Page 1 of 47

DOE Review Release: 06/24/2020 

Lawrence Livermore National Laboratory – 

Occupational Environmental Dose

ORAUT-TKBS-0035-4 Rev. 02

Effective Date: 06/09/2020

Supersedes: Revision 01

Subject Expert(s): Mutty M. Sharfi, Matthew H. Smith, and Stephen Spanos

Document Owner 

Approval: Signature on File

Stephen Spanos, Document Owner

Approval Date: 06/05/2020

Concurrence: Wade C. Morris Signature on File for

John M. Byrne, Objective 1 Manager

Concurrence Date: 06/05/2020

Concurrence: Signature on File

Scott R. Siebert, Objective 3 Manager

Concurrence Date: 06/05/2020

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 06/05/2020

Approval: Signature on File

Timothy D. Taulbee, Associate Director for Science

Approval Date: 06/09/2020

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.

New Total Rewrite Revision Page Change 
Document No. ORAUT-TKBS-0035-4 Revision No. 02 Effective Date: 06/09/2020 Page 2 of 47

 

PUBLICATION RECORD

EFFECTIVE

DATE

REVISION

NUMBER DESCRIPTION

11/18/2005 00 New technical basis document for the Lawrence Livermore National 

Laboratory (LLNL) – Occupational Environmental Dose. Training 

required: As determined by the Task Manager. Initiated by Jay J. 

Maisler.

03/16/2010 01 Text revised to address comments from Objective 1 management 

and Objective 3. Adds Attributions and Annotations section. 

Incorporates formal internal and NIOSH review comments. 

Incorporates additional data on environmental neutron 

measurements and SEC Class recommended by NIOSH. 

Constitutes a total rewrite of the document. Training required: As 

determined by the Objective Manager. Initiated by Matthew H. 

Smith, Stephen Spanos, and Ralph W. Kenning.

06/09/2020 02 Revised to address the cancellation of ORAUT-PROC-0060. 

Incorporates onsite ambient dose data and air concentration data

through 2018. Revised 1952 to 1972 tritium air concentration data. 

Revised to update environmental data tables and references before 

second formal internal review. Incorporates formal internal and 

NIOSH review comments. Constitutes a total rewrite of the 

document. Training required: As determined by the Objective

Manager. Initiated by Stephen Spanos.
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TABLE OF CONTENTS

SECTION TITLE PAGE

Publication Record.................................................................................................................................. 2

Acronyms and Abbreviations.................................................................................................................. 5

4.1 Introduction ................................................................................................................................. 7

4.1.1 Purpose........................................................................................................................... 8

4.1.2 Scope.............................................................................................................................. 8

4.1.3 Special Exposure Cohort ................................................................................................ 9

4.2 Internal Dose from Onsite Atmospheric Radionuclide Concentrations ....................................... 9

4.2.1 Ambient Air Sample Collection Network ......................................................................... 9

4.2.1.1 Before 1959...................................................................................................... 9

4.2.1.2 1959 through 1971 .........................................................................................10

4.2.1.3 After 1971.......................................................................................................10

4.2.1.4 Purpose and Placement of Sampling Locations.............................................11

4.2.1.5 Radionuclides of Significance ........................................................................13

4.2.2 Sampling and Analysis Methods ...................................................................................13

4.2.3 Estimation of Potential Annual Intakes from Airborne Radionuclides ...........................15

4.2.3.1 Gross Alpha and Gross Beta, before 1959 ....................................................16

4.2.3.2 Gross Alpha and Gross Beta, 1959 to 1970...................................................16

4.2.3.3 Tritium, 1952 to 1972 .....................................................................................18

4.2.3.4 Tritium, Uranium, and Plutonium, after 1970..................................................19

4.3 Intakes from Tritium in Drinking Water, 1952 to 2018...............................................................21

4.4 Ambient Radiation.....................................................................................................................23

4.4.1 Gamma Radiation .........................................................................................................23

4.4.2 Neutron Radiation .........................................................................................................25

4.5 Attributions and Annotations .....................................................................................................29

References ...........................................................................................................................................31

Glossary................................................................................................................................................47
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LIST OF TABLES

TABLE TITLE PAGE

4-1 Main site ambient air sampling station locations.......................................................................10

4-2 Site 300 ambient air sampling station locations........................................................................12

4-3 Main site estimated air concentrations and annual median intakes via inhalation, 1952 to 

1958..........................................................................................................................................17

4-4 Site 300 estimated air concentrations and annual median intakes via inhalation, 1955 to 

1960..........................................................................................................................................17

4-5 Main site maximum annual median air concentrations and estimated annual intakes via 

inhalation, 1959 to 1970............................................................................................................17

4-6 Site 300 maximum annual median air concentrations and annual intakes via inhalation, 

1961 to 1970.............................................................................................................................18

4-7 Main site maximum annual median air concentrations and annual intakes via inhalation, 

1971 to 2018.............................................................................................................................20

4-8 Site 300 maximum annual median air concentrations and annual intakes via inhalation, 

1971 to 2018.............................................................................................................................22

4-9 Main site external gamma radiation..........................................................................................26

4-10 Site 300 external gamma radiation ...........................................................................................27

4-11 Main site external neutron radiation..........................................................................................29

LIST OF FIGURES

FIGURE TITLE PAGE

4-1 Main site air particulate and tritium sampling locations.............................................................11

4-2 Site 300 and downtown Tracy air particulate and tritium sampling locations............................12

4-3 Calculated annual median concentrations of 239+240Pu, 1986 to 2005.......................................21

4-4 Main site gamma dosimeter locations, 2001.............................................................................24

4-5 Site 300 and vicinity gamma dosimeter locations, 2001...........................................................25

4-6 Main site neutron dosimeter locations, 1969 to present ...........................................................28
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ACRONYMS AND ABBREVIATIONS

aCi attocurie (1 × 10-18 Ci)

AEC U.S. Atomic Energy Commission

AWE atomic weapons employer

Bq becquerel

CEDE committed effective dose equivalent

Ci curie

d day

DCG derived concentration guideline

DOE U.S. Department of Energy

DOL U.S. Department of Labor

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000

EPA U.S. Environmental Protection Agency

Ge(Li) lithium-drifted germanium

hr hour

HT tritiated hydrogen gas

HTO tritiated water vapor

ICT Insulating Core Transformer

in. inch

kCi kilocurie

L liter

LBNL Lawrence Berkeley National Laboratory

LLNL Lawrence Livermore National Laboratory

m meter

MeV megaelectron-volt, 1 million electron-volts

MEI maximally exposed individual

MFAPs mixed fission and activation products

mi mile

min minute

mrem millirem

mSv millisievert

nBq nanobecquerel

NESHAPs National Emissions Standards for Hazardous Air Pollutants

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

PBq petabecquerel (1 × 1015 Bq)

s second

SEC Special Exposure Cohort
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SRDB Ref ID Site Research Database Reference Identification (number)

TBD technical basis document

TBq terabecquerel (1 × 1012 Bq) 

TLD thermoluminescent dosimeter

U.S.C. United States Code

wk week

yr year

χ/Q atmospheric dispersion coefficient

§ section or sections
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4.1 INTRODUCTION

Technical basis documents (TBDs) and site profile documents are not official determinations made by 

the National Institute for Occupational Safety and Health (NIOSH) but are rather general working 

documents that provide historical background information and guidance to assist in the preparation of 

dose reconstructions at particular U.S. Department of Energy (DOE) or Atomic Weapons Employer 

(AWE) facilities or categories of DOE or AWE facilities. They will be revised in the event additional 

relevant information is obtained about the affected DOE or AWE facility(ies), such as changing 

scientific understanding of operations, processes, or procedures involving radioactive materials. 

These documents may be used to assist NIOSH staff in the evaluation of Special Exposure Cohort 

(SEC) petitions and the completion of individual dose reconstructions under Part B of the Energy 

Employees Occupational Illness Compensation Program Act of 2000 (EEOICPA). 

In this document the word “facility” is used to refer to an area, building, or group of buildings that 

served a specific purpose at a DOE or AWE facility. It does not mean nor should it be equated to an 

“AWE facility” or a “DOE facility.” The term “AWE facility” is defined in EEOICPA to mean “a facility, 

owned by an atomic weapons employer, that is or was used to process or produce, for use by the 

United States, material that emitted radiation and was used in the production of an atomic weapon, 

excluding uranium mining or milling” [42 United States Code (USC) 7384I(5)]. On the other hand, a 

DOE facility is defined as “any building, structure, or premise, including the grounds upon which such 

building, structure, or premise is located—(A) in which operations are, or have been, conducted by, or 

on behalf of, the [DOE] (except for buildings, structures, premises, grounds, or operations ... 

pertaining to the Naval Nuclear Propulsion Program); and (B) with regard to which the [DOE] has or 

had—(i) a proprietary interest; or (ii) entered into a contract with an entity to provide management and 

operation, management and integration, environmental remediation services, construction, or 

maintenance services” [42 USC 7384I(12)]. The DOE determines whether a site meets the statutory 

definition of an AWE facility and the U.S. Department of Labor (DOL) determines if a site is a DOE 

facility and, if it is, designates it as such.

Under EEOICPA, a Part B cancer claim for benefits must be based on an energy employee’s eligible 

employment and occupational radiation exposure at a DOE or AWE facility during the facility’s 

designated time period and location (i.e., a “covered employee with cancer”). After DOL determines 

that a claim meets the eligibility requirements under Part B of EEOICPA, DOL transmits the claim to 

NIOSH for a dose reconstruction. EEOICPA provides, among other things, guidance on eligible 

employment and the types of radiation exposure to be included in an individual dose reconstruction. 

Under EEOICPA, eligible employment at a DOE facility includes individuals who are or were 

employed by DOE and its predecessor agencies, as well as their contractors and subcontractors at 

the facility [42 USC 7384I(11)]. Also under EEOICPA, the types of exposure to be included in dose 

reconstructions for DOE employees are those radiation exposures incurred in the performance of 

duty. As such, NIOSH includes all radiation exposures received as a condition of employment at DOE 

facilities in its dose reconstructions for covered employees, which may include radiation exposures 

related to the Naval Nuclear Propulsion Program at DOE facilities, if applicable. This is because 

NIOSH does not determine the fraction of total measured radiation exposure at a DOE facility that is 

contributed by the Naval Nuclear Propulsion Program at the DOE facility during a specified period of 

time for inclusion in dose reconstruction.

NIOSH does not consider the following types of exposure as those incurred in the performance of 

duty as a condition of employment at a DOE facility. Therefore these exposures are not included in 

dose reconstructions for covered employees [NIOSH 2010]: 

• Background radiation, including radiation from naturally occurring radon present in 

conventional structures, and

• Radiation from X-rays received in the diagnosis of injuries or illnesses or for therapeutic 

reasons. 
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4.1.1 Purpose

This technical basis document (TBD) documents historical practices at Lawrence Livermore National 

Laboratory (LLNL) in Livermore, California, and provides information for the evaluation of 

environmental radiation exposure data. It can serve as a supplement to, or substitute for, individual 

monitoring data.

LLNL began operations in 1952 as the University of California Radiation Laboratory, which was a 

branch of what is now the Lawrence Berkeley National Laboratory (LBNL). It was later known as the 

Lawrence Radiation Laboratory and the Lawrence Livermore Laboratory before assuming its current 

name. The University of California operated LLNL for DOE and its predecessor agencies from 1952 

through September 2007, when a partnership of the University of California, Bechtel Corporation, 

Babcock and Wilcox, the URS Corporation, and Battelle Memorial Institute assumed this role. 

Lawrence Livermore National Security has operated the site since then. Throughout its history, LLNL 

has processed and handled a variety of radionuclides, including uranium and transuranic elements, 

mixed fission and activation products (MFAPs), and accelerator-produced isotopes. This TBD 

discusses two sites: the main site (Site 200) where research and development activities have taken 

place since 1952 and Site 300 where explosive testing experiments have occurred. Site 300 

explosive testing included depleted and natural uranium, natural thorium, and tritium triggers. 

Site 300 began operations in 1955. This TBD addresses potential for internal dose from the breathing 

of airborne concentrations of radionuclides that have been released on the LLNL site. 

The receptors of concern in this TBD are unmonitored workers, namely LLNL employees who did not 

wear external dosimetry or who were not monitored for internal exposures. Initially, LBNL (Site 100) 

provided LLNL with beta/gamma film dosimeters including processing and pocket ionization chambers 

(Thompson 1953). The practice of providing film and pocket dosimeters to all workers has been in 

effect since March 1953 (Thompson 1953). In 1958, film badges became part of the security badge 

(Nolan 1958), which effectively mandated that all workers wear film dosimeters at all times. There is 

ongoing collaboration between LLNL and LBNL. To provide the basis for estimating the 

environmental dose for years when monitoring did not occur, this TBD provides annual intakes to 

2018 and ambient external doses from 1952 (1955 for Site 300) to 2018 (the last year with publicly 

available ambient external data for the revision to address cancellation of ORAUT-PROC-0060). 

4.1.2 Scope

Occupational environmental dose refers to dose from exposures workers received while on the site 

but outside the facilities at LLNL from elevated ambient radiation, facility discharges to the 

environment, and resuspension of radionuclides in soils. Effluents can result in internal and external 

exposures by inhalation of airborne radionuclides, ingestion of radionuclides, and exposure to external 

radiation. This TBD describes the estimated annual intakes for inhalation exposure and the estimated 

radiation doses as a result of ambient exposures at LLNL. Environmental measurements do not

distinguish sources of emissions and, therefore, reflect air concentrations from nearby as well as 

distant sources. The estimates of emissions were useful in filling some gaps in measurement data 

and were critical to estimating exposures before the start of comprehensive and routine measurement 

data reports.

Section 4.2 of this TBD contains detailed information about the collection and analysis of air samples 

and the use of this information for dose reconstruction. There was a potential for ingestion of 

radioactive materials from ingestion of water that might have contained tritium (Section 4.3). 

Section 4.4 describes the potential external doses from sources of radiation outside the process 

buildings.

Attributions and annotations, indicated by bracketed callouts and used to identify the source, 

justification, or clarification of the associated information, are presented in Section 4.5. 
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4.1.3 Special Exposure Cohort

The Secretary of the U.S. Department of Health and Human Services has designated the following 

classes of LLNL employees as additions to the SEC: 

Employees of the DOE, its predecessor agencies, and DOE contractors or 

subcontractors who were monitored for radiation exposure while working at the 

Lawrence Livermore National Laboratory from January 1, 1950, through December 31, 

1973, for a number of workdays aggregating at least 250 workdays or in combination 

with workdays within the parameters established for one or more other classes of 

employees in the Special Exposure Cohort (Leavitt 2008). 

All employees of the Department of Energy, its predecessor agencies, and their 

contractors and subcontractors who worked at the Lawrence Livermore National 

Laboratory in Livermore, California from January 1, 1950 through December 31, 1973, 

for a number of work days aggregating at least 250 work days, occurring either solely 

under this employment or in combination with work days within the parameters 

established for one or more other classes of employees in the Special Exposure Cohort

(Sebelius 2010). 

All employees of the Department of Energy, its predecessor agencies, and its contractors 

and subcontractors who worked in any area at the Lawrence Livermore National 

Laboratory in Livermore, California, during the period from January 1, 1974 through 

December 31, 1989, for a number of work days aggregating at least 250 work days, 

occurring either solely under this employment or in combination with work days within 

the parameters established for one or more other classes of employees in the SEC

(Burwell 2016). 

NIOSH determined that doses to monitored workers from MFAPs at LLNL cannot be reconstructed

with sufficient accuracy from 1950 through 1973 (NIOSH 2007). In addition, NIOSH determined that 

doses to unmonitored workers from MFAPs at LLNL cannot be reconstructed with sufficient accuracy 

between 1950 and 1973, inclusive (NIOSH 2010b). Further, NIOSH determined that internal doses 

from 233U at LLNL cannot be reconstructed with sufficient accuracy from 1974 through 1989 (NIOSH 

2016).

Each SEC class includes all workers during the SEC period. Because of the identified dose 

reconstruction infeasibility, all dose reconstructions for all workers having employment during an SEC 

period are considered partial dose reconstructions. If monitoring data are available for workers in the 

SEC, dose is to be assigned as appropriate based on such data. However, such dose 

reconstructions are considered partial dose reconstructions because exposure to MFAPs and 233U 

during the respective LLNL SEC periods cannot be reconstructed. 

4.2 INTERNAL DOSE FROM ONSITE ATMOSPHERIC RADIONUCLIDE CONCENTRATIONS

4.2.1 Ambient Air Sample Collection Network

4.2.1.1 Before 1959

A review of records indicates that the earliest available environmental monitoring data for the LLNL

main site was 1959 (Beaufait 1961) and that for Site 300 was 1961 (LRL 1962). Before the 1980s, 

the LLNL mission was almost exclusively weapons research. Therefore, it was assumed that the 

radionuclide emission rate would be proportional to the weapons-related activity at the site from 

design, fabrication, and analysis of samples that were retrieved after a test. The peak for testing at 

LLNL was from 1962 through 1971 with an average of 31 tests per year (DOE 2000). From 1953 
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through 1961, LLNL sponsored an average of 7 tests per year (DOE 2000). During the entire period 

of LLNL-sponsored weapons testing from 1953 through 1992 the average was 14.5 per year. 

It was assumed that all activity that was detected at the monitoring stations was from LLNL activities. 

This assumption is conservative because this was during a time of high fallout due to atmospheric 

testing, and in many cases offsite locations had higher activity than onsite locations due to the fallout. 

Therefore, for the early years before monitoring, dose reconstruction should use the highest 

measured results from the later years in which monitoring occurred. Section 4.2.3.1 provides 

estimated intakes based on the highest measured activity, despite location, as being favorable to 

claimants. For workers that should have been monitored, intakes based on co-exposure data might 

be more appropriate than environmental data.

4.2.1.2 1959 through 1971

Air samples were collected in seven locations around the main site, including two perimeter locations 

(LRL 1962). The two perimeter locations, southeast perimeter and west perimeter, were collected 

continuously for a 7-day period on HV-70 paper 4 in. wide by 9 in. long (LRL 1962). The other air 

sampling stations were at a variety of distances from along the perimeter to as far as 5 mi from the 

perimeter (LRL 1962). Table 4-1 lists the seven onsite sampling stations this analysis used for 

estimates of occupational environmental exposures, and Figure 4-1 shows their locations as black 

dots. The SALV and MESQ locations were established as early as 1961 for perimeter air monitoring 

(LRL 1962). An air sampling station was added on the east side of LLNL in 2000. This station, 

CRED, was near the area representative of the maximally exposed individual (MEI) for LLNL. 

Table 4-1. Main site ambient air sampling station locations (Gallegos et al. 2002). 

Designation Location

Direction from

center of LLNL

COW At security fence north of outer loop road N

MET Meteorological station NW

VIS At security fence near east entrance E

CAFÉ At security fence near south entrance S

SALV At security fence near southeast perimeter fence SE

MESQ At security fence near west entrance W

CRED Solar evaporators for plutonium waste processing; representative of MEI SE

At Site 300, six air sampling stations were established in 1962, each within the site perimeter. The air 

sampling equipment at Site 300 was equivalent to the equipment at the main site. Table 4-2 lists 

these stations, and Figure 4-2 shows their locations. The Bunker 801E, ECP, EOBS, GOLF, WCP, 

and WOBS locations were established in 1962. As stated above, this was during a time of high fallout

due to atmospheric testing, and in many cases offsite locations had higher activity than onsite 

locations due to the fallout. Therefore, Section 4.2.3.1 presents intakes estimated from the highest 

measured activity, despite location, as being favorable to claimants.

4.2.1.3 After 1971

In 1971, LLNL established a network of permanent stations to collect air samples from the site 

perimeter and other locations inside the site (Gallegos et al. 1992). LLNL collected and analyzed air 

samples for gross alpha and gross beta radiations, such as 90Sr, 238Pu, and 239+240Pu, and 235U and 

238U. The existing monitoring networks were established in 1992 for surveillance of air particulates 

and tritium in and around the Livermore site and Site 300, as well as in the surrounding Livermore 

Valley and the City of Tracy (Gallegos et al. 1992). Tables 4-1 and 4-2 list the stations, and 

Figures 4-1 and 4-2 show their locations; black triangles represent tritium monitoring stations. As 

stated above, this was during a time of high fallout due to atmospheric testing and in many cases 
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Figure 4-1. Main site air particulate and tritium sampling locations (Gallegos et al. 2002).

offsite locations had higher activity than onsite locations due to the fallout. The highest measured 

activity based on all onsite locations is presented, as being favorable to claimants.

4.2.1.4 Purpose and Placement of Sampling Locations

The principal purpose of the ambient air monitoring network was to assess if air emissions from LLNL 

affected the air quality in the surrounding area. Air samples were collected from locations where a 

significant concentration of effluents from LLNL operations could reasonably be detected regardless 
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Table 4-2. Site 300 ambient air sampling station locations (Gallegos et al. 2002). 

Designation Location

Direction from 

center of Site 300

COHO Near south perimeter of facility; representative of MEI S

EOBS Northeast of Bunker 801E NE

ECP Center of Site 300 E

WCP Test Area W

GOLF South perimeter near fence S

TFIR Offsite location in City of Tracy E

NPS North of Bunker 801E N

WOBS West of Bunker 850 W

801E East of Bunker 801E E

Figure 4-2. Site 300 and downtown Tracy air particulate and tritium sampling locations (Gallegos et 

al. 2002).

of local meteorology (Griggs and Buddemeier 1986). This demonstrated compliance with DOE

derived concentration guidelines (DCGs) or U.S. Environmental Protection Agency (EPA), State of 

California, and (as of 1997) U.S. Nuclear Regulatory Commission regulations for airborne releases to 

the general public around LLNL. There were seven onsite monitoring stations (Griggs and 

Buddemeier 1986). This TBD considers only those ambient air monitoring locations inside the LLNL 

security fence for worker intake. The largest air concentration value was reported based on all onsite 

monitoring locations, to be favorable to claimants. Table 4-1 lists these locations.

The Livermore site radiological air particulate sampling network consisted of seven samplers at the 

perimeter with one (CRED) serving as the sitewide MEI as reported for National Emissions Standards 
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for Hazardous Air Pollutants (NESHAPs) monitoring. CRED was in the southeast quadrant in an area 

of known plutonium contamination from historical operations that included solar evaporators for 

plutonium-containing liquid waste.

The Site 300 air particulate monitoring network included eight sampling units that were placed around 

the site and near firing tables and one in downtown Tracy. Site 300 is in a remote area and access is 

limited. LLNL based the selection of the monitoring sites on safety, power, and access 

considerations. The COHO location served as the sitewide MEI location for NESHAPs reporting 

purposes. LLNL added two sampling systems in the Livermore Valley in July 1997 as part of the new 

low-volume radiological air particulate sampling network (Althouse et al. 2001). These samplers were 

generally upwind of the Livermore site. LLNL used the results to establish background levels of gross 

alpha and beta activity for direct comparison to emissions from the air effluent samplers. 

In addition, LLNL maintained 12 continuously operating airborne tritium samplers on the main site to 

assess current activities that influence environmental impacts. These stations were deployed in 1973; 

specific stacks were sampled for tritium as early as 1971 (Gede and Gildea 1980; SAIC 1993). 

4.2.1.5 Radionuclides of Significance

The LLNL environmental monitoring program identified radionuclides of significance. The program 

analyzed air samples for the presence of gross alpha and gross beta radiations from 1959 through 

1970 and for specific isotopes afterward, which represented more than 90% of the LLNL radioactive 

materials inventory. It analyzed air samples specifically for the presence of tritium, 238Pu, 239+240Pu, 

and isotopes of uranium. From 1959 through 1970, dose reconstructors should select the assigned 

dose from the higher of two calculated doses: one using the gross alpha concentration to calculate 

the presence of 239Pu, and a second using 234U. The gross beta concentration should be assumed to 

result from 90Sr [1]. 

For Site 300, radionuclides of significance were selected according to the inventory of radioactive 

materials and the type of work that was performed at that site. Specifically, the presence of depleted 

uranium was indicated in the analysis of 238U and 235U. Based on a review of the ratios of 235U to 238U 

air sample concentration data in the environmental reports, depleted uranium was predominant in air 

samples through about 1985 at Site 300. After 1985, the Site 300 uranium air sample concentration 

data indicated that natural uranium was most prevalent. The main site uranium air sample 

concentration data indicated that natural uranium was predominant for all years of available data. For 

estimates based on this TBD, the dose reconstructor should assign the dose that is associated with 

234U for natural uranium, which is favorable to claimants. Through 1970, dose reconstruction should 

use the gross alpha concentration for Site 300 to calculate the presence of 234U; it is assumed that the 

maximum radiation dose is assigned as 100% 234U versus a varying percentage of 234U and 235U [2]. 

Data are listed in the tables in Section 4.2.3.2. Assume the gross beta concentration is 234Th [3]. 

After 1970, the 238U and 235U mass-based air concentration data were converted to activity 

concentration based on the specific activities in the environmental reports. The activity of 234U was 

determined by multiplying the 238U activity by the ratio of the activity fraction of 234U to 238U for natural 

uranium in ORAUT-TKBS-0035-5, Lawrence Livermore National Laboratory – Occupational Internal 

Dose (ORAUT 2010). The 234U, 238U, and 235U activities were then summed and reported as 234U. 

These values are presented later in Tables 4-7 and 4-8. 

4.2.2 Sampling and Analysis Methods

LLNL used several different networks, each representing a general location and type of analysis, to 

perform environmental air sampling. There were separate networks for sampling radiological 

particulates and beryllium particulates at the Livermore site and Site 300 as well as a low-volume 

radiological air sampling network, a tritium-sampling network in Livermore, and one tritium-sampling 

location at Site 300. Four collection media were employed: glass-fiber filters for radiological 
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particulates, cellulose filters for beryllium particulates, membrane filters for low-volume radiological 

particulates, and silica gel for tritium. All monitoring networks used continuously operating samplers 

(Gallegos et al. 1992). 

As outlined in the Environmental Regulatory Guide for Radiological Effluent Monitoring and 

Environmental Surveillance (DOE 1991), data for gross alpha, gross beta, and gamma isotopes on air 

filters were used only as trend indicators; specific radionuclide analysis occurred for plutonium and 

uranium dependent on location. All analytical results were reported as a measured concentration per 

volume of air. When activity was less than the minimum detectable concentration, the calculated 

value was reported. Particle size distributions were not determined because the estimated effective 

dose equivalent to the MEI is well below the 0.01-mSv (1-mrem) allowable limit (DOE 1991). The 

analytical laboratory used 230Th and 90Sr as calibration sources to determine alpha and beta counting 

efficiencies, respectively. Annual counting efficiency measurements were made for each detector. 

Periodic crosschecks used EPA-certified standards. Background and efficiency checks occurred 

daily, and a matrix and method blank were run with every batch of 20 samples. LLNL kept records of 

background and counting efficiency variations in the counting equipment. The analytical laboratory 

reported the actual instrumentation values, which included negative results when background 

measurements were higher than those for the filters (DOE 1991).

Concentrations of various airborne radionuclides were measured at Livermore site perimeters, at 

offsite locations near the Livermore site, and at Site 300. From 1959 to 1964, air samples were 

collected from two perimeter locations and nine offsite locations on 4- by 9-in. HV-70 paper at a 

sample flow rate of about 4 ft3/min of air (LRL 1964). As discussed in Section 4.2.1.1, no monitoring 

data were found for the years before 1959 for the main site or before 1961 for Site 300. The samples 

were collected for 7 days. After a 4-day delay for decay of radon and thoron progeny, gross alpha 

and beta activities on the filters were determined with an automatic gas-flow proportional counter. 

Monthly composites of perimeter filters were counted for specific gamma-emitting radionuclides using 

a Ge(Li) detector equipped with Compton suppression. 

After gamma counting, the perimeter filters were grouped by sampling location. The individual 

samples were analyzed for the presence of 239Pu, 238Pu, 137Cs, 235U, and 238U. In July 1964, four 

sample locations were added on the perimeter; six locations around the perimeter were sampled 

(Hughey 1965). The six samplers on the Laboratory perimeter used 0.052 m2 Whatman-41 cellulose 

filters. The particulates were collected on these filters using an average air flow rate of 700 L/min 

(Lindeken et al. 1978). Tritium was collected on columns packed with silica gel using an air flow rate 

of 0.5 L/min. Particulate filters were changed each week at all locations, and tritium samplers were 

changed every 2 weeks. From 1973 to 1976, area samples for tritium were exchanged each week. 

After 1976, tritium samples were exchanged every 2 weeks (SAIC 1993). Duplicate quality assurance 

samplers operated in parallel with the permanent sampler at each site; samples from these duplicates 

were analyzed to confirm results (Lindeken et al. 1978). 

In April 1997, the radiological air particulate sampling filter media changed from cellulose to glass 

fiber. However, blank glass-fiber filters contain nontrivial amounts of naturally occurring radiological 

isotopes including 234U, 235U, 238U, 40K, 226Ra, 228Ra, and 228Th (Althouse 1998). In fact, the amount of 

these naturally occurring isotopes in the filters is often greater than the amount the filter captures from 

the air. The filters are cut in half, and half of each filter is retained for beryllium analysis. 

Gross alpha and gross beta activities were determined by gas-flow proportional counting, plutonium 

and uranium isotopes by alpha spectrometry, gamma emitters by gamma spectroscopy, and tritium by 

liquid scintillation. In 2001, a correction factor was applied to tritium concentrations to account for 

dilution of the collected tritium from air moisture by an unknown quantity of water in supposedly dry 

silica gel (Althouse et al. 2001). On average, the corrected concentrations were 1.6 times higher than 

uncorrected concentrations. 
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Gross alpha, gross beta, and gamma emitters on air filters were used as trend indicators; specific 

radionuclide analyses were completed for plutonium and uranium after 1971. Radiological analytical 

results were reported as a measured activity per volume of air. Particle size distributions on air 

samples were not determined because the estimated effective dose equivalent to the MEI (from the 

total particulate) was below the 10-mrem committed effective dose equivalent (CEDE) (Althouse et al. 

2001).

Portions of the glass-fiber filters from the Livermore locations were analyzed for the presence of 

239+240Pu. Similarly, portions of the glass-fiber filters from Site 300 were analyzed for the presence of 

235U and 238U. The filters were placed in a muffle furnace to reduce organic content and then 

dissolved in a mixture of nitric and hydrochloric and/or hydrofluoric acids. Plutonium and uranium 

were separated by an ion exchange process. Each separated element was purified further by ion 

exchange. It was then electroplated onto a stainless-steel disk and analyzed by alpha spectrometry. 

For gamma scanning, a site composite was created using all of the weekly glass fiber filters for Site 

300 perimeter locations (801E, ECP, EOBS, GOLF, NPS, WCP, and WQBS). This composite was 

prepared for analysis in the same manner as that for plutonium and uranium samples. After it was 

muffled and digested, it was counted for more than 40 gamma-emitting radionuclides using Ge(Li) 

detectors. In addition to gamma scanning, the Site 300 composite was analyzed for plutonium. 

Duplicate radiological quality assurance samples were processed to confirm the precision of the 

analytical results obtained from the samplers. A duplicate sampler was operated for 2 months in 

parallel with the permanent sampler at a given site. In addition, a trip blank was collected during each 

collection trip. The trip blanks and duplicates were processed in the same manner as that for the 

routine samples and analyzed for the same radiological parameters. 

4.2.3 Estimation of Potential Annual Intakes from Airborne Radionuclides

This section discusses estimation of annual intakes from the air monitoring results for all air 

surveillance locations at the Livermore site and Site 300. This TBD relies on several data sources for 

estimating ambient airborne radionuclide concentrations and for annual airborne releases by 

radionuclide. The principal sources were the annual environmental reports for LLNL from 1959 to 

2018.1 The analysis for this TBD collected measurements from the air monitoring locations in 

Tables 4-1 and 4-2 from these documents and analyzed them in accordance with the collection and 

analysis methods Section 4.2.2 describes. If data were not available or additional information was 

necessary, these documents were supplemented by information from DOE or the University of 

California. 

1 The References section lists all directly cited references, then separately lists the environmental reports in date order.

Factors other than transport and release rates have influenced the gradual reduction in the measured 

air concentrations over the history of LLNL. Over the past 40 years of monitoring, concentrations of 

airborne radioactive materials have decreased by more than 3 orders of magnitude. These factors 

include:

• Improvements in monitoring methods that reduced minimum detectable concentrations;

• Reductions in releases of naturally occurring radioactive material from a nearby fossil-fuel 

generating plant, which has improved its environmental controls over the years; and

• Reductions in the effects of atmospheric weapons testing including radioactive decay of 

fallout.

 
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The method for calculation of the annual intakes from onsite atmospheric radionuclide concentrations 

was applied directly to available air sampling data. Earlier LLNL environmental reports provided 

annual average air concentrations through 1993. After this time, annual median air concentrations 

were reported. For simplicity, they are referred to as “medians” for each year. The largest annual 

median for the year, over all locations, is referred to as “maximum annual median air concentration.”

The following factors limited the estimates of airborne concentrations at specific locations around the 

LLNL site using traditional transport modeling approaches:

• Number of release points;

• Characteristics of the release points, which include stacks, vents, and other emission sources;

• Limited number of air sampling locations;

• Relatively short distances between the release points and the onsite receptor locations; and

• Density and configurations of buildings at the site.

Sections 4.2.3.1 and 4.2.3.2 provide information on gross alpha and gross beta inhalation exposures 

for the periods from 1952 to 1958 for the main site, and from 1955 to 1960 for Site 300 and from 1959 

to 1970 for the main site, and from 1961 to 1970 for Site 300, respectively; the estimates for the 

earlier period are based on the data from the later period. Section 4.2.3.3 discusses tritium exposures 

for the period from 1952 to 1972, before tritium monitoring began. Section 4.2.3.4 provides estimated 

inhalation exposures based on air monitoring for tritium starting in 1973 and for plutonium and 

uranium for 1971 to 2018. 

All inhalation intakes in the tables in the following sections are based on a 50-hour workweek, which 

was chosen based on a review of telephone interviews for LLNL claims (ORAUT 2020c). Over half of 

the telephone interviews indicated working more than 40 hr/wk. The inhalation exposure of 50 hr/wk

is favorable to claimants and applicable for most cases.

The 1952 to 1970 gross alpha and gross beta air concentration data in Sections 4.2.3.1 and 4.2.3.2, 

the 1973 to 2018 tritium air concentration data, and the 1971 to 2018 plutonium and uranium air 

concentration data in Section 4.2.3.4 are supported by ORAUT (2020a). The 1952 to 1972 tritium air 

concentration data in Section 4.2.3.3 are supported by ORAUT (2020b). 

4.2.3.1 Gross Alpha and Gross Beta, before 1959

For the main site before 1959, and for Site 300 before 1961, environmental air monitoring samples 

were not available. The estimated air concentrations and potential intakes of gross alpha and gross 

beta activity before 1959 for the main site and before 1961 for Site 300 are listed in Tables 4-3 and 

4-4. The annual intakes assumed a breathing rate of 3,000 m3/yr based on 20 L/min for 50 hr/wk and 

50 wk/yr with a geometric standard deviation for these data of 3 [4]. These data are based on using 

the highest annual average of the measured data for years during which environmental monitoring 

occurred. All assigned environmental internal doses for the main site before 1959, and for Site 300 

before 1961, are considered partial dose assessments due to the LLNL SECs for MFAPs and 233U. 

The intakes in Tables 4-3 and 4-4 may be adjusted to reflect work other than 50 hr/wk. The intake 

rates in Tables 4-3 and 4-4 would be multiplied by the ratio of the hours worked per week to 50 hr/wk. 

4.2.3.2 Gross Alpha and Gross Beta, 1959 to 1970

Data from the environmental reports were available for 1959 to 1970 for the main site and for 1961 to 

1970 for Site 300. The air monitoring data provided no isotopic analysis; the data were reported only 

for the gross alpha and gross beta radiations. Table 4-5 lists air concentrations and estimated intakes 

for the LLNL site, and Table 4-6 lists the values for Site 300. All assigned environmental internal 

doses for 1959 to 1970 are considered partial dose assessments due to the LLNL SEC classes for 

MFAPs and 233U. The intakes in Tables 4-5 and 4-6 may be adjusted to reflect work other than 
Document No. ORAUT-TKBS-0035-4 Revision No. 02 Effective Date: 06/09/2020 Page 17 of 47

 

Table 4-3. Main site estimated air concentrations and annual median intakes via inhalation, 1952 to 

1958.

a

Year

Gross alpha

(Pu-239 or U-234)

air concentration

(Bq/m3)

Gross alpha

(Pu-239 or U-234) 

annual inhalation 

intake (Bq/yr)

Gross beta

(Sr-90)

air concentration

(Bq/m3)

Gross beta

(Sr-90)

annual inhalation 

intake (Bq/yr)

1952 8.510E−04 2.553E+00 9.620E−01 2.886E+03

1953 8.510E−04 2.553E+00 9.620E−01 2.886E+03

1954 8.510E−04 2.553E+00 9.620E−01 2.886E+03

1955 8.510E−04 2.553E+00 9.620E−01 2.886E+03

1956 8.510E−04 2.553E+00 9.620E−01 2.886E+03

1957 8.510E−04 2.553E+00 9.620E−01 2.886E+03

1958 8.510E−04 2.553E+00 9.620E−01 2.886E+03

a. All intakes are based on a 50-hour workweek. The inhalation doses calculated may be adjusted based on the guidance 

in Section 4.2.3.1. 

Table 4-4. Site 300 estimated air concentrations and annual median intakes via inhalation, 1955 to 

1960.

a

Year

Gross alpha

(U-234)

air concentration

(Bq/m3)

Gross alpha

(U-234)

annual inhalation 

intake (Bq/yr)

Gross beta

(Th-234)

air concentration

(Bq/m3)

Gross beta

(Th-234)

annual inhalation 

intake (Bq/yr)

1955 4.810E−04 1.443E+00 1.554E−01 4.662E+02

1956 4.810E−04 1.443E+00 1.554E−01 4.662E+02

1957 4.810E−04 1.443E+00 1.554E−01 4.662E+02

1958 4.810E−04 1.443E+00 1.554E−01 4.662E+02

1959 4.810E−04 1.443E+00 1.554E−01 4.662E+02

1960 4.810E−04 1.443E+00 1.554E−01 4.662E+02

a. All intakes are based on a 50-hour workweek. The inhalation doses calculated may be adjusted based on the guidance 

in Section 4.2.3.1. 

Table 4-5. Main site maximum annual median air concentrations and estimated annual intakes via 

inhalation, 1959 to 1970.

a

Year

Gross alpha

(Pu-239 or U-234)

air concentration

(Bq/m3)

Gross alpha

(Pu-239 or U-234) 

annual inhalation 

intake (Bq/yr)

Gross beta

(Sr-90)

air concentration

(Bq/m3)

Gross beta

(Sr-90)

annual inhalation 

intake (Bq/yr)

1959 7.400E−04 2.220E+00 2.701E−01 8.103E+02

1960 8.510E−04 2.553E+00 9.620E−01 2.886E+03

1961 3.700E−04 1.110E+00 3.293E−02 9.879E+01

1962 2.331E−04 6.993E−01 9.250E−02 2.775E+02

1963 1.073E−04 3.219E−01 1.221E−01 3.663E+02

1964 1.554E−04 4.662E−01 2.738E−02 8.214E+01

1965 4.070E−05 1.221E−01 5.476E−03 1.643E+01

1966 3.700E−05 1.110E−01 2.627E−03 7.881E+00

1967 1.480E−05 4.440E−02 4.662E−03 1.399E+01

1968 3.700E−05 1.110E−01 4.366E−03 1.310E+01

1969 1.480E−05 4.440E−02 4.070E−03 1.221E+01

1970 1.480E−05 4.440E−02 7.844E−03 2.353E+01

a. All intakes are based on a 50-hour workweek. The inhalation doses calculated may be adjusted based on the guidance 

in Section 4.2.3.2. 

50 hr/wk. The intake rates in Tables 4-5 and 4-6 would be multiplied by the ratio of the hours worked 

per week to 50 hr/wk.
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The gross alpha and gross beta inhalation intakes in Tables 4-5 and 4-6 should be assigned as a 

lognormal distribution with a geometric standard deviation of 3.

The isotopes of significance at Site 300 are 238U and 235U, both of which decay by alpha radiation.

Table 4-6. Site 300 maximum annual median air concentrations and annual intakes via inhalation, 

1961 to 1970.

a

Year

Gross alpha

(U-234)

air concentration

(Bq/m3)

Gross alpha (U-234)

annual inhalation 

intake (Bq/yr)

Gross beta

(Th-234)

air concentration

(Bq/m3)

Gross beta

(Th-234)

annual inhalation 

intake (Bq/yr)

1961 4.810E−04 1.443E+00 2.960E−03 8.880E+00

1962 3.700E−04 1.110E+00 1.369E−01 4.107E+02

1963 1.073E−04 3.219E−01 1.554E−01 4.662E+02

1964 1.665E−04 4.995E−01 2.220E−02 6.660E+01

1965 3.700E−05 1.110E−01 6.290E−03 1.887E+01

1966 4.440E−05 1.332E−01 3.182E−03 9.546E+00

1967 3.700E−05 1.110E−01 5.550E−03 1.665E+01

1968 7.400E−06 2.220E−02 5.069E−03 1.521E+01

1969 3.700E−05 1.110E−01 5.735E−03 1.721E+01

1970 3.700E−05 1.110E−01 8.880E−03 2.664E+01

a. All intakes are based on a 50-hour workweek. The inhalation doses calculated may be adjusted based on the guidance 

in Section 4.2.3.2. 

4.2.3.3 Tritium, 1952 to 1972

Environmental air monitoring samples were not analyzed for tritium before 1973. A tritium dose 

reconstruction was performed in 2007 by LLNL (Peterson 2007). According to this study, although not 

reported to the public, the releases of tritium from significant sources (e.g., both the original Tritium 

Facility that opened in 1953 in what is now Building 231 and the present Tritium Facility [Building 331] 

that began operations in 1959) were estimated or measured during these years and, starting at least 

in 1956, were reported quarterly to the U.S. Atomic Energy Commission (AEC). Before 1956, tritium 

releases were estimated (Peterson 2007).

The sources of tritium were the stacks for Buildings 331 (north and south), 231, and 212; Building 212 

room air; and area sources such as Buildings 231, 331, 514, and 612 along with the Evaporation 

Trays. Routine tritiated water vapor (HTO), and routine tritiated hydrogen gas (HT) releases were 

reported in the study. The majority of tritium released was from the Building 231 and Building 331 

stacks. A comparison of the HTO and HT Buildings 231 and 331 stack releases indicate that from 

1953 through 1960 approximately 37% of the tritium released was HTO. From 1961 through 1972, 

approximately 54% of the released tritium was HTO. While the HTO and HT releases were within the 

same order of magnitude for 1953 through 1972, HT releases were not considered in this TBD

because HTO has a dose coefficient 10,000 times that of HT (ICRP 1995). 

The LLNL Discovery Center (Location VIS) location was assessed for the sitewide maximum exposed 

individual (Peterson 2007). Atmospheric dispersion coefficients (χ/Q) in s/m3 and annual HTO 

releases for 1953 through 1972 were determined for each LLNL tritium release. The annual tritium air 

concentrations were determined by the product of the annual tritium release multiplied by the 

appropriate χ/Q and summed. The χ/Q coefficients for Building 331 south stack were used as the 

basis for determining the Building 331 stack release concentrations because they were higher than 

those of the north stack. There were no tritium releases estimated or reported in 1952. LLNL began 

working with tritium late in 1952, very shortly after the laboratory opened, when a demand for a source 

of 14-MeV neutrons arose as a consequence of the nascent laboratory’s entry into thermonuclear 

weapons research (Gede and Gildea 1980). Routine releases from significant sources of tritium at 

LLNL did not start until 1953 when the original Tritium Facility began operations (Peterson 2007). Any 
Document No. ORAUT-TKBS-0035-4 Revision No. 02 Effective Date: 06/09/2020 Page 19 of 47

 

unreported tritium releases in late 1952 would likely have been small in comparison with routine

releases that began in 1953 and later. The largest tritium intake was 10,090 Bq/yr for 1957 (ORAUT

2020b). This results in an annual tritium dose of less than 0.001 rem. Therefore, the 1952 through 

1972 annual tritium doses are all less than 0.001 rem. Radionuclides contributing doses less than 

0.001 rem are not considered significant. The main site 1952 through 1972 tritium air concentrations 

and annual intakes are not listed for these years. All assigned environmental internal doses from 

1952 to 1972 are considered partial dose assessments due to the LLNL SEC classes for MFAPs and 

233U.

No tritium release data are available for Site 300 for 1955 to 1972. The Site 300 tritium doses are 

assumed to be the same as those for the main site. This is based on Section 4.3.2.4, which indicates 

that the Site 300 tritium values from 1973 and after are consistently less than 10% of the main site 

values during this time. Since the main site 1955 through 1972 annual tritium doses are all less than 

0.001 rem, the Site 300 1955 through 1972 tritium air concentrations and annual intakes are not listed

for these years.

4.2.3.4 Tritium, Uranium, and Plutonium, after 1970

Estimates of offsite doses to members of the public from the 1971 to 2018 environmental reports (see 

the References section) indicated that the potential internal dose from airborne releases to LLNL 

workers should be relatively low (10-mrem CEDE or less). Air data from nearby locations and at the 

security fence were consistent from location to location but dependent on year. This provided 

reasonable approximation of general airborne radioactivity and establishment of trends as a function 

of time. 

Samples were collected and analyzed for airborne radionuclides at the perimeter of the facility. Air 

sample measurements were available from onsite diffuse source locations such as tritium for 1991 

through 2007 for Buildings 292, 331, 514, and 624 and plutonium for 1991 through 1999 for Building 

531 and air sampling location CRED. The higher air concentrations between the diffuse sources and 

perimeter locations were assigned for these years. Table 4-7 lists main site concentrations for 

239+240Pu, and 234U. This TBD assumed that a worker inhaled 20 L of air per minute for 50 hr/wk or 

approximately 3.0 × 106 L of air per year (3,000 m3/yr). For tritium, the total uptake by the body was 

increased 50% to account for absorption by the skin in addition to the inhalation pathway (Gede and 

Gildea 1980). The largest main site tritium intake was 7,470 Bq/yr for 1998 (ORAUT 2020a). This 

results in an annual tritium dose of less than 0.001 rem. Therefore, the main site annual tritium doses 

after 1970 are all less than 0.001 rem. Radionuclides contributing doses less than 0.001 rem are not 

considered significant. The tritium air concentrations and annual intakes after 1970 are not listed for 

these years. Figure 4-3 shows how the concentration of 239+240Pu decreased from 1986 through 2005. 

The concentration dropped by more than 20 times over the 20 years of sampling. 

As Section 4.2.1.5 describes, the isotopes of significance at LLNL were 239+240Pu and 234U, which 

decay by alpha radiation. Isotopes that decay by beta radiation were determined to be progeny of 

these two parent isotopes. 

Due to the LLNL SEC classes, all assigned environmental internal doses for 1971 to 1973 from 

MFAPs, and those from 233U from 1971 to 1989, are considered partial dose assessments.

Tables 4-7 and 4-8 indicate the potential for exposure to inhalation of airborne radionuclides at the 

main site and Site 300 respectively. The Site 300 tritium doses are not listed because the Site 300 

values are consistently less than 10% of the main site values, and all main site annual tritium doses 

after 1970 are less than 0.001 rem. After 1970, only alpha-emitting radionuclides are listed. This is 

because the gross beta annual intakes after 1970 trend down to where the resulting internal doses 

are less than 0.001 rem. Radionuclides contributing doses less than 0.001 rem are not considered 

significant. In years for which air concentration data were unavailable, release data and maximum air 
Document No. ORAUT-TKBS-0035-4 Revision No. 02 Effective Date: 06/09/2020 Page 20 of 47

Table 4-7. Main site maximum annual median air concentrations and annual intakes via inhalation, 

1971 to 2018.

a,b,c

Year

Pu-239+240

air concentration

(Bq/m3)

Pu-239+240

annual inhalation 

intake (Bq/yr)

U-234d

air concentration

(Bq/m3)

U-234d

annual inhalation 

intake (Bq/yr)

1971 2.627E−06 7.881E−03 9.544E−06 2.863E−02

1972 1.184E−06 3.552E−03 1.646E−05 4.937E−02

1973 2.664E−04 7.992E−01 1.645E−05 4.936E−02

1974 3.108E−06 9.324E−03 1.333E−05 3.999E−02

1975 1.258E−06 3.774E−03 1.267E−05 3.801E−02

1976 1.036E−06 3.108E−03 1.481E−05 4.443E−02

1977 1.554E−06 4.662E−03 2.139E−05 6.417E−02

1978 1.961E−06 5.883E−03 2.698E−05 8.095E−02

1979 8.510E−07 2.553E−03 1.432E−05 4.295E−02

1980 5.180E−07 1.554E−03 1.267E−05 3.801E−02

1981 6.660E−07 1.998E−03 1.974E−05 5.923E−02

1982 2.220E−07 6.660E−04 1.777E−05 5.332E−02

1983 8.880E−07 2.664E−03 2.452E−05 7.356E−02

1984 1.480E−07 4.440E−04 1.580E−05 4.739E−02

1985 2.220E−07 6.660E−04 1.465E−05 4.394E−02

1986 1.517E−07 4.551E−04 1.445E−05 4.335E−02

1987 1.850E−07 5.550E−04 1.688E−05 5.065E−02

1988 1.184E−07 3.552E−04 3.624E−05 1.087E−01

1989 1.425E−07 4.274E−04 1.442E−05 4.325E−02

1990 1.517E−07 4.551E−04 1.070E−05 3.211E−02

1991 2.490E−07 7.470E−04 2.572E−05 7.716E−02

1992 2.740E−07 8.220E−04 1.386E−05 4.157E−02

1993 2.700E−07 8.100E−04 1.149E−05 3.446E−02

1994 1.660E−07 4.980E−04 6.388E−06 1.916E−02

1995 1.356E−07 4.068E−04 6.750E−06 2.025E−02

1996 1.259E−07 3.777E−04 7.442E−06 2.233E−02

1997 4.740E−08 1.422E−04 1.092E−05 3.275E−02

1998 1.550E−08 4.650E−05 3.639E−06 1.092E−02

1999 2.690E−08 8.070E−05 1.173E−05 3.520E−02

2000 1.520E−08 4.560E−05 1.173E−05 3.520E−02

2001 1.260E−08 3.780E−05 1.173E−05 3.520E−02

2002 8.360E−09 2.508E−05 3.109E−06 9.326E−03

2003 4.830E−09 1.449E−05 4.148E−06 1.245E−02

2004 4.610E−09 1.383E−05 4.788E−06 1.436E−02

2005 5.240E−09 1.572E−05 2.508E−05 7.524E−02

2006 1.440E−09 4.320E−06 1.023E−05 3.069E−02

2007 1.780E−09 5.340E−06 8.953E−06 2.686E−02

2008 5.880E−09 1.764E−05 8.395E−06 2.519E−02

2009 7.660E−09 2.298E−05 9.117E−06 2.735E−02

2010 5.310E−09 1.593E−05 8.067E−06 2.420E−02

2011 4.940E−09 1.482E−05 5.411E−06 1.623E−02

2012 3.320E−09 9.960E−06 8.166E−06 2.450E−02

2013 1.150E−09 3.450E−06 5.903E−06 1.771E−02

2014 1.980E−09 5.940E−06 6.985E−06 2.096E−02

2015 4.740E−09 1.422E−05 6.034E−06 1.810E−02

2016 1.540E−09 4.620E−06 5.411E−06 1.623E−02

2017 3.620E−09 1.086E−05 5.345E−06 1.604E−02

2018 3.380E−09 1.014E−05 4.181E−06 1.254E−02

a. The data are the maximum of the median measured value for a specific year from the available stationary monitoring

locations.

b. All intakes are based on a 50-hour workweek. The inhalation doses calculated may be adjusted based on the guidance

in Section 4.2.3.4.

c. The annual tritium doses are all less than 0.001 rem. The tritium air concentrations and annual intakes are not listed for

these years.

d. The actual concentration for this isotope was not reported. Isotopes of uranium were summed per Section 4.2.1.5 and

reported as U-234.
Document No. ORAUT-TKBS-0035-4 Revision No. 02 Effective Date: 06/09/2020 Page 21 of 47

 

Figure 4-3. Calculated annual median concentrations of 239+240Pu, 1986 to 2005 (Peterson et al. 

2005). 

concentration data were evaluated and estimates of the air concentration were generated. Tables 4-3 

through 4-8 list these data and demonstrate that the chosen values are reasonable and favorable to 

claimants. Using the maximum airborne radionuclide concentration in a year (either from actual data 

or an estimated value), annual intakes that are favorable to claimants for the radionuclides of concern 

were derived using an assumed individual annual respiration rate of 3,000 m3/yr. The intakes in 

Tables 4-7 and 4-8 may be adjusted to reflect work other than 50 hr/wk. The intake rates in 

Tables 4-7 and 4-8 would be multiplied by the ratio of the hours worked per week to 50 hr/wk. The 

plutonium and uranium inhalation intakes in Tables 4-7 and 4-8 should be assigned as a lognormal 

distribution with a geometric standard deviation of 3.

4.3 INTAKES FROM TRITIUM IN DRINKING WATER, 1952 TO 2018

The annual environmental reports discuss concentrations of radionuclides in the drinking water at 

LLNL (see the References section). Several water sources were sampled and analyzed; five were 

identified as sources of drinking water and are designated BELL, GAS, PALM, ORCH, and TAP. The 

water from these locations was sampled at least once per year. In addition, LLNL sampled the onsite 

swimming pool (POOL). The median activity in the drinking water was estimated from calculated 

values and found to be below the minimum analytical detectable activity. 

All assigned environmental internal doses for 1971 through 1973 are considered partial dose 

assessments due to the LLNL SEC for MFAPs, and 1971 through 1989 for 233U.
Document No. ORAUT-TKBS-0035-4 Revision No. 02 Effective Date: 06/09/2020 Page 22 of 47

 

Table 4-8. Site 300 maximum annual median air concentrations and annual intakes via inhalation, 

1971 to 2018.

a,b

Year

Pu-239+240c

air concentration

(Bq/m3)

Pu-239+240c

annual inhalation 

intake (Bq/yr)

U-234d

air concentration

(Bq/m3)

U-234d

annual inhalation 

intake (Bq/yr)

1971 2.109E−06 6.327E−03 1.530E−04 4.589E−01

1972 1.073E−06 3.219E−03 7.567E−05 2.270E−01

1973 6.290E−07 1.887E−03 3.948E−05 1.184E−01

1974 1.591E−06 4.773E−03 3.126E−05 9.377E−02

1975 1.036E−06 3.108E−03 2.139E−05 6.416E−02

1976 1.073E−06 3.219E−03 2.648E−05 7.945E−02

1977 8.880E−07 2.664E−03 3.011E−05 9.033E−02

1978 1.332E−06 3.996E−03 5.264E−05 1.579E−01

1979 5.180E−07 1.554E−03 1.596E−05 4.788E−02

1980 4.070E−07 1.221E−03 2.089E−05 6.268E−02

1981 7.030E−07 2.109E−03 1.290E−04 3.869E−01

1982 1.850E−07 5.550E−04 1.793E−05 5.380E−02

1983 3.700E−08 1.110E−04 3.093E−05 9.278E−02

1984 1.110E−07 3.330E−04 2.106E−05 6.317E−02

1985 7.400E−08 2.220E−04 9.050E−06 2.715E−02

1986 2.442E−08 7.326E−05 7.405E−06 2.221E−02

1987 2.960E−08 8.880E−05 1.218E−05 3.653E−02

1988 3.071E−08 9.213E−05 1.519E−05 4.556E−02

1989 1.110E−08 3.330E−05 8.062E−06 2.418E−02

1990 7.400E−09 2.220E−05 1.070E−05 3.209E−02

1991 2.300E−08 6.900E−05 1.288E−05 3.865E−02

1992 1.000E−08 3.000E−05 1.195E−05 3.584E−02

1993 3.900E−09 1.170E−05 1.185E−05 3.554E−02

1994 4.310E−09 1.293E−05 4.776E−06 1.433E−02

1995 4.800E−09 1.440E−05 4.446E−06 1.334E−02

1996 3.700E−09 1.110E−05 4.644E−06 1.393E−02

1997 3.600E−09 1.080E−05 5.614E−06 1.684E−02

1998 1.600E−09 4.800E−06 2.438E−06 7.314E−03

1999 1.790E−09 5.370E−06 7.487E−06 2.246E−02

2000 1.340E−09 4.020E−06 6.548E−06 1.964E−02

2001 2.070E−09 6.210E−06 5.778E−06 1.733E−02

2002 3.440E−09 1.032E−05 6.232E−06 1.870E−02

2003 1.810E−09 5.430E−06 3.788E−06 1.136E−02

2004 1.600E−09 4.800E−06 3.607E−06 1.082E−02

2005 1.500E−09 4.500E−06 2.509E−06 7.526E−03

2006 2.490E−09 7.470E−06 2.706E−06 8.117E−03

2007 1.200E−10 3.600E−07 2.804E−06 8.412E−03

2008 3.240E−09 9.720E−06 3.411E−06 1.023E−02

2009 2.670E−09 8.010E−06 2.935E−06 8.805E−03

2010 3.970E−10 1.191E−06 1.705E−06 5.116E−03

2011 9.320E−10 2.796E−06 2.263E−06 6.788E−03

2012 9.320E−10 2.796E−06 3.263E−06 9.789E−03

2013 3.980E−11 1.194E−07 2.656E−06 7.969E−03

2014 1.090E−10 3.270E−07 2.656E−06 7.969E−03

2015 1.090E−10 3.270E−07 2.132E−06 6.395E−03

2016 1.400E−10 4.200E−07 2.246E−06 6.739E−03

2017 7.480E−10 2.244E−06 2.460E−06 7.379E−03

2018 7.480E−10 2.244E−06 2.082E−06 6.247E−03

a. All intakes are based on a 50-hour workweek. The inhalation doses calculated may be adjusted based on the guidance 

in Section 4.2.3.4. 

b. The annual tritium doses are all less than 0.001 rem. The tritium air concentrations and annual intakes are not listed for 

these years. 

c. Originating from fallout (Gallegos 1998).

d. Isotopes of uranium were summed per Section 4.2.1.5 and reported as U-234.
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Concentrations of tritium in the POOL location ranged from 0.8 to 200 Bq/L; the maximum 

concentration was reported in 1988. The LLNL swimming pool is close to the main sources of tritium 

at LLNL (Gallegos et al. 2002). This TBD assumed that a worker at LLNL ingested 1.4 L of water per 

day for 5 days per week and 50 hr/wk or 350 L/yr. The 1.4 L of water per day intake was based on 

the maximum tap water intake of approximately 1.75 L/d (ICRP 2002). Assuming that the daily tap 

water intake of 1.75 L/d occurs over a 16-hour period, adjusting for 10 hours per workday yields 

approximately 1.1 L/d. This daily water intake is rounded up to 1.4 L/d, as being favorable to 

claimants. The intake of 1.4 L/d is 80 percent of the maximum tap water intake of 1.75 L/d. It is 

reasonable to assume that most of the daily water intake occurs during work hours because of higher 

physical activity. The daily water intake assumed is also consistent with the daily urine excretion rate 

of 1.4 L/d. The values before 1966 were selected from the maximum concentration that was reported 

for the period from 1966 to 2018. No data were available for drinking water at Site 300; this TBD 

assumed that the concentration of tritium was the same as that at LLNL. The largest tritium intake 

was 36.626 Bq/yr for 1975 (ORAUT 2020a). This results in an annual tritium dose of less than 0.001 

rem. Therefore, the 1952 through 2018 annual tritium doses from drinking water are all less than 

0.001 rem. Radionuclides contributing doses less than 0.001 rem are not considered significant. The 

tritium drinking water concentrations and annual intakes for 1952 through 2018 are not listed for these 

years. 

It should also be noted that the annual tritium dose from both air concentration and drinking water 

data combined are less than 0.001 rem. This is based on combining the largest tritium inhalation 

intake of 10,090 Bq/yr for 1957 (ORAUT 2020b), and the largest drinking water intake of 36.626 Bq/yr 

for 1975 (ORAUT 2020a). 

4.4 AMBIENT RADIATION

4.4.1 Gamma Radiation

From 1967 to the present, thermoluminescent dosimeters (TLDs) have been used on the main site to 

determine ambient external radiation levels, including natural background (terrestrial and cosmic) 

radiation. TLDs were deployed at Site 300 in July 1988. Figures 4-4 and 4-5 show the locations of 

the monitoring stations at the main site and Site 300, respectively. The data for this analysis were 

summarized from the annual environmental reports for 1989 to 2018 (see the References list). 

Observations from earlier environmental reports, which were based on surveys with portable 

instruments, state, “0.02 mrem/h at all locations.” The instrumentation might be considered primitive 

by today’s standards, and the site did not employ continuous monitoring, so these results have been

overshadowed by recent and more reliable observations. The external gamma dose rate of 

0.02 mrem/hr corresponds to 175 mrem/yr (0.02 mrem/hr × 8,760 hr/yr). This dose value is bounded 

by the assignment of the main site highest average and maximum gamma doses based on the 

reported data in Table 4-9 for 1972 and 1975, respectively, for 1952 through 1967 when no doses 

were reported.

Over the years, various combinations of TLD chip configurations and monitoring locations were used. 

From 1988 to the present, minimal changes in external radiation levels were observed at the 

perimeter. The analysis for this TBD developed the environmental radiological profile for LLNL for use 

by dose reconstructors when personal dosimetry or bioassay program participation was not required.

Site annual environmental reports, health physics surveys, and other reports were reviewed for data 

that would be useful in reconstructing ambient radiation levels. 

The ambient radiation that was measured by TLDs near the security fence included natural 

background radiation, nuclear weapons testing fallout, and cosmic radiation. The TLDs provided an 

indication of worker exposure levels in the general proximity of the security fence but not inside 
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Figure 4-4. Main site gamma dosimeter locations, 2001 (Gallegos et al. 2002). 

buildings. LLNL compared these data annually with TLD data from offsite locations and values for 

State of California and regional exposure levels. The determination has always been that onsite 

ambient radiological conditions as measured at the security fence were not significantly different from 

offsite, state, and regional annual exposure levels. This was attributed to the geology of the region 

around LLNL.

The locations of the monitoring points from which data were summarized in this section add 

uncertainty to the results. The monitoring points, as stated above, have been located around the 

LLNL perimeter and off the site to monitor public exposures.

The estimated accuracy of the area monitors for external radiation is ±20%. However, subtracting 

background from these measurements adds more uncertainty because of the variability and selection 

of background information. The environmental reports gave the results as cumulative exposures in 

millirem per year based on 8,760 hours of exposure, which is the total number of hours in 365 days. 

External dose for some years was not available. For the main site, the maximum external dose was 

reported in 1975; the maximum site average was reported in 1972; therefore, the 1972 and 1975 dose 

values were used respectively for the years noted. For Site 300, the maximum value was noted in 

1994; this value was used for the average for years before 1989 when monitoring began. These

maximum values of environmental exposure were recommended for years when data were 
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Figure 4-5. Site 300 and vicinity gamma dosimeter locations, 2001 (Gallegos 

et al. 2002).

unavailable for the main site and Site 300. Tables 4-9 and 4-10 provide, for the main site and Site 

300, respectively, average and maximum annual exposures for the 8,760-hr/yr exposure period. The 

yearly exposure values provided in Tables 4-9 and 4-10 should be adjusted in accordance with 

ORAUT-OTIB-0088, External Dose Reconstruction (ORAUT 2018). In cases where annual work 

hours and areas are uncertain or otherwise not specified, environmental doses are based on a bestestimate approach that assumes 2,500 hours at the site average dose values. Partial years of 

employment, or work other than 50 hr/wk may be adjusted in accordance with guidance in ORAUTOTIB-0088, External Dose Reconstruction (ORAUT 2018). Best estimate onsite ambient photon 

doses should be assigned as a normal distribution with an error of 20%. 

4.4.2 Neutron Radiation

Data that describe ambient neutron measurements on the main site were found in site environmental 

radiation reports beginning in 1972 (Gudiksen et al. 1973). From 1972 through 1987, elevated 

ambient neutron dose was measured at the perimeter fence near Building 212. The source of these 

elevated readings was the Insulating Core Transformer (ICT) accelerator, which began operations in 

1966 in Building 212 and produced 14-MeV neutrons (Olson 1974). The ICT accelerator ceased 

operations in 1987 (LLNL 1990). The ICT accelerator was also referred to as the Rotating Target 

Neutron Source I. This distinguished it from the Rotating Target Neutron Source II, which began 

operations in 1978 in Building 292. Figure 4-6 shows the locations of the environmental neutron 

dosimeters. Stations 5 and 3 were typically the maximum value locations. 

Table 4-11 lists the maximum and available average ambient neutron values for the main site. Only 

maximum values were available from the reports for 1972 to 1980. Average and maximum values 
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Table 4-9. Main site external gamma radiation (mrem/yr) [5].a,b 

Year

Average,

8,760 hr/yr

Maximum,

8,760 hr/yr

1952 89c 317d

1953 89c 317d

1954 89c 317d

1955 89c 317d

1956 89c 317d

1957 89c 317d

1958 89c 317d

1959 50 317d

1960 89c 317d

1961 88 317d

1962 44 317d

1963 50 317d

1964 50 317d

1965 50 317d

1966 89c 317d

1967 20 317d

1968 20 163

1969 34 83

1970 15 105

1971 77 257

1972 89 122

1973 80 96

1974 74 137

1975 88 317

1976 84 293

1977 79 227

1978 64 93

1979 61 96

1980 63 81

1981 54 61

1982 49 57

1983 51 73

1984 48 53

1985 59 80

Year

Average,

8,760 hr/yr

Maximum,

8,760 hr/yr

1986 61 70

1987 65 72

1988 63 70

1989 63 75

1990 65 72

1991 65 78

1992 66 76

1993 65 74

1994 72 80

1995 56 61

1996 55 60

1997 60 64

1998 60 66

1999 58 63

2000 57 65

2001 56 100

2002 65 65

2003 56 62

2004 57 64

2005 58 65

2006 58 64

2007 58 68

2008 57 64

2009 59 64

2010 55 60

2011 57 63

2012 56 63

2013 58 64

2014 57 63

2015 56 63

2016 57 63

2017 57 61

2018 58 63

a. The results in this table reflect LLNL data for an exposure period of 8,760 hr/yr. In cases where annual work 

hours and areas are uncertain or otherwise not specified, environmental doses are based on a best-estimate 

approach that assumes 2,500 hours at the site average dose values in accordance with ORAUT (2018). 

b. The 2018 main site onsite ambient gamma dose can be extended to later years.

c. External dose for these years was not available. The maximum average external dose was reported in 1972. 

Therefore, 1972 dose values are used for the noted years.

d. External dose for these years was not available. The maximum external dose was reported in 1975. 

Therefore, the 1975 dose values are used for the years noted.

were available for 1981 to 1993. Again, the values from the original data were for an 8,760-hr/yr 

exposure period. The yearly exposure values provided in Table 4-11 should be adjusted in 

accordance with ORAUT-OTIB-0088, External Dose Reconstruction (ORAUT 2018). In cases where 

annual work hours and areas are uncertain or otherwise not specified, environmental doses are based 

on a best-estimate approach that assumes 2,500 hours at the site average dose values. Partial years 

of employment, or work other than 50 hr/wk may be adjusted in accordance with guidance in ORAUTOTIB-0088, External Dose Reconstruction (ORAUT 2018). Best estimate onsite ambient neutron 

doses should be assigned as a normal distribution with an error of 20%.

Potential ambient neutron dose is captured by application of the neutron-to-photon ratio to gamma 

dose (applied through 1968) or by using measured and missed neutron dose data for the period from 
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Table 4-10. Site 300 external gamma radiation (mrem/yr) [6].a,b,c 

Year

Average,

8,760 hr/yr

Maximum, 

8,760 hr/yr

1955 88d 99d

1956 88d 99d

1957 88d 99d

1958 88d 99d

1959 88d 99d

1960 88d 99d

1961 88d 99d

1962 88d 99d

1963 88d 99d

1964 88d 99d

1965 88d 99d

1966 88d 99d

1967 88d 99d

1968 88d 99d

1969 88d 99d

1970 88d 99d

1971 88d 99d

1972 88d 99d

1973 88d 99d

1974 88d 99d

1975 88d 99d

1976 88d 99d

1977 88d 99d

1978 88d 99d

1979 88d 99d

1980 88d 99d

1981 88d 99d

1982 88d 99d

1983 88d 99d

1984 88d 99d

1985 88d 99d

1986 88d 99d

Year

Average,

8,760 hr/yr

Maximum, 

8,760 hr/yr

1987 88d 99d

1988e 88d 99d

1989 77 89

1990 78 94

1991 78 93

1992 77 87

1993 76 86

1994 88 99

1995 64 72

1996 66 72

1997 72 77

1998 72 78

1999 71 80

2000 64 70

2001 64 66

2002 67 76

2003 67 74

2004 69 77

2005 69 83

2006 68 77

2007 69 74

2008 69 75

2009 69 75

2010 66 72

2011 67 73

2012 63 69

2013 69 76

2014 69 75

2015 67 76

2016 66 75

2017 67 77

2018 69 73

a. The results in this table reflect LLNL data for an exposure period of 8,760 hr/yr. In cases where annual work 

hours and areas are uncertain or otherwise not specified, environmental doses are based on a best-estimate 

approach that assumes 2,500 hours at the site average dose values in accordance with ORAUT (2018). 

b. Site average (millirem per year) is based on the maximum average value from later years where monitoring was 

performed. Therefore, no maximum or uncertainty is provided.

c. The 2018 Site 300 onsite ambient gamma dose can be extended to later years.

d. External dose for these years was not available. The maximum average and maximum external doses were

reported in 1994. Therefore, the 1994 dose values are used for the years noted. 

e. Environmental radiation monitoring at Site 300 began on July 1, 1988. 

1969 to the present. Considering that all LLNL workers were using neutron sensitive TLDs beginning 

at least in 1969, any significant neutron dose should have been detected and measured by these 

dosimeters (Unruh ca. 1969). Therefore, it is not necessary to add additional ambient neutron dose 

for monitored workers. 

If dosimetry data are not available for a worker from 1969 to the present, then the maximum ambient 

neutron dose value may be adjusted in accordance with ORAUT-OTIB-0088, External Dose 

Reconstruction (ORAUT 2018). To be favorable to claimants, a neutron energy range of 0.1 to 

2.0 MeV should be chosen along with an International Commission on Radiological Protection 

Publication 60 weighting factor correction of 1.91 (ICRP 1991). The value for 1972 should be used for 
Document No. ORAUT-TKBS-0035-4 Revision No. 02 Effective Date: 06/09/2020 Page 28 of 47

 

Figure 4-6. Main site neutron dosimeter locations, 1969 to present (Griggs and Buddemeier 1986). 

1969 to 1971. If the worker was externally monitored from 1966 to 1969, the neutron-to-photon ratio 

can be assigned. If photon dosimetry data are not available for this period, then the neutron value for 

1972 can be assigned for 1966 to 1969. 

The neutron rem meters used by LLNL had aged and deteriorated by 1994 to the point where the 

neutron measurements did not meet the LLNL accuracy and precision requirements. Therefore, the 

neutron data collected during 1994 were not reported, and neutron monitoring was discontinued as of 

January 1995 (Harrach 1994). Table 4-11 indicates a significant drop in the onsite ambient neutron 

doses measured in later years after the ICT accelerator ceased operations in 1987. The measured 

onsite ambient neutron doses were a fraction of the measured onsite gamma doses after this time. 

The 1993 onsite ambient neutron dose can be extended to later years.
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Table 4-11. Main site external neutron radiation (mrem/yr) 

[7].a,b

Year

Average,

8,760 hr/yr

Maximum, 8,760 

hr/yr

1966 57 250

1967 57 250

1968 57 250

1969 57 250

1970 57 250

1971 57 250

1972 57 250

1973 57 250

1974 84 370

1975 160 700

1976 137 600

1977 126 550

1978 31 137

1979 18 80

1980 19 85

1981 8 33

1982 8 36

1983 26 113

1984 10 45

1985 2 7

1986 7 30

1987 2 9

1988 1 5

1989 1 6

1990 1 6

1991 2 7

1992 2 7

1993 2 7

a. The results in this table reflect data provided by LLNL for an 

exposure period of 8,760 hr/yr. In cases where annual work hours 

and areas are uncertain or otherwise not specified, environmental 

doses are based on a best-estimate approach that assumes 2,500 

hours at the site average dose values in accordance with ORAUT 

(2018). 

b. Neutron results were not reported in 1994 due to neutron detection 

equipment degradation not meeting accuracy and precision 

requirements. Neutron monitoring was discontinued as of January 

1995 (Harrach 1994). The 1993 main site onsite ambient neutron 

dose can be extended to later years.

4.5 ATTRIBUTIONS AND ANNOTATIONS

Where appropriate in this document, bracketed callouts have been inserted to indicate information, 

conclusions, and recommendations provided to assist in the process of worker dose reconstruction. 

These callouts are listed here in the Attributions and Annotations section, with information to identify 

the source and justification for each associated item. Conventional References, which are provided in 

the next section of this document, link data, quotations, and other information to documents available 

for review on the Project’s Site Research Database (SRDB).

[1] Szalinski, Paul A. Oak Ridge Associated Universities (ORAU) Team. Health Physicist. April 

2007. 

The surrogate radionuclides were derived from LLNL NESHAPs reports (Gallegos et al. 1998, 

2000). The following is a quote from the reports for the Livermore site: “In addition, isotopic 
Document No. ORAUT-TKBS-0035-4 Revision No. 02 Effective Date: 06/09/2020 Page 30 of 47

 

analyses of mixtures of radionuclides are not always available, and radionuclide inventories 

are stated as ‘gross alpha,’ ‘gross beta,’ ‘gross gamma,’ or ‘mixed fission products’.” In these 

cases, 239Pu was used as the surrogate for gross alpha, 137Cs was used as the surrogate for 

gross gamma, and 90Sr was used as the surrogate for gross beta and mixed fission products 

to provide conservative dose estimates.”

[2] Szalinski, Paul A. ORAU Team. Health Physicist. April 2007. 

The surrogate radionuclides for gross alpha at Site 300 were derived from LLNL NESHAPs 

reports (Gallegos et al. 1998, 2000). For Site 300 the following applies for gross alpha 

analyses: “During Site 300 explosives experiments, the device containing depleted uranium is 

placed on an open air firing table and detonated.”

[3] Szalinski, Paul A. ORAU Team. Health Physicist. April 2007. 

The surrogate radionuclide for gross beta at Site 300 is 234Th. Only tritium and depleted 

uranium were reported as released into the environment at Site 300 (Gallegos et al. 1998, 

2000). Thorium-234 is a progeny of the 238U.

[4] Szalinski, Paul A. ORAU Team. Health Physicist. March 2007. 

A geometric standard deviation of 3 is used in ORAUT-OTIB-0018, Internal Dose 

Overestimates for Facilities with Air Sampling Programs (ORAUT 2005). 

[5] Szalinski, Paul A. ORAU Team. Health Physicist. April 2007. 

The external gamma radiation data are directly from site annual environmental reports, except 

where indicated by footnote. The site maximum and average values from the reports are

listed in the table.

[6] Szalinski, Paul A. ORAU Team. Health Physicist. April 2007. 

The external gamma radiation data are directly from site annual environmental reports, except 

where indicated by footnote. The site maximum and average values from the reports are 

listed in the table.

[7] Smith, Matthew H. ORAU Team. Sr. Health Physicist. November 2009. 

The external neutron radiation data are directly from site annual environmental reports. The 

site maximum and average values from the reports are listed in the table.
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Year Environmental report

1994 Harrach, R. J., G. M. Gallegos, R. A. Failor, E. Christofferson, P. J. Tate, E. R. Brandstetter, 

J. M. Larson, J. R. McIntyre, B. C. Fields, R. A. Brown, L. M. Garcia, A. R. Grayson, 

K. A. Surano, S. J. Coleman, B. J. Qualheim, M. J. Taffet, D. H. MacQueen, R. G. 

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van Warmerdam, B. K. Balke, S. Mathews, W. G. Hoppes, and C. H. Grandfield, 

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1995 Harrach, R. J., R. A. Failor, G. M. Gallegos, P. J. Tate, E. Christofferson, E. R. Brandstetter, 

J. M. Larson, A. H. Biermann, R. A. Brown, B. C. Fields, L. M. Garcia, A, R. Grayson, 

M. J. Taffet, R. G. Blake, K. A. Surano, J. H. White, S. J. Coleman, C. E. DeGrange, 

J. Celeste, D. H. MacQueen, E. Eagan, K. J. Folks, F. J. Gouveia, S. P. Harris, D. M. 

Chase, J. M. Bennett, M. Mlekush, S. P. Mancieri, J. S. Woollett, Jr., K. C. Zahn, R. 

J. Vellinger, T. M. Carlsen, C. van Warmerdam, J. R. McIntyre, S. Mathews, S. S. 

Goodwin, D. Rice, W. G. Hoppes, B. J. Qualheim, C. H. Grandfield, R. Ragaini, and 

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1996 Harrach, R. J., G. M. Gallegos, P. J. Tate, E. Christofferson, E. R. Brandstetter, J. M. 

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Harrach, R. J., G. M. Gallegos, P. J. Tate, E. Christofferson, E. R. Brandstetter, J. M. 

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Year Environmental report

1997 Harrach, R. J., J. M. Larson, G. M. Gallegos, E. Christofferson, E. R. Brandstetter, P. J. 

Tate, A. H. Biermann, B. C. Fields, L. M. Garcia, P. Althouse, R. J. Vellinger, S. J. 

Coleman, K. J. Folks, R. A. Brown, J. Celeste, K. A. Surano, M. J. Taffet, R. G. 

Blake, D. H. MacQueen, F. J. Gouveia, W. Burks-Houck, S. Mathews, J. R. Merrigan, 

S. L. Brigdon, A. R. Grayson, J. M. Woods, D. H. Armstrong, H. K. Otsuki, C. van 

Warmerdam, S. P. Harris, J. M. Bennett, R. K. Henry, D. W. Short, J. C. Steenhoven, 

S. P. Mancieri, J. S. Woollett, Jr., K. C. Zahn, T. M. Carlsen, C. E. DeGrange, J. R. 

McIntyre, W. G. Hoppes, C. H. Grandfield, C. S. Jackson, K. V. Gilbert, and R. K. 

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Harrach, R. J., J. M. Larson, G. M. Gallegos, E. Christofferson, E. R. Brandstetter, P. J. 

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Environmental Report 1997, Data Supplement, UCRL-50027-97, H. L. Lentzner and 

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1998 Larson, J. M., R. J. Harrach, P. E. Althouse, N. A. Bertoldo, A. H. Biermann, R. G. Blake, E. 

R. Brandstetter, S. L. Brigdon, R. A. Brown, E. Christofferson, K. J. Folks, G. M. 

Gallegos, L. M. Garcia, T. A. Giesing, A. R. Grayson, L. C. Hall, D. H. MacQueen, S. 

Mathews, S. R. Peterson, M. J. Taffet, P. J. Tate, R. J. Vellinger, and R. J. Ward, 

1999, Environmental Report 1998, UCRL-50027-98, H. L. Lentzner, K. S. Rath, and 

G. S. Siemering, editors, University of California, Lawrence Livermore National 

Laboratory, Livermore, California, September 1. [SRDB Ref ID: 23045]

Larson, J. M., R. J. Harrach, P. E. Althouse, N. A. Bertoldo, A. H. Biermann, R. G. Blake, E. 

R. Brandstetter, S. L. Brigdon, R. A. Brown, E. Christofferson, K. J. Folks, G. M. 

Gallegos, L. M. Garcia, T. A. Giesing, A. R. Grayson, L. C. Hall, D. H. MacQueen, S. 

Mathews, S. R. Peterson, M. J. Taffet, P. J. Tate, R. J. Vellinger, and R. J. Ward, 

1999, Environmental Report 1998, Data Supplement, UCRL-50027-98, H. L. 

Lentzner, K. S. Rath, and G. S. Siemering, editors, University of California, Lawrence 

Livermore National Laboratory, Livermore, California, September 1. [SRDB Ref ID: 

140695]

1999 Larson, J. M., A. H. Biermann, R. J. Harrach, P. E. Althouse, N. A. Bertoldo, R. G. Blake, E. 

R. Brandstetter, S. L. Brigdon, R. A. Brown, E. Christofferson, K. J. Folks, G. M. 

Gallegos, L. M. Garcia, T. A. Giesing, A. R. Grayson, L. C. Hall, D. H. MacQueen, S. 

Mathews, S. R. Peterson, M. J. Taffet, P. J. Tate, R. J. Vellinger, R. J. Ward, and R. 

A. Williams, 2000, Environmental Report 1999, UCRL-50027-99, K. S. Rath, N. J. 

Woods, G. J. Cannon, and N. M. Sanford, editors, University of California, Lawrence 

Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 23046]

Larson, J. M., A. H. Biermann, R. J. Harrach, P. E. Althouse, N. A. Bertoldo, R. G. Blake, E. 

R. Brandstetter, S. L. Brigdon, R. A. Brown, E. Christofferson, K. J. Folks, G. M. 

Gallegos, L. M. Garcia, T. A. Giesing, A. R. Grayson, L. C. Hall, D. H. MacQueen, S. 

Mathews, S. R. Peterson, M. J. Taffet, P. J. Tate, R. J. Vellinger, R. J. Ward, and R. 

A. Williams, 2000, Environmental Report 1999, Data Supplement, UCRL-50027-99, 

K. S. Rath, N. J. Woods, G. J. Cannon, and N. M. Sanford, editors, University of 

California, Lawrence Livermore National Laboratory, Livermore, California, 

September 1. [SRDB Ref ID: 140700]
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Year Environmental report

2000 Althouse, P. E., N. A., Bertoldo, R. G. Blake, S. L. Brigdon, R. A. Brown, C. G. Campbell, E. 

Christofferson, L. M. Clark, K. J. Folks, G. M. Gallegos, A. R. Grayson, R. J. Harrach, 

J. M. Larson, D. H. MacQueen, S. Mathews, B. Nisbet, S. R. Peterson, M. J. Taffet, 

P. J. Tate, R. J. Vellinger, and R. A. Williams, 2001, Environmental Report 2000, 

UCRL-50027-00, N. J. Woods and L. L. Powers, editors, University of California, 

Lawrence Livermore National Laboratory, Livermore, California, September 1. 

[SRDB Ref ID: 23031]

Althouse, P. E., N. A. Bertoldo, R. G. Blake, S. L. Brigdon, R. A. Brown, C. G. Campbell, E. 

Christofferson, L. M. Clark, K. J. Folks, G. M. Gallegos, A. R. Grayson, R. J. Harrach, 

J. M. Larson, D. H. MacQueen, S. Mathews, B. Nisbet, S. R. Peterson, M. J. Taffet, 

P. J. Tate, R. J. Vellinger, and R. A. Williams, 2001, Environmental Report 2000, 

Data Supplement, UCRL-50027-00, N. J. Woods and L. L. Powers, editors, 

University of California, Lawrence Livermore National Laboratory, Livermore, 

California, September 1. [SRDB Ref ID: 140703]

2001 Gallegos, G. M., P. E. Althouse, N. A., Bertoldo, R. G. Blake, S. L. Brigdon, R. A. Brown, C. 

G. Campbell, E. Christofferson, L. M. Clark, A. R. Grayson, R. J. Harrach, H. E. 

Jones, D. H. MacQueen, S. Mathews, S. R. Peterson, M. A. Revelli, L. Sanchez, M. 

J. Taffet, P. J. Tate, R. Ward, and R. A. Williams, 2002, Environmental Report 2001, 

UCRL-50027-01, N. J. Woods and J. Kohl, editors, University of California, Lawrence 

Livermore National Laboratory, Livermore, California, September 1. [SRDB Ref ID: 

23032]

Gallegos, G. M., P. E. Althouse, N. A. Bertoldo, R. G. Blake, S. L. Brigdon, R. A. Brown, C. 

G. Campbell, E. Christofferson, L. M. Clark, A. R. Grayson, R. J. Harrach, H. E. 

Jones, D. H. MacQueen, S. Mathews, S. R. Peterson, M. A. Revelli, L. Sanchez, M. 

J. Taffet, P. J. Tate, R. Ward, and R. A. Williams, 2002, Environmental Report 2001, 

Data Supplement, UCRL-50027-01, N. J. Woods and J. Kohl, editors, University of 

California, Lawrence Livermore National Laboratory, Livermore, California, 

September 1. [SRDB Ref ID: 140704]

2002 Sanchez, L., P. E. Althouse, N. A. Bertoldo, R. G. Blake, S, L. Brigdon, R, A. Brown, C. G. 

Campbell, T. Carlsen, E. Christofferson, L. M. Clark, G. M. Gallegos, A. R. Grayson, 

R. J. Harrach, W. G. Hoppes, H. E. Jones, J. Larson, D. Laycak, D. H. MacQueen, S. 

Mathews, M. Nelson, L. Paterson, S. R. Peterson, M. A. Revelli, M. J. Taffet, P. J. 

Tate, R. Ward, R. A. Williams, K. Wilson, and N. J. Woods, 2003, Environmental 

Report 2002, UCRL-50027-02, N. J. Woods, editor, University of California, 

Lawrence Livermore National Laboratory, Livermore, California, August 29. [SRDB 

Ref ID: 28167]

Sanchez, L., P. E. Althouse, N. A. Bertoldo, R. G. Blake, S. L. Brigdon, R. A. Brown, C. G. 

Campbell, T. Carlsen, E. Christofferson, L. M. Clark, G. M. Gallegos, A. R. Grayson, 

R. J. Harrach, W. G. Hoppes, H. E. Jones, J. Larson, D. Laycak, D. H. MacQueen, S. 

Mathews, M. Nelson, L. Paterson, S. R. Peterson, M. A. Revelli, M. J. Taffet, P. J. 

Tate, R. Ward, R. A. Williams, K. Wilson, and N. J. Woods, 2003, Environmental 

Report 2002, Data Supplement, UCRL-50027-02, N. J. Woods, editor, University of 

California, Lawrence Livermore National Laboratory, Livermore, California, August 

29. [SRDB Ref ID: 176961]
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Year Environmental report

2003 Sanchez, L., P. E. Althouse, N. A. Bertoldo, R. G. Blake, S, L. Brigdon, R, A. Brown, E. 

Christofferson, L. M. Clark, G. M. Gallegos, A. R. Grayson, R. J. Harrach, W. G. 

Hoppes, H. E. Jones, J. Larson, D. H. MacQueen, S. Mathews, B. A. Nisbet, L. 

Paterson, S. R. Peterson, M. A. Revelli, D. Rueppel, M. J. Taffet, P. J. Tate, and K. 

Wilson, 2004, Environmental Report 2003, UCRL-50027-03, N. J. Woods, editor, 

University of California, Lawrence Livermore National Laboratory, Livermore, 

California, October 1. [SRDB Ref ID: 28168]

LLNL (Lawrence Livermore National Laboratory), 2004, Ambient Air Weekly Concentrations 

from Air Particulate Samples from Various Livermore Locations 2003, University of 

California, Lawrence Livermore National Laboratory, Livermore, California. [SRDB 

Ref ID: 176956] 

LLNL (Lawrence Livermore National Laboratory), 2004, Radioactivity in Surface and 

Drinking Water in Livermore Valley and Monitoring Data for Releases from the 

Drainage Retention Basin 2003, [SRDB Ref ID: 177003]

2004 Peterson, S. R., P. E. Althouse, N. A. Bertoldo, R. A. Brown, C. B. Campbell, L. M. Clark, G. 

M. Gallegos, A. R. Grayson, R. J. Harrach, H. E. Jones, D. H. MacQueen, S. 

Mathews, B. A. Nisbet, C. D. Noyes, L. Paterson, M. A. Revelli, D. Rueppel, L. 

Sanchez, M. J. Taffet, P. J. Tate, and K. Wilson, 2005, Environmental Report 2004, 

UCRL-50027-04, N. J. Woods, editor, University of California, Lawrence Livermore 

National Laboratory, Livermore, California, September 30. [SRDB Ref ID: 28169]

LLNL (Lawrence Livermore National Laboratory), 2005, Ambient Air Weekly Concentrations 

from Air Particulate Samples from Various Livermore Locations 2004, University of 

California, Lawrence Livermore National Laboratory, Livermore, California. [SRDB 

Ref ID: 176949] 

LLNL (Lawrence Livermore National Laboratory), 2005, Radioactivity in Surface and 

Drinking Water in Livermore Valley and Monitoring Data for Releases from the 

Drainage Retention Basin 2004, University of California, Lawrence Livermore 

National Laboratory, Livermore, California. [SRDB Ref ID: 176959]

2005 Peterson, S. R., D. Armstrong, N. A. Bertoldo, S. Brigdon, R. A. Brown, C. B. Campbell, S. 

Cerruti, C. L. Conrado, A. R. Grayson, H. E. Jones, J. Karachewski, D. H. 

MacQueen, S. Mathews, M. A. Revelli, D. Rueppel, L. Sanchez, M. J. Taffet, K. 

Wilson, and J Woollett, 2006, Environmental Report 2005, UCRL-50027-05, N. J. 

Woods, editor, University of California, Lawrence Livermore National Laboratory, 

Livermore, California, September 29. [SRDB Ref ID: 175545] 

LLNL (Lawrence Livermore National Laboratory), 2006, Ambient Air Weekly Concentrations 

from Air Particulate Samples from Various Livermore Locations 2005, University of 

California, Lawrence Livermore National Laboratory, Livermore, California. [SRDB 

Ref ID: 176958] 

LLNL (Lawrence Livermore National Laboratory), 2006, Radioactivity in Surface and 

Drinking Water in Livermore Valley and Monitoring Data for Releases from the 

Drainage Retention Basin 2005, University of California, Lawrence Livermore 

National Laboratory, Livermore, California. [SRDB Ref ID: 176960]
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Year Environmental report

2006 Matthews, S., N. A. Bertoldo, R. A. Brown, C. G. Campbell, S. Cerruti, C. L. Conrado, A. 

Grayson, H. E. Jones, J. A. Karachewski, G. Kumamoto, J. Larson, D. H. MacQueen, 

L. Paterson, S. R. Peterson, M. A. Revelli, D Rueppel, M. J. Taffet, K. Wilson, and J. 

Woollett, 2007, Environmental Report 2006, UCRL-TR-50027-06, D. C. Burke, 

editor, University of California, Lawrence Livermore National Laboratory, Livermore, 

California, September 28. [SRDB Ref ID: 140776] 

LLNL (Lawrence Livermore National Laboratory), 2007, Ambient Air Weekly Concentrations 

from Air Particulate Samples from Various Livermore Locations 2006, University of 

California, Lawrence Livermore National Laboratory, Livermore, California. [SRDB 

Ref ID: 176950] 

LLNL (Lawrence Livermore National Laboratory), 2007, Monitoring Data for Releases from 

Lake Haussmann, Rain Water Samples Near Livermore Site and Surface Drinking 

Water in Livermore Valley 2006, University of California, Lawrence Livermore 

National Laboratory, Livermore, California. [SRDB Ref ID: 176952] 

LLNL (Lawrence Livermore National Laboratory), 2007, Ambient Radiation Livermore Site 

Perimeter, Livermore Valley, Site 300 and Offsite Locations Near Site 300 2006, 

University of California, Lawrence Livermore National Laboratory, Livermore, 

California. [SRDB Ref ID: 176953]

2007 Matthews, S., G. Gallegos, R. Lindee, L. Berg, N. A. Bertoldo, C. G. Campbell, S. Cerruti, J. 

L. Doman, L. S. Ferry, A. R. Grayson, H. E. Jones, G. Kumamoto, J. Larson, D. H. 

MacQueen, L. Paterson, M. A. Revelli, M. Ridley, D. Rueppel, A. M. Wegrecki, K. 

Wilson, and Jim Woollett, 2008, Environmental Report 2007, UCRL-TR 50027-07 N. 

J. Woods, editor, University of California, Lawrence Livermore National Laboratory, 

Livermore, California, August 29. [SRDB Ref ID: 140877] 

LLNL (Lawrence Livermore National Laboratory), 2008, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2007, 

University of California, Lawrence Livermore National Laboratory, Livermore, 

California. [SRDB Ref ID: 176947] 

LLNL (Lawrence Livermore National Laboratory), 2008, Tritium Activity in Rain Water 

Samples Collected on the Livermore Site and Site 300 and Radioactivity in Surface 

and Drinking Water in Livermore Valley 2007, University of California, Lawrence 

Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 176948]

2008 Gallegos, G., N. A. Bertoldo, C. G. Campbell, S. Cerruti, V. Dibley, J. L. Doman, A. R. 

Grayson, H. E. Jones, G. Kumamoto, D. H. MacQueen, J. C. Nelson, L. Paterson, M. 

A. Revelli, A. M. Wegrecki, K. Wilson, and J. Woollett, 2009, Environmental Report 

2008, UCRL-50027-08, N. J. Woods, editor, Lawrence Livermore National Security, 

Lawrence Livermore National Laboratory, Livermore, California, August 31. [SRDB 

Ref ID: 137257] 

LLNL (Lawrence Livermore National Laboratory), 2009, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2008,

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176926] 

LLNL (Lawrence Livermore National Laboratory), 2009, Monitoring Data for Releases from 

Lake Haussmann, Rain Water Samples Near Livermore Site and Surface Drinking 

Water in Livermore Valley 2008, Lawrence Livermore National Security, Lawrence 

Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 176937]
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Year Environmental report

2009 Gallegos, G., N. A. Bertoldo, R. Blake, C. G. Campbell, S. Cerruti, J. Cody, V. Dibley, J. L. 

Doman, A. R. Grayson, H. E. Jones, G. Kumamoto, D. H. MacQueen, J. C. Nelson, 

L. Paterson, M. A. Revelli, A. M. Wegrecki, K. Wilson, and J. Woollett, 2010, 

Environmental Report 2009, UCRL-TR-50027-09, N. J. Woods, editor, Lawrence 

Livermore National Security, Lawrence Livermore National Laboratory, Livermore, 

California, August 31. [SRDB Ref ID: 140705] 

LLNL (Lawrence Livermore National Laboratory), 2010, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2009, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176927] 

LLNL (Lawrence Livermore National Laboratory), 2010, Monitoring Data for Releases from 

Lake Haussmann, Rain Water Samples Near Livermore Site and Surface Drinking 

Water in Livermore Valley 2009, Lawrence Livermore National Security, Lawrence 

Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 176939]

2010 Jones, H. E., D. Armstrong, R. Blake, N. A. Bertoldo, C. G. Campbell, S. Cerruti, J. Cody, V. 

Dibley, J. L. Doman, G. Gallegos, A. R. Grayson, K. Heidecker, R. Hollister, G 

Kumamoto, D. H. MacQueen, J. C. Nelson, L. Paterson, M. A. Revelli, C. Rosene, A. 

Terrill, A. M. Wegrecki, K. Wilson, and J. Woollett, 2011, Environmental Report 2010, 

UCRL-TR-50027-10, K. Fury, editor, Lawrence Livermore National Security, 

Lawrence Livermore National Laboratory, Livermore, California, September 12. 

[SRDB Ref ID: 137256] 

LLNL (Lawrence Livermore National Laboratory), 2011, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2010, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176928] 

LLNL (Lawrence Livermore National Laboratory), 2011, Monitoring Data for Releases from 

Lake Haussmann, Rain Water Samples Near Livermore Site and Surface Drinking 

Water in Livermore Valley 2010, Lawrence Livermore National Security, Lawrence 

Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 176940]

2011 Jones, H. E., D. Armstrong, R. Blake, N. A. Bertoldo, S. Cerruti, V. Dibley, J. L. Doman, A. 

R. Grayson, K. Heidecker, R. Hollister, G Kumamoto, D. H. MacQueen, J. C. Nelson, 

H. Ottaway, L. Paterson, M. A. Revelli, C. Rosene, A. Terrill, A. M. Wegrecki, K. 

Wilson, and J. Woollett, 2012, Environmental Report 11, UCRL-TR-50027-11, H. 

Jones, editor, Lawrence Livermore National Security, Lawrence Livermore National 

Laboratory, Livermore, California, August 29. [SRDB Ref ID: 140878] 

LLNL (Lawrence Livermore National Laboratory), 2012, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2011,

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176929] 

LLNL (Lawrence Livermore National Laboratory), 2012, Monitoring Data for Releases from 

Lake Haussmann, Rain Water Samples Near Livermore Site and Surface Drinking 

Water in Livermore Valley 2011, Lawrence Livermore National Security, Lawrence 

Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 176941]
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Year Environmental report

2012 Jones, H. E., D. Armstrong, R. Blake, N. A. Bertoldo, S. Cerruti, C. Fish, V. Dibley, J. L. 

Doman, A. R. Grayson, K. Heidecker, R Hollister, G. Kumamoto, D. H. MacQueen, J. 

C. Nelson, H. Ottaway, L. Paterson, M. A. Revelli, C. Rosene, A. Terrill, A. M. 

Wegrecki, K. Wilson, and J. Woollett, 2013, Environmental Report 2012, UCRL-TR50027-12, H. Jones, editor, Lawrence Livermore National Security, Lawrence 

Livermore National Laboratory, Livermore, California, October 1. [SRDB Ref ID: 

140879] 

LLNL (Lawrence Livermore National Laboratory), 2013, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2012, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176930] 

LLNL (Lawrence Livermore National Laboratory), 2013, Radioactivity in Surface and 

Drinking Water in Livermore Valley 2012, Lawrence Livermore National Security, 

Lawrence Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 

176942]

2013 Jones, H. E., N. A. Bertoldo, R. Blake, J. Byrne, S. Cerruti, V. Dibley, J. L. Doman, C. Fish, 

A. R. Grayson, K. Heidecker, G. Kumamoto, D. H. MacQueen, W. Montemayor, H. 

Ottaway, L. Paterson, M. A. Revelli, C. Rosene, A. Terrill, A. M. Wegrecki, K. Wilson, 

J. Woollett, and R. Veseliza, 2014, Environmental Report 2013, UCRL-TR-50027-13, 

H. Jones, editor, Lawrence Livermore National Security, Lawrence Livermore 

National Laboratory, Livermore, California, October 1. [SRDB Ref ID: 140647] 

LLNL (Lawrence Livermore National Laboratory), 2014, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2013, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176931] 

LLNL (Lawrence Livermore National Laboratory), 2014, Tritium Activities in Rain Water 

Samples on the Livermore Site and Radioactivity in Surface and Drinking Water in 

Livermore Valley 2013, Lawrence Livermore National Security, Lawrence Livermore 

National Laboratory, Livermore, California. [SRDB Ref ID: 176943]

2014 Jones, H. E., N. Bertoldo, R. Blake, M. Buscheck, J. Byrne, S. Cerruti, C. Fish, M. 

Fratanduono, A. Grayson, D. MacQueen, W. Montemayor, H. Ottaway, L. Paterson, 

M. Revelli, C. Rosene, K. Swanson, A. Terrill, A. Wegrecki, K. Wilson, and J. 

Woollett, 2015, Environmental Report 2014, UCRL-TR-50027-14, H. Jones, editor, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California, October 1. [SRDB Ref ID: 175546] 

LLNL (Lawrence Livermore National Laboratory), 2015, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2014, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176932] 

LLNL (Lawrence Livermore National Laboratory), 2015, Tritium Activities in Rain Water 

Samples and Radioactivity in Surface and Drinking Water in Livermore Valley 2014, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176945]
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Year Environmental report

2015 Rosene, C., H. Jones, R. Blake, M. Buscheck, H. Byrnes, C. Fish, M. Fratanduono, G. 

Gallegos, D. MacQueen, W. Montemayor, H. Ottaway, L. Paterson, J. Pyon, M. 

Revelli, K. Swanson, A. Terrill, A. Wegrecki, K. Wilson, and J. Woollett, 2016, 

Environmental Report 2015, UCRL-TR-50027-15, C. Rosene and H. Jones, editors, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California, October 1. [SRDB Ref ID: 175547] 

LLNL (Lawrence Livermore National Laboratory), 2016, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2015, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176933] 

LLNL (Lawrence Livermore National Laboratory), 2016, Tritium Activities in Rain Water 

Samples on the Livermore Site and Radioactivity in Surface and Drinking Water in 

Livermore Valley 2015, Lawrence Livermore National Security, Lawrence Livermore 

National Laboratory, Livermore, California. [SRDB Ref ID: 176946]

2016 Rosene, C., R. Blake, M. Buscheck, H. Byrnes, S. Diaz, C. Fish, H. Jones, D. MacQueen, 

W. Montemayor, C. Murphy, C. Noyes, H. Ottaway, L. Paterson, J. Pyon, K. 

Swanson, C. Vilila, A. Wegrecki, K. Wilson, and J. Woollett, 2017, Environmental 

Report 2016, UCRL-TR-50027-16, C. A. Rosene, editor, Lawrence Livermore 

National Security, Lawrence Livermore National Laboratory, Livermore, California, 

October 1. [SRDB Ref ID: 175548] 

LLNL (Lawrence Livermore National Laboratory), 2017, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2016, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176934] 

LLNL (Lawrence Livermore National Laboratory), 2017, Tritium Activity in Rain Water 

Samples Collected on the Livermore Site and Site 300 and Radioactivity in Surface 

and Drinking Water in Livermore Valley 2016, Lawrence Livermore National Security, 

Lawrence Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 

176955]

2017 Rosene, C., R. Blake, E. Brenner, M. Buscheck, H. Byrnes, S. Diaz, C. Fish, H. Jones, D. 

MacQueen, W. Montemayor, C. Murphy, C. Noyes, H. Ottaway, L. Paterson, K. 

Swanson, C. Vilila, A. Wegrecki, and K. Wilson, 2018, Environmental Report 2017, 

UCRL-TR-50027-17, C. A. Rosene, editor, Lawrence Livermore National Security, 

Lawrence Livermore National Laboratory, Livermore, California, October 1. [SRDB 

Ref ID: 175549] 

LLNL (Lawrence Livermore National Laboratory), 2018, Ambient Air Weekly Concentrations 

from Air Particulate Samples from the Livermore Perimeter Locations 2017, 

Lawrence Livermore National Security, Lawrence Livermore National Laboratory, 

Livermore, California. [SRDB Ref ID: 176936] 

LLNL (Lawrence Livermore National Laboratory), 2018, Tritium Activity in Rain Water 

Samples Collected on the Livermore Site and Site 300 and Radioactivity in Surface 

and Drinking Water in Livermore Valley 2017, Lawrence Livermore National Security, 

Lawrence Livermore National Laboratory, Livermore, California. [SRDB Ref ID: 

176957]
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Year Environmental report

2018 Rosene, C., M. Abri, M. Buscheck, H. Byrnes, C. Campbell, A. Chan, S. Diaz, T. Jackson, 

W. Montemayor, C. Murphy, C. Noyes, H. Ottaway, L. Paterson, L. Stephens, M. 

Taffet, A. Wegrecki, and K. Wilson, 2019, Environmental Report 2018, UCRL-TR50027-18, C. A. Rosene, editor, Lawrence Livermore National Security, Lawrence 

Livermore National Laboratory, Livermore, California, October 1. [SRDB Ref ID: 

178520]
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GLOSSARY

alpha radiation

Positively charged particle emitted from the nuclei of some radioactive elements. An alpha 

particle consists of two neutrons and two protons (a helium nucleus) and has an electrostatic 

charge of +2.

background radiation

Radiation from cosmic sources, naturally occurring radioactive materials including naturally 

occurring radon, and global fallout from the testing of nuclear explosives. Background 

radiation does not include radiation from source, byproduct, or Special Nuclear Materials 

regulated by the U.S. Nuclear Regulatory Commission. The average individual exposure from 

background radiation is about 360 millirem per year.

becquerel (Bq)

International System unit of radioactivity equal to 1 disintegration per second; 1 curie equals 

37 billion (3.7 × 1010) Bq.

beta radiation

Charged particle emitted from some radioactive elements with a mass equal to 1/1,837 that of 

a proton. A negatively charged beta particle is identical to an electron. A positively charged 

beta particle is a positron.

deep dose equivalent

Dose equivalent in units of rem or sievert for a 1-centimeter depth in tissue (1,000 milligrams 

per square centimeter).

dosimetry

Measurement and calculation of internal and external radiation doses.

radioactivity

Property possessed by some elements (e.g., uranium) or isotopes (e.g., 14C) of spontaneously 

emitting energetic particles (electrons or alpha particles) by the disintegration of their atomic 

nuclei.

rem

Traditional unit of radiation dose equivalent that indicates the biological damage caused by 

radiation equivalent to that caused by 1 rad of high-penetration X-rays multiplied by a quality 

factor. The sievert is the International System unit; 1 rem equals 0.01 sievert. The word 

derives from roentgen equivalent in man; rem is also the plural.

thermoluminescent dosimeter

Device for measuring radiation dose that consists of a holder containing solid chips of material 

that, when heated, release the stored energy as light. The measurement of this light provides 

a measurement of absorbed dose. Thermoluminescent dosimeters replaced film dosimeters 

at essentially all U.S. Department of Energy sites beginning in the 1960s.