Page 1 of 38

DOE Review Release 08/23/2022

Review of Potential Exposure to Exotic 

Radionuclides Using Radiological Work 

Permit Data at Los Alamos National 

Laboratory

ORAUT-RPRT-0103 Rev. 00

Effective Date: 08/15/2022

Supersedes: None

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

Document Owner 

Approval: Signature on File

Pat McCloskey, Document Owner

Approval Date: 08/11/2022

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 08/11/2022

Approval: Signature on File

Timothy D. Taulbee, Associate Director for Science

Approval Date: 08/15/2022

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

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

New Total Rewrite Revision Page Change
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 2 of 38

 

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

08/15/2022 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. This report is supplemental to 

ORAUT-RPRT-0101 and reviews radiological work permit 

information to ensure that RCT monitoring was appropriately 

performed. Incorporates formal internal and NIOSH review 

comments. Training is not required. Initiated by Pat McCloskey and 

authored by James M. Mahathy.
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TABLE OF CONTENTS

SECTION TITLE PAGE

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

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

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

1.2 Methodology of Report ................................................................................................. 8

2.0 Review of Radiological Work Permits..................................................................................... 10

2.1 TA-3 ........................................................................................................................... 11

2.1.1 RWP 96-3-29-9030-106 ............................................................................... 11

2.1.2 RWP 96-3-29-9030B-423............................................................................. 12

2.1.3 RWP 97-3-29-9030-99 ................................................................................. 12

2.1.4 RWP 97-3-29-Wing 9-162............................................................................ 13

2.1.5 RWP 99-3-29-1117-47 ................................................................................. 14

2.1.6 RWP 99-3-29-9030, 9060-144 ..................................................................... 16

2.1.7 RWP 99-3-29-4064-361 ............................................................................... 17

2.1.8 RWP 04-03-29-4064-275 ............................................................................. 18

2.2 TA-48 ......................................................................................................................... 19

2.2.1 RWP TA-48-98-46........................................................................................ 20

2.2.2 RWP TA-48-98-62........................................................................................ 21

2.2.3 RWP TA-48-98-47........................................................................................ 21

2.2.4 RWP TA-48-98-50........................................................................................ 23

2.2.5 RWP TA-48-03-01........................................................................................ 24

2.2.6 RWP TA-48-03-08........................................................................................ 25

2.2.7 RWP TA-48-03-09........................................................................................ 25

2.2.8 RWP TA-48-03-23........................................................................................ 26

2.3 TA-53 ......................................................................................................................... 27

2.3.1 RWP 1999-122-01 ....................................................................................... 27

2.3.2 RWP 2001-035-01 ....................................................................................... 28

2.3.3 RWP 2002-006-01 ....................................................................................... 29

2.3.4 RWP 2002-007-01 ....................................................................................... 29

2.3.5 RWP 2003-001-01 ....................................................................................... 30

2.3.6 RWP 2003-022-01 ....................................................................................... 31

2.3.7 RWP 2004-054-01 ....................................................................................... 32

2.3.8 RWP 2004-128-01 ....................................................................................... 32

3.0 Summary and Conclusion ...................................................................................................... 33

References ........................................................................................................................................ 35

ATTACHMENT A SUMMARY OF RWP INFORMATION............................................................. 38

LIST OF TABLES

TABLE TITLE PAGE

A-1 Summary of RWP information................................................................................................ 38
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ACRONYMS AND ABBREVIATIONS

1LSA service area in MPF-7, Room 200

ALARA as low as is reasonably achievable

anti-Cs anti-contamination clothing

APT accelerator production of tritium

CAM continuous air monitor

CED committed effective dose

C.F.R. Code of Federal Regulations

cm centimeter

CMR Chemistry and Metallurgy Research

CTRWP Changes to the RWP 

DAC derived air concentration

DOE U.S. Department of Energy

dpm disintegrations per minute

DU depleted uranium

EPD Electronic Personal Dosimeter

FP fission product

hr hour

ICRP International Commission on Radiological Protection

LANL Los Alamos National Laboratory

LAS large area swipe

m meter

MAPs mixed activation products

MDA minimum detectable activity

MFPs mixed fission products

mrem millirem

NDA no detectable activity

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

ORAUT ORAU Team

PCM personnel contamination monitor

PPE personal protective equipment

RCT radiological control technician

RIR Radiological Incident Report

RWP radiological work permit

SEC Special Exposure Cohort

SRDB Ref ID Site Research Database Reference Identification (number)

SWP Special Work Permit
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 5 of 38

TA Technical Area

TLD thermoluminescent dosimeter

WB whole body

yr year

§ section or sections
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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 
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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; therefore 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 supplements ORAUT-RPRT-0101, Bounding Intakes of Exotic Radionuclides at Los 

Alamos National Laboratory [RPRT-0101; Oak Ridge Associated Universities (ORAU) Team 

(ORAUT) 2022], which addressed an issue from the Advisory Board on Radiation Worker Health 

about the ability to bound dose for exotic (which for the purpose of this report will also include mixed 

fission and activation products) radionuclides [NIOSH 2018, pp. 11–16; 2019, pp. 18–25] 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]. In RPRT-0101, 

the ORAU Team evaluated surface contamination and air monitoring data and derived values to 

bound dose at 100 mrem CED per year. For surface contamination, results exceeding 400 dpm/100 

cm2 alpha and 3,200,000 dpm/100 cm2 beta were derived. For air monitoring, results exceeding 0.04 

dpm/m3 alpha and 320 dpm/m3 beta were derived. 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.

Cesium-137 is assumed in this report to be an indicator radionuclide for mixed fission products 

(MFPs) when present. This report will show examples of radiological work permit (RWP) packages to 

support the premise given in RPRT-0101 that LANL monitored work so they could determine which

workers to monitor by bioassay. LANL issued RWPs to establish radiological controls for intended 

work activities. RWPs inform workers of area radiological conditions and as low as is reasonably 

achievable (ALARA) requirements and provide a mechanism to relate worker exposure to specific 

work activities [DOE 1998]. Conclusions made in the report are subjective and not intended to provide 

a degree of statistical confidence. No dose assessment is performed for any worker identified in these 

RWP packages.

The ORAU Team notes the LANL Health Physics group only monitored by bioassay those workers

thought to have the potential to receive more than 100 mrem CED per year in the period January 1, 

1996, through December 31, 2005. This report examines RWPs for evidence to support the premise 

that LANL Health Physics performed radiological work in a disciplined manner that minimized 

inadvertent intakes of radioactive material.

Internal Dosimetry Technical Basis HSR-12-03-TB.0 describes LANL internal dosimetry processes. 

Sections 2.2.1 through 2.2.5 of that document describe the typical routine monitoring for the majority 

of radionuclides handled at LANL, which are plutonium, americium, uranium, and tritium [Archuleta 

2021a].

The ORAU Team queried LANL Health Physics for information regarding dosimetry thresholds for 

some exotic radionuclides and received the following information [Archuleta 2021b, p. 5]: 

During the period January 1, 1996 through December 31, 2005, LANL had no routine 

bioassay monitoring programs for the following isotopes:

• Ac-227

• Cm-244
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• Np-237

• Pa-231

• Sr-90

Routine monitoring programs for these isotopes would only have been established if 

there was routine work with associated materials likely to result in intakes of 100 mrem 

committed effective dose or greater. Consequently, no bioassay enrollment criteria for 

these radionuclides were adopted or promulgated.

A question posed to LANL Health Physics related specifically to 99Tc received the following response 

[Archuleta 2021a, p. 5]: 

During the period January 1, 1996 through December 31, 2005, LANL did not establish 

a routine bioassay monitoring program for Tc-99. Routine monitoring programs for this 

radionuclide would only have been established if there was routine work with associated 

materials likely to result in intakes of 100 mrem committed effective dose or greater. As 

this was not the case, no bioassay enrollment criteria for Tc-99 were adopted or 

promulgated. Any nonroutine work with, or events involving, Tc-99 during this time period 

would have been evaluated for bioassay monitoring on a case-by-case basis. This 

method was demonstrated following a LANL contamination event in 2012 involving 

Tc-99; based on the potential for intakes, LANL collected urine bioassay samples from 

involved workers, subcontracted analysis by an outside laboratory, and performed dose 

assessments. There were no such cases during the period January 1, 1996 through 

December 31, 2005.

Workers at LANL were enrolled in routine dosimetry programs commensurate with their work location, 

activity, and associated radiological hazards using the Health Physics Checklist process. Radiological 

work involving the potential for intakes was identified by operational health physics based on 

knowledge of ongoing activities and associated hazards, workplace monitoring data, and experience 

with contamination conditions. For radionuclides where in vivo measurements were deemed effective, 

workers were enrolled in the routine in vivo monitoring program. For-cause bioassay measurements 

were initiated when field indicators suggested the potential for intake in unusual or upset conditions. 

Based on the nature of planned nonroutine work, RWPs prescribed bioassay measurements when the 

work could result in radioactive material intakes. Workers were provided Radiological Worker training 

to understand their responsibilities regarding participation in prescribed dosimetry programs. Work 

covered by RWPs was initiated with prejob briefings during which all RWP requirements were 

covered, and all attendees were accountable for following those requirements. This included 

individuals verifying they were on the prescribed dosimetry program [Archuleta 2020].

1.2 METHODOLOGY OF REPORT 

The ORAU Team selected RWPs from the Site Research Database (SRDB) for the same technical 

areas used in RPRT-0101, TA-3, TA-48, and TA-53, and during the period from January 1, 1996, 

through December 31, 2005. These areas were selected based on documented evidence that exotic 

radionuclides were processed in them. Selected RWPs involved work with radionuclides other than 

plutonium, americium, and uranium. The ORAU Team cannot conclude that it has captured all such 

RWPs. Additionally, LANL Health Physics stated to the ORAU Team that there was no general intent 

to provide in process surveys in all RWP packages. LANL planned and prepared for nonroutine hot 

jobs which includes characterizing the as is conditions, commonly established with a pre job survey, 

potential changes in radiological hazards due to the activity, such as breaching containment devices, 

and established boundaries, hold points, electronic personal dosimeter (EPD) alarm settings, 
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maximum expected levels of contamination, dose rates and/or airborne contamination. During the 

work execution phase, conditions are monitored against limits. Radiological control technicians 

(RCTs) providing coverage monitor for applicable radiological conditions and direct the work team. 

Often in higher contamination areas, RCTs perform qualitative “go/no-go” direct monitoring, with no 

need to pause for quantitative measurements. Often, high contamination techniques are developed 

which do not require monitoring as it is safely assumed that involved materials are contaminated. 

Monitoring such materials increases the risk for spreading contamination, including contaminating 

survey instruments, rendering them useless, and causing immediate suspension of work [Archuleta 

2022]. 

In consideration of these factors, in process hot job surveys are not documented. While supporting the 

work, RCTs are regularly monitoring and directing actions to manage conditions within established

suspension limits. There is no occupational radiation protection benefit to stopping, recording, 

documenting, reviewing, filing, tracking, and archiving such survey results. Furthermore, it would not 

be consistent with ALARA principles to add cumbersome, unnecessary steps to an already higherhazard activity. In rare circumstances, there may be an external request or unusual driver to provide 

such data, such as a customer need to characterize radioactive waste; NIOSH/ORAU Team

requestors should not expect such surveys to be documented via typical RWP protocols. If conditions 

exceed suspension limits, work is paused and the condition is remediated, or the RWP is revised with 

updated hazard analysis and commensurate controls [Archuleta 2022]. 

Finally, upon completion of the hot job and cleanup activities, a post job survey is typically called for. If 

conditions indicate residual contamination, a second post job survey may be included following 

additional decontamination [Archuleta 2022]. 

To summarize, the ORAU Team should expect to see pre job and post job surveys for applicable 

RWPs. Requestors should not expect to see in process hot job surveys, as RCT monitoring during hot 

jobs is typically not formally documented. These statements represent current expectations and those 

during the time period under review [Archuleta 2022].

Archuleta [2022] states that LANL does not require documented in process surveys to be conducted 

during work under RWPs and the ORAU Team should not expect find such surveys. However, some 

of these in process surveys are provided in RWP packages and examples are included. Therefore, 

the ORAU Team was tasked by NIOSH to perform a qualitative review of some RWPs that identified 

exotic radionuclides to check for the inclusion of survey information. 

The initial search used the “notable” RWPs referenced in Section 5.6 of ORAUT-RPRT-0102 [ORAUT 

2021]. Notable RWPs were targeted for capture, where a “notable” RWP is defined as an RWP that:

• Occurred within the study period (January 1, 1996, to December 31, 2001); 

• Required urinalysis as noted on the RWP by having “Special Urinalysis” or “Pu Access List” 

checked or contained other equivalent terminology or notation indicating urinalysis was 

required; and 

• Contained an associated roster (acknowledgment sheet) with names of personnel 

acknowledging the RWP.

These “notable” RWPs consisted of 316 references and 2,252 RWPs. These documents cover the 

period from January 1, 1996, to December 31, 2001, and contained no TA-53 information. Therefore, 

additional RWP information to cover the years 2002 through 2005 and TA-53 were needed, so nine 

additional references containing 311 RWPs were selected from the SRDB and reviewed. Sections 
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2.1.8, 2.2.2, 2.2.5 through 2.2.8, and all of 2.3 contain these references. All other Subsections in 

Section 2.0 are from the “notable” references mentioned above. 

Thus, the ORAU Team subjectively selected 24 RWPs by manually reviewing those that:

• Occurred within the period January 1, 1996, through December 31, 2005, from TA-3, TA-48, 

and TA-53; 

• Listed exotic and/or mixed fission and activation products as expected radionuclides; and

• Appear to be properly monitored by containing prejob, in process (which can include prejob, 

postjob, hotjob, routine, and nonroutine, smear, large area swipe (LAS), nasal smears, direct 

reading and external radiation), postjob surveys, and prejob briefing logs with names of 

personnel acknowledging the RWP. 

As a result of the selection of the 24 RWPs, the ORAU Team identified one or more radionuclides of 

interest in each of the RWPs including 137Cs (indicator radionuclide), 237Np, 57Co, 58Co, 60Co, 82Sr 

90Sr/Y, 91Nb, 92Nb, 93Nb-metastable, 232Th, 248Cm, 88Zr/Y, 68Ga/Ge, 22Na, 54Mn, 7

Be, 172Hf, 175Hf, 171Lu, 

172Lu, and 148Gd. From January 1, 1996, to the December 31, 2005, evaluation period LANL had no 

routine bioassay monitoring programs for some of these radionuclides. A bioassay method would 

have been established only if there was to be work with associated materials likely to result in intakes 

of greater than 100 mrem CED/yr. No bioassay enrollment criteria for these radionuclides were 

adopted or promulgated, but LANL had the capacity to perform bioassay for these radionuclides if 

warranted [Hoover 2008, 2021].

2.0 REVIEW OF RADIOLOGICAL WORK PERMITS

This section presents data recorded in and discussions of work and radiological monitoring for RWPs 

by technical area in order to demonstrate LANL Health Physics monitored workers for conditions of 

work that could lead to intakes of exotic radionuclides.

The ORAU Team reviewed the 24 RWPs qualitatively to ensure that the jobs specified were 

monitored appropriately by comparing prejob radiological protection requirements such as protective 

clothing, respiratory, dosimetry, and monitoring requirements to the final post job review to ensure that 

the associated reports were included. No detailed analyses of any of the air monitoring, surface 

contamination smear surveys, nasal smears, direct or external reading data presented in these RWP 

packages were performed by the ORAU Team. Primary information such as location, work to be 

performed, dates of work, radionuclide(s), airborne radioactivity, prejob surveys, postjob surveys, in

process surveys, personal protective equipment (PPE) requirements, and prejob briefing logs (Prejob 

Briefing Acknowledgment Log and/or Radiological Work Permit Acknowledgment Log depending on 

form) are summarized and reviewed in Sections 2.1, 2.2, and 2.3. 

The prejob briefing logs are required rosters signed by workers before performing work under an 

RWP and indicate that the worker understands the radiological conditions, protection requirements, 

and monitoring requirements [DOE 1998]. Note that a worker could have signed an acknowledgment 

sheet and never performed work under that RWP; it is not a sign-in sheet. The dates of these logs 

were compared to dates of the survey data in the RWP packages to ensure they are consistent. 

The survey information and associated reports provided in the RWP packages was reviewed by the 

ORAU Team and compared to the review section of the RWP to ascertain that LANL Health Physics 

appropriately monitored work performed under the RWP. Table A-1 in Attachment A provides a brief 

summary of the RWP information. 
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2.1 TA-3 

During the time of evaluation, TA-3 has conducted 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 facilities are scattered throughout the area. These range from small 

laboratories with bench-scale operations to activities involving radioactive materials in the Chemistry 

and Metallurgy Research (CMR) facility in Building 29 [Romero and Faust 1992a; LANL 1998a]. LANL 

staff at TA-3 were potentially exposed to both alpha materials and exotic radionuclides, primarily FPs. 

2.1.1 RWP 96-3-29-9030-106

LANL issued RWP 96-3-29-9030-106 (effective March 8, 1996, expiration June 28, 1996). The permit 

authorized replacing shaft bearings and a motor at FE-40, FE-41, and FE-42 in Room 9030 in 

Building 29 of TA-3 [LANL 1996, pp. 12-37].

Cesium-137 was recorded as the anticipated radionuclide. The anticipated prejob airborne 

radioactivity was reported as less than 10% of the derived air concentration (DAC). Measured prejob 

surface contamination levels for direct readings were reported as no detectable activity (NDA) for 

alpha activity and a maximum of 50,000 disintegrations per minute (dpm)/100 cm2 for beta/gamma. 

The smear surveys were reported as NDA for alpha and beta contamination. The LAS survey was 

reported as NDA for alpha and a maximum of 4,000 dpm/100 cm2 for beta/gamma. These values are 

below the limits stated in RPRT-0101. 

The RWP required Level 1 (coveralls, 2 pairs of surgeon’s gloves, and booties) protective clothing 

with skull cap and taped openings, whole body (WB) dosimeter, intermittent RCT coverage, notifying 

RCT before job starts and ends, monitoring equipment and tools before removal, and self-frisking. 

LANL Form 107-02-3, Changes to the RWP (CTRWP), was initiated for workers to work inside the fan 

housing due to a bent shaft and required an upgrade to Level 2 (2 coveralls, 2 pairs of surgeon’s 

gloves, and 2 pairs of booties) protective clothing with hood, full face respirator, job-specific air 

monitoring, nasal smears, continuous RCT coverage, and RCT monitoring doffing of anticontamination clothing (anti-Cs). The estimated airborne radioactivity was updated and reported as 

greater than 10% DAC.

Twelve workers signed the Radiological Work Permit Acknowledgment Log with dates ranging from 

June 11, 1996, through June 14, 1996. Nasal smears were collected as part of a routine procedure, 

rather than a diagnostic procedure taken in response to suspected intakes, and were used as an 

indicator for potential intakes for five workers obtained June 11, 1996, and three obtained June 14, 

1996, all reported as NDA for both alpha and beta activity. 

Eight surveys consisting of prejob, postjob, hotjob, nonroutine item release smear, LAS, external 

radiation, and direct surveys covering March 13, 1996, through June 20, 1996, were provided. The 

surveys coincide with the dates on the acknowledgment logs except for the three prejob smears, LAS, 

and direct surveys from March 13, 1996.

No postjob airborne radioactivity was recorded on the RWP. However, the job-specific air sample 

activity from June 11, 1996 to June 14, 1996 was reported as NDA for alpha and 0.07 dpm/m3 with an 

uncertainty of 17.69 dpm/m3 for beta. The postjob surface contamination direct alpha measurements 

and LAS survey were reported as NDA for the highest and general area. Direct measurements for 

beta/gamma identified fixed contamination reported as 50,000 dpm/100 cm2 for the highest area and 

as NDA for the general area. The LAS beta/gamma survey was reported as NDA. These values are 

below the limits stated in RPRT-0101. There were no postjob smears for this RWP. The checkboxes 
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in the review section for job-specific air monitoring, prejob survey data, postjob survey data, nasal 

smear data, and RWP acknowledgment log were checked and included in this RWP package. No 

personnel were contaminated above applicable limits. Review of this RWP indicates that LANL RCTs 

monitored this job appropriately.

2.1.2 RWP 96-3-29-9030B-423

LANL issued RWP 96-3-29-9030B-423 (effective November 7, 1996, expiration February 5, 1997). 

The permit authorized the installation of vibration pickups and thermocouples for filter banks located in 

Room 9030B in Building 29 of TA-3 [LANL 1996–1997, pp. 10–31].

Cesium-137 was recorded as the anticipated radionuclide. The anticipated prejob airborne 

radioactivity was reported as greater than 10% DAC. Measured prejob radiological conditions for 

surface contamination LAS were reported as NDA for alpha activity, and as 5,500 dpm beta/gamma 

activity for the highest area. These values are below the limits stated in RPRT-0101. 

For work performed on the filter banks FE-44 through 46, the RWP required Level 2 protective 

clothing, full-face respirator, WB dosimeter, continuous RCT coverage, monitoring personnel before 

leaving job, monitoring equipment and tools before removal, RCT monitoring of personnel doffing antiCs, and notifying RCT at job end. For work outside of the filter banks FE-44 through 46, the RWP 

reduced the requirement for protective clothing to Level 1, no respirator, and intermittent RCT 

coverage. Contacting an RCT before entering the fan area was an additional requirement.

Twenty-two workers signed the Radiological Work Permit Acknowledgment Log with dates ranging 

from November 14, 1996, through November 22, 1996. Nineteen nasal smears used as an indicator 

for potential intakes were obtained on November 21, 1996 and three were obtained on November 22, 

1996. Results for all 22 samples were reported as NDA for both alpha and beta activity.

Eight surveys consisting of prejob, postjob, hotjob, and routine were obtained via LAS, nasal smears, 

and fixed air samplers. These surveys were obtained with dates ranging from November 13, 1996, to 

January 7, 1997 and coincide with dates from the acknowledgment log.

The postjob review of the RWP estimated airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for surface contamination for alpha direct readings were 

reported as less than 200 dpm/100 cm2 for the highest area and as NDA for the general area. For 

beta/gamma the direct result was reported as less than 10,000 dpm/100 cm2 for the highest area and 

as NDA for the general area. Smears were marked as not applicable. The LAS survey was NDA for 

alpha and the highest beta/gamma result was reported as 4,000 dpm/100 cm2 and the general area 

as NDA. These values are below the limits stated in RPRT-0101. The checkboxes in the review 

section for prejob survey data, postjob survey data, FAS filters, nasal smear data, and RWP 

acknowledgment logs were checked and were included in the package. The postjob section of the 

RWP indicates that no personnel were contaminated above applicable limits. Review of this RWP 

indicates that LANL RCTs monitored this job appropriately.

2.1.3 RWP 97-3-29-9030-99 

LANL issued RWP 97-3-29-9030-99 (effective February 7, 1997, expiration December 24, 1997) to 

check, troubleshoot, and repair if required, the limit switches on the hot cell doors in Room 9030 in 

Building 29 of TA-3 [LANL 1997a, pp. 30–43].

Cesium-137 was recorded as the anticipated radionuclide. The measured prejob airborne radioactivity 

was reported as less than 10% DAC. There was one survey form with four LAS results considered as 

the prejob and postjob surveys for the hotjob work performed, which indicates no change in 
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radiological conditions, and an associated contamination area map on June 12, 1997. The alpha 

results were reported as NDA, and the beta/gamma results ranged from 3,000 dpm to 5,000 dpm. No 

surface area was provided. These values are below the limits stated in RPRT-0101. There was also 

one radiation area survey map from June 12, 1997.

The RWP required Level 2 protective clothing with hood, full face respirator, WB dosimeter, 

supplemental dosimeter, nasal smears, continuous RCT coverage, monitoring of personnel before 

leaving job, monitoring equipment and tools before removal, RCT monitoring of personnel doffing 

anti-Cs, and notifying RCT before and after job.

Special instructions written on the RWP stated that an RCT would monitor the worker(s) for hot 

particles every 15 minutes via WB frisk while they were working in the door cavity. If hot particles were 

identified, they were to be removed before continuing. If levels exceeded greater than 100 times LANL 

Radiological Control Table 2-2 values [Hoover 2021, p. 4] and could not be removed, work was to be 

stopped and reevaluated.

Four workers signed the RWP Acknowledgment Log, all dated June 13, 1997. Two workers submitted 

nasal smears used as an indicator for potential intakes in the morning and afternoon on June 13, 

1997; results were reported as NDA for both alpha and beta activity. Both workers were wearing 

respirators and signed the RWP Acknowledgment Log.

One air sample result was included for June 13, 1997, the same day that nasal smears were 

acquired. Note that these were collected one day after LAS and radiation area measurements were 

taken.

The postjob review of the RWP measured airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for surface contamination were reported as the same as the 

prejob. The checkboxes in the review section for prejob, postjob, nasal smears, and RWP 

acknowledgment log were checked and included in the package. No personnel were contaminated 

above applicable limits. Review of this RWP indicates that LANL RCTs monitored this job 

appropriately.

2.1.4 RWP 97-3-29-Wing 9-162

LANL issued RWP 97-3-29-Wing 9-162 (effective March 24, 1997, expiration December 24, 1997) to 

inspect, maintain, and repair as needed bridge cranes and hoists in Building 29, Wing 9 of TA-3 

[LANL 1997b, pp. 114–129].

Cesium-137 was recorded as the anticipated radionuclide. The measured prejob airborne radioactivity 

was reported as less than 10% DAC. Prejob/postjob surface contamination results from an LAS 

survey were reported as NDA for alpha activity and as NDA to 15,000 dpm for beta/gamma activity. 

No surface area was provided. These values are below the limits stated in RPRT-0101. 

The RWP required Level 1 with skull cap, no respirator, WB dosimeter, intermittent RCT coverage, 

monitoring of personnel before leaving job, monitoring equipment and tools before removal, and 

notifying an RCT before start and end of job.

This RWP had two RWP Acknowledgment Logs. Eleven workers signed one with dates ranging from 

April 14, 1997, through July 22, 1997. Twelve workers signed the second one with dates ranging from 

October 7, 1997 to November 21, 1997.

The RWP notes prejob surveys will be performed as the job progresses. Four crane inspections with 

associated smear surveys were performed on October 7, 1997, November 20, 1997, November 21, 
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1997, and December 8, 1997. Two of the surveys on November 20, and 21, 1997, indicated 

contamination was identified but was decontaminated to NDA. The November 20, 1997, survey 

indicated that the CTO-8 rail had 25 dpm/100cm2 alpha and 1,500 dpm/100cm2 beta contamination, 

and the CTO-6 rail had 48 dpm/100cm2 alpha contamination. The November 21, 1997, survey 

indicated the CTO-4 Trolley had 1,456 dpm/100cm2 beta contamination. These dates cover the 

ranges of the acknowledgment logs.

The postjob review of the RWP measured airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for surface contamination were the same as the prejob. The 

checkboxes in the review section for prejob, postjob, and RWP acknowledgment log were checked 

and included in the package. No personnel were contaminated above applicable limits. Review of this 

RWP indicates that LANL RCTs monitored this job appropriately.

2.1.5 RWP 99-3-29-1117-47

LANL issued RWP 99-3-29-1117-47 (effective December 12, 1998, expiration February 26, 2000) to 

decontaminate Rooms 1117, 1117A, and 1119 in Building 29 of TA-3 [LANL 1998–2000, pp. 2–853].

Technetium-99 and uranium were recorded as the anticipated radionuclides. The expected prejob 

airborne radioactivity was reported as less than 10% DAC. Measured prejob radiological conditions 

for both direct and smear surveys ranged from NDA to 1,000,000 dpm/100 cm2 and were from the 

August, 1991 surveys referred to on page 1 of the RWP [LANL 1998–2000, pp. 8, 73–75]. This value 

exceeds the alpha limit derived in RPRT-0101 but the RWP prescribes adequate protection 

requirements as described in the paragraphs below. The ORAU Team assumes this is the last time 

work was performed in that room because it could find no evidence to the contrary. 

The RWP required Level 2 protective clothing, full face respirator, WB dosimetry, nasal smears, 

continuous RCT coverage, monitoring of personnel before leaving job, monitoring equipment and 

tools before removal, and RCT monitoring of personnel doffing anti-Cs. Subsequent requirement 

reductions due to three CTRWPs explained below.

Two additional RWPs were included in the package to support work done under RWP 99-3-29-1117-

47. RWP 99-3-29-1117/1119-406 (effective August 18, 1999, expiration November 16, 1999) was 

initiated for tours and inspections with all activity restricted to walk-ins and visual inspection of room 

conditions, and RCT direct and smear surveys of non-intrusive items. The RWP required Level 1 skull 

cap, WB dosimeter, notifying RCT at start and finish of job, continuous RCT coverage, and RCT 

monitoring of doffing anti-Cs [LANL 1998–2000, pp. 46–53]. 

RWP 99-3-29-1117/1119-383 (effective July 16, 1999, expiration October 14, 1999) was initiated to 

install a high efficiency particulate air filter holder and filter on the inside corridor door to Room 1117A. 

The same radiological protective requirements for RWP 99-3-29-1117-47 were required.

Sixteen workers signed the RWP 99-3-29-1117-47 Prejob Briefing Acknowledgment Log with dates 

ranging from February 8, 1999, through November 22, 1999. Subsequently, there were three CTRWP 

forms with dates for change number 1 of August 24, 1999, through November 29, 1999, signed by 

17 workers, change number 2 of January 3, 2000, through January 5, 2000, signed by six workers, 

and change number 3 of January 4, 2000, through January 5, 2000, signed by five workers [LANL 

1998–2000, p. 24].

CTRWP Number 1 for RWP 99-3-29-1117-47 stated that airborne contamination levels did not justify 

respirators. Additionally, protective clothing requirements were reduced from Level 2 to Level 1 with 

skull cap. Job-specific air monitoring and a beta continuous air monitor (CAM) set for 1 DAC was 

added as a requirement. Radiological conditions were updated and direct surface contamination 
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levels for alpha were reported as less than the minimum detectable count rate; the highest direct for 

beta/gamma was reported as 320,000 dpm/100 cm2

; and the beta/gamma general area was reported 

as 750 dpm/100 cm2

. Updated smear surface contamination levels for alpha was reported as 

81 dpm/100 cm2 for the highest area and as NDA for the general area. For beta/gamma the highest 

area smear was reported as 3,256 dpm/100 cm2 and the general area was reported as 

100 dpm/100 cm2

. The measured airborne radioactivity was reported as <10% DAC for 99Tc [LANL 

1998–2000, p. 26].

CTRWP Number 2 for RWP 99-3-29-1117-47 extended the expiration date to February 26, 2000. 

Radiological conditions were updated and direct surface contamination levels for alpha were reported 

as less than the minimum detectable activity (MDA). The highest direct for beta/gamma was reported 

as 26,000 dpm/100 cm2 and the beta/gamma general area was reported as 1,000 dpm/100 cm2

. 

Updated smear surface contamination levels for alpha were reported as less than the MDA; the 

highest beta/gamma was reported as 2,000 dpm/100 cm2

; and the general area was reported as less 

than the MDA. The measured airborne radioactivity was reported as <10% DAC for 99Tc [LANL 1998–

2000, p. 28].

CTRWP Number 3 for RWP 99-3-29-1117-47 stated that air sampling results justify the discontinued 

use of CAM instruments. The updated radiological conditions were reported as the same as CTRWP 

Number 2 in the preceding paragraph [LANL 1998–2000, p. 30].

CTRWP Number 1 for RWP 99-3-29-1117/1119-406 relaxes the PPE to lab coat, skull cap, gloves, 

and booties. Updated radiological conditions for a tent enclosure indicated surface contamination 

levels for direct for both alpha and beta/gamma were less than the minimum detectable count rate. 

Smear levels were reported as NDA. The measured airborne radioactivity was reported as <10% DAC 

for 99Tc and 238U [LANL 1998–2000, p. 47].

Ten workers signed the RWP 3-29-1117/1119-406 Prejob Briefing Acknowledgment Log with dates 

ranging from August 18, 1999, through January 10, 2000. Seventeen workers signed one CTRWP 

form with dates ranging from August 26, 1999, through December 9, 1999 [LANL 1998–2000 pp. 48–

49]. Five workers signed the RWP 3-29-1117/1119-383 Prejob Briefing Acknowledgment Log with 

dates ranging from July 26, 1999, through August 12, 1999 [LANL 1998–2000, p. 59].

Nasal smears used as an indicator for potential intakes were required after jobs involving cutting of 

metal and/or wood, removal of ductwork, trash cleanup and size reduction, working around 

contaminated drain lines, and hammer drilling operations to remove floor contamination. Results of 

15 nasal survey forms with 65 individual results were obtained with dates ranging from February 8, 

1999, through January 5, 2000, and reported as NDA.

RWP 99-3-29-1117-47 was a large job containing 213 surveys consisting of prejob, postjob, routine, 

nonroutine, hotjob, item release, nasal smears, and air monitoring surveys throughout its duration. 

These surveys consisted of smears, LAS, direct readings, external radiation surveys, nasal smears, 

and air monitoring using giraffe samplers, CAMs, and a lapel sampler. The dates of the surveys 

ranged from February 8, 1999, to March 30, 2000, and coincide with dates from the acknowledgment 

logs. The rooms were kept under negative air pressure to prevent contamination spread. In many 

cases when an RCT determined values were high, the area was decontaminated. One positive smear 

of 624 dpm/100cm2 beta contamination (which did not exceed the limit of 1,000 dpm/100cm2

) was 

identified on a scaffold wheel and decontaminated. This reinforces that LANL RCTs were monitoring 

and reviewing results against regulatory limits. In addition, a Work Package was embedded in the 

RWP with craftwork instructions detailing how the remediation of Rooms 1117, 1117A, and 1119 will 

be performed [LANL 1998–2000, pp. 117–147]. 
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The postjob review of the RWP measured airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for surface contamination direct readings were reported as 

less than the MDA for alpha activity and as less than 5,000 dpm/100 cm2 for beta/gamma activity for 

the highest and general area, with the exception of two items, a sprinkler head and an emergency 

light that were reported as greater than 5,000 dpm. Smears were reported as less than the MDA for 

alpha activity and as less than 1,000 dpm/100 cm2 for the highest location and general area for 

beta/gamma. LAS were reported as less than the MDA for alpha and beta/gamma activity. These 

values are below the limits stated in RPRT-0101. The checkboxes in the review section for CAMs, job 

specific, prejob, postjob, nasal smears, changes in radiological protection requirements, and other 

prejob survey were checked and included in the package. They also stated that no problems were 

encountered. No skin contaminations occurred. Review of this RWP indicates that LANL RCTs 

monitored this job appropriately.

2.1.6 RWP 99-3-29-9030, 9060-144

LANL issued RWP 99-3-29-9030, 9060-144 (effective January 16, 1999, expiration December 31, 

1999) to decontaminate under cell door numbers 10 and 12 in Rooms 9030 and 9060 in Building 29 of 

TA-3. Temporary enclosures to contain hot particles were designed and fabricated [LANL 1999a, 

pp. 17–37].

Cesium-137 was recorded as the anticipated radionuclide. The anticipated prejob airborne 

radioactivity was reported as less than 10% DAC. The prejob radiological conditions for surface 

contamination with direct readings were reported as 20,000 dpm/100 cm2 for the highest alpha activity 

and as NDA for the general area. Direct readings for beta/gamma were reported as greater than 

1,000,000 dpm/100 cm2 for the highest area and as 1,000 dpm/100 cm2 for the general area. The 

surface contamination for the highest and general area alpha smear activity was reported as NDA; the 

beta/gamma highest activity was reported as 56,000 dpm/100 cm2

; and the general area was reported 

as 1,000 dpm/100 cm2

. LAS activity for the highest area for alpha activity was reported as 

5,000 dpm/100 cm2 and the general area was reported as NDA. LAS for beta/gamma activity was 

reported as 100,000 dpm/100 cm2 for the highest area and the general area was reported as 

10,000 dpm/100 cm2

. Some of these values exceed the alpha limit derived in RPRT-0101 but the 

RWP prescribes adequate protection requirements as described in the paragraphs below.

The RWP required Level 2 protective clothing with hood and taped openings, full face respirator, WB

dosimeter, supplemental dosimeter, continuous RCT coverage, monitoring personnel before leaving 

job, and monitoring of equipment and tools before removal. A CTRWP was initiated as radiological 

conditions reduced. Level 1 protective clothing with skull cap and taped openings, no respirator, 

intermittent RCT coverage, and notifying RCT before job starts and ends was required. Radiological 

conditions were updated to not applicable for direct alpha and beta/gamma activity, NDA for the 

highest and general area alpha smears, 4,322 dpm/100 cm2 for the highest area for beta/gamma 

activity, and NDA for the general area. LAS for alpha activity was reported as NDA for the highest and 

general area for alpha activity and as 500 dpm/100 cm2 for the highest beta/gamma activity with NDA 

for the general area.

Two workers signed the Prejob Briefing Acknowledgment Log on January 21, 1999. Eight workers 

signed the CTRWP acknowledgment form with dates ranging from January 25, 1999, through 

February 9, 1999. One nasal smear used as an indicator for potential intakes obtained for a worker on 

January 22, 1999, was reported as NDA for alpha and beta activity.

Seven prejob, hotjob nonroutine, nasal smears, and postjob smear and LAS surveys were obtained 

from January 19, 1999, to February 9, 1999. These dates coincide with dates from the 

acknowledgment log.
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The postjob review of the RWP airborne radioactivity was determined to be not applicable. Measured 

postjob radiological conditions for surface contamination direct readings for alpha activity were 

reported as 20,000 dpm/100 cm2 for the highest area and as NDA for the general area. Direct 

readings for beta/gamma were reported as greater than 7,000,000 dpm/100 cm2 for the highest area 

and as 1,000 dpm/100 cm2 for the general area. Smears were reported as NDA for the highest and 

general area for alpha activity; as 56,000 dpm/100 cm2 for the highest beta/gamma smear; and as 

1,000 dpm/100 cm2 for the general area. LAS surveys were reported as NDA for alpha activity; as 

13,000 dpm/100 cm2 for the highest beta/gamma area; and as NDA for the general area. These 

values are below the limits stated in RPRT-0101. The checkboxes in the review section for prejob 

survey data, postjob survey data, nasal smear data, and prejob briefing log were checked and 

included in the RWP package. A nonroutine LAS floor survey annotated as during job was also 

included. No skin contaminations occurred. Review of this RWP indicates that LANL RCTs monitored 

this job appropriately.

2.1.7 RWP 99-3-29-4064-361

LANL issued RWP 99-3-29-4064-361 (effective July 6, 1999, expiration December 24, 1999) to 

decontaminate Room 4064 in Building 29 of TA-3 [LANL 1999b, pp. 17–61].

Technetium-99 and uranium were recorded as the anticipated radionuclides. The anticipated prejob 

airborne radioactivity was reported as less than 10% DAC. The measured prejob radiological 

conditions for surface contamination with direct readings were reported as 1,000 dpm/100 cm2 for the 

highest alpha activity and as NDA for the general area. Direct readings for beta/gamma were reported 

as 1,000,000 dpm/100 cm2 for the highest area and as NDA for the general area. The measured 

surface contamination for the highest alpha smear activity was reported as 2,000 dpm/100 cm2 and 

the general area was reported as less than the MDA. This value exceeds the alpha limit derived in 

RPRT-0101 but the RWP prescribes adequate protection requirements as described in the 

paragraphs below. For beta/gamma smears, the highest result was reported as 1,000,000 dpm/100 

cm2 and the general area was reported as less than the MDA.

The RWP required Level 2 protective clothing with hood and taped openings, full face respirator, WB

dosimetry, continuous RCT coverage, monitoring of equipment and tools before removal, RCT 

monitoring of personnel doffing anti-Cs, and notifying RCT before job starting. The RWP included an 

additional stipulation for inspections with no hands-on work and called for Level 1 protective clothing 

with no respirator requirement.

Twelve workers signed the RWP Acknowledgment Log with dates ranging from July 7, 1999 to 

August 27, 1999. There were six CTRWP forms and they are summarized below.

A CTRWP was initiated on July 28, 1999, due to a change in radiological conditions. The monitoring 

requirements changed from continuous RCT coverage to intermittent RCT coverage. Radiological 

conditions were updated and surface contamination levels for alpha smears were reported as 

525 dpm/100 cm2 for the highest location and as less than the MDA for the general area. Seventeen 

workers signed the acknowledgment form with dates ranging from July 28, 1999, to August 24, 1999.

A second CTRWP was initiated on August 18, 1999, due to possible contamination in a high efficiency 

particulate air inlet filter for a hood. The monitoring requirement for this work required continuous RCT 

coverage and Level 1 protective clothing with plastic or paper sleeves. Prejob and postjob smears 

were reported as less than the MDA for alpha and beta/gamma. Five workers signed the 

acknowledgment form with dates ranging from August 18, 1999, to August 27, 1999.

A third CTRWP was initiated on August 25, 1999, due to decontamination and associated activities in 

Rooms 4066 and 4068. This was associated with Radiological Incident Report (RIR) 99-29-4064-102. 
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The highest alpha surface contamination smear obtained was reported as 200 dpm/100 cm2 and the 

general area was reported as NDA. The beta/gamma smears were reported as less than the MDA. 

LAS floor surveys were reported as NDA for both alpha and beta/gamma. Five workers signed the 

acknowledgment form with dates ranging from August 20, 1999, to August 30, 1999.

A fourth CTRWP was initiated on August 31, 1999, due to the need to add a smoke test to the RWP. 

A Special Work Permit (SWP) was initiated on August 31, 1999, to address this smoke test. A glove 

on a glovebox was lost and this smoke test was initiated to determine the turbulence and air 

movement pattern in Room 4064. The updated radiological conditions were reported as less than 

250 dpm/100 cm2 for the highest alpha smear and as NDA for the general area. For the beta/gamma 

smears the highest result was reported as less than 1,000 dpm/100 cm2 and the general area as 

NDA. Nine workers signed the acknowledgment form with dates ranging from September 2, 1999, to 

September 7, 1999.

A fifth CTRWP was initiated on September 7, 1999, to add a sprayer to the insides of the gloveboxes 

in Room 4064. The updated radiological conditions were reported as less than 100 dpm/100 cm2 for 

the highest alpha smear and as NDA for the general area. For the beta/gamma smears, the highest 

result was reported as less than 231 dpm/100 cm2 and the general area was reported as NDA. LAS 

floor surveys were reported as NDA for alpha and beta/gamma. Seven workers signed the 

acknowledgment form with dates ranging from September 9, 1999, to October 6, 1999.

A sixth and final CTRWP initiated on October 7, 1999, reduced the requirement for tours and normal 

work to lab coat with gloves and booties with taped openings, no respirator, and intermittent RCT 

coverage with the requirement to notify an RCT before the start and at the end of a job. The updated 

radiological conditions for surface contamination smears were reported as less than 400 dpm/100 cm2

for the highest location and as NDA for the general area for alpha and beta/gamma. LAS floor surveys 

were reported as NDA. Fourteen workers signed the acknowledgment form with dates ranging from 

October 7, 1999, to November 3, 1999.

Eight surveys were provided in this RWP package consisting of prejob, postjob, hotjob, and 

nonroutine smear, LAS, and external radiation surveys. The dates ranged from August 1, 1999, to 

September 7, 1999, and coincide with dates from the acknowledgment log. 

There were several smear surveys identified as greater than LANL Radiological Control Table 2-2 

limits [Hoover 2021, p. 4] in this RWP package. One survey obtained on the north wall of a glovebox 

exceeded the beta/gamma limit of 1,000 dpm/100cm2

. It was noted as decontaminated to NDA. This 

reinforces that LANL RCTs were monitoring and reviewing results against regulatory limits.

The postjob review of the RWP measured airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for surface contamination smears were reported as less 

than 400 dpm/100 cm2 for the highest location and as NDA for the general area for alpha and 

beta/gamma. LAS surveys were reported as NDA for alpha and beta/gamma. These values are below 

the limits stated in RPRT-0101. The checkboxes in the review section for prejob and postjob were 

checked and included in the RWP package. The RWP acknowledgment log and six CTRWPs were 

also included. No skin contaminations occurred. Review of this RWP indicates that LANL RCTs 

monitored this job appropriately.

2.1.8 RWP 04-03-29-4064-275

LANL issued RWP 04-03-29-4064-275 (effective January 5, 2004, expiration December 31, 2004) to 

perform an initial survey for contamination assessment, decontaminate affected areas, and 

investigate cause and repair as needed if contamination was found for Room 4064 in Building 29 of 

TA-3 [LANL 2004–2005, pp. 12–73].
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 19 of 38

Technetium-99 and uranium were recorded as the anticipated radionuclides. The expected prejob 

airborne radioactivity was reported as less than 10% DAC. The measured prejob radiological 

conditions for surface contamination smears for alpha activity was reported as 63 dpm/100 cm2 for the 

highest area and as NDA for the general area. Beta/gamma smears were reported as 

83,000 dpm/100 cm2 for the highest area and as NDA for the general area. LAS for alpha was 

reported as NDA for the highest and general area. LAS for beta/gamma was reported as 

33,000 dpm/100 cm2 for the highest area and as 1,000 dpm/100 cm2 for the general area. These 

values are below the limits stated in RPRT-0101. Direct readings were determined to be not 

applicable.

The RWP required Level 1 protective clothing without respirator for work in the buffer area around the 

high contamination area during decontamination efforts and Level 2 protective clothing if working in 

the high contamination area, with hood, taped openings, anti-C gloves, and booties, full face 

respirator, job-specific air monitoring, WB dosimeter, continuous RCT coverage, monitoring of 

equipment and tools before removal, RCT monitoring personnel before leaving job, RCT monitoring of 

personnel doffing anti-Cs, and notifying RCT before job starts and ends.

Two workers signed the Prejob Briefing Log on April 28 and 29, 2004. 

Eleven surveys were performed for this RWP, and the types were prejob, routine, and nonroutine

LAS, and nonroutine and postjob for smears. Three of the surveys were from a previous 2003 RWP 

03-03-29-4064-275 and were used as the initial assessment for work to be performed for this RWP. 

The other surveys dates ranged from May 3, 2004, to October 4, 2004, and coincide with dates from 

the acknowledgment log.

There were several LAS and smear surveys identified as greater than LANL Radiological Control 

Table 2-2 limits [Hoover 2021, p. 4] in this RWP package. These surveys were of the floor below 

gloveboxes. The RWP noted areas that could not effectively be decontaminated because leaching 

from the glovebox leg pads had been painted over to seal the contamination. This reinforces that 

LANL RCTs were monitoring and reviewing results against regulatory limits.

The postjob review of the RWP measured airborne radioactivity was reported as NDA. Measured 

postjob radiological conditions for surface contamination alpha activity was reported as 

49 dpm/100 cm2 for the highest area and as NDA for the general area. For beta/gamma smears the 

highest area was reported as 83,185 dpm/100 cm2 and as 1,480 dpm/100 cm2 for the general area. 

LAS surveys were all reported as NDA for alpha and beta/gamma for the highest and general area. 

These values are below the limits stated in RPRT-0101. Direct readings were determined to be not 

applicable. The checkboxes in the review section for prejob survey data, postjob survey data, and 

prejob briefing log were checked and included in the RWP package. Nonroutine surveys were also 

included. No skin contaminations occurred. Review of this RWP indicates that LANL RCTs monitored 

this job appropriately.

2.2 TA-48

TA-48 is known as the Radiochemistry Site. The facilities at TA-48 supported 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. 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]. Activities at Building RC-1 included small-scale 
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 20 of 38

 

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].

2.2.1 RWP TA-48-98-46

LANL issued RWP TA-48-98-46 (effective July 22, 1998, expiration July 22, 1999) to cover general 

maintenance and decontamination of all acid line plumbing in RC-1 of TA-48 [LANL 1998b, pp. 172–

244].

All radionuclides used at TA-48 were recorded as the anticipated radionuclides. The anticipated 

prejob DAC was reported as NDA. Prejob surface contamination levels were reported as 

16,500 dpm/100 cm2 for the highest direct alpha reading and less than the MDA for the general area. 

The highest direct reading for beta/gamma was reported as 36,000 dpm/100 cm2 and less than the 

MDA for the general area. The highest result of alpha smear surface contamination was reported as 

5,000 dpm/100 cm2 and less than the MDA was reported for the general area. This value exceeds the 

alpha limit derived in RPRT-0101 but the RWP prescribes adequate protection requirements as 

described in the paragraphs below. For beta/gamma the highest smear was reported as 35,000 

dpm/100 cm2 and the general area as less than the MDA.

The RWP required Level 2 protective clothing, waterproof if systems breached, full face respirator 

which can be removed if removable contamination is less than 50,000 dpm beta/gamma or less than 

5,000 dpm alpha, WB thermoluminescent dosimeter (TLD), supplemental dosimeter, nasal smears,

intermittent RCT coverage, notifying RCT before job starts and ends, self-frisking, monitoring of 

equipment and tools before removal, monitoring personnel before leaving job, and Job Specific air 

monitoring via a giraffe sampler.

Eleven workers signed the Prejob Briefing Acknowledgment Log with dates ranging from October 10, 

1998, through October 20, 1998. Five workers had positive beta nasal smears that did not exceed the 

limit of 500 dpm sum of both nostrils from a hotjob on October 17, 1998, which would not require a 

followup bioassay sample [LANL 1998c, p. 2]. The alpha results were reported as NDA. The jobspecific air sample results covering this job were reported as NDA. Three of the five were wearing 

respirators [LANL 1998b, p. 225].

A Special Work Procedure titled Acid Waste Line Repair TA-48, B-001, C1 Basement provided a 

procedure for decontaminating and patching leaks [LANL 1998b, pp. 176–178].

Fourteen prejob, postjob, hotjob, and nonroutine surveys consisting of smears, LAS, direct, nasal, jobspecific air monitoring, and a liquid sample were performed with dates ranging from September 4, 

1998 to December 7, 1998. The maintenance started on October 16, 1998, which covers the 

acknowledgment log dates. Six surveys performed had an RIR number 48-98-40 written on their 

associated forms. This RIR occurred on July 15, 1998, a week before the initiation of this RWP [LANL 

1998c, pp. 128–134].

There were several direct and smear surveys identified as greater than LANL Radiological Control 

Table 2-2 limits [Hoover 2021, p. 4] in this RWP package. The samples were from the floor area 

below a leaking pipe and were successfully decontaminated. This reinforces that LANL RCTs were 

monitoring and reviewing results against regulatory limits.

The postjob review of the RWP measured airborne radioactivity was reported as less than MDA. 

Measured postjob radiological conditions were all reported as NDA. These values are below the limits 
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 21 of 38

 

stated in RPRT-0101. The checkboxes in the review section for job specific, prejob, postjob, nasal 

smears and RWP acknowledgment log were checked and included in the package. There was a 

lessons learned statement that all personnel involved in decontaminating and repair of acid line 

plumbing need to be actively involved in the planning process to address all potential hazards. No 

skin contaminations occurred. Review of this RWP indicates that LANL RCTs monitored this job 

appropriately.

2.2.2 RWP TA-48-98-62

LANL issued RWP TA-48-98-62 (effective November 10, 1998, expiration November 10, 1999) to 

offload targets in the warm corridor of RC-1 Hot Cell of TA-48 [LANL 1998–1999, pp. 8–37].

Mixed activation products (MAPs) were recorded as the anticipated radionuclides. The anticipated 

prejob airborne radioactivity was reported as NDA. Anticipated surface contamination values were 

reported as not applicable for alpha direct and as NDA for beta/gamma direct. Anticipated alpha 

smears and LAS were reported as NDA and beta/gamma highest anticipated value was reported as 

greater than 1,000 dpm/100 cm2

. Anticipated beta/gamma LAS was reported as NDA. These values 

are below the limits stated in RPRT-0101. 

The RWP required Level 1 protective clothing with hood, WB dosimeter, supplemental dosimeter, 

continuous RCT coverage, notifying RCT before job starts and ends, self-frisking, monitoring of 

equipment and tools before removal, and monitoring personnel before leaving job.

Ten workers signed the Prejob Briefing Acknowledgment Log with dates ranging from November 30, 

1998, through December 21, 1998.

Eleven surveys consisting of prejob, hotjob, routine, nonroutine, postjob, and item release smear and 

LAS surveys were performed from December 1, 1998, to November 30, 1999. These dates cover the 

acknowledgment dates. Posting and Area Sweep Checklists for CST-SOP-326 covering several days 

were included, and mention of SOP-326 is in the hold point or special instructions portion of the RWP

that provides individual dose limits, collective dose limits, contamination limits, and other instructions. 

Hot Cell dose rate maps were also included with this RWP.

The postjob review of the RWP measured airborne radioactivity was reported as less than MDA. 

Measured postjob radiological conditions were all marked as not applicable for direct, NDA for alpha 

smear and LAS (including beta/gamma), and 5,000 dpm/100 cm2 for the highest beta/gamma smear 

and 1,000 dpm/100 cm2 for the general area. These values are below the limits stated in RPRT-0101. 

The checkboxes in the review section for prejob, postjob, and RWP acknowledgment log were 

checked and included in the package. Additionally, there were in process routine and hotjob surveys. 

A lessons learned statement indicates there are no beta/gamma direct reading surveys because the 

warm corridor background is too high and there has been no airborne radioactivity. No skin 

contaminations occurred. Review of this RWP indicates that LANL RCTs monitored this job 

appropriately.

2.2.3 RWP TA-48-98-47

LANL issued RWP TA-48-98-47 (effective July 24, 1998, expiration December 30, 1998) for the 

removal of gloveboxes in Room 430 in RC-1 of TA-48 [LANL 1998b, pp. 245–261].

All radionuclides associated with shot debris (uranium, transuranic, MAP, MFP) were recorded as the 

anticipated radionuclides [ORAUT 2004, p. 15]. The measured prejob airborne radioactivity was 

reported as NDA. Measured surface contamination results for alpha were reported as less than the 

MDA for direct surveys for the highest and general area and as 59.5 dpm/100 cm2 for the highest 
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 22 of 38

 

area; less than the MDA for the general area for smears; and less than the MDA for LAS surveys for 

the highest and general area. Measured surface contamination results for beta/gamma were reported 

as less than the MDA for direct surveys for the highest and general area; as 243.3 dpm/100 cm2 for 

the highest area; less than the MDA for the general area for smears, and less than the MDA for LAS 

surveys for the highest and general area. These values are below the limits stated in RPRT-0101. 

The RWP required Level 1 protective clothing with hood and taped openings, full-face respirator, WB 

dosimeter, intermittent RCT coverage, notifying RCT before job starts and ends, self-frisking, 

monitoring of equipment and tools before removal, and monitoring personnel before leaving job. 

Additional special instructions were that respirators may be removed if removable contamination is 

less than 50,000 dpm beta/gamma or less than 5,000 dpm for alpha. Lab coat and gloves with taped 

openings may be worn if prejob survey results are less than respirator requirements. Gloveboxes

were to be wiped down before starting the job. The surrounding area was to be masked with plastic to 

minimize spread of contamination, and an RCT will perform a postjob survey to ensure surrounding 

area is less than MDA.

Three workers signed the Prejob Briefing Acknowledgment Log on August 24, 1998.

Two prejob surveys and one postjob smear survey were provided in this RWP package. There is 

evidence that other in process surveys were performed and not included in the RWP package. There 

were lessons learned stating that the greatest amount of contamination was located under the 

gloveboxes as they were lifted. This contamination was due to spills over the years seeping under the 

gloveboxes and there was no way to clean without lifting the glovebox. On the surveys provided there 

were no locations identified as under a glovebox. This reinforces an answer LANL Health Physics 

staff provided the ORAU Team on a January 26, 2022, conference call. The ORAU Team asked 

about in process surveys because some RWPs typically lasted for approximately a year and there 

appeared to be gaps. LANL Health Physics staff stated that it was the nature of their work to 

decontaminate and perform surveys as work progressed, they did not generally include those surveys 

in the RWP packages, and the ORAU Team should not necessarily expect to see them [Archuleta 

2022].

Six smears from inside of the gloveboxes had maximum results of 45 dpm/100cm2 alpha 

contamination and 341 dpm/100cm2 beta contamination. The ORAU Team assumes the respiratory 

requirements stated in the above paragraph likely were removed due to these low levels of 

contamination inside the gloveboxes. Based on survey data in various sections of this report, it is 

evident that LANL RCTs were vigilant and were monitoring and reviewing results against regulatory 

limits. If the respiratory requirement was removed, it is unlikely that further work would have caused 

contamination limits to be exceeded. 

No airborne radioactivity was measured on the postjob review of the RWP. Measured postjob 

radiological conditions for surface contamination for alpha direct survey was reported as 

57 dpm/100 cm2 for the highest area and as 8 dpm/100 cm2 for the general area. Alpha smears were 

reported as 52 dpm/100 cm2 for the highest area and as not applicable for the general area. The LAS 

surveys were reported as less than the MDA for the highest and general area. Measured post job 

radiological conditions for surface contamination for beta/gamma direct survey were reported as 

2,000 dpm/100 cm2 for the highest area and as 400 dpm/100 cm2 for the general area. Beta/gamma 

smears were reported as 2,000 dpm/100 cm2 for the highest area and as not applicable for the 

general area. The LAS surveys were reported as less than the MDA for the highest and general area.

These values are below the limits stated in RPRT-0101. The checkboxes in the review section for 

prejob survey data, postjob survey data, and prejob briefing log were checked and included in the 

package in addition to a lessons learned statement. No skin contaminations occurred. Review of this 

RWP indicates that LANL RCTs monitored this job appropriately.
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2.2.4 RWP TA-48-98-50

LANL issued RWP TA-48-98-50 (effective August 6, 1998, expiration August 6, 1999) to transport 

accelerator production of tritium (APT) foil stacks from CMR in steel containers to Building 311 of 

TA-48 [LANL 1998b, pp. 383–404].

MAPs were recorded as the anticipated radionuclides. The anticipated prejob airborne radioactivity 

was reported as NDA. Prejob measured surface contamination values were reported as NDA for 

direct and smear, and LAS alpha and beta/gamma for both the highest area and the general area.

These values are below the limits stated in RPRT-0101. 

The RWP required a lab coat with taped openings and gloves, WB dosimeter, supplemental 

dosimeter, TLD finger rings, intermittent RCT coverage, monitoring personnel before leaving job, 

monitoring equipment and tools before removal, and notifying RCT before job starts and ends. There 

were hold point or special instructions as follows: 

• 40 mrem hold point per person. 

• RCT will dose rate and monitor incoming APT foil shipment. 

• Proper postings and ALARA safeguards such as minimizing time, distance, and shielding. 

• RCT will perform a prejob and postjob LAS to ensure outer hood and surrounding area 

remains less than MDA. 

• During initial unpacking, RCT will check for radiation streaming and ensure adequate shielding 

is in place. 

• All APT foils will be remotely handled. 

• RCT coverage is not required once APT foils are taped to counting plate and sent to Room 24 

for analysis. When analysis is complete, operators will wipe down equipment and ensure area 

is free from contamination.

• Operator will ensure APT foils are properly stored in RAD safe or hood and dose rate remains 

less than 5 mrem/hr at 30 cm. 

• All APT foil handling will be performed in an operational hood in Room 311 except during 

analysis in Room 24. 

• Finger rings and supplemental dosimeter will be worn at all times while working with APT foils. 

Nine workers signed the Prejob Briefing Acknowledgment Log with dates ranging from August 12, 

1998, through December 17, 1998. There was one CTRWP issued stating that continuous coverage 

is only required to unpack APT foils. Safety glasses were added as a requirement to be worn. 

Measured radiological conditions for surface contamination remained unchanged from the prejob 

surveys. An updated measured airborne radioactivity was reported as NDA. Six workers signed the 

form with dates ranging from December 17, 1998, to May 11, 1999.

Twenty surveys consisting of prejob and postjob smears, LAS, and external radiation surveys were 

obtained from May 11, 1998, to May 11, 1999. The dates are consistent with the acknowledgment 

logs. An annotation for lessons learned indicated additional postjob surveys are contained in monthly 

and quarterly routine monitoring instructions for Room 311. ALARA actions included placing additional 
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shielding in the hood to minimize streaming. The RWP package included a foil activation analysis 

status/progress memo relevant to this RWP from RWP TA-48-98-11 dated March 30, 1998.

The postjob review of the RWP estimated airborne radioactivity was reported as NDA. Measured 

surface contamination was NDA for direct, smear, and LAS surveys for alpha and beta/gamma activity

for the highest area and general area. These values are below the limits stated in RPRT-0101. The 

checkboxes in the review section for job-specific air monitoring and postjob survey data were 

checked. However, no job-specific results were included or required according to the RWP, but as 

mentioned above on the CTRWP form, the airborne activity was marked as measured. Additionally, 

prejob surveys and a lessons learned statement were included. No skin contaminations occurred. 

Review of this RWP indicates that LANL RCTs monitored this job appropriately.

2.2.5 RWP TA-48-03-01

LANL issued RWP TA-48-03-01 (effective January 10, 2003, expiration December 31, 2003) to 

inspect the radiological inventory in hot cell pits in RC-1, Room 322 of TA-48 [LANL 2003a, pp. 322–

331]. 

MAPs were recorded as the anticipated radionuclides. The expected prejob airborne radioactivity was 

reported as less than 10% DAC. Prejob anticipated radiological conditions for surface contamination 

for direct alpha readings were reported as NDA for the highest area and general area and the 

beta/gamma direct survey was marked as not applicable. The smear surveys were reported as less 

than the MDA for alpha and beta/gamma for both the highest area and general area. LAS surveys 

were reported as NDA for alpha and beta/gamma for both the highest area and general area. These 

values are below the limits stated in RPRT-0101. 

The RWP required a lab coat with anti-Cs gloves and booties, WB dosimeter, supplemental 

dosimeter, extremity dosimeter, continuous RCT coverage, monitoring personnel before leaving job, 

monitoring equipment and tools before removal, and notifying RCT before job starts. If surface 

contamination levels exceeded 10 times the Appendix A level of the LANL Radiation Protection 

Program, work was to be stopped and reevaluated. If radiation levels exceed 40 mrem/hr at 30 cm, 

work will stop to reevaluate implementation of engineering controls. Only the inventory verifier is 

required to wear extremity and supplemental dosimetry if the dose rate of 40 mrem/hr at 30 cm is 

exceeded.

Thirteen workers signed the Prejob Briefing Log with dates ranging from January 17, 2003, to 

March 20, 2003.

Four surveys consisting of prejob, hotjob and postjob smears and an external radiation survey were 

obtained on March 20, 2003, which covers the dates of the Prejob Briefing Log. A Supplemental 

Dosimetry Issue Sheet for one worker was included as well.

The postjob review of the RWP measured airborne radioactivity was marked as not applicable.

Measured postjob radiological conditions for surface contamination for alpha direct surveys were 

reported as NDA for the highest area and general area and as not applicable for beta/gamma. The 

smear surveys were reported as less than MDA for alpha and beta/gamma for the highest area and 

general area. LAS surveys were reported as NDA for alpha and beta/gamma for the highest and 

general areas. These values are below the limits stated in RPRT-0101. The checkboxes in the review 

section for prejob survey data, postjob survey data, dose tracking report, and prejob briefing log were 

checked and included in this RWP package. No skin contaminations occurred. Review of this RWP 

indicates that LANL RCTs monitored this job appropriately.
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2.2.6 RWP TA-48-03-08

LANL issued RWP TA-48-03-08 (effective January 13, 2003, expiration December 31, 2003) to 

perform warm corridor and hot cell entries for health physics, waste, maintenance, and shipping 

operations in Building 1, Room 332 at TA-48 [LANL 2003a, pp. 221–249].

MAPs were recorded as the anticipated radionuclides. The anticipated prejob airborne activity was 

reported as less than 10% of the DAC. Prejob measured surface contamination values were reported 

as NDA for direct, smear, and LAS alpha surveys. Measured beta/gamma smears were reported as 

80,000 dpm/100 cm2 for the highest area and as 10,000 dpm/100 cm2 for the general area. These 

values are below the limits stated in RPRT-0101. Direct and LAS surveys for beta/gamma were 

marked as not applicable.

The RWP required Level 1 protective clothing with hood with taped openings, WB dosimeter, 

supplemental dosimeter, intermittent RCT coverage, notifying RCT before job starts and ends, 

monitoring of equipment and tools before removal, and monitoring personnel before leaving job. 

Additional hold point/special instructions called for respiratory protection for hot cell entry where 

volatile radionuclides or chemicals have been processed.

Eight workers signed the Prejob Briefing Log with dates ranging from February 3, 2003, through 

April 9, 2003.

Twenty-four surveys consisting of routine smear surveys and radiation surveys occurred on an 

approximate monthly basis throughout the duration of this RWP. Both types of surveys were 

performed on the same day. Twelve of each type were included in this RWP package and they cover 

the dates of the acknowledgment logs. On the review section of the RWP under lessons learned, it 

was noted that monthly mopping of the warm corridor greatly reduced contamination and dose levels 

from previous years. There was a recommendation to maintain the monthly mopping schedule for 

future similar jobs.

The postjob review of the RWP measured airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for surface contamination for alpha smears were reported as 

less than MDA for the highest and general area. For beta/gamma smears the highest result was 

reported as 6,000 dpm/100 cm2 and 3,000 dpm/100 cm2 for the general area. These values are below 

the limits stated in RPRT-0101. Direct and LAS surveys were marked as not applicable. The 

checkbox in the review section for monthly surveys was checked and the surveys were included in the 

RWP package in addition to a lessons learned statement. No skin contaminations occurred. Review of 

this RWP indicates that LANL RCTs monitored this job appropriately.

2.2.7 RWP TA-48-03-09

LANL issued RWP TA-48-03-23 (effective February 10, 2003, expiration March 7, 2003) to 

decontaminate Room 413 in RC-1 of TA-48 [LANL 2003b, pp. 2–42].

Strontium/yttrium-90 were recorded as the anticipated radionuclides. The measured prejob airborne 

radioactivity was reported as less than 10% DAC. Prejob measured surface contamination values for 

smears were reported as less than the MDA for the highest and general area and as not applicable for 

direct and LAS. Measured beta/gamma smears was reported as 340,000 dpm/100 cm2 for the highest 

area and as not applicable for the general area. An LAS survey of the highest area was reported as 

500,000 dpm/100 cm2 and as not applicable for the general area. These values are below the limits 

stated in RPRT-0101. Direct surveys were marked as not applicable. An ALARA review checklist was 

also provided for this RWP.
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 26 of 38

 

The RWP required Level 2 protective clothing, full-face respirator WB dosimeter, supplemental 

dosimeter, extremity dosimeter, continuous RCT coverage, and notifying RCT before job starts. A 

hold point was required for torn PPE. If EPDs alarm, the job and dose exposure minimization 

techniques would be reevaluated.

Seven workers signed the Prejob Briefing Log with dates ranging from February 10, 2003, through 

February 11, 2003.

Nine surveys consisting of prejob, postjob, hotjob, and nonroutine smear, external radiation surveys, 

and job-specific air sampling results covering February 10, 2003, through February 13, 2003, were 

included. There were two accompanying survey maps. The surveys cover the dates on the 

acknowledgment logs. A worker dose tracking report and extremity exposure results were also 

included in this RWP.

The postjob review of the RWP measured airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for surface contamination for alpha and beta/gamma direct 

surveys were reported as less than the MDA for the highest and general area. The smears and LAS 

surveys were reported as NDA for the highest and general area. These values are below the limits 

stated in RPRT-0101. The checkboxes in the review section for job-specific air monitoring, prejob 

survey data, postjob survey data, dose tracking report, prejob briefing log, and ALARA review 

checklist were checked and included in the RWP package. No skin contaminations occurred. Review 

of this RWP indicates that LANL RCTs monitored this job appropriately.

2.2.8 RWP TA-48-03-23

LANL issued RWP TA-48-03-23 (effective September 10, 2003, expiration December 31, 2003) to 

clean up hoods in RC-1 of TA-48 [LANL 2003a, pp. 85–99].

A mixture of 91Nb, 92Nb, 93Nb-metastable, 94Nb, depleted uranium (DU), 232Th, 239Pu, 242Pu, 243Am, 

248Cm, 237Np, 88Zr/Y, 83Rh, 75Se, 68Ga/Ge, and 22Na were recorded as the anticipated radionuclides. 

The expected prejob airborne radioactivity was reported as less than 10% DAC. Prejob measured 

radiological conditions for surface contamination for alpha were reported as NDA for direct, less than 

MDA for smears, and not applicable for LAS. For beta/gamma the direct readings were reported as 

NDA, the smears were reported as less than the MDA, and as not applicable for LAS. These values 

are below the limits stated in RPRT-0101. 

The RWP required Level 1 protective clothing, WB dosimeter, intermittent RCT coverage, notifying 

RCT before job starts, and RCT monitoring of bagged items leaving hoods. Additional hold 

point/special instructions were for torn PPE, contamination found outside of the hoods, and 

contamination or dose rates exceeding expected levels.

Six workers signed the Prejob Briefing Log with dates ranging from September 10, 2003, through 

September 25, 2003.

Fifteen surveys consisting of prejob, hotjob, and postjob smear, direct, and radiation surveys were 

performed covering September 10, 2003, through September 25, 2003. These dates coincide with the 

acknowledgment logs.

There were several smear surveys identified as greater than LANL Radiological Control Table 2-2 

limits [Hoover 2021, p. 4] inside the hoods in this RWP package. This is expected because the 

purpose of this RWP was to decontaminate hoods. This reinforces that LANL RCTs were monitoring 

and reviewing results against regulatory limits.
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 27 of 38

 

The postjob review of the RWP estimated airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for surface contamination for alpha direct surveys were 

reported as NDA for the highest and general area and the smears were reported as less than MDA for 

the highest and general area. These values are below the limits stated in RPRT-0101. LAS surveys 

were marked as not applicable. The checkboxes in the review section for prejob, postjob, and prejob 

briefing log were checked and included in this RWP package. No skin contaminations occurred. 

Review of this RWP indicates that LANL RCTs monitored this job appropriately.

2.3 TA-53

TA-53 housed the Los Alamos Neutron Science Center. During the period of this evaluation, TA-53 

had approximately 400 buildings and other structures. 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]. LANL staff at TA-53 were potentially exposed to both alpha materials and 

exotic radionuclides that were chiefly activation and spallation products, some with short half-lives.

2.3.1 RWP 1999-122-01

LANL issued RWP 1999-122-01 (effective June 7, 1999, expiration September 30, 1999) to set up an 

area in and around A-East for removal of inserts in the A-6 pit and culvert area of Sector M of 

Building 3 of TA-53 [LANL 1999c, pp. 290–384].

Cobalt-60, 57Co, 58Co, 54Mn, 7

Be, and 22Na were recorded as the anticipated radionuclides. The 

anticipated prejob airborne radioactivity was reported as less than 10% DAC. Prejob measured 

radiological conditions for surface contamination for beta/gamma smear and LAS surveys were 

reported as greater than 100,000 dpm/100 cm2

. This value could potentially exceed the limit stated in 

RPRT-0101. All other prejob surveys were marked as not applicable.

The RWP required Level 1 protective clothing with skull cap and taped openings with RCT authority to 

upgrade or downgrade based on current surveys, WB TLD, EPD, notifying RCT before job starts, 

monitoring personnel before leaving job, monitoring equipment and tools before removal, continuous 

RCT coverage, and RCT monitoring doffing of anti-Cs. After setup of this job, operations were to be 

done remotely and personnel will only make entries to change tools on monitor in a low exposure 

area. This RWP package contained an SWP titled Special Work Permit for Cutting Experiments from 

their A6 Inserts to aid operators in preventing accidents and releases of radioactive material, as well 

as four cask radiation surveys. The SWP states contamination levels up to several million 

dpm/100cm2 can be expected. The highest result noted in this RWP package was an LAS beta survey 

of a landing and tool change area with 115,500 dpm. No surface area given.

Twenty-two workers signed the Prejob Briefing Acknowledgment Log with dates ranging from June 8, 

1999, to September 20, 1999. Thirty nasal smears used as an indicator for potential intakes were 

obtained and all were reported as NDA. No forms were associated with these individual workers.

Twenty surveys of routine smear and LAS, nonroutine LAS, offsite item release, radiation surveys, 

and nasal smears were provided in this RWP package. Additionally, 125 air sample analyses of jobspecific and CAMs were provided. Eleven air samples had positive results and combined 

radionuclides such as 7

Be, 56Co, 57Co, 58Co, 60Co, 54Mn, 22Na, 83Rb, 46Sc, and 75Se were identified. 

The date ranges for these surveys covered July 22, 1999, to September 24, 1999. The surveys are 

consistent with the dates on the acknowledgment logs. A table with weekly exposures from July 19, 

1999, to September 26, 1999 was included. Prejob radiological conditions did not require air sampling 

or respirators initially; there was a caveat for an RCT to upgrade requirements, which was done, 

showing RCTs reacted to changing conditions during the job.
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 28 of 38

 

The postjob review of the RWP measured airborne radioactivity was reported as less than 10% DAC.

The measured postjob radiological conditions for surface contamination was reported as less than 

100,000 dpm/100 cm2 for beta/gamma smears and as 684 dpm/100 cm2 for beta/gamma LAS. These 

values are below the limits stated in RPRT-0101. All other postjob surface contamination surveys 

were marked as not applicable. The checkboxes in the review section for CAM results, job-specific air 

monitoring, prejob survey data, postjob survey data, nasal smear data, dose tracking report, and RWP 

acknowledgment log were checked and included in this RWP package. No personnel were 

contaminated above applicable limits. Review of this RWP indicates that LANL RCTs monitored this 

job appropriately.

2.3.2 RWP 2001-035-01

LANL issued RWP 2001-035-01 (effective February 14, 2001, expiration May 31, 2001) to replace 

target system Culligan bottles in the Service Area, Target 1L in Building 7 of TA-53 [LANL 2001, 

pp. 86–154].

Cobalt-57, 60Co, 175Hf, 171Lu, 54Mn, and 22Na were recorded as the expected radionuclides. The 

anticipated prejob airborne radioactivity was reported as less than 10% DAC. Prejob measured 

radiological conditions for surface contamination for beta/gamma were reported as 

2,100 dpm/100 cm2 from a LAS survey. These values are below the limits stated in RPRT-0101. All 

other prejob surveys were marked as not applicable.

The RWP required Level 2 protective clothing with skull cap and taped openings with RCT authority to 

change pending contamination levels, splash anti-Cs with face shield recommended if water is

present, full face respirator with RCT having authority to change respiratory requirements pending 

contamination levels, job-specific air monitoring via giraffe sampler, WB TLD, EPD, notifying RCT 

before job starts, self-frisking, monitoring personnel before leaving job, monitoring equipment and 

tools before removal, and continuous RCT coverage.

Twelve workers signed the Prejob Briefing Acknowledgment Log with dates ranging from February 20, 

2001, through May 23, 2001. Nasal smears used as an indicator for potential intakes were obtained 

for two workers and both workers signed the RWP acknowledgment log. However, no results were 

included in this RWP package. An RWP worksheet mentions them being processed [LANL 2001, p.

97].

Twenty-four surveys consisting of prejob, postjob, hotjob, routine, and nonroutine smear, LAS, jobspecific air sampling, and external radiation surveys covering February 5, 2001, through June 16, 

2001, were provided. Many have accompanying maps. The surveys are consistent with the dates on 

the acknowledgment logs. Also included were RWP worksheets summarizing activities performed for 

the duration of this RWP and worker EPD goals for the RWP.

There were several LAS and smear surveys identified as greater than LANL Radiological Control 

Table 2-2 limits [Hoover 2021, p. 4] in this RWP package. This reinforces that LANL RCTs were 

monitoring and reviewing results against regulatory limits.

The postjob review of the RWP estimated airborne radioactivity was reported as less than 10% DAC. 

Measured postjob radiological conditions for beta/gamma smears was reported as 

25,155 dpm/100 cm2 and as 15,300 dpm/100 cm2 for beta/gamma LAS. These values are below the 

limits stated in RPRT-0101. All other prejob surface contamination values were marked as not 

applicable. The checkboxes in the review section for job specific air monitoring, prejob survey data, 

postjob survey data, dose tracking report, and RWP acknowledgment log were checked and included

in the package. No personnel were contaminated above applicable limits and there were no 
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 29 of 38

 

annotations of lessons learned. Review of this RWP indicates that LANL RCTs monitored this job 

appropriately.

2.3.3 RWP 2002-006-01

LANL issued RWP 2002-006-01 (effective January 7, 2002, expiration March 31, 2002) for the 

installation of traps in three radioactive liquid waste lines in Experimental Area Room 1 on the lower 

floor in Building 7 of TA-53 [LANL 2002, pp. 406–442].

Cobalt-57, 60Co, 172Hf, 172Lu, 54Mn, and 22Na were recorded as the expected radionuclides. The 

estimated prejob airborne radioactivity was reported as less than 10% DAC. Prejob anticipated 

radiological conditions for alpha surface contamination for LAS were reported as less than 

20 dpm/100 cm2 and as 500,000 dpm/100 cm2 for beta/gamma. These values are below the limits 

stated in RPRT-0101. Direct and smear surveys were marked as not applicable.

The RWP required Level 2 protective clothing with outer pair of waterproof coveralls if water is 

present, full face respirator, WB TLD, alarming dosimeter, i.e., EPD if working in target cell only, 

continuous RCT coverage, notifying RCT before job starts, self-frisking, monitoring of equipment and 

tools before removal, RCT monitoring of doffing anti-Cs, frisking through the personnel contamination 

monitor (PCM) in Experimental Area Room 2, and job specific air monitoring via a giraffe sampler. 

Water lines were to be flushed before commencing this job and plastic was to be laid down.

Seven workers signed the Prejob Briefing Acknowledgment Log with dates ranging from January 14, 

2002, through January 19, 2002. Nasal smears used as an indicator for potential intakes were taken 

for six workers and all results were NDA for alpha and beta radioactivity. Nasal smears were not a 

requirement of this RWP, and a postjob survey included six respirator smear results that were less 

than MDA. This reinforces that LANL RCTs were monitoring and reviewing results against regulatory 

limits and were taking conservative steps to ensure worker safety. All of the workers signed the RWP 

acknowledgment log.

Twelve surveys consisting of prejob and postjob smear, LAS, nasal smears, and job-specific air 

sampling radiation survey from January 5, 2002, to February 7, 2002, were provided. One job-specific 

air sample analyzed via gamma spectroscopy identified 7

Be, 172Lu, 175Hf, and 173Lu, and the reported 

levels were below the limits stated in RPRT-0101. The surveys are consistent with the dates on the 

acknowledgment logs.

The postjob review of the RWP estimated airborne radioactivity was reported as less than 10% DAC.

Measured postjob radiological conditions for surface contamination were marked as not applicable for 

direct, less than LANL Radiological Control Table 2-2 limits [Hoover 2021, p. 4] for smears, and as 

less than 1,000 dpm/100 cm2 for beta/gamma LAS. These values are below the limits stated in RPRT0101. The checkboxes in the review section for job specific, prejob, postjob, nasal smears, and RWP 

acknowledgment log were checked and included in the package. No personnel were contaminated 

above applicable limits. Review of this RWP indicates that LANL RCTs monitored this job 

appropriately.

2.3.4 RWP 2002-007-01

LANL issued RWP 2002-007-01 (effective January 7, 2002, expiration July 31, 2002) to open the 

1L hydrogen system cold box following a move from a service area in MPF-7, Room 200 (1LSA) to 

repair and rebuild for reinstallation in Building 3 of TA-53 [LANL 2002, pp. 443–498].

Cobalt-57, 60Co, 172Hf, 172Lu, 54Mn, and 22Na were recorded as the expected radionuclides. The 

estimated prejob airborne radioactivity was reported as less than 10% DAC. Prejob measured 
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 30 of 38

 

radiological conditions for surface contamination were marked as not applicable except for a reported 

result of 2,000 dpm/100 cm2 for beta/gamma LAS. This value is below the limit stated in RPRT-0101. 

The RWP required Level 2 protective clothing with RCT authority to change pending contamination 

levels, full face respirator with RCT having authority to change respiratory requirements pending 

contamination levels, WB TLD, notifying RCT before job starts, self-frisking via PCM-1B, monitoring of 

equipment and tools before removal, continuous RCT coverage, and job specific air monitoring via a 

giraffe sampler if contamination exceeds 100,000 dpm.

Fourteen workers signed the RWP 2002-007-01 Prejob Briefing Acknowledgment Log with dates 

ranging from February 1, 2002, through February 27, 2002.

Twenty-three surveys consisting of prejob, postjob, hotjob, routine, nonroutine, and offsite shipments 

for smear, LAS, external radiation, direct, and job-specific air samples were provided. The surveys 

were performed from January 23, 2002, to March 5, 2002. These dates are consistent with the signed 

acknowledgment logs. A Special Work Permit for Repair of Components Inside the Hydrogen 

Moderator System Cold Box was included in this RWP package (LANL 2002 pp. 453–465). It lists 

detailed procedures for accessing and repairing the unit.

There were several beta/gamma LAS and smear surveys identified as greater than LANL Radiological 

Control Table 2-2 limits [Hoover 2021, p. 4] in this RWP package; the highest was 18,600 

dpm/100cm2

. This reinforces that LANL RCTs were monitoring and reviewing results against 

regulatory limits.

The postjob review of the RWP measured airborne radioactivity was reported as less than MDA. 

Measured postjob radiological conditions for surface contamination were marked as not applicable 

except for reported results of beta/gamma less than Table 2-2 limits [Hoover 2021 p.4] for smears and 

less than background for beta/gamma LAS. These values are below the limits stated in RPRT-0101. 

The checkboxes in the review section for job specific, prejob, postjob, and RWP acknowledgment log 

were checked and included. No personnel were contaminated above applicable limits. Review of this 

RWP indicates that LANL RCTs monitored this job appropriately.

2.3.5 RWP 2003-001-01

LANL issued RWP 2003-001-01 (effective January 2, 2003, expiration December 24, 2003) to operate 

the 1L Target systems in the Building 7 Service Area of TA-53 [LANL 2003c, pp. 2–101].

Cobalt-60, 59Fe, 172Lu, and 54Mn were recorded as the expected radionuclides. The anticipated prejob 

airborne radioactivity was reported as less than 10% DAC. The prejob surface contamination smear 

for beta/gamma provided was reported as 50,000 dpm/100 cm2

. This value is below the limit stated in 

RPRT-0101. 

The RWP required Level 2 protective clothing with RCT authority to adjust PPE, splash anti-Cs with 

face shield if free liquids are present, WB TLD, EPD turned in daily, notifying RCT before job starts 

and ends, monitoring equipment and tools before removal, self-frisking via PCM, and continuous RCT 

coverage.

Seventeen workers signed the RWP Prejob Briefing Acknowledgment Log with dates ranging from 

January 27, 2003, through August 12, 2003.

Forty-two surveys consisting of prejob, postjob, hotjob, routine, and nonroutine smear, LAS, external 

radiation, and direct surveys were provided. The surveys covered dates from January 2, 2003, 

through June 24, 2003. Many have accompanying maps. The surveys are consistent with the dates 
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 31 of 38

 

on the acknowledgment logs. RWP worksheets summarizing activities performed for the duration of 

this RWP were included. Prejob and postjob LAS surveys performed on August 20, 2003, were not 

included in this RWP package. They did record the results as less than MDA on an RWP worksheet 

and this appears to be the last day work was performed under this RWP. Worker EPD goals and 

actual dose for this RWP were included. 

There were several beta/gamma LAS and smear surveys identified as greater than LANL Radiological 

Control Table 2-2 limits [Hoover 2021, p. 4] in this RWP package; the highest was 547,000 

dpm/100cm2

. This reinforces that LANL RCTs were monitoring and reviewing results against 

regulatory limits. 

The postjob review of the RWP estimated airborne radioactivity was recorded as less than 10% DAC. 

The postjob beta/gamma smear was recorded as 9,000 dpm/100 cm2 and the LAS was reported as 

500,000 dpm/100 cm2

. These values are below the limits stated in RPRT-0101. Alpha surface 

contamination surveys were marked as not applicable. The radionuclides differed from page 1 of the 

RWP and they are recorded as measured for 57Co, 58Co, and 60Co. There is no information in this 

RWP package as to why these changed. The checkboxes in the review section for prejob, postjob, 

special dosimetry results, formal ALARA review, and RWP acknowledgment log were checked and 

included in this RWP package. RWP worksheets were also included. No personnel were 

contaminated above applicable limits. Review of this RWP indicates that LANL RCTs monitored this 

job appropriately.

2.3.6 RWP 2003-022-01

LANL issued RWP 2003-022-01 (effective January 28, 2003, expiration July 20, 2003) to perform 

maintenance and upgrades to 1L water, hydrogen and instrumentation control systems located in the 

Target Cell and Pump Alcove in support of a 2003 outage at 1L Target systems in the Building 7 

Service Area of TA-53 [LANL 2003c, pp. 102–276].

Cobalt-60, 59Fe, 172Lu, and 54Mn were recorded as the expected radionuclides. The anticipated prejob 

airborne radioactivity was reported as less than 10% DAC. The measured prejob surface 

contamination LAS for beta/gamma was recorded as 20,000 dpm/100 cm2

. This value is below the 

limit stated in RPRT-0101. All other prejob surface contamination values were marked as not 

applicable.

The RWP required Level 2 protective clothing, full-face respirator until RCT gives approval to remove, 

WB TLD, EPD turned in daily, notifying RCT before job starts and ends, monitoring equipment and 

tools before removal, monitoring personnel before leaving job, monitor EPDs, continuous RCT 

coverage, all items released by RCT, and personnel exit via PCM.

Twenty-four workers signed the RWP Prejob Briefing Acknowledgment Log with dates ranging from 

February 10, 2003, through June 11, 2003.

Seventy-four surveys consisting of prejob, postjob, hotjob, routine, and nonroutine smear, LAS, and 

external radiation surveys were provided. The dates ranged from January 28, 2003, through June 16, 

2003. Many have accompanying maps. The surveys are consistent with the dates on the 

acknowledgment logs. RWP worksheets summarizing activities performed for the duration of this 

RWP, EPD tracking records, and worker goals and actual dose were included for this RWP.

There were several LAS and smear surveys identified as greater than LANL Radiological Control 

Table 2-2 limits [Hoover 2021, p. 4] in this RWP package. One smear survey from inside a cask

exceeded the beta/gamma limit of 1,000 dpm/100cm2

. This reinforces that LANL RCTs were 

monitoring and reviewing results against regulatory limits.
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 32 of 38

 

The postjob review of the RWP estimated airborne radioactivity was recorded as less than 10% DAC. 

The postjob surface contamination LAS for beta/gamma provided was recorded as 230 dpm/100 cm2

. 

This value is below the limit stated in RPRT-0101. All other postjob surface contamination values 

were marked as not applicable. The checkboxes in the review section for prejob, postjob, special 

dosimetry results, dose tracking report, formal ALARA review, and acknowledgment log were checked 

and included in this RWP package. No personnel were contaminated above applicable limits. Review 

of this RWP indicates that LANL RCTs monitored this job appropriately.

2.3.7 RWP 2004-054-01

LANL issued RWP 2004-054-01 (effective April 27, 2004, expiration May 20, 2004) for a target 

shipment from the New Isotope Production Facility Building 984 in TA-53 [LANL 2004, pp. 346–366]. 

Strontium-82 was recorded as the expected radionuclide. The anticipated prejob airborne radioactivity 

was reported as less than 10% DAC. Prejob anticipated surface contamination levels were reported 

as less than 20 dpm/100 cm2 for alpha and reported as less than 1,000 dpm/100 cm2 for beta/gamma.

These values are below the limits stated in RPRT-0101. 

The RWP required Level 1 protective clothing, monthly TLD, continuous RCT coverage, notifying RCT 

before job starts and ends, self-frisking, and monitoring of equipment and tools before removal.

Eight workers signed the Prejob Briefing Acknowledgment Log with dates ranging from April 20, 2004, 

through May 12, 2004.

Eleven surveys consisting of consisting of prejob, postjob, hotjob, and nonroutine smear, LAS, and 

external radiation, and direct surveys were provided. The dates ranged from April 20, 2004 to May 14, 

2004. These surveys are consistent with the dates on the acknowledgment logs. RWP worksheets 

summarizing activities performed for the duration of this RWP and EPD dose tracking records were 

included. 

One LAS survey result of 1,110 dpm/100cm2 beta/gamma exceeded the LANL Radiological Control 

Table 2-2 limits [Hoover 2021, p. 4] value of 1,000 dpm/100cm2

. The location was decontaminated. 

This reinforces that LANL RCTs were monitoring and reviewing results against regulatory limits.

The postjob review estimated airborne radioactivity was reported as less than 10% DAC. Measured 

postjob radiological conditions surface contamination were marked as not applicable except for LAS 

beta/gamma reported as less than 1,000 dpm/100 cm2

. This value is below the limit stated in RPRT0101.The checkboxes in the review section for prejob, postjob, RWP acknowledgment log, dose 

tracking, and RWP worksheets were checked and included in the package. No personnel were 

contaminated above applicable limits and there were no annotations of lessons learned. Review of 

this RWP indicates that LANL RCTs monitored this job appropriately.

2.3.8 RWP 2004-128-01

LANL issued RWP 2004-128-01 (effective December 9, 2004, expiration December 31, 2004) to 

perform contamination surveys to characterize, post, establish controls, and establish the 

decontamination efforts required for the Building 7 Service Area and Crypt, Target 1L and 1LSA in 

TA-53 [LANL 2004 pp. 367–414].

Gadolinium-148, 60Co, 57Co, 22Na, 54Mn, and 172Lu were recorded as the expected radionuclides. The 

anticipated prejob airborne radioactivity was reported as less than 10% DAC. The prejob measured 

LAS surface contamination level for beta/gamma was reported as 33,304 dpm/100 cm2 and noted as

not applicable for alpha. This value is below the limit stated in RPRT-0101. 
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 33 of 38

 

The RWP required Level 2 protective clothing, monthly TLD, EPD, continuous RCT coverage, 

notifying RCT before job starts and ends, self-frisking, monitoring of personnel before leaving job, job 

specific air monitoring via a giraffe sampler, monitoring of equipment and tools before removal, shoe 

survey, RCT monitoring for doffing anti-Cs, and frisking.

Four workers signed the Prejob Briefing Acknowledgment Log on December 9, 2004.

Eight surveys consisting of prejob, postjob, hotjob, routine, and nonroutine smear, LAS, external 

radiation, and job-specific air samples were provided. The dates ranges from October 26, 2004 to 

February 1, 2005. Several of these surveys were outside of the date ranges for this RWP. They were 

recorded on a review of reports sheet provided. They were a monthly smear survey used as prejob 

from October 26, 2004, two postjob smear surveys acquired on January 6, 2005 and January 31, 

2005, a postjob direct survey from January 31, 2005, and a postjob LAS from February 1, 2005. A 

gamma spectroscopy analysis of the job-specific air sample filter positively identified 173Lu. The 

surveys coincide with the dates on the acknowledgment logs. RWP worksheets summarizing activities 

performed for the duration of this RWP were included as were EPD tracking records.

Many hotjob characterization smear surveys not held to any LANL Radiological Control Table 2-2 

limits [Hoover 2021, p. 4] had positive results for alpha and beta/gamma. One other hot job smear 

survey had several results exceeding Table 2-2 alpha and beta/gamma limits. This reinforces that 

LANL RCTs were monitoring and reviewing results against regulatory limits.

The postjob measured airborne radioactivity was reported as less than 10% DAC. Measured postjob 

radiological conditions for alpha surface contamination levels were reported as 6.34 dpm/100 cm2 for 

the highest area and as less than the MDA for the general area. The highest beta/gamma level was 

reported as 508.19 dpm/100 cm2 and the general area was reported as 200 dpm/100 cm2

. LAS levels 

for beta/gamma were reported as 5.2 dpm/100 cm2 and as 3.46 dpm/100 cm2 for the general area. 

These values are below the limits stated in RPRT-0101. The checkboxes in the review section for jobspecific air monitoring, prejob, postjob, special dosimetry, dose tracking report, and RWP 

acknowledgment log were checked and included in the package. No personnel were contaminated 

above applicable limits. Review of this RWP indicates that LANL RCTs monitored this job 

appropriately.

3.0 SUMMARY AND CONCLUSION

In this report that supplements information and conclusions presented in RPRT-0101, the ORAU 

Team subjectively reviewed 24 RWP packages from LANL for areas TA-3, TA-48, and TA-53 where 

the primary anticipated radionuclides were other than plutonium, americium and uranium. Prejob 

surveys, in process surveys, postjob surveys, and radiological conditions were reviewed to ensure 

that RCT monitoring was appropriately performed to ensure worker safety. RWP requirements for 

PPE, dosimetry, respiratory protection, and prejob acknowledgment logs indicating the worker 

understood the monitoring requirements were reviewed. Nasal smears were included in nine of the 

RWPs and were used to indicate potential intakes.

The ORAU Team review of RWPs in Sections 2.1, 2.2, and 2.3 concludes that LANL Health Physics, 

via intermittent RCT and/or continuous RCT coverage, appropriately monitored jobs covered by 

RWPs. The ORAU Team examined monitoring data around the dates recorded by workers on the 

prejob briefing logs to assess if Health Physics personnel monitored the job and work conditions. 

Instances presented by CTRWP Form and/or hold point and special instructions show that LANL 

RCTs reacted to changing radiological conditions to protect worker safety. The review of these RWP 

packages supports the premise that LANL Health Physics personnel monitored workers for nonroutine

radiological work conditions and radiological situations, reinforcing the conclusion in RPRT-0101 that 

could have led to LANL workers receiving intakes of exotic radionuclides in excess of 100 mrem 
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 34 of 38

CED/yr. LANL maintained the capacity to perform bioassay for these radionuclides if that had been 

warranted [Hoover 2008, 2021].
Document No. ORAUT-RPRT-0103 Revision No. 00 Effective Date: 08/15/2022 Page 35 of 38

 

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0 Effective Date: 08/15/2022 Page 38 of 38

ATTACHMENT A 

SUMMARY OF RWP INFORMATION

Table A-1. Summary of RWP information. 

RWP number TA Radionuclide(s)

Number of 

signatures 

signed logs

Nasal smears 

(Y-#/N) RCT coverage

Number of

surveys 

provided

96-3-29-9030B-423 3 Cs-137 22 Y-22 Continuous and intermittent 8

96-3-29-9030-106 3 Cs-137 12 Y-8 Continuous and intermittent 8

99-3-29-1117-47 3 Tc-99, U 44 Y-65 Continuous 213

97-3-29-9030-99 3 Cs-137 4 Y-2 Continuous 4

97-3-29-Wing 9-162 3 Cs-137 22 N Intermittent 6

99-3-29-4064-361 3 Tc-99, U 69 N Continuous and intermittent 8

01-03-29-4064-275 3 Tc-99, U 2 N Continuous 11

99-3-29-9030, 9060-144 3 Cs-137 10 Y-1 Continuous and intermittent 7

TA-48-98-46 48 All used at TA-48 11 Y-5 Intermittent 14

TA-48-98-62 48 MAP 10 N Continuous 11

TA-48-98-47 48 All associated with shot debris 3 N Intermittent 3

TA-48-98-50 48 MAP 15 N Intermittent 20

TA-48-03-08 48 MAP 8 N Intermittent 24

TA-48-03-23 48 Nb-91, Nb-92, Nb-93m, Nb-94, DU, Th-232, 

Pu-239, Pu-242, Am-243, Cm-248, Np-237, 

Zr/Y-88, Rh-83, Se-75, Ga/Ge-68, Na-22 

8 N Intermittent 15

TA-48-03-01 48 MAP 13 N Continuous 4

TA-48-03-09 48 Sr/Y-90 7 N Continuous 9

1999-122-01 53 Co-60, Co-57, Co-58, Mn-54, Be-7, Na-22 22 Y-30 Continuous 20

2001-035-01 53 Co-57, Co-60, Hf-175, Lu-171, Mn-54, Na-22 12 Y-2 Continuous 24

2002-006-01 53 Co-57, Co-60, Hf-172, Lu-172, Mn-54, Na-22 7 Y-6 Continuous 12

2002-07-01 53 Co-57, Co-60, Hf-172, Lu-172, Mn-54, Na-22 14 N Continuous 23

2003-001-01 53 Co-60, Fe-59, Lu-172, Mn-54 17 N Continuous 42

2003-022-01 53 Co-60, Fe-59, Lu-172, Mn-54 24 N Continuous 74

2004-054-01 53 Sr-82 8 N Continuous 11

2004-128-01 53 Gd-148, Co-60, Co-57, Na-22, Mn-54, Lu-172 4 N Continuous 8