services (ECS), for comparative analyses during the first three Typically, a lot consists of 10 or fewer samples.The quarters. In the fourth quarter,5% of the results of the spiked method blank are recorded on samples were submitted to Enwn,ght Labo-a quality control chart and compared by E EI. Blanks ratories, Greenville, SC, and Weston and duplicates are also recorded for each lot, if the Analytic, Lionville, PA, n,or comparative res ults of any one of these analyses are considered to be out of control limits, the cause of the problem is E B in sa nples representing 2% of the total investigated ana corrected and the entire sample lot number of samples were sent to'the two is reanalyzed.

laboratories for comparative analyses.

EEI Program. To ensure the reliability ofits ana-In addition to the daily quality control, EEI periodi.

lytical data, eel has established a QA/QC program cally participates in interlaboratory programs spon-specifically for SRP samples IENVJ. This estab-sored by the EPA. Thesc involve nnalyzing unknown lished program is based on HandbookforAnalytical performance evaluation samples, known EPA Quality Control, which covers the topics listed at the performance standards, and laboratory check top of the right column.

standards.

,___ _ w

k 118 SAVANNAH RIVER PLANT - Environmental Report for 1987 A summary of the quality control procedure used for internally reviewed. Both radiological and nonradi.

each measurement is given in the table at the ological programs were evaluated. The review was bottom of the page.

conducted as part of a continuing efrort to enhance the QNQC program. Areas reviewed included the Performance Audits. EEI's QNQC program was following:

audited by SRP in 1987. This quality assurance audit was divided into seven areas ofinvestigation 5 sampling techniques listed below.

E instrument calibration E radioanal ' cal procedures E personnel E counting methods E QNQC manual E error limits E facility inspection E data reportirg E sample handling E documentation of QNQC activities E instrumentation 5 chemical procedures Recommendations for improving the program in.

E data validation and reporting cluded the following:

The general audit results were favorable. Recom.

E employment of a full-time QNQC coordi.

mendations made by the audit report were imple.

nator (a full time coordinator has been mented by EEI during 1987, hired in 1988);

E development of a comprehensive INTERNAL REVIEW OF SitP quality assurance manual; QNQC PROGRAhls E establishment of a complete calibration plan for all equipment and Durii.g 1987, the SRP Environmental hionitoring standards; Quality Assurance / Quality Control Program was E use of chain-of-custody for all samples (will be done in 1988).

l Lasurement Typical Procedure Cyanide Blank, check standard to verify previously established calibration curve, duplicate sample.

Sulfate Seven point calibration curve, blanks between samples, check standard every 10 samples, one duplicate /10 samples.

Total Organic Carbon Four point calibration curve, blank, duplicate, check standard.

Fluoride Blank, check standard to verify previously established curve, duplicate sample.

i Phenol Five-point calibration curve, blanks between samples, check l

standard and duplicate for each 10 samples.

Surfactants Six-point calibration curve, blank, duplicate /10 samples.

Sulfide Standardize titrant, blank, hietals Five-point calibration curve, two check standards, two blanks, duplicate /10 samples.

Pesticides Blank, calibration standard to verify curve, duplicate, check standard IIerbicides Blank, calibration standard to verify curve, duplicate, check standard.

GCscan Blank, calibration standard to verify curve, duplicate, check standard.

i

11. Data Analysis and Quality Assurance 119 The radiochemist who reviewed the program pro-graphs, drying ovens, and atomic absorption spec-vided technical assistance in implementing several trophotometers. The history books contain the improvements. Regular calibratinn of all instru-following:

ments was identified as the most important area needing improvement, and a systematic, docu-E equipment and instrument mented calibration program was established for sev-calibration forms eral key instruments. Instrument history books E quality control check forms were established for se' eralinstruments, including E control charts nuclear counting systems, analytical balances, E equipment nonconformance conductivity and turbidity meters, ion chromato-notice forms.

1987 HIGHLIGHTS E SRP uses a standardized algorithm to determine the lower limits of detection (LLDs) for allits nuclear counting systems and adjusts the values for various factors, including sample geometry, detector efficiencies, and radioactive decay.

E LLD values for various radionuclides are given (in Vol.11) for SRP's HPGe gamma ray spectrometer systems as derived from two ditferent spectrum analysis software systems.

E Results of the EPA and DOE intertaboratory programs verify SRP's analytical accuracy.

E The 1987 results of the ambient air quality program, conducted by Zedek Corporation, showed that SRP's gaseous analyzers and total suspended particulate samplers were performing satisfactorily.

E NPDES compliance audits by the South Carolina Department of Health and Environ.

mental Control resulted in a 99.7% compliance rating for the SRP liquid etfluent program.

E Metals analyses performed by outside contractors ECS and eel on replicate samples f rom SRP streams and the Savannah River were in agreement and compared f avorably with SRP's 1996 values.

E An SRP audit of the groundwater QA/OC program established by the primary contractor, j

eel, yielded favorable results.

l E A full-time OA/OC coordinator has been hired as a result of a 1987 internal review of a!I of SRP's OA/QC programs for environmental monitoring. Other recommendations for further improvements are beingimplemented.

12 Environmental Management and Research Programs

SUMMARY

- This chapter describes various SRP and SRL environmental management and research programs, including Savannah River Ecology Laboratory programs and Savannah River Forest Station programs. (1) The comprehensive SR P Environmentallmplementation Plan was completed and will be presented to Congress in 1988, and SRP initiated and/or participated in a number of activities to ensure compliance with regulations mandated by the Environmental Protection Agency, the South Carolina Department of Health and EnvironmentalControl,and the Department of Energy, particularly as embodied in SARA Title Ill, and the RCRA Part B permit.

Environmentalimpact statements were issued on groundwater protection and alternative cooling water systems. (2) SRL management and research programs included a number of studies to follow the dispersion and effect of SRP pollutants in the environment, to develop and implement procedures to comply with regulations and to conduct pollution abatement activities, and to meet permit or environmentalimpact statement requireme nts. (3) Savannah River Ecology Laboratory programs included biogeochemical ecology studies, stress and wildlife ecology studies, and wetlands ecology research. (4) U.S. Forest Service Savannah River Forest Station programs included a forest management program and several forest research programs, plus studies of endangered species.

L

)

This chapter describes the environmental manage-Environmental Audits and Appraisals ment and research programs of the Savannah River Plant, the Savannah River Laboratory, the Savan.

SRP environmental programs are reviewed annu-nah River Ecology Laboratory, and the Savannah ally by the Environmental Protection Agency (EPA)

River Forest Station of the U.S. Forest Service, and the South Carolina Department ofIIcalth and Environmental Control (SCDilEC) by compliance SAVANNAll RIVER PLANT audits. The Department of Energy and Du Pont also ENVIRON 51 ENTAL 51ANAGE51ENT conduct internal environmental appraisals and PROGRA31S audits.

Environmental Implementation Plan From the third quarter of 1986 into 19S7, EPA, as-sisted by SC DlIEC, conducted the largest SRP envi-SRP h as developed a compreh en sive Environmental ronmental audit. The audit, known as a multimedia Implementation Plan (EIP) that has set specific en.

audit, required 17 EPA and eight SCDlIEC repre-vironmental goals for the site for the next five to 10 sentatives and encompassed seven areas: hazard-years and will provide an integrated approach to ous waste (as defined by the Resource Conservation SRP environmental programs. The plan, which the and Recovery Act [RCRAl), solid waste ma nagemen t Department cf Energy (DOE) will present to Con-units (SW31Us), wastewater (as covered by the gress in early 1988, outlines specific programs to National Pollutant Dischargo Elimination System maintain air quality, to prevent surface water and

[ NPDES 1), drinking water, groundwater, toxic sub-groundwater contamination, and to protect wildlife, stances, and air quality. The audit identified no It also establishes the associated manpower and major problems and 98 administrative findings, budget requirements.

which were immediately corrected. During its

122 SAVANNAH RIVER PLANT - Environmental Report for 1987 followup audit hlay 20 29,1987, EPA noted the ini-of the permit became effective on November 1,1987, tiatives taken by SRP to correct the administrative and expires on November 1,1992.

items and complimented SRP for a much improved environmental performance.

RCHA Facility Investigation. For coordination and oversight of the EPA portion of the SRP Part B In January 1987, the Department of Energy Head-Permit, the SRP Environment and Energy Depart-quarters (HQ) conducted a comprehensive environ-ment formed a task team to develop an overall RFI mental survey at SRP, fulfilling its commitment to program plan, which is to be followed by waste-site-Congress to perform a baseline environmental sur-specific RFI plans, investigations, and reports. The vey of all DOE facilities. The three-week DOE HQ RFI program plan is scheduled to be submitted to survey surpassed the scope of the EPA multimedia SCDilEC on or before April 1,1988. Following audit and required over six man-years of SRP SCDHEC review and approval, the waste-site-effort.

specific RFI plans will be developed and submitted according to a set schedule, on or before October 1, 1989. The waste-site-specific investigations and Hesponses to Superfund Amendments and RFI reports will follow similar schedules. The clo.

Heauthorization Act, Title III sure actions and schedules will be determined by the RFI reports. The cost of this effort (excluding clo-In 1986, Congress passed the Superfund Amend-sures)is expected to be over $4 million.

ments and Reauthorization Act (SARA), which in-cluded a Community Right to Know section (Title Addition of Hadioactive Waste Facilities. On 1H). This title requires SRP to make public a sub-31ay 1,1987, DO E issued a final interpretive rule for stantial amount ofinformation on the safety, use, the "by product material" as defined in the Atomic and locations of chemicals used on the plant. In Energy Act of 1954, as amended. Under this final addition, SRP must r trticipate with local emer-rule, radioactive wastes that are also RCRA hazard-gency planning commissions (LEPCs) in preparing ous wastes are to be jointly regulated by DOE and plans to handle emergencies involving hazardous EPA, with DOE continuing oversight for the radio-chemicals.

active component of the waste and EPA assuming regulatory authority over the hazardous compo-In September 1987, SRP sponsored a Title HI Work-nent. As a result of this final rulemaking, SRP filed shop attended by over 100 people, including mem-protective revisions to its RCRA permit application.

bers of the Central Savannah River Area LEPCs, Facilities added to the application include the High local industry, law enforcernent agencies, news Level Radioactive Waste Tanks, the Defense Waste media, and state planning committees. In October Processing Facility (DWPF), the Savannah River 19S7, SRP provided the Aiken, Allendale, and Laboratory (SRL) Waste Tanks, and the Transu-Barnwell county LEPCs a detailed list of approxi-ranic (TRU) Storage Pads. EPA was requested to mately 8,000 hlaterial Safety Data Sheets ( AISDSs) provide a ruling as to whether the waste tanks for chemicals and chemical products used at SRP.

and DWPF could be permitted as wastewater treatment units.

Operations Under Hazardous Waste RCHA Part H Permit Environmental Awareness / Training Programs On September 30,1987, SCDHEC issued to SRP a RCRA Part B Permit for operation of the Hazardous In 1987, an Environmental Awareness / Training Waste Storage Facilities (Buildings 709.G,709 20, Coordinator was designated by the SRP E & E 709-4G, and 710-U) and post-closure maintenance Department with responsibilities for implementing of the 51 Area Settling Basin and vicinity (overCow a program to communicate site environmental goals ditch, seep area, and lost Lake). The permit expires and enhance employee commitment to protecting i

on September 30,1992. The EPA issued the federal the environment. Employee training is a line man-portion of the permit covering the requirements of agement responsibility, and E & E assistsline man-3004 (u) and 3005 (h) of the 1984 RCRA Amend-agement with environmental training to satisfy ments. This portion of the permit identifies 65 solid regulatory requirements. Three specialized courses,

{

wa ste management units at SRP that will require a "Environmental Auditing,""Clean Water Act Over.

RCRA Facility Investigation (RFI). The E PA portion view," and "Fundamentals of RCRA," were ofTered

12. Environmental Management and Research Programs 123 onsite by E & E. These awareness and training Alternative Cooling Water Systems, SRP, DOE /

programs will provide employees with the appropri-EIS-0121, October 1987. (The Record ofDecision ate mixture of environmental awareness and job-was delayed until early 1988 pending a decision specific environmental training, on an EPA and SCDHEC recommendation to install a recirculating cooling tower for K Area.

Preparation of NEPA Documentation for The Record of Decision was issued on February SRP/SRL Activities 12, 1988, and recommended installation of the tower.)

Thc National Environmental Policy Act (NEPA) of 1969, the Council on Environmental Quality imple-menting regulations (40 CFR 1500-1508), and DOE SsL ENVIRONMENTAL MANAGEMENT AND guidelines (52 FR 47662) require the early consid-RESEARCH PROGRAMS eration of environmental factors during the plan-ning and assesn.'ent process for all proposed federal Special Studies for Determining the actions.The NEPA Group of the E & E Department Dispersion and Effect of SRP Pollutants is respon sible for preparation and/or coordination of all appropriate NEPA documentation for SRP/SRL Development of Mass Spectrometry Methods, activities. It manaps the transmittal of NEPA Development of high sensitivity isotope dilution document recomm endations and information to the mass spectrometric (IDMS) methods for measuring DOE-Savannah River (DOE-SR), with approval of plutonium (Pu)in body fluids is in progress. IDMS the SRP/SRL management required for all formal bionssay methods are greater than 1000 times more transmissions. In order to ensure their technical sensitive than ultra-low-level counting techniques accuracy, SRL staff reviews many of the NEPA and will permit assessment of the average Pu body documents prepared for DOE. Determination of the burden in the population caused by global fallout.

appropriate level of documentation is the responsi-These levels are too low to be measured easily by bility of DOE.

conventional counting techniques. Development of IDMS methods for measuring"Te and 2"Np in the In 1987, the NEPA group processed 289 SRP/SRL environment is also in progress.

activities. The NEPA and Permits Groups reviewed the SRP/SRL NEPA, safety analysis, and permits In addition, a mass spectrometer is being designed checklists for these activities to determine the ap-to measure the nonradioactive fission product iso-propriate level of NEPA documentation and for topes of Kr and Xe at ultra low levelsin the environ.

permitting requirements. Du Pont issued one ment. Direct measurement of these isotopes will Memorandum-to-File (MTF) for a Test Authoriza-permit more accurate assessment of environmental tion and DOE SRissued 10 MTFs for projects based releases of the short-lived radioactive Xe and Kr on draft MTFs prepared by Du Pont personnel, isotopes.

During 1987, DOE-IlQ continued to edit, with In a third study, the 11e/9fe mass spectrometeris 8

NEPA personnc! assistance, the final Environ-being used to confirm very low concentrations of mental Assessment (EA), Management Activities environmental tritium. Samples are collected di-for Retrieved and Newly Generated Transuranic rectly or by removing moisture from air streams an d Waste-SRP (DOE /EA-0315), which will be issued adsorbents followed by recovery of the water in the 1

early in 1988.

laboratory. Trapped 8He is removed by degassing under vacuum, and the sample is then sealed and Preparation of EnvironmentalImpact stored to allow He to accumulate from the decay of 8

Statements tritium. ARer a suitable accumulation period, 8

the He is removed and measured in the mass During 1987, the following two Environmental spectrometer.

Impact Statements (EISs) were issued:

1 The 11e/*lle mass spectrometer is also being used to 8

Waste Management Activitiesfor the Protection of measure the consistency of atmospheric 'llel'He Groundwater at the Sa cannah River Plant, DO E/

ratios directly in small volumes of air. The resulting EIS 0120, December 1987. (The Record of Deci-baseline will be useful in studying very low concen-sion was issued in March 1988.)

trations of atmospheric tritium.

l

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124 SAVANNAH RIVER PLANT - Environmental Report for 1987 Improvement of Aqueous Effluent Tritium the Savannah Itiver, and 0.015 pCi/g in the river 31onitors. An evaluation of efiluent tritium moni-sediment. Other radionuclides were lower by an tors showed that proposed improvements would order of magnitude or more, except for 311. Tritium allow prompt detection of tritium releases of I concentrations were determined with less sensitiv-Ci/hr from 100-D Area.The proposed monitor uses a ity and were less than 2 pCi/mL in the river. All flow through design and a solid scintillant. A proto-levels were below 1/1000 of the DOE guides for type monitor is to be built and tested in 19SS, drinking water.

In post operational surveys, controlle I releases by Vogtle 1 were detected in the Savannah Iliver near the plant and farther downstream. During a hiny 1987 relcase, a maximum "Co concentration of1.31 i

pCi/L was observed in samples taken about 0.1 mile below the outfall. The only other release occurred in October /Novernber 1987, when c maximum Co sn a t

concentration of 13.2 pCi!L was observed at the same sample location. At downstream locations, these activities decrease by dispersion to approxi-mately 10% of the maximum at liighway 301 bridge and approximately 1G at lleaufort-Jasper. In addi-tion to ^Co, minor amounts of"Cr,5'51n,"Fe,'oCo, 5

"Nb, and *Zr were observed. All observed levels were below 1/10C0 of the DOE guides for drinking y 4.h ;

water.

The Sith measurements have been compared with those made by V.,gtle stafT. The Sitt time depend.

,[Q[ k

~~ A ments at the discharge site. This fraction is reason-ent activity profiles agree well with the Vogtle re-lease data. SitL measurements 0.1 mile below the

'r outfall are about 1/5 as large as Vogtle measure-able in view of dispersion by the river. TI.e mutual Vogtle 1 cooling towers sharing of SItIWogtle data related to discharges will continue, as these studies have already illus.

Environmental Surveys in the Vicinity of trated a sensitive capability for detecting potential Vogtle 1 Nuch ar Power Plant. Eavironmental release problems well before they develop into haz-radionuclide concentration data were collected by ards. The *Co was detected down to 1/1,000,000 of SRP personnel in the vicinity of Vogtle 1 Nuclear the DOE guide levels.

Power Plant (near Waynesboro, GA) over a four-month period prior to its startup operation in the Studies of "C Stack Emissions. Stack emissions spring of 1987. Soil, stream, and sediment samples from P Iteactor were sampled for "C during the site-were examined for 1!, "Co, "'Cs, "7Cs, "Pu, and wide environmental survey conducted in the fall of 8

"Pu. Background natural radioactivities were also 1987. During 1988,"C samplers will be insta&d in examined as a consistency check. The samples were all reactor stacks and also in the II-Area Separa-analyzed using low level counting capabilities of the tions stack.Operntion of the existing samplerin the TRAC van (Tracking Itadioactive Atmospheric F Area Separations stack will continue.

d Contaminants), the Ultra Low Level Counting Facility, and the Underground Counting Facility.

j All results were consistent with typical earlier Studies of *! Itcleases, hicasurements of *l in measurements in comparable areas.

surface waters and groun rater on the plant site since 1970 were compileri into a comprehensive In the Vogtle vicinity,"7Cs was the only manmade report. htonit oring of the separation stack emissions radionuclide readily detected. Average concentra-was continued. lleactor stack emissions will also be-tions of 0.5 pCUg were found in soils,0.012 pCi/L in monitored in 1988 l

1

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12. Environmental Management and Research Programs 125 Water Study, and various NEPA activi-dhhb9 h.c ties, including the Alternative Cooling "L

% Q. g @:7%dF[+Ny[a\\]Mh.),

Water Systems EIS and technical sup-

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port documentation.

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N&[@y Lower cost h!SS systems are being W@ W 'W\\,1

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yG N evaluated in the newly developed SRL

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J on E T M remote sensing analysis laboratory.

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!'l 4 jj Mid-These systems include a false color in-o W(..a frared video camera and SPOT AfSS

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/p B

data. Use of SPOT AfSS data may pro-

, ;/ gig t

vide a low cost supplement for j[n p!.'.DW f.

1 i

%7 landcover characterization for environ-mental, wetlands, and habitat assess-l

.. E io ment. The relatively high resolution of

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.i the SPOT satellite sensor system may j

provide detailed seasonal and regional d-coverage not previously available in a s

format readily used at SRP.

Studies of Plants Exposed to Ent:ance to Underground Counting Facility Tritium in Controlled Environ.

Development of Remote Sensing Techniques.

ments. Research at SRP has indicated that the Development of remote sensing techniques contin.

concentration oforganically bound tritium in plants ued in 1987 as a cost-effective means of environ-is higher than the equilibrium concentration in the mental monitoring oflarge areas, such as L Lake, plant ti.; sue water. It has been suggested that this Par Pond, the SRP Savannah River swamp, and F-efTect may be caused by the combination of a physio-and li-Area seepage basins. Remote sensing meth.

logical process for incorporation of tritiated hydro-ods currently used include airborne multispectral gen in plants and the relatively high specific activity scanner (31SS) surveys, airborne (helicopter) o# tritiated hydrogen in the environment of SRP.

gamma radiation surveys, and vertical and oblique A controlled environmental chamber system has aerial photography. Test overflights of a variety of been constructed as part of a research program landcover types on SRP were also made with three designed to understand the role of tritiated hydro-difTerent types of multispectral video cameras gen in determining the organic tritium content of mounted in small aircraft Data were collected primarily through contracts to EG&G (51SS, photography, and gamma surveys), and 1TD/ NASA (31SS surveys). In addition, h!SS and panchromatic data from the French SPOT satellite were acquired.

y Data analysis yielded information on the envi-ronmental impact to wetlands, the potential

~

g habitats for endangered species, thermal pat-g d

terns and dye studies of L Lake, and the distri-

~

5. 'gM l X A"*

I bution of radionuclides on site. Techniques to

=

determine the water quality and algae distri.

i butions in Par Pond and L Lake were devel-oped. The photographic and AfSS data were

/~

]

valuable in mapping potential outcrop areas to the upper Four hiile Creek watershed froni.he

^

F and II Area seepage basins. Information gathered by remote sensing supported the L Ultra low level gamma analysis Lake studies, the Comprehensive Cooling 7-e e

-me

.,.-----,---~~~w

- ---+-~ ~ ~,---._---

126 SAVANNAH RIVER PLANT - Environmental Report for 1987 exposed plants. The chamber system consists of a face Microbiological Culture Collection (SMCC), ha s conditioning system which supplies air at controlled been developed. Phase II (FY 1988 to FY 1997) is temperature and humidity to three glass exposure concentrating on exploiting some of the scientific chambers. Tritium gas of carefully controlled aivances and research opportunities identined in specific activity is mixed with the air in the Phase I. Phases I and 11 will provide information chambers.

that willlead to an understanding of the interaction between the biosphere and geosphere.They will also Tomato, pepper, and pine plants have been exposed lead to microbial processes for mitigation of subsur.

in the chambers for 2-hr periods under conditions face contaminaticn, to environmental understand-controlled by a microcomputer, which also moni-ing of stimulation tech niques that will contribute to tored the experiments and provided environmental mitigation, and in time, to evaluation of the impact data ready for computer analysis. Water was re.

of bioengineered organisms on subsurface moved from the plants by freeze drying, and the dry ecosystems, plant material was exposed to a saturated air stream for 72 hr to remove easily exchangeable trit-The program began in 1986 with the drilling of three ium. The plant material was then combusted in a wells through the various water bearing formations furnace and the water of combustion collected and to the bedrock. Microbiological samples were col-analyzed for tritium. The amount of tritium in the lected in an aseptic, undisturbed manner to a depth organic fraction was very small-below detection in of 851 ft. Pore water ch emistry h as been analyzed for some cases.

49 different physical-chemical parameters, includ-ing metals, anions and cations.

During the exposure period, small but measurable amounts of tritium were oxidized to tritiated water Microbiological data indicate that microorganisms in the plants. Measurable organic tritium was found occur in great diversity and densities regardless of only in the vegetation containing the highest levels the sample depth. The densities are comparable to of tritiated water. This suggests that most of the surface densities, one to 10 million bacteria per tritium is incorporated from tritiated water, proba-gram ofsoil sample, and their diversity is very great.

bly by photosynthesis. Further exposures oflonger Rates of denitrifiention, nitrogen filtration, and duration are planned to provide greater accumula-carbon metabolism have been measured at depths of tions of tritium in the organic fraction. This will 850 R and are higher in sands than in clays. All 4

i provide a better measure of the rate of organic functional groups of microorganisms are present tritium uptake and the factors which induence at depth.

uptake.

Fungi and protozoa are also present at depth. Proto-Studies of the Microbiology of the Deep Sub-zoa have been found to a depth of 700 f1 and at surface. Together with a consortium of national concentrations high enough to significantly reduce laboratories and universities, SRL and the Ecologi-the densities of bacteria on which they feed. At cal Research Division of DOE are working to charac-depths of 232 to 235 ft and 667 to 670 fl, bacteria terize the biomass, community structure, and envi.

were not isolated. This indicates the samples were ronmental fa: tors that control microbial communi-collected in such a manner to ensure that ties of the deep subsurface. A long-term goalis the microbiological contamination from other sources use of active microorganisms in in situ bioreciama-did not occur.

tion (ISB) to degrade organic contamination at SRL and other DOE sites.

Sitewide Seismic Survey. A reflection refraction 4

seismic survey was conducted on the SRP site in A two-phase program is under way. Phase I (FY 1987 to define subsurface geological structure and 1986 and FY 1987), an exploratory research phase, stratigraphy. About 218 km ofseismic lines were re-focused on the presence, abundance, and diversity of corded across the 816 km' site. Data quality was indigenous microorganisms, on their community generally good. A refraction velocity of 5.49 km/see structure, and on the hydrogeologic, geochemical, measured in the crystalline basement provided a and physicalinteractions that control the presence distinct contrast to the overlying sediments and the and activity of microorganisms at depth. Prelimi.

sedimentary rocks in the Dunbarton Triassic Basin.

nary information on biodegradation capabilities and Results of the seismic survey will provide a three-di-

{

functioning of these organisms, as well as a Subsur-mensional representation of the geologic structure

12. Environmental Management and Research Programs 127 beneath the SRP for use in permitting and environ-distribution and dose, road networks, routing and mental documents and in safety analyses.

location of emergency response vehicles, land use, topography and maps of the impact regions.

Activities to Aid Compliance with Pollution Abatement Regulations Additional computer hardware was installed in the environmental transport area of the SRP Emer-Improvements in Emergency itesponse Sys-gency Operating Center (EOC). A super microcom.

tem. Several changes were made to the remote puter was linked to the WIND system computer environmental monitoring system for emergency to improve reliability of emergency response sup-response. Data signals from the tritium monitors on port. It provides a backup menu of WIND system the stacks of the separations facilities and at 12 emergency response codes to the EOC if WIND perimeter sites were linked to the Weather INfor-system computers are unavailable. An upgraded mation and Display (WIND) system computer and computer terminal and printer were also incorporated into the VANTAGE data management installed.

system. Previously, incoming signals consisted only of meteorological data, river and stream monitoring The Tracking Radioactive Atmospheric Contami-data, and Ielake il ermal monitoring data. When na nts (TRAC) mobile laboratory was used in experi-fully implemented, this system wi'.1 provide auto-ments to study the dispersion of a harmless tracer matic monitoring cf abnormal stack releases from gas SF during the transition from nighttime to all process facilities and automatic inclusion of daytime. The SF, was released from a 60 m stack, these source terms in the emergency response and surface concentrations were measured with a codes.

continuous analyzer onboard t te TRAC vehicle.

h1eteorological data were obtain ud with SRL's tower New instrumentation and data ecquisition/trans-system and a Doppler sonar.

mission systeme were instalkd on meteorological monitoring wwers in eigli production areas. The Two Nal detectors have been installed in the TRAC new instruments are mere accurate, sensitive, and mobile laboratory to allow terrestrial scans. The reliable ard require kss frequent calibration than detectors will be useful in localizing (at a distance) the instruments they replaced. The new data acqui-any land masses that might inadvertently become sition system eliminates susceptibility to total sys-contaminated due to an unplanned release. In efTect, tem failure by having each tower feed data inde-the monitors will act as the plume monitor, except pendently into the WIND system computers over they will view the ground rather than the sky.

dedicated telephone lines. The data available from Performance tests on the monitors are currently the WIND system are supplemented by data from a under way.

second data acquisition system that provides con-tinuous display of 1-min-average wind data in each production area control room. The new system also 51onitoring '"Cs Transport from I-Heactor. A provides for system maintenance and surveillance comprehensive environmental sampling and analy-l by constant monitoring of vital functions by tele-sis program to monitor "7Cs transported from Steel phone. An uninterruptible power supply at each site Creek prior to and following the startup ofIeReactor provides continuous service during short power continued. This program provides the transport and

failures, material balance data necessary to demonstrate that no significant ofTsite changes occur in "Cs Revision of WIND system software continued dur-concentrations associated with the restart of the L-ing the year. This revision included modularization Reactor in 1985.

ofkey functions, as well as improved methods to the control and documentation of software.

Evaluation of the effect ofI Reactor restart on the concentrations of SCs in the Savannah River and A Geographic Information System (GIS) was in-downriver water treatment plants has been com-stalled in the Weather Center Analysis Laboratory pleted. Cesium 137 concentrations increased (WCAL). The GIS will couple data from the emer-slightly in the Savannah River below SRP (from gency response codes to environmental and geo-0.078 pCi/L in 1985 to 0.118 pCi/L in 1986) the year graphic digital databases. Coupling of these data aRer I Reactor restart, partially because of low will provide and display information on population ilows in the Savannah River. Annual average mCs i

I

l 128 SAVANNAH RIVER PLANT - Environmental Report for 1987 concentrations in the drinking water resultin a dose was mapped using aerial remote sensing and sur-ofless than 0.003 mrem /yr. This is approximately face measurements from boats.

0.001% of the average person's exposure to natural radiation (295 mrem /yr)in the United States.

In order to further study the cooling efliciency of L Lake, SRL developed cooling pond models. These Measurements of"7Cs transport across the Savan-models have been efTective in delineating steady-nah River Goodplain at the site boundary during state conditions at L Lake but have been less suc-Gooding were not made until 1987. (The river was cessfulin modeling conditions during speciGe peri-not in Goodstage during 1986.) Normally, SRP ods, partly because or the lake surface's sensitivity streams discha rge directly into the Savan nah River, to changing meteorological conditions.

but during floodstage, the discharges are con-strained to flow near the upland edge of the The thermal conditions in L Lake can be portrayed floodplain for a distance of about five miles before accurately by combination of high resolution quali-mixing with the full flow of the Savannah River, tative thermal imagery (generated during over-Cesium-137 concentrations measured in the flights conducted by EG & G, Inc.) and monitoring Goodplain while the river was in Goodstage in 1987 data gathered by 31 floating platforms near the showed that L-Reactor restart had only a minor center of L Lake. However, EG & G overnights are effect on "7Cs transport ofTsite. Less than 1 Ci of expensive and are routinely available only as sup.

"7Cs was transported across the floodplain during plements to other annual SRP surveys. Satellite flooding in 1987.

multispectral imagery gathered by a Land Re-sources Observatory Satellite (LANDSAT) is avail-able frequently (four times a month) and could prove useful in providing data to supplement g',

monitoring data and to refine the cooling pond models. However, to date LANDSAT data have

~

been less useful than other data owing to the satellite's lower resolution and poor calibration V

44 of atmospheric efTects.

.o m

.j-jg

{

SRL is collaborating with NASA to perform g

g LANDSAT thermalimagery calibration studies at SRP's cooling ponds. To date, four experi-ments have been conducted at Par Pond and C Pond. SRL is gathering ground data from in stru-mental buoys, surface water observation by v~ q infrared thermometers, and tethered balloons and air sondes, which measure temperature and humidity profiles through the atmosphere.

Airplane used in overflight studies STABLE Program: Study of Contaminant Dispersal Through Cooling of SHL Air Thermal Studies of SRP Cooling Ponds The Layer.The stable planetary boundary layer (SBL) research program to enhance understanding of the is the warm layer in the night air. Lyingjust above cooling process in L Lake and Par Pond and to the ground, it is cooled by contact with the cold evaluate methods that may improve the cooling ground. Because chemical and radioactive accidents efliciency of L Lake was continued.

can happen at night (e.g., Bhopal, Chernobyl), it is important to understand how airborne contami-A new canal was constructed to divert the hot water nants disperse in the SBL.

from the reactor to the upper end of L Lake. Dye tracers were used to show that the new canal in-The STABLE (Stable Atmospheric Boundary Layer creased the flow time to the middle of the lake by Experiment) is an efTort to understand how turbu-several hours, which allowed a slight increase in lence and difTusion in the SBL affect dispersion of production in L Heactor.The dye tracer distribution contaminants. Active groups in the project are l

..,-----an_w,.,,--,-----.~,-----

12. Environmental Management and Research Programs 129 DOE afTiliated laboratories (SRL, Atmospheric processed to prepare joint frequency distribution Turbulence and Diffusion Division, and Lawrence tables for each tower. These tables are now being Livermore National Laboratory) and North Caro-used in computer programs to calculate offsite ef-lina State University.

fects ofnormal releases of radioactivity to the atmos-phere and the effects of hypothetical unplanned A goal of the program is to investigate how turbu-release events.

lence in the SBL transports and disperses airborne contaminants. STABLE's initial efrorts produced a Activities to 5fect Permit or Environmental "climatology" of turbulence structure for the SBL at Impact Statement Requirements the SRP site using SRL's turbulence data base.

SRL's turbulence data base was collected from 1973 Monitoring L Lake Status. Only three years old, through 1979 when bivane and cup anemometer L Lake is classified as a young lake. As a lake ages, measurements at seven levels on an 1100-f1 TV structural and functional internal adjustments oc-tower were digitized every 5 see and stored on cur within the lake's communities and ecosystem.

magnetic tapes.

These internal changes respond to several external physical, chemical, and biological forces. The forces The SB L climatology study has shown that a variety affecting the successional process of L Lake include of phenomena occur including waves, turbulent water quality characteristics of the Savannah River episodes, large shear zones, and mesoscale eddies, input, thermal load from L Reactor, depth of with-The turbulent episodes have been linked to changes drawal at the lake's outlet dam, weather conditions in the Richardson number, a parameter comprised which impact rainfall, cloud cover, temperature, of wind speed and temperature gradient. Further and the nature of the drainage basin itself.

extensive investigations are planned for 1988, in-j cluding a two-week field program for intensive The pelagic region (open water) of L Lake comprises measurement and documentation of the intermit-the lake's plankton and contains most of the lake's tent episodes of the SBL biomass. This region is responsible for most of the

)

lake's energy flux. Its structural and functional l

1 Calculation of Offsite Doses with CAAC Code.

characteristics respond to several physical condi-To demonstrate compliance with EPA National tions, including temperature, dissolved oxygen, pII, Emission Standards for Hazardous Air Pollutants and submarine irradiance. In L Lake, temperatures (NESHAPS): Standards for Radionuclides (Title 40 ranged from 13 to 34C during 1986 through 1987.

Part 61 Code of Federal Regulations), SRP devel-When the lake was thermally stratified, epilimnetic oped a capability to calculate ofTsite doses from temperatures ranged from 14 to 34C and hypolim-atmospheric releases of radioactivity with the EPA-notic temperatures from 13 to 28t. Dissolved oxy.

approved CAAC Code [CAAC86] (Clean Air Act gen (DO) ranged from 1 to 6 ppm, similar to other Code, formerly called AIRDOS-EPA). This com-area reservoirs. Correspondingly, pH varied from puter code calculated offsite radiation doses for four 6.510 9.0 during these periods, which is also compa-projects planned for the Savannah River Plant, with rable to other basins in this part of the country.

l the results showing that ofTsite efTects would be negligible. This information was used in NESH APS The littoral (inehore) community, an important applications for new emission source permits re-nursery forjuvenile fish,is known for its high rates quired by the Clean Air Act for construction of new of macrophyte productivity and plays a significant facilities that will release radioactive materials to role in stabilizing the lake's shoreline. From Janu-the atmosphere.

ary through August 1987, Savannah River Ecology Laboratory (SREL) personnel planted five vegeta-Meteorological Data for Dispersion Calcula-tive types of macrophytes in L Lake. In October, tions. Wind data from the production area meteoro-monitoring efforts with plot counts and remote logical towers are stored on magnetic com puter tape sensing techniques indicated that the plantings and are used for periodic updating of the databases were successful.

used in calculating dispersion of atmospheric re-leases of radioactive (and also nonradioactive) mate-For the past two years, insects, mostly midges (Chi-rials to th e atmosph ere. In 1987, data from the seven ronomidae), hwe dominated the benthic (lake bot-towers for the period 1982-1986 were verified and tom) and littoral communities. In addition to

130 SAVANNAH RIVER PLANT - Environmental Report for 1987 midges, the amphipod Hyalella asteca, common Coastal Plain stream water chemistries. The river throughout North America, was another summer-and associated thermal streams have higher nutri-time dominant in L Lake. Total densities were ent concentrations than the ambient streams. In comparable to other southeastern reservoirs, in-addition, high flow rates induce erosion in the ther-cluding Par Pond.

mal stream channels and erente elevated suspended solid loads that are removed as water passes across Successional changes in the fish community of L the stream deltas and through the SRP Savannah Lake have been apparent throughout its history.

River swamp.

Initially, stream, swamp, and pond species were successfulin L Lake, including golden shiners, sev-Aquatic releases of radionuclides associated with eral species of minnows, brook silversides, and SRP operations are low and, except for tritium, are mosquitofish. In late 1987, the threadfin shad, a largely contained within the SRP boundaries. Radi-common pelagic species in southeastern United onuclide releases, substantially reduced since the States reservoirs, made a significant increase. The early 1970s, remain well within DOE and EPA present populations are considered healthy and the concentration guidelines.

observed succession in L Lake has been typical of other reservoirs. Largemouth bass and adult Physical factors associated with the release of reae-bluegills continue to play an important role as the tor cooling water, such as flooding, elevated tem-top keystone predators in the lake. Their feeding peratures, erosion and sedimentation, continue to habits significantly structure planktivorous fish eliminate cypress tupelo swamp forest canopy in populations and their recruitment.

the river swamp. The trend of canopy loss may be reversed by long-term reductions in thermal efilu-Comprehensive Cooling Water Study. The ent flows and temperatures. As shown by studies in Comprehensive Cooling Water Study (CCWS) was the post-thermal Steel Creek, stream corridor and initiated in 1983 to evaluate environmental effects delta areas are rapidly recolonized by herbaceous associated with SRP eocling water withd rawals and and shrub-scrub species after reactor operations discharges, and to determine the significance of cease, llowever, sedimentation and altered flow the dects on the onsite and downriver environ.

paths may retard or prohibit recovery of the original ments The CCWS report, published in October cypress tupelo swamp forest.

1987, summarizes historical information and pres-ents the results of the two year study. The seven major program elements addressed in the report are When the reactors are operating, thermal streams water quality, radionuclide and heavy metal trans-and sedimentary deltas are largely devoid of fish port, wetlands, aquatic ecology, ecology of Par Pond, and aquatic insects, except for thermally tolerant endangered species, and waterfowl.

species. These areas are rapidly invaded by aquatic species when reactors are not operating. Limited The water quality ofonsite streams at SRP has been spawning takes place in thermal streams, and may influenced primarily by the elevated temperatures occur earlier than in nonthermal streams. In con-and flow rates associated with reactor operation.

trast, ambient temperature tributaries to thermal During reactor operation, heated cooling water dis-effluent streams appear to support self sustaining charges at temperatures ranging from 32*C to about communities of aquatic organisms typical of SRP 70*C are discharged to onsite streams, in which nonthermal streams of similar size.

mean annual temperatures range from 15 to 19*C, Although substantial cooling occurs during passage In the vicinity ofSRP, the Savannah River contains l

through the streams and swamp, thermal stream an abundant, diverse fish population. In general, water reaches the Savannah River at temperatures the fish are attracted to thermal plumes in the ranging from 9 to 41*C, compared to 4 to 26*C in the winter, but there is no evidence that river popula-ambient river.

tions are adversely affected by SRP cooling water discharges.Neither impingement of adult and juve.

The large volumes of reactor cooling water dis-nile fish nor entrainment offish eggs and larvae had 2

charges (2.5 to 11.3 m%) relative to natural dis-significant effect on the Savannah River during the charges of the receiving streams (less than 1 m%)

CCWS period. impingemen t rates were low, averag-result in thermal stream water chemistries more ing less than 18 fish per day. Entrainment at the similar to Savannah River water chemistry than to SRP cooling water intakes on the Savannah River

- - - - - - - - - - - - - - - - - - " " - ^ ' - " ^ " - - - - " - - - - - - ^ - - - - - - " - - ^ - - - - - - - - - - - - ' - - - - - - - - - - - - " - ~ ~ - ~ - ~ - " - - - ~ - - - - ~ ~

12. Environmental Management and Research Programs 131 affected approximately 8.3% of the fish eggs and lar-benefits from the large fish population of Par Pond vae that drified past the intakes in 1984, and 12.1%

and the protective nature of the SRP reservation.

in 1985. Because natural mortality rates of fish eggs and larvae are high, the entrainmentlosses had no The American alligator, listed as an endangered apparent adverse efTects on the Savannah River species during the CCWS period and subsequently fishery.

downgraded to

threatened by similarity of appear-ance,"is found on the SRP site, predominantly in the Overall, the CCWS determined that reactor opera-Beaver Dam Creek delta, Par Pond, and the Steel tions have no adverse impact on the Par Pond Creek area. Although elevated temperatures re-system. The flora and fauna continue to flourish, strict use of portions of thermal streams, the mildly and communities remain diverse, balanced, and thermal habitats promote alligator use in winter representative of the region.

months.

Four threatened or endangered species use areas Almost every SRP body of water serves as a water-that could be affected by SRP cooling water with-fowl habitat. During the CCWS period, midwinter drawal or release. Shortnose sturgeon spawn in the waterfowl numbers increased 73% on the SRP site, Savannah River near the SRP. This species has not while th ey decreased 33% in th e Atlantic flyway and been found in impingement or entrainment collec-70% in South Carolina. These trends indicate tions at the SRP cooling water intakes, and physical the importance of SRP as a waterfowl wintering properties of the shortnose sturgeon make impinge-refuge area.

ment or entrainment unlikely.

Wood storks from a colony near Millen, GA forage Protection on the SRP site, primarily in the Steel Creek delta and Beaver Dam Creek. IIigh cooling water eft 1uent Waste Management and Groundwater Protec-flows probably limit wood stork use of the SRP site, tion Environmental Impact Statement. An but replacement foraging sites constructed at Kath-environmental impact statement (EIS) on waste 4

wood Lake provide substantial new habitat for wood management activities for groundwater protection storks and more than compensate for foraging sites at SRP has been prepared and was issued in Decem-lost after the L-Reactor restart.

ber 1987. The three issues addressed in the EIS are (1) closure of waste disposal sites,(2) construction of Bald eagle sightings at SRP have increased over the new waste management facilities for low-level ra-last decade. The eagles are seen primarily on the Par dioactive and hazardous materials, and (3) disposal Pond system, L Lake, and the Savannah River of tritiated waste water. Technical support on the swamp, and one pair nested south of Par Pond in environmental analyses of waste-site closure op-1986 and 1987. The pair fledged two juveniles suc-tions has been provided by the SRL Environmental cessfully in both years. The bald eagle probably Sciences and Environmental Technology Divisions.

A total of 77 waste sites at 45 distinct geo-graphical locations around SRP were ana-y lyzed for impacts on human health and the p.

i M;

s ecology resulting from postulated closure actions.

Twenty six environmentalinformation docu-

^ -

ments (EID) encompassing the 77 waste sites fj),/f, have been completed. These EIDs describe the

~

waste disposal sites at SRP and contain de-tailed evaluations of the closure options con-sidered for each site. Each document de-scribes the nature of the waste deposited at the site, discusses the geohydrologic setting, defines the waste site characteristics,identi.

SitP is home to American alligator

132 SAVANNAH RIVER PLANT - Environmental Report for 1987 the impacts to human health and the environment previously obtained data were examined. Existing for postulated options identified. Five supple men tal data and environmental standards for soil and documents describe geochemical parameters, waste groundwater concentrations were compared to de-inventories, health effects parameters, modeling termine whether additional data would be required.

methodologies, and quality assurance reviews asso-If additional information for a site was required, ciated with this environmental analysis.

strategies for collecting samples for chemical and physical parameters were specified. For several The results of the environmental analysis of waste waste sites for which characterization activities disposal sites at SRPindicate that the risk to human have already been conducted and the data for devel-health and the ecology is quite low. For many sites, oping acceptable c!csure plans exist, no further no remedial action is needed. For others, back611ing action is recommended. For tr% sitea. miditional and capping the waste site previde the required pro-characterization is recommended using soil gas tection. At one site and possibly two, removal of the surveys, ground penetrating radar, soil samples, waste may be required to reduce the calculated risk groundwater monitoring wells, and geologic bor-to the human population.

ings. Over 200 soil cores to nominal depths of 3 to 6 m are ecommended. Installation ofover 100 Waste Site Characterization. SRP is required to groundwater monitoring wells, mostly to the water close all waste sites in a manner consiet with table,is suggested. Use orground penetrating radar protecting human health and the enviNnmens and to define backfilled waste site boundaries is speci.

complying with applicable enviramental regula-fied for 26 individual waste sites. Soil gas su rveys fo r I

tions. The first step in this closure procedure is to the presence ofvolatile organic materials are recom-develop waste site characterization requirements.

mended at 17 speciGc waste sites.These recommen-These requirements are based on technical consid-dations will provide the basis for collecting the erations and speciGeations for RCRA and CERCIA data necessary to develop closure plans for all SRP facility investigations developed by the EPA.

waste sites.

Recommendations for characterizing all waste dis-Soil Cleanup by Vacuum Extraction. In situ posal sites at SRP have been developed. A total of vacuum extraction has been shown to remove sig.

166 individual waste sites were evaluated according niGeant amounts of trichloroethylene and tetrachlo-i to th e type ofwaste deposited. Ilistoricai records and roethylene from the vadose zone (the zone of soil I

located above the permanent water table) of SRP soils contaminated with these solvents. In a pilot study conducted in M Area, almost 1,500 pounds of solvent was removed over a three week test period.

"~

Three parallel efTorts to further develop and apply vacuum extraction technolo-e

.~

4,. -

gies at SRP are planned. These include research studies to determine Dow rates l

of gases in the vadose zone during vac-

]

t. [4[' t "

uum extraction and the dagrec of removal l

of volatile organic compounds (VOCs),

AR i

W field tests using horizontal wells to dem-kM 5 fpi

[p. -W p.h[fI b,

y onstrate vacuu m extraction of VOCs from c

5 7 a s

/F w

the adose zone alone and in combination hkh bh?%..

J$dirn

{hQd with injection of air into the underlying M4 M E M 9* [ [ % c,.

7:p groundwater, and full-scale application M.chhD W/$U MM)/M$?MfM [Td of vacuum extraction to remove VOCs N A h 'I 5h4 from the vadose zone in a facility to be Nhi.@~.li bM..~h h

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, w 1p. n Q

, " @"' Q constructed near Outfall A 14. Applica-tions are being prepared for permits re-quired by SCDilEC for these activities.

Cluster of groundwater monitoring wells

12. Environmental Management and Research Programs 133 1

Baseline Hydrogeologic Investigation. The withdrawal of Black Creek-hiiddendorf water, and SRP Baseline Hydrogeologic Investigation for pro-collection of additional water-level data.

viding hydrogeologie data over the entire site was completed in 1987. This is the first program at SRP Groundwater Flow 51odeling Program. Devel-to obtain continuous geologic cores of the unconsoli-opment of a validated, documented regional three-dated Coastal Plain sediments underlying the plant dimensional flow model that simulates the ground-from the ground surface through the 51iddendorf water flow system at SRP continued in 1987. The Formation (formerly called the lower Tuscaloosa model is being developed to provide a hydrologic Aquifer).

management tool that allows assessment of onsite and offsite impacts of pumpago and that can be Eighteen clusters of observation wells were in-coupled with a transport simulator to consider con-stalled at key locations across the plant site to pro-vective, dispersive, adsorptive, and decay processes.

vide detailed information on lithology, stratigraphy, and groundwater hydrology. These observation The general approach used in modeling the regional wells also provided the means to monitor groundwa-groundwater consists of three main phases: system ter quality, hydraulic head relation sips. gradients, conceptualization, model calibration, and simula-and now paths. In all, a total of 129 wells were tion. Preliminary calibration of the model for a installed in accordance with SCDHEC regulations.

region of SRP was completed in 1987. The model is The program was divided into th ree phases. Phase I, now being compared with other numerical models.

completed in 198 4, included installation of 20 obser-Calibration of the model for the entire SRP site is vation wells at three cluster sites. Phase II, com-expected to be completed in 1988. Upon completion, pleted in 1985, comprised in stallation of 56 observa-this program will provide a management tool for tion wells at eight cluster sites. Phase III, completed assessing alternative uses ofgroundwater resources in 1987, included in stallation of 53 cbservation wells at SRP.

at seven cluster sites. Phase I and Phase II concen-trated on collection ofdata from areas of the SRP site Use of Herbicide Impregnated Polymer 5fa-for which little or no data previously existed. Phase trix to Exclude Plant Roots from Buried l

Ill was designed to supplement data gaps and pro-Waste. Radionuclides and some toxic wastes can j

vide observation points for the major groundwater move from burial in the ground to the surface i

2 I

extraction areas of the plant. The program estab-th rough uptak e by plant roots. Roots h ave the poten.

lished a high quality geologic and hydrogeologic tial not only to remove waste but also to penetrate database for the site where all of the data have been physical barriers and disrupt the waste contain-consistently collected and evaluated.

ment systems. Since living roots have been found at more than 100 ft below the surface, there has been Water level measurements from this program have a great dea' of interest in systems to limit root i

been used to construct an updated map of the head growth. The herbicide tri0uralin (Treflan)is a root reversal across the Ellenton Formation which sepa-retardant (prevents roots from penetrating the soil rates the Black Creek 41iddendorf and Congaree layer). Because it is biodegradable, trifluralin alone i

Formations beneath SRP. The reversal should pro-is undesirable for long-term exclusion of roots. Re.

vido a barrier to water Gow into the Black Creek-search scientists at Batelle Northwest Laboratories hiiddendorf Formations from overlying sediments.

have overcome this problem by incorporating trinu-A head reversalis the presence of a higher pressure ralin in a slow release matrix and bonding the below a confining unit than above, creating the matrix to the geofabric material Typar* for ease potential for upward now. Since the early days of of handling.

l l:

SRP operation, a head reversal was thought to exist over much of the plant area. This condition does not Several characteristics make the bonding of triflu-occur in the N31 Area and the east-central zone of ralin and Typar* promising for use in waste sites.

th e site. Continued work on this program will assure Trifluralin is released at a rate that should keep it that future plant operations, such as new produc-active for a s long as 100 years. Becau se tri0uralin is tion wells and increased pumping from the Black biodegradable a nd adheres strongly to soil, the zone Creek 4tiddendorf Formations, do not adversely of action is about 4 in below the retardantlayer and l

afTect the head reversal. These tasks include nu-tri0uralin is not transported to the groundwater.

merical modeling, the search for alternatives to Tri0uralin retards root growth,butis not a systemic

]

i

134 SAVANNAH RIVER PLANT - Environmental Report for 1987 herbicide and will not kill plants growing above the the recirculating towers counterbalanced the retardant layer. The last characteristic is impor-greater stream a rea available with the once through tant, since vegetation is often used to stabilize the tower.

overburden of waste sites.

Five infarmation documents were aise developed by The root retardant system is being manufactured by SRL to support the ACWS FEIS. Four of these Reemay, Inc. of Old Hickory, TN. Because of its documents addressed the potential environmental potential as a barrier to root penetration into radio-impacts of recirculating and once-through cooling active and/or h azardous waste, SRL and SREL have towers for C and K Reactors.Studiesindicated that begun a series of tests of the root barrier in the SRE L both cooling tower options would significantly re-rhizotron. The rhizotron facility is designed to study duce the temperature ofcooling water discharged to root growth by visually in specting the roots through site streams, thereby improving conditions for specially constructed soil-filled cells with glass in-aquatic life. Recirculating towers would also reduce spection portals. A number -f conGgurations of the peak efiluent Cows to about 7% of the present vol-root barrier (horizontal, vertical, and stair stepped) ume. Similarly, recirculating towers would dampen have be(n placed in the soil to see the reaction of the Dow Quetuations induced by reactor cycles, roots growing around edges and in corners. Two con sequen tly enhancing fish spawning and alligator vegetation types have been used, soybean and Ber-nesting in the stream corridors and wood stork muda grass. Results to date indicate that the root foraging in the deltas.

barrier is functioning and th e roots are not penet rat-ing the material. However, the roots are growing The fifth information document assessed effects of around and about 6 in under the barrier.This means the "increa sed flow and mixing" thermal mitigation an effective root barrier will have to surround the alternative for the D-Area power plant. Studies volume of soil from which roots are to be excluded.

indicated that the additional water pumped to the powe rhouse during extreme sum mer weath er condi-tions would keep discharge temperatures below the Activities Supporting Alternative Cooling 90*F limit. However, the environmental benents Water Systeins Environmental Impact obtained by the reduced temperatures might be Statement. Several activities were performed in offset by increased and fluctuating flows.

support of the Alternative Cooling Water Systems (ACWS) Final Environmental Impact Statement I

(FEIS). In one, the potential effects on wildlife asso-NATIONAL ENVIRON 51 ENTAL RESEAllCH ciated with the proposed cooling water alternatives l' ARK l'H OGitA51 for C and K Reactors and D Area power plant were evaluated using a liabitat Evaluation Procedures Under the National Environmental Research Park (HEP) assessment. (The HEP analysis was devel-(NERP) program, scientific investigators from uni-oped by the U. S. Fish and Wildlife Service (US FWS) versities and other organizations are encoaraged to and modified by SRL for the SRP environment.)

use the S RP site a s an outdoor laboratory for studies of the environmental impact of man's activities.

I The potential wildlife impacts and benefits of once.

Since the site was designated as the nation's first through and recirculating cooling towers located at NERPin 1972, many visiting scientists have worked C-and K-Reactors were evaluated for n ear-term (30-there in cooperation with SRL, the Savannah River year) and long term (100 year) periods. Results Ecology Laboratory, and the Savannah River Forest from these analyses were compared with the pro.

Station.

jected effects of current reactor operations. For the representative wildlife species selected, H EP analy.

During 1987, approximately 15 NERP program sis results showed that both the once through and research projects were conducted, with baseline the recirculating cooling tower designs would im-studies providing information on the variability of prove overall aquatic habitat suitability by substan-plant and animal communities. The site was sur-tially reducing water tem peratures from the present veyed for plants listed by state or federal agencies as conditions. Neither cooling tower design could be endange red, th reate n ed, or ofspecial con cern. Oth er clearly identified as the best thermal mitigation scientists surveyed soil organisms, shallow pond alte rnative; the lower tem peratures a ssociated with protozoa, stream insects and forest vines.

12. Environmental Management and Research Programs 135 Many of the SRP studies started in 1987 are SAVANNAH RIVER ECOLOGY comparative, as is apparent from the following LABORATORY PROGRAMS

, examples:

1 m Wetland bacteria of the Okefenokee Swamp Division of Biogeochemical Ecology (Georgia and Florida) are being compared with bacterin of thermally-impacted swamps at SRP.

Environmental Chemistry of Sodium Tetraphenylboron.The Savannah River Ecology E Th e feeding behavior of wadin g birds at S RP an d Laboratory (SREL) has conducted research for the of those at the Okefenokee and the Belle Baruch past several years on understanding the emiron-Long Term Ecologic Research Site at North mental chemistry of sodium tetraphenylboron Inlet, SC,is being compared.

(NaTPB), an organo-borate compound that will be used in the new Defense Waste Processing Facility E A regional study offorested wetlands of the Gulf (DWPF) to precipitate radiocesium from high level and Atlantic Coastal Plains is examining com-nuclear wastes.

j munity structure, factors controlling productiv-ity, and stress responses. Similar data are being In general, the mobility and fate of nonvolatile taken at SRP.

organic compounds in soil and aquatic environ-ments are largely determined by sorption and degra-E The cesium binding capacities of SRP, Los dation reactions. Previous research has shown that Alamos, and Bikini Atoll soils are being tetraphenylboron degrades in the soil to form compared.

diphenylborinic acid and biphenyl as initial degra-dation products. Other research has shown that tetraphenylboron is not readily degraded by microorganisms.1)ur-ing the past year, the effects of vari-j ous abiotic soil parameters on the degradation rate ofTPB were exam-ined. These studies showed that the reaction tales are inversely re-lated to soil water content and J..

~

k directly related to humic acid i

3-i

~ e concentration.

1 Hiogeochemical Cycling in L Lake. Microcosm studies were con-

~

ducted to investigate the inGuence s

A ofoxidation reduction status on the

~

potential remobilization of metals I

+

and nutrients from L-12ke sedi-

' ~ ~

ments. Previoua research indicated j

Wood storks nesting at rookery near Millen, GA that only iron and manganese con-centrations were probably high I

Two highlights of the 1987 NERP program were:

enough to present a toxicological threat from remo-bilization.

E A NERP-sponsored SRP meeting at which sci-entists from across the country learned about Efrorts during the pastyear focused on determining opportunities to study microorganisms found in the bioavailable fractions of the totaliron and man-the sedimentary rocks hundreds of feet beneath ganese present, as well as the mobilization poten-the SRP.

tials of these two metals in L Lake sediments.Under reducing conditions of -150 mV, all labile manga.

E A workshop held on the ecology and conserva-nese fraction s were mobilized aRer 72 hr, while only 1

tion of storks to share the results of SRl' re.

6% of the labile iron was released aner 75 hr. The search activities.

results suggest that during conditions comparable

136 SAVANNAH RIVER PLANT - Environmental Report for 1987 to those occurring in the anoxic hypolimnion of L The solubility and movement of selenium in soils Lake, there is a potential for rapid and complete and waters are closely associated with the chemical mobilization of labile manganese fractions. Addi-species in solution. The major factors controlling tional data are being collected to calculate potential these chemical species are the redox potential and ranges of iren and manganese concentrations re.

pl!. At high redox potential, selenate (SeO 8-)is the sulting from remobilization processes under vary-predominant species. At moderate redox, both bise-ing redox conditions.

lenite (IISeOS-) and selenite (SeO 8-) are important.

3 At low redox conditions, mono-hydrogen selenide Separate field and laboratory studies have focused (hse-)is the most important species, on the bacterial processes involved in dissimilation of the particulate and dissolved organic matter from Statistical Variance in Mercury Coneentra.

blue-green algal blooms, and from vascular plant-tions of Fish. Research was initiated to define the derived lignocellulosic detritus. This research in.

variance structure for mercury concentrations vol"ed following the rates of degradation of radiola-within a dominant fish species population, the belled organic matter prepared to be similar to that dusky shiner (Notropis cummingsae), in Upper in the lake itself. Results have shown that, although Three Runs Creek. A nested analysis of variance reactor operations may increase rates of primary was used to define the structure of variance within production, there does not appear to be a consequent the mainstream of Upper Three Runs Creek.

accumulation of organic matter, owing to the Sources ofvariance were reaches within the stream, adaptability of the degrative microbial community sites within each reach, schools within sites, and in L Lake to the higher temperatures.

sample error. After size normalization of mercury l

concentrations, only mean s between stream reaches j

Diogeechemical Cycling in Pond B. To under-were identified as significantly different. Baseline 4

stand the long term efTects of radionuclide contami-data were collected prior to the introduction of natian in an aquatic ecosystem, SREL has been mercury to Upper Three Runs Creek from the pro-studying the aquatic chemistry, aquatic macro-posed F/II Area Efnuent Treatment Facility. The phytes, benthic invertebrates and waterfowl of the results provide a statistical benchmark for similar i

Pond B reservoir. Recent research has focused on surveys aRer facility operations begin.

i determining radiocesium levels in various biotic components of the reservoir. Results indicate that Division of Stress and Wildlife Ecology i

less than 0.6% of the totalinventory of radiocesium I

in Pond B is found in the biota. Approximately 99%

Life Illstory Patterns of Mosquitofish (Gam-I of the radiocesium is found in the sedhnents, with busia affinis) in Thermal and Ambient i

the remainder being in the water column. Of the Environments. Reproductive patterns of mosqui.

radiocesium found in the biota, over 99% is incorpo-tofish (Gambusia affinis) from both ambient and rated into the biomass of the macrophytes.

thermally stressed habitats on the Savannah River Plant were compared to determine short term evo-Hiogeochemistry of D Area Coal Pile and Ash lutionary changes imposed by thermal stress. Previ.

l Basins. Recent research has focused on under-ous studies of thermally stressed ecosystems have standing the chemical speciation, solubility and demonstrated profound efTects of elevated tempera-mobility of selenium, a potential contaminant of ture on community attributes such as species diver-soils and groundwater th at can be released from coal sity, biomass, and general condition. Such changes piles and runofTbasins. Thermodynamic data were would in turn afTect community structure. Somatic used to develop equilibrium reactions and constants and reproductive data were analyzed from monthly for 83 selenium minerals and solution species that samples at each location. The two populations were may be present in soils, surface waters, and ground-significantly difTerent in annual reproductive cycle, water.Studiesof thesolubilitiesof17 metal selenite fecundity and somatic condition (Fig.121, Vol. II).

minerals suggest that manganese selenite is the Other studies have demonstrated genetic differ-only selenite mineral that might persist in strongly enees between thermal and ambient populations of acid soils, such as those that occur on the SRP site.

mosquitofish, implying a possible genetic basis for Of the 17 metal selenides, cuprous selenide is the life history differences (Fig.12-2, Vol. II). Further most stable mineralin acid soils.

research should emphasize genetic versus

i 1

12. Environmental Management and Research Programs 137 environmental components of life history differ-peripheral to the construction area and is conduct-ences in these populations to determine if thermal ing an experiment in them. Lata from the experi-stress has resulted in evolutionary change of life ment suggest that interactions among hydroperiod, history characters.

predation, and competition may be important deter-minants of amphibian reproductive success at these Effects of Overhead Forest Canopy on Leaf sites. Salamanders first colonized the refuge ponds Decomposition Dynamics in an SRP Hlackwa-in appreciable numbers during FY 1986 and FY ter Stream. EfTects of overhead forest canopy on 1987 (Table 12-1, Vol. H). Two species, the red-rates ofleafbreakdown were estimated in regions of spotted newt, Notophthalmus viridescens, and the open and closed forest canopy on a second-order S RP mole salamander, A. talpoideum, have established coastal plain stream (Tinker Creek). Six sets ofleaf breeding populations at the refuge ponds. Nearly packs placed in each habitat over a period ofone year half of the A. talpoideum that have entered the showed difTerences in the rates of decomposition refuge ponds to breed have been marked animals that were linked to riparian characteristics, from Sun Bay. Mole salamanders normally return to temperature, and macroinvertebrate community the site where they were born to breed; however, structure. Leaf decomposition was faster in the some individuals of these species responded to the closed canopy habitat than in the open canopy habi-elimination of Sun Bay and other construction dis-tat. Microbial processing was similar between habi-turbances by migrating to the refuge ponds.

tat types, accounting for approximately 30 to 40%

loss of dry weight. Observed differences between open and closed habitats were apparently the result DWPF Peripheral Stream Water Quality Stud-of macroinvertebrate processing. Since leaf packs les. Mean total suspended solids (TSS) levels in are temporary resources that function as both food McQueen Branch (one of the main creeks draining resource and habitats,it was anticipated that micro-the DWPF site) increased for FY 1987, but not i

bial and macroinvertebrate responses should vary significantly. Other streams showed a mixture of th rough time. Temporal difTerences in rates of proc-nonsignificant increases and decreases in TSS con.

essing were related to changes in water tempera.

centrations for FY 1987. Rainfall one day prior to ture. They were also affected by changes in macroin-sampling was two times greater in FY 1987 than in vertebrate population and community structure FY 1986, which may account for some of the in-within and between sets ofleaf packs.

creases in TSS. McQueen Branch showed a nonsig-nificantincrease in turbidity in FY 1987,while other Natural Variation in Stream and Wetland streams showed a mixture of nonsignificant in.

Ecosystems and the Effects of Defense Waste creases and decreases in turbidity. TSS loadings for Processing Facility (DWPF) Construction.

McQueen Branch (construction impacted stream) 1 Density manipulations of marbled salamander lar-were higher than Tinker Creek (unimpacted l

vae in field pens within a Carolina bay revealed that stream) for both FY 1986 and FY 1987. For both larval density may affect a suite oflarval characters.

years, TSS loading rates were not statistically dif-Individuals in low-density pens grew faster, at.

ferent either within or among streams, i

tained larger body size at metamorphosis, and ex.

hibited higher survival. These density dependent For FY 1987 (as in past years), there were indica-efTects were consistent during FY 1986 and FY 1987.

tions that during periods of rainfall, inputs from However, the density efTects can be mediated by McQueen Branch were suflicient to increase (in one abiotic factors, presumably hydroperiod, as was case slightly for FY 1987) the TSS levels in Upper evident by significant year efTects. This research Three Runs Creek below its confluence with illustrates that intraspecific interactions in the lar-McQueen Franch. Two TSS increases associated val environment can affect adult characters related with McQueen Branch were observed in Upper to fitness (e.g. body size and fecundity) and ulti.

Three Runs Creek for FY 1987 and were supported mately the populatien dynamics of amphibians that by similar increases in turbidity levels, specific breed in SRP wetlands.

conductance, and percent ash weight data. The combined TSS loadings from Tinker Creek and The construction of the DWPF eliminated a McQueen Branch appear to account for six other l

1 hectare Carolina bay (Sun Bay).To partially miti-times during FY 1987 when in creases were observed i

gate the efTects of the loss of the bay, SREL con.

in Upper Three Runs Creek below the confluences of j

structed three artificial refuge or breeding ponds Tinker and McQueen.

1 4

138 SAVANNAH RIVER PLANT -- Environmental Report for 1987 Crouch Branch is a second creek draining the DWPF S. odoratus BP of soma and eggs were approxi-l site. Mean TSS concentrations obscrved in Crouch mately equal. Biomass production of eggs repre-i Branch were signincantly higher than those in all sen ted approximately 20% of the total production by other streams for FY 1987 for five of the 12 months.

all six species in Ellenton Bay.

Crouch Branch appears to have increased (in some cases slightly) the TSS load in Upper Three Runs Mature populations are generally thought to have Creek for five of the 12 months in FY 1987. Data for high standing crop biomass relative to biomass turbidit,, specific conductance, and percent ash production rates. Turtles seem to follow this pattern weight, all support these five observed TSS concen-as the ratio of total BP to SCB for Ellenton Bay is tration increases.

0.13. BP to SCB rates for primary producers range from 25 to 42 in aquatic habitats and from 0.4 to 0.65 Flow Cytometric Analysis of the Effects of in terrestrial com munities. If th e total prima ry BPor Low level Radiation Exposure on Natural wetland habitats averages 2,500 g/m'/ year, then Populations of Slider Turtles (Pseudemys total BP orthe entire turtle communities represents scripta). Aquatic turtles inhabiting seepage basins 3.88 x 102% at Ellenton Bay.

that contain low concentrations of radioactive and nonradioactive contaminants possess significantly UP of eggs compared to soma is high within turtle greater variatien in DNA content in blood cells than populations, presumably because turtles are rela-turtles from a control population. This variation, tively long-lived animals and growth rates of older measured on a flow cytometer as the coefUcient of individuals are very low. BP ratios of eggs to soma variation of the cells in G1 of the cell cycle, is ranged from 0.18 to 1.0 nmong the six turtle species positively correlated with plastron length and esti-from Ellenton Bay. Although these figu res are rough mated age of the turtles. M ultiple peaks indicative of estimates calculated from cumulative data that do aneupleid mosaicism (a condition in which distinct not reveal annual variability, they provide evidence "populations"ofeells contain substantially different that the proportion of total BP resulting from turtle amounts of nuclear DNA) aise were observed. It is egg production can be relatively high in freshwater concluded that radiation or some unidentified wetland habitats.

chemical in the seepage basins likely acts as a clastogenic agent that causes chromosomal rear.

Wood Storks at Kathwood Artificial Fornging rangements leading to deletions and duplications Ponds. The United States breeding population of that have the efTect of increasing DNA content wood storks (Mycertia americana) has decreased variation in bhiod cells. The proliferation of a mu-over the last 30 years, and in 1984 the U. S. Fish and tant cell line leads to aneuploid mosaicism and Wildlife Service listed that population as endan-the observation of multiple peaks in the DNA gered. The decrease in numbers han been attributed histograms.

largely to loss of foraging habitat. When DOE de-cided to restart the IcReactor at the Savannah River liiomass Productivity of Turtles in Freshwn-ter Wetlands. Adults of six turtle species examined at Ellenton Bay ranged from 93 to 264 mm in

_1 f f,.

s maximum plastron length and from 298 to 10,000 g

.h w

A"W in maximum body mass (Table 12 2, Vol. II). The

- W'MNedh ratio of the minim'um to maximum plastron lengths

~N and body masses of adult turtles among the six 1

[g

^ %%

species in Ellenton Bay were approximately 3 and hWf% " ' A- --q^

j%

35, respectively. Standing crop biomass (SCB) and Qgc hQ7 -

hiomass production (BP) of soma and eggs were QN -cV em y

highest in T. scripta, the numerically dominant b

species, and lowest for S. odoratus, a species of M' P C - N A $n7ft

.a, small bodied individuals occurring at low densities MTJ Q @Wh in this location. The second highest SCB and HP M

~?. y were found in C. eerpentina, large bodied turtles

%M that occur at r/ stwely low densities and produce M'

large clutches of e,as. For most species HP of soma greater than that of eggs. Ilowever, for Wood storks foraging at Kathwood I ake was

12. Environmental Management and Research Programs 139 total variation in mass and composition of eggs (Fig.12-4, Vol. II). Body mass of hens du ring early incubation was correlated with sq

d estimates of pre-egg laying lipid reserves

.E%'*""%

(r, = 0.66); therefore, body mass was a good Gma

- as-a measure of female quality. Body mass of y.-.-

feds was independent of age and struc-j- @ g;g gE& w !1 m rw nr.aaame_ggMA tural size and was positively related to a

g

==m mean egg mass, egg composition, energy

-.~,.m- ~. g 7 7pg' T. 4[ [jl[ [ g

%(Q content of eggs (kJ/g), and clutch mass, but not to clutch size of time of nesting Female

'!,}

/b-j body mass explained more variation in al-Q%$

bumen components than in yolk or shell

.? M "'

components. These results support Drobney's (1980) hypothesis that prebreed-ing conditions of female wood ducks is important because it allows hens to accu.

Kathwood Lake mulate exogenou s protein for egg synthesis.

Plant, there was concern that reactor cooling water The data do not support predictions based on opti-would increase the water level in the Steel Creek mal egg size theory.

delta and make this area unavailable to wood storks that nest in a rookery near Millen, GA, and fly to The body mass of ducklings averaged 23.7 g(n = 43);

SRP to feed on fish. To replace the potentially lost there were no intersexual differences in mass or foraging habitat, DOE created 14 hectares of ponds composition. Ducklings contained 65.91 water and at the site of Kathwood Lake on the National 32.57 lipids (dry masst Components of ducklings Audubon Society's Silver Bluff Plantation Sanctu-increased in direct proportion to fresh egg mass,but ary in 1%5 These ponds were stocked with aquatic egg mass was a poor predictor of duckling lipid prey and managed specifically for wood storks.

con te n t.

DOE is providing research funds to SREL to assure Factors Affecting l'roductivity of a White-continued availability of adequate forage for this Tailed Deer lierd. Reproductive and demographic endangered species. In 1986, wood storks foraged on data on female white tailed deer (Odocoilcus rir-the ponds for over two months and 97 storks were ginianus) were collected from 1965 to 1984. Inten-ccunted feeding at one time; this number increased sive either-sex hunting has resulted in a shin to-to 150 in 1987. The pattern 3 of numbers of storks at wards a younger age structure in the herd. Mean the pondsin 1986(Fig.12 3,Vol. ID suggest that the fetal number va rie.s according to female age artificial ponds do indeed present a ppropriate forag-(0.5< 1.5<2.5<3 5 or greater years). Does of all age ing habitat. In the future it is hoped that fish clas es have significantly low er fetal numbers in the reproduction will make restocking unnecessary as swa mp than in the upla nds, but th ere is little an nual the ponds become self-sustaining; however, as a variation in mean fetal number (Table 12 3,Vol. lit precautionary measure the ponds were stocked with Conception dates for fawns are significantly later 64h in early 1987 and 1988.

than those of older females. Mean conception date for all females on the site has remained relatively constant over time at November 20 : 3.4 days with Factors Affecting Variation in the Egg and no significant h abitat difference s. The percentage of Duckling Components of Wood Ducks Three breeding fawns varies from 16 to 697 from year to eggs from each of 35 female wood ducks (Aix s/mnsa) year with an average of 391 (Table 12 4, Vol. lit were collected. Fresh egg mass averaged 41.2 g and There was also significant temporal variation in consisted of 53.19 albumen,36Ei yolk, and 9.67 fawn breeding between habitat types. The overall shell. Albumen and yolk contained 56.27 and 41.9'i productivity of the herd has remained essentialiy wator, respectively. I,ipids comprised 65.1G of the constant at 126 fetuses per 100 does of any age. The dry yolk. All egg components except dry albumen relative con sistency of th e reproductive rate is main.

increased in direct proportion to fresh egg mass.

tained in both the swamp and upland habitats but at Variation among females explained 52 to 807 of the difTe rent levels.

4

-m m.y

,_,,_._._...c

--,,._,.__,r

140 SAVANNAH RIVER PLANT - Environmental Report for 1987 l

l seedlings. Factors that have modified Goodplain hy.

l I

drology, such as cooling water discharge from SitP h

reactors and upstream control of Savannah Itiver

+

1 l I. -

tupelo regeneration in the Goodplain forest.

6 flows, may effectively limit bald cypress and water I

l 3

k" Using I'lants, Soils, Soll Chemistry and Flood-ing llegime to Delineate a Wetland lloundary, J

s 3

SitEL and Louisiana State University are involved in a cooperative research effort to understand the

' a complex relationships between Gooding, wetland

.d plants and wetland soils. This work is of consider.

As L.

/

able interest to wetland managers and scientists i

6 f

I concerned with deliner. tion of wetland boundaries g

as required by the Clean Water Act Section 404.

+

Transects were established on the SIIP which repre-sent a wide range in Gooding frequency. Probes and wells were installed at sites along each transect and i:

used to monitor flooding depth, soil oxygen content 4

(,

j' and soil reduction / oxidation (redox) potential. Soils

/

at each site were classined, and plant communities s'

were described using sampling plots.

Flooding in the rooting zone ollen caused anoxic conditions to develop, llowever, soils did remain i

i acrobic when saturated for short periods of time. All l

the sites that were flooded in the rooting zone during liald cypress measured for ecology studies the growing season had hydrie soils, llowever, one

.3.

f i

site with hydrie soils was not Gooded during the 4

Division of Wetlands Ecology growing season because of altered hydrology.

Dynamies of Wetland Forest Species.The popu-Most sites were dominated by facultative wetland lation dynamics of bald cypress (Taxodium disti.

species, llecause facultative species are as likely to chum) and water tupelo (Nyssa aquatica) and the occur in nonwetlands as in wetlands, the vegetation potential regeneration of these forests on th e Savan-on these sites wouhl not be useful for delineating a nah ]{iver Goodplain near SitP are induenced by boundary. Identincation of soils would have been changes in the hydrologie regime. SitEL studies reouired in most cases. Army Corps of Engineers' 1

show that the production and dis;:ersal of viable

...ethods for wetland delineatinn would have cor-seeds difTer between the species and between years.

rectly identined soils at 90% of the sites assuming l

Seed viability is generally low in bald cypress (7 to fiehl personnel were properly trained in soil identi-1 14"r viable) and higher in w ater tupelo (40 to 50"r).

fication.

Once shed from the trees during the late fall and j

winter months, seeds are dispersed by water and G rowth and i'hotosynthesis in Chinese Tallow may he moved great distances by winter and early Tree, American Sycamore, and Cherrybark

!l spring floods. En'ergent structures such as stumps, Oak Seedlings Subjected to Different Light logs,and tree bases are criticalin trapping the seeds itegimes. Net photosynthesis and dry weight pro-of these species and in providing safe sites for duction were measured for 0rst year seedlings of the germination and seedling establishment. Extensive exotic Chinese tallow tree (Sapium schiferum) and inundation of the Goodplain decreases this seed two native bottomland hardwoods, American syca-trapping and reduces availability of microsites for more (Platanus occidentalis) and cherryhark oak seedling establishment. Floods during the growing (Quercus falcata var. pagali/blia). Plants were season may additionally causc high mortality of t ree grown in M and 100"r full sunlight to simulate

)

i

12. Environmental Management and Research Programs 141 i

forest understory and open environments. In 3%

stations at the upper end ef the lake. U e cladocerun light, tallow tree exceeded sycamore and oak in net Diaphanosoma and the calanoid copepod Dicp-photosynthesis and dry-weight accumulation, while tomus dorsalis are major components of the zo-in full sunlight, both tallow tree and sycamore ex-oplankton community when blue-green algae domi-ceeded oak (Fig.12 5, Vol. II). Com pared to th e other nate the phytoplankton; other crustacean species, species, tallow tree allocated less dry weight to including Daphnia parvula, are important only leaves, more to stems, and an intermediate amount when the blue-greens are absent. The patterns to roots. These results show that the exotic species suggest a strong trophic component to the determi-may grow faster and regenerate better than co-nants of community composition. In addition to the occurring native bottomland hardwood species in ongoing analysis and modeling of the zooplankton select situations.

community, SRE L is begin nin g feedin g experi men ts to determine which food resources are used by the SRP Threatened and Ilare Plant Species. An major zooplankton species.

ongoing National Environmental Research Park (NERP) project hu located and identified 30 plant Revegetation of Steel Creek Corridor and species categorized by the federal and South Caro.

Delta. A survey of the vegetation in the Steel Creek lina governments as threatened or rare. Of these floodplain and delta, conducted 17 years after ther-plants, eight are candidate species possibly appro-mal discharges to Steel Creek ceased, demon strated priate for the proposed federallist. Of those listed by continued revegetation of this highly disturbed South Carolina, one is nationally threatened, three wetland system.There has been very limited regen-are regionally threatened, seven are threatened eration by bald cypress and water tupelo, co-domi-statewide, and 16 are considered rare (final status nants of the undisturbed swamp forest. Limited unresolved). About two thirds of these 30 plant establishment of other early successional hardwood species are associated with wetland habitats.

species (e.g., red maple, sweetgum) is evident near adjacent uplands. Much of the Steel Creek delta is Some results of the project aie:

still dominated by freshwater marsh and shrub communities (the latter comprised primarily of wil.

E Nine locations of a species new to SRP were low and buttonbush). The early stages of revegeta-found; tion resemble patterns ofold field succession in that E 34 new locations of plants already known to dominance proceeds from annual to perennial herbs occur on the SRP site were found; to shrubs. Because this system is unique, the final E DOE has begun to use the inventoried popu-stages of st:ccession (increasing dominance by trees) lations in the overall management of the SRP.

cannot be predicted; however, it appears unlikely that bald cypress or water tupelo will regain Some of the recommendations of the project are:

dominance.

E consider adding eight new sites to the pr o plant p es; E begin detailed studies on selected populations that have federal status, j

.'y\\ ;. -

N-Studies are beinginitiated to study the popula-

/

i 3e, 1'

/

.i tion dynamics of two of the federally listed i

M,,,.

q.' i,,..

,(,

plants: Echinacca lacrigata (Fig.12 6, Vol.

(,)t b

+

b' II) and Croton elliottii.

f.'p h '

['.

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l Zooplankton Community Development in

/

y.

+

-' \\

/

L Lake. SREL research to assess the efTects of y~[ h.

thermal stress and elevated nutrients on the 3

.uses.

zooplankton at L Lake continues, and the sam-pling program has been expanded to include Wetland vegetation established in L Lake l

142 SAVANNAH RIVER PLANT - Environmental Report for 1987 Establishment of Littoral / Wetland Vegeta-tion at L Lake. Littoral / wetland vegetation was

(

b established in L Lake during the period January-August 1987. Over 125,000 individuals repre-

~

senting over 50 species along 5400 m of shoreline g'

were either transplanted from Par Pond or ac-

~

quired from nurseries. In August 1987, vegeta-

' J c

I tion from planted and unplanted sites was f

sampled to (1) evaluate establishment success of the planted vegetation an d (2) compare the rate of k

vegetation establishment between planted and unplanted and planted areas was greatest in the

.i.

['

unplanted areas. Difference in coverage between emergent zone (9% and 32%). Submersed vegeta-tion was slow to become established and coverage in both areas was low (0% and 3%). Species which increased most in density following planting include Eleocharis equisetoides, 6.

L quadrangulata, Polygonum sp. and Typha latifo-lia. The planting project was successful in estab-o lishing diverse plant communities and wildlife habitat' Hald eagles find refuge at SItP U. S. FOllEST SEltVICE valuable for wildlife. Based on the prescriptions, SAVANNAH IllVElt FOltEST STATION timber sales are prepared an d the trees to be sold are

)

PIl O G ItA SIS marked.

Timber cut during 1987 brought the federal govern-Forest 31anagement ment nearly $2.3 million for 27 million board feet.

Cut-over land was reforested as soon as possible.

In response to the need for the DOE to make the best Before reforestation, the land was cleared by burn-use of public lands under its control, a program of ing, shearing and raking, drum chopping, c.r by forest management has been conducted on the 300 herbicide application. Pine seedlings were planted square miles of the SRP site since 1952. This pro-on over 2,200 acres during FY 1987.

gram is conducted through an interagency agree-ment with the U. S. Department of Agriculture On 560 of these acres, the Savannah River Forest Forest Service. In addition to producing timber, the Station (SRFS) planted longleaf pine. Although dif-forest management program contributes to enhanc-Ocult to grow, longleaf pine was the native pine of in g en viron m en tal diversity, p rotec tin g en dangered SRP sandhill h abitats and is preferred by the en dan-species, providing quality habitats for native wild-gered red cockaded woodpecker. Superior tree seed-life, protecting soil and watershed values, and pro-lings are needed for successful survival of planted viding a healthy forest for environmental research.

longleaf pines. The South Carolina Forestry Com-mission Nursery is under contract to DOE to use the Planning for forest management is enhanced by most advanced technologyidentiGed by U. S. Forest preparing timber compartment prescriptions for Service (USFS) researchers to grow seedlings for one-tenth of the forest area cach year. Prescriptions planting at the SRP in future years. The promising include a comprehensive collection of data required new technology is being closely watched by nu rsery-for vegetative manipulation, road main tenance, and men, the forest industry and regional tree farmers.

coordination with other programs. The DOE Site A workshop of the new techniques (sponsored by Use Approval system includes more than 800 activi-SRFS, the Southeastern Forest Experiment Station ties using SRP lan d for such program s as operation s (SEFFS), and the South Carolina Forestry Commis-and research. Data include timber stand types and sion) brought participants to the nursery and to condition, and inventories of areas especially planting demonstrations on SRP.

t

12. Environmental Management and Research Programs 143 SRFS thinned noncommercial stems on 200 acres all three pairs of red cockaded woodpeckers nested using heavy-duty brush saws to allow the remaining successfully. They produced seven fledglings, in-trees to produce more valuable timber. On more creasing the known SRP population to 14 birds.

than 700 acres, the competition of undesirable vegetation was reduced by application of selective liabitat was improved for the red cockaded wood-herbicides.

peckers on more than 300 acres of older pine forest by applying herbicide to weed out the competing Secondary roads used for the timber harvest are scrub oak. Prescribed burning of 222 acres had a being upgraded to handle the large trucks used for similar efTect. On more than 660 acres, noncommer-hauling tree length sawtimber and pulpwood. Dur-cial and commercial thinnin g opened up the longleaf ing FY 1987 nearly four miles of secondary roads pine forest to the parklike condition the bird prefers were upgraded. The road banks were seeded with for foraging and nesting.

plants that provide food for wildlife and control erosion. Routine road maintenance was performed Several wildlife species require control to protect i

on over 160 miles of roads, forests, roads, and research sites. During FY 1987, J

trapping contractors removed 170 wild hogs and 84 Under a continuing program of reclaiming eroding beavers from locations where they were causing land, approximately seven acres of bare areas were damage.

reshaped, subsoiled, and planted with legumes, grasses, hardwoods, and other wildlife food plants.

Prescribed burning of 4,300 acres stimulated i

I The plants also control erosion.The areas stabilized growth of vegetation on the forest floor for wildlife in 1986 were fertilized to improve their value for food. The cool burns conducted each winter under wildlife and erosion control.

carefully selected weather conditions also reduce 4

fuel on the forest floor to protect the forest against Endangered species receive special consideration as wildfires.The wet winter in 1987 limited prescribed i

forests are managed. Southern bald eagles returned burning opportunities. Fire danger was high during to SRP to nest in 1987. For the second year, two the spring and summer of 1987, but effective wild-eaglets were raised to fledging. A buffer zone estab.

fire suppression by Du Pont and USFS held 22 lished by SRFS prevented disturbance of the nesting wildfires to only 90 acres.

birds. The SRFS developed an eagle habitat man-agement plan to improve possible nesting sites for At DOE request, the USFS is writing a plan for long-other eagles.The plan will be used as a model for term management of natural resources at SRP. The Southern Forests.

plan will coordinate USFS activities with Du Pont activities outlined in the Environmental Implemen-The very small SRP population of endangered red tation Plan. During 1987, the USFS planners met cockaded woodpeckers is the subject of an intensive with the other organizations using the SRP site, research program testing the feasibility of translo.

They identified the various interests to be consid-i cating a few red cockaded woodpeckers to the SRP ered in the plan to be written in 1988.

forests to counteract possible inbreeding in the local 3

population. In 1987, SEFES scientists successfully The SRFS designed a walking trail that was con-i experimented with cross fostering chicks. Two structed to support the DOE wellness program. The chicks were removed from a nest at Francis Marion safe, attractive trail is available to the several thou-l National Forest, transported to SRP, and substi-sand workers in the Administratis e Area.

]

tuted for two chicks of the same age in an SRP nest.

The SRP chicks were then placed in the nest at The detailed mapping of SRP soils was completed Francis Marion Forest. All of the swapped chicks during 1987. The Soil Conservation Service stafron j-were accepted and reared by their foster parents, site described soils on about 16,000 a:res and com-1 This technique increases the genetie diversity of the pleted the maps and manuscript for the Soil Survey 1

i woodpecker population in both forests. Cavity com.

Report scheduled for publication in 1989. The soil i

petitors, such as flying squirrels, were removed from scientist also provided specific information needed the colonies. Artifical cavities, installed to make at SRP for plans for forest management, environ-i room for an increased population of woodpeckers, mental research, environmental assessment, and have yet to be used by the endangered birds. In 1987, facility siting.

I j

5

144 SAVANNAH RIVER PLANT - Environmental Report for 1987 i

Forest Management Research walnut were measured and the data analyzed. Re-sults were published in 14 research articles.

Units of SEFES are conducting numerous studies that are anticipated to improve the overall forest Five new studies were established in 1981. Pines management activities conducted at SRP.

grown from seed from a new seed onhidd of resis-tant trees are being exposed at SRP to the very Techniques for producing seedlings for more sue.

abundant fusiform rust in a field test. Anether study cessful reforestation are being tested at SRP.

examines the differences in sweetgum g-wn from j

seed collected from swamp trees compared to E Trees grow better if their feeder roots develop sweetgum with upland parents.

a symbiotic relationship with mycorrhizal fungi to facilitate absorption of water and in two large pine field studies, certslo common l

nutrients. Ifseedlings in the nursery beds are nursery practices, i.e. seedbed dentities and top innoculated with superior, selected fungi, pruning, are being studied to determine the effect of then field performance will be enhanced.

these practices on lateral root devel6pment and i

mycorrhizal development as they influence survival i

E Seedlings with more lateral roots show better and early growth. Another study will measure what field performance. Scientists use genetic se-effect removing pine straw frem the forest floor has lection to obtain families that have a higher on the growth and nutrition of the trees. lf there are l

percentage oflateral roots. Pruning the roots changes, the scientists will determine iffertilization in the nursery bed also improves root can compensate for the nutrients removed. Also in morphology.

1987, USFS administrators from Washington, D.C.,

Atlanta, GA, and Asheville, NC, favorably reviewed During 1987,27 field studies varying in age from one the cooperative research/ management program l

to 12 years and involving over 20,000 trees of at SRP.

longleaf pine, lobloll.v pine, sweetgum, and black 1

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12. Environmental Management and Rasearch Programs 145 1987 HIGHLIGHTS SRP Environmental Management Programs E A comprehensive SRP Environmental implementation Plan was completed and will be presented to Congress in 1988.

E A large and Intensive environmental audit of SRP by EPA revealed no major problems.

E in response to S AR A Title 111, SRP conducted a workshop tor local emergency planning com-missions and provided surrounding counties with 8000 MSDSs for chemicals and chemical prcducts.

E SRP received a five year RCRA Part B Permit for hazardous waste facilities from South Carolina Department of Health and Environmental Control (SCDHEC). A task team will perform RCRA Facility lnvestigations for 65 solid waste management units covered under the EPA portion of permit. The permit includes radioactive wastes jointly regulated by EPA and DOE.

E An Environmental Awareness / Training Coordinator was designated to promote employee commitment to protecting the environment.

E The SRP NEPA group reviewed P89 SRP/SRL activities for early consideration of environ-mental factors.

5 Two e nvironmentalimpact statements were issued: DOE /EIS-0120 (protection of groundwa-ter) and DOE /EIS-0121 (alternative cooling water systems).

E The National Environmental Research Park program conducted 15 research projects, sponsored a meeting on microorganisms in deep sedimentary rocks, and held a workshop on the ecology and conservation of storks.

SRL Environmental Management and Research Programs Programs following the dispersion and effect of SRP pollutants included the following studies:

E Mass spectrometry methods were improved for measuring Pu in body fluids, the nonradio-active fission product isotopes of Kr and Xe at ultra low levels in the environment, and very low concentrations of environmental tritium.

E Construction and testing began in 1988 of a prototype aqueous effluent tritium monitor that will detect 1 Ci/hr releases f rom 400 D Area within five minutes.

]

E Pre-and post-opera'ional environmental surveys for the Vogtle 1 Nuclear Power Plant showed consistency with Vogtle measurements.

E Measurements of "C enissions from the stack of P Reactor were made in the fall of 1987, and a comprehensive report on measurements of Slin surf ace waturs and groundwater was issued.

140 SAVANNAH RIVER PLANT - Environmental Report for 1987 E Development of remote sensing techniques continued as a cost-effective means for environmental monitoring of large areas, a Tomato, pepper, and pine plant exposures to tntium in a controlled environmental chamber indicated that the plants' intake of intium is from tritiated water, probably by photosynthesis.

E An ongoing study of the microbiology of the deep subsuriace has shown that microorganisms occurh great diversity and densities at depths down to 851 ft. The long-term goal of this study is to use active microorganisms to degrade or0anic contaminations, u Sitewide seismic surveys were conducted to obtain a three dimensional representation of the geologic structure beneath the SRP for use in environmental studies.

Programs to develop and Implement procedures to comply with regulations and to conduct pollution abatement activities included the following:

M The emergency response system was upgraded by linking its tritium monitors to the WIND systeni computer and the VAN TAGE data management system, by installing new instrumen.

tation and data acquistiiorttransmission systems on meteorological monito,-ing towers, by installing a Geographic Information System in the b/eather Center Analysis Laboratory, by adding computer hardware in the SRP Emergency Operating Center, and by adding two Nal detectors on the TR AC vehicle to identify (at a distance) localized land masses contaminated with radicadivity.

E A "'Cs transport monitoring program showed that restart of L Peactor had only a minor etfect on offsite concentrations of "7Cs.

E Dye tracers in L Lake showed that the construction of a new canal substantially increased the flow time to the middle of the lake and thereby siightly improved the production of L Reactor. Remote thermalimagery studies of SRP's cooling ponds are under way.

E A STABLE program (a study of the stable planetary boundary layer [SBL) of warm night air just above the ground) was initiated to study the potential d:spersal of contaminants via SBL turbulence and diffusion.

E Calculations of offsite radiation doses with the EPA approved CAAC Code (Clean Air Act Code) were performed to demonstrate NESHAPS compliance (National Emission Stan-dards for Hazardous Air Pollutants).

Activltles to meet permit or environmentalimpact statement requirements included the following:

m Monitoring and maintenance of L Lake showed that the lake had dissolved oxygen content and pH values, inshore vegetative macrophyte growth, and insect and fish populations simitar to those in other southeastom reservoirs.

E A final report on the Comprehensive Coohng Water Study initiated in 1983 to evaluate environmental efiects associated with SRP cooling water withdrawals and discharges shows that no large permanent adverse ettects are presently occurring, and, in fact, some animal species are benefiting from the eff ects.

12. Environmental Management and Research Programs 147 E An environmental impact statement on waste management activities fcr groundwater protection has progressed to the point that 26 environmentalinformation documents (EIDs) encompassing the 77 waste sites have been completed, allindicating that the risk to human health and ecology is low.

E As a first step in characterizing 166 individual waste sites (a preclosure requirement).

historical records were exarained and for some sites recommendations were made that fuither investigative activities be initiated (i.e., soil gas surveys, ground-penetrating radar, soil sample, groundwater monitoring wells, and geologic borings).

E in a pilot study 1,500 pounds Of the :0lvents trichloroethylene and tetrachloroethylene contaminating SRP soils a%ve the permanent water table were removed by in situ vacuum extraction.

E The SRP Baseline Hydrogeologic Investigation for providing hydrogeologic data over the entire SRP site was completed. Water level measurements from this program were used to construct an updated map of the head reversal across the Ellenton Formation that separates the Tuscaloosa and Congaree Formations beneath SRP.

E Development of a validated, documented regional three-dimensional flow model that simulates the groundwater flow system at SRP continued. Upon completion, the model will be used for assessing attemative uses of groundwater resources at SRP.

E SRL and SREL have begun tests in which the herbicide trifluralin (heflan)- an effective plant root retstdant -is incorporated in a slow release matrix that could prevent plant roots from penetrating into radioactive anWor hazardous waste and transporting contaminants to the surface.

E Evaluations supporting the Altemative Cooling Water Systems Environmental impact Statement indicated that the potential effects on wildlife of the proposed systems would be positive and that the temperatures discharged into site streams would be significantly i

reduced.

Eavannah River Ecology Laboratory Programs Bageochemical ecology studies included the following:

E Continued rosearch on t1e environmental chemistry of sodium tetraphenylboron (NaTPB),

an organo-borate compound to be used in tha new Defense Waste Processing Facility, included examination of the effects of vadous abiotic soilparameters on the degradation rate of TPB.

E Microcosm studies to investigate the potential remobilization of metals and nutrients f rom L-Lake sediments showed that under reducing conditions all tabile manganese fractions were rnobilized after 72 hr but only 6% of the labile iron was released after 75 hr. Other research indicates that elevated temperatures in the lake do not increase the accumulation of organ'c matter.

E Radiocesium deposits in Pond B reservoir are largely retained in sediments, with less than 0.6% of the totalinventory being found in the biotic components of the reservoir.

148 SAVANNAH RIVER PLANT - Environmental Report for 1987 E The solubility and movement of selenium, a potential contaminant of soils and groundwater that can be released from coal piles and runoff basins, are closely associated with the chemical species in solution, the major factors controlling the species being the redox potential and pH.

E The variance structure f or mercury concentrations within a dominant fish species population, the dusky sNoer (Notropis commingsae), in Upper Three Runs Creek was defined and will serve as a statistical benchmark.

Stress and wildlife ecology studies encompassed the following:

E Water quality studies of streams peripheral to the DWPF showed some increases in the concentrations of total suspended solids and in turbioity levels.

E Research indicates that aquatic turtles inhabiting seepage basins containing low concentra-tions of radioactive and nonradioactive contaminants possess significantly greater variation in DNA content in blood cells than turtles from a control population.

E A study of the biomass productivity of adults from six turtle species in freshwater Wetlands showed large variations in the ratios of minimum to maximum plastron lengths and body masses.

E To replace a potentially lost foraging habitat for wood storks with the restart of L Reactor, SRP created 14 hectares of ponds at the site of Kathwood Lake and stocked them with aquatic prey. The number of wood storks foraging at the ponds increased substantially in 1987.

E Examination of reproductive and demographic data on female white-tailed deer collected over a 20 year period shows that a relative consistency of the reproductive rate is maintained in both the swamp 80d upland habitats, but that those in the swamp have significantly lower fetal numbers.

Wetlands ecology research Included the following:

E Studies of the dynamics of wetland forest species show that f actors that modify the Savannah River floodplain hydrology such as cooling water discharge from SRP reactors and upstream control of river flows, may eff ectively limit bald cypress and water tupelo regeneration in the floodplain forest because of the rerreval of safe sites for seed germination and seedling establishment.

E SREL and Louisiana State University are engaged in research to understand the complex relationships between flooding, wetland plants and wetland soils on the SRP site. This work will be used to delineate wetland boundaries as required by the Clean Water Act Section 404.

E NERP Project inventories of plant species categorized by the federal and South Caro 5na governments as threatened or rare are being used by DOE in the overall management of the SRPsite andstudiesof the populationdynamicsof twoof thefederallylistedplants have been

)

initiated.

E SREL research to assess the effects of thermal stress and elevated nutrients on the zooplankton community development in L Lake has been expanded to include additional stations and feeding experiments to determine the food resources used by major zooplank-ton spedes.

12. Environmental Management and Research Programs 149 E Revegetation of the highly disturbed wetland system in the Steel Creek floodplain and detta (17 years after thermal discharge s ceased) is continuing, but it appears unlikely that the bald cypress and water tupelo, co dominants of the undisturbed swamp forest, will regain dominance.

E LittoralAvetland vegetation planting project in L Lake during 1987 was successfuf in estab-lishing diverse plant communities and wildlife habitat.

U.S. Forest Service Savannah River Forest Station Programs E Timber cut during 1987 brought the federal government nearly $2.3 million for 27 million board feet.

E Pine seedlings were planted on over 2,200 acres during FY1987, including longfeaf pines preferred by the endangered red cockaded woodpecker, E The South Carolina Forestry Commission Nursery is under contract to DOE to use the most advanced technology identified by the U.S. Forest Service to grow seedlings for plantinq at SRP.

E Secondary roads were upgraded and seven acres of bare areas were planted with wildlife food plants.

E A buffer zone established for nesting Southem bald eagles was utilized.

E The translocation cf a f ew red cockaded woodpeckers to SRP f orests to counteract possible inbreeding in the small local population was successful.

E St eps we re t aken to control the population ot wild hogs and bo avers f rom locations whe re they were causing damage.

E A detailed mapping of SRP soils was completed for use in a soil survey repor1 scheduled for publication in 1989.

E Techniques for producing seedlings for more successful reforestation were tested.

E The results of 27 field studies on over 20,000 trees were published in 14 research articles.

5 Five new studies were initiated on the germination and growth of pines and sweetgum under varying conditions and nursery practices.

References CAAC86 Radiation Shielding Information Center,1986,

Code System for Implementation of Atmos-pheric Dispersion Assessment Required by the Clean Air Act,"Report CCC 476, Oak Ridge, National Laboratory, Oak Ridge, TN.

DuS4 Dukes, E.K,1984, The Savannah Riece Plant Environment, Report DP 1642, Savannah River Laboratory, Aiken, SC.

Ec80 Eckerman, KF., et al, June 1980, Users Guide to GASPAR Code, Report NUREG.0597, U.S.

Nuclear Regulatory Commission.

ENV Envirodyne Engineers, Inc., flandbook for Analytical Quality Control, St. Louis, MO.

EPA 75 U.S. Environmental Protection Agency,1975,"National Interim Primary Drinking Water Regulation s," Title 40, Code of Federal Regulations, Part 141, Washington, DC.

EPA 82, EPA 83 U.S. Environmental Protection Agency,1982 and 1983, EnvironmentalRadiation Data, Reports 31-33 (Sept., Dec.1982 and Mar.1983). USEPA 520/5 83,-015 and -016, Washington, DC.

EPA 85 U.S. Environmental Protection Agency,1985,"National Emission Standards for llazardous Air Pollutants: Standards for Radioactivity," Title 40, Code ofFederal Regulations, Part 61, Washington, DC.

EPAS6 U.S. Environmental Protection Agency,1986. "Proposed Rules," Title 40, Code ofFederal Regula-tion s, Part 141, Washington, DC.

EPA 87 U.S. Environmental Protection Agency,1987. "National Primary Drinking Water Regulations,"

Title 40, Code of Federal Regulations, Part 141, Washington, DC.

IlPS80 llealth Physics Society,1980,"Upgrading Environmental Radiation Data,"llealth Physics Society Committee Report HPSE-1, prepared for the OfTice of Radiation Programs, U.S. Environ.

mental Protection Agency, EPA 520/180-012, Washington, DC.

ICRP59 International Commission on Radiological Protection,1959,ICRP Publication 2,(Oxford:

Pergamon Press).

1 ICRP65 International Commission on Radiological Protection,1965, Principles of Environmental Monitoring Related to the IIandling of Radicactive Materials,"ICRP Publication 7,(New York:

)

Pergamon Press).

ICRP68 International Commission on Radiological Protection,1968,ICRP Publication 10,(Oxford-Pergamon Press).

ICRP77 International Commission on Radiological Protection,1977,ICRP Publication 26, Annals of the ICRP 1(3).

ICRP79 International Commission on Radiological Protection,1979,

Limits for Intake of Radionuclides by Workers,"ICRP Publication 30, Annals of the ICRP 3(4).

ICRP81 International Commission on Radiological Protection,1981,"Limits ofinhalation of Radon Daughters by Workers,"ICRP Publication 32, Annals of the ICRP G(1),

l 152 SAVANNAH RIVER PLANT - Environmental Report for 1987 1

Ka87 Kantelo, M.V.,1987,"Summary ofI 129 Measurements in Ground and Surface Waters," Report d

DPST 87 820, Savannah River Laboratory, Aiken, SC.

Ku87 Kurzeja, R.J.; Taylor, R.W.; Sharma, J.; Burckhalter, L.T.1987,"Environmental Efrects of the a

July 31,1987 Tritium Release From the Savannah River Plant,"Report DP 1758, Savannah River Laboratory, Aiken, SC.

Mar 84 Marter, W.L.,1984, "Environmental Dosimetry for Normal Operation at SRP," Report DPST 83-270 Rev.1, Aiken, SC.

I Mi80 Michel, J.; Moore, W.S.1980,"Ra 228 and Ra 226 Content of Groundwater in Fall line Aquifers,"

i Health Physics, Vol. 38, pp. 663 671.

NCRP78 National Council on Radiation Protection and Measurements,1971,"A Ilandbook of Radioactivity Measurements Procedures,NCRP No. 58, Washington DC.

NCRP79 National Council on Radiation Protection and Measurements,1979,"Tritium in the Environment," NCRP Report No. 62, Washington, DC.

I NCRP87a National Council on Radiation Protection and Measurements,1987,"Ionizing Radiation Exposure of the Population of the United States,"NCRP Report No. 93, Washington, DC, t

t NCRP87b National Council on Radiation Protection and Measurements,1987,"Recommendations on Limits for Ionizing Radiation Exposure,"NCRPReport No. 91, Washington, DC.

j NUREG84 Office of Nuclear Reactor Regulations,1984, Lower Limit ofDetection: Definition and Elaboration ofa Proposed Position for Radiological Effluent and Environmental 1feasurements, prepared by the National Bureau of Standards for the Division of Systems Integration, Oflice of Nuclear Reactor Regulations, U.S Nuclear Regulatory Commission, NCR FIN B8615.

i Sa77 Sagendorf, J.F.; Goll, J.T.,1977, XOQlDOQ Program for biettorological Evaluation ofRoutine Effluent Releases at Nuclear Power Stations, U.S. Nuclear Regulatory Commission, Washington DC.,

NUREG 0324 (Draft),

j SCDilEC81 South Carolina Department ofIIealth and Environmental Control,1981, Water Classification Standards System for the State of South Carolina, Columbia, SC.

SCDilEC85 South Carolina Department ofIlealth and Environmental Control,1985,

Savannah River Plant, Aiken, Allendale, and Barnwell Counties," NPDES Permit 0000175, Columbia, SC.

Si80 Simpson, D.B; McGill, B.L.,1980, Users Afanualfor LADTAP U A Computer Program for Calculating Radiation Exposure to bian from Routine Release ofNuclear Reactor Liquid Effluents, Oak Ridge National Laboratory, Oak Ridge,TN, NUREG/CR 1276 (ORNI/NUREG/f0MC 1).

StS3 Stone, J.A.,1983,"Technical Summary of Groundwater Quality Protection Program at Savannah River Plant,"Report DPST-83-829, Volume II, Savannah River Laboratory, Aiken, SC.

Tu83 Turcotte, M.D.S.,1983,"Georgia Fishery Study: Implications for Dose Calculations,"Report DPST-83 319, Rev.1, Savannah River Laboratory, Aiken, SC.

1 USNRC71 U.S. Nuclear Regulatory Commission,1971, Calculations ofAnnual Doses to Afan from Routine Releases ofReactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appen.

l dix I, Regulatory Guide 1.109, Washington, DC.

l I

I

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References 153 I

USNRC73 U.S. Nuclear Regulatory Commission,1973,"Methods for Estimating Atmospheric l

Transport and Dispersion of Gaseous Efiluents in Routine Releases from Light. Water. Cooled i

Reactors," Regulatory Guide 1.111, Washington, DC.

l USNRC79 U.S. Nuclear Regulatory Commission,1979,"NUREG 172," prepared by Battelle Pacific l

Northwest Laboratory for the U. S Nuclear Regulatory Commission.

I Ze87 Zeigler, C.C.; Lawrimore, I.B.; Heath, E.M.; Till, J.E.,1986, U.S. Deparfment o/ Energy Savannah River Plant Environmental Report for 1986, Report DPSPU.86 30-1, Savannah River Plant, Aiken, SC.

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Glossary activity. See radioactivity, microcurie (pCl)-10' Q, one-millionth of a curie; 3.7 x 10' disintegrations per second.

alpha particle. A positively charged particle emitted from the nucleus of an atom having the nanocurie (nCl)-10' Ci, one-billionth of a same chargo and mass as that of a helium nucleus curie; 37 disintegrations per second.

(2 protons,2 neutrons).

picoeurie (pCl) " Ci, one-trillionth of a atom. Smallest particle of an element capable of curie; 0.037 disinte; rations per second.

er.tering into a chemical reaction.

femtocurie (fCl)-1018 Ci, ccae-quadrillionth of beta particle. A negatively charged particle a curie; 0.000037 disintegrations per second.

emitted from the nucleus of an atom having a mass and charge equal to that of an electron.

attocurie (aCl)-10 " Ci, one-quintillionth of a curie; 0.000000037 disintegrations per second.

l blota.The animal and plant life of a particular i

I region considered as a total ecological entity.

decay, radioactive.The spontaneous transfor-Central Savannah River Area (CSRA). A active or nonradioactive nuclide, or into a differ-

~

mation of one radionuclide into a difTerent radio-13-county area in Georgia and South Carolina ent energy state of the same radionuclide, surrounding Augusta, GA. SRP is included in the CSRA.

Derived Concentration Guide (DCG).The standards applicable to concentrations of radionu.

contamination. The deposition of unwanted clides in air and water as given in DOE Order radioactive material on the surfaces of structures, 5480.1A.

areas, objects, or personnel.

diatoms. Unicellular or colonial algae of the class concentration.The amount of a specified sub.

Bacillariophyceae, having siliceous cell walls with stance or amount of radioactivity in a given two overlapping, symmetrical parts. Diatoms i

l volume or mass, represent the predominant periphyton (attached algae)in most waterbodies and have been shown i

l cosmic radiation. Radiation of many types with to be reliable algal indientors of water quality.

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very high energies, originating outside the earth's I

l atmosphere. Cosmic radiation is one source diatometer. Diatom collection equipment consirt.

l contributing to natural background radiation.

ing of a series of microscope slides in a holder.

counter. A general designation applied to radia, disintegration, nuclear. A spontaneous nuclear tion detection instruments or survey meters that transformation (radioactivity) characterized by detect and measure radiation.

the emission of energy and/or mass from the i

nucleus.

l curie (Cl). Unit of radioactivity. One curie is I

defined as 3.7 x 10"(37 billion) disintegrations dose, absorbed. The amount of energy deposited

(

l per second. Several fractions and multiples of the by radiation in a (;iven amount of material. The j

l curie are in common usage:

unit of absorbed dose is the rad.

kilocurie (kcl) -10'Ci, one thousand curies; dose commitment.The radiation dose received 3.7 x 10u disintegrations per second.

from major pathways of exposure, both internal l

l and external, throughout a specified lifetime of an i

l millicurie (mCl)-108 Ci, one thousandth of a individual (generally 50 years).

l curie; 3.7 x 10' disintegrations per second.

i

t 156 SAVANNAH RIVER PLANT - Environmental Report for 1987 dose equivalent. A modification to absorbed dose person rem. Collective dose to a population which expresses the biological efhets of all radia-group. For example, a dose of one rem to 10 i

tions on a common scale. The unit of dose equiva-individuals results in a collective dose of 10 lent is the rem.

person rem.

exposure. A measure of the ionization produced quality factor. The factor by which the absorbed in air by x or gamma radiation. The special unit dose (Rad)is multiplied to obtain a quantity that of exposure is the rcentgen (R).

expresses, on a common scale for all ionizing radiation, the biological damage to exposed gamma ray,liigh. energy short wavelength persons. It is used because some types of radia-electromagnetic radiation emitted from the tion, much as alpha particles, are more biologically nucleus. Gamma radiation frequently accompa-damaging than others, nies the emission of alpha or beta particles.

Gamma rays are identical to x. rays except for the rad. The unit of absorbed dose.

source of the emission, radioactivity.The spontaneous emission of half life, radionettve. The time required for a radiation, generally alpha or beta particles, onen given radionuclide to lose half ofits activity by accompanied by gamma rays, from the nucleus of radioactive decay Each nuclide has a unique an unstable isotope.

halflife, radionuellde. A species of atom characterized by half life, biological.The time required for a the constitution ofits nucleus, i.e., by the num.

biological system, such as that of a human, to bers of neutrons and protons it contains.

eliminate by natural processes half the amount of a substance (such as a radioactive material) that rem.The unit of dose equivalent. Dose equiva.

has entered it.

lent is frequently reported in units of millirem (mrem) which is one thousandth of a rem.

isotopes. Forms of an element having the same i

number of protons in their nuclei and differing in sievert (Sv). International Standards Organiza-the number of neutrons.

tion (S.I.) Unit for radiation dose,1 Sv = 100 rem.

milli roentgen (mit). A measure of x or gamma thermoluminescent dosimeters (TLDs). A radiation.

device used to measure external radiation levels.

I minimum detectable concentration (MDC).

tritium (11-3).The hydrogen isotope with one The smallest amount or concentration of a radio-proton and two neutrons in the nucleus. It emits element that can be distinguished in a sample by a low energy beta particle (0.0186 MeV max).

a given measurement system in a preselected counting time at a given confidence level, uncontrolled area. Any area to which access is not controlled for the purpose of protecting indi-i natural radiation. Radiation arising from viduals from exposure to radiation and radioactive cosmic sources and from naturally occurring materials. The area beyond the boundary of the radionuelides (such as radon) present in the Savannah River Plant is an uncontrolled area.

human environment.

l watershed.The region draining into a river,

]

outfall.The place where a storm sewer or effluent river system or body of water.

j line discharges to the environment.

j worldwide fallout. Radioactive debris from part per million (ppm). Concentration unit atmospherie weapons tests that is either airborne i

equivalent to mg/L.

and cycling around the earth or has been depos.

ited on the earth's surface.

1 parts per billion (ppb). Concentration unit j

equivalent to ng/mL or pg/L.

Appendix A:

Listing of Environmental Monitoring Reports ONSITE ItEPOltTS beginning in 1963. Attempts to find a report for July-December 1953 have been unsuccessful. The Reports of the routine environmental monitoring onsite report was discontinued in 1985 when the program at SRP have been prepared periodically onsite and offsite reports were merged into a single since before SRP startup. The monitoring report publication.

numbering system and titles have been changed several times over the years to reflect the evohing Some of the monitoring reports originally contained progress in the concepts of environmental monitor-secret information, primarily radioactive release ing. The amount of detailed information contained values that could be related to production rates.The in the reports also varies from time to time and secret information in these reports was deleted in probably reflects the relative impcrtance and em-the mid 1970s and a deleted version (DEL) of the phasis given to topics by different authors.

report was issued.

Except for July-December 1953, reports were is-Listed below are onsite environmentai reports since sued semi annually from 1951 to 1962 and annually 1951.

Number Period Title DP27 Jun 1951-Jan 1953 Natural Radioactivity Content of the Savannah River Plant DPSPU 5411 12 Jan-Jul 1953 Works Technical Department Data Record, llealth Physics Site Survey Data No report Jul-Dec 1953 DP92 Jan-Jul 1954 Radioactivity in the Environrnent of the Savannah River Plant DPSP 55-25 34 Jul--Dec 1954 Semi Annual Progress Report-Regional DPSP 56-25-13 Jan-Jun 1955 DPSP 56 25-54 (DEL) Jul-Dec 1955 IIealth Physics Regional Monitoring DPSP 56 25-4 (DEL) Jan-Jun 1956 DPSP 57 2515 (DEL) Jul-Dec 1956 DPSP 57 25-43 (DEL) Jan-Jun 1957 DPSP 58 2517 (DEL) Jul-Dec 1957 DPSP 58-25-38 (DEL) Jan-Jun 1958 DPSPU 591123 Jul-Dec 1958 DPSPU 5911-30 Jan-Jun 1959 DPSPU 60-119 Jul-Dec 1959 DPSP 60-25 26 (DEL) Jan-Jun 1960 DPSP 6125 4 (DEL) Jul-Dec 1960 DPSP 62 25 2 (DEL) Jan-Jun 1961 DPSP 62 25-9 (DEL) Jul-Dec 1961 DPSP 63 25-3 (DEL) Jan-Jun 1962 DPSP 63 2510(DEL) Jd-Dec 1962 DPSPU 6411 12 Ja -Dec 1963 Environmental Monitoring at the Savannah River Plant DPST 65-302 Jan-Dec 1964 DPST 66-302 Jan-Dec 1965 DPST 67 302 Jan-Dec 1966

i 158 SAVANNAH RIVER PLANT - Environmental Report for 1987 Number Period Title i

l 1

DPST 68 302 Jan-Dec 1967 DPST 69 302 Jan-Dec 1968 DPST 70 302 Jan-Dec 1969 DPST 71302 Jan-Dec 1970 DPSPU 72-302 Jan-Dec 1071 DPSPU 73 302 Jan-Dec 1972 -

DPSPU 74-302 Jan-Dec 1973 DPSPU 75-302 Jan-Dec 1974 DPSPU 76-302 Jan-Dec 1975 j

DPSPU 77 302 Jan-Dec 1976 DPSPU 78-302 Jan-Dec 1977 DPSPU 79-302 Jan-Dec 1978 DPSPU 80-302 Jan-Dec 1979 DPSPU 81302 Jan-Dec 1980 I

DPSPU 82-302 Jan-Dec 1981 DPSPU 83-302 Jan-Dec 1982 DPSPU 84-302 Jan-Dec 1983 DPSPU 85-302 Jan-Dec 1984 DEL-reissue of reports with secret information deleted.

OFFSITE "PUBLIC" REPORTS 1

Results of the environmental monitoring program The offsite report was discontinued in 1985 when that affected the offsite environment have been the onsite and offsite reports were merged into a reported to the public since 1959. These reports single publication. A listing of the offsite reports contained data from the site boundary and beyond.

follows:

Number Period Title f

No document Jan-Dec 1959 The Effect of the Savannah River Plant on a

number Environmental Radioactivity

]

Jan-Mar 1960 3

Apr-Jun 1960 Jul-Sep 1960 Oct-Dec 1960 l

Jan-Mar 1961 i

Apr-Jun 1961 1

Jul-Sep 1961 DPSPU 62 30-11 Oct-Dec 1961 DPSPU 62-30-24 Jan-Jun 1962 DPSPU 63 30-12 Jui-Dec 1962 DPSPU 63-30-1 Jan-Jun 1963 DPSPU 64-301 Jul-Dec 1963 i

DPSPU 64 30-2 Jan-Jun 1964 I

DPSPU 65-30-1 Jul-Dec 1964

}

DPST 65-30-2 Jan-Jun 1965 DPST 66-30-1 Jul-Dec 1965 DPST 66-30-2 Jan-Jun 1966 i

f

I Appendix A 159 I

Number Period Title i

I DPST 67 301 Jul-Dec 1966 DPST 67 30 2 Jan-Jun 1967 DPST 68-301 Jul-Dec 1967 DPST 68 30 2 Jan-Jun 1968 DPST 69 301 Jul-Dec 1968 f

DPST 69 30 0 Jan-Jun 1969 DPST 70-301 Jul-Dec 1969 DPST 70 30-2 Jan-Jun 1970 DPST 7130-1 Jul-Dec 1970 DPST 71-30-16 Jan-Jnn 1971

.i DPSPU 72 30-1 Jan-Dec 1971 Environmental Monitoring in the Vicinity of 1

the Savannah River Plant DPSPU 73 30-1 Jan-Dec 1972 DPSPU 74 30-1 Jan-Dec 1973 DPSPU 75-30-1 Jan-Dec 1974 1

DPSPU 76-30-1 Jan-Dec 1975 DPSPU 77-301 Jan-Dec 1976 DPSPU 78-30-1 Jan-Dec 1977 DPSPU 79-30-1 Jan-Dec 1978 DPSPU 80-30-1 Jan-Dec 1979 DPSPU 81301 Jan-Dec 1980 4

DPSPU 82 301 Jan-Dec 1981 DPSPU 83-30-1 Jan-Dec 1982 DPSPU 84 30-1 Jan-Dec 1983 DPSPU 85-301 Jan-Dec 1984 Savannah River Plant Environmental Report ENVIRONMENTAL REPORTS l

(COMBINED ONSITE AND OFFSITE)

In 1985, the onsi.e and ofTsite environmental I

monitoring reports were merged into a single i

publication. A listing of these reports follows:

1 Number Period Title j

4 DPSPU 86-30-1 Jan-Dec 1985 Savannah River Plant Environmental Report DPSPU 87 30-1 Jan-Dec 1986 I

i i

i

Appendix B:

Groundwater Monitoring Sites A. AREA SIETALS BUltNING PIT gradient position. Well FAC 4 is sidegradient and at a greater distance from the basin than the other The A Area 51etals Burning Pit (731-4A), placed wells.

in service about 1960, is west of Road D, about halfway between A Area and Road 2 (Fig. 4 22, Vol.

The K Area Acid / Caustic Basin (D%80G)is on H). The materials deposited at this site consisted the northeast side of K Area a few hundred meters mainly of lithium. aluminum alloy, aluminum from a tributary of Pen Branch (Fig. 418, Vol. II).

pieces, plastic pipe, metal drums, and other metal The basin is monitored by the four wells of the KAC scraps. They were deposited in open piles and series. Wells KAC 1,2, and 3 are near the basin, with burned periodically. In 1974, the solid materials well KAC 3 in an upgradient position, well KAC 2 in remainingin the pit were covered with soil, and the a sidegradient position, and well KAC 1 in a down-site was regraded.

gradient position. Well KAC 4 is a greater distance from the basin than the other wells and is screened The basin is monitored by the four wells of the ABP below the water table.

series.The tops of the sercens in wells ABP 1A,2A, and 4 are below the water table, makinginterpreta-The L Area Acid / Caustic Basin (004 79G) is tion of the upgradient an d downgradient position s of southeast of L Area adjacent to the L-Area Oil and the wells dimeult.

ChemicalBasin(904 83G)ona slopeleadingtoSteel Creek (Fig. 4 19, Vol. II).The site is monitored by the ACID / CAUSTIC BASINS four wells of the LAC series. Wells IAC 1,3, and 4 are downgradient of the basin, and well LAC 2 is The Acid' Caustic Basins, unlined earthen depres-upgradient of the basin.

sions approximately 15 m by 15 m by 2 m deep, were used for disposal of dilute sulfuric acid and sodium The P. Area Acid / Caustic Basin (004 78G) is hydroxide solutions employed to regenerate ion northeast of P Area and Road F on a slope that!eads exchange units in the water purification processes to a tributary of Par Pond (Fig. 4-20, Vol. II). The site at the reactor and separations areas. Other wastes is monitored by the four wells in the PAC series.

discharged to the basins included water rinses from Wells PAC 3 and 4 are near the basin, with PAC 3 in the ion exchange units, steam condensate, and any a downgradient position and PAC 4 in an upgradient rain that collected in the storage tanks spill contain-position. Wells PAC 1 and 2 are a greater distance ment enclosures.

from the basin, with PAC l in an upgradient position and PAC 2 in a sidegradient position.

The basins were constructed between 1952 and 1951.The R Area basin was abandoned in 1964;the The R Area Acid / Caustic Basin (D04 77G) is L-Area basin was abandoned in 1968; the other south of R Area,just south of Road G. The site is basins remained in service until the in-process monitored by the four wells of the RAC series. Well neutralization facilities became operationalin 1982.

RAC 1 is upgradient of the basin, and wella RAC 2, The basins are uncovered and abandoned in place.

3, and 4 are downgradient of the basin.

Stost of the basins are dry during dry weather and contain up to approximately 1 m of water during HACKGROUND WELLS periods of prolonged precipitation.

The A Area Background Well Near the Firing The F. Area Acid / Caustic Basin (90074G)is east Range, a single well(ABW 1) installed to serve as a of F Area, on a slope that leads to an unnamed background well for A Area, is located approxi-tributary of Upper Three Runs Creek (Fig. 4-4, Vol.

mately 700 m northeast of the SRL Seepage Basins.

II). The site is monitored by the four wells of th e FAC The screen in this well was placed below the water series. Wells FAC 1,2, and 3 are near the basin, with table in the Congaree Aquifer. The well is down-well FAC 3 in an upgradient position, well FAC 2 in gradient from the SRL Seepage Basins and the A 1 a sidegradient position, and well FAC 1 in a down-outfall.

162 SAVANNAH RIVER PLANT - Environmental Report for 1987 The Backgmund Well Near Hawthorne Fire The D Area HurningStubble Pits (431 D and Tower is in the north central part of SRP between 4311D)are approximately 300 m west of D Area Upper Three Runs Creek and Tinker Creek. Well (Fig. 4 26, Vol. II). The site is monitored by the four GBW 1 was installed at this remote site to provide wells of the DBP series. Wells DBP 1 and 3 are background groundwater quality information.

upgradient, well DBP 4 is sidegradient, and well DBP 2 is downgradient.

j IlURNINGatUHHLE P1TS The F Area Hurning/Itubble Pits (231.F and 231 1F)are northwest o the intersection of Road C r

The Burningatubble Pits were shallow excavations, and the F-Area entrance road (Fig. 4 5, Vol.11). The commonly 3 m deep, where burnable waste was site is monitored by the four wells of the FBP series.

collected continuously beginning in 1951. Waste Well FBP 2A is downgradient, well FBP 3A is side-collected included paper, plastics, wood, rubber, gradient, and wells FBP 1 A and 4 are upgradient of rags, cardboard, oil, degreasers, and drummed or-the basin. Upgradient well FBP 1 A may be affected ganic solvents. The collected waste was then by the old pipeline to the F Area Seepage Basins.

burned, usually monthly. Disposal of chemically contaminated oils was not permitted at the burning The K Area HurningStubble Pit 031 K)is ap-

pits, proximately 60 m northeast of K Area (Fig. 4 18, Vol.

J ID. The site is monitored by the four wells of the KRP When burning of waste in the pits was discontinued series. Well KRP 2 is upgradient of the basin, wells in October 1973, a layer of soil was placed over the KRP 1 and 3 are sidegradient, and well KRP 4 is j

remaining burnirig pit waste, and the pits were downgradient. KRP 41s deeper than the other wells, opened to receive nonsalvageable rubble such as which may result in a lower water level elevation in concrete, bricks, tile, asphalt, plastics, wallboard, this well, rubber, and nonreturnable empty drums. As each pit reached its capacity, it was closed and backfilled The L Area Hurning/Itubble Pit 031 L)is north.

with soil to grade. All Burning / Rubble Pits were west of L Area, between Road 7 1 and the steam line inactive by 1981, and all are covered except for Pit road (Fig. 4 19, Vol.10. The site is monitored by the l

131 1R in R Area, which was not backfilled.

four wells of the LRP series. Relative to the pit, well LRP 21s upgradient, well LRP l is sidegradient, and The A Area Hurning/Rubblo Pits (731 A and wells LRP 3 and 4 are downgradient, j

731 1 A)are west of Road D to the north orthe A. Area hietals Burning Pit (Fig. 4-22, Vol.10. The site is The P. Area HurningStubble Pit (131 P)is westof i

monitored by the four wells of the ARP series. Well P Area, south of Road C-7(Fig. 4 20, Vol. ID. The site ARP 3 is upgradient from the pits, well ARP 1A is monitored by th e four wells of the PRP series. Well is downgradient, and wells ARP 2 and 4 are PRP 4 is upgradient of the pit, wells PHP 2 and 3 are sidegradient.

sidegradient, and well PRP 1 A is downgradient.

4 The C Area HurningStubble Pit 031 C)is ap.

The R Area Hurning/ Rubble Pits 031 R and proximately 300 m west of C Area (Fig. 4 17, Vol.10.

131 IR)are southeast of R Area, southeast of Road I

The site is monitored by the four wells of the CRP F-8, The site is monitored by the four wells of the series. Relative to the pit, well CRP 1 is upgradient, RRP series. Relative to the pits, well RRP 1 is well CRP 3 is downgradient, and wells CRP 2 and 4 upgradient, well RRP 2 is sidegradient, and wells are both sidegradient. Elevated conductivity and pH RRP 3 and 4 are downgradient, levels in well CRP 3 indicate that this well has been afTeeted by teaching of the well grout.

CHEh11CALS, h1ETALS, AND PESTICIDES (Ch1P) HURIAL PITS The Central Shops Hurningatubble Pits (631-IG and 631-5G)are about 600 m north of Central The Chemicals, hietals, and Pesticides Hurial Sh ops between Road C and Road 5(Fig. 4 24, Vol.10.

Pits (080170,17,1G,18G,18.1G,18 2G,18.3G, The site is monitored by the four wells of the CSR and 19G) are southwest of Road C at the top of a hill l

series. All of the wells are either upgradient or near the head of Pen Branch (Fig. 4 25,Vol. ID.The sidegradient from the site.

Ch1P Pits were used to dispose of waste from 1971 j

i I

Appendix B 163 i

through 1979. The waste consisted of drummed oil tainment Basin but is directly downgradient of the and organic solvents, as well as small amounts of coal pile itself. Seven new wells (DCB 6 through 12) pesticides and toxic metals. Detailed inventories of were installed in the area in August 1987 for a SRL i

l the wastes disposed ofin each pit are not available, research project.

in 1984, the pits were completely excavated, back-i filled, and capped. During excavation, much of the The F Area Coal Pile Runoff Containment liquid waste was recovered in drums.

Basin (289 F) is southeast of F Area (Fig. 4 6, Vol.

f H).The coal pile in F Area was removed in 1985, and The site is monitored by the 20 wells of the CMP the basin, although no lunger in use, still receives series. Wells CM P 8,90,10,11,12,13,140,150, and rainfall runoff from the coal pile crea. The basin is i

160 monitor the water table, The remaining wells monitored by the four wells of the FCB series. Wells monitor lower aquifers. The water table flows away FCB 1 and 2 are upgradient of the basin, FCB 4 is from the pits on three sides so that all of the wells are sidegradient, and FCB 3 is downgradient. Elevated downgradient except CM P 10, which is sidegradient conductivity and pH levels in well FCB 1 indicate t

1 I

or upgradient, this well has been affected by leaching of the well l

I grout.

l COAL PILE RUNOFF i

]

CONTAINMENT HASINS The H Ana Coal Pile Runoff Containment Basin (289 H)is east of 11 Area (Fig. 411, Vol. ID.

Coal has been stored in open piles at seven locations The site is monitored by the four wells of the HCB i

at SRP. The coal is generally moderate-to low sulfur series. Relative to the basin, well llCB 3 is upgradi-

]

coal (1-2% S). Surface runofT from these piles is ent, well HCB 4 is downgradient, and wells !!CB 1 directed into coal pile runoffcontainment basins via and 2 are sidegradient.

gravity flow ditches and sewers. Work on the A and i

D basins was completed in October 1978, and the F, The K Ama Coal Pile Runoff Containment C, K P, and II basins were completed in March 1981.

Hasin (189 K)is southwest of K Area, between the All of the basins are active exceptfor those in C and ash disposal basin and the reactor seepage basin i

l F areas. The C and F-Area basins still collect rain.

(Fig. 4 18, Vol. II). The site is monitored by the four i

water, but no coal remains at either area.

wells of the KCB series. Relative to the basin, well l

J KCB 1 is upgradient, wells KCB 2 and 4 are side.

j The A Area Coal Pile Hunoff Containment gradient, and well KCB 3 is downgradient.

Hasin (788 3A)is east of Road D and southeast of the A Area coal storage facility (Fig. 4 22, Vol. II).

The P Area Coal Pile Runoff Containment l

The site is monitored by the four wells of the ACB Hasin (189 P)is southeast of the coal pile and south series. The horizontal gradients in the area are very of P Area (Fig. 4 20,Vol. II).The site is monitored by i

low, making the terms upgradient and downgradi-the four wells of the PCB series. Horizontal ground-i ent inappropriate at this site.

water gradienta in this area are low, making inter-l i

pretation ofgroun d water flow direction difTicult, but The C. Area Coal Pile Runoff Containment well PCB 1A appears to be upgradient, wells Ilasin (189 C)is southeast of C Area approximately PCB 2A and 4A sidegradient, and well PCB 3A j

200 m southeast of the C. Area coal storage facility downgradient.

(Fig. 4 17, Vol. II). The C-Area coal pile was removed 1

in 1985.The basin still receives rainfall runoff from D AREA OIL DISPOSAL HASIN the coal pile area.The site is monitored by the four wells of the CCB series. Relative to the basin, well The D Area Oil Disposal Basin (631 G) is north CCB 4 is upgradient, wells CCB 1 and 3 are side-of D Area between Roads A.4.4 and A-4.5(Fig. 4 27, j

gradient, and well CCB 2 is downgradient.

Vol.11). The basin was constructed in 1952 and l

began receiving waste oil products from D Area that I

The D Area Coal Pile Runoff Containment were unacceptable for incineration in the power-l Hasin (489-D) is south of D Area (Fig. 4 26, Vol.11) house boilers. These waste oils may have contained i

and is monitored by the wells of the DC B series. Well hydrogen sulfide, chlorinated organies, or other i

DCB 2A is upgradient, well DCB 3A is sidegradient, chemicals. In 1975, the oil basin was removed from and wells DCB 4A and 5A are dowrigradient. Well service and backfilled with soil. The basin is moni.

}

DCB 1A is sidegradient to the coal pile runoff con.

tored by the four wells of the DOB series. The i

164 SAVANNAH RIVER PLANT - Environmental Report for 1987_

horizontal gradient in this arca is very low, and at the reactors are distolved using nitrie acid, and the least two major Cow directica teversals have oc-desired radionuclides are separated from the other curred since mid 1984. The dat water table and Ossion products.

resultant Ductuations in dow direction make char-l aeteritation of the hydrologie regime dimeult.

The groundwater at these buildings is monitored by the two wells of the FAL series an>. six wells of the DISASSEh!HLY HASINS FCA series. Eight other shallow wells of the FCA i

series, which are usually dry, monitor the Canyon i

The disassembly basms were constructed adjacent Building base slab The results of this monitoring to each reactor at SRP for storing irradiated assem-are reported in Chapter 8. These buildings are near i

blics prior to their shipment to the separations the groundwater divide between Upper Three Runs areas. The disassembly basins are concrete lined Creek and Four hiile Creek. llorizontal gradients in tanks containing 10 m of water. The irradiated the water table are low, making it dimeult to deter-assemblies are rinsed, but some radioactivity is mine which wells are upgradient or downgradient.

transferred from the irradiated assemblies to the I

water in the basins. Sand Glters are used to main.

F AREA SEEPAGE HASINS 1

tain the clarity of the disassembly basin water and remove radioactive particulates. The basin water is The F Area Seepage Hasins (904 41G,-42G,and circulated through deionizers to reduce ion concen-

-43G) are on either side of Road C 4, south of Road trations. The deionirers are regenerated, then the C (Fig. 4 7, Vol. H). Since 1955, the basins have basin water is purged through the deionizers and received wastewater from F Area containing low-replaced with clean water. The basin water is peri-level radioactivity and chemicals, including nitric J

odically purged to reduce radiation exposure to acid, mercury, and sodium hydroxidc. They are operating personnel from the accumulation of trit-currently operating under Resource Conservation lum in the basin.

and Recovery Act (RCRA) interim status. A RCRA Part B application was filed with the South Carolina Wells CDB 1 end 2 monitor the C Area Disassem-Department ofllealth and Environmental Control bly Basin (Fig. 417, Vol. II). There is insumeient (SCDilEC) on February 6,1985.

information to determine the horizontal groundwa-ter gradient at this site.

It is believed that two unconnned aquifers are un-derneath the F Area Seepage 11asins. The first is a Wells KDB 1,2, and 3 monitor the K Area Disas-perched groundwater table 3 to 78 m below the sembly Hasin (Fig. 418, Vol.11). Relative to the ground surface. The second is the normal water l

basin well KDB 2 is downgradient, and wells KDB 1 table, which is 18 to 20 m below the ground surface.

l and 3 are sidegradient.

Both of these unconnned aquifers discharge into Four 51ile Creek about 500 m to the southeast.

i Wells LDB 1 and 2 monitor the L Area Disassem-bly Hasin (Fig. 4-19, Vol. II). There is insuliielent Three other aquifers are monitored mder the F-information to determine the horizontal groundwa-Area Seepage Basins. The AfcBean..uifer is be-i ter gradient at this site, tween 40 and 50 m mean ser. level (n.m, the Upper Congaree Aquifer is between 25 and 35 m msl, and Wells PDB 2 and 3 monitor the P Area Disassem-the lower Congaree Aquifer is between 8 and 18 m

]

bly Hasin (Fig. 4 20, Vol. II). Both wells are msl. The vertical groundwater gradient is down-screened below the water table, making interpreta-ward from the water table to the Upper Congaree tion of the site hydrology dimeult.

Aquifer. The vertical gradient is upward to neutral between the Upper Congaree Aquifer and the Lower F AREA A LINE AND CANYON DUILDING Congaree Aquifer. The hicBean Aquifer Cows south toward Four blile Creek. The Upper and lower i

The F Area Canyon Hullding (221 F)is in the Congaree Aquifers now west toward Upper Three l

center of F Area.The A Line Uranium Recovery Runs Creek.

Facility (2211F)is east of the south end of the d

Canyon Building (Fig. 4 3, Vol. II). At the A Line The F-Area Scepage Basins are monitored by nine Building, uranium is processed in the form ofuranyl wells of the F series and 48 wells of the FSB series.

nitrate. At the Canyon Building, target rods from During 1987,31 wells in the FSB 88 through FSB l

)

I t

i Appendix B 165 l

110 clusters were installed. Well F 10 is the only ings in F Area. Because the wells are almost in aline, g

currently active well monitoring the perched water it is difficult to interpret the local groundwater flow I

table. The remaining wells of the F series and the direction, but it appears to be toward the ennt.

l wells of the FSB series with a "D" or no letter t

designator after the well cluster number are FIRE DEPART 51ENT TitAINING FACILITY screened in the water table.The water table is above the tan clay in the upper portion of the Dry Branch The Fire Department Training Facility l'

Formation and the Tobacco Road Formation. Be-(9%113G) also known as the Central Shops tween the tan clay and the green clay in the lower Burnable Oil Basin,is at the southeast end of the portion of the Dry Branch Formation and the Santee Central Shops Area (Fig. 4 24),about 150 m north of Formation are screened FSB wells with a "C* letter the Ford Building (690 0). The site was used from i

designator. Below the green clay in the upper por.

1979 to 1982 by the SRP Fire Department to train l

tion of the Congaree Formation are screened wells personnel to use firefighting equipment. The site is l

j FSB 76B,78B,79B,87B,96A,97A,98A,99A,100A, monitored by the two wells of the CSO series. CSO and 101A. Wells FSB 76A,78A,79A, and 87A are 1 is sidegradient of the basin, and CSO 2 is screened in the lower portion of the Congaree upgradient.

i Formation.

FORD HUILDING SEEPAGE BASIN 1

F AREA TANK FARSI I

The Ford Huilding Scepage Basin (904 91G)is The F Area Tank Farm, at the southwest edge of in the Central Shops Area (Fig. 4 24, Vol.10, ap-F Area (Fig. 4 9, Vol.11), comprises 22 subsurface proximately 30 m from the Ford Building (690-G).

tanks containing aqueous radioactive wastes. These The basin received very low level radioactive waste-wastes consist of sludges, supernatant liquid of waters from Ford Building operations (repairing i

]

varying salt concentrations, and salt cake. The heat exchangers) from 1964 to January 1984. The sludges are composed primarily of a mixture of basin is monitored by the three wells of the IIXB i

i oxides and hydroxides of manganese, iron, and alu-series. All of the llXB wells are screened below the minum and a small amount ofuranium, plutonium, water table. Relative to the basin, wells IIXB 2 and and mercury, with essentially all of the fission prod-3 are upgradient, and well I!XB 1 is sidegradient.

ucts of original irradiated fuel except cesium. The supernate is primarily a solution of sodium nitrate, H AltEA CANYON HUILDING j

sodium nitrite, sodium hydroxide, sodium alumi-nate, and all of the fission products including the The H Area Canyon llullding (22110 is in the i

1 major cesium isotopes. The solution is put in tha north central part of the area (Fig. 4-10, Vol. lD. At tank farm evaporators, then stored in cool tanks to the building, target rods from the reactors are dis-precipitate the sodium nitrate and sodium nitrite.

solved using nitric acid, and the desired radionu.

This precipitate forms the salt cake. In 1961. Tank clides are separated from waste products.

8 was overfilled, causing soil contamination and subsequent gro mdwater contamination.

The groundwater is monitored by the four wells of 1

the IICA series. The 25 wells of the 11C0 series are The site is monitored by the 27 wells of the PrF dry wells monitoring the edges of the building base series. The tank farm is located on the groundwater slab. The horizontal gradient in the groundwater in divide between Upper Three Runs Creek and Four this area is low,but well llCA 2 is slightly upgradi.

Stile Creek. The horizontal flow direction of the ent compared to the other wells.

water table under most of the site is to the south,but j

in the north part of the site the flow is to the H AREA RETENTION BASLNS northwest.

The Il Area Retention Basins (281311 and 281 I

F AREA NAVAL FUELS FACILITY 810 are southeast of the intersection of Road 4 and j

Road E (Fig. 4 12, Vol.10. A small, unlined earthen

]

The Naval Fuels Facility (247 F) began operating retention basin (281 310 was used from 1955 to 1973

]

in 1986(Fig.4 3,Vol. ID.The siteis monitored by the to provide temporary emergeney storage for radioac.

five wells of the NBG series, which are placed be-tively contaminated eocling water from the chemical tween the Naval Fuel Facility and the other build-separations process. The water contained radionu.

100 SAVANNAH RIVER PLANT - Environmental Report for 1987 clides and possibly trace quantities of chemicals. A II AltEA TANK FAlth!

larger, mbber lined retention basin (28181D re-placed the original basin in 1973 and is stillin use.

Theli AreaTank Farm,at the south endof11 Area The basins are adjacent to each other, and all of the (Fig. 414, Vol. ID, comprises 29 subsurface tanks elevated contaminant levels in the groundwater are containing aqueous radioactive wastes. These probably due to the unlined 281311 basin, wastes consist of sludges, supernatant liquid of varying salt concentrations, and salt cake. The The basins are monitored by the six wells of the IIR3 sludges are composed primarily of a mixture of and liR8 series. Wells llR311 a nd 13 are upgradient oxides and hydroxides of manganese, iron, and alu-l of the basins and wells llR814 and 11 are sidegradi-minum and a small amount of uranium, plutonium, ent of the new basin, but ilR814 is downgradient of and mercury, with essentially all of the Gssion prod-the old basin, and wells IIR812 and 13 are down.

uets oforiginal irradiated fuel except cesium, which l

gradient of both basins.

remains in the supernate. The supernate is primar.

ily a solution of sodium nitrate, sodium nitrite, l

sodium hydroxide, sodium aluminate, and all of the Il AltEA SEEPAGE HASINS Gssion products including the major cesium iso-l topes. The solution is put in the tank farm evapora.

The II Area Scepage Hasins (9(M 4IG, 45G, tors, then stored in cool tanks to precipitate the 46G, and 5GG) are southwest of 11 Area, south-sodium nitrate and sodium nitrite. This precipitate west of the intersection of Road E and Road 4 (Fig.

forms the salt enke. Tank 16 was known to leak prior 413, Vol. ID. Starting in 1955 the basins received to the removal of the waste fr< m that tank in 1972.

wastewater from the II Separations Area contain.

A spill occurred at Tank 13 in 1984, ing low level radioactivity and ch emicals, including nitricacid, mercury chrotnium,and sodiumhydrox.

The site is monitored by the 32 wells of the IITF ide Basins 1,2, and 4 are currently operating under series. The site is located on the groundwater divide RCRA interim status, and a Part B application was between Upper Three Runs Creek and Four Stile l

Cled on February 6,1985. Basin 3 has been inactive Creek. Well 24111 is a 1.8-m--deep well between since 1962.

Tanks 9 and 11.

At *be li Area Seepage Basins, the water table is 5 IIAZAltDOUS WASTE STOllAGE to 8 m below the ground surface and outcrops adja-FACIIIIT AT CENTitAL SilOPS cent to Four Stile Creek 100 to 400 m from the basins. Below the water table are the hicBean, The liarardous Waste Storage Facility (709 G)

Upper Congaree, and lewer Congaree Aquifers.

is west of tho Central Shops Area (Fig. 4 24, Vol.10.

Vertical groundwater gradients are predominantly The wastes are stored inside the budding in drums downward from the water table to the fewer Conga-placed on diked concrete doors designed to contain ree Aquifer. The h!cBean Aquifer Down south to-liquid spills. The facility is inspected routinely for ward Four Stile Creek. The Upper Congaree container leakage. The site is monitored by the two Aquifer flows toward Upper Three Runs Creek to groundwater monitoring wells of the llWS series.

the west.

Pelative to the building, well llWS 2 is upgradient, and well HWS 1A is sidegradient.

The H Area Seepage Basins are monitored by the 28 wells of the llSB series and 16 wells of the 11 series.

IlYDROFLUOltlC ACID SPILL AltEA The H series w ells and w ells llSB 65,65C,66,67,68, 69,70,71,83D,84 D,85C,86C, and 86D monitor the The liydronuoric Acid Spill Area (6314G)is at water table, which is above the tan clay in the upper the south end of the Central Shops Area,just north portion of the Dry Branch Formation and the To-of the rail line to C Area (Fig. 4 24, Vol.10. It is baeco Road Formation. Below the tan clay in the Dry uncertain whether a spill occurred at this site or Branch Formation are screened wells !!SB 68C, contaminated soil or containers were buried here.

83C, and 84C. In the Santee Formation above the The spill or burial occurred prior to 1970. This site is green clay are screened IISB wells with "B* designa-monitored by the four wells of the CSA series. Rela-tors. The llSD wells with *A* designators are tive to the site, well CSA 2 is upgradient, wells CSA screened in the upper portion of the Congaree For.

I and 3 are sidegradient, and well CSA 4 is down.

mation below the green clay.

gradient.

i l

l w

Appendix B 167 l

i l

K AltEA ASilBASIN installed along with a 50-gal / min air stripper. A full-i scale recovery system, which replaced the previous j

The K. Area Ash liasin (188 K)is southwest of K air strippers in April 1985, consists of 11 recovery i

Area, about 100 m south of the coal pile (Fig. 418, wells and a 400-gaVmin air stripper. Through De-l Vol. II).The basin receives ash sluice water from the cember 1987, 143,000 lb of organies have been i

powerhouse in K Area and has been in service since removed from 482,000,000 gal of water.

l 1951. The site is monitored by the four wells of the l

KAB series. Well KAB 2 is upgradient of the basin, Besides the groundwater monitoring in A and M i

wells KAB 1 and 3 are sidegradient, and well KAB 4 areas conducted for the waste-site monitoring wells is downgradient. Wells KAB 1,2, and 4 ate down.

(Fig. 4 22, Vol. II), groundwater is also monitored for

[

gradient of the K Area coal pile, organies by approxim Stely 200 M Area plume oefi-j l

nition wells, which include the MSB wella not under c

the waste site monitoring program,the ASB 8 well L AltEA OIL AND CilEMICAL BASIN cluster, and the AC well series. During 1987, 19 plume definition wells were added to the MSB well Thel ArenOilandChemica1Hanin(904 83G)is series.

t southeast of L Area (Fig. 4 19, Vol.11), betwem the 3

]

reactor seepage basin (904 64G) and the a # aus-Several water. bearing zones are menitored within tie basin (904 79G). Frorr 1961 to 1979, ths, Win the contaminant plume.The water table in the area received small quantities of radioactive oil and is relatively flat with drainage toward Tims Branch chemical waste from throughout the plant. The and the Savannah River. Upper and 14wer Conga-i purpose of the facility was to dispose of small sol-ree sands drain to the southeast toward Upper j

umes of wastes that were not appropriate for dis-Three Runs Creek. Water in Cretaceous sediments charge to efiluent streams, regular seepage basins, below the Ellenton Formation drains to the south i

or the 200-Area waste management system. The toward the Savannah River.

waste came primarily from the reactor areas. The basin has been inactive since 1979. The vegetation jl inside the basin perimeter fence is removed and the M. AREA IIAZAltDOUS WASTE j

area kept bare.

MANAGEMENT FACILrlY OIWMF) i j

The basin is monitored by the four wells of the LCO The M. Area llazardous Waste Management Facil-l series. Relative to the basin, w ells LCO 2 and 3 are ity OlWMF) consists of the M Area Settling Hasin upgradient, and wells LCO 1 and 4 are downgradi-(904 51G), south of the M Fuel Fabrication Area f

j ent. Wells LCO 3 and LC0 4 are downgradient of the and west of Road D, and lest Lake (904 1120 )(Fig.

l nearby L-Area AcidCaustic Basin and may be af.

4 22, Vol.11). The unlined basin received wastewa.

l fected by constituents released there.

ter containing metal cleaning solvents, uranium, 1

and other chemleals and metals from the M Fuel i

Fabrication Area. In operation from 1958 until 1985, M AltEA GitOUNDWATElt PLUME thebasin overflowed into test Lake to the south.The DEFINITION WELLS basin is currently uncovered, contains water, and is j

undergoing RCRA closure.

1 Groundwater beneath A and M Areas is contami-l nated with halogenated organtes as a re? ult of past The M Area llWMF la monitored by wells MSB 1A, 1

operation s. Since the discovery of the contamination 2A, 3A,4A, 5A,6A,7A, and 8A. Because several 1

in June 1981, significant progress has been made in sources of contamination exist in M Area and te-j assessing the extent of the contamination and in cause the water table aquifer has a low gradient, establishing a remediation program. The inventory most wells are downgradient of a source ef contami-of organies in the groundwater is estimated to be nation or are affected by contamination dispersion i

450,000 lb with peak concentrations of 300 mg/1 from nearby sources. Therefore, designation of f

upgradient and downgradient wells at this site is A Groundwater Remediation Program is under way inappropriate. Instead, wells MSB 29B,290,29D, j

to clean up the groundwater contamination. In 43A,43B,and43Dtothenorthofthe700 A Admini.

February 1983, a 20-gal /rnin air stripper began stration Area are used to establish background ope ration. In January 1984, two recove ry w ells were water quality for the area.

168 SAVANNAH RIVER PLANT - Environmental Report for 1987 1,

1 51ETALLURGICAL LABOltATOltY NPDES Outrall A 14, a known source of haloge-

]

SEEPAGE IIASIN nated organies.

3 i

The hietallurgical Laboratory Scepage Basin NEW TNX SEEPAGE IIASIN l

(9611100)attheeastedgeofA Area (Fig.4 22,Vol.

!!), received wastewater e01uent from the htetallur.

The New TNX Scepage Hanin (904102G) has 1'

gical Laboratory Building (723 A) from 1956 until been in operation since 1980 and is in the east 1985. Wastewater released to the basin consisted of section of the TNX facility, across River Road from small quantities oflaboratory wastes from metallo-the TNX process area (Fig. 4 29, Vol.10. The basin graphic sample preparation (degreasing, cleaning, receives waste from pilot scale tests conducted at I

etching) and corrosion testing of stainless steels and TNX. The basin will be closed when the TNX i

nickel. based alloys. The volumes of wastewater E01uent Treatment Plant begins operation in the from the lab were small(5 to 10 gaVday) and con-second quarter of 1988. The depth of water in the sisted mostly of rinsewater. Noncontact cooling large section of the basin ranges from 1.8 to 3.0 m, s

water (approximately 900 gal / day) was also dis-depending upon rainfall and the number of charged. The basin is currently inactive and con-processes discharging to the basin.

tains rainwater.

The basin is monitored by the four wells of the YSB The basin is monitored by the three wells ofthe Ah!B series. Well YSB 2A is upgradient, wells YS B 1 A and I

series. The groundwater surface in this area is Cat, 3A are sidegradient, and well YSB 4 A is downgradi-making the terms upgradient and downgradient ent of the basin.

mappropnate.

1 OLD F AREA SEEPAGE HASIN 511SCELLANEOUS CHE511 CAL HASIN j

The Old F Area Seepage liasin (904 49G) is The 511scellaneous Chemical Hasin (7315A)is northwest of the F Area perimeter security fence west of Road D near the A Area 51etals Burning Pit.

and north of Building 221 F (Fig. 4-8, Vol. ID. The The basin was in operation by 1956 and was closed first seepage basin constructed in the area, it was 1

and the site graded in 1974. There are no records of used for disposal cf wastewater from Building i

the materials disposed of at this site. Soil gas inves-221 F from November 1954 until mid41ay 1955, tigations revealed halogenated organics in the near-when it was abandoned in place. During operation, surface soils at the site. During 1987, wells the seepage basin received a variety ofwastewaters, h1CB 2,4,5, and 6 were installed to monitor the including evaporator overheads, laundry wastewa.

l groundwater, ter, and an unknown amount of chemicals. Cur-j ren tly the ba sin is ope n an d eontain a som e rain wa te r, i

510TOlt SHOP OIL BASIN i

The basin is monitored by the four wells of the FNB The 51otor Shop Oil Basin (904101G)is at the series. Well FNB 4 is upgradient of the basin, wells I

south edge of A Area, by the 716-A hiotor Shop (Fig.

FNB 3 and FNB 1 are sidegradient, and well FNB 2 l

4 22, Vol.10. This unlined basin was placed in is downgradient.

service in 1977 to receive liquid waste from the l

l Stotor Shop. E01uent discharges from the biotor OLD TNX SEEPAGE HASIN j

Shop included waste engine oil, grease, kerosene, l

j ethylene glycol, and soapy water. All wastes passed The Old TNX Scepage Hasin (94176G), in the through an oil skimmer prior to discharge into the southwest corner of the TNX facility (Fig. 4 29, Vol.

basin. In August 1983, all discharges to the oil basin II), was in operation from 195S to 1980 and received i

)

were terminated. The site is currently inactive but waste from pilot-scale tests conducted at TNX. In i

1 collects rainwater during periods of heavy 1981, the west wall of the basin was breached to precipitation.

drain the impounded water, and the basin was hackfilled with a sand and clay mixture and the top l

The basin is monitored by the two w ells of the AOB capped with clay.

{

i series. It is in an area oflow horizontalgroundwater i

i gradients, making the terms upgradic.' and down.

The basin is monitored by the seven wells of the XSB

]

gradient inappropriate. The basin is near the series. Wells XSB 1,2,3A, and 4 are adjacent to the 1

t i

Appendix B 169 basin with well XSB 2 upgradient, wells XSB 1 and TheI Area HeactorScepage Basin (904 64G)is 3A sidegradient, and well XSB 4 downgradient.

southeast of L Area adjacent to the I, Area Oil and Wells XSB 5,5A, and ST are downgradient of the Chemical Basin (Fig. 419, Vol. II). The I Area basin and are screened to monitor deeper aquifers.

Reactor Seepage Basin wcs used from 1958 until 1969 and from 1985 to the present The basin is REACTOR SEEPAGE HASINS monitored by the four wells in the IEB series.

Relative to the basin, well LSB 3 is upgradient, well Renetor seepage basins receive water from the reac-LSB 1 is downgradient, and well LSB 2 and 4 are tor disassembly basins. The water in the disassem.

sidegradient-bly basins is periodically purged as described on p.

164. Monitoring of the purge water ensures that par.

The P. Area Heactor Scepage Basins (9N 610, ticulate radioactivity and ionic levels are within 62G, and 63G) are southwest of the reactor build.

specified limits before release to the seepage basins.

ing (Fig. 4 20, Vol.11). The basins are connected in An environmental release report is issued for each series with water entering Basin 1 then moving to purge.

Basins 2 and 3. The basins are monitored by the neven wells in the PSB series. Well PSB 5A is The reactor seepage basins were constructed in upgradient of Basin 3. Well PSB 6A is upgradient of 1957. Initially, purge water was pumped directly Basin 2 but downgradient of part of Basin 1. Well into the seepage basins.The use of mixed bed deion-PSB 7A is sidegradient to upgradient of Basin 1.

irers and sand filters began in the 1960s. From 1970 Well PSB 1A is downgradient of the basins. Well to 1978, the seepage basins were bypassed, and the PSB 4A is sidegradient of Basin 3.

deionized purge water was discharged directly into plant streams. In 1978, the basins were reactivated The six R Area Reactor Scepage Basins (9N.

and are currently in use.

103G,104G,and 57G thmugh 60G)arelocated just outside the perimeter fence northwest of R Area The C Area Heactor Scepage Basins (904 MG,-

(Fig. 4 21, Vol. II). The basins received purge water 67G, and 68G) are about 200 m southwest of the from the R Area Disassembly Basin from 1957 until reactor building (Fig. 417. Vol. II). The basins are 1964. Overflow was sequential via overCow chan-connected in series, with water entering Basin 1 nals from Basin 1 to Basin 2, to Basin 3, to Basin 4.

then moving to Basins 2 and 3. The basins are Basin 5 received water directly from the disassem-monitored by the six wells in the CSB series. Well bly basin. Basin 6 received water pumped from CSB 1A maintains an upgradient position. Well Basins 2,3, and 4 and then was used for receiving CSB 6A is sidegradient, and wells CSB 2A,3A,4 A, water from the disassembly basin.

and 5A are downgradient. Elevated conductivity and pH levels in wells CSB 1A,5A, and 6A indicate On November 8,1957, an experimental fuel element that these wells have been afTeeted by leaching of failed during a calorimeter test in the emergency well grout.

section of the R-Area Disassembly Basin. Following this incident, the seepage basins received approxi-The K Area Retention Basin (9N 88G)is north-mately 2,700 Ci of radionuclides, including 200 Ci of west of K Area, about 100 m from the perimeter

Sr and 1,000 Ci of u'Cs. About half orthe *Sr and fence (Fig. 4 18, Vol.10. It has been used since 1965

"'Cs has decayed since the incident. A large portion for disposal of purge water from the K Area Disas-of the released radionetivity was contained in Basin sembly Basin. The basin is monitored by the Ove 1, which was backfilled in December 1957. Basins 2 wells of the KRB series. Well KRB 8 is upgradient of through 6 were placed in operation in 1957 and 1958 the basin, wells KRB 1 and 13 are sidegradient, and after the incident to assist in containing the wells KRB 14 and 15 are downgradient.

radioactivity.

TheK Area HeactorSeepage Hasin(9N 65G)in in 1960, Basins 2 through 5 were closed and back-west ofK Area (Fig. 4 18, Vol.10.The ba sin was used Olled. The ground surface nbove Basins 1 through 5 from 1957 until 1960. The basin is monitored by the was treated with herbicide and covered with an-four wells in the KSB series. Well KSB lis upgradi-phalt. In addition, a kaolinite dike (down to a clay ent of the basin, KSB 2 and 4 A are sidegradient, and layer) was constructed around !!asin 1 and the KSB 3 is downgradient.

northwest end of Basin 3 to minimize latera move-

170 SAVANNAH RIVER PLANT - Environmental Report for 1987 ment of the radioactive contamination. Basin 6, SANITAltY IANDFILL which was active until 1964, was backGiled in 1977.

The Sanitary Landfill (740 G)is south of Road C The R Area Reactor Seepage Basins are monitored about midway down the slope from the Aiken Pla-by the wells of the RSA, RSB, RSC, RSD, RSE, and teau to Upper Three Runs Creek (Fig. 4 28, Vol.11).

RSP series. In 1975, a substantial increase in *Sr The site was opened in 1973. At thelandGil, material activity (3,400 pCi/L) occurred in groundwater such as paper, plastics, rubber, wood, cardboard, monitoring well RSE 13 on the southeast side of and rags are placed in trenches, which are covered Basin 1 outside the clay dike. Investigations re-with soil daily. The landfill receives approximately vealed that the source of the contamination was 4,000 tons of waste peryear. In addition to the waste migration through a sewer line that had been aban-alrevly listed, the landfill receives pesticide bags, doned after completion of R Reactor construction.

pun dured and empty aerosol cans, food waste, and Subsequently, eight groundwater monitoring wells asbetos in bags. The landGli is operated under (RSD 4 through RSD 11) were installed downgradi.

South Carolina Domestic Waste Permit No. 87A.

ent from well RS E 13.These wells are located on two lines,15 to 46 m south and parallel to wells RSD 4, The landfillis monitored by the 31 wells of the LFW 5, and 6. During 1987, five new monitoring wells series. All of the wells monitor the water table. The (RSE 24 and 25 and RSP 1,2, and 3) were installed horizontal groundwater flow direction is to the to monitor the R-Area Reactor Seepage Basins.

southeast toward Upper Three Runs Creek.

In general, the water table gradient in the north.

SAVANNAH RIVElt IAHORATORY west part of the site is to the north. To the south of SEEPAGE HASINS Basin 6, and in the vicinity of Basin 1 and the nearby abandoned sewer line, the water. table Cow direc.

The Savannah River Laboratory (SitL) Scep-tion is to the southeast.

age Basins (904 53G1, 53G2, 54G, and 55G) are east of Road 1 A across from SRL(Fig. 4 22, Vol.

ROAD A CHEMICAL BASIN 11). These four basins, constructed between 1954 and 1960, received low level radioactive wastewater The Road A Chemical Basin (9(M 111G)is ap-through underground drains from laboratories in proximately 800 m west of the intersection of SRP Buildings 735 A and 773 A. The basins were taken Road A (SC Rt.125) and SRP Road 6 (about 3.2 km out of service in October 1982, southeast of the D Area Powerhouse) (Fig. 4-30, Vol. II).The basin was closed and backfilled in 1973.

The basins are monitored by seven wells of the ASB The basin received miscellaneous radioactive and series (1A,2A,3A,4,5A,6A, and 7). The remaining chemical aqueous waste, but no data on the wastes wells in the ASB series are not adjacent to the hasin, are available.

The gradients in this area are relatively Dat, and changes in the flow direction and gradient have The basin is monitored by the four wells of the BRD occurred. Generally, wells ASB 1A and 2A are series. Well BRD 3 is upgradient, well BRD 2 is upgradient Wells ASB 4 and 6A are downgradient, sidegradient, and wells BRD 1 and 4 are sidegradi-Well cluster ASB 8 is near the NPDES Outfall A 1, ent to downgradient of the basin.

which could be a source of contaminants. Well ASB 9 is 500 m southeast of the seepage basins.

SAREA SILVERTON ROAD WASTE SITE The Defense Waste Processing Facility is under construction in S Area (Fig. 415, Vol. II). The six The Silverton Road Waste Site (7313A)is south-wells of the SBG series are located at the perimeter west of Road C-1.1, midway between Road 1 and of the area and are screened below the water table.

Road D (Fig. 4 23,Vol. II). It was used for disposal of The groundwater now direction appears to be to the metal shavings, construction debris, tires, drums, northwest toward Upper Three Runs Creek. Wells tanks, and miscellaneous items. The site was proba.

SBG 1 and 2 are downgradient, wells SBG 4 and 5 bly used before construction of SRP, but the startup are upgradient,and wells SBG 3 and 6 are sidegradi-date is unknowr, and no records of waste disposal ent of the area. Well SBG 5 was installed in 1987, activities have been kept. The site was closed in

Appendix B 171 1974. The waste material is presently covered with blixed wastes (low. level radioactive waste contain-soil and vegetation, ing hazardous waste) stored within the Radioactive Waste Burial Grounds include lead (used for shield.

The basin is monitored by the 30 wells of the SRW ing), cadmium (from control rods, safety rods, and series. The wells monitor the water table aquifer shielding), tritiated pump oil, and mercury. Some of and deeper aquifers The wells with an "A" or a "B" the waste is contained in welded stainless steel aner the well number monitor the lower aquifers containers or metal drums and stored within con-except for well SRW 3A, which is a water table well.

crete cylinders. Newly generated mixed waste is Well clusters SRW 1 through 6 are at the edge of the stored in Building 643 29G permitted by the site, with wells SRW 1,2 and 3A upgradient, well SCDilEC and operating under interim status.

SRW 4 sidet,radient, and wells SRW 5 and 6 down-Degraded solvents and tritiated pump oil are stored gradient. The remaining wells are farther from the in tanks installed in 1975. A program is under way site, with well cluster 16 upgradient, elusters 14 and to incinerate the degraded solvents and tritiated oil.

15 sidegradient, and the remaining wells In h! arch 1986, disposal operations for radioactive downgradient.

waste containinglead or any other listed hazardous substance were discontinued. A plan was imple-SOLID WASTE STOltAGE FACILITY mented to ensure that all other wastes are certified (BUltIAL GitOUNDS) to be free of hazardous materials.

The Solid Waste Storage Facility is between F The Burial Grounds are monitored by the wells of and II Areas (Fig. 4 2,Vol. II) and is used for storage the BG, blGA, htGC, htGE, htGG, and htGI series.

of radioactive solid waste produced at the plant and All of these wells are screened in the water table at shipped from other U.S. Department of Energy fa-a depth of 15 to 30 m. The namingof wells within the cilities. The original area (643.G) began receiving Burial Ground in this report is difTerent from presi-waste in 1952 and was filled in 1972. Operations ons annual reports. The water table at the Burial then shifted to an adjacent site, the 643 7G burial Grounds generally Cows toward the west except in ground. Site 643 2SG, an area within 643 7G, was the east corner, where the Dow is to the east.

denned in 1986. There are plans for the 643 7G site l

to be closed and capped.

Z AND ZW WELLS The Burial Grounds are used for disposal of transu.

The Z and ZW wells were originally installed as ranic (TRU) alpha waste, low level alpha and beta-pierometers in 1951 (Fig. 416, Vol. II). These pie-gamma waste, intermediate-level beta gamma rometers, which range from 7 to 26 m deep, measure waste, and waste generated of' site. Until 1965,TRU water table elevations in the separations areas, These wells also monit' r for groundwater contami.

waste was buried in plastic bags and cardboard o

boxes in earthen trenches. Between 1965 and 1974, nation that might exist within a large radius of P and l

TRU waste was segregated according to TRU con-II areas.

tent into two categories. Waste containing less than 0.1 Ci per package was buried unencapsulated in Z AltEA l

trenches. Waste containing greater than 0.1 Ci per l

package was buried in retrievable concrete contain-Z Area, located north of the intersection of Road F ers or encapsulated in concrete. Since 1974, transu-and Road 4,is being developed for the disposal of ranie wastes contaminated with greater than 10 nCi saltstone. The saltstone will be made by mixing TRU/g have been stored in water tight containers treated supernate from the high level waste tanks that can be retrieved intact for at least 20 years from with concrete. During 1987, three wells were in-I the time of storage. Containers are stored on a stalled in Z Area for groundwater monitoring. Wells i

concrete pad with a monitoring sump. Some bulky ZilG 1 and 2 monitor the water table. Well ZBG IP wastes are stored directly in shallow land burial monitors a perched water zone.

trenches. Since mid 1984, newly generated low-level waste has been placed in metal boxes or metal drums and is currently stored in trenches covered l

with soil shortly aRer emplacement.

4

Appendix C:

Environmental Permits Expiration Permit Number Tyng Tit]g Dals SC0000175 Wastewater SCDilEC Water Pollution Control Permit 12'31/88 (SPDES)

SC1890008989 liarardous SCDilEC OfUce of Ensironmental Quality W aste Control, Bureau of Solid and Ilazardous 9/30/92 Waste Management, liarardous Waste Permit SC1990008989 liarardous Environmental Protection Agency RCRA Waste llazardous Waste Permit 11/1/92 0300-0015 Air Permit to operate concrete batch plant, Steel Creek Dam construction project 0080 0060.CE Air 300 hTV Emergency Diesel Generator,654.T 0080-0046-CJ Air 455 DV Emergency Diesel Generator,72011 0080 0042 CC Air 455 DV Emergency Diesel Generator,720 2A 0080-0045.CJ Air 455 KW Emergency Diesel Generator,720 F 0080-0060 CP Air 1000 h7V Emergency Diesel Generator,6541T 0080-0045.Cl Air Silos and baghouse facility for naval fuel 0080 0042 01 Air Boiler (71.7 mmBta'hr) 784 A F31/89 0080-0042 02 Air Boiler (71.7 mmBta/hr) 784 A 931/89 0080-0042 03 Air Diesel Generator (600 KW) 794 A 5/31/89 0080 0042 04 Air Diesel Generator (400 KW) 773-A 9 31/89 0080 0042 05 Air Diesel Generator (200 DV) 703-A 5/31/89 0080-0043-01 Air Diesel Generator (150 KW) 108-4C 1/31/89 0080-0043-02 Air Dienel Generator (150 KW) 108 4C 1/31/89 0080-0043-03 Air Diesel Generator (1000 MV) 10810 1/31/89 0080-0043-04 Air Diesel Generator (1000 KW) 108 2C 1/31/89 0080-0044 01 Air Boiler (396 mmBtuhr) 484 D 2'25U89 0080 0044 02 Air Boiler (396 mmBtahr) 484 D 2'2 R'89 0080-0044 03 Air Boiler (396 mmBtuhr) 484 D 2'2A'89 0080-0044-04 Air Boiler (396 mmBtuhr) 484 D 2'2W89 0080-0044 05 Air Diesel Generator (150 DV) 501 D 22W89 0080-0044 06 Air Reject System (1.1 T/h7) 484.D 22R'89 0080-0044 07 Air Coal Crusher (300 T,hr) 484 D 2'2W89 0080 0045 05 Air U Dissolution 221.F l'2W89 1

0080 0045 06 Air Diesel Generator (200 MV) 254-5F.1 2/2W89 0080-004407 Air Diesel Generator (200 KW) 254-5F 2 2'2W89 i

0080-0045 08 Air Diesel Generator (175 DV) 772 F 1 2'2W89 0080-0045-09 Air Diesel Generator (175 DV) 772F 2 2'2W89 0080-0045 10 Air Diesel Generator (350 KW) 241-19F 2'2W89 0080-0045 11 Air Diesel Generator (350 IGV) 235-F 2'2W89 0080-0045 12 Air Diesel Generator (350 IGV) 254 4F 22W89 0080-0045-13 Air Diesel Generator (250 }GV) 2541F 2'2R89 0080-0045 14 Air Diesel Generator (200 KW) 24174F 2'2W89 0080-0045-15 Air Diesel Generator (600 lGV) 292-F 2'28J89 0080 0045-16 Air Diesel Generator (600 h3V) 2471F 2'2W89 0080-0045 17 Air Diesel Generator (315 IGV) 221.FB 22W89 0080-0045-18 Air Diesel Generator (415 KW) 7721F 2'2W89 0080-0045-19 Air Diew) Generator (300 IGV) 292 2F 2'2A89 0080 0045 20 Air Diesel Generator (300 }GV) 254 9F 2'2A 89 0080-0045 21 Air Diesel Generator (1000 KW) 221.F 2'2W89 Blank indicates no expiration date-1

174 SAVANNAH RIVEll PLANT - Environmental Report for 1987 Expiration Permit Number Tac Titic Date 0080 0045 22 Air Diesel Generator (600 KW) 25410F

?.'2R'89 0080 0046 01 Air Boiler (717 mmBtutr) 2841I a'31/89 0080-0046-02 Air Boiler (717 mmBta/hr) 28411 3'31/89 0080-0046 03 Air Boiler (717 mmBtahr) 284 !!

3'31/89 0080-0046 04 Air BGl(400 lbshr) a'31/89 0080-0016 05 Air Separation Process 22111 1'31/89 0080-0046 06 Air Diesel Generator (200 h3V) 234-411 3'31/89 0080 0046 07 Air Diewi Generator (200 h7V) 29911l l'31/89 0080 0046-08 Air Diesel Generator (200 KW) 24171!

3'31/89 0080-0016 09 Air Diesel Generetor (250 h7V) 254111 131/89 0080-0046 10 Air Diesel Generator (275 KW) 254-311 3'31/89 0080 0046-11 Air Diesel Generator (300 KW) 22111B 3'31/89 0080-0046 12 Air Diesel Generator (300 KW)254 5111 1'31/89 0080-0046-13 Air Ihesel Generator (300 h V) 254 5112 1'31/89 0080-0046 14 Air Ihesel Generator (300 h1V) 2321!

3'31/89 0080-0046-15 Air Diesel Generator (300 h3V) 234 l!

3'31/89 0080 0046 16 Air Dienel Generator (500 h7V) 232112 3/31/89 l

0080-0046 17 Air Diesel Generator (500 h7V) 254-11 a'31/89 i

0080-0046 18 Air Ihesel Generator (600 h3V) 29211 3'31/89 l

n080-004619 Air Dienel Generator (1000 KW) 221 11 a'31/89 l

0080-0047 01 Air Boiler (194 5 mmiltu/hr)184 K l'31/89 l

0080-0047 02 Air Boiler (191.5 mmBtuhr) 184 K l'31/89 l

0080 0047 03 Air Diesel Generator (1000 KW) 1081K W31/89 00S0-0047 04 Air thenel Generator (1000 h7D 108 2K

'l/31/89 0050 0047 05 Air Ihesel Generator (150 KW) 108 4K l'31/89 0080-0047-06 Air Ihesel Generator (150 KW) 108-4K 131/89 0080 0047 07 Air lhesel Generator (225 KW)152 7K a'31/89 0080 0049 01 Air Diesel Generator (1000 KW) 108-1L 4'30'89 l

0050 0049-02 Air Diesel Generator (1000 KW) 108 2L 4'3a'89 0080-0049 03 Air Diesel Generator (400 KW) 191 L 4'3aV9 0080-0049 04 Air Diesel Generator (150 KW) 108-4L 4'3a'89 0080-0049 05 Air Ihesel Generator (150 KW) 108-4L 4'3a'89 0080-0049 06 Air Diesel Generator (225 KW) 152 7L 4'3a?9 0080 0055-01 Air U Metal Cleaning 313 M a'31/89 i

0080-0055 02 Air Al Tube Cleaning 321 M 3'31/89 l

0080-0055-03 Air Diesel Generator (200 KW) 320-M 331/89 0080-0055 04 Air Air Stripper (400 gpm) 3'31/89 0080 0048-01 Air Boil-r(104.5 mmBtuhr)184 P 4'3a39 0080 0048 02 Air Boiler (194 5 mmBtu'hr) 184 P 4'3as9 0080-0048-03 Air lhe sel Generator (1000 KW) 1081P 4'30'89 0080 0048-04 Air Diesel Generator (1000 KW) 103-2P 4'3039 l

0080-0048 05 Air Ihemel Generator (150 KW) 108-4P 4'3a?9 0050 0048 06 Air thesel Generator (150 KW) 108-4P 4'3439 0080-0048 07 Air lhesel Generator (225 KW)152 7P 4'34'89 l

0080-0066-01 Air Cement Silo (540 T,hr) s'31/89 0080-0066-02 Air Fly Ash Silo (540 Tehr) 5'31/89 0080-0066 03 Air Mixer (540 T,hr) 531/89 0080-0066 04 Air New Cen bilo( A4 Tehr) 531/89 0080 0060-01 Air Ihesel Generator (750 h3V) 673-T 5/31/89 0080-0060 02 Air Diesel Generator (300 KW) 672 T 5'31/89 0080-0060 03 Air lhesel Generator (300 KW) 673-T

&'31/89 0080-0060-04 Air Shiro Incinerator (20 lbshr) 5'31/89 0080-0060-05 Air P)[EF 6R2-T 531/89 IS 23 W lbmestic Water DWPF '1T. emergency water supply 200092 Ikmestic Water Deep Wells,905-104L,904105L Blank indicates no espiration date-1

Appendix C 175 Expiration Permit Number Iyng litle Date 48061 Domestic Water Temporary water supply 905104L,904105L 402874 Domestic Water Segregated domestic water supply,30W700 Area, phase 1 403434 Domestic Water Segregated domestic water supply,304700 Area, phaw !!

LS4.W Domestic Water Water line, omce building,70341 A 13 1.W Domestic Water Water line, tritium facilities support building, 235 li 405184 Domestic Water Water line,77341 A, 773-42A LS-7 W Domestic Water Water line navel fuels material facility,221 17F, 22118F LS-8 W Domestic Water Water line,7034A,703-6A,703-34 A LS 11.W Domestic Water Water line navel fuels material facility,247 F 208434 Domestic Water Domestic water system, barricades,70160, 701 12G,701 13G 209454 Domestic Water TNX domestic water system and well 409484 Domestic Water Water line, reactor simulator facility, 707-C 201715 Domestic Water Domestic deepwell, railroad classification yard, 905-107C 202915 Domestic Water Polyphosphate feed system, TC S Area well 402925 Domestic Water DWTF temporary domestic water 202915 Domestic Water Water supply and well system, D%TP construction support area LS 25 W Domestic Water Chemical feed facility water system,100 C 206575 Domestic Water Domestle water deepwells and distribution line, A Area 207005 Domestic Water Activated carbon treatment system,3,700 Area 408285 Domestic Water Domestic water service for sanitary waste treatment facility, TNX LS43.W Domestic Water Technical area water main bypass, 77314 A 408595 Domestie Water Domestic water line, construction omce building, 300 M 409955 Domestic Water llelicopter facility domestic water line LS 54.W Domestic Water Domestic w ater line,707.!!

LS-56 W Domestic Water Nmestic water supply for chemleal feed facilities in G&ll Areas (11)

LS-55.W Domestic Water Domestic water supply for chemical feed facilities in Gall Areas (G)

LS-57.W Domestic Water Domestie water line relocation & senice line install 73511 A 411995 Domestic Water Water distribution system,340-M,341.M 208425 Domestic Water ATTA domestic water system LS-61.W Domestic Water Domestic water line to feed D%TF sanitary treatment plant 1&60 W Domestic Water Domestic water line for 704 S administration building D%TF LS-59 W Nmestic Water Water sy stem DWTF ice house 41225 Domestic Water 3M00 A Area waterline from new domestie wells 212745 Domestic Water D%TF domestic water wells 1 and 2 401446 Domestic Water Production control facility for 200 Area process 7721F 402186 Domestic Water DWTF domestic water distribution system i

203786 Domestie Water Drinking water well 905114G,6813G LS-81.W Dumestic Water Dornestic water for construction omco building, i

C-Area Blank indicates no espiration dats.

]

9 4

176 SAVANNAH RIVER PLANT - Environmental Report for 1987 Expiration Permit Number Tyne Title Date LS-82-W Domestic Water Domestic water for sanitary treatment facility, U-Area 405556 Domestic Water Domestic water system,200-H 405566 Domestic Water Domestic water system,200 F 208866 Domestic Water Domestic water well for Aiken barneade gate house 701-5G LS 106-W Domestic Water DWPF auxiliary pump pit water lines, S-511 410406 Domestic Water Drinking water system,777-A LS-115 W Domestic Water Water line, crafts and engineers, CAB / Cantle Shop LS-118-W Domestic Water Waer line, 719-4A 111626 Domestic Water Upgrade gaseous chlorination facility, DC Areas LS-119-W Domestie Water Water line,730-hi 400347 Domestic Water Domestic water headers, TNX Area 400367 Domestic Water Fuel productbn facility water system,225-H LS-139 W Domestic Water Replace tritium facility domestic water,233-H, 249-H 400737 Domestic Water Water line DWPF, Z Area 203427 Domestic Water Sodium hypochlorite system,280 F 203467 Domestic Water Sodium hypochlonte system,280 H 205217 Domestic Water Upgrade instrumentation 280-1, F/H Areas 205877 Domestic Water Augusta barricade water well,905116G 406137 Domestic Water Int 4 s storage and redrumming facility, dom

.c water 7091G,709-2G 208177 Domestic Water Phos, ste feed system, B Area LS-178 W Domestic Water Computer repair building domestic water,722-5A LS-135 W Domestic Water Domestic water main,901 A LS-187 W Domestic Water ETF F lift station domestic water 210 657 Domestic Water Drinking water well and distribution system, 905-39F 411357 Domestic Water ETF F lift station domestic water 412917 Domestic Water Drinking water system, ETF,241-84H,241-81H 441118 Domestic Water Domestic water for NWTF 233638 Domestic Water Replace Allendale barricade well f.03628 Domestic Water Replace pistol range well

'204138 Domestic Water Replace domestie deepwell,905-94K 204198 Domestic Water Replace domestic deepwell,905-66H 404618 Domestic Water 705-C domestic water 404608 Domestic Water 717.K domestic water LS-233 W Domestic Water Temporary domestic water for F&H ETF construction offlee i

LS 238-W Domestic Water Temporary domestic water for FPF a RTF facilities LS-238 W Domestic Water ECF/CAS security upgrade facilities, H Area 411337 Domestic Water Install sodium hypochlorite system,780-A DWP-087A Ind. Solid Waste Sanitary landfill expansion IWP 210 Ind. Solid Waste D F steamline erosion control site IWP 211 Ind. Solid Waste 200-H erosion control site IWP 212 Ind. Solid Waste Coal-ash waste landfill,100-P Area IWP-219 Ind. Solid Waste 200-F erosion control site 10,349 Ind. Wastewater 672 T TNX process sewer to outfall X-008 10,389 Ind. Wastewater hi Area drain line 11,413 Ind. Wastewater DWPF chemical tret tment facility,8 Area 11,760 Ind. Wastewater Wastewater for PCB clean up,320 51 10,920 Ind. Wastewater SREL wastewater disinfection facility 7289 Ind. Wastewater "As built" wastewater treatment facilities, A and hi Areas Blank indicates no expiration date.

1 l

l Appendix C 177 Expiration i

Permit Number Txan Title Hain 7290 Ind. Wastewater "As built" wastewater treatment facilities, F Area l

7291 Ind. Wastewater "As built" wastewater treatment facilities, II Area l

7292 Ind. Wastewater "As built" wastewater treatment facilities, P Area l

7293 Ind. Wastewater "As built

wastewater treatment facilities, K Area 7294 Ind. Wastewater "As built" wastewater treatment facilities, C Area 7295 Ind. Wastewater "As built" wastewater treatment facilities, D Area 7296 Ind. Wastewater "As built" wastewater treatment facilities, CS Area 9886 Ind. Wattawater M Area 50 gpm air stripper 9974 Ind. Wastewater Concrete batch plant, S Area 10,253 Ind. Wastewater M Area 330 gpm air stripper 10,287 Ind. Wastewater Liquid emuent treatment facilities,300 M 10,358 Ind. Wastewater S Area oil separator 10,469 Ind. Wastewater 735-11A lab building process sewer system neutralization facility 10,475 Ind. Wastewater Non contact cooling water diversion,300-M Area 10,696 Ind. Wastewater Interim sludge storage tank M Aret-10,765 Ind. Wastewater Wastewater neutralization facility,704 U 10,778 Ind. Wastewater Wastewater treatment facility, naval fuels LS-42-S Ind. Wastewater Inert L facility loading dock sewer relocation, 234 11 10,995 Ind. Wastewater DWPF concrete batch plant wastewater treatment pond, S Area 10,949 Ind. Wastewater Trade waste flow equalization tank,60718A LS-53-S Ind. Wastewater Sanitary sewer line construction esflice line, M Area 11,411 Ind. Wastewater DWPF treated emuent line 11,406 Ind. Wastewater Fire brigade training facilities oil separator,411 D 11,498 Ind. Wastewater Flow monitoring station for NPDES outfall L-007 11,497 Ind. Wastewater Production control facility sanitary / process sewer 772-1F 11,588 Ind. Wastewater Powerhouse emuent diversion to ash basins, D/II Areas 11,589 Ind. Wastewater Powerhouse emuent diversion to ash basins, K&P Areas 11,971 Ind. Wastewater Carbon bed piping for organics removal demonstration project TNX 12,622 Ind. Wastewater Organics removal facility, TNX 10,633 Ind. Wastewater Emuent treatment plant, TNX 12,888 Ind. Wastewater Metallurgicallaboratory neutralization facility, 723-A 12,973 Ind. Wastewater P Area neutralization facility,183-2P 13,286 Ind. Wastewater Portable chromium removal system, SRL 13,354 Ind. Wastewr

D Area Neutralization facility,4831D 13,355 Ind. Wastewater F Area neutralization facility,280-1F 13,356 Ind. Wastewater 11 Area neutralization facility,28011 13,357 Ind. Wastewater K Area neutralization facility,183 2K 13,431 Ind. Wastewater Flume at M 0004 outfall 13,456 Ind. Wastewater L Tank "as built" 13,734 Ind. Wastewater Industrial wastewater pli control system,211 11 13,735 Ind. Wastewater Industrial wastewater pli control system,211 F 12,773 Ind. Wastewater L Lake thermal barrier curtain 12,683 Ind. Wastewater Z Area saltstone mfg. facility 12,782 Ind. Wastewater Peplacement tritium facility process sewer 12,070 Ind. Wastewater Emuent treatment facility F/II Area 12,894 Ind. Wastewater Filtrate hold tank covers, M Area Blank indicates no expiration date.

e 178 SAVANNAH RIVER PLANT - Environmental Report for 1987 l

Expiration Permit Number Iyme Title Date 12,922 Ind. Wastewater Naval fuel facGty modifications 13,105 Ind. Wastewater ETF process sewerlines, F/II Area Lc '86-S Ind. Wastewater FPF process sewer line s,154 Ind. Wastewater Flow measurement device, L Area 13,457 Ind. Wastewater L Tank mercury removal LS-10-S

'an. Waste Sanitary sewer system, ntwal fuels material facility,248 F 14,443 San. Wastewater Septic tank and tile field,11 Area 9256P San. Wastewater Septic tank and tile field landfill monitoring building 642-G 8611 P San. Wastewater Septic tank and tile field CS Area 7091G 13,717 San. Wastewater Wastewater treatment facility Z Area 8881 San. Wastewater Flow equalization basin,700 A 8928 San. Wastewater FMF sanitary waste trer.tment plant 9326 San. Wastewater Sanitary wastewater treatment plant F,II, P&G Areas LS 3-S San. Wastewater Sanitary sewer system oflice building 703-41 A LS 2-S San. Wastewater Sanitary sewerline tritium facilities support building 23511 9694 San. Wastewater Sanitary sewer system,773-41A,773-42A 9888 San. Wastewater DWPF sanitary waste treatment plant 9940 San. Wastewater Sanitary sewer system, reactor simulator facility, 707-C 9983 San. Wastewater Sanitary treatment plan,100-C Area 10,236 San. Wastewater Lift station, change station facility,241-5811 10,499 San. Wastewater DWPF sanitary sewer system,200S 10,521 San. Wastewater Chemical feed facility, A Area 10,522 San. Wastewater Chemical feed facility, F Area 10,523 San Wastewater Chemical feed facility,II Area 10,524 San. Wastewater Chemical feed facility, P Area 10,525 San. Wastewater Chemical feed facility, G Area 10,526 San. Wantewater Chemical feed facility, D Area LS-32-S San. Wastewater Sanitary sewer line, Wackenhut building, TC/U Area 10,530 San. Wadewater TNX sanitary wastewater treatment plant 607-40-G LS-35-S San. Wastewater Sanitary sewer relocation, building 73511A 10,825 San. Wastewater Sanitary sewerlift station,60719 A 10,906 San. Wastewater Sanitary sewer,341 M LS 52-S San. Wastewater Sanitary sewer,70711 11,407 San. Wastewater Sanitary waste transfer station 321 M change room renovation 11,442 San. Wastewater Lift station force main,2418211 LS 78-S San. Ws.stewater Sanitary sewer line for construction oflice building C Area LS-80-S San. Wastewater Sanitary sewerline receiving & stores warehouse construction central shops LS 79-S San. Wastewater Sanitary sewer line electrical office building construction central shops 11,847 San. Wastewater Efiluent weir for sanitary treatment system, TNX 11,847 San. Wastewater Efiluent weir, TNX LS-98-S San. Wastewater Sanitary sewer addition, S Area 11,615 San. Wastewater Sanbary treatment plant U Area LS 112-S San. Wastewater Fhe training facility process sewer 904-D LS.129-S San. Wastewater Sanitary sewer,719-4A LS 134-S San. Wastewater DWPF sanitan sewer line modification Blank indicates no expiration date.

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Appendix C 179 Expiration Permit Number Tyne Titic Date 12,383 San. Wastewater Fuel production facility sanitary sewer,22511 12,386 San. Wastewater Sanitary sewer,730 M 12,453 San. Wastewater Bromide feed system,607-18F 12,452 San. Wastewater Bromide feed system,607-19L 12,498 San. Wastewater P Area STP Phase II LS-149-S San. Wastewater Sanitary sewer, TNX ETP l

LS 158-8 San. Wastewater Sanitary sewer,3/700 construction facility i

12,725 San. Wastewater F Area STP Phase III 12,910 San. Wastewater Sanitary treatment facility, II Area 13,155 San. Wastewater Naval fuels flow measurement device outfall F-003(A) 13,175 San. Wastewater Flow equalization basin, building 607-22A LS-206 S San. Wastewater Sewer pipe and manhole,704-1T TNX 9998 San. Wastewater Septic tank and drain field for P&ll ETF 10,131 P San. Wastewater Septic tank and drain field for RTF construction engineers office 10,132-P San. Wastewater Septic tank and drain field for FTP construction engineers office LS 227-S San. Wastewater 705-C sanitary sewer LS 228-S San. Wastewater 717 K sanitary sewer LS-239 S San. Wastewater ECF/CAS security upgrade facilities, F Area LS 240-S San. Wastewater 3/700 Area security upgrade, building 720 2A LS-244-S San Wastewater ECF/CAS security upgrade facilities,11 Area 10,314 San. Wastewater DWPF construction site sanitary sewer system LS-62-S San. Wastewater 717.F sanitary sewer relocation for DWPF 12,695 San. Wastewater Replacement tritium facility sanitary sewer LS 168-S San. Westewater A Area sanitary sewer 13,156 San. Wastewater 716-2A sanitary sewer 13,157 San. Wastewater Computer repair building sanitary sewtr,722 5A 13,173 San. Wastewater Sanitary sludge land application, K Area and Par Pond borrow pits 13,430 San. Wastewater Sanita.y sewage treatment facility,607-21F 12,076 Ind. Solid Waste Sanitary sludge land application, F&ll Area borrow pit Blank indicates no expiration date.

TRADITIONAL AND NGW RADIOLOGICAL UNITS (Conventional units are in parentheses)

Expression in Terms of Quantity Name Symbol other Units activity bequerel Bq 1 dps (curie)

Cl 3.7 x 10Bq absorbeddose '

gray Gy jag' (rad) rad 10'* Gy dose equivalent sievert Sv.

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(rem)

. rem 10 Sv exposure coulombper kilogram CAg5 (roentgen)

R 2.58 x 10 CAg '

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