Page 1 of 54

DOE Review Release 09/192023 

Bounding Intakes of Exotic Radionuclides at 

Los Alamos National Laboratory

ORAUT-RPRT-0101 Rev. 01

Effective Date: 08/30/2023

Supersedes: Rev. 00

Subject Expert(s): James M. Mahathy and Richard E. Merrill

Document Owner 

Approval: Signature on File

James M. Mahathy, Document Owner

Approval Date: 08/09/2023

Concurrence: Signature on File

Pat McCloskey, Objective 4 Manager

Concurrence Date: 08/08/2023

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 08/09/2023

Approval: Signature on File

Timothy D. Taulbee, Associate Director for Science

Approval Date: 08/30/2023

FOR DOCUMENTS MARKED AS A TOTAL REWRITE OR REVISION, 

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

New Total Rewrite Revision
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 2 of 54

 

PUBLICATION RECORD

EFFECTIVE

DATE

REVISION

NUMBER DESCRIPTION

03/01/2022 00 New report to address an issue from the Advisory Board on 

Radiation Worker Health regarding the ability to bound dose for 

exotic radionuclides for Los Alamos National Laboratory energy 

employees from 1996 through 2005 using surface contamination 

survey data, air monitoring data, and personnel contamination 

monitoring to assure that doses for unmonitored workers are less 

than 100 mrem. Incorporates formal internal and NIOSH review 

comments. Training required: As determined the Objective Manager. 

Initiated by Michael S. Kubiak and authored by James M. Mahathy.

08/30/2023 01 Revision initiated to correct self-identified errors discovered while 

screening documents used to generate Tables 3-1 through 3-5, and 

A-2 through A-7. The errors consisted of large area swipes, direct 

reading surveys, external radiation surveys, and radiological work 

permit related contamination and air monitoring surveys that were 

mistakenly entered. There were also duplicates of some surveys that 

were entered as well as some that should have been entered that 

were missed originally. Added per year to many of the 100 mrem 

occurrences throughout the report. Incorporates formal internal and 

NIOSH review comments. Constitutes a total rewrite of the 

document. Training required: As determined the Objective Manager.

Initiated by Pat McCloskey and authored by James M. Mahathy.

TRADEMARK INFORMATION

KimwipesTM is a trademark of Kimberly-Clark Worldwide, Inc. in the United States and/or other 

countries.

Masslinn® is a registered trademark of PGI Polymer, Inc. in the United States and/or other countries.

All other trademarks are the property of their respective owners.
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 3 of 54

 

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ............................................................................................................... 4

1.0 Introduction .............................................................................................................................. 6

1.1 Purpose........................................................................................................................ 7

1.2 Scope........................................................................................................................... 8

2.0 Radiological Control................................................................................................................. 8

2.1 Workplace Controls ...................................................................................................... 9

2.2 Workplace Monitoring................................................................................................... 9

2.3 Worker Self-Monitoring............................................................................................... 11

2.3.1 Portal Monitors............................................................................................. 12

2.3.2 Evidence of Portal Monitoring Use ............................................................... 15

3.0 Contamination Survey and Air Monitoring Data in Technical Areas 3, 48, and 53 .................. 18

3.1 Technical Area 3......................................................................................................... 23

3.2 Technical Area 48....................................................................................................... 24

3.3 Technical Area 53....................................................................................................... 25

3.4 Summary of Technical Area Evaluation...................................................................... 26

4.0 Conclusions ........................................................................................................................... 26

References ........................................................................................................................................ 28

ATTACHMENT A SUPPORTING TABLES.................................................................................. 35

LIST OF TABLES

TABLE TITLE PAGE

2-1 Table 2-2, LANL RadCon Manual summary of contamination values with action levels ......... 10

2-2 PCM use, 1996 to 2005 ......................................................................................................... 13

2-3 HFM use, 1996 to 2005.......................................................................................................... 14

2-4 Some documents with results of portal monitors .................................................................... 15

3-1 Monitoring data by TA............................................................................................................22

3-2 Monitoring data by year.......................................................................................................... 22

3-3 Breakdown of smear results above lower limits...................................................................... 23

3-4 Breakdown of results above upper surface contamination limits............................................. 23

3-5 Air concentrations above alpha and beta limits ...................................................................... 23

A-1 Smear and air monitoring source documents ......................................................................... 36

A-2 Smear results exceeding contamination limits, TA-3 .............................................................. 40

A-3 Air monitoring results exceeding airborne contamination limits, TA-3 ..................................... 43

A-4 Smear results exceeding contamination limits, TA-48 ............................................................ 47

A-5 Air monitoring results exceeding airborne contamination limits, TA-48................................... 49

A-6 Smear results exceeding contamination limits, TA-53 ............................................................ 50

A-7 Air monitoring results exceeding airborne contamination limits, TA-53................................... 52
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 4 of 54

ACRONYMS AND ABBREVIATIONS

1LSA service area in MPF-7, Room 200

1LTC linear accelerator target crypt, MPF-7

ALI annual limit on intake

Bq becquerel

CA Controlled Area

CAM continuous air monitor

CED committed effective dose

C.F.R. Code of Federal Regulations

cm centimeter

CMR Chemistry and Metallurgy Research

cpm counts per minute

DAC derived air concentration

DOE U.S. Department of Energy

dpm disintegrations per minute

DU depleted uranium

ER-1 Experimental Area Room 1

ER-2 Experimental Area Room 2

F fast (absorption type)

FP fission product

FP-2 flight path 2

HFM hand-and-foot monitor

HI hazard index

hr hour

ICRP International Commission on Radiological Protection

LANL Los Alamos National Laboratory

LANSCE Los Alamos Neutron Science Center

m meter

MAPs mixed activation products

MDA minimum detectable activity

MFAPs mixed fission and activation products

MFPs mixed fission products

min minute

mR milliroentgen

mrem millirem

NDA no detectable activity

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

ORAUT Oak Ridge Associated Universities Team
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 5 of 54

PCM personnel contamination monitor

PSR Proton Storage Ring

RadCon radiological control

RBA Radiological Buffer Area

RCA Radiological Control Area

RCT Radiological Control Technician

RLW radioactive liquid waste

RWP radiation work permit

S slow (absorption type)

SEC Special Exposure Cohort

SNM special nuclear material

SRDB Ref ID Site Research Database Reference Identification (number)

Sv sievert

TA Technical Area

TGT target

UCNI Unclassified Controlled Nuclear Information

WNR Weapons Neutron Research Facility

yr year

§ section or sections
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 6 of 54

1.0 INTRODUCTION

On April 3, 2008, the National Institute for Occupational Safety and Health (NIOSH) received a 

Special Exposure Cohort (SEC) petition for the Los Alamos National Laboratory (LANL) in Los 

Alamos, New Mexico. The petition, SEC-00109, requested that a class be added to the SEC for 

service support workers (which includes but is not limited to security guards, firefighters, laborers, 

custodians, carpenters, plumbers, electricians, pipefitters, sheet metal workers, ironworkers, welders, 

maintenance workers, truck drivers, delivery persons, radiation technicians, and area work 

coordinators) who worked in any operational Technical Area (TA) with a history of radioactive material 

use at LANL from January 1, 1976, through December 31, 2005 [NIOSH 2012]. 

In Revision 1 of the SEC-00109 petition evaluation report, NIOSH defined a single class of employees 

for which NIOSH cannot estimate radiation doses with sufficient accuracy. The class included

[NIOSH 2012, p. 2]:

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

contractors and subcontractors who worked at the Los Alamos National Laboratory in 

Los Alamos, New Mexico from January 1, 1976 through December 31, 1995, for a 

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

this employment or in combination with work days within the parameters established for 

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

The dose reconstruction limitations identified for the specified class period included the inability to 

bound unmonitored intakes of exotic alpha emitters, fission products (FPs), and activation products.

NIOSH [2012] defined “exotic radionuclides” as being everything other than 234/235/238U, 238/239Pu, 3

H, 241Am, and 137Cs.

NIOSH selected the December 31, 1995, end date for the class based on its presumption that by 

January 1, 1996, LANL would have been in full compliance with 10 Code of Federal Regulations

(C.F.R.) Part 835, Occupational Radiation Protection, § 402 and 702, which stated in 1993 [U.S. 

Department of Energy (DOE) 1993, pp. 35, 37]: 

§ 835.402 Individual monitoring. 

(c) For the purpose of monitoring individual exposures to internal radiation, internal dose 

evaluation programs (including routine bioassay programs) shall be conducted for: 

(1) Radiological workers who, under typical conditions, are likely to receive 0.1 rem 

(0.001 sievert) or more committed effective dose equivalent, and/or 5 rems (0.05 sievert) 

or more committed dose equivalent to any organ or tissue, from all occupational 

radionuclide intakes in a year.

§ 835.702 Individual monitoring records.

(a) Records shall be maintained to document doses received by all individuals for whom 

monitoring was required pursuant to § 835.402 and doses received during planned 

special exposures, accidents, and emergency conditions.

The 10 C.F.R. Part 835 rule became effective on January 13, 1994, and required full compliance by 

January 1, 1996 [DOE 1993, p. 9]. 

The 1993 edition of 10 C.F.R. Part 835 [DOE 1993] incorporated the recommendations of 

International Commission on Radiological Protection (ICRP) Publications 26 and 30 for the calculation 

of doses [ICRP 1977, 1979]. In 2007, DOE revised the rule to incorporate the newer 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 7 of 54

 

recommendations of ICRP Publications 60 and 68 [ICRP 1991, 1995]. With this update to the 

calculated dose came a change in terminology: the dose of interest became committed effective dose 

(CED). The Energy Employees Occupational Illness Compensation Program Act of 2000 applies this 

later system of dose assessment, so it is used for all calculations in this document. Unless specified 

otherwise, the term “dose” in this document refers to the CED.

1.1 PURPOSE

This report addresses an issue from the Advisory Board on Radiation Worker Health about the ability 

to bound dose for exotic radionuclides for LANL workers from 1996 through 2005 using surface 

contamination survey data, air monitoring data, and personnel contamination monitoring to comply 

with 10 C.F.R. Part 835 [DOE 1993]. 

During deliberations after designation of the SEC class for 1976 through 1995, the LANL Work Group 

questioned the ability of NIOSH to bound doses from exotic radionuclides; these include short-lived 

activation and spallation products from the Los Alamos Neutron Science Center (LANSCE; TA-53) 

and mixed fission products (MFPs) in TAs 3 and 48 after 1995. NIOSH maintains that, by complying 

with 10 C.F.R. Part 835 [DOE 1993], LANL monitored all workers with a potential to receive in excess 

of 100 mrem/yr. NIOSH has indicated in previous papers and presentations to the LANL Work Group 

that it does not rely solely on 10 C.F.R. Part 835 compliance for the conclusion that unmonitored 

workers were unlikely to have received intakes resulting in greater than 100 mrem/yr [NIOSH 2019, 

pp. 19–21].

The LANL radiological control program was designed to comply with 10 C.F.R. Part 835 [DOE 1993] 

but with an intended outcome that unmonitored individuals would be unlikely to receive doses greater 

than 100 mrem/yr. The Oak Ridge Associated Universities (ORAU) Team (ORAUT) discusses the 

tenets and requirements of that program in this report with the focus on limiting exposure to 

nonplutonium radionuclides. These radionuclides include exotic radionuclides and heavy elements 

such as 227Ac, 237Np, 241Am, 244Cm, and thorium. Emphasis is placed on workers doing routine work, 

such as guards and custodians, and actions taken during contamination incidents. That latter 

emphasis is supplemented with an analysis of data from surface contamination surveys, air 

monitoring, and incidents to demonstrate program effectiveness.

In addition, NIOSH has a substantial amount of internal dosimetry data for LANL workers. These data 

show that intakes for monitored workers from 1996 to 2005 were generally less than 100 mrem/yr, 

and doses for unmonitored workers would likely have been even lower [ORAUT 2009]. NIOSH found 

no evidence that unmonitored workers received doses above the 10 C.F.R. Part 835 monitoring limit

[DOE 1993]. 

During LANL Work Group deliberations, routine work monitoring has been described as monitoring for 

plutonium, uranium, and tritium. Such routine work is defined as work not done under a radiation work 

permit (RWP) and that involved workers such as guards and custodians. After the November 29,

2018, LANL Work Group meeting, NIOSH and the ORAU Team determined that additional surface 

contamination survey data and air monitoring data were needed to support the position that the areas 

where exotic radionuclides were handled were well monitored for contamination [NIOSH 2018]. Three 

TAs where exotic radionuclides are known to have been handled were selected for review: the South 

Mesa Site (TA-3) containing Chemistry and Metallurgy Research (CMR); the Meson Physics Facility 

(TA-53) containing the LANSCE; and the Radiochemistry Site (TA-48) [LANL 1995, pp. 25, 68, 125]. 

In 2019, the ORAU Team captured some surface contamination survey data and air monitoring data 

from these three TAs for the period from January 1, 1996, to December 31, 2005. These data were 

primarily gross alpha and gross beta air concentrations and swipe surface contamination results. The 

ORAU Team produced a QA outline and data entry instructions to facilitate the use of these data 

[ORAUT 2023a]. The ORAU Team compared the data from the first and second data entries and 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 8 of 54

 

resolved differences [ORAUT 2023b]. Section 3.0 discusses the data from the three TAs, the 

assessment methods, and the results. NIOSH makes no claim that these data are complete. The goal 

of this report was to produce a qualitative analysis of these data.

1.2 SCOPE

This report:

• Discusses the LANL radiological control program,

• Uses examples of routine airborne and surface contamination monitoring data from monitoring 

programs in areas where exotic radionuclides and radionuclides other than plutonium were 

handled at LANL from 1996 through 2005 to demonstrate that LANL maintained exposures to 

less than 100 mrem/yr, and

• Discusses the use of worker self-monitoring with portal monitors by LANL Health Physics to 

screen workers for contamination when leaving contaminated work locations.

2.0 RADIOLOGICAL CONTROL

LANL Health Physics operated a comprehensive radiological control program through the entirety of 

the evaluated period, 1996 to 2005. The program included workplace controls, workplace monitoring, 

radiation worker training, worker self-monitoring, and worker external and internal monitoring and 

RWPs. 

Classification of potential contamination areas is as follows:

• Contamination Area. Any area, accessible to individuals, where removable surface 

contamination levels exceed or are likely to exceed the removable surface contamination 

values specified in appendix D of 10 C.F.R. Part 835 [DOE 1993], but do not exceed 100 times 

those values.

• Airborne Radioactivity Area. Any area, accessible to individuals, where:

– The concentration of airborne radioactivity, above natural background, exceeds or is 

likely to exceed the derived air concentration (DAC) values listed in appendix A or 

appendix C of this part; or

– An individual present in the area without respiratory protection could receive an intake 

exceeding 12 DAC-hours in a week.

• Radiological Buffer Area (RBA). Intended to provide boundaries to minimize the spread of 

contamination and to limit doses to general employees who have not been trained as 

radiological workers.

• Controlled Area (CA). Any area to which access is managed by or for DOE to protect 

individuals from exposure to radiation and/or radioactive material. 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 9 of 54

 

2.1 WORKPLACE CONTROLS

LANL incorporated engineering controls to protect workers from both external and internal radiation 

exposure [Hoover 2021a]. These controls were designed to limit potential doses of radiation to 

workers to 100 mrem/yr. Examples of these controls included:

• Facility design, 

• Laboratory hoods,

• Laboratory gloveboxes,

• Hot cells,

• Shielding,

• Ventilation systems, and

• Closed entry to beam lines. 

2.2 WORKPLACE MONITORING

Workplace monitoring was a linchpin used by LANL Health Physics to ascertain the effectiveness of 

workplace controls and compliance with 10 C.F.R. Part 835 [DOE 1993]. By January 1, 1996, the 

health physics field monitoring and contamination control programs at LANL were well established

and formalized with more than 60 procedures addressing various aspects of radiological protection as 

well as an established process for tracking and notifying staff of revisions [Rodriguez 1996a,b]. These 

procedures covered program administration, exposure and contamination control, monitoring, 

instrumentation, protective equipment, emergency response, and the as low as is reasonably 

achievable program.

In addition to sitewide procedures, area-specific routine monitoring instructions were an important part 

of the radiological control program at facilities where radioactive materials were handled and stored. 

The survey locations and frequencies helped to define the “safety envelope” for a facility. For 

example, the stated purpose of the ESH-1 / TA-3 CMR Building Wing 2 Routine Monitoring 

Instructions was to provide survey frequencies for ESH-1 Radiological Control Technicians (RCTs) 

and Health Protection Technicians to use in operating the radiological control program at TA-3 

[Costigan et al. 2000]. This document defines the routine monitoring tasks of the RCTs assigned to 

TA-3 and delineates responsibilities. Routine surveys are described with survey frequencies ranging 

from daily to annually. These instructions also specify types of routine external radiation surveys and

air monitoring, which include annual continuous air monitor (CAM) system calibration, monthly 

performance tests, and daily operability checks. LANL published similar routine monitoring 

instructions for each technical area. Additional examples of these instructions for the three technical 

areas evaluated in Section 3.0 are for TA-3 [Montoya 2004; Lesses and Montoya 2005], TA-48 

[Costigan 1997; LANL 2000a] and TA-53 [Salazar 2005]. LANL Health Physics maintained the same 

level of monitoring across the site where radiological operations were conducted. An example of 

routine monitoring instructions for other areas included in this report is TA-55 radiation monitoring 

instructions (memorandum to UNCI-ESH-1 at TA-55 [Stokes 2000]) used at TA-55.

Routine surveys were a primary way in which LANL demonstrated to DOE that radiological operations 

were being conducted in a manner that did not compromise the health and safety of workers or 

threaten the environment [Hoover 2021a]. By procedure, “A surface shall be considered contaminated

if either the removable or total radioactivity is detected above the levels in Table 2-2” [Hoover 2021a, 
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p. 13]. Table 2-2 of the LANL Radiological Control Manual (RadCon Manual) is reproduced below in 

Table 2-1. Further, by procedure, “If an area cannot be decontaminated promptly, then it shall be 

posted by ESH-1 as specified in 10 CFR 835. For area surveys where more than 10% of the total 

number of samples (swipes, smears, or instrument measurements) exceed Table 2-2 values, the 

affected area shall be decontaminated and/or posted accordingly” [Hoover 2021a, p. 13]. Health 

Physics either decontaminated areas of surface contamination or covered them. By procedure, 

routine area contamination monitoring was performed weekly, monthly, quarterly, semiannually, and 

annually [Hoover 2021a]. 

Table 2-1. Table 2-2, LANL RadCon Manual summary of contamination values with action levels

[Hoover 2021b, p. 4].

Summary of contamination values

Nuclidea

Removableb,c

(dpm/100 cm2)

d

Total

(fixede + removablec) 

(dpm/100 cm2)

d

Natural U, 235U, 238U, and associated decay products 1,000 alpha 5,000 alpha

Transuranics, 226Ra, 228Ra, 230Th, 228Th, 231Pa, 227Ac, 125I20 500

Natural Th, 232Th, 90Sr, 223Ra, 224Ra, 232U, 126I, 129I, 131I, 133I200 1,000

Beta-gamma emitters (nuclides with decay modes 

other than alpha emission or spontaneous fission) 

except 90Sr and others noted abovef

1,000 beta-gamma 5,000 beta-gamma

Tritium organic compounds, surfaces contaminated 

by HT [elemental tritium (tritiated gas)], HTO [tritiated 

water], and metal tritide aerosols

10,000 10,000

a. The values in this table apply to radioactive contamination deposited on, but not incorporated into, the 

interior of the contaminated item. For purposes of this table only, it is assumed that tritium 

contamination deposits onto the surface but is not incorporated into the interior of the contaminated 

item. This table does not apply to personnel contamination. → Where contamination by both alphaand beta-gamma-emitting nuclides is present, the limits established for the alpha- and beta-gammaemitting nuclides apply independently. 10 CFR 835, Appendix D

b. The amount of removable radioactive material per 100 cm2 of surface area should be determined by 

first swiping the area with dry filter paper or soft absorbent paper while applying moderate pressure 

and then assessing the amount of radioactive material on the swipe with an appropriate instrument of 

known efficiency. (Note: the use of dry material may not be appropriate for tritium.) 10 CFR 835, Appendix D

→ For objects with a surface area less than 100 cm2, the entire surface should be swiped, and the 

activity per unit area should be based on the actual surface area. 10 CFR 835, Appendix D → Except for 

transuranics, 228Ra, 227Ac, 228Th, 230Th, 231Pa, and alpha emitters, it is not necessary to use swiping 

techniques to measure removable contamination levels if direct scan surveys indicate that the total 

residual contamination levels are below the values for removable contamination. 10 CFR 335, Appendix D

c. The “removable” and “total” levels may be averaged over 1 m2 provided the maximum activity in any 

area of 100 cm2 is less than three times the values in Table 2-2. For purposes of averaging, any 

square meter of surface shall be considered to be above the activity guide G if (1) from measurements 

of a representative number n of sections it is determined that 1/n ∑n Si ≥ G, where Si is the dpm/100 

cm2 determined from measurement of section i; or (2) it is determined that the sum of the activity of all 

isolated spots or particles in any 100-cm2 area exceeds 3 G. 10 CFR 335, Appendix D

d. As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive 

material as determined by correcting the counts per minute (cpm) observed by an appropriate 

detector for background, efficiency, and geometric factors associated with the instrumentation. At 

LANL, the instrument is calibrated so that the meter reading will directly correspond to the alpha or 

beta surface emission rate. A nominal conversion to activity in dpm is possible by multiplying the 

instrument contact reading in cpm by a factor of 2.

e. When measuring fixed contamination during a survey, the active area of the probe used must be 

taken into account. For example, if the active area is 100 cm2 and the nuclide is natural uranium, then 

the 5000-dpm α/100-cm2 limit will apply. For a 40-cm2 probe, 2000 dpm α would be the limit because 

of the reduced active area of the probe.

f. This category of radionuclides includes mixed fission products [MFPs], including the Sr-90 that is 

present in them. It does not apply to Sr-90 that has been separated from the other fission products or 

mixtures in which the Sr-90 has been enriched. 10 CFR S35, Appendix D
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According to 10 C.F.R. § 835.403(a), DOE required monitoring of airborne radioactivity to be 

performed: (1) where an individual is likely to receive an exposure of 40 or more DAC-hr in a year 

(2% of an annual limit on intake [ALI]), or (2) as necessary to characterize the airborne radioactivity

[DOE 1993; Fanning and Keith 2001]. LANL used a hazard index (HI) approach to define need for air 

monitoring. In general, an HI less than 1 indicated a low hazard potential from airborne radioactivity 

and no air monitoring was prescribed. An HI between 1 and 100 indicated a low to moderate airborne 

potential and general air monitoring was prescribed. Note that an HI of 2 corresponds to a potential 

intake of 2% of an ALI. Air monitoring was performed on daily and weekly frequencies and included

real-time sampling. The LANL radiological control program also used continuous air monitoring to 

identify airborne contamination. The ORAU Team has access to many incident records of CAM 

alarms. CAM alarms allowed LANL to respond quickly to airborne radiation areas, which in turn

helped to reduce surface contamination and prevented prolonged exposure to contaminated areas. 

An analysis of some LANL routine surface contamination and air monitoring results is presented in 

Section 3.0 to help evaluate the effectiveness of workplace controls. 

2.3 WORKER SELF-MONITORING

The requirement for workers exiting areas suspected of contamination to self-monitor was another key 

tenet of the LANL radiological control program in the period of evaluation. Hoover [2021a, p. 13] 

states:

1. Personnel exiting Contamination Areas, High Contamination Areas, Airborne 

Radioactivity Areas, and Radiological Buffer Areas or Controlled Areas established 

for contamination control shall frisk for contamination as required by Article 338. This 

does not apply to personnel exiting areas containing only radionuclides, such as 

tritium, that cannot be detected using hand-held or automatic frisking equipment.

2. Monitoring for contamination should be performed using frisking equipment that 

under laboratory conditions can detect total contamination of at least the values 

specified in Table 2-2. Use of automatic monitoring units that meet the above 

requirements is encouraged.

3. Personnel found with detectable contamination on their skin, personal clothing, or 

company-issued clothing other than noble gases or natural background radioactivity 

should be promptly decontaminated as described in Article 541.

The radiological protection program provided fixed instruments for personal contamination monitoring 

in each TA. Attachment A of the LANL RadCon Manual stated [Hoover 2021a, p. 14]:

1. Personnel shall perform a whole-body frisk [survey themselves] under the following 

conditions:

a. Immediately upon entry into an uncontaminated area after leaving existing 

Contamination Areas, High Contamination Areas, and Airborne Radioactivity 

Areas;

b. As directed by the radiological work permit, the ESH-1 RCT, or the area exit 

posting.

2. In addition to the above, personnel exiting a Controlled Area or Radiological Buffer 

Area containing Contamination, High Contamination or Airborne Radioactivity Areas 

should, at a minimum, perform a hand and foot frisk. The frisk is optional if the 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 12 of 54

 

Controlled Area or Radiological Buffer Area exit is immediately adjacent to the 

location where the existing worker has already performed a whole-body frisk.

3. Where frisking cannot be performed at the exit from Contamination Areas, High 

Contamination Areas, and Airborne Radioactivity Areas due to high background 

radiation levels, personnel shall perform the following:

a. Remove all protective equipment and clothing at the exit.

b. Proceed directly to the nearest designated monitoring station.

c. Conduct whole-body-frisk.

4. Personnel frisking shall be performed after removal of protective equipment and 

before washing or showering.

Attachment A of the LANL RadCon Manual stated that personnel should take actions including the 

following in response to a contamination alarm [Hoover 2021a, p. 16]:

5. Response to a personnel contamination monitor alarm should include the following 

actions:

a. Remain in the immediate area.

b. Notify ESH-1 personnel and line supervision.

c. Take actions that may be available to minimize cross-contamination, such as 

putting a glove on a contaminated hand.

2.3.1 Portal Monitors

LANL maintained a large and comprehensive inventory of instrumentation for monitoring individuals 

and areas in accordance with 10 C.F.R. Part 835 [DOE 1993]. These included fixed and portable 

instruments appropriate for the wide variety of radiological activities at LANL. Portal monitors 

consisted of personnel contamination monitors (PCMs) and hand-and-foot monitors (HFMs). 

Radiation protection instruments were calibrated in house at LANL. Table 2-2 lists PCMs used in TAs; 

Table 2-3 lists HFMs [Hoover 2021a]. These tables provide additional support showing that LANL 

Health Physics operated a comprehensive radiological control program through workplace monitoring

and worker self-monitoring. Section 2.3.2 provides examples of LANL Health Physics’ responses to 

alarms on these monitors.
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Table 2-2. PCM use, 1996 to 2005.a,b

Model HS# TA Building Location

PCM-1B 8505 3 29 Wing 9

PCM-2 6421 3 29 Wing 2

PCM-2 7145 3 29 Wing 2

PCM-2 9995 3 29 Wing 2

PCM-2 6422 3 29 Wing 2

PCM-2 7147 3 29 Wing 3

PCM-2 7143 3 29 Wing 4

PCM-2 7144 3 29 Wing 4

PCM-2 6411 3 29 Wing 5

PCM-2 7150 3 29 Wing 5

PCM-2 6420 3 29 Wing 5

PCM-2 6419 3 29 Wing 7

PCM-2 7148 3 29 Wing 7

PCM-2 7149 3 29 Wing 7

PCM-2 9999 3 29 Wing 7

PCM-2 6412 3 29 Wing 9

PCM-2 7146 3 29 Wing 9

PCM-1B 8502 3 102 Not available

PCM-1B 8503 3 66 S102

PCM-1B 8501 21 312 Not available

PCM-1B 8501 54 G Not available

PCM-1B 8507 54 1009 Not available

PM-6A 6503 48 RC-1 Not available

PM-6A 6504 48 RC-1 S Hallway

PCM-1B 4868 48 RC-1 Main/North Hallway

PCM-1B 5004 48 RC-1 Hot Cell Area

PCM-1B 5005 48 RC-1 Hot Cell Area

PCM-1B 8508 48 RC-1 Machine Shop

PCM-2 11501 48 RC-1 ARF Entrance

PCM-2 11502 48 RC-1 Alpha Wing

PCM-1B 4867 50 RC-1 Decontamination

PCM-1B 8501 50 37 Not available

PCM-1B 5007 50 37 Not available

PCM-2 6423 50 69 Not available

PCM-2 9995 50 69 Not available

PCM-2 9997 50 1 Main

PCM-2 11503 50 1 Main

PCM-2 11504 50 1 Main

PCM-2 11505 50 1 Main

PCM-1B 4870 53 Proton Storage Ring Shack Not available

PCM-1B 5006 53 Area A West

PCM-1B 5009 53 Area A East

PCM-1B 8503 53 ER-2 Not available

PCM-1B 5010 53 1L Service Shack

PCM-1B 8509 53 M111B / ER-2 Not available

PCM-2 9999 53 PRAD Area Not available

Ludlum 53 PN 1232409 53 ER-2 Not available

PCM-2 6413 55 Not available Station 118

PCM-2 6414 55 Not available Station 118

PCM-2 6415 55 Not available Station 116

PCM-2 6416 55 Not available Station 116

PCM-2 6417 55 Not available Station 116

PCM-2 6418 55 Not available Station 116
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 14 of 54

 

Model HS# TA Building Location

PCM-2 11506 55 Not available Station 116

PCM-2 11507 55 Not available Station 116

PCM-2 11508 55 Not available Station 116

a. Source: Hoover [2021a].

b. ARF = Actinide Research Facility; HS# = instrument number prefix; PRAD = Proton 

Radiography Facility.

Table 2-3. HFM use, 1996 to 2005.a,b

Model HS# TA Building Location

HFM-6 7027 3 29 Wing 7

HFM-6 7028 3 29 Wing 4

HFM-6 7029 3 29 Wing 2

HFM-6 7034 3 29 Wing 4

HFM-6 7035 3 29 Wing 4

HFM-6 7038 3 29 Wing 2

HFM-6 7039 3 29 Wing 9

HFM-7 5240 3 29 Wing 3 / Wing 2

HFM-7 5241 3 29 Wing 7

HFM-7 5242 3 29 Wing 4

HFM-7 5243 3 29 Wing 5 / Wing 9

HFM-7 5244 3 29 Wing 3

HFM-7 5245 3 29 Wing 5

HFM-7 5246 3 29 Wing 9 / Wing 2

HFM-7 8711 3 29 Wing 5

HFM-7 8713 3 29 Wing 4

HFM-7 8714 3 29 Wing 3 / Wing 9

HFM-7 8715 3 29 Wing 7

HFM-7 8716 3 29 Wing 9

HFM-7 9323 3 29 Wing 9

HFM-7 5250 3 66 D106

HFM-7 8705 3 66 B2A

HFM-7 8706 3 66 K105

HFM-7 8707 21 150 Not available

HFM-7 5249 48 RC-1 Basement

HFM-7 8703 48 RC-1 Machine shop

HFM-7 8704 48 RC-1 Alpha Wing

HFM-7 8708 48 RC-1 ARF

HFM-7 8709 50 69 Not available

HFM-7 8718 50 69 Not available

HFM-6 7034 54 33 Not available

HFM-7 5247 54 Various Not available

HFM-7 8506 54 Various Not available

HFM-7 8507 54 Various Not available

HFM-7 8702 54 412 Not available

HFM-7 8707 54 231 Not available

HFM-7 8710 54 Various Not available

HFM-7 8717 54 Various Not available

HFM-7 9324 54 Various Not available

HFM-8 180 units in TA-55-4 55 Lab exits Not available

a. Source: Hoover [2021a].

b. ARF = Actinide Research Facility. 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 15 of 54

 

2.3.2 Evidence of Portal Monitoring Use

Multiple examples of workers alarming PCMs and HFMs are present in LANL documents; some of 

these documents are listed in Table 2-4. The following examples help demonstrate that LANL not only 

complied with 10 C.F.R. Part 835 [DOE 1993], but also had a coordinated system to protect workers.

Table 2-4. Some documents with results of portal monitors.a

Title

SRDB

Ref ID

Radiation Incident Report Notification Checklists – August 1996 178426

Notification Checklists 1999 55552

Radiological Incident Reports January–May 1999 55553

Radiological Incident Report TA-53 Building 7 - 1999 178757

Contamination of Room 408 With Tc-99 in TA-48 55578

Radiological Incident of Employee Foot and Shoe Contamination in TA-48 55580

Radiological Incident of Employee Wing 300 in TA-48 55583

Radiological Incident of Employee Contamination in 400 Wing of TA-48 55585

Radiological Incident of Employee Contamination in Alpha Wing of TA-48 55587

Radiological Incident Reports TA-48 2003 59508

Radiological Incident Reports TA-54 Area G 2002 61765

Radiation Protection Work Control Breakdown Results in Unplanned Uptake 164550

Radiological Incident Reports TA-48 1999 176857

UCNI - RWPs TA-55 2001 (Set 6 Box 2-0691 - Ten Notable RWPs) 178195

UCNI - Radiological Incident Reports TA-55 32-63 178413

Index of Radiological Incidents for TA-55 1999 178420

Radiological Incident Reports LANL 1997 178425

UCNI - Radiological Incident Reports TA-55 64-95 178435

UCNI - Radiological Incident Reports TA-55 96-127 178446

UCNI - Radiological Incident Reports TA-55 128-155 178447

UCNI - Radiological Incident Reports TA-55 1-31 178453

Radiological Incident Reports TA-3 CMR 2000 178739

Worksheets Logbook Notes and Shift Attendance List TA-53 2001 178799

Radiological Incident Reports TA-3 Building 29 December 2003–December 2004 181206

Radiological Incident Reports TA-48 January, March, May–December 1998 181219

Radiological Incident Reports TA-3 Building 29 February–April, October 2000 181222

UCNI - Radiological Incident Reports TA-55 (1-201) 1997 183593

UCNI - RWPs TA-55 CY1998 (One Notable RWP) 183625

a. SRDB Ref ID = Site Research Database Reference Identification (number); UCNI = uncontrolled classified nuclear 

information.

On [redacted], a worker alarmed the PCM-2 in [redacted]. Contamination levels of 50,000 dpm alpha 

and 15,000 dpm beta were detected on the worker’s [redacted]. Contamination of 3,000 dpm alpha 

was removed with Masslinn. Collected nasal smears were reported as no detectable activity (NDA) 

[LANL 1999a, p. 2].

On [redacted], after bagging contaminated filters in [redacted], a worker set off the alarm on a PCM-2. 

Contamination of approximately 6,400 to 6,900 dpm beta was detected on the [redacted] of the 

worker’s [redacted]. The worker was decontaminated using soap and water. Collected nasal smears 

were reported as NDA [LANL 2000b, pp. 31–57]. No bioassay was performed on the worker for this 

event; however, the worker participated in routine bioassay. The worker was monitored for both 239

Pu 

and 241Am on September 6, 2002; results were reported as less than minimum detectable activity 

(MDA) [LANL 1963–2004]. 

On [redacted], a worker frisking in [redacted] set off the alarm on a fixed monitor for the wing. Health 

Physics personnel arrived after the monitor alarmed. They monitored the worker’s [redacted], which 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 16 of 54

 

were contaminated to about 500 dpm alpha with 60 dpm removable alpha contamination. On 

examination, Health Physics found alpha contamination in Room 5120. The [redacted] of [redacted]

workers were collected. Those workers performed whole-body frisks using an HFM-7. Nasal smears 

were collected from each worker from those rooms; all were negative [LANL 2000c, pp. 11–28].

On [redacted], a worker alarmed an HFM-7 in [redacted]. One [redacted] was decontaminated. No 

area contamination was found. The cause of contamination was considered to be a hot particle. Nasal 

smears were collected from each worker from those rooms; all were negative [LANL 2000c, pp. 2–11].

On [redacted], a worker set off a PCM at the exit to [redacted]. Health Physics confirmed [redacted]

contamination of 52,000 dpm/100 cm2 beta and [redacted] contamination of 26,000 dpm/100 cm2

beta. The worker’s [redacted] was immediately decontaminated, and the [redacted] were removed for 

analysis and decontaminated. A collected nasal smear was negative. Later analysis of the 

contamination on the [redacted] revealed the radionuclides were 82/85Sr [LANL 1999b, pp. 86–104].

On [redacted], a worker leaving [redacted] set off an HFM. Health Physics confirmed alpha 

contamination of the right [redacted] and personal [redacted] with the highest reading being 700 

counts alpha. The [redacted] was decontaminated. The worker was able to clear HFM-6 and exit the 

contaminated area. The floors of [redacted] were decontaminated [LANL 2002a]. While not required 

for this particular contamination, the worker was on routine bioassay for plutonium and uranium. 

Results of routine bioassay performed after the contamination event were less than the MDAs 

reported for plutonium and uranium.

On [redacted], a worker alarmed the PCM-1B in [redacted]. The worker’s [redacted] were 

contaminated with 4,800 dpm beta. Subsequent surveys also detected 47,000 dpm on the worker’s 

[redacted] dosimeter. Collected nasal swipes were reported as NDA [LANL 2003a, pp. 9–20].

On [redacted], a [redacted] to [redacted] alarmed the PCM-1B. Contamination was found on the 

[redacted] of a [redacted] and the isotope was identified as 188W. The activity was 46,000 dpm and not 

removable with tape. The [redacted] and other personnel performed no work with radioactive 

materials. Masslinn swipes and direct surveys of the floor, hoods, and office sign in the area detected 

no contamination. It was determined that the contamination was brought to LANL on the [redacted]

from a facility in Texas. The [redacted] was washed to NDA. No bioassay was performed for this 

visitor [LANL 2003a, pp. 482–490].

Portal monitors were extremely beneficial in the LANSCE (TA-53). LANL [2001a] documents many 

examples of PCM use. The following is an account recorded on August 12, 2001 (p. 19), in which 

1LSA is a service area in MPF-7, Room 200; 1LTC is the linear accelerator target crypt, MPF-7; ER-1 

is Experimental Area Room 1; ER-2 is Experimental Area Room 2; FP-2 is flight path 2; and REB is a 

room in the Proton Storage Ring (PSR), MPF-28: 

While waiting for beam to stabilize between 1900 and 2000 hrs we prepared the FP-2 

grid; documentation; and staged instruments. At 2000 hrs the beam was stabilized @ 

56uA and we started the survey. At 2030 hrs the 2080 failed and we had to get another 

instrument, and then the beam dropped off until approx 2100 hrs. From 2100 hrs to 2300 

hrs we finished the FP-2, shutter open survey in both ER-1 and ER-2 with 60 survey 

points. In ER-1 the highest reading was survey point #1 next to the shield bulk head 

which read 10 mR/hr gamma and 29 mrem neutron. The remaining readings in ER-1 

were <5mR gamma + neutron. On top of FP#2 there is a lot of background radiation from 

the hole in the roof from the 1LSA and from the RLW [radioactive liquid waste] drain line: 

These reading were 180 mR/hr @contact, 100 mR/hr @ 30cm, 30 mR/hr @ 1m from the 

roof, 8 mR/hr from the RLW line, and the general background is approx 10 mR/hr: As 

the radiation levels from 1LSA [may] increase, I believe the south section of FP#2 should 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 17 of 54

 

be roped off to prevent entry without an RCT to verify dose rates in that area, FP#2 has 

a safety fence on the west side between FP#3, but needs a safety fence on the East 

side between FP#1. No readings were taken in the gap between FP#1 and FP#2. A 

proper ladder also needs to be installed to allow access to the top of FP#2. In ER-2 all 

reading [sic] were <0.2 mR/hr gamma and 0 mrem neutron: No reading [sic] were taken 

on top of FP#2 in ER-2 because there was no safety tape or fall barriers. All personnel 

surveyed NDA through the ER-2 PCM.

On [redacted], work was being performed in [redacted] on the target water system in the [redacted]. 

After the work was completed, the worker removed his anti-contamination clothing and proceeded to 

the PCM which alarmed. RCTs were notified and the worker was surveyed and found to have 

contamination levels on [redacted] of 800 to 3,000 cpm. Contamination was also found on the 

worker’s [redacted] with levels up to 1,200 cpm. The RCTs also checked all areas where 

contamination might have been tracked and no contamination was detected. The worker was 

decontaminated and nasal smears were taken with a combined result of 208 dpm beta; the action 

level for beta combined was 500 dpm. Health Physics analyzed the smears with a photon detector;

lutetium and hafnium isotopes were noted [LANL 1999c, pp. 13–26]. While not required by the results 

of the nasal smears Health Physics monitored the worker by whole body counting on February 4, 

1999, with radionuclides 22Na, 7

Be, 54Mn, 11C, 13N, and 152Eu all reported as less than MDA [LANL 

1963–2004]; neither lutetium nor hafnium were identified in the whole body count. 

On [redacted], the ESH-1 Field Office received a call informing RCTs that a worker alarmed the PCM1B in [redacted] while doing a self survey before exiting [redacted]. An RCT responded to the scene 

and found beta/gamma contamination on the [redacted] (380,000 dpm), [redacted] (1.6 × 106 dpm), 

and [redacted] (4,000 dpm) of the worker. The worker donned a [redacted] and [redacted] and was 

escorted to the MPF-502 Decontamination Facility. The worker’s [redacted] were removed, bagged, 

and retained by ESH-1. The [redacted] and [redacted] were successfully decontaminated. While not 

required by the results of the nasal smears, Health Physics monitored the worker by whole body 

counting on February 10, 1999, with radionuclides 22Na, 7

Be, 54Mn, 11C, 13N, and 152Eu all reported as 

less than MDA. The area was secured and posted until Health Physics was able to do a complete 

survey of the area [LANL 1999c, pp. 27–34; 1963–2004]. 

On [redacted], a worker alarmed a PCM-1B in [redacted] after using the monitor. The worker’s 

[redacted] was contaminated to approximately 86,000 dpm beta/gamma. The worker was escorted to 

a decontamination trailer and the [redacted] was successfully decontaminated with soap and water

[LANL 1999c, pp. 48–53]. The worker participated in the routine bioassay program.

On [redacted], a worker alarmed the PCM-1B while exiting [redacted]. [Redacted] contamination of 

48,000 dpm beta activity was detected around the [redacted] and [redacted]. The worker was 

successfully decontaminated using soap and water. A result of collected [redacted] smears showed 

42 dpm beta was detected in the [redacted] [LANL 1999c, pp. 66–82]. Health Physics monitored the 

worker by whole body counting on May 14, 1999, with 173Hf reported as less than MDA [LANL 1963–

2004].

On [redacted], a worker alarmed the PCM-1B while exiting [redacted]. Skin contamination of 47,000 

dpm beta/gamma was detected on the [redacted]. The cause of contamination was considered to be a 

hot particle. The [redacted] was successfully decontaminated using a mild cleanser and Kimwipes

[LANL 1999c, pp. 87–92]. The ORAU Team has no evidence of bioassay results for this worker.

On [redacted], a worker exiting [redacted] alarmed a PCM. Health Physics determined contamination 

of the worker’s [redacted] with a hot spot (contamination area greater than neighboring regions of the 

area) on the [redacted] reading 1,200 dpm beta and 200 dpm alpha. On investigation, Health Physics 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 18 of 54

 

determined the cause of the alarm was radon contamination (NIOSH assumes this meant from radon 

progeny) and released the worker [LANL 2001a, p. 92].

LANL Health Physics documented instances where workers failed to comply with the requirements for 

using portal monitors or left a controlled area with a PCM alarm, as indicated in two instances for 

which Radiological Incident Reports were initiated [LANL 1999d, pp. 19–20]. Although the use of 

personnel self-monitoring was a component of the radiological control program, it was not the only 

component. The program relied on each component to keep doses to 100 mrem/yr or less, including 

but not limited to contamination surveys, air monitoring, and worker training. Rare instances of 

noncompliance with PCM use requirements by workers does not prevent NIOSH from performing 

dose reconstructions.

Additionally, many Occurrence Reporting and Processing System reports were reviewed for the 

period 1996 through 2005. There were 386 reports sitewide for the period. Of these, 127 

(approximately 33%) were from TA-3, 39 (approximately 10%) were from TA-48, and 14 

(approximately 4%) were from TA-53.

3.0 CONTAMINATION SURVEY AND AIR MONITORING DATA IN TECHNICAL AREAS 3, 48, 

AND 53

To evaluate the effectiveness of the LANL radiological control program, the ORAU Team analyzed 

example survey and air monitoring data. The ORAU Team selected results of routine smear surveys 

in three areas, TA-3, TA-48, and TA-53, and routine air sampling results for the same TAs. The three 

TAs were selected because exotic radionuclides were known to have been handled there from 

January 1, 1996, to December 31, 2005. This exercise was not intended to be all inclusive of all areas 

at LANL that handled exotic radionuclides. Although data from 1996 through 2005 are represented, 

the ORAU Team does not have data for each TA for every year and the data are not distributed 

equally among the TAs. Documents with routine smear and air monitoring data used for this report are 

listed in Attachment A, Table A-1.

Routine surface contamination documents typically contained laboratory results for many smears 

taken within a building on a weekly or quarterly frequency. Information extracted from each surface 

contamination monitoring document includes sample collection date, TA and building number, survey 

frequency, number of results, number of gross alpha results exceeding 20 dpm/100 cm2

, number of 

gross alpha results exceeding 400 dpm/100 cm2

, number of gross beta results exceeding 

1,000 dpm/100 cm2

, and number of gross beta results exceeding 3,200,000 dpm/100 cm2. The limits

of 400 dpm/100 cm2 and 3,200,000 dpm/100 cm2 were derived in ORAUT [2021] and are explained in 

the equations provided later in this section. These two limits are referred to as “ORAU Team criteria.” 

The 20 dpm/100 cm2 and 1,000 dpm/100 cm2 were standard action levels as indicated in the LANL 

RadCon Manual [Hoover 2021b, Table 2-2] (Table 2-1 in this report). 

The purpose of compiling these data was twofold:

1. To determine whether the routine surface contamination survey programs conducted during 

the period of interest (1996 through 2005) in the areas where exotic radionuclides could have 

been handled were robust. The numbers of surveys and smears per survey were tallied. Note

that the data in this report include results from routine surveys only. 

2. To assess the routine surface contamination status in these areas and to determine the 

likelihood that unmonitored workers in these areas could have received significant intakes due 

to resuspended surface contamination. Contamination areas are defined in 10 C.F.R. Part 835 

as having removable alpha contamination exceeding 20 dpm/100 cm2 or removable beta 

contamination exceeding 1,000 dpm/100 cm2 [DOE 1993]. The number of smears per survey 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 19 of 54

 

that exceeded this threshold was tallied. LANL worked to maintain removable alpha and beta 

contamination to those values under the LANL RadCon Manual [Hoover 2021b, Table 2-2] 

(Table 2-1 in this report).

Areas with readings above the limits listed in Table 2-2 of the LANL RadCon Manual for 

surface contamination areas were posted and/or resurveyed, as demonstrated in a 1997 

memorandum [LANL 1997a, p. 2]:

SUBJECT: THIRD QUARTER SMEAR SURVEY FOR TA-53

Attached is the 1997 Third Quarter Smear Survey for TA-53. The survey 

information is provided on a smear data/map format. All smears were taken 

during the months of August and September 1997.

A 100cm2 smear was taken at each survey location using NuCon smears. The 

smears are then taken to the TA-53 ESH-1 Satellite Count Lab located in MPF-1, 

Laboratory Operations Building (L. O. B.) and are counted on the Canberra 2400 

alpha/beta proportional counter and an NaI gamma counter. All data is corrected 

for background and counter efficiencies and reported in disintegrations per 

minute (dpm). Areas with readings above release limits listed in Table 2-2 of the 

LANL RadCon Manual for Surface Contamination Areas are posted appropriately 

and/or resurveyed. [emphasis added] 

The purpose of tallying the number of smears per survey exceeding 400 dpm/100 cm2 alpha 

and 3,200,000 dpm/100 cm2 beta was to assess the likelihood that unmonitored individuals 

could have received intakes resulting in doses exceeding 100 mrem/yr. For this assessment, 

227Ac type F was assumed to represent the worst-case alpha emitter and 90Sr type S was 

assumed to represent the worst-case beta emitter. The rationale behind these numbers is 

given later in this section. 

Routine air monitoring documents typically contained laboratory results for air filters exchanged on a 

weekly or other periodic frequency for multiple locations within a building. Information extracted from 

each air monitoring document included sample collection date, TA and building number, survey 

frequency, number of results, number of gross alpha results exceeding 0.04 dpm/m3 and if the 

measurement had sufficient sensitivity to detect 0.04 dpm/m3

, and the number of gross beta results 

exceeding 320 dpm/m3

. Like with the surface contamination data, the purpose of compiling these air 

monitoring data was twofold:

1. To determine whether the routine air monitoring programs during the period of interest (1996 

through 2005) in the areas where exotic radionuclides could have been handled were robust. 

This is why the numbers of surveys and samples were tallied. As with the surface 

contamination data, the air monitoring results in this report only include results from routine air 

monitoring contained in the analyzed set of data. 

2. To assess the routine air contamination status in these areas and to determine the likelihood 

that unmonitored workers in these areas could have received significant intakes due to

airborne contamination. The purpose of tallying gross alpha results exceeding 0.04 dpm/m3

and gross beta results exceeding 320 dpm/m3 was to assess the likelihood that unmonitored 

individuals could have received intakes resulting in doses exceeding 100 mrem/yr. As with the 

surface contamination assessment, 227Ac type F was assumed to represent the worst-case 

alpha emitter and 90Sr type S was assumed to represent the worst-case beta emitter. The 

rationale behind these numbers is given later in this section. 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 20 of 54

 

Under 10 C.F.R. Part 835, DOE did not require bioassay programs for workers who were unlikely, 

under typical conditions, to receive 100 mrem in a year [DOE 1993]. However, to ascertain if LANL 

controlled internal doses from exotic radionuclides, the ORAU Team used limiting assumptions with 

the analysis of monitoring data. These assumptions include:

• Worker breathing rate = 0.02 m3

/min; 

• Worker occupancy = 2,000 hr/yr (100% occupancy); and

• Surface contamination resuspension factor = 1.0 × 10-6 m-1 (90th-percentile maximum 

likelihood) [Abu-Eid et al. 2002]. 

In previous LANL documents and discussions, including evaluation reports, Work Group meetings 

and associated papers, the following radioactive materials have been identified as having data 

deficiencies potentially affecting the feasibility of dose reconstruction: MFPs and mixed activation 

products (MAPs), 241Am (separated from plutonium), 232Th, 230Th, 227Ac, 231Pa, 237Np, and 244Cm. Of 

these, considering the dose conversion factors presented in ICRP Publication 68 [ICRP 1995], NIOSH 

has determined that 227Ac type F (assigned to the alpha category because of its progeny) and 90Sr 

type S are the alpha and beta emitters handled at LANL that would result in the highest dose 

consequences per unit activity of material. In this evaluation therefore, when evaluating gross alpha 

and gross beta survey results when the specific radionuclides are unknown, NIOSH assumed 227Ac 

type F (alpha) or 90Sr type S (beta). This ensured that the worst case scenario was being evaluated. 

The ORAU Team derived projected doses from direct air monitoring or resuspended surface 

contamination using effective dose coefficients for inhalation from ICRP Publication 68 [ICRP 1995] 

for alpha- (227Ac type F) and beta-emitting (90Sr type S) radionuclides. Air concentration values 

(dpm/m3

) that would result in 100 mrem CED per year using the above assumptions are presented in 

ORAUT [2021]. The selected radionuclides resulted in the lowest calculated air concentration value 

for their respective categories. Type S 90Sr was chosen as the more limiting beta emitter because it 

has a lower air concentration than type F even though type F was the likely material type to be found 

on site at LANL. Note that these assumptions result in a conservative estimate of the workplace 

values, indicating a potential for intakes resulting in 100 mrem/yr. The selected radionuclides and 

associated material types are not likely to be the predominant component of an encountered mixture, 

and a worker does not typically spend 2,000 hours in a single location for a year. Doses based on 

more realistic assumptions at these airborne activity and surface contamination levels will be smaller. 

The following equations from ORAUT [2021] were used to determine the 100-mrem values:

(3-1) 100

1

2

D C AC

HC RF

× = × ××

where:

AC100 = air concentration (Bq/m3

) of 227Ac type F or 90Sr type S that would result in 

100 mrem/yr

D = dose of 100 mrem/yr

C1 = 0.00001 Sv/mrem conversion factor

H = 2,000 hr/yr worked

C2 = 60 min/hr conversion factor

R = breathing rate of 0.02 m3

/min

F = ICRP effective dose coefficient of 6.3 × 10-4 Sv/Bq for 227Ac or 7.7 × 10-8 Sv/Bq for 

90Sr
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 21 of 54

 

Note: To convert to dpm/m3, the 6.6 × 10-4 Bq/m3 result for 227Ac is multiplied by 60 dpm/Bq yielding 

0.04 dpm/m3 and the 5.4 Bq/m3 for 90Sr is multiplied by 60 dpm/Bq yielding 320 dpm/m3

. 

(3-2) 1 2

100

3 4

DC C SC

F R H C RF C

× × = ××× × ×

where:

SC100 = resuspended surface contamination (Bq/100cm2

) of 227Ac type F or 90Sr type S that 

would result in 100 mrem/yr from inhalation

D = dose of 100 mrem/yr

C1 = 0.00001 Sv/mrem conversion factor

C2 = constant value of 100 to adjust result to 100 cm2 to account for surface smear area

F = ICRP effective dose coefficient of 6.3 × 10-4 Sv/Bq for 227Ac or 7.7 × 10-8 Sv/Bq for 

90Sr 

R = breathing rate of 0.02 m3

/min

H = 2,000 hr/yr worked

C3 = 60 min/hr conversion factor

RF = resuspension factor of 1 × 10-6 m-1 

C4 = 10,000 cm2/m2 conversion factor

Note: To convert to dpm/100 cm2

, the 6.6 Bq/100 cm2 for 227Ac is multiplied by (60 dpm/Bq) yielding 

400 dpm/100 cm2 and the 5.4 × 104 Bq/100 cm2 for 90Sr is multiplied by (60 dpm/Bq) yielding 

3,200,000 dpm/100 cm2

. 

Note: The overall difference between equations 3-1 and 3-2 is a factor of 10,000. This is the product 

of the 1 × 10-6 m-1 resuspension factor and the conversion from cm2 to 100 cm2 for surface 

contamination.

Table 3-1 summarizes monitoring results for all three TAs as a whole (TA-3, TA-48, and TA-53) and 

individually. Table 3-2 summarizes them by year. A review of the data in Tables 3-1 and 3-2 shows 

that more than 98% of all smears and 99% of air monitoring results used in the report were below the 

lower limits for alpha of 20 dpm/100 cm2 and 0.04 dpm/m3

, respectively. While evaluated data do not 

represent a random sample or all survey data, these results suggest workplaces were well controlled 

in terms of radioactive contamination. However, the results over those limits must be considered to 

determine if any could have contributed to internal doses greater than 100 mrem/yr. These data are 

provided in Table 3-3. 

To determine if resuspended surface contamination could have led to worker doses greater than 

100 mrem/yr, the ORAU Team looked at the number of alpha and beta results exceeding the upper 

limits (400 dpm/100 cm2 alpha and 3,200,000 beta dpm/100 cm2

). A total of 26 alpha surveys 

exceeded 400 dpm/100 cm2 in TA-3, or 0.3% of all spots surveyed in TA-3. Sixteen of the 26 spots 

were found in the Sigma complex with uranium being the radionuclide of interest in 1999. A total of 

four alpha surveys exceeded 400 dpm/100 cm2 in TA-48, or 0.05%: one smear each in Rooms 309, 

312, 338 Hot Cell, and 409, all where alpha-emitting radionuclides were handled. A total of two alpha 

surveys exceeded 400 dpm/100 cm2 in TA-53, or 0.01%. While the ORAU Team does not have 

specific documentation specifying the controlled contamination designations of areas in these three 

areas, all these areas were controlled under routine monitoring. An example is provided for each TA

as follows: TA-3 [Costigan et al. 2000], TA-48 [Costigan 1997], and TA-53 [Salazar 2005]. Summary 

data on the number of smears that exceeded upper limits are given in Table 3-4. The 
 

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

0

8/30/2023 Page 22 of 54

Table 3-1. Monitoring data by TA.1

1 Tables 3-1 through 3-5 report surface contamination survey data and air monitoring data from these three TAs for the period from January 1, 1996, to December 31, 

2005, captured only during 2019. These tables demonstrate the effectiveness of the LANL contamination control programs.

TA

No. of 

survey 

results

Alpha smear 

results

exceeding

20 dpm/100 cm2

Alpha smear

results

exceeding

400 dpm/100 cm2

Beta smear

results

exceeding

1,000 dpm/100 cm2

Beta smear 

results exceeding 

3,200,000 dpm/100 cm2

No. of air 

monitoring 

results

Alpha air 

results 

exceeding

0.04 dpm/m3

Beta air 

results 

exceeding

320 dpm/m3

All 39,639 723 32 188 0 66,419 504 17

3 7,794 552 26 113 0 61,378 179 0

48 7,709 55 4 19 0 3,120 29 0

53 24,136 116 2 56 0 1,921 296 17

Table 3-2. Monitoring data by year.

Year

No. of 

survey 

results

Alpha smear 

results 

exceeding

20 dpm/100 cm2

Alpha smear 

results 

exceeding

400 dpm/100 cm2

Beta smear

results

exceeding

1,000 dpm/100 cm2

Beta smear

results exceeding 

3,200,000 dpm/100 cm2

No. of air 

monitoring 

results

Alpha air 

results 

exceeding 

0.04 dpm/m3

Beta air 

results 

exceeding 

320 dpm/m3

All 39,639 723 32 188 0 66,419 504 17

1996 3,937 61 2 28 0 186 51 1

1997 6,004 64 5 9 0 1,741 174 12

1998 587 0 0 0 0 1,617 46 2

1999 8,191 440 17 134 0 1,480 38 1

2000 4,624 54 5 8 0 12,940 60 1

2001 1,423 5 0 0 0 13,757 50 0

2002 497 0 0 0 0 12,045 72 0

2003 6,750 1 0 3 0 265 0 0

2004 5,007 90 2 3 0 13,437 8 0

2005 2,619 8 1 3 0 8,951 5 0
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 23 of 54

Table 3-3. Breakdown of smear results above lower limits.

TA

Alpha smear 

results 

exceeding

20 dpm/100 cm2

Beta smear results 

exceeding

1,000 dpm/100 cm2

Total 

number of 

area smearsa

Total results 

exceeding 

lower limit 

(alpha+beta)

% of single TA 

results 

(alpha+beta)a

All 723 188 39,639 911 1.2

3 552 113 7,794 665 4.27

48 55 19 7,709 74 0.48

53 116 56 24,136 172 0.36

a. The total number of smears is multiplied by 2 to represent alpha and beta results.

ORAU Team also tallied the number of air monitoring results above limits for alpha of 0.04 dpm/m3

and for beta 320 dpm/m3

 (Table 3-5). Results used in this report are evidence that LANL controlled

contamination in routine workplaces. Eight percent of air samples collected in TA-53 exceeded either

alpha or beta limits; however, these results represent samples collected at or around the accelerator 

target or in Experimental Area A where isotope production work was performed in hot cells. Twelve of 

the 17 air sample results exceeding the air concentration beta limit were recorded in 1997 in TA-53 

with spallation activities (see Section 3.3). These locations were not accessible by workers during 

beam generation and as such would not have contributed to intakes.

Table 3-4. Breakdown of results above upper surface contamination limits (100-mrem/yr 

limit).

TA

Alpha results 

exceeding 

400 dpm/100 cm2

Beta results 

exceeding 

3,200,000 

dpm/100 cm2

Total number 

of area 

smears

Total results 

exceeding 

upper limit

% of single 

TA results 

(alpha+beta)a

All 32 0 39,639 32 0.04

3 26 0 7,794 26 0.17

48 4 0 7,709 4 0.03

53 2 0 24,136 2 0.00

a. The total number of smears is multiplied by 2 to represent alpha and beta results.

Table 3-5. Air concentrations above alpha and beta limits.

TA

Alpha air 

results 

exceeding 

0.04 dpm/m3

Beta air 

results 

exceeding

320 dpm/m3

Total number 

of area air 

sample results 

Total results 

exceeding 

limits

% of single 

TA results 

(alpha+beta)a 

All 504 17 66,419 521 0.39

3 179 0 61,378 179 0.15

48 29 0 3,120 29 0.46

53 296 17 1,921 313 8.15

a. The total number of air samples is multiplied by 2 to represent alpha and beta results.

Based on the results above, it is clear that very few surveys exceeded either LANL limits or ORAU 

Team criteria, which indicates LANL had an effective contamination control program. As a reminder, 

workers exiting Contamination Areas, High Contamination Areas, Airborne Radioactivity Areas, RBAs, 

and CAs were required to frisk for contamination. The ORAU Team has provided examples of Health 

Physics response and followups to personnel monitor alarms in Section 2.3.2. 

3.1 TECHNICAL AREA 3 

TA-3 has contained a mixture of LANL activities that include experimental sciences, work with special 

nuclear materials, administrative work, public and corporate access, theoretical studies and

computations, and physical support operations. Many of the major facilities for providing physical 

support such as utilities and maintenance are in TA-3. Much like a university campus, research 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 24 of 54

facilities are scattered throughout the area. These range from small laboratories with bench-scale 

operations to activities involving radioactive materials in the CMR facility in Building 29 [Romero and 

Faust 1992; LANL 1998a].

Survey results for TA-3 were obtained for Building 29 (CMR) and the Sigma Complex (Building 66). 

All smears for alpha plus beta were taken from RBAs or CAs. Alpha surface contamination exceeded 

the lower limit in 552 individually smeared spots of 100 cm2

, and beta surface contamination 

exceeded the lower limit in 113 smears of 100 cm2

. Surface contamination was not found in the same 

location over more than two consecutive surveys. The most contaminated areas were in Building 29 

Room 5023 where actinides were detected on a November 10, 1999 survey. In that survey, 

34 smears exceeded the lower limit of 20 dpm/100 cm2

, and 1 smear exceeded 400 dpm/100 cm2. In 

all, 171 smears revealed surface contamination above the lower limits in Building 29 over all surveys. 

Note that smears were part of an overall survey and that one survey can have many smears. The 

radionuclides used in these locations primarily included actinides and special nuclear material (SNM). 

Three hundred eighty-six smears revealed surface contamination above the lower limits in the Sigma 

Complex (primarily Building 66) where SNM comprised the primary radionuclides of interest. The set 

of individual smears exceeding lower surface contamination limits was 4.27% of the total smears 

available for TA-3 (alpha and beta smears tabulated as individual smears). Smear data for TA-3 are 

given in Attachment A, Table A-2.

Considering the upper limits for alpha and beta surface contamination, the ORAU Team found 

26 spots that exceeded 400 dpm/100 cm2 alpha. No spot surveys exceeded the 

3,200,000 dpm/100 cm2 beta limit (Table 3-1). Sixteen of the 26 spots were found in the Sigma 

Complex with uranium being the radionuclide of interest. The rest were found in Building 29 with 

actinides being the primary source term, and 99.67% of smears were at or below upper surface 

contamination limits. Surveyed spots with readings above the limits listed in Table 2-2 of the LANL

RadCon Manual (Table 2-1 in this report) for surface contamination areas were posted and/or cleaned 

and resurveyed [LANL 1997a, p. 2]. Routine workers such as custodians would not have been 

exposed to these levels of surface contamination over time. They would typically not be monitored if 

their potential dose would not exceed 100 mrem/yr. 

Airborne contamination results exceeding either the alpha or beta airborne contamination limit were 

found on 117 sets of airborne results for TA-3. All these were recorded for Building 29 due to alpha 

radiation exceeding 0.04 dpm/m3

. The most results over the alpha limit were obtained in Wing 5 

(59 results), while the fewest were found in Wing 4 (3 results). In all, 179 individual air monitoring 

results exceeded 0.04 dpm/m3

. The set of individual air monitoring results that exceeded the alpha 

and beta limits in TA-3 is 0.15% of the total air monitoring results (alpha plus beta) available for TA-3; 

results are given in Attachment A, Table A-3.

3.2 TECHNICAL AREA 48

TA-48 is known as the Radiochemistry Site. The facilities at TA-48 support research and development 

in nuclear and radiochemistry. Some measurements of radioactive substances were taken in hot cells 

equipped for remote handling. Although radiochemical operations were conducted primarily in 

Buildings 1, 8, 28, 45, and 107, only Building 1 contained sufficient radioactive materials to be 

considered hazardous because it is a Category 3 hazard based on the potential for only significant, 

localized consequences. During the period of evaluation, the RC-1 building was divided into an office 

wing, light chemistry laboratories for performing low-level radiochemistry, a hot cell complex to 

produce medical radioisotopes, an alpha wing for processing alpha-emitting radioactive and toxic 

materials, a “counting room” complex, and a secure data wing with a classified computer and vault 

containing historical data [LANL 1998a].
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 25 of 54

Activities at Building RC-1 included small-scale radiochemistry in the laboratories area, chemical 

research of high alpha activity materials in the alpha facility, final analysis of samples in the counting 

room, and small-scale production of medical radioisotopes in the hot cells area. The dissolution area 

housed a high-activity chemistry area. The activities conducted there involved the largest amounts of 

beta/gamma radioactivity outside of the hot cells area. Both alpha materials and FPs were handled 

and separated in this building [LANL 1998a].

Surface contamination results exceeding either the lower alpha or beta contamination limit were found 

in 50 surveys performed in TA-48 across 1997, 1999, 2004, and 2005, all in Building RC-1. From 

these 50 surveys, alpha surface contamination was found on 55 individual smears while beta surface 

contamination was found on 19 individual smears. The radionuclides used in these locations primarily 

included actinides and mixed fission and activation products (MFAPs). All smears exceeding the lower 

limits of surface contamination were collected in RBA or CA locations. The set of individual smears 

exceeding lower surface contamination limits is 0.48% of the total smear results available for TA-48; 

results are given in Attachment A, Table A-4.

Considering the upper limits for alpha and beta surface contamination, the ORAU Team found only 

four smeared spots that exceeded 400 dpm/100 cm2 alpha. No spots exceeded 

3,200,000 dpm/100 cm2 beta (Table 3-1). All four surveyed spots were in Building RC-1; 99.9% of 

evaluated smears were at or below upper surface contamination limits. Surveyed spots with readings 

above the limits listed in Table 2-2 of the LANL RadCon Manual (Table 2-1 in this report) for surface 

contamination areas were posted and/or cleaned and resurveyed [LANL 1997a, p. 2]. Routine 

workers such as custodians would not have been exposed to these levels of contamination over time. 

They would typically not be monitored if their potential dose would not exceed 100 mrem/yr. 

Airborne contamination results exceeding either the alpha or beta airborne contamination limit were 

found on 10 sets of airborne results for TA-48. All these were recorded for Building RC-1 around the 

hot cell and supporting rooms. Twenty-nine individual air monitoring results exceeded 

0.04 dpm/m3 alpha. The set of air monitoring results that exceeded the alpha and beta limits in TA-48 

is 0.46% of the total air monitoring results available. These data are presented in Attachment A, 

Table A-5.

3.3 TECHNICAL AREA 53

TA-53 housed the LANSCE. During the period of this evaluation, TA-53 had approximately 

400 buildings and other structures and housed about 800 personnel. That population could have 

increased by several hundred when the linear accelerator was in operation as visiting scientists from 

around the globe came to Los Alamos to monitor and participate in experiments. Site workers were 

protected by shielding, fencing, access controls, sweep procedures, beam shutoff mechanisms, 

monitoring devices, dosimetry, posted safety information, training, administrative controls, and 

emergency response mechanisms [LANL 1998a].

Surface contamination results exceeding either the lower alpha or beta contamination limit were found 

in 42 surveys performed in TA-53. These surveys were collected at the target area, along the beam 

line, and in the beam service area, PSR, and ancillary support facilities. All smeared locations were 

within Health Physics regulated areas that LANL monitored for external exposures and intakes. From 

these 42 surveys, alpha surface contamination was found on 116 smeared spots, and beta surface 

contamination was found on 56 smeared spots. The radionuclides in these locations primarily 

included actinides and MFAPs. The set of individual smears (alpha plus beta) exceeding lower 

surface contamination limits is 0.36% of the total smears available for TA-53; results are given in 

Attachment A, Table A-6.
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 26 of 54

Considering the upper limits for alpha and beta surface contamination, the ORAU Team found two

spots that exceeded 400 dpm/100 cm2 alpha (Table 3-4). No spot survey exceeded the 

3,200,000 dpm/100 cm2 beta; 99.9% of smears were at or below upper surface contamination limits. 

One of the spots in TA-53 was found in the experimental area in MPF-3M, and the other one was

found in the beam target area. None of 24,136 smeared spots exceeded the upper limit for beta.

Surveyed spots with readings above the limits listed in Table 2-2 of the LANL RadCon Manual 

(Table 2-1 in this report) for surface contamination areas were posted and/or cleaned and resurveyed 

[LANL 1997a, p. 2]. Routine workers such as custodians would not have been exposed to these levels 

of surface contamination over time. They would typically not be monitored if their potential dose would 

not exceed 100 mrem/yr. 

For air monitoring samples analyzed for gross alpha and beta contamination, 296 individual air 

monitoring results exceeded 0.04 dpm/m3 alpha, and 17 individual results exceeded the beta limit of 

320 dpm/m3

. The set of air monitoring results that exceed the alpha and beta limits in TA-53 is about 

8.15% of the total available air monitoring results (alpha plus beta). Air monitoring results represent 

sampling at the target area, along the beam line, and at the beam service area, PSR, and ancillary 

support facilities. A majority of these results were reported for Experimental Area A where 

244 individual air monitoring results exceeded 0.04 dpm/m3 alpha and 12 individual results exceeded

the beta limit of 320 dpm/m3

, the latter not unexpected given activation products arising from the 

spallation processes. The set of air monitoring results that exceed the alpha and beta limits in TA-53 

is given in Attachment A, Table A-7.

3.4 SUMMARY OF TECHNICAL AREA EVALUATION

While the analysis included limited survey and air monitoring data for three TAs, results of smear 

surveys and air monitoring demonstrate that LANL controlled radioactive contamination. 

Radionuclides of interest for the period of evaluation were primarily actinides (uranium, plutonium, and 

americium) in all three TAs but included activation and FPs in TA-48 and TA-53.

4.0 CONCLUSIONS

In this report, the ORAU Team has discussed the LANL radiological control program and 

demonstrated that contamination was well controlled in TA-3, TA-48, and TA-53. Data evaluated in 

Section 3.0 shows that LANL controlled routine contamination that could lead to doses greater than 

100 mrem/yr at all three TAs. While data used in the report are not the total set of data collected by 

LANL, the weight of evidence supports the premise that unmonitored doses can be bounded at 

100 mrem/yr. The ORAU Team has shown that LANL operated a radiation protection and control 

program that included the use of portal monitors to identify and remediate workplace radiological 

contamination. 

The ORAU Team criteria defined and discussed in Section 3.0 were developed using conservative 

worst case assumptions. All alpha emitting radionuclides are assumed to be 227Ac type F and all beta 

emitting radionuclides are assumed to be 90Sr type S. Furthermore, it was assumed that areas were 

uniformly contaminated at these levels and that unmonitored workers spent 2,000 hours per year in 

the contaminated areas to receive a dose of 100 mrem/yr. These are bounding, rather than realistic, 

assumptions.

LANL Health Physics responded to even small levels of contamination. When contamination was 

identified through routine monitoring programs, LANL Health Physics took actions to minimize worker 

exposures, such as identifying the source of contamination and either decontaminating the source or 

posting and restricting worker access into such areas. In many cases, the discovery of contamination 

would result in workers being monitored by nasal smears or bioassay. Primary radionuclides of 
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 27 of 54

interest were fission and activation products and actinides (primarily uranium and plutonium) in TA-3 

and TA-48 and spallation products in TA-53.

A crucial part of the LANL radiological control program required workers exiting Contamination Areas, 

High Contamination Areas, Airborne Radioactivity Areas, and RBAs to frisk for contamination. The 

ORAU Team has provided examples of Health Physics’ response and followup to personnel monitor 

alarms in Section 2.3.2. 

The ORAU Team concludes the weight of the evidence clearly indicates that worker doses to 

unmonitored exotic radionuclides would not have exceeded 100 mrem/yr. Doses for workers 

monitored by bioassay can be bounded using bioassay results. Doses for unmonitored workers can 

be bounded at 100 mrem/yr because no evidence was found that would contradict these conclusions. 

Therefore, the conclusion, based on data and facts provided in the report, is that no unmonitored 

workers received a dose above 100 mrem/yr during normal operations.
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 28 of 54

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Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 32 of 54

LANL [2001–2002c]. Air samples TA-3 Building 29 2001 and January 2002. Los Alamos National 

Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180913]

LANL [2002a]. Radiological incident of employee foot and shoe contamination in TA-48. Los Alamos 

National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 55580]

LANL [2002b]. Fixed head air sample results TA-3 CMR. Los Alamos National Laboratory, Los 

Alamos, NM: University of California. [SRDB Ref ID: 178716]

LANL [2002c]. Fixed head air sample results TA-3 Building 29. Los Alamos National Laboratory, Los 

Alamos, NM: University of California. [SRDB Ref ID: 178727]

LANL [2002d]. Air samples TA-3 CMR Building. Los Alamos National Laboratory, Los Alamos, NM: 

University of California. [SRDB Ref ID: 180968]

LANL [2002–2003]. Fixed air samples TA-3 Building 29 Wing 2 January 2002 - January 2003. Los 

Alamos National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180974]

LANL [2003a]. Radiological incident reports TA-48. Los Alamos National Laboratory, Los Alamos, 

NM: University of California. [SRDB Ref ID: 59508]

LANL [2003b]. Smear and semi-annual site surveys TA-53 February, March, June, August - October. 

Los Alamos National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180890]

LANL [2003c]. Smear surveys TA-53 February, March, May - July, August - December. Los Alamos 

National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180862]

LANL [2004a]. Smear surveys TA-3 Building 29 February, July - October. Los Alamos National 

Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 181007]

LANL [2004b]. RWPs TA-3 CY2004. Los Alamos National Laboratory, Los Alamos, NM: University of 

California. [SRDB Ref ID: 181134]

LANL [2004c]. Radiological incident reports TA-3 Building 29 December 2003 - December 2004. Los 

Alamos National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 181206]

LANL [2004d]. Routine monthly direct and smear contamination surveys TA-3. Los Alamos National 

Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 178822]

LANL [2004e]. Fixed head air sample results TA-3 Building 29. Los Alamos National Laboratory, Los 

Alamos, NM: University of California. [SRDB Ref ID: 178820]

LANL [2004f]. Smear surveys TA-48 March, May - July, September, October, December. Los Alamos 

National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180928]

LANL [2004g]. Smear surveys TA-53. Los Alamos National Laboratory, Los Alamos, NM: University of 

California. [SRDB Ref ID: 178821]

LANL [2004h]. HSR-1 surveys TA-53. Los Alamos National Laboratory, Los Alamos, NM: University of 

California. [SRDB Ref ID: 178706]

LANL [2004i]. Air analysis reports TA-53 Building 7. Los Alamos National Laboratory, Los Alamos, 

NM: University of California. [SRDB Ref ID: 178707]
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 33 of 54

LANL [2004–2005a]. Fixed air samples TA-3 Building 29 Wing 7 January 2004 - January 2005. Los 

Alamos National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180939]

LANL [2004–2005b]. Fixed air samples TA-3 Building 29 January 2004 - January 2005. Los Alamos 

National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180976]

LANL [2005a]. LAS, direct and smear surveys TA-3 Building 29 August - December. Los Alamos 

National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180965]

LANL [2005b]. Hot cell radiation and smear surveys TA-48 Building RC-1 January - November. Los 

Alamos National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 180820]

LANL [2005–2006]. Fixed air samples and monthly routine radiological surveys TA-3 Building 29 

January 2005 - January 2006. Los Alamos National Laboratory, Los Alamos, NM: University of 

California. [SRDB Ref ID: 180980]

Lesses E, Montoya B [2005]. Routine monitoring instructions TA-3 CMR Building Wing 2 January - 

December. Los Alamos National Laboratory, Los Alamos, NM: University of California. RMI-48-10, 

December 20. [SRDB Ref ID: 180981]

Montoya B [2004]. Routine monitoring instructions TA-3 CMR Building Wing 3 January - December. 

Los Alamos National Laboratory, Los Alamos, NM: University of California. [SRDB Ref ID: 178819]

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Alamos National Laboratory (LANL) qualified May 29, 2008. Cincinnati, OH: U.S. Department of 

Health and Human Services, Centers for Disease Control and Prevention, National Institute for 

Occupational Safety and Health. SEC-00109 Rev. 1, August 13. [SRDB Ref ID: 165232]

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Institute for Occupational Safety and Health Advisory Board on Radiation and Worker Health Los 

Alamos National Laboratory work group Thursday, November 29. Transcript. Washington, DC: U.S. 

Department of Health and Human Services, Centers for Disease Control, National Institute for 

Occupational Safety and Health. November 29. [SRDB Ref ID: 184934]

NIOSH [2019]. U.S. Department of Health and Human Services Centers for Disease Control National 

Institute for Occupational Safety and Health Advisory Board on Radiation and Worker Health Los 

Alamos National Laboratory (LANL) work group Thursday, July 25. Transcript. Washington, DC: U.S. 

Department of Health and Human Services, Centers for Disease Control, National Institute for 

Occupational Safety and Health. July 25. [SRDB Ref ID: 184933]

ORAUT [2009]. Los Alamos National Laboratory bioassay repository database. Oak Ridge, TN: Oak 

Ridge Associated Universities Team. ORAUT-OTIB-0063 Rev. 00, August 24. [SRDB Ref ID: 73101] 

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Spreadsheet. Oak Ridge, TN: Oak Ridge Associated Universities Team. March 3. [SRDB Ref ID: 

184929]

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Ridge Associated Universities Team. May 19. [SRDB Ref ID: 197547] 

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Oak Ridge, TN: Oak Ridge Associated Universities Team. May 19. [SRDB Ref ID: 197546] 
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Rodriguez P [1996a]. Procedures. Memorandum to P. Hoover. Los Alamos National Laboratory, Los 

Alamos, NM: University of California. April 18. [SRDB Ref ID: 187246] 

Rodriguez P [1996b]. Procedures. Memorandum to P. Hoover. Los Alamos National Laboratory, Los 

Alamos, NM: University of California. July 10. [SRDB Ref ID: 187247] 

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National Laboratory, Los Alamos, NM: University of California. March 23. [SRDB Ref ID: 69340]

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Ref ID: 151760]
Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 35 of 54

ATTACHMENT A 

SUPPORTING TABLES

LIST OF TABLES

TABLE TITLE PAGE

A-1 Smear and air monitoring source documents ......................................................................... 36

A-2 Smear results exceeding contamination limits, TA-3 .............................................................. 40

A-3 Air monitoring results exceeding airborne contamination limits, TA-3 ..................................... 43

A-4 Smear results exceeding contamination limits, TA-48 ............................................................ 47

A-5 Air monitoring results exceeding airborne contamination limits, TA-48................................... 49

A-6 Smear results exceeding contamination limits, TA-53 ............................................................ 50

A-7 Air monitoring results exceeding airborne contamination limits, TA-53................................... 52
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 36 of 54

Table A-1. Smear and air monitoring source documents.

a

Year Title

SRDB 

Ref ID

1996 Air Samples TA-53 1996 176863

1996 Smear Surveys TA-53 May and June 1996 178723

1996 Smear Surveys TA-53 July and August 1996 178740

1996 Smear Surveys TA-53 August–November 1996 178790

1996 Smear Surveys TA-53 March 29–May 17, 1996 180912

1996 Direct and Smear Surveys TA-3 1996 180957

1996 Smear and Contamination Surveys TA-3 1996 180987

1996 Smear Surveys TA-53 February 13–March 29, 1996 and May 10, 1997 180906

1997 Portable Air Samples TA-53 1997 176864

1997 Smear Surveys TA-53 September–November 1997 and January 1998 180852

1997 Air Samples TA-48 Building 1 January–November 1997 180854

1997 Weekly and Monthly Routine Surveys TA-48 Building 1 1997 180884

1997 Smear Surveys TA-53 1996 180893

1997 Smear Surveys TA-53 Third and Fourth Quarter 1997 180905

1997 Smear and Counter Surveys TA-53 April, May, July 1997 180927

1997 Radiation and Contamination Surveys in LANSCE Beam Area 1997 178711

1998 Hot Cell Air Samples TA-48 1998 178786

1998 Smear and Counter Surveys TA-53 January–April 1998 180840

1998 Air Samples TA-48 Hot Cell December 1996–January 1998 180886

1998 Smear and Counter Surveys TA-53 September–November 1998 180947

1998 Fixed Air Samples TA-48 Building 1 1998 181015

1999 Hot Cell Wing Monthly Surveys TA-48 January–November 1999 176856

1999 Smear Surveys TA-53 First, Second, Third Quarter 1999 178731

1999 Hot Cell Wing Air Samples TA-48 1999 178769

1999 Monthly Routine Smear Surveys TA-48 1999 178770

1999 RWPs TA-53 1999 178775

1999 Air, Contamination and Smear Surveys TA-53 June–August 1999 180830

1999 Smear and Counter Surveys TA-53 December 1999 180841

1999 Smear and Counter Surveys TA-53 May, June, July 1999 180843

1999 Smear and Counter Surveys TA-53 January–April 1999 180846

1999 Smear and Counter Surveys TA-53 July–October 1999 180847

1999 Smear and Contamination Surveys TA-3 January 1999–January 2000 180849

1999 Smear Surveys TA-3 January–September, November, December 1999 180850

1999 Smear Surveys TA-3 Building 2008-2010, 1734, 130, SM-65 August–September 1999 180982

1999 Fixed Contamination, Direct, Smear and Nasal Surveys TA-3 Building 29 Wing 5 1999 180992
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 37 of 54

Year Title

SRDB 

Ref ID

1999 Giraffe Air Samples TA-53 1999 180993

1999 RWPs TA-3 CY1999 (Ten Notable RWPs) 183678

2000 Smear Surveys TA-53 2000 176870

2000 Fixed Air Head Results TA-3 CMR 2000 178725

2000 Fixed Head Air Sample Results TA-3 2000 178736

2000 Air Sample Results TA-3 Building 29 2000 178801

2000 Radiological Surveys TA-3 Building 29 2000 178803

2000 Giraffe Air Samples TA-53 2000 178812

2000 Radiological Incident Reports, Nasal Swipes, Smear, LAS and Direct Surveys TA-3 Building 29 180915

2000 Air Samples TA-3 Building 29 Wing 2 December 1999 and January, April–November 2000 180916

2000 Air Samples TA-3 Building 29 2000 180930

2000 Air Samples TA-3 Building 2000 180950

2000 Smear, Counter, Radiation and Contamination Surveys TA-53 April, May, July–September 2000 180971

2000 Fixed Head Air Samples TA-3 Building 29 Wing 4 2000 181009

2000 Smear and Counter Surveys TA-53 February–May 2000 181010

2000 Fixed Head Air Samples TA-3 Building 29 Wing 7 2000 181343

2001 Smear Surveys TA-53 February, March, July, August, October 2001 180863

2001 Fixed Air Samples and Radiological Surveys TA-3 Building 29 January–September 2001 180903

2001 Air Samples and CAM Filter Surveys TA-53 Building 29 2001 180907

2001 Air and Smear Samples TA-3 Building 29 2001 180917

2001 Air Samples TA-3 Building 29 2001 180945

2001 Smear and Counter Surveys TA-53 Building 3 May–December 2001 180949

2001 Air Samples TA-3 Building 29 Wing 7 2001 180986

2001 Air Samples TA-3 Building 29 Wing 5 2001 181005

2002 Fixed Head Air Sample Results TA-3 CMR 2002 178716

2002 Fixed Head Air Sample Results TA-3 Building 29 2002 178727

2002 Smear and LAS Surveys TA-53 March, April, December 2002 180871

2002 Smear and LAS Surveys TA-53 August–December 2002 180875

2002 Smear and Counter Surveys TA-53 January–April 2002 180887

2002 Air Samples TA-3 Building 29 July–October 2002 180896

2002 Air Samples TA-3 Building 29 2001 and January 2002 180913

2002 Air Samples TA-3 CMR Building 2002 180968

2002 Fixed Air Samples TA-3 Building 29 Wing 2 2002 180974

2002 Air Surveys TA-3 Building 29 2002 181011

2002 Smear and LAS Surveys TA-53 May–August, November, December 2002 181027

2002 UCNI - Smear Surveys Performed in TA-3 2002 183590
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

0

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Year Title

SRDB 

Ref ID

2003 Direct, Smear, Radiation Routine Monthly Surveys TA-3 2003 178887

2003 Smear Surveys TA-53 February, March, May–July, August–December 2003 180862

2003 Smear Surveys TA-53 February, March, April 2003 180864

2003 Smear Surveys TA-53 2003 180889

2003 Smear and Semi-Annual Site Surveys TA-53 February, March, June, August–October 2003 180890

2003 Air Samples TA-3 2002 and January 2003 180904

2004 HSR-1 Smear Surveys TA-53 2004 178706

2004 Air Analysis Reports TA-53 Building 7 2004 178707

2004 Direct, Smear, Radiological Surveys TA-3 2004 178817

2004 Fixed Head Air Sample Results TA-3 Building 29 2004 178820

2004 Smear Surveys TA-53 2004 178821

2004 Routine Monthly Direct and Smear Contamination Surveys TA-3 2004 178822

2004 Air Samples TA-48 RC-1 Alpha Wing January–March 2004 180922

2004 Smear and External Radiation Surveys TA-48 Alpha and Dissolving Wings January–March, June, December 2004 180923

2004 Smear Surveys TA-48 March, May–July, September, October, December 2004 180928

2004 Fixed Air Samples TA-3 Building 29 Wing 7 2004 180939

2004 Fixed Air Samples TA-3 Building 29 Wing 5 2004 180941

2004 Fixed Air Samples TA-3 Building 29 2004 180969

2004 Fixed Air Samples TA-3 Building 29 2004 180976

2004 Fixed Head Air Samples TA-3 2004 181006

2004 Smear Surveys TA-3 Building 29 February, July–October 2004 181007

2004 UCNI - RWPs TA-3 February–December 2004 181147

2004 Radiological Incident Reports TA-3 Building 29 2004 181206

2004 RWPs TA-3 CY2004 181134

2005 Hot Cell Radiation and Smear Surveys TA-48 Building RC-1 January–November 2005 180820

2005 Air Samples TA-3 Building 29 January 2005–January 2006 180900

2005 Routine Monthly Direct, Smears and Tritium Contamination Surveys TA-3 Buildings 180909

2005 Fixed Air Samples TA-3 Building 29 Wing 3 180943

2005 Daily RCA Exit Large Area Swipe, Smear and Direct Surveys and RWPs TA-3 Building 29 Wing 3 2005 180948

2005 Smear Surveys TA-53 January, March, April, September, December 2005 180961

2005 LAS, Direct and Smear Surveys TA-3 Building 29 August–December 2005 180965

2005 Fixed Air Samples and Monthly Routine Radiological Surveys TA-3 Building 29 2005 180980

2005 Smear and Radiological Surveys TA-53 Building 54 July 2005 180990

2005 Smear, LAS and Radiological Surveys TA-53 January, February, May, September, October 2005 180991

1995–2005 Smear and Air Samples TA-3 Building 29 Wing 7 1995-2005 180834

1996–1997 Smear and Counter Surveys TA-53 February and March 1996 and March 1997 180955
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 08/30/2023 Page 39 of 54

Year Title

SRDB 

Ref ID

1997–1998 Direct and Smear Surveys TA-3, TA-48, TA-59 December 1997–December 1998 181014

1999–2000 Smear and Counter Surveys TA-53 December 1999–February 2000 181013

2004–2005 Fixed Air Samples TA-3 Building 29 October 2004–January 2005 180964

a. RCA = Radiological Control Area; UCNI = uncontrolled classified nuclear information.
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Table A-2. Smear results exceeding contamination limits, TA-3.

Date

Building 

number Location

Primary 

source

Number 

of 

results

Exceeded 

lower 

limit alpha

Exceeded 

upper limit 

alpha

Exceeded 

lower 

limit beta

Exceeded 

upper 

limit beta Source

Start 

page

06/26/1996 66 D5A SNM 30 1 0 0 0 LANL 1996a 99

12/17/1997 2009 Rm-132 SNM 100 2 1 0 0 LANL 1997–1999 10

01/05/1999 66 B-100, 107 SNM 20 4 0 0 0 LANL 1999e 207

01/11/1999 66 B-100, 107 SNM 20 8 0 2 0 LANL 1999e 203

01/19/1999 66 B-107, B-3 Vault SNM 20 3 0 0 0 LANL 1999e 199

01/25/1999 66 B-100, 107, B-3 Vault SNM 20 7 0 0 0 LANL 1999e 195

01/28/1999 66 B-100 SNM 90 13 1 1 0 LANL 1999–2000a 174

02/01/1999 66 B-100, B-3 Vault SNM 20 18 3 11 0 LANL 1999e 191

02/09/1999 66 B-100, B-3 Vault SNM 20 10 3 5 0 LANL 1999e 187

02/17/1999 66 B-100, B-3 Vault SNM 20 19 5 11 0 LANL 1999e 183

02/24/1999 66 B-100, B-3 Vault SNM 20 8 0 3 0 LANL 1999e 179

02/26/1999 66 B-100 SNM 75 2 0 0 0 LANL 1999–2000a 159

03/01/1999 66 B-100, B-3 Vault SNM 20 8 0 2 0 LANL 1999e 175

03/09/1999 66 B-100, B-3 Vault SNM 20 11 0 5 0 LANL 1999e 171

03/15/1999 66 B-100, B-3 Vault SNM 20 10 0 0 0 LANL 1999e 166

03/22/1999 66 B-100, B-3 Vault SNM 20 9 0 0 0 LANL 1999e 162

03/29/1999 66 B-100 SNM 20 3 0 1 0 LANL 1999e 158

03/30/1999 66 B-101 DUa 80 1 0 0 0 LANL 1999–2000a 20

04/05/1999 66 B-100 SNM 20 2 0 1 0 LANL 1999e 154

04/12/1999 66 B-100 SNM 20 3 0 0 0 LANL 1999e 150

04/19/1999 66 B-100, B-3 Vault SNM 20 4 0 1 0 LANL 1999e 146

04/26/1999 66 B-100, B-3 Vault SNM 20 3 0 1 0 LANL 1999e 142

05/03/1999 66 B-100, B-3 Vault SNM 20 5 0 1 0 LANL 1999e 138

05/10/1999 66 B-100 SNM 20 3 0 2 0 LANL 1999e 134

05/17/1999 66 B-100 SNM 20 5 0 0 0 LANL 1999e 126

05/24/1999 66 B-100 SNM 20 5 0 2 0 LANL 1999e 122

06/01/1999 66 B-100, B-3 Vault SNM 20 7 0 3 0 LANL 1999e 130

06/07/1999 66 B-100 SNM 20 3 0 1 0 LANL 1999e 118

06/14/1999 66 B-100, B-3 Vault SNM 20 7 0 1 0 LANL 1999e 115

06/15/1999 66 B-101, 108 SNM 110 2 0 0 0 LANL 1999–2000a 124

06/24/1999 66 B-100, B-3 Vault SNM 20 7 0 2 0 LANL 1999e 111

06/28/1999 66 B-100 SNM 20 3 0 0 0 LANL 1999e 107

07/06/1999 66 B-100, B-3 Vault SNM 20 7 0 2 0 LANL 1999e 103

07/12/1999 66 B-100, B-3 Vault SNM 20 5 0 0 0 LANL 1999e 99

07/14/1999 66 B-100 SNM 110 3 0 1 0 LANL 1999–2000a 107
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

0

8/30/2023 Page 41 of 54

Date

Building 

number Location

Primary 

source

Number 

of 

results

Exceeded 

lower 

limit alpha

Exceeded 

upper limit 

alpha

Exceeded 

lower 

limit beta

Exceeded 

upper 

limit beta Source

Start 

page

07/19/1999 66 B-100, B-3 Vault SNM 20 8 0 0 0 LANL 1999e 95

07/26/1999 66 B-100 SNM 20 3 0 0 0 LANL 1999e 91

08/02/1999 66 B-100, B-3 Vault SNM 20 5 0 0 0 LANL 1999e 87

08/09/1999 66 B-100, B-3 Vault SNM 20 7 0 1 0 LANL 1999e 83

08/16/1999 66 B-100, B-3 Vault SNM 20 7 1 1 0 LANL 1999e 79

08/24/1999 66 B-100 SNM 20 4 0 0 0 LANL 1999e 75

08/25/1999 66 B-100 SNM 98 1 0 0 0 LANL 1999–2000a 90

08/30/1999 66 B-100 SNM 20 4 0 0 0 LANL 1999e 71

09/07/1999 66 B-100, B-3 Vault SNM 20 4 0 0 0 LANL 1999e 67

09/13/1999 66 B-100, B-3 Vault SNM 20 6 0 1 0 LANL 1999e 63

09/20/1999 66 B-100 SNM 20 3 0 1 0 LANL 1999e 59

09/21/1999 66 B-100 SNM 98 2 0 0 0 LANL 1999–2000a 73

09/27/1999 66 B-100 SNM 20 3 0 1 0 LANL 1999e 43

09/27/1999 29 5130 Actinides 50 1 0 0 0 LANL 1999f 89

09/29/1999 29 5116, 5126 Actinides 56 4 0 0 0 LANL 1999f 84

10/04/1999 66 B-100 SNM 20 3 0 2 0 LANL 1999e 55

10/12/1999 66 B-100 SNM 20 3 0 0 0 LANL 1999e 51

10/18/1999 66 B-100 SNM 20 3 0 0 0 LANL 1999e 47

10/25/1999 66 B-100 SNM 20 4 0 3 0 LANL 1999e 39

11/01/1999 66 B-100, B-3 Vault SNM 20 7 1 5 0 LANL 1999e 25

11/03/1999 29 5114, 5116, 5125 Actinides 56 4 0 0 0 LANL 1999f 79

11/08/1999 66 B-100, B-3 Vault SNM 20 7 0 5 0 LANL 1999e 35

11/10/1999 29 5023 Actinides 40 34 1 0 0 LANL 1999f 2

11/15/1999 66 B-100, B-3 Vault SNM 20 10 0 3 0 LANL 1999e 30

11/22/1999 66 B-100, B-3 Vault SNM 20 10 0 2 0 LANL 1999e 21

11/24/1999 29 Wing 5 Actinides 27 4 1 0 0 LANL 1999f 16

11/29/1999 66 B-100, B-3 Vault SNM 20 8 0 1 0 LANL 1999e 7

12/07/1999 66 B-100, B-3 Vault SNM 20 12 0 6 0 LANL 1999e 17

12/13/1999 66 B-100, B-3 Vault SNM 20 17 0 10 0 LANL 1999e 13

12/20/1999 66 B-100, B-3 Vault SNM 20 11 0 9 0 LANL 1999e 11

12/21/1999 66 B-100 SNM 98 9 1 0 0 LANL 1999–2000a 2

01/03/2000 66 B-100, B-3 Vault SNM 20 10 0 3 0 LANL 1999e 2

01/25/2000 66 B-100 SNM 98 6 1 0 0 LANL 1999–2000a 37

04/05/2000 29 5113, 5121, 5125 Actinides 100 3 0 0 0 LANL 2000d 446

04/05/2000 29 5116, 5120, 5126 Actinides 100 3 1 0 0 LANL 2000d 466

04/13/2000 29 2130, 2134 Actinides 80 3 0 0 0 LANL 2000c 8

04/17/2000 29 2114 Actinides 90 7 1 0 0 LANL 2000c 17
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Date

Building 

number Location

Primary 

source

Number 

of 

results

Exceeded 

lower 

limit alpha

Exceeded 

upper limit 

alpha

Exceeded 

lower 

limit beta

Exceeded 

upper 

limit beta Source

Start 

page

05/26/2000 29 Wing 5 Actinides 50 1 0 0 0 LANL 2000d 476

08/16/2000 29 2114, 2129 Actinides 5 2 2 0 0 LANL 2000e 307

12/13/2000 29 5047 Actinides 100 1 0 0 0 LANL 2000d 433

12/13/2000 29 5012 Actinides 30 3 0 0 0 LANL 2000f 107

06/14/2001 29 2124, 2131 Actinides 100 3 0 0 0 LANL 2000f 395

12/21/2001 29 2113, 2128 Actinides 100 2 0 0 0 LANL 2000f 386

02/04/2004 29 4130 SNM 20 1 0 0 0 LANL 2004a 53

04/26/2004 29 2114 Actinides 12 1 0 0 0 LANL 2004b 88

05/10/2004 29 2134 Actinides 12 1 0 0 0 LANL 2004b 74

05/17/2004 29 2112, 2136 Actinides 12 2 0 0 0 LANL 2004b 67

06/07/2004 29 2136 Actinides 12 1 0 0 0 LANL 2004b 46

06/14/2004 29 2136 Actinides 12 1 0 0 0 LANL 2004b 39

06/30/2004 29 3158, 3024, 3034 Actinides 66 4 1 0 0 LANL 2004c 650

07/13/2004 29 4160 Uranium 20 1 0 0 0 LANL 2004a 101

07/13/2004 29 4161 Uranium 48 2 0 0 0 LANL 2004a 105

07/30/2004 2008 124 SNM 65 1 0 0 0 LANL 2004d 71

08/02/2004 29 4130 SNM 100 1 0 0 0 LANL 2004a 2

08/03/2004 29 4110 SNM 100 1 0 0 0 LANL 2004a 25

08/10/2004 29 4125, 4129, 4131 SNM 100 4 0 0 0 LANL 2004a 36

08/12/2004 29 4066 SNM 100 1 0 0 0 LANL 2004a 45

08/13/2004 29 4034, 4064 SNM 100 22 0 0 0 LANL 2004a 11

08/13/2004 29 4023 SNM 77 12 1 0 0 LANL 2004a 19

09/23/2004 29 4295 SNM 70 8 0 0 0 LANL 2004a 58

09/27/2004 29 4177, 4195 SNM 100 4 0 0 0 LANL 2004a 70

09/28/2004 29 Wing 4 SNM 100 7 0 0 0 LANL 2004a 78

09/29/2004 29 Wing 4 SNM 100 6 0 0 0 LANL 2004a 86

10/29/2004 2010 47 SNM 65 1 0 0 0 LANL 2004d 108

01/03/2005 29 2112 Actinides 18 1 0 0 0 LANL 2005–2006 336

01/11/2005 29 2136 Actinides 18 1 0 0 0 LANL 2005–2006 344

06/24/2005 29 2129 Actinides 15 1 1 0 0 LANL 2005–2006 319

08/08/2005 29 4137 SNM 100 1 0 0 0 LANL 2005a 137

08/10/2005 29 4034, 4064 SNM 100 2 0 0 0 LANL 2005a 143

08/10/2005 29 4064 SNM 20 1 0 0 0 LANL 2005a 150

a. DU = depleted uranium. 
ATTACHMENT A

SUPPORTING TABLES (continued)

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Table A-3. Air monitoring results exceeding airborne contamination limits, TA-3. 

Date

Building 

number Location Primary source

Number of 

results

Exceeded limit 

alpha

Exceeded limit 

beta Source

Start 

page

01/26/2000 29 Wing 5 Actinides 67 1 0 LANL 2000d 187

02/02/2000 29 Wing 5 Actinides 67 3 0 LANL 2000d 195

02/02/2000 29 Wing 2 Actinides 62 3 0 LANL 2000e 257

02/09/2000 29 Wing 5 Actinides 67 3 0 LANL 2000d 2

02/16/2000 29 Wing 5 Actinides 67 3 0 LANL 2000d 10

03/01/2000 29 Wing 5 Actinides 68 2 0 LANL 2000d 26

03/08/2000 29 Wing 7 Actinides 58 2 0 LANL 2000–2001 115

03/15/2000 29 Wing 5 Actinides 68 1 0 LANL 2000d 42

03/15/2000 29 Wing 9 MAP/MFP/Actinides 28 1 0 LANL 1999–2001 21

03/15/2000 29 Wing 7 Actinides 58 1 0 LANL 2000–2001 127

03/22/2000 29 Wing 7 Actinides 20 6 0 LANL 2000–2001 146

04/12/2000 29 Wing 2 Actinides 64 1 0 LANL 1999–2000b 147

04/12/2000 29 Wing 9 MAP/MFP/Actinides 28 1 0 LANL 1999–2001 12

04/19/2000 29 Wing 2 Actinides 64 1 0 LANL 1999–2000b 140

04/26/2000 29 Wing 5 Actinides 64 3 0 LANL 1999–2000b 137

05/31/2000 29 Wing 2 Actinides 64 3 0 LANL 1999–2000b 112

06/14/2000 29 Wing 5 Actinides 68 1 0 LANL 2000d 129

06/21/2000 29 Wing 5 Actinides 1 1 0 LANL 2000d 137

06/21/2000 29 Wing 5 Actinides 68 1 0 LANL 2000d 139

06/28/2000 29 Wing 5 Actinides 68 1 0 LANL 2000d 203

10/11/2000 29 Wing 9 MAP/MFP/Actinides 28 2 0 LANL 1999–2001 2

10/18/2000 29 Wing 5 Actinides 69 2 0 LANL 2000d 322

11/01/2000 29 Wing 5 Actinides 69 2 0 LANL 2000d 336

11/15/2000 29 Wing 7 Actinides 58 1 0 LANL 2000–2001 11

12/20/2000 29 Wing 5 Actinides 69 1 0 LANL 2001c 87

01/03/2001 29 Wing 5 Actinides 69 2 0 LANL 2001c 80

01/24/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 59

02/28/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 23

03/07/2001 29 Wing 2 Actinides 64 1 0 LANL 2001b 250

03/14/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 9

04/04/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 185

04/25/2001 29 Wing 5 Actinides 69 2 0 LANL 2001c 163

05/02/2001 29 Wing 4 Actinides 10 1 0 LANL 2001d 69

05/02/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 155

05/09/2001 29 Wing 2 Actinides 64 1 0 LANL 2001b 185
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Date

Building 

number Location Primary source

Number of 

results

Exceeded limit 

alpha

Exceeded limit 

beta Source

Start 

page

05/09/2001 29 Wing 9 MAP/MFP/Actinides 28 2 0 LANL 2001–2002a 115

05/16/2001 29 Wing 2 Actinides 64 1 0 LANL 2001b 178

05/23/2001 29 Wing 9 MAP/MFP/Actinides 28 2 0 LANL 2001–2002a 111

05/30/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 123

06/06/2001 29 Wing 9 MAP/MFP/Actinides 28 1 0 LANL 2001–2002a 107

06/06/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 115

06/20/2001 29 Wing 4 Actinides 10 2 0 LANL 2001d 53

06/20/2001 29 Wing 5 Actinides 59 2 0 LANL 2001c 94

06/27/2001 29 Wing 2 Actinides 66 1 0 LANL 2001b 134

07/04/2001 29 Wing 5 Actinides 69 2 0 LANL 2001c 287

07/11/2001 29 Wing 9 MAP/MFP/Actinides 28 1 0 LANL 2001–2002a 91

07/18/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 271

07/25/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 263

08/01/2001 29 Wing 5 Actinides 69 2 0 LANL 2001c 255

08/15/2001 29 Wing 7 Actinides 58 1 0 LANL 2001–2002b 92

08/22/2001 29 Wing 2 Actinides 64 1 0 LANL 2001b 94

08/29/2001 29 Wing 7 Actinides 58 1 0 LANL 2001–2002b 82

09/05/2001 29 Wing 7 Actinides 58 1 0 LANL 2001–2002b 77

09/12/2001 29 Wing 3 Actinides 32 2 0 LANL 2001–2002c 51

09/12/2001 29 Wing 7 Actinides 58 3 0 LANL 2001–2002b 72

09/12/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 207

09/19/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 199

10/03/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 372

10/10/2001 29 Wing 2 Actinides 64 1 0 LANL 2001b 55

10/10/2001 29 Wing 7 Actinides 58 1 0 LANL 2001–2002b 38

10/10/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 364

10/24/2001 29 Wing 2 Actinides 64 1 0 LANL 2001b 49

11/20/2001 29 Wing 5 Actinides 69 1 0 LANL 2001c 324

12/12/2001 29 Wing 7 Actinides 60 1 0 LANL 2001–2002b 2

01/09/2002 29 Wing 7 Actinides 60 1 0 LANL 2002d 261

02/06/2002 29 Wing 7 Actinides 60 2 0 LANL 2002d 240

02/13/2002 29 Wing 9 MAP/MFP/Actinides 28 1 0 LANL 2002b 176

02/27/2002 29 Wing 2 Actinides 64 1 0 LANL 2002–2003 229

03/06/2002 29 Wing 5 Actinides 69 1 0 LANL 2002c 277

03/20/2002 29 Wing 7 Actinides 60 1 0 LANL 2002d 208

04/03/2002 29 Wing 5 Actinides 69 1 0 LANL 2002c 249
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Date

Building 

number Location Primary source

Number of 

results

Exceeded limit 

alpha

Exceeded limit 

beta Source

Start 

page

04/10/2002 29 Wing 2 Actinides 64 1 0 LANL 2002–2003 196

05/08/2002 29 Wing 5 Actinides 69 1 0 LANL 2002c 214

05/29/2002 29 Wing 9 MAP/MFP/Actinides 28 1 0 LANL 2002b 113

05/29/2002 29 Wing 7 Actinides 61 6 0 LANL 2002d 155

06/05/2002 29 Wing 2 Actinides 64 1 0 LANL 2002–2003 156

06/12/2002 29 Wing 7 Actinides 61 7 0 LANL 2002d 144

06/19/2002 29 Wing 5 Actinides 69 1 0 LANL 2002c 169

07/03/2002 29 Wing 7 Actinides 61 1 0 LANL 2002d 128

07/03/2002 29 Wing 2 Actinides 64 1 0 LANL 2002–2003 127

07/10/2002 29 Wing 7 Actinides 61 1 0 LANL 2002d 122

07/24/2002 29 Wing 5 Actinides 69 1 0 LANL 2002c 138

07/31/2002 29 Wing 9 MAP/MFP/Actinides 29 1 0 LANL 2002b 79

07/31/2002 29 Wing 2 Actinides 64 2 0 LANL 2002–2003 104

08/07/2002 29 Wing 9 MAP/MFP/Actinides 29 3 0 LANL 2002b 75

08/07/2002 29 Wing 5 Actinides 69 1 0 LANL 2002c 122

08/14/2002 29 Wing 7 Actinides 61 2 0 LANL 2002d 97

08/21/2002 29 Wing 5 Actinides 69 1 0 LANL 2002c 108

08/28/2002 29 Wing 9 MAP/MFP/Actinides 29 1 0 LANL 2002b 64

09/04/2002 29 Wing 9 MAP/MFP/Actinides 29 1 0 LANL 2002b 60

09/04/2002 29 Wing 7 Actinides 61 1 0 LANL 2002d 82

09/11/2002 29 Wing 7 Actinides 61 4 0 LANL 2002d 76

09/18/2002 29 Wing 9 MAP/MFP/Actinides 29 1 0 LANL 2002b 52

09/18/2002 29 Wing 7 Actinides 61 1 0 LANL 2002d 70

09/25/2002 29 Wing 9 MAP/MFP/Actinides 29 2 0 LANL 2002b 48

09/25/2002 29 Wing 7 Actinides 61 3 0 LANL 2002d 64

09/25/2002 29 Wing 2 Actinides 65 1 0 LANL 2002–2003 63

10/02/2002 29 Wing 9 MAP/MFP/Actinides 29 2 0 LANL 2002b 44

10/02/2002 29 Wing 7 Actinides 61 2 0 LANL 2002d 58

10/09/2002 29 Wing 9 MAP/MFP/Actinides 29 2 0 LANL 2002b 40

10/09/2002 29 Wing 7 Actinides 61 1 0 LANL 2002d 53

10/09/2002 29 Wing 2 Actinides 65 1 0 LANL 2002–2003 52

10/23/2002 29 Wing 7 Actinides 61 4 0 LANL 2002d 42

10/30/2002 29 Wing 9 MAP/MFP/Actinides 29 1 0 LANL 2002b 30

10/30/2002 29 Wing 7 Actinides 61 1 0 LANL 2002d 37

11/20/2002 29 Wing 5 Actinides 69 1 0 LANL 2002c 18

11/27/2002 29 Wing 9 MAP/MFP/Actinides 29 1 0 LANL 2002b 14
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Date

Building 

number Location Primary source

Number of 

results

Exceeded limit 

alpha

Exceeded limit 

beta Source

Start 

page

12/11/2002 29 Wing 9 MAP/MFP/Actinides 29 1 0 LANL 2002b 6

01/21/2004 29 Wing 3 Actinides 34 1 0 LANL 2004e 12

01/28/2004 29 Wing 3 Actinides 33 2 0 LANL 2004e 15

04/21/2004 29 Wing 7 Actinides 67 1 0 LANL 2004–2005a 142

12/01/2004 29 Wing 2 Actinides 66 1 0 LANL 2004–2005b 10

02/16/2005 29 Wing 2 Actinides 66 1 0 LANL 2005–2006 30

03/09/2005 29 Wing 2 Actinides 66 1 0 LANL 2005–2006 43

05/04/2005 29 Wing 5 Actinides 69 1 0 LANL 2005–2006 135

10/05/2005 29 Wing 5 Actinides 69 1 0 LANL 2005–2006 46

11/09/2005 29 Wing 2 Actinides 66 1 0 LANL 2005–2006 257
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Table A-4. Smear results exceeding contamination limits, TA-48.

Date

Building 

number Location Primary source

Number 

of 

results

Exceeded 

lower limit 

alpha

Exceeded 

upper limit 

alpha

Exceeded 

lower limit 

beta

Exceeded 

upper limit 

beta Source

Start 

Page

02/04/1997 RC-1 423 MAP/MFP/Actinides 53 1 0 0 0 LANL 1997b 458

03/13/1997 RC-1 322 MAP/MFP/Actinides 46 1 0 0 0 LANL 1997b 627

04/07/1997 RC-1 326 MAP/MFP/Actinides 46 1 0 0 0 LANL 1997b 632

05/29/1997 RC-1 338 MAP/MFP/Actinides 46 1 1 1 0 LANL 1997b 637

06/18/1997 RC-1 326 MAP/MFP/Actinides 46 1 0 0 0 LANL 1997b 644

07/24/1997 RC-1 322 MAP/MFP/Actinides 46 1 0 0 0 LANL 1997b 649

08/06/1997 RC-1 326 MAP/MFP/Actinides 46 1 0 0 0 LANL 1997b 654

09/25/1997 RC-1 305 MAP/MFP/Actinides 36 1 0 0 0 LANL 1997b 89

09/25/1997 RC-1 306 MAP/MFP/Actinides 17 1 0 0 0 LANL 1997b 94

09/25/1997 RC-1 309 MAP/MFP/Actinides 40 1 0 0 0 LANL 1997b 142

09/25/1997 RC-1 312 MAP/MFP/Actinides 36 2 0 0 0 LANL 1997b 201

09/30/1997 RC-1 408 MAP/MFP/Actinides 32 2 0 2 0 LANL 1997b 276

09/30/1997 RC-1 412 MAP/MFP/Actinides 18 1 0 0 0 LANL 1997b 354

09/30/1997 RC-1 421 MAP/MFP/Actinides 29 1 0 0 0 LANL 1997b 442

10/26/1997 RC-1 308 MAP/MFP/Actinides 32 1 0 0 0 LANL 1997b 134

10/28/1997 RC-1 305 MAP/MFP/Actinides 36 2 0 0 0 LANL 1997b 77

10/29/1997 RC-1 310 MAP/MFP/Actinides 16 1 0 0 0 LANL 1997b 162

10/29/1997 RC-1 312 MAP/MFP/Actinides 38 1 1 0 0 LANL 1997b 196

10/30/1997 RC-1 402 MAP/MFP/Actinides 28 1 0 0 0 LANL 1997b 254

10/31/1997 RC-1 421 MAP/MFP/Actinides 29 1 0 0 0 LANL 1997b 438

11/19/1997 RC-1 314 MAP/MFP/Actinides 70 3 0 0 0 LANL 1997b 677

11/25/1997 RC-1 309 MAP/MFP/Actinides 36 1 0 0 0 LANL 1997b 151

11/25/1997 RC-1 310 MAP/MFP/Actinides 16 1 0 0 0 LANL 1997b 166

11/25/1997 RC-1 402 MAP/MFP/Actinides 28 1 0 0 0 LANL 1997b 250

11/26/1997 RC-1 309 MAP/MFP/Actinides 16 1 0 0 0 LANL 1997b 300

11/26/1997 RC-1 415 MAP/MFP/Actinides 28 1 0 0 0 LANL 1997b 395

11/26/1997 RC-1 421 MAP/MFP/Actinides 29 1 0 0 0 LANL 1997b 446

12/01/1997 RC-1 315 MAP/MFP/Actinides 70 5 0 0 0 LANL 1997b 682

12/17/1997 RC-1 309 MAP/MFP/Actinides 32 2 1 0 0 LANL 1997b 155

12/17/1997 RC-1 312 MAP/MFP/Actinides 32 1 0 0 0 LANL 1997b 188

12/18/1997 RC-1 402 MAP/MFP/Actinides 28 1 0 0 0 LANL 1997b 246

12/18/1997 RC-1 415 MAP/MFP/Actinides 28 1 0 0 0 LANL 1997b 391

12/19/1997 RC-1 4B MAP/MFP/Actinides 15 1 0 0 0 LANL 1997b 226

12/19/1997 RC-1 6 MAP/MFP/Actinides 32 1 0 0 0 LANL 1997b 229
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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8/30/2023 Page 48 of 54

Date

Building 

number Location Primary source

Number 

of 

results

Exceeded 

lower limit 

alpha

Exceeded 

upper limit 

alpha

Exceeded 

lower limit 

beta

Exceeded 

upper limit 

beta Source

Start 

Page

12/19/1997 RC-1 409 MAP/MFP/Actinides 16 1 0 0 0 LANL 1997b 296

12/19/1997 RC-1 421 MAP/MFP/Actinides 29 1 1 0 0 LANL 1997b 450

01/04/1999 RC-1 315 MAP/MFP/Actinides 70 0 0 1 0 LANL 1999g 2

03/01/1999 RC-1 Hot Cell MAP/MFP/Actinides 79 0 0 8 0 LANL 1999g 16

04/01/1999 RC-1 430 MAP/MFP/Actinides 60 1 0 0 0 LANL 1999h 21

04/08/1999 RC-1 314, 326 MAP/MFP/Actinides 70 2 0 0 0 LANL 1999g 22

06/01/1999 RC-1 606 MAP/MFP/Actinides 50 1 0 0 0 LANL 1999h 247

07/01/1999 RC-1 315, 338 MAP/MFP/Actinides 70 0 0 2 0 LANL 1999g 36

08/03/1999 RC-1 315 MAP/MFP/Actinides 70 0 0 1 0 LANL 1999g 45

09/01/1999 RC-1 430 MAP/MFP/Actinides 60 1 0 0 0 LANL 1999h 46

10/01/1999 RC-1 606 MAP/MFP/Actinides 50 1 0 1 0 LANL 1999h 188

09/16/2004 RC-1 414 MAP/MFP/Actinides 95 1 0 0 0 LANL 2004f 2

12/08/2004 RC-1 414 MAP/MFP/Actinides 95 1 0 0 0 LANL 2004f 21

05/31/2005 RC-1 315 MAP/MFP/Actinides 40 1 0 0 0 LANL 2005b 54

07/26/2005 RC-1 314 MAP/MFP/Actinides 50 0 0 1 0 LANL 2005b 66

09/28/2005 RC-1 315 MAP/MFP/Actinides 50 0 0 2 0 LANL 2005b 96
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Table A-5. Air monitoring results exceeding airborne contamination limits, TA-48.

Date

Building 

number Location Primary source

Number of 

results

Exceeded 

limit alpha

Exceeded 

limit beta Source

Start 

page

03/18/1997 RC-1 332-D MAP/MFP/Actinides 18 1 0 LANL 1996–1998 172

05/27/1997 RC-1 Hot Cell MAP/MFP/Actinides 4 3 0 LANL 1996–1998 301

08/05/1997 RC-1 332, 344 MAP/MFP/Actinides 18 5 0 LANL 1996–1998 222

10/01/1997 RC-1 332 MAP/MFP/Actinides 18 3 0 LANL 1996–1998 235

11/05/1997 RC-1 332 MAP/MFP/Actinides 18 1 0 LANL 1996–1998 239

01/05/1998 RC-1 332 MAP/MFP/Actinides 18 3 0 LANL 1998b 6

01/28/1998 RC-1 332 MAP/MFP/Actinides 18 4 0 LANL 1998b 11

02/17/1998 RC-1 606 MAP/MFP/Actinides 15 4 0 LANL 1998–1999 30

03/01/1999 RC-1 332 MAP/MFP/Actinides 18 4 0 LANL 1999i 12

08/03/1999 RC-1 332 MAP/MFP/Actinides 18 1 0 LANL 1999i 31
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Table A-6. Smear results exceeding contamination limits, TA-53.

Date

Building 

number Location Primary source

Number 

of 

results

Exceeded 

lower 

limit alpha

Exceeded 

upper 

limit alpha

Exceeded 

lower 

limit beta

Exceeded 

upper 

limit beta Source

Start 

page

01/04/1996 MPF-3M Area A MAP/Rn/Tn 60 0 0 1 0 LANL 1996–1997a 70

02/01/1996 MPF-3M Switchyard MAP/Rn/Tn 26 7 1 4 0 LANL 1996–1997a 574

02/06/1996 MPF-3M Area A MAP/Rn/Tn 50 1 0 1 0 LANL 1996–1997a 704

02/07/1996 MPF-3M Area A MAP/Rn/Tn 86 0 0 1 0 LANL 1996–1997a 850

02/13/1996 MPF-3M Area A MAP/Rn/Tn 70 11 0 2 0 LANL 1996–1997b 2

02/15/1996 MPF-3M Area A MAP/Rn/Tn 50 1 0 2 0 LANL 1996–1997b 92

03/15/1996 MPF-3M Area A MAP/Rn/Tn 50 3 0 2 0 LANL 1996–1997b 553

03/26/1996 MPF-3M Area A MAP/Rn/Tn 100 8 0 7 0 LANL 1996–1997b 765

03/26/1996 MPF-25 Aberdeen Steel MAP/Rn/Tn 100 2 0 0 0 LANL 1996–1997b 835

04/05/1996 MPF-3M Area A MAP/Rn/Tn 70 3 0 4 0 LANL 1996b 141

04/19/1996 MPF-3M Area A MAP/Rn/Tn 100 1 0 0 0 LANL 1996b 381

04/24/1996 MPF-7 1LSA MAP/Actinides/Rn/Tn 60 10 1 2 0 LANL 1996b 475

04/30/1996 MPF-7 1LSA MAP/Actinides/Rn/Tn 42 6 0 1 0 LANL 1996b 569

05/03/1996 MPF-3M Area A MAP/Rn/Tn 100 2 0 0 0 LANL 1996b 613

05/15/1996 MPF-3M Area A MAP/Rn/Tn 70 1 0 0 0 LANL 1996c 259

05/25/1996 MPF-7 ER-1 MAP/Actinides/Rn/Tn 30 2 0 0 0 LANL 1996c 19

05/28/1996 MPF-3M Area A MAP/Rn/Tn 100 1 0 1 0 LANL 1996c 87

05/31/1996 MPF-3M Area A MAP/Rn/Tn 70 1 0 0 0 LANL 1996c 459

03/14/1997 MPF-3M Area A MAP/Rn/Tn 90 3 0 0 0 LANL 1996–1997c 32

05/18/1997 MPF-8 PSR MAP/Rn/Tn 30 1 0 1 0 LANL 1997c 56

07/14/1997 MPF-3P HRS MAP/Rn/Tn 40 3 0 4 0 LANL 1997d 19

10/24/1997 MPF-7 1LTC MAP/Actinides/Rn/Tn 10 9 0 0 0 LANL 1997–1998 326

11/06/1997 MPF-3M Area A MAP/Rn/Tn 10 0 0 1 0 LANL 1997–1998 278

02/03/1999 MPF-7 1LSA MAP/Actinides/Rn/Tn 100 2 0 1 0 LANL 1999j 251

12/14/1999 MPF-30 ER-2 MAP/Actinides/Rn/Tn 100 4 0 3 0 LANL 1999k 15

12/15/1999 MPF-7 Blue Room MAP/Actinides/Rn/Tn 20 12 0 7 0 LANL 1999k 8

01/13/2000 MPF-7 ER-1 MAP/Actinides/Rn/Tn 25 1 0 0 0 LANL 1999–2000c 78

02/03/2000 MPF-8 PSR MAP/Rn/Tn 100 2 0 0 0 LANL 1999–2000c 280

08/30/2000 MPF-7 Blue Room MAP/Actinides/Rn/Tn 6 0 0 5 0 LANL 2000g 210

09/21/2000 MPF-27 Exit Light 28 MAP/Rn/Tn 100 1 0 0 0 LANL 2000g 36

10/14/2000 MPF-25 Aberdeen Steel MAP/Rn/Tn 100 8 0 0 0 LANL 2000g 603

10/24/2000 MPF-1 LOB MAP/Rn/Tn 90 2 0 0 0 LANL 2000g 535

12/12/2000 MPF-30 ER-2 MAP/Actinides/Rn/Tn 100 1 0 0 0 LANL 2000g 338

02/18/2003 MPF-7 1LSA MAP/Actinides/Rn/Tn 100 0 0 1 0 LANL 2003b 47

06/12/2003 MPF-7 1LSA MAP/Actinides/Rn/Tn 100 0 0 1 0 LANL 2003b 143
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Date

Building 

number Location Primary source

Number 

of 

results

Exceeded 

lower 

limit alpha

Exceeded 

upper 

limit alpha

Exceeded 

lower 

limit beta

Exceeded 

upper 

limit beta Source

Start 

page

08/26/2003 MPF-7 1LSA MAP/Actinides/Rn/Tn 100 0 0 1 0 LANL 2003c 337

10/07/2003 MPF-3S Switchyard MAP/Rn/Tn 95 1 0 0 0 LANL 2003c 175

07/02/2004 MPF-7 1LSA MAP/Actinides/Rn/Tn 100 0 0 1 0 LANL 2004g 120

09/13/2004 MPF-7 1LSA MAP/Actinides/Rn/Tn 100 1 0 1 0 LANL 2004g 113

12/16/2004 MPF-3M Area A MAP/Rn/Tn 100 2 0 1 0 LANL 2004h 285

12/18/2004 MPF-3M Area A MAP/Rn/Tn 92 1 0 0 0 LANL 2004h 210

12/18/2004 MPF-7 1LSA MAP/Actinides/Rn/Tn 100 2 0 0 0 LANL 2004h 222
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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Table A-7. Air monitoring results exceeding airborne contamination limits, TA-53.a

Date

Building 

number Location Primary source

Number 

of results

Exceeded 

limit alpha

Exceeded 

limit beta Source

Start 

page

01/02/1996 MPF-3M Area A MAP/Rn/Tn 2 2 0 LANL 1996d 34

01/08/1996 MPF-3M Area A MAP/Rn/Tn 2 2 0 LANL 1996d 30

01/16/1996 MPF-7 1LTC MAP/Actinides/Rn/Tn 10 1 0 LANL 1996d 27

01/22/1996 MPF-3M Area A MAP/Rn/Tn 7 5 0 LANL 1996d 14

02/12/1996 MPF-3M, 7 1LTC, Area A MAP/Actinides/Rn/Tn 6 4 0 LANL 1996d 18

02/20/1996 MPF-3M Area A MAP/Rn/Tn 2 2 0 LANL 1996d 11

02/26/1996 MPF-3M, 7 Area A, ER-1 MAP/Actinides/Rn/Tn 8 2 0 LANL 1996d 93

03/04/1996 MPF-3M, 7 Area A, ER-1 MAP/Actinides/Rn/Tn 9 5 0 LANL 1996d 94

03/11/1996 MPF-3M, 7 1LSA, Area A MAP/Actinides/Rn/Tn 7 4 0 LANL 1996d 89

03/22/1996 MPF-3M Area A MAP/Rn/Tn 8 5 0 LANL 1996d 77

03/28/1996 MPF-3M, 7 Area A, 1LSA, 1LTC MAP/Actinides/Rn/Tn 14 9 1 LANL 1996d 80

04/01/1996 MPF-3M Area A MAP/Rn/Tn 3 3 0 LANL 1996d 84

04/08/1996 MPF-3M Area A MAP/Rn/Tn 8 2 0 LANL 1996d 67

04/15/1996 MPF-3M Area A MAP/Rn/Tn 7 1 0 LANL 1996d 64

12/24/1996 MPF-3M Area A MAP/Rn/Tn 9 3 0 LANL 1997e 40

12/30/1996 MPF-3M Area A MAP/Rn/Tn 2 1 0 LANL 1996d 103

01/13/1997 MPF-3M Area A MAP/Rn/Tn 24 2 1 LANL 1997e 44

01/31/1997 MPF-3M Area A MAP/Rn/Tn 14 1 0 LANL 1997e 56

02/10/1997 MPF-3M Area A MAP/Rn/Tn 1 1 1 LANL 1997e 60

02/13/1997 MPF-3M Area A MAP/Rn/Tn 17 2 0 LANL 1997e 66

02/20/1997 MPF-3M Area A MAP/Rn/Tn 6 3 0 LANL 1997e 70

02/25/1997 MPF-3M Area A MAP/Rn/Tn 10 5 0 LANL 1997e 75

03/03/1997 MPF-3M Area A MAP/Rn/Tn 14 1 0 LANL 1997e 81

03/10/1997 MPF-3M Area A MAP/Rn/Tn 8 1 0 LANL 1997e 84

03/17/1997 MPF-3M Area A MAP/Rn/Tn 6 4 0 LANL 1997e 87

03/17/1997 MPF-3M, 30 Area A, ER-2 MAP/Actinides/Rn/Tn 8 2 0 LANL 1997e 93

03/24/1997 MPF-3M, 7, 30 Area A, ER-1, 2 MAP/Actinides/Rn/Tn 5 4 0 LANL 1997e 90

04/03/1997 MPF-3M Area A MAP/Rn/Tn 10 1 0 LANL 1997e 97

04/10/1997 MPF-3M Area A MAP/Rn/Tn 5 1 0 LANL 1997e 101

04/16/1997 MPF-3M, 29 Area A, Not available MAP/Actinides/Rn/Tn 6 2 0 LANL 1997e 125

04/21/1997 MPF-3M, 7 Area A, ER-1 MAP/Actinides/Rn/Tn 9 7 2 LANL 1997e 105

04/30/1997 MPF-3P HRS MAP/Rn/Tn 7 1 0 LANL 1997e 113

06/04/1997 MPF-3M Area A MAP/Rn/Tn 8 2 0 LANL 1997e 132

06/13/1997 MPF-3M, 30 Area A, ER-2 MAP/Actinides/Rn/Tn 14 3 1 LANL 1997e 136

06/22/1997 MPF-3M Area A MAP/Rn/Tn 9 1 0 LANL 1997e 139
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

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8/30/2023 Page 53 of 54

Date

Building 

number Location Primary source

Number 

of results

Exceeded 

limit alpha

Exceeded 

limit beta Source

Start 

page

06/27/1997 MPF-3M, 7 Area A, ER-1 MAP/Actinides/Rn/Tn 4 2 0 LANL 1997e 143

07/20/1997 MPF-3M Area A MAP/Rn/Tn 4 1 0 LANL 1997e 153

08/15/1997 MPF-3M Area A MAP/Rn/Tn 21 1 0 LANL 1997e 161

08/25/1997 MPF-7 1LTC MAP/Actinides/Rn/Tn 20 0 1 LANL 1997e 164

09/02/1997 MPF-7 1LTC MAP/Actinides/Rn/Tn 11 2 2 LANL 1997e 167

09/03/1997 MPF-3M Area A MAP/Rn/Tn 9 1 0 LANL 1997e 172

09/22/1997 MPF-3M, 7 Area A, 1LTC MAP/Actinides/Rn/Tn 15 4 0 LANL 1997e 178

09/29/1997 MPF-3M Area A MAP/Rn/Tn 24 3 0 LANL 1997e 181

10/03/1997 MPF-3M, 7 Area A, 1L TGT MAP/Actinides/Rn/Tn 36 7 0 LANL 1997e 184

10/10/1997 MPF-3M, 7 Area A, 1L TGT MAP/Actinides/Rn/Tn 31 8 0 LANL 1997e 187

10/17/1997 MPF-3M, 7 Area A, 1L TGT MAP/Actinides/Rn/Tn 34 16 0 LANL 1997e 190

10/27/1997 MPF-3M, 7 Area A, 1L TGT MAP/Actinides/Rn/Tn 32 12 0 LANL 1997e 193

11/03/1997 MPF-3M, 7 Area A, 1L TGT, ER-1 MAP/Actinides/Rn/Tn 33 22 1 LANL 1997e 196

11/07/1997 MPF-3M, 7 Area A, 1L TGT MAP/Actinides/Rn/Tn 19 12 1 LANL 1997e 199

11/17/1997 MPF-7 1L TGT MAP/Actinides/Rn/Tn 23 7 0 LANL 1997e 202

11/22/1997 MPF-3M, 7 Area A, 1L TGT MAP/Actinides/Rn/Tn 11 7 0 LANL 1997e 205

11/25/1997 MPF-3M, 7 Area A, 1L TGT MAP/Actinides/Rn/Tn 35 8 0 LANL 1997e 208

12/15/1997 MPF-3M Area A MAP/Rn/Tn 22 3 2 LANL 1997e 216

12/19/1997 MPF-3M Area A MAP/Rn/Tn 9 1 0 LANL 1997e 213

01/15/1998 MPF-3M Area A MAP/Rn/Tn 18 1 0 LANL 1998c 163

01/29/1998 MPF-3M Area A MAP/Rn/Tn 27 1 0 LANL 1998c 157

02/06/1998 MPF-3M Area A MAP/Rn/Tn 25 1 2 LANL 1998c 154

02/13/1998 MPF-7 1L TGT MAP/Actinides/Rn/Tn 10 2 0 LANL 1998c 152

02/17/1998 MPF-7 1L TGT MAP/Actinides/Rn/Tn 32 2 0 LANL 1998c 149

03/09/1998 MPF-7 1L TGT MAP/Actinides/Rn/Tn 15 3 0 LANL 1998c 143

03/12/1998 MPF-7 1L TGT MAP/Actinides/Rn/Tn 14 1 0 LANL 1998c 138

03/19/1998 MPF-7 1L TGT MAP/Actinides/Rn/Tn 11 2 0 LANL 1998c 136

04/10/1998 MPF-7 1LSA MAP/Actinides/Rn/Tn 21 4 0 LANL 1998c 127

05/11/1998 MPF-3M, 7 Area A, 1LSA, 1LTC MAP/Actinides/Rn/Tn 15 2 0 LANL 1998c 116

05/18/1998 MPF-7 1LSA MAP/Actinides/Rn/Tn 12 1 0 LANL 1998c 112

05/21/1998 MPF-3M Area A MAP/Rn/Tn 18 2 0 LANL 1998c 109

06/01/1998 MPF-3M Area A, ES-3 MAP/Rn/Tn 22 2 0 LANL 1998c 106

06/12/1998 MPF-3M Area A MAP/Rn/Tn 15 2 0 LANL 1998c 100

06/19/1998 MPF-3M Area A MAP/Rn/Tn 24 1 0 LANL 1998c 97

07/01/1998 MPF-3M Area A MAP/Rn/Tn 8 1 0 LANL 1998c 94

08/04/1998 MPF-3M Area A MAP/Rn/Tn 12 1 0 LANL 1998c 80
ATTACHMENT A

SUPPORTING TABLES (continued)

Document No. ORAUT-RPRT-0101 Revision No. 01 Effective Date: 

0

8/30/2023 Page 54 of 54

Date

Building 

number Location Primary source

Number 

of results

Exceeded 

limit alpha

Exceeded 

limit beta Source

Start 

page

08/10/1998 MPF-3M Area A MAP/Rn/Tn 15 1 0 LANL 1998c 77

08/25/1998 MPF-3M Area A MAP/Rn/Tn 15 3 0 LANL 1998c 71

09/08/1998 MPF-3M Area A MAP/Rn/Tn 12 1 0 LANL 1998c 65

10/26/1998 MPF-29 WNR MAP/Actinides/Rn/Tn 10 1 0 LANL 1998c 43

09/08/1999 MPF-3M Area A MAP/Rn/Tn 6 4 0 LANL 1999l 100

09/14/1999 MPF-3M Area A MAP/Rn/Tn 10 1 0 LANL 1999l 98

09/20/1999 MPF-3M Area A MAP/Rn/Tn 5 1 0 LANL 1999l 96

10/24/1999 MPF-7, 28 ER-1, Not available MAP/Actinides/Rn/Tn 6 3 0 LANL 1999l 66

11/05/1999 MPF-3M, 8, 28 Area A, Not available, PSR MAP/Actinides 20 4 0 LANL 1999l 56

11/05/1999 MPF-29 Not available MAP/Actinides/Rn/Tn 14 1 0 LANL 1999l 63

11/08/1999 MPF-3M, 7, 28 Area A, ER-1, PSR MAP/Actinides/Rn/Tn 25 13 0 LANL 1999l 5

11/19/1999 MPF-3M Area A MAP/Rn/Tn 9 1 0 LANL 1999l 49

12/07/1999 MPF-7, 28 ER-2, PSR MAP/Actinides/Rn/Tn 8 2 1 LANL 1999l 39

12/10/1999 MPF-7, 28 ER-2, PSR MAP/Actinides/Rn/Tn 15 3 0 LANL 1999l 32

01/10/2000 MPF-7, 28 ER-1, PSR MAP/Actinides/Rn/Tn 8 3 1 LANL 2000h 133

02/07/2000 MPF-7 ER-1 MAP/Actinides/Rn/Tn 5 1 0 LANL 2000h 124

02/17/2000 MPF-7 ER-1 MAP/Actinides/Rn/Tn 29 1 0 LANL 2000h 112

03/06/2000 MPF-28 PSR MAP/Rn/Tn 6 1 0 LANL 2000h 105

03/15/2000 MPF-7, 28 ER-1, Not available MAP/Actinides/Rn/Tn 24 3 0 LANL 2000h 97

03/27/2000 MPF-28 PSR MAP/Rn/Tn 31 1 0 LANL 2000h 94

04/04/2000 MPF-28 PSR MAP/Rn/Tn 22 1 0 LANL 2000h 91

07/21/2000 MPF-29 WNR MAP/Actinides/Rn/Tn 2 2 0 LANL 2000h 72

10/12/2004 MPF-7 1LSA MAP/Actinides/Rn/Tn 2 1 0 LANL 2004i 52

11/01/2004 MPF-7 1LSA MAP/Actinides/Rn/Tn 1 1 0 LANL 2004i 46

11/22/2004 MPF-7 1LSA MAP/Actinides/Rn/Tn 1 1 0 LANL 2004i 37

a. TGT = target; WNR = Weapons Neutron Research Facility.