Page 1 of 70

DOE Review Release 06/19/2019

Evaluation of Savannah River Site 

Americium-241 Source Terms Between 1971 

and 1999 Using Bioassay Frequency Tables 

ORAUT-RPRT-0091 Rev. 00

Effective Date: 06/10/2019

Supersedes: None

Subject Expert(s): Roger L. Halsey

Document Owner 

Approval: Signature on File

James M. Mahathy, Document Owner

Approval Date: 06/06/2019

Concurrence: Signature on File

Daniel H. Stempfley, Objective 4 Representative

Concurrence Date: 06/06/2019

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 06/06/2019

Approval: Signature on File

Timothy D. Taulbee, Associate Director for Science

Approval Date: 06/10/2019

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-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 2 of 70

 

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

06/10/2019 00 New report initiated in order to evaluate Savannah River Site 241Am 

source terms between 1971 and 1999 using bioassay frequency 

tables. Incorporates formal internal and NIOSH review comments. 

Initiated by James M. Mahathy. 
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TABLE OF CONTENTS

SECTION TITLE PAGE

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

1.0 Introduction ................................................................................................................................. 7

2.0 Internal Dosimetry Program Self-Assessment ............................................................................ 7

3.0 In Vivo and In Vitro Bioassay Monitoring .................................................................................... 8

3.1 Routine Bioassay Sampling Program ............................................................................. 8

3.2 Special Bioassay Sampling Program .............................................................................. 9

3.3 Whole-Body and Chest Counts.....................................................................................10

3.3.1 Chest Counting...............................................................................................10

3.3.2 Whole-Body Counting ....................................................................................10

3.3.3 Whole-Body Count and Chest Count Totals...................................................11

3.4 Routine Bioassay Sample Frequency Tables ...............................................................14

3.4.1 DPSOL 193-302, Bioassay Control, Revision 5, September 1, 1971.............15

3.4.2 DPSOL 193-302, Bioassay Control, Revision 7, October 15, 1976 ...............16

3.4.3 DPSOL 193-302T, Bioassay Control, Revision 0, February 25, 1985............17

3.4.4 DPSOL 193-211, Bioassay Control, Revision 0, March 9, 1989 ....................17

3.4.5 Manual 5Q1.1, Procedure 506, In Vivo and In Vitro Bioassay 

Scheduling and Administration, Revision 0, December 16, 1992...................18

3.4.6 Manual 5Q1.1, Procedure 506, In Vivo and In Vitro Bioassay 

Scheduling and Administration, Revision 5, April 1, 1996..............................20

3.4.7 Manual 5Q1.1, Procedure 506, In Vivo and In Vitro Bioassay 

Scheduling and Administration, Revision 10, March 2, 1999 .........................20

3.4.8 Specification of Urine Bioassay Requirements on Radiological Work 

Permits ...........................................................................................................21

4.0 Americium, Curium, and Californium Source Terms from Bioassay Frequency Tables ...........23

4.1 Urine Bioassay ..............................................................................................................23

4.2 Chest Counts ................................................................................................................24

5.0 Dose Reconstruction Considerations........................................................................................25

5.1 Air Sampling..................................................................................................................25

5.2 Chest Counts ................................................................................................................26

5.3 Routine Urine Bioassay................................................................................................. 26

5.4 Routine Bioassay Not Required in Bioassay Procedures .............................................27

6.0 Conclusions ..............................................................................................................................31

6.1 Response to SC&A Comments.....................................................................................31

6.1.1 Americium and Curium...................................................................................32

6.1.2 References Quoted by SC&A.........................................................................33

6.1.3 Questions Raised by SC&A ...........................................................................34

References ...........................................................................................................................................38

ATTACHMENT A BIOASSAY FREQUENCIES AND SOURCE TERMS.......................................45

ATTACHMENT B EXAMPLES OF WHOLE-BODY AND CHEST COUNT REPORTS..................68
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LIST OF TABLES

TABLE TITLE PAGE

3-1 WBCs and chest counts, 1972 to 1985.....................................................................................12

3-2 WBCs and chest counts, 1974..................................................................................................14

3-3 Workers with only WBCs, only chest counts, or both, 1974 .....................................................14

3-4 In vivo counting frequency reproduced from DPSOL 193-302T ...............................................17

4-1 Areas with recommended routine Am/Cm/Cf bioassay sampling .............................................24

4-2 Summary of annual chest count requirements from the bioassay control procedures 

and tables ................................................................................................................................. 25

5-1 Annual totals for urine bioassay samples, 1972 to 2005 ..........................................................27

5-2 MPPF RWPs.............................................................................................................................29

5-3 Workers signed in to one or more MPPF RWPs.......................................................................30

5-4 Lung count dates for MPPF workers with data in NOCTS or SRDB.........................................31

A-1 Routine bioassay sampling frequencies excluding construction division, 

DPSOL 193-302, Revision 5, samples per year .......................................................................46

A-2 Bioassay frequencies, DPSOL 193-302, Revision 7................................................................. 48

A-3 Bioassay frequencies, DPSOL 193-302T, Revision 0 ..............................................................50

A-4 Bioassay frequency table, DPSOL 193-211, Revision 0...........................................................52

A-5 Minimum bioassay schedules for SRS facilities, Manual 5Q1.1, Procedure 506, 

Revision 0 ................................................................................................................................. 53

A-6 Minimum bioassay schedules for SRS facilities, Manual 5Q1.1, Procedure 506, 

Revision 5 ................................................................................................................................. 58

A-7 Source terms from Farrell and Findley (1999) ..........................................................................64

A-8 Source terms from Farrell and Findley (1999) versus Manual 5Q1.1, Procedure 506, 

Revision 5, minimum bioassay schedules ................................................................................65

LIST OF FIGURES 

FIGURE TITLE PAGE

3-1 Whole-body counter used in the 1970s ....................................................................................11

3-2 WBCs and chest counts, 1972 to 1982.....................................................................................12

3-3 WBCs, 1986 to 1992.................................................................................................................13

3-4 Chest counts, 1986 to 1992......................................................................................................13

3-5 WBCs and chest counts, 1974..................................................................................................15

5-1 Americium samples, 1972 to 2005 ............................................................................................28

B-1 WBC and chest count report, 1983...........................................................................................69

B-2 WBC and chest count report, 1998...........................................................................................70
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ACRONYMS AND ABBREVIATIONS 

ACD Analytical Chemistry Division

ADS Analytical Development Section

ALARA as low as is reasonably achievable

CFR Code of Federal Regulations

CHTS Chemical and Hydrogen Technology Section

CLAB Central Laboratory Facility

cm centimeter

D&D decontamination and decommissioning

D&R dismantling and removal

DAC derived air concentration

decon decontamination

DOE U.S. Department of Energy

DWPF Defense Waste Processing Facility

E&I Electrical and Instrumentation

EU enriched uranium

FEB Facilities Evaluation Board

FP fission product

ft foot

HEPA high-efficiency particulate air

HLC high-level cave

HLW high-level waste

HP Health Physics

HPRED Health Protection Radiation Exposure Database

HTO tritiated water vapor

IA induced activity

in. inch 

L liter

LSC liquid scintillation counting

mo month

MPPF Multi-Purpose Processing Facility

mrem millirem

NIOSH National Institute for Occupational Safety and Health

NMD Nuclear Materials Division

NOCTS NIOSH-Division of Compensation Analysis and Support Claims Tracking System

OEI Office of Enforcement and Investigation

ORAU Oak Ridge Associated Universities

PUREX plutonium-uranium extraction

RA Radiological Area

RBA Radiological Buffer Area
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RBOF Receiving Basin for Offsite Fuel

RCA radiologically controlled area

RCG radioactivity concentration guide

RCO Radiological Control Operations

RM Reactor Maintenance

RQB radiation qualification badge 

RWP Radiation Work Permit

SCD Separations Chemistry Division

SED Separations Engineering Division

SRDB Ref ID Site Research Database Reference Identification (number)

SRS Savannah River Site 

SRTC Savannah River Technology Center 

SWE Solid Waste Engineering 

T&T Traffic and Transportation 

TNX code designation for Semi-works Laboratory 

WBC whole-body count 

WSRC Westinghouse Savannah River Corporation 

yr year 

μCi microcurie 
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1.0 INTRODUCTION

On January 11, 2018, SC&A submitted a memorandum, “Missing or Incomplete Radiological Source 

Terms,” to the Savannah River Site (SRS) Work Group of the Advisory Board on Radiation and 

Worker Health (SC&A 2018). 

In 1999, a sitewide characterization effort at SRS identified 241Am in areas that had not previously 

required routine bioassay sampling for 241Am. The memorandum was a review of and details on 

SC&A’s finding that some SRS workers in those areas were enrolled in incorrect bioassay programs 

under Radiation Work Permits (RWPs). 

SC&A provided Site Research Database (SRDB) references for their finding and posed several 

questions about the implications of the finding on the ability to achieve sufficiently accurate dose 

reconstructions. In their conclusion they state (SC&A 2018): 

SC&A believes that ... there was a clear deficiency recognized that may have impacted 

the proper bioassay enrollment of workers under RWPs prior to the implementation of a 

new site-wide formal policy, “Specifications of Urine Bioassay Requirements on 

Radiological Work Permits,” issued on March 10, 1999. Lack of proper specification of 

radionuclides of significance for internal dosimetry may have led to unmonitored 

exposures for which dose reconstruction with sufficient accuracy may not be feasible. 

This concern should be investigated further to ascertain its significance, scope, and 

implications for dose reconstruction.

The results of the investigation into the finding are provided in this report. 

2.0 INTERNAL DOSIMETRY PROGRAM SELF-ASSESSMENT 

In 1998, the SRS Facilities Evaluation Board (FEB) audited the Solid Waste Division (LaBone 1998). 

The audit noted that although the recommended routine bioassay requirements in Manual 5Q1.1, 

Procedure 506 (5Q1.1-506), In Vivo and In Vitro Bioassay Scheduling and Administration (e.g., 

WSRC 1996), specified only plutonium and strontium bioassays for workers at the burial ground, 

documentation showed the presence of curium. Investigation with Solid Waste Division personnel 

“resolved the concern over performing RWP sampling for curium ... due to inaccessibility to the 

curium present and the fact that plutonium is always present with the curium.” However, a pilot 

program was established for the solid waste disposal facilities to develop guidelines for selecting the 

radionuclides of concern for routine urine bioassays (Findley 1998). 

In early 1999, the U.S. Department of Energy (DOE) Office of Enforcement and Investigation (OEI) 

requested all DOE sites review their dose evaluation programs. The SRS contractor Westinghouse 

Savannah River Corporation (WSRC) established an internal assessment team to review the overall 

internal dosimetry program. A February 9, 1999, report from this team indicated that one of the areas 

evaluated was the method of identifying the predominant radionuclides in facilities to ensure 

appropriate bioassay sample analysis (WSRC 1999a, p. 11). In July 1999, the OEI issued a report 

summarizing responses from all DOE sites as a list of 31 general deficiencies and recommended that 

all contractors review their programs against this list.

Item B.8 on the list was, “Workers enrolled in incorrect routine bioassay program.” WSRC said in its 

November 2, 1999, report documenting their review of the 31 general deficiencies that this item was 

an SRS issue and that they had previously determined that “in some areas site workers were 

potentially exposed to americium, but that radionuclide was not recognized as an issue when 

preparing RWPs for those areas.” This report does not say which areas or workers were involved

(Morgan 1999). 
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WSRC answered Item B.8 by listing improvements that were made in the documentation and review 

of the radiological hazards. It referenced “Specification of Urine Bioassay Requirements on 

Radiological Work Permits” (Farrell and Findley 1999), which defined a formalized method of 

determining radiological source terms for bioassay compliance. Farrell and Findley (1999) also 

contained summaries from characterization reports from all eight WSRC divisions at SRS. The 

summary listed each radionuclide that contributed 10% or more of the internal dose from inhalation for 

locations or waste streams under each division (Farrell and Findley 1999). 

Before March 1999, site bioassay control procedures included a table of locations and job functions 

with recommended routine bioassay sampling types and frequencies. The radioisotope selection for 

each location was primarily based on process knowledge. The 1998 FEB audit found that some 

individuals responsible for establishing the bioassay requirements in RWPs were relying solely on the 

tables instead of establishing the radioisotopes actually present as required by the procedures

(LaBone 2004). 

In March 1999, the bioassay sample frequency table was removed from the bioassay control 

procedures. All radioisotopes that contributed 10% or more of the internal dose from inhaled material 

were to be considered for bioassay sampling when writing RWPs.

3.0 IN VIVO AND IN VITRO BIOASSAY MONITORING

SRS implemented bioassay programs to cover 35 facilities that processed actinides, fission products, 

and tritium (Thomas et al. 1993). From 1971 through 1999, SRS performed in vivo and in vitro

sampling for radioactive material using both routine and special sampling. 

For monitoring purposes, SRS assessed three ranges of internal exposure probability: 

• Workers “likely” to exceed 100 millirem annually and therefore be required to have routine 

bioassay monitoring under 10 CFR 835.402(c); 

• Workers with “reasonable potential” for exposure, those workers unlikely to exceed 

100 millirem annually but whose tasks required used respiratory protection while handling 

large amounts of unencapsulated radioactive materials; and 

• Workers with “no potential,” those who did not encounter unencapsulated sources nor used 

respiratory protection for radiological exposure.

No workers were considered to fall into the first range because none was considered to have routine 

internal exposures in excess of 100 millirem annually. Workers with “reasonable potential” for internal 

exposure were included in the Routine Bioassay Sampling Program. The Special Bioassay Sampling 

Program was designed for assessing “inadvertent intakes” of radioactive material that could exceed 

the 100-mrem threshold (LaBone 2001). 

The bioassay program was part of an overall strategy described as “Defense in Depth” and included a 

zero-intake policy, engineered and procedural controls, personal protective equipment, and 

surveillance. This surveillance included air monitoring, facility and personnel contamination surveys, 

and the routine bioassay program (LaBone 1997). 

3.1 ROUTINE BIOASSAY SAMPLING PROGRAM

Workers supplied urine samples on a prescheduled routine basis to be analyzed for tritium, plutonium, 

strontium, neptunium, uranium, enriched uranium (EU), americium, curium, californium, and fission 

products (FP) and induced activity (IA). Workers also supplied routine samples as requested when 
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necessitated by working under RWP with bioassay requirements. Internally deposited radioisotopes 

were measured directly in workers by the use of whole-body counters and chest counters. Details on 

the analysis techniques and their detection efficiencies are available in ORAUT-TKBS-0003, 

Savannah River Site (ORAUT 2005). 

A worker’s enrollment in the program was based on the radioactive hazards associated with the 

facility where the individual worked and the type of work the worker normally performed. Enrollment 

in the program was defined by building or specific operation and by the task, such as operators, 

laboratory personnel, supervisory personnel, etc. 

Tables in the bioassay control procedures defined urine bioassay types and sample frequencies. 

Whole-body count (WBC) and chest count frequencies were listed in the tables or described in the 

procedures. Except for the Construction Division, workers assigned to the listed buildings with the 

specified jobs were to have prescheduled routine bioassays according to these tables. Until 1992, 

Construction Division workers had separate requirements for routine bioassay in the procedures and 

were not required to use the bioassay frequency tables.

Job-specific sampling was used to sample workers, including Construction Division workers, who 

needed to enter locations with bioassay requirements not covered by prescheduled bioassay testing. 

These bioassay requirements were placed on RWPs when respiratory protection was used. A 

definition of the job-specific sampling from September 1997 was (Findley 1997a): 

Job-specific urine sampling is also known as “RWP (Radiation Work Permit) sampling” 

and is administered exclusively by radiological control personnel. RWPs are written to 

describe a specific scope of work to be performed. Additional information such as the 

expected radiological hazards to be encountered, respiratory protection if needed, and 

dosimetry requirements are listed on the RWP. Based on the degree and nature of the 

radiological hazards it may be necessary to request each worker performing “hands on” 

work to leave a urine bioassay sample, hence the term “job-specific sampling.” If a 

worker is wearing respiratory protection and is not on an appropriate routine sampling 

program then a job-specific sample should be requested. 

The Routine Bioassay Sampling Program, including both the prescheduled and the job-specific 

bioassays, was not used at SRS to detect and assess the intake of actinides. It was a “final quality 

control check that exposure control measures and workplace monitoring programs worked” (ORAUT 

2017a). It was implemented in excess of the regulatory requirements; none of the SRS workers met 

the 10 CFR Part 835 definition for requiring bioassay (ORAUT 2017a). 

3.2 SPECIAL BIOASSAY SAMPLING PROGRAM

SRS designed the Special Bioassay Sampling Program to assess “inadvertent intakes” of radioactive 

material that could exceed the 100-mrem threshold (WSRC 1990a, p. 36). Under this program, 

samples were required in response to unusual or unanticipated circumstances such as being involved 

in a contamination incident or from the results of air sampling. Intakes of radionuclides were assigned 

to the worker’s record of exposure when positive results of special bioassay sampling were confirmed.

The Special Bioassay Sampling Program did not use the bioassay frequency tables. Selection of the 

bioassay type for follow-up samples included obtaining information about the sources of exposure 

from air sample results, including isotopic composition (WSRC 1987). 

In an interview with a former SRS employee who worked exclusively in internal dosimetry between 

1986 and 2005, the former employee was asked about the source terms not including 241Am in certain 

locations leading to some workers not enrolling in the correct routine bioassay programs. In the 
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response, the former employee stated that “we did not have this problem for special samples, where 

we always required specification of the source term by analysis of the contamination that triggered 

collection of the sample” (SC&A 2018). In another interview on a similar topic, the same former 

employee stated that starting in 1986, SRS analyzed all bioassay samples by isotopic analysis 

(ORAUT 2013, p. 3). 

3.3 WHOLE-BODY AND CHEST COUNTS

3.3.1 Chest Counting

Chest counting was initially performed using a 5-in.-diameter thin NaI detector from 1966 to around 

1971. In 1971, a phoswich detection system was implemented that used a NaI/CsI sandwiched 

detector. This system was modified to a dual phoswich system in 1972 that remained in use until 

around 1987 or 1988. The phoswich chest counter was capable of measuring 241Am, 244Cm, and

252Cf, in addition to uranium and plutonium radioisotopes (ORAUT 2005). Two examples of combined 

WBC and chest count reports are provided in Attachment B, one from 1983 for a laboratory technician 

and one from 1998 for a construction laborer (SRS 1975–2018). 

In the early 1980s, two germanium detector systems were in use by SRS for chest counting, each 

with a single lithium-drifted solid-state germanium detector. The germanium detectors required 

cooling with liquid nitrogen and provided a much higher gamma resolution. The 51-mm-diameter by 

20-mm-thick germanium detectors were “low energy extended energy range” detectors. The 

phoswich detectors were kept as backup as late as 1990 (WSRC 1990a, p. 409; DuPont 1987,

p. 129). 

A new facility was placed in operation in April 1994 that included a graded liner in the shielding for 

reduced low-energy gamma background. A report from 1994 described the chest counter (WSRC 

1993, p 16): 

The counter consists of an array of six high-purity germanium detectors that are placed 

over the chest region during counting. The counting chamber is located in a 9' by 12' by 

8' high room that is constructed of 12" thick pre-World War II battleship steel. A 1/4" thick 

lead lining covers the inside walls and ceiling of the chamber.

In 1992 new limits based on lifetime committed dose instead of annual dose led to a significantly 

smaller amount of plutonium that had to be measured in a worker. Chest counting was no longer 

feasible for meeting plutonium requirements but was still used for 241Am. The overall result was a 

reduced number of chest counts performed annually (Taylor et al. 1995, p. 69). 

3.3.2 Whole-Body Counting

The Whole Body Counting Facility at SRS was used since 1960 to measure fission product activities 

directly in workers by counting them in a shielded room using a 4- by 8-in. NaI detector. The 

monitored individual sat in a reclining chair positioned in an arc around the detector; this was referred 

to as the “40-cm arc geometry” in bioassay monitoring reports. Bioassay via this method was not 

used for plutonium and americium due to their low-energy emissions. It is reported this detector was 

in service until September 1995. In the early 1970s, WBCs using an array of NaI detectors were 

implemented (Figure 3-1). WSRC-IM-90-139 (WSRC 2001) indicates five 4- by 4-in. detectors were 

used, while WSRC-RP-95-234 (Taylor et al. 1995) says that four 4- by 5-in. detectors were used. In 

addition, in the mid-1980s, WBCs using standup geometry and large (4-by-4-by-16-in. or 5-by-3-by16 in.) NaI detectors were implemented. The counting room was an 8-ft by 10-ft room with 8-ft

ceilings and was constructed of 12 in. of pre-WWI battleship steel and 0.25 in. of lead for shielding 

(WSRC 1990a, p. 417). 
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Figure 3-1. Whole-body counter used in the 1970s (Baker 2018) 

In 1988, the site began using Fastscan whole-body counters. These were commercially available 

standup counters that used large NaI detectors and a shadow shield arrangement that allowed much 

shorter counting time, 2 to 4 minutes, while retaining the necessary sensitivity. Two Fastscan 

counters were mounted in trucks so that they could be moved as needed (WSRC 1990a, p. 410). 

A third was installed at the Whole Body Counting Facility. By 1992, five Fastscan units were in use. 

The number of WBCs went from approximately 5,000 in 1986 to over 25,000 in 1990, while the 

number of chest counts remained relatively even between 2,000 and 3,000 per year (McFee 1992). 

Two examples of combined WBC and chest count reports are provided in Attachment B, one from 

1983 for a laboratory technician and one from 1998 for a construction laborer (SRS 1975–2018). 

Details on the equipment used and its detection efficiencies can be found in ORAUT-TKBS-0003

(ORAUT 2005). 

3.3.3 Whole-Body Count and Chest Count Totals

In the 1970s through the 1980s the Health Physics (HP) Division issued a series of monthly reports 

listing the numbers of positive urine bioassay results, positive WBCs, positive chest counts, and total 

numbers of chest and WBCs (DuPont 1982a to 1982e, 1983a and 1983b, 1984a to 1984e, 1985a to 

1985i; Wasser 1984; ORNL 1979). A positive result was when the radioactive material was detected 

above a given threshold. A complete series of these reports between January 1972 and December 

1981 was reviewed. For 1972 and 1973, the WBCs and chest counts were combined as one value. 

Monthly totals for the number of counts and the number of individuals counted were reported. 

Between December 1973 and December 1974, the number of chest counts and individuals getting 

chest counts were reported separately. In January 1975, the WBC and chest counts were combined 

to one value again in the reports and remained combined through December 1981 for all monthly 

reports. The monthly totals from these reports were added to provide annual totals and are shown in 

Table 3-1 and plotted in Figure 3-2. Note that 1974 is a sum of reported WBCs solely.
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Table 3-1. WBCs and chest counts, 

1972 to 1985. 

Year WBCs and chest counts

1972 1,302

1973 1,115

1974 1,756

1975 2,143

1976 1,736

1977 1,974

1978 2,148

1979 2,042

1980 2,190

1981 2,763

1982 2,641

1984 2,704

1985 2,454a

a. For 1985, the year to date total from 

November was used. HP Division

monthly reports for 1983 have not yet 

been acquired from SRS.

Figure 3-2. WBCs and chest counts, 1972 to 1982. 

Totals for later years were found in a presentation by SRS given at an internal dosimetry users group 

meeting in 1992. The presentation included a graph of the annual number of WBCs and a graph of 

the total number of chest counts between 1986 and 1992. These graphs are copied as Figures 3-3 

and 3-4 (McFee 1992). 

For 1974, each HP Division monthly report listed the number of WBCs and the number of chest 

counts (Table 3-2 and Figure 3-4). The data showed that generally the number of chest counts was 

similar to the number of WBCs in the month but several months showed significant differences 

between the two monthly totals. 
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Figure 3-3. WBCs, 1986 to 1992.

Figure 3-4. Chest counts, 1986 to 1992. 
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Table 3-2. WBCs and chest counts, 1974.

Month WBCs Chest counts

Jan 167 143

Feb 146 141

Mar 175 175

Apr 152 167

May 162 181

Jun 126 131

Jul 90 51

Aug 119 20

Sep 172 160

Oct 211 97

Nov 93 17

Dec 143 143

The 1974 reports also listed the numbers of workers who had only WBCs, only chest counts, and both

(Table 3-3 and Figure 3-5). For the entire year, 24% of the workers had only WBCs, 8% had only 

chest counts, and 69% had both. Note that the month of November had 3 chest counts, 46 WBCs, 

and no combined chest and WBCs. Note, too, that in some months, the numbers of WBC and chest 

counts exceed the numbers of workers. This is due to some workers receiving multiple counts during 

the year.

Table 3-3. Workers with only WBCs, only chest 

counts, or both, 1974.

Month WBC only WBC and chest Chest only

Jan 12 138 28

Feb 17 125 7

Mar 22 156 6

Apr 21 121 22

May 24 120 15

Jun 18 98 13

Jul 14 23 11

Aug 68 8 1

Sep 16 93 2

Oct 88 69 4

Nov 46 0 3

Dec 3 68 1

3.4 ROUTINE BIOASSAY SAMPLE FREQUENCY TABLES 

The bioassay frequencies were established in procedure DPSOL 193-302, Bioassay Control, for the 

1960s through 1988 (DuPont 1968a, 1970, 1971a, 1971b, 1976, 1978, 1989a). This procedure was 

replaced on March 9, 1988, by DPSOL 193-211, Bioassay Control (DuPont 1989b, p. 118). 

In 1992, the procedures were revised into a new format and the bioassay frequency table was listed in 

5Q1.1-506, Routine In Vivo and In Vitro Bioassay Scheduling and Administration (WSRC 1992a; 

1995a, p. 9; 1996, p. 117). The bioassay frequency table was removed from the procedure as of 

Revision 10, effective March 2, 1999 (WSRC 1999b, p. 16). 

Although the amount of detail on the frequency and types of Routine Bioassay Sampling Program 

samples varied between procedures, significantly larger portions of each procedure dealt with Special 

Bioassay Sampling Program samples, including specifics on their types and collection methods.
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Figure 3-5. WBCs and chest counts, 1974.

The frequencies for bioassay sampling under the Routine Bioassay Sampling Program were based on 

locations and job descriptions under the DPSOL procedures. In all of the procedures that defined the 

bioassay requirements between 1971 and 1999, the frequencies were based on exposure potential. 

For example, in 1971 the frequency for a plutonium urine bioassay varied between once every 3 years 

for “minimum potential” personnel assigned to nonprocess sections and patrolmen to twice a year 

samples for laboratory personnel and personnel in process sections of selected buildings. In 1992, 

with the introduction of the 5Q1.1 procedures, all personnel were defined into three categories of 

potential risk. Category I personnel were to provide Am/Cm/Cf urine bioassay samples twice yearly 

for Building 773-A, Category II personnel were to provide Am/Cm/Cf urine bioassay samples once a 

year, and Category IIII personnel were not required to provide samples. With the revisions in March 

1999, routine bioassay samples were required annually for all workers who worked in radiologically 

controlled areas (RCAs). 

3.4.1 DPSOL 193-302, Bioassay Control, Revision 5, September 1, 1971

In DPSOL 193-302, the types and frequencies of routine bioassay sampling were shown in table form 

with the urine bioassay analytes shown for specific areas and tasks such as Operators or Reactor 

Department Personnel. The types of samples for urine bioassay listed in DPSOL 193-302, Revision 5 

included tritium, plutonium, neptunium, fission products, EU, uranium, and combined 

americium/curium/californium (Am/Cm/Cf) shown as one type (DuPont 1971b). 

For the chest count frequencies, the table included a column for EU and one column for all of 

plutonium, americium, curium, and californium, as one type. The frequencies were shown in samples 

per year for each type, typically one to four samples per year. The footnotes indicated certain jobs 

that required more frequent samples, such as a requirement for weekly uranium urine samples for 

A-Line operators. 

Routine urine sampling for Am/Cm/Cf was indicated twice a year for analytical chemistry, high-level 

caves (HLC), building services, radiation control, maintenance and other selected personnel in 
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Building 773A, and sample aisle operators in Building 221-F. Sampling for Am/Cm/Cf was indicated 

annually for selected clerical, supervisory, and 100-Area personnel.

The table was under the heading “Routine Bioassay Sampling Frequencies (excluding Construction 

Division).” The routine requirements for the Construction Division personnel were listed in the text 

after the table and indicated a minimum of one sample per year for fission products and one sample 

every 3 years for plutonium with tritium at a frequency to be specified by DPSOP 40-1 or by 

Construction Job Plans and for other radionuclides as specified by Construction Job Plans. 

DPSOP 40-1 was the procedure Radiation and Contamination Control. A 1968 copy of the procedure 

described bioassay only in general terms, stating that urine samples would be routinely analyzed for 

employees in Regulated Zones and Radiation Danger Zones (DuPont 1968b, p. 107). 

A WBC and chest count were required for new Construction Division employees who had previously 

“worked in Radiation Zones at another installation where radioactive materials were handled.” A WBC 

or chest count was required for Construction Division employees whenever there was a confirmed 

uptake of radioactive material or when HP supervision considered it necessary after a contamination 

incident. These were also required for terminating employees with a previous WBC or chest count at 

the site.

The bioassay sampling frequency table from DPSOL 193-302, Revision 5, is provided as Table A1 

(DuPont 1971a). 

3.4.2 DPSOL 193-302, Bioassay Control, Revision 7, October 15, 1976

In Revision 7, the table had been reduced from 17 categories to 9. The types of analyses in the table 

for urine remained the same with the addition of a type “F-

”. Although it is not explained in the text of 

the procedure, this might indicate fluoride. Contemporary bioassay data show fluoride results 

alongside results for radioactive materials. The only entry in the F column is for selected personnel in 

Category C including Buildings 221-HB Line, 221-FB Line, JB-Line, 235-F, 772-F, and 773-A 

(DuPont 1976). 

The footnotes described many of the details of the personnel to be sampled. For example, in both 

instances where the Am/Cm/Cf analysis was required, the indication was footnote “f,” which stated, 

“Selected personnel in 221-F, 211-F, and 773-A sampled for Am-Cm once a year.” This is consistent 

with Revision 5 for 221-F and 773-A but with annual sampling instead of twice yearly sampling for 

773-A. Building 211-F was not listed in the earlier Revision 5.

The table was in the procedure Section 3.1.d, “Routine urine samples and chest count frequencies.” 

The WBC requirements and chest count requirements were not listed separately in the procedure. 

The requirements changed to “in vivo” counts. Rather than the chest counting frequency columns, 

there were two columns for in vivo counts frequencies as annually or every 2 years for most 

categories and once every 3 years for Category A, defined as personnel with minimum potential for 

exposure. This in vivo requirement is applied to more categories and is more frequent than the chest 

count requirement in Revision 5. 

The requirements for the Construction Division precede the table in the procedure. All Construction 

Division personnel were to provide annual routine samples for fission products and samples every 

3 years for plutonium. All Construction Division personnel with a confirmed uptake were to have an in 

vivo count. 

The bioassay sampling frequency table from DPSOL 193-302, Revision 7, is provided as Table A2 

(DuPont 1976).
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3.4.3 DPSOL 193-302T, Bioassay Control, Revision 0, February 25, 1985

DPSOL193-302T, Bioassay Control (DuPont 1985j), stated that it was a duplicate of Revision 8 of 

DPSOL193-302 and was to remain in effect until DPSOL 193-211 was issued. The T indicated 

“temporary.”

In the bioassay frequency table, the categories were replaced with specific areas or buildings with a 

notation for “All assigned personnel”, “Selected personnel”, or personnel specified by job or activity. 

For each area or building, one or more “suggested code” is listed to indicate both the frequency and 

analysis type, such as “A” for three times a year plutonium, “B” for annual plutonium, etc. The areas 

and materials sampled appear to be consistent with DPSOL 193-302, Revision 7. 

Routine annual samples for Am/Cm/Cf are listed for selected Analytical Chemistry Division (ACD), 

Separations Engineering Division (SED), Separations Chemistry Division (SCD), Nuclear Materials 

Division (NMD), HLC, radiation control, building services, and maintenance personnel in 

Building 773-A and selected personnel in Building 221-F. Routine twice-yearly sampling for 

Am/Cm/Cf is listed for selected personnel in Buildings 773-A and 221-F.

Chest and whole-body counting requirements were combined as “in vivo” counting. The frequencies 

for in vivo counts were linked to urinalysis frequencies for plutonium, EU, and Am/Cm/Cf in a table in 

the procedure, In Vivo Counting Frequency, reproduced below as Table 3-4. 

Table 3-4. In vivo counting frequency reproduced from DPSOL 193-302T.a

Urine sampling

nuclide

Urine sampling

samples/year

Shift employees 

counts/year

Day employees 

counts/year

Pu 0.3 0.3 0

Pu 1-2 2 1

Pu 4 2 2

EU 4 2 1

EU 12 2 2

Am/Cm/Cf 1-2 2 1

Am/Cm/Cf 4 2 2

a. Source: DuPont (1985j). 

The above urine and in vivo sampling frequencies (DuPont 1985j, p. 36) are under Section 1, 

Operations, and are followed by Section 2, Construction Division. Routine urine samples for 

Construction Division workers were required annually for “Fission products and/or Induced Activity” 

and every 3 years for plutonium. Tritium was required as indicated in DPSOP 40 and Construction 

Job Plans. All other radioisotopes for routine bioassay samples were specified by HP in Construction 

Job Plans. 

No required frequencies for in vivo counts were listed in the procedure for Construction Division 

personnel.

The bioassay sampling frequency table and a table of codes used in it (Tables A and B from DPSOL 

193-211) are provided as Table A-3.

3.4.4 DPSOL 193-211, Bioassay Control, Revision 0, March 9, 1989

The bioassay frequency table in DPSOL 193-211 maintained a similar design as DPSOL 193-302T 

with the requirements listed by building or area and, except for the Fission Product/Induced Activity 

codes, the table used an identical code list. The table lists the minimum urine sampling frequencies 

suggested for the work assignments listed. The Fission Product/Induced Activity codes were 

removed from both the code list and from the bioassay frequency table. All remaining analyses for 
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plutonium, EU, uranium, Am/Cm/Cf, neptunium, and strontium remained as before and were applied

similarly (DuPont 1989b). 

Under the section Routine Urine Sampling Frequencies was the statement, “Employees who change 

work assignments will have their bioassay frequency codes updated to match the work group they are 

joining.”

Am/Cm/Cf was only listed for Building 773-A. Routine annual samples were required for selected 

ACD, SED, SCD, NMD, HLC, radiation control, building services, and maintenance personnel. 

Routine samples were required twice yearly from selected personnel and had the added notation 

“Maximum potential.”

Routine monitoring for FP and IA radioisotopes was by whole-body counting. Section 2.0, In-Vivo 

Counting, contains a list of minimal detectable activities for the whole-body counting with the heading 

“Fastscan (Fission Products-Induced Activity).” 

For routine in vivo count frequencies, a similar table was included as in the previous 

DPSOL 193-302T for Operations employees “with a potential for uptake of actinides.” The table 

indicated annual in vivo counts for all other operations employees providing plutonium, EU, or 

Am/Cm/Cf samples except those employees who provided routine plutonium samples once every 

3 years. Routine whole-body counting is not required by the procedure, but it does include:

An in-vivo count shall be performed whenever an employee's bioassay sample (except 

tritium) indicates he has a confirmed uptake, or when he has been involved in a 

contamination incident and a count is considered necessary by Health Protection.

Construction Division requirements were also separated in this procedure, and the requirements were 

in greater detail. The procedure stated that all Construction Division personnel were to provide a 

routine annual 1-L urine sample. It added requirements for an annual WBC for Construction Division 

workers with a potential exposure to FP and IA and a sample every 3 years for potential exposure to 

plutonium. Frequencies for tritium and other nuclides were covered by DPSOP 40 and Construction 

Job Plans. 

The bioassay frequency table from DPSOP 193-211 is provided as Table A-4 (DuPont 1989b, p. 122). 

3.4.5 Manual 5Q1.1, Procedure 506, In Vivo and In Vitro Bioassay Scheduling and 

Administration, Revision 0, December 16, 1992

The initial version of the bioassay scheduling procedure in the 5Q1.1 format eliminated separate 

requirements for Construction Division workers (WSRC 1992a). In the Scope section, it stated:

The guidance provided in this procedure applies to all Site personnel including WSRC, 

DOE, BSRI, Construction, WSI, and subcontractor personnel (permanent subcontractors 

such as Forestry, EBASCO, SREL, etc. as well as short-term, or temporary, 

subcontractors) and serves as a reference for Health Protection Department (HPD) 

personnel in prescribing and auditing Site bioassay programs.

This procedure also introduced three categories of employees based on their risk of intake of 

radioactive materials. All requirements in the Minimum Bioassay Schedules for SRS Facilities table 

were listed by category: 
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• The Category I Bioassay Program was applied to personnel with a higher probability of 

intake—those who wore respiratory protection, or who routinely performed hands-on work in 

posted Contamination or Airborne Radioactivity Areas.

• The Category II Bioassay Program was for personnel with a lower probability of intake—those 

who did not routinely wear respiratory protection or work in posted Contamination or Airborne 

Radioactivity Areas, but who regularly entered RCAs where protective clothing was required.

• The Category III Bioassay Program was for those personnel with essentially no risk of intake—

those who were not required to routinely enter RCAs where protective clothing was required, 

and who were not performing tasks requiring work in Contamination or Airborne Radioactivity 

Areas. 

A fourth group, nonradiation workers, were those employees who worked onsite but did not enter 

RCAs. If any nonradiation workers needed to enter RCAs, they were required to have a WBC and to 

follow the site visitor requirements.

The procedure also defined some workers as “Roving Employees,” those whose job assignments 

required them to enter RCAs in different facilities across the site during the course of their regular 

work. The definition included site support personnel and subcontracted construction workers. The 

guidance required each worker to be categorized as I, II, or III, depending on the facilities where the 

majority of their time was spent. It warned against automatically selecting the most conservative 

category because this would “oversample the workforce, produce high bioassay sample processing 

costs, and result in unnecessary delays in analyzing valid sample requests.”

The Routine Bioassay Program Assignment section stated: 

Personnel who wear respiratory protection or who work in posted Contamination or 

Airborne Radioactivity Areas must be sampled for the nuclide to which they are 

potentially exposed, via either the routine sampling program or non-routine, job-specific 

sampling program.

The Minimum Bioassay Schedules for SRS Facilities table lists each facility, then each work area 

within the facility, then the bioassay types and frequencies for Category I, Category II, and (for some 

locations) Category III workers. For those areas where Category III workers are listed, the 

requirements include annual WBCs and for some of those areas, monthly tritium sampling.

Although the codes in the table were changed from those in DPSOL 193-211, the urine bioassay 

types were the same: plutonium, strontium, tritium, uranium, EU, and Am/Cm/Cf.

In this procedure, the routine WBC frequencies and chest count frequencies were listed separately. 

Routine annual chest counts were required for Category I workers assigned to facilities that handle 

actinides. Chest counts were also required for a randomly selected percentage of Category II workers 

at actinide facilities, although the percentage amount is not stated.

The Minimum Bioassay Schedules for SRS Facilities table contains an entry for roving employees 

subdivided by those working in RCAs excluding uranium handling facilities and those working in RCAs 

including uranium handling facilities. For both, Category I workers were required to have annual chest 

counts.

The area names are not identical to the areas in the bioassay frequency table in DPSOL 193-211 but, 

where the areas can be matched together, there were changes in the routine bioassay types. Annual 

strontium sampling was added for 221-F Canyon, 221-F A-Line, and certain areas in Buildings 773-A, 
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772-F, and 241-84H. The 400-Areas, C-Area, K-Area, L-Area, and P-Area no longer required 

plutonium sampling. 

Routine bioassay samples twice a year for Am/Cm/Cf are listed for the Savannah River Technology 

Center (SRTC) Building 773-A Chemistry Technology Section, Analytical Development Section

(ADS), and high-level cave Category I workers and for Buildings 773-A, 776-A Maintenance and 

Electrical and Instrumentation (E&I) Category I workers. Routine bioassay samples annually for 

Am/Cm/Cf are listed for Buildings 773-A, 776-A Maintenance/E&I Category II workers. Building 

776-A, the Liquid Waste Handling Facility (WSRC 1990a, p. 349), is not listed in previous bioassay 

frequency tables.

Table A-5, Minimum Bioassay Schedules for SRS Facilities, from 5Q1.1-506, Revision 0, is provided 

as Table A-5 (WSRC 1992a). 

3.4.6 Manual 5Q1.1, Procedure 506, In Vivo and In Vitro Bioassay Scheduling and 

Administration, Revision 5, April 1, 1996

The differences in the Minimum Bioassay Schedules for SRS Facilities tables between Revisions 0 

and 5 were minor. Some facilities were no longer listed separately, such as the C-, K-, L-, and PAreas, and a new area was added, Building 221-S/512-S (WSRC 1996). Building 221-S is the 

Vitrification Building within the Defense Waste Processing Facility and houses the process equipment 

used to vitrify high-level radioactive waste. Building 512-S is part of the transfer system between the 

tank farm and Building 221-S (WSRC 2015). 

No changes were made in the types of urine bioassay, although some plutonium and tritium 

requirements were reduced in frequency. Two work areas in Building 221-F, the New Special 

Recovery Area and the Plutonium Storage Facility, dropped an annual requirement for a chest count.

This revision listed a new worker group for bioassay purposes. The Category IV Bioassay Program 

was for those workers who infrequently entered Radiological Buffer Areas (RBAs) for administrative or 

oversight purposes. It stated that “Category IV employees are not required to submit any bioassay 

samples nor have in-vivo counts.” There are no entries in the Minimum Bioassay Schedules for SRS 

Facilities table for Category IV workers.

This procedure contained a job-specific sampling section that required bioassay samples for the 

radionuclides of concern for work under RWPs or Standing RWPs that required the use of respiratory 

protection. The requirement was met by either being on a routine bioassay program as indicated on 

the worker’s Radiation Qualification Badge (RQB) or by providing a sample following the work activity.

3.4.7 Manual 5Q1.1, Procedure 506, In Vivo and In Vitro Bioassay Scheduling and 

Administration, Revision 10, March 2, 1999

As a result of the response to the internal FEB audit, the OEI report, and the Notice of Violation issued 

by DOE under 10 CFR Part 820, major changes were made to the site bioassay programs and 

implemented in March 1999, including the method of sample collection and schedule for annual 

samples. Revision 10 of 5Q1.1-506 (WSRC 1999b) included the note:

Effective 3/1/99, a new routine bioassay program was implemented sitewide. This 

program requires workers to bring urine samples to 735-28 when their annual WBC is 

due. To transition into this program and randomize the population of affected workers, 

all WBC expiration dates have been set to the worker's birth month. During this 

transition, the time between WBCs may exceed 12 months (up to 23 months). After this 

transition period, WBCs will resume on an annual basis.
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Categories for workers were removed from the procedure. The selection of workers to participate in 

the routine bioassay program was changed from a description of their likelihood of exposure to those 

workers having Radiological Worker I or Radiological Worker II training. Workers without such

training were not on a routine bioassay program.

Annual WBCs were required for all workers with a Radiological Worker I or II qualification. Routine 

chest counts were required for workers who worked in SRTC, FB-Line, HB-Line, 772-F, or 772-IF and 

wore respiratory protection.

All routine urine bioassay samples with the exception of tritium were to be collected annually in 

conjunction with the WBC. Tritium samples were to be collected every 30 days. During the year, 

workers who entered areas under a RWP that required bioassay types not indicated on their RQB 

would have their badges punched to indicate the analysis needed. The badge was presented with the 

sample and a new badge issued showing the expiration date of the WBC and, as applicable, the chest 

count.

The bioassay frequencies table was no longer included in 5Q1.1-506. Radiological Workers I and II 

were to provide bioassay samples during the year as specified on the RWPs they worked under with 

the types tracked by the holes punched into their RQBs, which were turned in with their annual 

samples. 

3.4.8 Specification of Urine Bioassay Requirements on Radiological Work Permits

The sitewide characterization effort in 1999 resulted in the memorandum, “Specification of Urine 

Bioassay Requirements on Radiological Work Permits” (Farrell and Findley 1999). It listed default 

bioassay requirements by each of the eight operational areas: 

• Nuclear Materials Stabilization and Storage Division, 

• High Level Waste Management Division, 

• Solid Waste Division, 

• Spent Fuels Storage Division, 

• Facilities Decommissioning Division, 

• Defense Programs Division, 

• Savannah River Technology Center, and 

• Central Laboratory Facility (CLAB). 

These requirements were taken from characterization reports prepared by each division. It 

summarized each radioisotope that contributed 10% or more of the internal dose through inhalation 

for each location or waste stream. For the CLAB, 10 waste streams were defined, each with its own 

specified radionuclides defined by the origin of the wastes from Building 772-F or 772-1F laboratory 

modules. 

The list of radionuclides in the procedure for urine bioassay sample analysis was:

• Pu, plutonium (238Pu and 239Pu), 

• U, uranium (234U, 235U, and 238U), 

• Np, neptunium (237Np), 

• Am, americium/curium/californium (241Am, 244Cm, 252Cf), 

• Sr, strontium (S-90), and

• H, hydrogen (H-3). 
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The list had a note below saying “The Am bioassay sampling program also provides analysis for 

Curium and Californium.”

With the exception of tritium and uranium, routine urine bioassay for the listed radionuclides was to be 

specified for work under all RWPs where respiratory protection was required. For uranium, routine 

urine bioassay sampling was to be specified on RWPs when uranium contamination was present in 

M-Area and H-Area and for other locations when RWPs required respiratory protection. Routine urine 

bioassays for tritium were required for K-, L-, C-, P-, R-, and M-Areas, the Receiving Basin for Offsite 

Fuel (RBOF), CLAB Waste Stream J for work under RWPs in High Contamination Areas or Airborne 

Contamination Areas established due to the presence of tritium. 

A table summarizing the locations, the radioisotopes that contribute more than 10% of the internal 

dose, and their relative dose fractions from Farrell and Findley (1999) is provided as Table A-7. 

A comparison of the source terms data in Farrell and Findley (1999) and the bioassay frequency table 

from 5Q1.1-506 is provided in Table A-8. This table selects all locations and waste streams from 

Farrell and Findley (1999) and their radioisotopes that contribute 10% or more of the dose along with 

comparable locations from the 1996 procedure 5Q1.1-506, Revision 5, and the recommended 

analyses.

Two locations in Farrell and Findley (1999) indicate Am/Cm/Cf only and no other radioisotopes: 

F-Wing Boot Waste Stream and Californium Waste Stream (773-A F-Wing californium facilities). Both 

are from 773-A, which had previously recommended routine bioassay samples for Am/Cm/Cf, 

strontium, and plutonium. 

Six locations have Am/Cm/Cf bioassay sample requirements that did not have them in the matched 

areas in 5Q1.1-506, Revision 5: 

1. Multi-Purpose Processing Facility (MPPF), 

2. Building 221-H/Outside Facilities, 

3. F- & H-Area Tanks, 

4. RBOF, K- and L-Areas, 

5. C-, P-, and R- Areas, and

6. Casks Waste Stream [high-level waste (HLW) sludge]. 

These six locations also listed plutonium as a bioassay requirement and had listed plutonium 

previously. The relative dose contribution from 241Am at the MPPF was 99%. At the 221-H/Outside 

facilities, 8% was from 241Am with 12% from 244Cm. The remaining locations did not have the relative 

dose contributions provided in Farrell and Findley (1999). 

With the exception of the MPPF (processed americium), the Californium Waste Stream (from the 

former californium processing facilities in Building 773-A), and the F-Wing Waste Stream (from the air 

handling system in the F-Wing of 773-A), for the majority of locations the 241Am was present as a 

decay product of 241Pu. The activity of the americium was a calculable fraction of the plutonium 

activity based on the age of the material since separation. If the time since separation is not known, 

ratios can be estimated based on the age of the plutonium.

In each of the above locations showing americium as a new routine bioassay requirement, plutonium 

was listed in this report and previously listed in the bioassay frequency tables as a routine bioassay 

requirement.

Four CLAB Streams listed Am/Cm/Cf, which was not recommended for Buildings 772-F or for 772-1F 

locations previously: 
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1. CLAB Waste Stream E (Building 772-F laboratory modules L131, L138, L139, L146, L147, 

L154, L155, and L171), 

2. CLAB Waste Stream G (772-F/772-4F filter room), 

3. CLAB Waste Stream H (Building 772-F laboratory modules L142, L143, L146, L147, L174, 

L175, and L183), and

4. CLAB Waste Stream J [Building 772-F laboratory modules waste disposed of in the 772-F 

liquid scintillation counting (LSC) drum]. 

Each of these waste streams also listed plutonium. Plutonium was a recommended routine bioassay 

sample for both 772-F and 772-1F previously. The relative dose contributions from 241Am for these 

four waste streams range from 67% to 89%.

Note that Building 773-A was the Main Technical Laboratory Building and Building 772-F was the 

CLAB. These laboratories received samples from various processes and wastes across the site. The 

samples varied greatly in concentrations and relative activity ratios. 

Other differences between the required radioisotopes in Farrell and Findley (1999) and those 

recommended in 5Q1.1-506, Revision 5, were the addition of tritium for RBOF, K- and L-Areas, the 

addition of strontium and plutonium for RBOF, K- and L-Areas, and the addition of tritium for CLAB 

Waste Stream I and CLAB Waste Stream J.

4.0 AMERICIUM, CURIUM, AND CALIFORNIUM SOURCE TERMS FROM BIOASSAY 

FREQUENCY TABLES 

The radioisotopes listed in the bioassay frequency tables show the expected dominant radioisotopes 

for SRS facilities in relation to internal dose. The bioassay frequency tables do not provide 

information about volumes, forms of the material, accessibility by workers, or time frames narrower 

than the procedure revisions. 

With the sitewide characterization effort in 1999, the application of the Am/Cm/Cf routine bioassay 

sample in 10 new areas was the largest source term change identified, although it was added in two 

cases not as the dominant radioisotope but due to the new rule requiring the inclusion of all 

radionuclides that provide 10% or more of the internal dose. One location, the MPPF, was listed for 

the first time as a distinct location from the building that housed it, Building 221-F. 

4.1 URINE BIOASSAY

The single Am/Cm/Cf bioassay analysis was used to measure 241Am, 244Cm, and 252Cf. A source with 

any one of those isotopes or with any combination of those isotopes would be measured by 

Am/Cm/Cf urine bioassay sampling. 

Only one location in Farrell and Findley (1999) was shown to have 252Cf contribute more than 10% of 

the dose, and that was the Californium Waste Stream in 773-A. Building 773-A has listed Am/Cm/Cf 

bioassay in the bioassay frequency tables consistently since 1971.

Between 1971 and 1999, the locations for recommended Am/Cm/Cf for routine bioassays and for use 

on RWPs are shown in Table 4-1. With the sitewide characterization in 1999, 10 new locations and 

waste streams were added outside of Building 773-A for routine Am/Cm/Cf bioassays. The 

10 locations are listed in Table 4-1 as “1999–not 773-A.” The report included the relative dose 

contributions from the selected radionuclides for 7 of the 10 locations. 
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Table 4-1. Areas with recommended routine Am/Cm/Cf bioassay sampling.a

Year Buildings

1971 773-A, 221-F

1976 773-A, 221-F, 211-F

1985 773-A, 221-F

1989 773-A

1992 773-A, 776-A

1996 773-A, 776-A

1999–773-A 776-D Waste Stream (773-A 776-5A), B-Process Waste Stream (773-A), F-Wing Boot Waste 

Stream, ADS-1 Waste Stream (Analytical Development System Laboratories), Non-Canyon 

Waste Stream (773-A non-CHTS, ADS laboratories), Californium Waste Stream (773-A F 

Wing Cf facilities)

1999–not 

773-A 

MPPF, 221-H/Outside Facilities, F- & H-Area Tanks, RBOF, K- and L-Areas, C-, P-, and RAreas, Casks Waste Stream (HLW sludge), CLAB Waste Stream E, CLAB Waste Stream G , 

CLAB Waste Stream H, and CLAB Waste Stream J

a. ADS = Analytical Development Section; CHTS = Chemical and Hydrogen Technology Section.

The B-Process Waste Stream (773-A), and F-Wing Boot Waste Stream are compared to 

Building 773-A, which has previously shown Am/Cm/Cf requirements. 

The MPPF was not listed separately in previous bioassay frequency tables. The MPPF is wholly 

within Building 221-F, for which the tables indicated routine Am/Cm/Cf bioassays for selected 

personnel up to March 1989 when DPSOL 193-211 came into effect. No routine urine bioassay 

requirement for Am/Cm/Cf was listed for Building 221-F or the MPPF from 1989 until the source term 

analysis report in 1999. Note, however, that routine plutonium urine samples were listed for select

personnel in Building 221-F in each of the bioassay frequency tables between 1971 and 1999, and 

annual chest counts were required for personnel in 221-F as described below. A further description of 

MPPF bioassay is provided in Section 5.4. 

Data collected for ORAUT-OTIB-0081, Internal Coworker Dosimetry Data for the Savannah River Site

(ORAUT 2016), for the years between 1966 and 1987 include routine urine Am/Cm/Cf results. That 

data can be found in DuPont (1956–1961, 1961–1969, 1963–1970, 1968–1972, 1969, 1969–1973, 

1970–1973, 1973–1978, 1973–1979, 1978–1983, 1979–1980, 1980–1981a, 1980–1981b, 1981–

1986, 1986–1989). A total of 10,469 routine urine sample results for Am/Cm/Cf from the coworker 

study were reviewed and 598 of those or 6% were for Area F.

SRS calculated committed effective dose equivalent and maintained a database for those workers 

who received a dose greater than 10 mrem (WSRC 2008, p. 97; ORAUT 2004, 2017b). Figure 5-1 

lists all Am/Cm/Cf doses and the number of workers who were confirmed to have received an 

exposure greater than 10 mrem for the years 1960 through 2005.

The RBOF and the K- and L-Reactor areas under the Spent Fuel Storage Division listed americium 

with the 1999 characterization. The K and L process water and disassembly basin water waste 

streams were isotopically analyzed along with the RBOF and found to be similar in composition. 

Americium was present as a plutonium decay product due to the age of the stored fuel. The 

requirement for routine plutonium and Am/Cm/Cf urine bioassays was applied for those areas when 

respirators were required due to the presence of particulate materials, such as for disassembly basin 

workers. 

4.2 CHEST COUNTS

Americium exposures, along with curium, californium, and plutonium, were also monitored through 

chest counts. Table 4-2 summarizes the locations and worker categories with annual or more 

frequent chest count requirements in the Bioassay Control procedures. There were separate 
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bioassay requirements in the procedures for operations and construction personnel until the 1992 

version of 5Q1.1, Procedure 506, Routine In Vivo and In Vitro Scheduling and Administration (WSRC 

1992a). After 1992, the procedures explicitly state that the requirements apply to all personnel. 

Table 4-2. Summary of annual chest count requirements from the bioassay control procedures and 

tables. 

Year Operations workers Construction workers

1971 Workers in specified jobs in 221-H, 221-F, 772-F, 221-H BLine, 221-F B-Line, JB-Line, 235-F, 773-A After event or confirmed uptake 

(special bioassay) or when 

terminating if worker had previous 

WBC or chest count

1976 Workers in specified jobs in 221-FH, 241-FH, 211-FH, 723-F, 

A-Line, 643-G, 244-H, 772-F, 235-F, 200-FH, 773-A, 100

Areas, 221-HB Line, 221-FB Line, JB-Line, 235-F, 322-M,

772-F, 773-A, 321-M, and certain Reactor Department

personnel

After confirmed uptake (special 

bioassay) or when terminating if 

worker had worked in areas where 

radioactive materials were present

1985 All workers with annual routine Pu, EU, or Am/Cm/Cf urine 

bioassay requirements

No requirement listed

1989 All workers with annual routine Pu, EU, or Am/Cm/Cf urine 

bioassay requirements

“As specified by area Health 

Protection in Construction Job 

Plan.”

1992 Category I workers and random Category II workers assigned 

to facilities with actinides; all Category I Roving Employees

Same requirements for all workers

1996 Category I workers and random Category II workers assigned 

to facilities with actinides; all Category I Roving Employees

Same requirements for all workers

1999 Workers who wear respirators in SRTC, FB Line, HB Line, 

772-F or 772-1F

Same requirements for all workers

In the 1999 characterization, the MPPF waste stream was listed with 241Am providing 99% of the dose 

fraction. The MPPF was not listed separately in previous bioassay frequency tables and is wholly 

within Building 221-F, for which the tables indicated annual chest counts during this entire period. 

Note that plutonium urine bioassay was listed for Building 221-F, and chest counts that were initiated 

by positive plutonium urine bioassay would distinguish and quantify any 241Am uptakes.

5.0 DOSE RECONSTRUCTION CONSIDERATIONS

Routine bioassay sampling provides greater confidence in the controls and monitoring programs in 

place, but it was not the basis for assignment of dose at SRS nor is it the only source of dose 

information available for dose reconstruction. The Routine Bioassay Sampling Program was used to 

monitor the controls in place. The Special Bioassay Sampling Program was used to evaluate and 

assign worker internal exposure for any suspected uptakes of radionuclides. Information from SRS 

for claimants includes all bioassay results from both sampling programs. 

The sitewide characterization in 1999 identified three places where americium was present and 

plutonium contributed less than 10% of the dose. All had routine monitoring requirements between 

1971 and 1999 that would have identified uptakes of americium. The B-Process Waste Stream in 

773-A, and the F-Wing Boot Waste Stream had listed requirements for Am/Cm/Cf urine bioassay and

annual chest counts. Building 221-F had requirements for Am/Cm/Cf urine bioassay until 1989 and

had requirements for annual chest counts through 1999.

5.1 AIR SAMPLING

SRS used radioactivity concentration guides (RCGs) in the 1970s to determine when respiratory 

protection was required. The Guide for americium was 6 × 10-12 μCi/cm3. For plutonium, it was 
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2 × 1012 μCi/cm3, and for unidentified alpha activity it was 2 × 10-12 μCi/cm3. All other Guides in use 

were equal to or lower than americium (DuPont 1974). 

By the 1990s, the site used one-tenth of the derived air concentrations (DACs) as the threshold for 

determining an airborne radioactivity area. One-tenth of the DAC for americium was 2 × 10-13

μCi/cm3, for plutonium, it was 2 × 10-13 μCi/cm3, and for unidentified alpha, it was 2 × 1013 μCi/cm3. All 

other DACs in use were equal to or lower than americium (WSRC 1990b). 

Because 241Am is a decay product of 241Pu, both were generally found in the same source term with 

the ratio of americium to plutonium a function of the age of the material. For both RCGs and DACs, 

plutonium was the controlling and limiting radionuclide.

Any indication of failure of the controls such as a break in containment, skin contamination, or high air 

sample readings would lead to the Special Bioassay Sampling Program with followup bioassay 

sampling based on the isotopes found to be present, identified by methods including isotopic analysis 

of the air samples.

5.2 CHEST COUNTS

Routine chest counts were used to monitor exposures to Am/Cm/Cf providing additional data beyond 

the routine urine bioassay samples. These routine chest counts were required from a greater 

population than that working in the areas listed for Am/Cm/Cf in the bioassay frequency tables. Chest 

count data are routinely included in claimant exposure records from SRS. Totals are listed in 

Section 3.3.3 above.

A review of a dataset created for dose reconstruction and used as source data for the SRS coworker 

study found 1,039 records showing 241Am results obtained by chest counts for 469 individual workers. 

These were from a population of 28,000 total records for 4,920 individuals. Of these, 365 were 

associated with Building 221-F. The dataset was created from claimant records provided by SRS. 

The 469 individual workers included both construction and non-construction workers, as indicated by 

their job titles. Two examples of combined WBC and chest count reports are provided in 

Attachment B, one from 1983 for a laboratory technician (SRS 1995) and one from 1998 for a 

construction laborer (SRS 1975–2018). 

5.3 ROUTINE URINE BIOASSAY

A series of annual reports titled Savannah River Plant History Plantwide Activities contained annual 

totals of urine samples received by the Bioassay Laboratory between 1972 and 1987 (DuPont 1983c, 

p. 282; 1987; 1988). Totals were provided for several analytes including Am/Cm/Cf. The 1990 Health 

Protection Annual Report listed the number of samples processed through the Bioassay Laboratory

for the years 1982 through 1990 (WSRC 1992b). 

A review of the Health Protection Radiation Exposure Database (HPRED) provided annual totals of 

urine bioassay samples and Am/Cm/Cf samples between 1991 and 2005. 

The HPRED database also included indicators for routine and special samples. For americium, 91% 

of the samples were flagged as routine and 9% were flagged as special. Samples flagged as 

baseline, termination, and routine followup were included in the routine totals.

The data for the SRS coworker study agrees closely with the totals for the years 1972 to 1988. 

Annual totals from the Savannah River Plant History Plantwide Activities reports, the HPRED 

database, and the SRS coworker study are shown in Table 5-1. Figure 5-1 shows the overall trend in 

americium samples from 1971 through 2005.
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Table 5-1. Annual totals for urine bioassay 

samples, 1972 to 2005. 

Year Am/Cm/Cf Routine Special

1968 480 NA NA

1969 1,194 NA NA

1970 2,730 NA NA

1971 2,016 NA NA

1972 1,820 NA NA

1973 1,332 NA NA

1974 1,274 NA NA

1975 891 NA NA

1976 761 NA NA

1977 593 NA NA

1978 446 NA NA

1979 664 NA NA

1980 387 NA NA

1981 344 NA NA

1982 375 NA NA

1983 324 NA NA

1984 334 NA NA

1985 244 NA NA

1986 540 NA NA

1987 420 NA NA

1988 389 NA NA

1989 489 NA NA

1990 888 NA NA

1991 833 720 113

1992 617 568 49

1993 318 230 88

1994 301 249 52

1995 390 313 77

1996 412 269 143

1997 689 476 213

1998 1,200 664 536

1999 1,827 1,601 226

2000 2,441 2,296 145

2001 2,622 2,449 173

2002 2,612 2,535 77

2003 2,798 2,760 38

2004 2,532 2,484 48

2005 2,350 2,311 39

The data collected for the SRS coworker study include in most cases the area associated with the 

sample. For the routine urine Americium results, 36% listed the area as “773”, 8% were for area “A”, 

and 6% were for area “F”. Over a third, 39%, listed the area as “none”.

5.4 ROUTINE BIOASSAY NOT REQUIRED IN BIOASSAY PROCEDURES 

Although the MPPF was not listed in the bioassay procedures before 1999 and Building 221-F did not 

have a requirement for Am/Cm/Cf bioassay samples between 1989 and 1999, routine urine bioassay 

sampling for americium was required on job-specific RWPs during that time.

The MPPF was inactive for much of the 1990s. In 1995, DOE made a commitment to process an

inventory of americium and curium solution stored in F-Canyon using vitrification. SRS planned a 

demonstration project for the vitrification program that included operations in the MPPF (WSRC 
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Figure 5-1. Americium samples, 1972 to 2005 combined with data from the SRS Intake Database 

(ORAUT 2004, 2017b). 

1995b, p. 24). “Modification to the MPPF required to support this project include dismantling and 

removal (D&R) of existing equipment to provide space for new systems/equipment” (WSRC 1997, 

p. 6). The processing and vitrification of the americium/curium solution for this demonstration project 

did not occur in the 1990s and was scheduled to happen in 2004 and 2005 (DOE 2000, p. 73). 

Eight RWPs and their sign-in sheets were located that covered work in the MPPF in 1996 and 1998. 

Three also included Post-Job As Low As is Reasonably Achievable (ALARA) Review forms (WSRC 

1996–1998). These RWPs and their dates, job descriptions, and protective measures are listed in 

Table 5-2. A total of 34 workers signed in to one or more of these RWPs.

The box for “Job-Specific RWP” was checked on each RWP and only plutonium, strontium, and 

americium were checked under the Job Specific Bioassay Requirements. Additional requirements 

were written on the RWP under Special Precautions, including in each a requirement that “Workplace 

air sampling will be conducted.” The RWPs listed one or more tasks to accomplish the job and listed 

protective clothing and respirator requirements for each task. 

The sign-in sheets associated with the RWPs included the worker’s printed name, signature, social 

security number, date and time of entry, and the date and time of exit. Some of the later RWPs used 

only the last four digits of the social security number. 
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Table 5-2. MPPF RWPs (WSRC 1996–1998). 

RWP 

number Issue date Job description

Jobspecific 

bioassay

Respirator 

requirement

Workplace 

air 

sampling?

Number 

of 

workers

Earliest 

sign-in 

date

Latest 

sign-in 

date

96-FC-200 

Rev 0

06/04/1996 Construction to D&R Transite

ceiling panels in MPPF first 

level

Pu, Sr, 

Am

Full face or none 

based on task

Yes 6 06/10/1996 04/06/1998

96-FC-202 

Rev 0

07/10/1996 Install oil filled shielding 

window in Cell #8 in MPPF

Pu, Sr, 

Am

Full face or none 

based on task

Yes 7 07/15/1996 07/15/1996

96-FC-202 

Rev 1

09/04/1996 Prepare window frame to 

install new window

Pu, Sr, 

Am

Fresh air hood or 

none based on task

Yes 7 09/05/1996 10/08/1996

96-FC-202 

Rev 2

09/24/1996 Prepare window frame to 

install new window

Pu, Sr, 

Am

Fresh air hood or 

none based on task

Yes 9 06/11/1996 10/09/1996

98-FC-103 

Rev 0

01/06/1998 Remove manipulators in 

MPPF 1st level and transport 

to SRTC for decontamination 

and repair. Reinstall 

manipulators after repairs are 

complete.

Pu, Sr, 

Am

Plastic suita, full 

face, fresh air hood, 

or none based on 

task

Yes 7 01/07/1998 01/27/1998

98-FC-103 

Rev 1

01/20/1998 Remove manipulators in 

MPPF 1st level and transport 

to SRTC for decontamination 

and repair. Reinstall 

manipulators after repairs are 

complete.

Pu, Sr, 

Am

Full face, fresh air 

hood, or none 

based on task and 

area

Yes 9 01/07/1998 04/01/1998

98-FC-103 

Rev 2

04/08/1998 Remove manipulators in 

MPPF 1st level and transport 

to SRTC for decontamination 

and repair. Reinstall 

manipulators after repairs are 

complete.

Pu, Sr, 

Am

Full face, fresh air 

hood, or none 

based on task and 

area

Yes 6 03/16/1998 05/18/1998

98-FC-115 

Rev 0

01/26/1998 Decontamination hut and open 

dampers in MPPF Lab on 2nd 

level

Pu, Sr, 

Am

Plastic suit, fresh air 

hood, or none 

based on task

Yes 5 01/27/1998 01/27/1998

a. A fully encapsulating suit with supplied air (DuPont 1968b, p. 66).
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The HPAREA bioassay sample database was used to find each worker’s next americium, plutonium, 

or strontium urine bioassay sample after their latest sign-in date for any of the RWPs. Their sign-in 

dates and subsequent bioassay dates are listed in Table 5-3. All 34 workers had strontium analyses 

and plutonium analyses within 1.3 years of the date. 

Table 5-3. Workers signed in to one or more MPPF RWPs (WSRC 1996–1998). 

Worker

Earliest sign-in 

date

Latest sign-in 

date

Americium 

sample

Plutonium 

sample

Strontium 

sample

1 06/10/1996 06/10/1996 06/17/1996 12/11/1996 06/11/1997

2 06/10/1996 06/11/1996 11/21/2000 10/07/1996 10/07/1996

3 06/10/1996 06/13/1996 07/10/1996 10/07/1996 10/07/1996

4 06/10/1996 01/07/1998 02/18/1998 03/18/1998 03/18/1998

5 06/12/1996 06/13/1996 12/22/1999 06/27/1996 12/10/1996

6 06/13/1996 09/17/1996 None 12/15/1997 12/15/1997

7 07/15/1996 07/15/1996 04/07/1998 08/03/1996 08/03/1996

8 07/15/1996 07/15/1996 10/14/1996 03/05/1997 03/05/1997

9 07/15/1996 07/15/1996 07/12/1999 07/16/1996 07/16/1996

10 07/15/1996 07/15/1996 04/05/1998 12/07/1996 12/07/1996

11 07/15/1996 01/20/1998 01/21/1998 03/18/1998 03/18/1998

12 07/15/1996 05/18/1998 09/02/1998 09/02/1998 09/02/1998

13 07/15/1996 05/18/1998 08/04/1998 08/04/1998 02/08/1999

14 09/05/1996 09/11/1996 10/02/1996 10/02/1996 10/02/1996

15 09/05/1996 09/17/1996 None 10/15/1996 10/15/1996

16 09/05/1996 09/17/1996 03/14/2000 03/03/1997 03/03/1997

17 09/16/1996 09/26/1996 None 08/21/1997 08/21/1997

18 09/17/1996 03/16/1998 04/07/1998 04/07/1998 10/09/1998

19 09/25/1996 09/25/1996 12/03/1998 1/201/1997 06/08/1997

20 09/25/1996 09/26/1996 None 03/18/1997 03/18/1997

21 09/25/1996 10/08/1996 None 12/18/1996 12/18/1996

22 09/25/1996 10/08/1996 05/02/2000 11/11/1996 11/11/1996

23 10/09/1996 10/09/1996 02/10/1999 02/11/1997 08/14/1997

24 01/07/1998 01/07/1998 03/26/1998 02/13/1998 03/26/1998

25 01/07/1998 05/18/1998 09/29/1998 09/29/1998 04/22/1999

26 01/15/1998 01/15/1998 09/21/1999 03/03/1998 09/05/1998

27 01/27/1998 01/27/1998 04/02/1998 05/26/1998 05/26/1998

28 01/27/1998 04/01/1998 07/07/1998 07/28/1998 07/28/1998

29 01/27/1998 04/01/1998 04/04/1998 09/09/1998 04/05/1999

30 03/16/1998 03/16/1998 04/07/1998 08/01/1998 02/05/1999

31 04/01/1998 04/01/1998 04/03/1998 08/21/1998 08/21/1998

32 04/06/1998 04/06/1998 09/04/1998 07/21/1998 07/21/1998

33 04/06/1998 04/06/1998 11/04/1998 06/10/1998 06/10/1998

34 04/06/1998 04/06/1998 02/29/2000 08/05/1998 02/15/1999

Twenty-nine workers had americium analyses within 4.5 years of their latest sign-in date. Five

workers did not have americium bioassay samples after their last sign-in date. Termination dates in 

HPAREA show that 3 of the 5 left SRS less than one year after their last sign-in date for these RWPs.

These 5 workers without the follow-on americium analyses signed into 5 RWPs on 10 different dates. 

The sign-in sheets were reviewed to find all other workers who signed in for the same RWP on the 

same day. For each of these 5 workers in all cases, one or more other workers signed into the same 

RWP on the same date who also later had an americium bioassay analyses.

Five of the 34 workers were found in NOCTS and an additional 5 were found in comprehensive 

exposure records in the SRDB (SRS 1975–2018). Of these, 6 had lung counts after their last sign-in 

date. Table 5-4 lists these workers and the lung count dates. 
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Table 5-4. Lung count dates for MPPF workers with data in NOCTS or SRDB (SRS 1975–2018). 

Worker

Earliest sign-in 

date

Latest sign-in 

date In NOCTS In SRDB Lung count

1 06/10/1996 06/10/1996 No Yes None

2 06/10/1996 06/11/1996 No Yes 11/04/1997

5 06/12/1996 06/13/1996 No Yes 12/15/1997

6 06/13/1996 09/17/1996 Yes No None

10 07/15/1996 07/15/1996 Yes No 12/29/2005

12 07/15/1996 05/18/1998 Yes No 08/11/1999

16 09/05/1996 09/17/1996 Yes No 03/17/2009

15 09/05/1996 09/17/1996 No Yes None

23 10/09/1996 10/09/1996 No Yes None

30 03/16/1998 03/16/1998 Yes No 02/01/2006

There was no indication found in the available exposure data for the workers or in the paperwork with 

the RWPs that any internal exposures occurred. The three Post-Job ALARA forms each indicated no 

exposure events had occurred and estimated a total of “0.00 man-rem” for the job. 

6.0 CONCLUSIONS

The required types and locations for routine bioassay sample analyses remained largely constant 

between 1971 and 1999 with a few areas adding and dropping analytes in procedure revisions. The 

definitions of workers to be routinely sampled varied in almost each procedure revision but focused 

on workers most likely to be in contact with radioactive materials. 

Routine bioassay samples were used at SRS only to monitor other work controls and were not used 

to assess dose. The Special Bioassay Sampling Program was used whenever internal exposure 

was suspected and provided results for dose assessment. In 1999, the sitewide characterization 

effort identified all radioisotopes that contributed 10% or greater to internal exposure for each 

location or waste stream. Analyses for these radioisotopes were to be included on RWPs. These 

were also required analytes for routine bioassay samples from workers doing work under any RWPs 

when working with actinides whenever respiratory protection was required. 

The bioassay procedures and RWP requirements were for routine bioassay sampling. Workers were 

also monitored by personnel contamination surveys and by air sampling programs. Any indication of 

internal exposures from this monitoring or from any positive results obtained in the Routine Bioassay 

Sampling Program led to further sampling under the Special Bioassay Program, which was used to 

assign dose. Results from the routine program were not used to assign dose; instead they were 

used to monitor work conditions. 

Sufficient accuracy is achieved in dose reconstructions when the available information allows a 

maximum estimate of worker exposure. Worker exposure records from SRS, including routine 

bioassay sample results, special bioassay sample results, chest count results, and WBC results, 

provide that information. 

6.1 RESPONSE TO SC&A COMMENTS 

SC&A asked questions about the conditions at SRS before 1999 and described the facility source 

terms at SRS before 1999 as “inadequate”. The term “inadequate” is their professional judgment. A 

different interpretation is that the changes in the routine bioassay program after the characterization 

effort were continuous improvements in worker monitoring. 

SC&A referenced “Field Protocols for Determining Radionuclides of Interest in a Facility 

Radiobioassay Program” and found it to be a “lessons learned” of experience gained with the WSRC 
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source term characterization program originally implemented 6 years earlier in 1999. In this 

reference, WSRC quotes the site policy for routine and special bioassays (Hadlock et al. 2005): 

A routine bioassay program is designed to detect (previously unknown) intakes of 

radionuclides that a person has a “reasonable potential” to assimilate. This is in contrast 

to a special bioassay program, which is designed to assess intakes of specific 

radionuclides to which a person has been exposed. The key point here is that:

• A special bioassay program is initiated in response to a real, measurable source 

term, e.g., the material that is on an air filter paper. 

• A routine bioassay program is initiated in response to a “hypothetical” source 

term, e.g., a particular mix of radionuclides that might typically be expected to be 

present on any given day at a particular location.

• The specification of the source term for a routine bioassay program is largely a 

professional judgment because we are trying to predict the mixture of 

radionuclides that a person might be exposed to at some undetermined time in 

the future and there is a limited amount of information available to make the 

prediction.

• Great care must be taken to match a special bioassay program to the source 

term because the bioassay program is being used to demonstrate compliance 

with the federal rule 10 CFR Part 835.

• An occasional mismatch between the routine bioassay program and the source 

term is to be expected and is not an indication of an inadequate bioassay 

program. 

This policy from 2005 is consistent with the SRS distinction between routine bioassay sampling and 

special bioassay sampling before 1999 and with the changes implemented in 1999. It clearly 

separates the adequacy of a source term for samples under the Routine Bioassay Sampling Program 

used to monitor workers not known to be exposed from the adequacy of a source term for assessing 

dose to workers with suspected internal exposure under the Special Bioassay Sampling Program. 

6.1.1 Americium and Curium

The two radioisotopes mentioned in the SC&A memorandum are 241Am and 244Cm. The changes in 

the use of the Am/Cm/Cf bioassay sample requirement and the result of the 1999 characterization 

effort are discussed above in Section 4.0.

Central to the issue of 241Am at SRS is the fact that it is a decay product of 241Pu with a half-life of 

approximately 432 years. Freshly separated plutonium has little americium, but it continues to 

increase in relative activity as the plutonium ages. The ratio of 241Am activity to the total alpha activity 

in a 6% reference plutonium mix goes from 0.1% after 2 weeks to 6.5% after 5 years (DOE 2006, 

p. 123). 

A quote from the former internal dosimetry employee in the SC&A memorandum touches on this

(SC&A 2018): “I think that when SRS moved from the production phase to the decontamination and 

decommissioning (D&D) phase in the 1990s there were changes in the source terms that were not 

fully anticipated because of the change in mission.” This was a change from working with freshly 

separated production materials to older waste materials with increased amounts of americium. 
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As an incidental benefit, this buildup of americium can make the mixture “somewhat easier to detect 

by in vivo methods” (DOE 2006, p. 121). Chest counts at SRS to monitor plutonium exposures would 

also have identified associated americium exposures.

The MPPF RWPs illustrate a case where americium existed without any associated plutonium. 

Potential exposures in 1996 and 1998 would have resulted from existing MPPF contamination. This 

contamination was just as it was characterized later in 1999 and reported in Farrell and Findley 

(1999); there was no new production during this period. Although all workers had Sr and Pu 

bioassays, if any internal exposure had occurred, the dose would have been due primarily to 241Am. 

Exposure to 241Am would have been assessed by workplace air sampling, through lung counts, and 

through 241Am bioassay analyses.

All were monitored directly or indirectly for internal exposure to 241Am: 

• Air sampling was required on each RWP. 

• Some, although not all, workers had subsequent lung counts.

• All 34 workers either had 241Am analyses or worked under the same RWP on the same day as 

another worker with subsequent 241Am analyses.

6.1.2 References Quoted by SC&A

SC&A (2018) provides five references from the SRDB: 

1. “Understanding Urine Bioassay Sampling,” Revision 3, November 7, 1997 (Findley 1997b).

This reference states that in 1997 SRS had identified the issue that some RWP bioassay 

requirements were written to meet the bioassay frequency tables rather than being based on 

the identification of the radioisotopes actually present. It states that SRS removed the linkage 

between the RWP procedure 5Q1.1-504, Radiological Work Permit, and the bioassay 

frequency table in 5Q1.1-506, In Vivo and In Vitro Bioassay Scheduling and Administration.

2. “Specification of Bioassay Requirements on Radiological Work Permits,” August 13, 1998

(Findley 1998).

This reference is a memorandum describing the status, in 1998, after the internal FEB audit 

and during the pilot program for the Burial Ground. Further details on this are described above 

in Section 2.0.

3. “Missed Dose from Curium Intakes by Solid Waste Workers,” August 25, 1998 (LaBone 1998).

SC&A wrote, “The author seems to be suggesting that there is no need to be concerned about 

missing radionuclides for bioassay purposes because any such routine monitoring is not 

required for dose assessment under 10 CFR Part 835 regulations, in any case. This position 

seems to be at odds with other WSRC documentation and will need further follow-up.”

Research for this report indicates that WSRC was consistent in its use of the bioassay 

sampling program; routine bioassay samples were collected to confirm the adequacy of the 

overall worker protection program. The argument being made in this reference is that there 

was no indication of exposures to the workers. It includes the statement, “This could be a

valid concern for a special urine sample, but for the reasons given below, is not a concern for 

a routine urine sample.”
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Investigation of the curium found at the Burial Ground indicated that it was inaccessible and 

that it was part of a mixture that included plutonium, which was a component of the worker’s 

routine bioassay sampling (Findley 1998). Exposure to curium could not have occurred

without concurrent exposure to plutonium. That is, any indication of internal exposure 

identified in a plutonium urine bioassay obtained through the Routine Bioassay Sampling 

Program would have triggered the Special Bioassay Sampling Program and an analysis of the 

source term for all radionuclides present.

4. “Specifications of Urine Bioassay Requirements on Radiological Work Permits,” March 10, 

1999 (Farrell and Findley 1999).

This is Farrell and Findley (1999), the summarized results of the 1999 characterization, and 

includes the process implemented in March 1999 for identifying and annually revisiting source 

terms. This report is discussed above in Section 3.4.8.

5. “Response to the Compilation of PAAA Internal Dosimetry Issues,” November 2, 1999 

(Morgan 1999).

This is the report from WSRC that summarized its response to the 31 general deficiencies 

identified by OEI. Its response to Item B.8 is described above in Section 2.0.

6.1.3 Questions Raised by SC&A

In their memorandum, Missing or Incomplete Radiological Source Terms, SC&A asked five questions 

about the 1999 recharacterization concerning both the use of the bioassay data by SRS and the 

effects on National Institute for Occupational Safety and Health (NIOSH) dose reconstruction.

1. What are the ramifications to dose reconstruction with sufficient accuracy if RWP job-specific 

bioassays neglected to include relevant radionuclides, particularly for certain facilities where 

complex, mixed, or unusual radioactive sources existed, e.g., SRTC, solid waste, burial 

grounds, tank farms, and decontamination and decommissioning projects?

There are not any ramifications to dose reconstruction because the relevant radionuclides 

were included in the bioassay program. There were relatively few changes in the bioassay 

monitoring by area from 1971 through 1999 with the exception of americium as discussed in 

Section 4.0 of this report. 

Job-specific routine bioassay samples were required across many site locations. The 

locations, the analytes for these locations, and the personnel participating in the Routine 

Bioassay Sampling Program varied in the procedures between 1971 and 1999. The routine 

bioassay results along with routine lung counts, routine WBCs, workplace air sampling, 

workplace surveys, and worker monitoring were used to monitor the effectiveness of worker 

protections. The Special Bioassay Sampling Program was in place to measure and assess 

actual internal exposures. It was designed to measure worker exposures for anyone at SRS 

who had the potential for an internal exposure that exceeded 100 millirem (WSRC 1990a, 

p. 36).

Dose reconstruction reviews all available bioassay data for the worker, including WBCs, chest 

counts, and bioassay results. Workers who were not monitored for a specific analyte and who 

may be reasonably expected to have worked in an area with that analyte will be assigned dose 

using ORAUT-OTIB-0081, Internal Coworker Dosimetry Data for the Savannah River Site

(ORAUT 2016). 
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2. If WSRC instituted such a policy in March 1999 requiring the RCOs to base bioassay 

monitoring on actual, updated workplace characterization versus expert judgment or 

longstanding facility knowledge, how incomplete were bioassays (including RWPs) prior to this 

date with regard to appropriately targeted radionuclides? 

There is no indication that bioassays under the Special Bioassay Program were incomplete. 

Most radionuclides targeted under the Routine Bioassay Program were not incomplete 

because their monitoring requirements did not change. Although routine monitoring 

requirements for americium did change, in almost all locations the presence of americium can 

be assumed and calculated from the age of the plutonium. In addition, in areas where 

americium was present without plutonium, such as at the MPPF, routine bioassay samples 

were required on RWPs and then collected and analyzed.

The March 1999 policy changes applied solely to the Routine Bioassay Sampling Program. 

The routine program along with routine lung counts, routine WBCs, workplace air sampling, 

workplace surveys, and worker monitoring were used to monitor the effectiveness of worker 

protections. The routine sampling was applied broadly to workers who were not expected to 

have internal uptake of radionuclides that would exceed 100 millirem. The Special Bioassay 

Sampling Program was triggered whenever there was an indication or suspicion of an uptake 

by a worker. This included high air sample results, skin contamination events, failure of 

protective clothing or protective barriers, and elevated results found by the routine program. 

Air sampling was one of the primary methods of worker protection and would detect alpha 

activity in the air regardless of the source alpha-emitting radionuclide. For example, the 1990 

Internal Dosimetry Technical Basis Manual required continuous air monitoring for workers 

entering RCAs and listed the components of a monitoring program for SRS transuranic 

workers to include urine bioassay, chest counts, fecal bioassay, and personal air samplers 

(portable breathing-zone air samplers worn by the workers) (WSRC 1990a, p. 235). Another 

example is found in the systems analysis of Building 772-F (Durant and Pritchard 1986), which 

describes the building’s air monitoring system as “designed to continuously monitor for 

particulate alpha contamination in air and provide prompt and adequate warning if [the] 

concentration of airborne alpha contamination increases above a preset alarm level” (Durant 

and Pritchard 1986, p. 32). 

Bioassay monitoring for the purposes of establishing worker exposures as required under 

10 CFR Part 835 and earlier DOE Orders was performed under the Special Bioassay

Sampling Program. The program, along with workplace air monitoring, surveys, and scans, is 

considered to have met the DOE requirements and is therefore a “complete” program. The 

SRS program, however, exceeded those requirements with the Routine Bioassay Sampling 

Program. 

Dose reconstruction by NIOSH uses all bioassay data from SRS and, where necessary, uses 

ratios of expected radionuclides to address intakes that were not measured by the site. Due to 

the ingrowth of 241Am in 241Pu, it would be expected in any aged plutonium sources. Particular 

to the characterization results showing 241Am as providing more than 10% of the dose in 

locations not previously established for routine Am/Cm/Cf bioassay monitoring, the 241Am 

contribution to the dose can be calculated for these locations using estimates of the age of the 

241Pu present, as has been calculated at other sites.

3. How does this impact dose reconstruction with sufficient accuracy if workers were incorrectly 

enrolled in bioassay programs, with potential exposure to key radiological sources not 

evaluated? 
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There is no indication workers were enrolled incorrectly in the bioassay programs. The March 

1999 change in policy by SRS does not impact the accuracy of dose reconstruction by NIOSH. 

In addition, coworker models can be used to estimate exposures for unmonitored workers.

The issues discussed by SC&A relate solely to the collection of samples under the Routine 

Bioassay Sampling Program. 

The Special Bioassay Sampling Program was designed to assess inadvertent intakes of 

radioactive material that could exceed 100 millirem to the worker (WSRC 1990a, p. 36). 

Workers with suspected or confirmed uptakes of radionuclides were monitored under the 

Special Bioassay Sampling Program. New requirements for routine bioassays do not indicate 

that workers in those areas were previously “incorrectly enrolled.” They were enrolled in the 

Routine Bioassay Program according to the requirements in place at that time.

Dose reconstruction by NIOSH uses all bioassay data from SRS, which includes the worker’s 

nonroutine special bioassay results and routine bioassay results, such as WBC and chest 

count results.

4. What is the significance of an apparent lack of ongoing facility source term characterization to 

adequate internal dose monitoring during the 1990s with the advent and growth of new 

activities and programs involving new and complex radiological sources, e.g., decontamination 

and decommissioning (D&D), solid waste management, environmental cleanup, and SRTC? 

The March 1999 sitewide source term characterization did not affect the adequacy of SRS to 

monitor workers for internal dose. It did change urine bioassay requirements for the Routine 

Bioassay Program, however the Routine Program was implemented in excess of the DOE 

regulatory requirements. No worker at SRS met the 10 CFR Part 835 definition for bioassay 

monitoring.

This source term characterization relates solely to the selection of analyses for routine 

bioassay samples, including job-specific (RWP) samples. There is no indication in the 

research for this report or in the references cited by the SC&A memorandum of a lack of 

radioisotopic characterization from special bioassay sampling.

The 1999 sitewide characterization effort did result from the instance of 244Cm found 

unexpectedly in the Burial Ground, although it was determined to be not an issue there 

because it was inaccessible to the workers and because plutonium was always present with 

the curium. 

Most of the changes identified after the 1999 characterization effort involved stored wastes 

and specific waste streams. The shift in mission as SRS moved from production into cleanup 

in the 1990s resulted in working with aging plutonium and higher relative amounts of 

americium. Americium sources measured in the 1999 characterization can be accounted for 

in earlier years using plutonium age estimates, as have been at other sites.

Note, however, that the addition of Am/Cm/Cf bioassays in certain areas was also due to a 

new requirement implemented with Farrell and Findley (1999) to include all radioisotopes for 

routine bioassay that contributed to 10% or more of the internal dose. Routine monitoring for 

the dominant nuclide would still have provided confirmation in the adequacy of the worker 

protection program, the stated purpose of routine bioassay sampling. In addition, routine 

sampling requirements for americium were applied in job-specific RWPs before 1999 at 

locations identified in Farrell and Findley (1999) to have americium and not listed for routine 

bioassays in the pre-1999 procedures. 
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Special bioassay sampling was indicated where there was an indication of an exposure that 

could exceed 100 millirem within one year. There were many fewer special bioassay samples 

collected than routine bioassay samples. The coworker model uses all applicable bioassay 

data including results from special and routine bioassay samples.

5. If key radionuclides such as americium had been missed, what other sources were not 

reflected on RWPs over time and what are the ramifications for dose reconstruction with 

sufficient accuracy for those workers potentially affected?

Key radionuclides were not “missed” before 1999 in the Routine Bioassay Sampling Program; 

there was a change in the methods used to list radionuclides required under the Routine 

Bioassay Program. The March 1999 change in policy by SRS does not impact the accuracy of 

dose reconstruction by NIOSH. In addition, coworker models could be used to estimate 

exposures for any unmonitored workers.

In March 1999, there was a change in the methods used to select locations and analytes for 

routine bioassay sampling. Procedures between 1971 and 1999 listed the requirements for 

the Routine Bioassay Sampling Program. This program was used across many site locations 

to confirm workplace controls. Routine bioassay sampling was also applied by job-specific 

RWPs. Any indication of an internal exposure led to the Special Bioassay Sampling Program, 

which included requirements for isotopic analysis of the source term for that potential 

exposure. The Special Bioassay Sampling Program was not limited to the analytes required 

by the Routine Bioassay Sampling Program nor did it rely on results from that program.

Changes between bioassay frequency tables between 1971 and 1999 for the routine sampling 

are described in Section 3.4 of this report. A comparison of the isotopes by location and waste 

stream in the 1999 characterization effort and published in Farrell and Findley (1999) and the 

preceding bioassay frequency table from 5Q1.1-506, In Vivo and In Vitro Bioassay Scheduling 

and Administration, Revision 5, is found in Table A-8. 

Dose reconstruction reviews all bioassay data for the worker, including WBCs, chest counts, 

and bioassay results. For SRS, the routine bioassay sample results were collected for 

workers not known to have received an intake of radioactive material, and special bioassay 

samples were collected for workers suspected to have had an intake due to events such as 

elevated air sample results, skin contamination, wounds, and failures in protective equipment. 

Sufficient accuracy is achieved in dose reconstructions when the available information allows 

a maximum estimate of worker exposure. Worker exposure records from SRS, including 

routine bioassay sample, special bioassay sample, chest count, and WBC results, provide that 

information.
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WSRC (Westinghouse Savannah River Company), 1996–1998, collection of Radiological Work 

Permit files, Savannah River Site, Aiken, South Carolina. [SRDB Ref ID: 175484]

WSRC (Westinghouse Savannah River Company), 1999a, Independent Assessment of the Savannah 

River Site Internal Dosimetry Program, ESH-HPT-99-0022, Savannah River Site, Aiken, South 

Carolina, February 9. [SRDB Ref ID: 45995, p. 8]

WSRC (Westinghouse Savannah River Company), 1999b, In Vivo and In Vitro Bioassay Scheduling 

and Administration, Manual 5Q1.1, Procedure 506, Rev. 10, Savannah River Site, Aiken, 

South Carolina, March 2. [SRDB Ref ID: 129596, p. 16]

WSRC (Westinghouse Savannah River Company), 2001, The Savannah River Site internal Dosimetry 

Technical Basis Manual, WSRC-IM-90139, Rev. 8, Savannah River Site, Aiken, South 

Carolina, December 31. [SRDB Ref ID: 722]

WSRC (Westinghouse Savannah River Company), 2008, The Savannah River Site internal Dosimetry 

Technical Basis Manual, WSRC-IM-90139, Rev. 12, Savannah River Site, Aiken, South 

Carolina, December 31. [SRDB Ref ID: 157076, p. 4]

WSRC (Westinghouse Savannah River Company), 2015, Final Safety Analysis Report Savannah

River Site Defense Waste Processing Facility, WSRC-SA-6, Rev. 34, Savannah River Site, 

Aiken, South Carolina, July. [SRDB Ref ID: 172668] 
Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 45 of 70

 

ATTACHMENT A 

BIOASSAY FREQUENCIES AND SOURCE TERMS

LIST OF TABLES

TABLE TITLE PAGE

A-1 Routine bioassay sampling frequencies excluding construction division, 

DPSOL 193-302, Revision 5, samples per year .......................................................................46

A-2 Bioassay frequencies, DPSOL 193-302, Revision 7................................................................. 48

A-3 Bioassay frequencies, DPSOL 193-302T, Revision 0 ..............................................................50

A-4 Bioassay frequency table, DPSOL 193-211, Revision 0...........................................................52

A-5 Minimum bioassay schedules for SRS facilities, Manual 5Q1.1, Procedure 506, 

Revision 0 ................................................................................................................................. 53

A-6 Minimum bioassay schedules for SRS facilities, Manual 5Q1.1, Procedure 506, 

Revision 5 ................................................................................................................................. 58

A-7 Source terms from Farrell and Findley (1999) ..........................................................................64

A-8 Source terms from Farrell and Findley (1999) versus Manual 5Q1.1, Procedure 506, 

Revision 5, minimum bioassay schedules ................................................................................65
ATTACHMENT A

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Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 46 of 70

Table A-1. Routine bioassay sampling frequencies excluding construction division, DPSOL 193-302, Revision 5 (DuPont 1971b), samples 

per year.a,b

Worker category/personnel description

H3

(urine)

Pu

(urine)

FP 

(urine)

EU 

(urine)

U 

(urine)

Am, 

Cm, 

Cf 

(urine)

EU

(chest)

Pu,

Am,

Cm, 

Cf

(chest)

Category A: Minimum Potential (Except HTO). Personnel assigned to 

284-F & -H, 704-F & -H, 706-F & -H, 717-F, and nonprocess sections of 

other facilities; patrolmen.

N/A (c) N/A N/A N/A N/A N/A N/A

Category B: 221-F &-H Fourth Level. Separations supervision; all 

Separations Technology personnel, control room operators, janitors, 

and clerical personnel.

N/A 1 1 N/A N/A N/A N/A N/A

Category C: 221-H & H-Area Outside Facilities. All operators (except 

control room and sample aisle), HP personnel, and selected Power, 

E&I, and maintenance personnel assigned to 22l-H process areas; all 

personnel assigned to H-Area outside facilities.

2 1 2 1 N/A N/A N/A N/A

Category D: 221-H Sample Aisle. All 221-H sample aisle operators. N/A 2 2 2 N/A N/A N/A 1

Category E: 221-F Sample Aisle. All 221-F sample aisle operators; 

selected 772-F personnel. N/A 2 2 N/A N/A 2 N/A 1 

Category F: 221-F, 723-F, & 643-G. All operators (except control room 

and sample aisle), HP personnel, and selected power, E&I, and 

Maintenance personnel assigned to 221-F process areas; all personnel 

assigned to 723-F and 643-G.

N/A 1 2 N/A N/A N/A N/A N/A

Category G: 221-H B-Line, 221-F B-Line, JB-Line, & 235-F. All 

personnel assigned to process sections in 235-F, and all assigned 

personnel in other facilities.

N/A 2 2 N/A N/A N/A N/A 1 

Category H: F-Area Outside Facilities. All assigned personnel. N/A (c) 2 N/A 4d N/A N/A N/A

Category J: 772- F (Excluding UO3 Section). All assigned personnel. N/A 2 2 1 1 N/A N/A 1e

Category K: 313-M. All assigned personnel. N/A N/A N/A N/A 4 N/A N/A N/A

Category L: 322-M. All assigned personnel (excluding personnel 

processing samples from field). 320-M. All laboratory and selected RM 

personnel. 773-A. Reactor Engineering group and 777-M assigned 

personnel.

N/A (c) N/A 1 4 N/A N/A N/A

Category M: 3 22-M. Personnel processing samples from the field. 

772-F, UO3 Section. All assigned personnel. N/A (c) 1 1 4 N/A N/A N/A

Category M: 321-M. All assigned personnel. N/A 1 N/A 4f N/A N/A 2g N/A
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 47 of 70

Worker category/personnel description

H3

(urine)

Pu

(urine)

FP 

(urine)

EU 

(urine)

U 

(urine)

Am, 

Cm, 

Cf 

(urine)

EU

(chest)

Pu,

Am,

Cm, 

Cf

(chest)

Category T: 100-Area, 105 Building. Reactor Department personnel 

from Charge and Discharge crews, purification, and pump room 

observation; control room and monitor operators, all 100-Area HP, 

Maintenance, and T&T personnel; all E&I personnel assigned to 105 

Buildings, T&T personnel in Central Shops; and selected Reactor 

Technology and 400-Area personnel.

(h) N/A 1i N/A N/A N/A N/A N/A

Category V: 773-A. Analytical Chemistry, HLCs, Building Services, 

Radiation Control, and maintenance personnel. N/A (c) 1 N/A N/A 2 N/A 1e

Category W: 773-A. Selected clerical, supervisory personnel, and 

selected 100-Area personnel. N/A (c) N/A N/A N/A 1 N/A N/A

Category X: 232-H, 234-H, 237-H, & 238-H. All assigned personnel. 

241·H & 244-H. Selected personnel. (h) (c) N/A N/A N/A N/A N/A N/A

700-Area: Shop personnel.j N/A N/A N/A N/A N/A N/A N/A N/A

a. FP = fission product; HLC = high-level cave; HTO = tritiated water vapor; N/A = not applicable; RM = Reactor Maintenance; T&T = Traffic and Transportation. 

b. Neptunium analysis is performed when requested by area HP. Np has never been detected without at least an equal amount of Pu.

c. One sample every 3 years.

d. Except A-Line where operators are sampled weekly.

e. Selected personnel.

f. Except casting area where operators are sampled monthly.

g. Only personnel assigned to casting area.

h. Sample frequency established by local procedures.

i. Samples are also analyzed for IA. 

j. 700-area shop personnel provide samples as considered by HP. 
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 48 of 70

Table A-2. Bioassay frequencies, DPSOL 193-302, Revision 7 (DuPont 1976, p. 4).aa

Category and personnel work assignment Pu EU U

IA, 

FP

Am, 

Cm, 

Cf Sr H3 F

In vivo 

counts/yr

(days)

In vivo 

counts/yr

(shift)

(Category A) Minimum potential: Personnel working in 

tritium facilities, 200-FH facilities not mentioned below, 

723-A Environmental Effects Division, and 305-M. 

Selected 100-Area and 773-A personnel.

1/3 N/A N/A N/A N/A N/A (b) N/A 1/3c 1/3

(Category B) 221-FH: All operators, Separations

Technology, HP, and fourth-level personnel: E&I, 

Maintenance, Clerical, and Service Department personnel 

assigned to process areas. 

241-FH, 211-FH, 723-F, A-Line, 643-0, and 244-E: All 

assigned personnel.

772-F and 235-F: Personnel assigned to non-process 

areas.

Patrol and T&T: All personnel assigned to 200-FH Areas.

773-A: Selected clerical and supervisory personnel.

100-Areas: Selected personnel.

1 (d) (e) N/A (f) (g) N/A N/A 1 2

(Category C) 221-HB Line, 221-FB Line, JB-Line: All 

assigned personnel.

235-F: Personnel assigned to process areas.

772-F: Personnel assigned to process areas.

773-A: Selected ACD, SED, SCD, NMD, HLC, Radiation

Control, Building Services, and Maintenance personnel.

2 (d) N/A N/A (f) N/A N/A (c) 1h 2

(Category K) 313-M: All assigned personnel. N/A N/A 4 N/A N/A N/A N/A N/A N/A N/A

(Category L) 322-M and 772-F (UO3 Section): All 

assigned personnel.

320-M: All laboratory and selected RM personnel.

773-A: Reactor Engineering and 777-M personnel.

1/3 1 4 N/A N/A N/A N/A N/A (i) (i)

(Category N) 321-N: All assigned personnel except those 

in Casting Area.

1 4 N/A N/A N/A N/A N/A N/A 1/3 1

(Category R): Used by Personnel Monitoring to designate 

personnel with a confirmed transuranic uptake. Area HP

can increase sample frequencies with job assignments 

warrant. Do not change category letter.

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
ATTACHMENT A

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Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 49 of 70

Category and personnel work assignment Pu EU U

IA, 

FP

Am, 

Cm, 

Cf Sr H3 F

In vivo 

counts/yr

(days)

In vivo 

counts/yr

(shift)

(Category T): Reactor Department personnel from CH 

purification and pump room observation; control room and 

monitor operators; all 100-Area HP, Maintenance, and 

T&T personnel; E&I and Service personnel assigned to 

105 buildings; T&T personnel in Central Shops and 610-

C; selected Reactor Technology, Project, and 400-Area 

personnel.

1c N/A N/A 1 N/A N/A (b) N/A 1j 1j

(Category U) 321-M: All personnel assigned to Casting 

Area.

1 12 N/A N/A N/A N/A N/A N/A 2 2

a. IA = induced activity; N/A = not applicable.

b. Sample frequency established by local procedures.

c. Selected personnel.

d. Selected personnel in 221-H, 211-H, and 772-F sampled for EU four times a year.

e. A-Line assigned personnel in F-Area sampled weekly; samples collected after day(s) of rest and before exposure.

f. Selected personnel in 221-F, 211-F, and 773-A sampled for Am-Cm once a year.

g. Selected personnel assigned to waste management work sampled for Sr once a year.

h. All B-Line and JB-Line personnel and 772-F lab attendants counted twice a year.

i. 322-M personnel processing 200-Area samples and 772-F (UO3 Section) personnel counted once a year.

j. Selected day and all shift personnel; urine sample not required if in vivo count scheduled.
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 50 of 70

Table A-3. Bioassay frequencies, DPSOL 193-302T, Revision 0 (DuPont 1985j).a 

Personnel Work assignment

Suggested 

code

100-400 Areas Selected day personnel and all shift Reactor Department CH, purification, pump observation room, and 

monitor operators. 

N

100-400 Areas Reactor control room operators; HP, Maintenance, T&T, E&I, and Service personnel assigned to 105 Building, 

T&T personnel in Central Shops and 618-G; selected Reactor Technology, Project, and selected 400-Area 

personnel.

AP

100-400 Areas Maximum potential. Selected personnel. B

100-400 Areas Other personnel assigned to 105 Building. Selected 400-Area personnel. P

200-Areas Personnel working in tritium facilities or 200-FH facilities not mentioned below. A

221-FH; 723-F; 643-G; 

A-Line; 241-FH; 244-H

All Separations operators; Sep. Tech, HP, and other 4th-level personnel; E&I, Maintenance, Clerical, and 

Service Dept. personnel assigned to process areas.

B

235-F; 772-F Selected personnel. B

221-F Selected personnel. BT

211-H Selected personnel. BG

643-G Selected personnel assigned to waste management work. BX

221-FB Line, JB-Line All assigned personnel. C

235-F Personnel assigned to process areas. CW

772-F Personnel assigned to laboratories in the PUREX and Pu sections. CE

221-F Selected personnel. CU

221-H; 772-F Selected personnel. CG

221 HB-Line All assigned personnel. D

300-Areas; 313-M All assigned personnel. L

322-M UO3 sections and other selected personnel. BEL

322-M All other assigned personnel. AEL

320-M All laboratory and selected RM personnel. EL

321-M All personnel assigned to charge prep, casting, and machining area. BH

321-M All other assigned personnel. BG

773-A Minimum potential. A

773-A Selected ACD, SED, SCD, NMD, HLC, Radiation Control, Building Services, and maintenance personnel. CT

773-A Reactor engineering and 777-M personnel. AEL

773-A Selected clerical and supervisory personnel. B

773-A Maximum potential. Selected personnel. CFLU

a. PUREX = plutonium-uranium extraction.
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 51 of 70

Description of Code

Nuclide Samples/year Code

Pu 0.3A

Pu1B

Pu2C

Pu4D

EU1E

EU2F

EU4G

EU 12H

Natural U1J

Natural U2K

Natural U4L

Natural U 12M

Fission product induced activities0N

Fission product induced activities1P

Fission product induced activities2R

Fission product induced activities4S

Am, Cm, and Cf1T

Am, Cm, and Cf2U

Am, Cm, and Cf4V

Np1W

Sr1X

Sr2Y

Sr4Z
ATTACHMENT A

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Table A-4. Bioassay frequency table, DPSOL 193-211, Revision 0 (DuPont 1989b).a,b

Personnel Work assignment

Suggested 

code

100-400 Areas, all Reactor 

Area Departments and 

Construction

Selected day personnel and all shift Reactor Department CH, purification, pump observation room, and 

monitor operators. Maintenance, T&T, E&I, and Service personnel assigned to 105 building, T&T 

personnel in Central Shops and 618-G; selected Reactor Technology, Project, and selected 400-Area 

personnel.

A

100-400 Areas, all Reactor 

Area Departments and 

Construction

HP, selected CH. B

211-H Selected personnel. BG

643-G Selected personnel assigned to waste management work. BX

FB-Line Operators and first-line supervisors. Solid Waste Engineering (SWE) mechanics. D

FB-Line Other assigned personnel. B

HB-Line Operators. DW

HB-Line Other assigned personnel. BW

235-F Operators. DW

235-F Other assigned personnel. BW

A-Line (F) All assigned personnel. BM

772-F Personnel assigned to laboratories in the PUREX and Pu sections. CE

221-F Selected personnel. B

221-H Selected personnel. CG

313-M All assigned personnel. L

322-M All assigned personnel. BGL

320-M All laboratory and selected RM personnel. GL

321-M All personnel assigned to charge prep, Casting, and machining, and assembly weld areas BH

321-M All other assigned personnel. BG

773-A Minimum potential. A

773-A Selected ACD, SED, SCD, NMD, HLC, Radiation Control, Building Services, and Maintenance personnel. CT

773-A Reactor Engineering and 777-M personnel. AEL

773-A Selected clerical and supervisory personnel. B

773-A Maximum potential. Selected personnel. CFLU

221-S All assigned personnel. BX

250-S All assigned personnel. BX
ATTACHMENT A

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Personnel Work assignment

Suggested 

code

210-Z All assigned personnel. BX

247-F Personnel who perform work in process core. H

247-F Personnel who do not perform work in process core. G

a. Source: DuPont (1989b). 

b. Codes are identical to those in Table A-3 above.

Table A-5. Minimum bioassay schedules for SRS facilities, Manual 5Q1.1, Procedure 506, Revision 0 (WSRC 1992a, p. 41). 

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

SRTC

773-A

Chemical Technology

Section

Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Am, Cm, and Cf, 2/yr

Pu02;

Am02

SRTC

773-A

Chemical Technology 

Section

Category II WBC, 1/yr Pu, 1/yr Pu01

SRTC

773-A 

ADS Category I WBC, 1/yr; chest count, 1/yr Pu, 1/yr; 

Sr, 1/yr; 

Am, Cm, and Cf, 1/yr

Pu01; 

Sr01; 

Am01

SRTC

773-A

ADS Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr

Pu01; 

Sr01

SRTC

773-A

Interim Waste Section Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr

Pu01; 

Sr01

SRTC

773-A

Defense Waste Section Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

SRTC

773-A 

HLCs Category I WBC, 1/yr; chest count, 1/yr Pu, 1/yr; 

Sr, 1/yr; 

Am, Cm, and Cf, 2/yr

Pu01; 

Sr01; 

Am02

SRTC

773-A 

Materials Technology

Section

(Fab Lab)

Category I WBC, 1/yr Uranium, 12/yr; 

Pu, 1/yr

U12; 

Pu01

SRTC

773-A 

Materials Technology

Section

(Fab Lab)

Category II WBC, 1/yr Pu, 1/yr Pu01

779-A Equipment Engineering. 

Section

Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1 yr

Pu02; 

Sr01

779-A Equipment Engineering. 

Section

Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01
ATTACHMENT A

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Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 54 of 70

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

773-A;

776-A 

Maintenance/E&I Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1/yr; 

Am, Cm, and Cf, 2/yr

Pu02;

Sr01;

Am02

773-A;

776-A 

Maintenance/E&I Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr; 

Am, Cm, and Cf, 1/yr

Pu01;

Sr01; 

Am01

SRTC Environmental Control

Inspector

Category III WBC, 1/yr None required X00

SRTC All RCAs Category III WBC, 1/yr None required X00

C-Area All RAs Category I WBC, 1/yr Tritium (job-specific sampling) TJS

C-Area All RCAs Category III WBC, 1/yr Tritium, 12/yr T12

K-Area All RAs Category I WBC, 1/yr Tritium (job-specific sampling) TJS

K-Area All RCAs Category III WBC, 1/yr Tritium, 12/yr T12

L-Area All RAs Category I WBC, 1/yr Tritium (job-specific sampling) TJS

L-Area All RCAs Category III WBC, 1/yr Tritium, 12/yr T12

P-Area All RAs Category I WBC, 1/yr Tritium (job-specific sampling) TJS

P-Area All RCAs Category III WBC, 1/yr Tritium, 12/yr T12

400-Areas All RAs Category I WBC, 1/yr Tritium (job-specific sampling) TJS

400-Areas All RCAs Category III WBC, 1/yr Tritium, 12/yr T12

TNX All RCAs Category I WBC, 1/yr EU, 4/yr EU04

TNX All RCAs Category II & III WBC, 1/yr None required X00

221-F Canyon All RCAs Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1 yr

Pu02; 

Sr01

221-F Canyon All RCAs Category II WBC, 1/yr Pu, 1/yr Pu01

221-F Canyon All RCAs Category III WBC, 1/yr None required X00

221-F A-Line & 211-F 

(Outside Facilities)

All RCAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr

Pu01; 

Sr01

221-F A-Line & 211-F 

(Outside Facilities)

All U RCAs Category I WBC, 1/yr Uranium, 12/yr U12

221-F A-Line & 211-F 

(Outside Facilities)

All RCAs Category II & III WBC, 1/yr None required X00

221-F

B-Line

All RCAs Category I WBC, 1/yr; chest count, 1/yr Pu, 4/yr Pu04

221-F

B-Line

All RCAs Category II WBC, 1/yr Pu, 1/yr Pu01
ATTACHMENT A

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Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

221-F

B-Line

All RCAs Category III WBC, 1/yr None required X00

221-F 

New Special Recovery

All RCAs Category I WBC, 1/yr; chest count, 1/yr Pu, 4/yr Pu04

221-F 

New Special Recovery

All RCAs Category II WBC, 1/yr Pu, 1/yr Pu01

221-F 

New Special Recovery

All RCAs Category III WBC, 1/yr None required X00

221-F Pu Storage 

Facility

All RCAs Category I WBC, 1/yr; chest count, 1/yr Pu, 4/yr Pu04

221-F Pu Storage 

Facility

All RCAs Category II WBC, 1/yr Pu, 1/yr Pu01

221-F Pu Storage 

Facility

All RCAs Category III WBC, 1/yr None required X00

235-F All RCAs excluding Np 

Line

Category I WBC, 1/yr; chest count, 1/yr Pu, 4/yr Pu04

235-F All RCAs excluding Np 

Line

Category II WBC, 1/yr Pu, 1/yr Pu01

235-F All RCAs excluding Np 

Line

Category III WBC, 1/yr None required X00

235-F All RCAs including Np 

Line

Category I WBC, 1/yr; chest count, 1/yr Pu, 4/yr; 

Np, 1/yr

Pu04; 

Np01

235-F All RCAs including Np 

Line

Category II WBC, 1/yr Pu, 1/yr Pu01

235-F All RCAs including Np 

Line

Category III WBC, 1/yr None required X00

772-F PUREX & Pu Sections Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1 yr

Pu02; 

Sr01

772-F PUREX & Pu Sections Category II WBC, 1/yr Pu, 1/yr Pu01

772-F Uranium Section Category I WBC, 1/yr; chest count, 1/yr EU, 2/yr EU02

772-F Uranium Section Category II WBC, 1/yr EU, 1/yr EU01

772-F All RCAs in all sections Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr;

EU, 1/yr; 

Sr, 1 yr

Pu02; 

EU01; 

Sr01

772-F All RCAs in all sections Category II WBC, 1/yr Pu, 1/yr Pu01

772-F All RCAs Category III WBC, 1/yr None required X00
ATTACHMENT A

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Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

772-1F PUREX & Pu Sections Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1 yr

Pu02; 

Sr01

772-1F All RCAs Category II WBC, 1/yr Pu, 1/yr Pu01

772-1F All RCAs Category III WBC, 1/yr None required X00

247-F All RCAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr EU04

247-F All RCAs Category II WBC, 1/yr EU, 1/yr EU01

247-F All RCAs Category III WBC, 1/yr None required X00

221-H Canyon All RCAs Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

EU, 4/yr

Pu02; 

EU04

221-H Canyon All RCAs Category II WBC, 1/yr Pu, 1/yr; 

EU, 1/yr

Pu01; 

EU01

221-H Canyon All RCAs Category III WBC, 1/yr None required X00

221-H

B-Line

All RCAs Category I WBC, 1/yr; chest count, 1/yr Pu, 4/yr; 

Np, 1/yr

Pu04; 

Np01

221-H

B-Line

All RCAs Category II WBC, 1/yr Pu, 1/yr Pu01

221-H

B-Line

All RCAs Category III WBC, 1/yr None required X00

211-H All RCAs Category I WBC, 1/yr; chest count, 1/yr Pu, 1/yr; 

EU, 4/yr

Pu01; 

EU04

211-H All RCAs Category II WBC, 1/yr Pu, 1/yr; 

EU, 1/yr

Pu01; 

EU01

211-H All RCAs Category III WBC, 1/yr None required X00

232-H All RAs Category I WBC, 1/yr (if entering Line III) Tritium (job-specific sampling) TJS

232-H Assignment to RCAs Category II WBC, 1/yr (if entering Line III) Tritium, 1/week T52

232-H All RCAs Category III WBC, 1/yr (if entering Line III) Tritium, 12/year T12

234-H All RAs Category I None required Tritium (job-specific sampling) TJS

234-H Assignment to RCAs Category II None required Tritium, 1/week T52

234-H All RCAs Category III None required Tritium, 12/year T12

238-H All RAs Category I None required Tritium (job-specific sampling) TJS

238-H Assignment to RCAs Category II None required Tritium, 1/week T52

238-H All RCAs Category III None required Tritium, 12/year T12

244-H All RCAs Category I & II WBC, 1/yr Pu, 1/yr Pu01

244-H All RCAs Category III WBC, 1/yr None required X00

241-F All RCAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 57 of 70

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

241-F All RCAs Category II & III WBC, 1/yr None required X00

241-H All RCAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 2 yr

Pu01; 

Sr02

241-H All RCAs Category II & III WBC, 1/yr None required X00

299-H All RCAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

299-H All RCAs Category II & III WBC, 1/yr None required X00

241-84H All RCAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

241-84H All RCAs Category II & III WBC, 1/yr None required X00

643-E; 643-1E & 

Support Facilities

All RCAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

643-E; 643-1E & 

Support Facilities

All RCAs Category II & III WBC, 1/yr None required X00

210-Z All RCAs Category I & II WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

210-Z All RCAs Category III WBC, 1/yr None required X00

313-M All RCAs Category I & II WBC, 1/yr U, 12/yr U12

313-M All RCAs Category III WBC, 1/yr None required X00

320-M All RCAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr; 

uranium, 12/yr

EU04; 

U12

320-M All RCAs Category II WBC, 1/yr EU, 1/yr EU01

320-M All RCAs Category III WBC, 1/yr None required X00

321-M All RCAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr EU04

321-M All RCAs Category II WBC, 1/yr EU, 1/yr EU01

321-M All RCAs Category III WBC, 1/yr None required X00

322-M All RCAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr; 

uranium, 12/yr

EU04; 

U12

322-M All RCAs Category II WBC, 1/yr EU, 1/yr EU01

322-M All RCAs Category III WBC, 1/yr None required X00

341-M & 341-1M All RCAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr EU04

341-M & 341-1M All RCAs Category II WBC, 1/yr EU, 1/yr EU01

341-M & 341-1M All RCAs Category III WBC, 1/yr None required X00

Roving Employees RCAs excluding U 

handling facilities

Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1/yr

Pu02; 

Sr01
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 58 of 70

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

Roving Employees RCAs excluding U 

handling facilities

Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr

Pu01; 

Sr01

Roving Employees RCAs excluding U 

handling facilities

Category III WBC, 1/yr None required X00

Roving Employees RCAs including U 

handling facilities

Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

EU, 2/yr; 

Sr, 1/yr

Pu02; 

EU02; 

Sr01

Roving Employees RCAs including U 

handling facilities

Category II WBC, 1/yr Pu, 1/yr; 

EU, 1/yr; 

Sr, 1/yr

Pu01; 

EU01; 

Sr01

Roving Employees RCAs including uranium 

handling facilities

Category III WBC, 1/yr None required X00

a. RA = Radiological Area; TNX = code designation for Semi-works Laboratory.

Table A-6. Minimum bioassay schedules for SRS facilities, Manual 5Q1.1, Procedure 506, Revision 5 (WSRC 1996).a

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

SRTC Chemical Technology Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Am, Cm, and Cf, 2/yr

Pu02;

Am02

SRTC Chemical Technology Category II WBC, 1/yr Pu, 1/yr Pu01

SRTC Analytical Development Category I WBC, 1/yr; chest count, 1/yr Pu, 1/yr; 

Sr, 1/yr; 

Am, Cm, and Cf, 1/yr

Pu01; 

Sr01; 

Am01

SRTC Analytical Development Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr

Pu01; 

Sr01

SRTC Interim Waste Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr

Pu01; 

Sr01

SRTC Defense Waste Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

SRTC High-Level Cave Category I WBC, 1/yr; chest count, 1/yr Pu, 1/yr; 

Sr, 1/yr; 

Am, Cm, and Cf, 2/yr

Pu01; 

Sr01; 

Am02

SRTC Materials Technology

(Fab Lab)

Category I WBC, 1/yr U, 12/yr; 

Pu, 1/yr

U12; 

Pu01

SRTC Materials Technology

(Fab Lab)

Category II WBC, 1/yr Pu, 1/yr Pu01
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 59 of 70

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

SRTC Equipment Engineering Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1 yr

Pu02; 

Sr01

SRTC Equipment Engineering Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

SRTC Support Personnel 

(Maintenance/E&I, RCO, 

Construction, etc.)

Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1/yr; 

Am, Cm, and Cf, 2/yr

Pu02;

Sr01; 

Am02

SRTC Support Personnel 

(Maintenance/E&I, RCO, 

Construction, etc.)

Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr; 

Am, Cm, and Cf, 1/yr

Pu01;

Sr01; 

Am01

SRTC All RBAs Category III WBC, 1/yr None required X00

100-Areas & 400-Area All RBAs Category I, II, & 

III

WBC, 1/yr Tritium, 1/mob T30

TNX All RBAs Category I WBC, 1/yr EU, 4/yr EU04

TNX All RBAs Category II & III WBC, 1/yr None required X00

221-F Canyon All RBAs Category I WBC, 1/yr Pu, 2/yr; 

Sr, 1 yr

Pu02; 

Sr01

221-F Canyon All RBAs Category II WBC, 1/yr Pu, 1/yr Pu01

221-F Canyon All RBAs Category III WBC, 1/yr None required X00

221-F A-Line & 211-F 

(Outside Facilities)

All RBAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

221-F A-Line & 211-F 

(Outside Facilities)

All U RBAs Category I WBC, 1/yr U, 12/yr U12

221-F A-Line & 211-F 

(Outside Facilities)

All RBAs Category II & III WBC, 1/yr None required X00

221-F

B-Line

All RBAs Category I WBC, 1/yr; chest count, 1/yr Pu, 4/yr Pu04

221-F

B-Line

All RBAs Category II WBC, 1/yr Pu, 1/yr Pu01

221-F

B-Line

All RBAs Category III WBC, 1/yr None required X00

221-F 

New Special Recovery

All RBAs Category I WBC, 1/yr Pu, 1/yr Pu01

221-F 

New Special Recovery

All RBAs Category II WBC, 1/yr Pu, 1/yr Pu01
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 60 of 70

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

221-F 

New Special Recovery

All RBAs Category III WBC, 1/yr None required X00

221-F Plutonium 

Storage Facility

All RBAs Category I WBC, 1/yr Pu, 1/yr Pu01

221-F Plutonium 

Storage Facility

All RBAs Category II WBC, 1/yr Pu, 1/yr Pu01

221-F Plutonium 

Storage Facility

All RBAs Category III WBC, 1/yr None required X00

235-F All RBAs excluding Np 

Line

Category I WBC, 1/yr Pu, 4/yr Pu04

235-F All RBAs excluding Np 

Line

Category II WBC, 1/yr Pu, 1/yr Pu01

235-F All RBAs excluding Np 

Line

Category III WBC, 1/yr None required X00

235-F All RBAs including Np 

Line

Category I WBC, 1/yr Pu, 4/yr; 

Np, 1/yr

Pu04; 

Np01

235-F All RBAs including Np 

Line

Category II WBC, 1/yr Pu, 1/yr Pu01

235-F All RBAs including Np 

Line

Category III WBC, 1/yr None required X00

772-F PUREX & Pu Sections Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1 yr

Pu02; 

Sr01

772-F PUREX & Pu Sections Category II WBC, 1/yr Pu, 1/yr Pu01

772-F U Section Category I WBC, 1/yr; chest count, 1/yr EU, 2/yr EU02

772-F U Section Category II WBC, 1/yr EU, 1/yr EU01

772-F All RBAs in all sections Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr;

EU, 1/yr; 

Sr, 1 yr

Pu02; 

EU01; 

Sr01

772-F All RBAs in all sections Category II WBC, 1/yr Pu, 1/yr Pu01

772-F All RBAs Category III WBC, 1/yr None required X00

772-IF PUREX & Pu sections Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1 yr

Pu02; 

Sr01

772-IF All RBAs Category II WBC, 1/yr Pu, 1/yr Pu01

772-IF All RBAs Category III WBC, 1/yr None required X00

247-F All RBAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr EU04

247-F All RBAs Category II WBC, 1/yr EU, 1/yr EU01
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 61 of 70

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

247-F All RBAs Category III WBC, 1/yr None required X00

221-H Canyon All RBAs Category I WBC, 1/yr Pu, 2/yr; 

EU, 4/yr

Pu02; 

EU04

221-H Canyon All RBAs Category II WBC, 1/yr Pu, 1/yr; 

EU, 1/yr

Pu01; 

EU01

221-H Canyon All RBAs Category III WBC, 1/yr None required X00

221-H, B-Line All RBAs Category I WBC, 1/yr Pu, 4/yr; 

Np, 1/yr

Pu04; 

Np01

221-H, B-Line All RBAs Category II WBC, 1/yr Pu, 1/yr Pu01

221-H, B-Line All RBAs Category III WBC, 1/yr None required X00

211-H All RBAs Category I WBC, 1/yr Pu, 1/yr; 

EU, 4/yr

Pu01; 

EU04

211-H All RBAs Category II WBC, 1/yr Pu, 1/yr; 

EU, 1/yr

Pu01; 

EU01

211-H All RBAs Category III WBC, 1/yr None required X00

232-H, Line III All RBAs Category I, II, & 

III

WBC, 1/yr Tritium 1/mob T30

232-H; 233-H; 234-H; 

238-H

All RBAs Category I, II, & 

III

None Required Tritium 1/mob T30

244-H All RBAs Category I & II WBC, 1/yr Pu, 1/yr Pu01

244-H All RBAs Category III WBC, 1/yr None required X00

241-F All RBAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

241-F All RBAs Category II & III WBC, 1/yr None required X00

241-H All RBAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 2 yr

Pu01; 

Sr02

241-H All RBAs Category II & III WBC, 1/yr None required X00

299-H All RBAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

299-H All RBAs Category II & III WBC, 1/yr None required X00

241-84H All RBAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

241-84H All RBAs Category II & III WBC, 1/yr None required X00

643-E; 643-1E; Burial 

Ground & Support 

Facilities

All RBAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 62 of 70

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

643-E; 643-1E; Burial 

Ground & Support 

Facilities

All RBAs Category II & III WBC, 1/yr None required X00

210-Z All RBAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

210-Z All RBAs Category II & III WBC, 1/yr None required X00

221-S; 512-S All RBAs Category I WBC, 1/yr Pu, 1/yr; 

Sr, 1 yr

Pu01; 

Sr01

221-S; 512-S All RBAs Category II & III WBC, 1/yr None required X00

313-M All RBAs Category I & II WBC, 1/yr U, 12/yr U12

313-M All RBAs Category III WBC, 1/yr None required X00

320-M All RBAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr; 

U, 12/yr

EU04; 

U12

320-M All RBAs Category II WBC, 1/yr EU, 1/yr EU01

320-M All RBAs Category III WBC, 1/yr None required X00

321-M All RBAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr EU04

321-M All RBAs Category II WBC, 1/yr EU, 1/yr EU01

321-M All RBAs Category III WBC, 1/yr None required X00

322-M All RBAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr; 

U, 12/yr

EU04; 

U12

322-M All RBAs Category II WBC, 1/yr EU, 1/yr EU01

322-M All RBAs Category III WBC, 1/yr None required X00

341-M & 341-1M All RBAs Category I WBC, 1/yr; chest count, 1/yr EU, 4/yr EU04

341-M & 341-1M All RBAs Category II WBC, 1/yr EU, 1/yr EU01

341-M & 341-1M All RBAs Category III WBC, 1/yr None required X00

Roving Employees RBAs excluding uranium 

handling facilities

Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

Sr, 1/yr

Pu02; 

Sr01

Roving Employees RBAs excluding uranium 

handling facilities

Category II WBC, 1/yr Pu, 1/yr; 

Sr, 1/yr

Pu01; 

Sr01

Roving Employees RBAs excluding uranium 

handling facilities

Category III WBC, 1/yr None required X00

Roving Employees RBAs including uranium 

handling facilities

Category I WBC, 1/yr; chest count, 1/yr Pu, 2/yr; 

EU, 2/yr; 

Sr, 1/yr

Pu02; 

EU02; 

Sr01
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 63 of 70

Facility Work area

Worker 

classification In vivo requirements In vitro requirements

Schedule 

code

Roving Employees RBAs including uranium 

handling facilities

Category II WBC, 1/yr Pu, 1/yr; 

EU, 1/yr; 

Sr, 1/yr

Pu01; 

EU01; 

Sr01

Roving Employees RBAs including uranium 

handling facilities

Category III WBC, 1/yr None required X00

SRELc N/A N/A N/A N/A N/A

a. RBA = Radiological Buffer Area; RCO = Radiological Control Operations. 

b. For personnel entering RBAs >1/mo. where sampling is required. For other, less frequent entry, job specific samples should be left (bioassay code X-00 assigned).

c. Routine program not required under normal conditions. Contact Bioassay Customer Representative for guidance for special work or unusual occurrences. 
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 64 of 70

Table A-7. Source terms from Farrell and Findley (1999). 

Location or waste stream Radioisotope Dose fraction

221-F B Line Pu 98% Pu

235-F Pu, Np 99% Pu

221-F Canyon/Outside Facilities Pu 95% Pu

MPPF Pu, Am 99% Am

221-F A-Line U 97% U

221-H B-Line Pu 94% Pu

221-H/Outside Facilities Pu, Am, Np 68% Pu 8% Am 12% Cm

221-H A-Line U 98% U

F- & H-Area Tanks Pu, Am, Sr Not provided

DWPF (200-S Area) Pu Not provided

Low Level Waste Sort Facility Pu Not provided

RBOF, K- and L-Areas Pu, Am, H Not provided

C-, P-, and R-Areas H, Pu, Am, Sr Not provided

M-Areas H, U Not provided

H-Area (Tritium Production Facilities) H, U Not provided

776-D Waste Stream (773-A 776-5A) Pu, Am 88% Pu 11% Am

B-Process Waste Stream (773-A) Pu, Am 83% Am 17% Cm 

C-Process Waste Stream (773-C) Pu 93% Pu

F-Wing Boot Waste Stream Am 71% Am 29% Cm

SCH-3-D Waste Stream (773-A) Pu, Am 70% Cm 24% Pu 6% Am

776-4A HEPA Filters Waste Stream Pu, Am 78% Pu 7% Am 15% Cm

ADS-1 Waste Stream (Analytical Development System Laboratories) Pu, Am 88% Pu 11% Am & Cm

Canyon Waste Stream (773-A CHTS , ADS laboratories) Pu 97% Pu

Non-Canyon Waste Stream (773-A non CHTS, ADS laboratories) Pu, Am 76% Pu 23% Cm

Casks Waste Stream (HLW sludge) Pu, Am 82% Cm 17% Pu

Casks Waste Stream (HLW supernate) Pu 99% Pu

Californium Waste Stream (773-A F Wing Cf facilities) Am 100% Cf

CLAB Waste Stream A (Building 772-1F Laboratory Modules L120, L122, L126, L127, and L130) Pu 99% Pu

CLAB Waste Stream B (772-1F Laboratory Modules L125, L128, L129, L132, L137, L156, 772-1F 

Cells (including Cell exhaust system) and 772-1F Filter Room)

Pu 94% Pu

CLAB Waste Stream C (Building 772-1F Laboratory Modules L108, L121, L133, L149, L150, L152, 

Off Gas Exhaust, RCO Exhausts, 772-1F drain line exhaust, 772-1F vacuum systems and Building 

772-F Shielded Area/Fan Room, Liquid By-Product Tanks, Laboratory Module L162 and the 772-4F 

Area)

Pu 99% Pu

CLAB Waste Stream D (Building 772-1F Laboratory Module L134) Pu, U 78% Pu 16% U
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 65 of 70

Location or waste stream Radioisotope Dose fraction

CLAB Waste Stream E (Building 772-F Laboratory Modules L131, L138, L139, L146, L147, L154, 

L155, and L171)

Pu, Am 67% Am 32% Pu

CLAB Waste Stream F (772-F Laboratory Modules L126, L130, L158, L159, and L163) Pu 97% Pu

CLAB Waste Stream G (772-F/772-4F filter room) Pu, Am 79% Pu 18% Am

CLAB Waste Stream H (Building 772-F Laboratory Modules L142, L143, L146, L147, L174, L175, 

and L183)

Pu, Am 89% Am 11% Pu

CLAB Waste Stream I (Building 772-F Laboratory Modules L110, L111, and L119) H 100% H

CLAB Waste Stream J (Building 772-F Laboratory Modules, which is disposed of in the 772F LSC 

drum)

Pu, Am, H 53% Am, 33% H, 12% Pu

a. DWPF = Defense Waste Processing Facility; HEPA = high-efficiency particulate air.

Table A-8. Source terms from Farrell and Findley (1999) versus Manual 5Q1.1, Procedure 506, Revision 5, minimum bioassay schedules. 

Farrell and Findley (1999) location or waste stream

Farrell and Findley (1999) 

analyses

Manual 5Q1.1, 

Procedure 506, 

Revision 5 location

Manual 5Q1.1, 

Procedure 506, 

Revision 5 analyses

221-F B Line Pu 221-F B Line Pu 

235-F Pu, Np 235-F Pu, Np

221-F Canyon/Outside Facilities Pu 221-F Canyon Pu, Sr, U

MPPF Pu, Am 221-F Canyon Pu, Sr, U

221-F A-Line U 221-F A-Line and 221-F Pu, Sr, U

221-H B-Line Pu 221-H B line Pu, Np

221-H/Outside Facilities Pu, Am, Np 221-H Canyon Pu, U

221-H A-Line U 221-H Canyon Pu, U

F- & H- Area Tanks Pu, Am, Sr 241-F, 241-H Pu, Sr, Pu

DWPF (200-S Area) Pu 241-H Pu

Low Level Waste Sort Facility Pu 643-E, 643-1E and 

Support Facilities

Pu, Sr

RBOF, K- and L-Areas Pua, Ama, H 244-H, K-Area, L-Area Pu; H

C-, P-, and R-Areas H, Pu, Am, Sr C-Area, P-Area H

M-Area H, U 313-M, 321-M, 322-M,

342-M, and 341-M

U

H-Area (Tritium Production Facilities) H, U 232-H, 234-H, 238-H H

776-D Waste Stream (773-A 776-5A) Pu, Am 773-A, 776-A Pu, Sr; Pu, Sr, Am

B-Process Waste Stream (773-A) Pu, Am 773-A, Analytical 

Development Division

Pu, Sr, Am

C-Process Waste Stream (773-C) Pu 773-A, Analytical 

Development Division

Pu, Sr, Am
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 66 of 70

Farrell and Findley (1999) location or waste stream

Farrell and Findley (1999) 

analyses

Manual 5Q1.1, 

Procedure 506, 

Revision 5 location

Manual 5Q1.1, 

Procedure 506, 

Revision 5 analyses

F-Wing Boot Waste Stream Am 773-A, Analytical 

Development Division

Pu, Sr, Am

SCH-3-D Waste Stream (773-A) Pu, Am 773-A Pu, Am

776-4A HEPA Filters Waste Stream Pu, Am 776-A Pu, Sr, Am

ADS-1 Waste Stream (Analytical Development System 

Laboratories)

Pu, Am 773-A, Analytical 

Development Division

Pu, Sr, Am

Canyon Waste Stream (773-A CHTS, ADS laboratories) Pu 773-A, Analytical Dev. 

Division, Chem. Tech. 

Section

Pu, Sr, Am

Non-Canyon Waste Stream (773-A non CHTS, ADS 

laboratories) 

Pu, Am 773-A, Int. Waste 

Section, Def. Waste 

Section; 773-A, Mat. 

Science Section; 773A, 

HLC

Pu, Sr; U, Pu; Pu, Sr, Am

Casks Waste Stream (HLW sludge) Pu, Am 773-A Pu, Sr

Casks Waste Stream (HLW supernate) Pu 773-A Pu, Sr

Californium Waste Stream (773-A F Wing Cf facilities) Am 773-A, HLC, Analytical 

Development Division

Pu, Sr, Am

CLAB Waste Stream A (Building 772-1F Laboratory 

Modules L120, L122, L126, L127, and L130)

Pu 772-1F Pu, Sr

CLAB Waste Stream B (772-1F Laboratory Modules 

L125, L128, L129, L132, L137, L156, 772-1F Cells 

(including Cell exhaust system) and 772-1F Filter Room)

Pu 772-1F Pu, Sr

CLAB Waste Stream C (Building 772-1F Laboratory 

Modules L108, L121, L133, L149, L150, L152, Off Gas 

Exhaust, RCO Exhausts, 7721F drain line exhaust, 772-

1F vacuum systems and Building 772F Shielded 

Area/Fan Room, Liquid By-Product Tanks, Laboratory 

Module L162 and the 772-4F Area)

Pu 772-1F Pu, Sr

CLAB Waste Stream D (Building 772-1F Laboratory 

Module L134)

Pu, U 772-1F Pu, Sr

CLAB Waste Stream E (Building 772-F Laboratory 

Modules L131, L138, L139, L146, L147, L154, L155, and 

L171)

Pu, Am 772-F Pu, U, Sr

CLAB Waste Stream F (772-F Laboratory Modules L126, 

L130, L158, L159, and L163)

Pu 772-F Pu, U, Sr
ATTACHMENT A

BIOASSAY FREQUENCIES AND SOURCE TERMS (continued)

Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 67 of 70

Farrell and Findley (1999) location or waste stream

Farrell and Findley (1999) 

analyses

Manual 5Q1.1, 

Procedure 506, 

Revision 5 location

Manual 5Q1.1, 

Procedure 506, 

Revision 5 analyses

CLAB Waste Stream G (772-F/772-4F filter room) Pu, Am 772-F Pu, U, Sr

CLAB Waste Stream H (Building 772-F Laboratory 

Modules L142, L143, L146, L147, L174, L175, and L183)

Pu, Am 772-F Pu, U, Sr

CLAB Waste Stream I (Building 772-F Laboratory 

Modules L110, L111, and L119)

H 772-F Pu, U, Sr

CLAB Waste Stream J (Building 772-F Laboratory 

Modules which is disposed of in the 772-F LSC drum)

Pu, Am, H 772-F Pu, U, Sr

a. For those RWPs requiring respiratory protection due to the presence of particulate contamination such as for disassembly basin workers.
Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 68 of 70

 

ATTACHMENT B 

EXAMPLES OF WHOLE-BODY AND CHEST COUNT REPORTS

LIST OF FIGURES

FIGURE TITLE PAGE

B-1 WBC and chest count report, 1983...........................................................................................69

B-2 WBC and chest count report, 1998...........................................................................................70
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ATTACHMENT B 

EXAMPLES OF WHOLE-BODY AND CHEST COUNT REPORTS

Figure B-1. WBC and chest count report, 1983 (SRS 1995). 
Document No. ORAUT-RPRT-0091 Revision No. 00 Effective Date: 06/10/2019 Page 70 of 70

ATTACHMENT B 

EXAMPLES OF WHOLE-BODY AND CHEST COUNT REPORTS

Figure B-2. WBC and chest count report, 1998 (SRS 1975–2018).