Page 1 of 54

DOE Review Release 02/13/2017

Potential Neptunium Exposure to Plutonium 

Fuel Facility Construction Workers in 

Building 235-F at the Savannah River Site

ORAUT-RPRT-0080 Rev. 00

Effective Date: 02/07/2017

Supersedes: None

Subject Expert(s): Roger Halsey and Edward D. Scalsky

Document Owner 

Approval: Karin A. Jessen Signature on File for

James M. Mahathy, Document Owner

Approval Date: 01/25/2017

Concurrence: Signature on File

Daniel H. Stempfley, Objective 4 Representative

Concurrence Date: 01/25/2017

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 01/25/2017

Approval: Signature on File

James W. Neton, Associate Director for Science

Approval Date: 02/07/2017

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-0080 Revision No. 00 Effective Date: 02/07/2017 Page 2 of 54

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

02/07/2017 00 New report about neptunium exposure to the plutonium fuel facility 

construction workers in Building 235-F at the Savannah River Site. 

Incorporates formal internal and NIOSH review comments. Training 

required: As determined by the Objective Manager. Initiated by 

James M. Mahathy. 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 3 of 54

 

TABLE OF CONTENTS

SECTION TITLE PAGE

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

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

2.0 Neptunium Billet Work.............................................................................................................. 6

3.0 Construction of the Facility..................................................................................................... 11

4.0 Radiological Controls ............................................................................................................. 12

5.0 Conclusion ............................................................................................................................. 16

References ........................................................................................................................................ 18

ATTACHMENT A SELECTED BUILDING 235-F AIR CONCENTRATIONS................................ 23

ATTACHMENT B AIR MONITORING QUALITY ASSURANCE REPORT................................... 29

ATTACHMENT C PROBABILITY PLOTS OF AIR CONCENTRATIONS..................................... 35

ATTACHMENT D NEPTUNIUM BILLETS FABRICATED DURING THE DESIGN AND 

CONSTRUCTION OF THE PuFF.................................................................... 41

ATTACHMENT E CONSTRUCTION AREA PHOTOGRAPHS.................................................... 46

LIST OF TABLES

TABLE TITLE PAGE

2-1 Radiation levels from selected Mark 53A neptunium billets...................................................... 8

2-2 Radiation levels from selected Mark 42 plutonium billets ......................................................... 8

2-3 Air concentrations from routine air samples in Building 235-F, 1973 to January 1977.............. 9

D-1 Neptunium billet fabrication during design and construction, 1973 to 1977 ............................ 41
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 4 of 54

LIST OF FIGURES

FIGURE TITLE PAGE

2-1 Building 235-F First Floor Plan.................................................................................................7

2-2 Neptunium glovebox line..........................................................................................................7

2-3 Neptunium billet glovebox line..................................................................................................8

3-1 PuFF construction progress and air sample results in the construction area .......................... 11

4-1 Typical airflow survey for Building 235-F................................................................................ 15

A-1 Construction area air concentrations, February 12, 1974, to December 28, 1976 .................. 24

A-2 Clean Corridor East air concentrations, January 4, 1974, to January 31, 1977 ...................... 24

A-3 Regulated Corridor (107F) air concentrations, January 4, 1974, to January 31, 1977 ............ 25

A-4 Room 107A air concentrations, December 28, 1973, to January 28, 1977............................. 25

A-5 Room 107D air concentrations, December 31, 1973, to January 31, 1977............................. 26

A-6 Room 107B air concentrations, December 31, 1973, to January 31, 1977............................. 26

A-7 Room 160 air concentrations, December 31, 1973, to January 31, 1977 ............................... 27

A-8 Room 162 air concentrations, December 31, 1973, to January 31, 1977 ............................... 28

C-1 Air concentrations against standard normal quantiles, construction areas and Room 

107C ......................................................................................................................................36

C-2 Air concentrations against standard normal quantiles, Clean Corridor East ........................... 37

C-3 Air concentrations against standard normal quantiles, Regulated Corridor............................. 37

C-4 Air concentrations against standard normal quantiles, Room 107A........................................ 38

C-5 Air concentrations against standard normal quantiles, Room 107D........................................ 38

C-6 Air concentrations against standard normal quantiles, Room 107B........................................ 39

C-7 Air concentrations against standard normal quantiles, Room 160 .......................................... 39

C-8 Air concentrations against standard normal quantiles, Room 162 .......................................... 40

E-1 Worker readying to pour concrete, April 4, 1973 .................................................................... 47

E-2 Roof above the PuFF Facility in Building 235-F, April 4, 1973................................................ 48

E-3 Additional work on the roof of Building 235-F, April 4, 1973 ................................................... 49

E-4 Glovebox housing area during construction, December 11, 1973........................................... 50

E-5 Concrete removal in glovebox housing area, April 4, 1974..................................................... 51

E-6 Completed hot cell structure, February 26, 1975.................................................................... 52

E-7 Construction of a support room, February 26, 1975 ............................................................... 52

E-8 Duct work in construction area, November 20, 1976 .............................................................. 53

E-9 Room construction, November 20, 1976 ................................................................................ 54

E-10 Room construction demonstrating safety awareness and hazard markings, November 

20, 1976.................................................................................................................................54
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 5 of 54

ACRONYMS AND ABBREVIATIONS

cm centimeter

cpm counts per minute

DOE U.S. Department of Energy

dpm disintegrations per minute

ft foot

GM geometric mean

GSD geometric standard deviation

HEPA high-efficiency particulate air

HP health physics

hr hour

H&V heating and ventilation

in. inch

kg kilogram

mrad millirad

mrem millirem

NBL Neptunium Billet Line

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

PuFF 238PuO2 Plutonium Fuel Form Facility

qtr quarter

R roentgen

SRDB Ref ID Site Research Database Reference Identification (number)

SRS Savannah River Site

TLD thermoluminescent dosimeter

yr year

μCi microcurie
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 6 of 54

1.0 INTRODUCTION

Operations at the neptunium billet line in Building 235-F at the Savannah River Site (SRS) continued 

during the construction of the Plutonium Fuel Form Facility (PuFF) in the same building. Construction 

started in 1973 and was complete in January 1977. However, equipment acceptance tests and 

procedures preparation began earlier, and test runs were conducted through June 1977, with cold 

runs completed in July 1977.

The purpose of this discussion is to determine if workers constructing the PuFF facility received 

significant exposure from the work in the neptunium billet line. To this end, it is first necessary to 

review operations during the construction period and to determine the radiological conditions that 

existed at the time. The source of potential neptunium and plutonium exposure to construction 

workers would be expected to result from the operations in the neptunium billet line facility.

2.0 NEPTUNIUM BILLET WORK

Building 235-F was part of original construction at SRS in the early 1950s. It hosted various 

production missions through its operational life. Three of the facilities in Building 235-F are the 

Actinide Billet Line (which in this paper is called the Neptunium Billet Line or NBL), the Alloy Line, and 

the PuFF.

The Alloy line was constructed in the 1960s to cast and machine uranium alloyed metal cores. It 

operated until the early 1970s and was decontaminated and decommissioned in 1984 and 1985 (DOE 

1996, p. 236).

Figure 2-1 presents the layout of the first floor of Building 235-F. Note that “A/L” indicates the 

locations of air locks between rooms. Rooms 107A, 107D, and 107B contained the NBL, designated 

as “AB Line” in this floor plan. The Operations side was in Room 107A and the Maintenance side of 

the line was in Room 107D. The end of the line, where the billets were removed, was in Room 107B

(DuPont 1974l, 1980). The Alloy Line can be seen in Figure 4-1, below, in the area that later became 

Rooms 160 and 162 in Figure 2-1. It divided this area vertically with the operations side on the left 

and the maintenance side on the right as viewed in this figure (DuPont 1975c, p. 135; DuPont 1969,

p. 12).

Rooms 1002, 1003, and 1004 in Figure 2-1 comprised the PuFF. Room 1005 between the neptunium 

facility and the PuFF was a regulated storage room for PuFF. It should be noted that Room 123 

designates the men’s change room, and Room 136 designates the women’s change room.

Figure 2-2 shows the neptunium glovebox line. This is in a fairly small room with several gloveboxes. 

This photo shows the front side of the gloveboxes with several technicians and supervisors observing 

the work. The technicians are dressed in protective clothing and appear to be wearing pocket 

dosimeters on the upper left part of their clothing. On their waists, they are wearing bellybutton 

dosimeters because there was a significant gamma and neutron dose rate emanating from the 

neptunium inside the gloveboxes.

Figure 2-3 provides two photos of the maintenance side of the neptunium glovebox line. Billets were 

taken out of the line at the end, smeared for contamination, and packaged for transfer to storage or to 

building 321M for further operations. The wrapped billets are shown on the floor in the left photo.

Tables 2-1 and 2-2 list examples of the neutron and gamma dose rates on several neptunium and 

plutonium billets before transfer to another facility for storage or further processing. Although the 

neptunium billets were processed in August 1980, and the plutonium billets in April 1980, the radiation 

levels should be representative of those during the PuFF construction period. Note that the gamma 
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Figure 2-1. Building 235-F First Floor Plan (Taylor and Phifer 2012, p. 55). 

Figure 2-2. Neptunium glovebox line (DuPont ca. 1975) (DPSPF 30200-6). 
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Figure 2-3. Neptunium billet glovebox line (NIOSH 2014). 

Table 2-1. Radiation levels from selected Mark 53A neptunium billets.a 

Billet #

γ + nf at 8 cm 

(mrem/hr) nf at 8 cm

Fixed alpha 

contamination, 

top 

<3,000 dpm

Fixed alpha 

contamination, 

bottom/sides 

<3,000 dpm

Fixed alpha 

contamination, 

bottom/sides 

<1,000 dpm

NJ 393 710 10 <3,000 <500 <1,000

NJ 394 702 2 <3,000 <500 <1,000

NJ 395 1,010 10 <3,000 <500 <1,000

NJ 396 900 5 <3,000 <500 <1,000

NJ 397 1,050 5 <4,000 <1,000 <1,000

NJ 398 1,005 5 <5,000 <1,000 <1,000

NJ 399 900 3 <3,000 <500 <1,000

NJ 400 800 5 <3,000 <500 <1,000

a. Source: NIOSH (2014). 

Table 2-2. Radiation levels from selected Mark 42 plutonium billets.a 

Billet #

γ + nf at 8 cm 

(mrem/hr) nf at 8 cm

Fixed alpha 

contamination, 

top and sides, 

<1,000 dpm

Fixed alpha 

contamination, 

bottom, 

<3,000 dpm

6063 120 20 Yes Yes

3060 140 20 Yes Yes

3063 160 30 Yes Yes

3064 180 50 Yes Yes

3065 165 15 Yes Yes

2064 120 20 Yes Yes

6075 115 15 Yes Yes

3066 140 40 Yes Yes

a. Source: NIOSH (2014). 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 9 of 54

dose rates for the neptunium billets are higher than for the plutonium billets, whereas the neutron 

dose rates are higher for the plutonium billets (NIOSH 2014). Fixed alpha contamination levels for the 

sides, top, and bottom of each billet were measured for compliance with the existing criteria. For the 

alpha levels in these examples, either a checkmark was used or a dpm value with a less than sign.

Over 1,500 air sample report forms with over 18,600 individual air sample results for Building 235-F 

that were collected between 1973 and 1977 were obtained from site records. Although these forms

may not include all air sampling that was done in 235-F, they are taken to be representative of the air 

concentration levels.

Table 2-3 summarizes air concentrations from routine air samples in Building 235-F between 1973 

and January 1977 for eight locations in the building. These locations are the production and 

maintenance sides of both the NBL and the Alloy Line, the expected sources of airborne 

contamination, corridors adjacent to the construction area, and the construction area.

Table 2-3. Air concentrations from routine air samples in Building 235-F, 1973 to January 1977.a

Location

Number 

of 

samples

Maximum 

(μCi/cm3 × 

1.0E-12)

50th

percentile 

(μCi/cm3 ×

1.0E-12)

95th

percentile 

(μCi/cm3 ×

1.0E-12)

GM

(μCi/cm3 ×

1.0E-12) GSD

Construction Area 101 0.22 -0.045 0.169 0.0322 2.22

Clean Corridor East 729 1.20 -0.054 0.190 0.0384 5.15

107F - Regulated Corridor 1507 1.71 -0.045 0.230 0.0234 5.18

107A - NBL Operations 1004 11.5 -0.029 0.185 0.0422 9.98

107D - NBL Maintenance 953 1.83 -0.021 0.200 0.0381 5.49

107B - NBL End 697 1.10 -0.043 0.200 0.0253 5.65

160 - Alloy Line Operations 1624 10.7 -0.044 0.266 0.0366 4.66

162 - Alloy Line Maintenance 1623 174 -0.039 0.300 0.0928 10.8

a. Sources: Brown (2012, 2016a, 2016b, 2016c, 2016d), DuPont (1973–1974).

Routine air samples were typically collected over 24 hours and in most cases were collected end to 

end; when one stopped the next began. The results on the air sample report forms had units of 

μCi/cm3 × 10-12. The air filters were counted for alpha activity and were reported as plutonium. SRS 

used Radioactivity Concentration Guides in the 1970s to determine when workers were required to 

use respirators. The guide for neptunium was 4 × 10-12 μCi/cm3 and for plutonium was 2 × 10-12

μCi/cm3 (DuPont 1974a). Results were reported as plutonium because both might have been present 

and the plutonium guide was more restrictive.

Routine air samples were taken daily at many locations in the building during the construction of the 

PuFF. Air samples were collected on the production side of the NBL and were indicated as 107A, and 

on the maintenance side of the NBL as 107D. Samples from the area at the end of the NBL line were 

marked as 107B. Samples were also collected from the area of the Alloy Line and indicated as Room 

160 and Room 162.

Samples collected in the construction area on the first floor, Rooms 1002, 1003, and 1004 in 

Figure 2-1, and a few on the second floor for work in rooms containing air moving equipment, were 

marked as First Level Construction Area and Second Level Construction Area. These are combined 

in Table 2-3 as Construction Area. The Clean Corridor East was between the PuFF Facility and 

Rooms 160 and 162. The Regulated Corridor, designated 107F in Figure 2-1, was along the side of 

Rooms 107A and 107B, connecting the NBL to the PuFF Facility (DuPont 1986a).

Results less than one-tenth of the plutonium concentration guide, or 0.2 × 10-12 μCi/cm3 , were not 

calculated further and were listed on the forms as “<0.2”. More than 95% of the results reviewed were 

below this concentration. The air sample forms in most cases contained the original counts per 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 10 of 54

 

minute (cpm) results where the air filters were counted for alpha activity at 6 hours and 24 hours after 

collection. For results that exceeded the “<0.2” threshold, recounts were generally performed days 

later. This was to distinguish any short-lived alpha activity on the filters resulting from radon progeny 

from long-lived alpha activity resulting from plutonium or neptunium. The air concentrations 

determined by these recounts were noted on the forms and, in some cases, the recount results and 

time of the analyses were also included. For those cases where the recount exceeded one tenth of 

the plutonium concentration guide, the forms usually had an additional notation describing the activity 

that created the airborne contamination, such as a broken glove.

Using these count data along with the sample volumes and a conversion factor to translate the 

measured counts per minute into disintegrations per minute, the site’s equations were used to 

calculate air concentrations in μCi/cm3 for those samples where the site personnel had not; those 

cases where the forms listed the air concentration only as “<0.2”. These equations used to calculate 

air concentrations from the count data were found in site documents from the time (DuPont 1986b, pp. 

106–107) and included on the air sample forms. For those samples where the results were reported 

on the forms and were over 0.2 × 10-12 μCi/cm3

, the calculated results matched well with the results 

reported by the site. For those cases where the air filter had no long-lived alpha activity, the 

calculation would provide results close to zero and in many cases, due to the random nature of the 

counting statistics, negative results.

Attachment A provides graphs of these calculated and reported concentrations plotted by date. 

These graphs are lognormal plots of air concentrations against the date of sample collection. Only 

the positive values from the site-provided results or the calculated results are plotted in these graphs.

Results from site air sample collection forms from 1973 through 1977 for Building 235-F were entered 

into datasets that were used for the calculations. A quality assurance review was performed on these 

data to determine that the data agreed with the original forms with an acceptably low error rate. 

Errors identified in the review and during the subsequent statistical analysis were corrected in the data 

sets against the original forms. Attachment B contains the quality assurance report for this review.

In Table 2-3, the Number of samples column lists the number of routine air sample results with a 

plutonium concentration either provided on the air sample forms or calculated by the analysis. The 

Maximum column indicates the highest value for that area. The 50th percentile and 95th percentile 

for each location were calculated from these data.

A statistical model was developed for each location that included a linear, normal component to 

include the negative values and the smaller positive values combined with a lognormal component to 

include the higher air concentrations. The geometric mean (GM) and geometric standard deviation 

(GSD) for each location were calculated from only the lognormal portion of each model. Probability 

plots showing the data and the fitted models for each location are presented in Attachment C and 

include other statistical parameters resulting from these models.

For all areas, the GMs and the 95th percentiles for the routine air sample results were far less than 

the radioactivity concentration guides for plutonium or neptunium of 2 × 10-12 μCi/cm3

 and 

4 × 10-12 μCi/cm3

, respectively. The 50th percentiles for all locations were very close to zero. This 

would be the result if the greatest majority of the samples did not contain long-lived alpha activity.

Samples collected for specific activities and for short periods, typically 10 or 15 minutes, were labeled 

as Special. One special sample result labeled East Maintenance Room and collected on 

December 4, 1975, and had the job description “removing concrete from hole.” The East 

Maintenance Room was Room 1002 in Figure 2-1, inside the PuFF. Two special air samples were 

found from the construction period and identified as 1st Level Construction. Both were on December 

3, 1974. The job descriptions on those forms were “Cut Drain Line” and “Weld Drain Line.” These 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 11 of 54

 

and the East Maintenance Room results were less than 0.2 × 10-12 μCi/cm3. No special air samples 

were identified as for the 2nd Level Construction Area.

An additional 69 routine samples for the 1st Level Construction Area were collected between 

February and July of 1977, after construction was completed and during startup activities for the 

PuFF. Those were also all less than 0.2 × 10-12 μCi/cm3 and are included in the air sample data 

plotted in Figure 3-1 below. 

3.0 CONSTRUCTION OF THE FACILITY

The following is a brief description of the construction progress described in more detail in 

Attachment D. The PuFF construction work was apparently started very soon after the initial mention 

of the design work in the November 1973 Works Technical Report, DPSP-73-1-11 (DuPont 1973a). 

The first report of construction progress was 12% complete as of April 1974.

As seen in Figure 3-1, construction in 1974 proceeded at a steady but slower pace than in 1975. 

During 1974, the effort consisted of preparatory work including removing existing structures, pouring 

foundations for columns and walls (Figure E-1), embedding conduit, stripping floor coverings, 

installing the concrete air-duct housing on the top of Building 235 (Figures E-2 and E-3), installing 

high-efficiency particulate air (HEPA) filter housings, pouring the concrete base under the cells and 

the walls of the trench under the cells, pouring concrete for the building-supply fans and air 

conditioning equipment, installing the electrical conduit from the substation, installing base plates for 

the front-shield walls and framing for the back-shield walls, and refinishing the stainless-steel cell 

0%

10%

20%

30%

40%

50%

60%

70%

80%

90%

100%

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

12/1/1973 6/19/1974 1/5/1975 7/24/1975 2/9/1976 8/27/1976 3/15/1977 10/1/1977

μCi/cc

PuFF Construction Progress and Construction Area Air Samples

Air Concentration % Complete

Figure 3-1. PuFF construction progress and air sample results in the construction area (based on 

Table D-1).
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 12 of 54

liners. This work accomplished during 1974 made up approximately 29% of the overall construction 

effort.

During 1975, the pace picked up considerably. The following systems were installed: air-supply 

ducts for the process areas, hot-press and vacuum pumps, main-line glove cabinets, radiation shield 

walls in front of the east and west cell lines, manipulators through tubes for all cells (aligned and tackwelded), inlet ventilation ducts containing reheat coils and connections to the primary heat exchanger 

outside Building 235-F, radiation shields, service panels, hydraulics, three process furnaces, HP 

monitoring system blowers, Metallography Laboratory cabinets, instrumentation cells, wiring for cell 

consoles, and the halon fire protection system. Figure E-6 shows a completed hot cell structure that 

reflects the final stages of construction. These systems and the testing of other systems resulted in 

92% construction completion by the end of October 1975. During the next 2 months, dye checks and 

rework of welds on fittings in the copper lines in the argon, helium, and air-monitoring systems 

continued.

Beginning in January 1976, PuFF construction was 97% complete. However, the construction and 

turnover completion slipped by several months because of the design and installation of cell pressurerelief devices. Because of these problems, construction was suspended on March 12, 1976, and 

resumed on July 12, 1976. Construction was completed during January 1977. From January through 

July 1977, various test runs and cold runs with ThO2 were conducted. Processing of 238PuO2 began 

on July 23, 1977.

As indicated above, there were times when there were no billets being fabricated and transferred, and 

when construction of PuFF was suspended. Either of these circumstances would imply minimal 

potential for construction worker exposure.

Attachment E shows a series of photographs taken at various stages of PuFF development and 

construction. Although the dates on these photographs allow them to be related to the construction 

progress described in Attachment D, the subject matter visible in them provides little information. 

Nevertheless, the areas shown are all very clean with little to no debris. There are also no radiation 

barriers or signs indicating a radiation or contamination area. The workers in Figures E-1 and E-4

appear to be in regular clothing rather than protective clothing, implying the construction work area 

was considered a radiologically clean area. It cannot be determined from the photograph if the 

workers were wearing film badges.

4.0 RADIOLOGICAL CONTROLS

The purpose of this section is to discuss the controls for construction workers during the construction 

of the PUFF Facility. The SRS radiological controls were specified in various documents and 

procedures, such as DPSOP 40, Special Hazards Bulletins, standards, Special Work Permits, and 

Control Guides. These documents specified the basic requirements for the type and use of protective 

clothing, radiation and contamination control levels in specific areas, external dosimetry, bioassay, air 

sampling, posting of radiation and contamination areas, use of stepoff pads, limits of exposure, and 

anything else that could affect worker health and safety.

Daily, weekly, and monthly control surveys were performed at specified locations in Building 235-F. 

These were performed to monitor ambient exposure rates and to ensure contamination levels were 

within either regulated zone guides that required the survey to include a “P.T. smear survey” or clean 

zone guides that required the survey to include a “Disc smear survey.” The term “paper towel” smear 

survey is used in other documents and is a large area smear sample (Brown 2012).

The stepoff pads between the regulated areas and the clean areas were surveyed daily and 

compared to the Clean Zone Guides. The process room stepoff pads were also surveyed daily and 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 13 of 54

 

compared to the Regulated Zone Guides. The Regulated Corridor and the decontamination room 

were surveyed weekly and compared to the Regulated Zone Guides. The second-level shops, 

offices, corridors, and storage areas were surveyed quarterly and compared to the Clean Zone 

Guides (Brown 2012). 

A set of 16 weekly forms including the daily surveys for that week and 2 quarterly forms that included 

the monthly surveys for those quarters have been acquired for Building 235-F for the period between 

December 1973 and December 1974. The surveyors’ initials were entered on the forms when the 

areas were within the guidelines. No survey data were included on these forms; exceeding the 

guidelines for any area would have required that the data be recorded in the Radiation Survey Log. 

For all of these forms, the surveyors’ initials were entered and there was no indication of any area 

exceeding the appropriate guideline (Brown 2012).

One set of floor smear results for the 2nd Level Regulated Area taken on July 12, 1974, was within 

the set of forms from SRS. The form showed 18 locations with results between less than 3 dpm to 

17 dpm (Brown 2012, p. 32). 

Five Radiation Survey Logsheets for Building 235-F were reviewed that showed radiation surveys 

during the construction period. None of these was in the PuFF work area (Brown 2012, pp. 24–29). 

• A survey in the Heating and Ventilation (H&V) Room on the second level dated June 10, 1974, 

was for the removal of “North bank of compact line room air exhaust filters and duct work.” It 

stated that the air sample collected during the job calculated to <0.2 × 10-12 μCi Pu/cm3 and 

that a paper towel survey of the floor area revealed <500 dpm alpha transferable 

contamination. A paper towel smear survey of the exterior of the ductwork showed removable 

contamination was also below this level.

• A Radiation Survey Logsheet dated June 11, 1974, for the H&V Room had smear and air 

sample results for construction work that involved the removal of Room 6 air exhaust duct. 

The air sample during this job was <0.2 × 10-12 μCi Pu/cm3 and smears in the general area 

and outside of the ductwork were <500 dpm alpha. The form also showed surveys for a job in 

the Material Transfer Room, Room 162 in Figure 2-1, that was completed without the spread 

of contamination and with an air sample result of <0.2 × 10-12 μCi Pu/cm3

. 

• Surveys in the Material Transfer Room and the H&V Room including smears and air samples 

taken on June 12, 1974, during the dismantling of ductwork and the placement of the materials 

into an airlock. The form indicates the job was completed without the spread of contamination

and an air sample was <0.2 × 10-12 μCi Pu/cm3

. Smears taken read <1,000 cpm beta-gamma 

and <500 dpm alpha. That form also noted that the workers were in “fresh air supplied plastic 

suits.” 

• On June 17, 1974, during the removal of a hood exhaust and room exhaust duct in the H&V 

Room, all air samples were <0.2 × 10-12 μCi Pu/cm3

. At the completion of the job smears were 

taken and measured to be <1,000 cpm beta-gamma and <500 dpm alpha. This form also said 

workers were in “fresh air hoods” during the removal of the exhaust duct.

• On June 20, 1974, during installation of ductwork in the H&V Room, one worker tore a glove 

and his hand was contaminated to 3000 dpm alpha. The worker, named on the form, was 

successfully decontaminated and nasal smears were negative. Fresh air hoods were worn on 

the job. The air sample during the work was <0.2 × 10-12 μCi Pu/cm3

. A smear on a flange to 

the hood exhaust showed 8,000 dpm alpha. Smears of the floor showed <1,000 cpm betagamma and <500 dpm alpha. 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 14 of 54

 

• Tools were surveyed on June 28, 1974, in the Health Physics (HP) Office, Room 131 in 

Figure 2-1, for Construction Division workers to be able to move them from the area. No fixed 

or smearable contamination was detected on the tools. Materials in the Material Transfer 

Room that were ready to put in an airlock were surveyed. The job was completed without the 

spread of contamination. However, an air sample showed 1 × 10-12 μCi Pu/cm3

. The workers 

were already on mask requirements due to contamination in the North Airlock.

The primary procedure specifying the various criteria for SRS worker protection was DPSOP-40, 

Radiation and Contamination Control. The particular procedure either stated the necessary 

requirements or directed the workers to other documents such as Special Hazards Bulletins for 

specific instructions. The personnel monitoring requirements given in DPSTS-RH-0.07 were as 

follows (DuPont 1966): 

For all personnel who enter areas in which they will receive a sustained radiation dose 

at a rate greater than 1 mrem/hr, or intermittent exposure which accumulate to greater 

than 25 mrem in a week, shall be required to wear film badges somewhere between the 

waist and neckline. The film shall be processed, read, and the data permanently 

recorded at least once a month. 

The external radiation exposure guidelines were provided in the Special Hazards Bulletin # 7, 

Radiation Exposure Control (DuPont 1975a). The guidelines for external whole-body exposure limit 

dose were 3 rem/qtr and 3 rem/yr. 

Bioassay control guidelines for construction workers were provided in Revision 5 of DPSOL 193-302 

(DuPont 1971, p. 4). This procedure provided the frequency of routine urine samples based on the 

radionuclides that construction workers could have encountered during their work. Workers who 

could have been exposed to plutonium provided one sample every 3 years and at employment 

termination. Neptunium is not specified, but there is a category for “other radionuclides,” the sampling 

frequency for which would be specified in the project plans by area HP. 

Provision was also made for whole-body or chest counting for new employees who worked in 

radiation zones at another installation where radioactive materials were handled. They were required 

to have a whole-body and chest count, preferably at the same time as their entry physical. A wholebody or chest count was required whenever an employee’s bioassay sample indicated a confirmed 

intake or had been involved in a contamination incident and the count was considered necessary by 

HP. In addition, a whole-body or chest count was required at employment termination if the employee 

previously had a whole-body or chest count. 

In the design of all facilities used for working with high levels of radiation, there were engineered 

controls in place to minimize worker exposure. In the case of the NBL, the gloveboxes served that 

purpose. The NBL gloveboxes are assumed to have contained shielding to reduce the radiation 

levels to which the workers fabricating the billets could be exposed. Buildings were designed to have 

air flowing from areas of lower contamination potential into areas with higher potential. This airflow

was routinely verified. Figure 4-1 shows a form used to document airflow directions in key locations in 

Building 235-F. It shows that the air was flowing from clean areas and corridors into the NBL and 

Alloy Line areas.

Along with the engineered controls, the workers wore protective clothing for contamination control and 

badges for monitoring their exposures. They were also required to have whole-body counts and 

provide urine samples if conditions warranted. HP personnel also performed routine radiation and 

smear surveys, took air samples, or operated continuous air monitors in the area. 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 15 of 54

 

Figure 4-1. Typical airflow survey for Building 235-F (DuPont 1983).

The work in the NBL facility was designated as a Regulated Zone (radiation levels <300 mrad or 

50 mrem/hr). At times, when billets were wrapped and placed in the work area waiting to be 

transferred (see Figure 2-3), the NBL was designated (at least temporarily) as a Radiation Danger 

Zone. However, the radiation levels outside the NBL would have been considerably lower. For 

workers at the PuFF construction site to be exposed to radiation from the NBL, they would have to 

have passed in close proximity to the facility. As noted above, the NBL is a small, self-contained unit, 

which (according to Figure 2-3) has several access portals. 

Areas within the corridors were monitored routinely for ambient exposure rates. It is not certain they 

entered the PuFF construction area via the corridor outside of the NBL facility to report for work.

Attachment D lists the months during the construction period that Mark 53A compact billets were 

being fabricated as well as the quantity of neptunium used for the billet fabrication. The data show 

that billets were not fabricated every month. Note that there were no billets fabricated in May and 

August 1974 and November 1975 due to the unavailability of NpO2. It is unclear from the available 

reference (ORAUT 2014) whether billets were fabricated during the months of January, February, 

March, May, June, and September 1975. In addition, billet fabrication is not indicated for February, 

April, May, October, November, and December 1976, and January, February, and March 1977.

Also listed in Attachment D is the percentage of progress in the design of the PuFF facility, along with 

the percentage of construction progress. Many of the jobs that were completed or in progress are 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 16 of 54

 

also listed for each month. Note that the design of the facility was completed in February 1975 and 

construction was completed in January 1977. Beyond that, additional work that was in progress 

included acceptance testing, procedures development, and preparation for startup, which continued 

into 1977.

5.0 CONCLUSION

The Savannah River Site had an extensive radiation protection program from the initial operation of 

the first facility, and expanded as new facilities were placed into operation. The radiation protection 

program included but was not limited to:

• Engineered controls in the design of the facilities (e.g., gloveboxes, shielding, hot cells, and 

remote-handling tools), 

• Defined areas that were access controlled (i.e., Regulated Areas and Radiation Danger 

Areas), 

• Use of protective clothing, 

• Film badges and/or thermoluminescent dosimeters (TLDs) for determining exposure to 

penetrating radiation, 

• Routine urine bioassay samples and whole-body and chest counting for measuring internal 

exposure, 

• Radiation safety training, 

• Procedures and special work permits for conducting work, and

• Radiation surveys, smear surveys for detecting contamination, and air sampling. 

The primary source of any external exposure to PuFF construction workers would have been due to 

close proximity to the NBL. As indicated, the NBL is a relatively small facility that was self-contained 

in one room. Although the NBL was classified as a high hazard facility (WSRC 1990), there is no 

indication it significantly affected the surrounding areas. PuFF construction workers would not have 

had access inside the NBL due to work controls in place, and they had very little access to the area 

immediately surrounding the facility except during the early stages of construction when they could 

have passed through the corridor next to the NBL to access the worker change rooms. Ambient 

radiation levels in the corridors, in the production areas, and in the clean areas were routinely 

monitored.

A close examination of the photographs shows that the PuFF work area was treated as radiologically 

clean. There are no radiation or contamination signs or barriers in the photos, and there is evidence 

of safety precautions being considered.

Because of the radiological controls in place at the NBL and around the construction of the PuFF and 

the procedures requiring film or TLD badges in areas where potential worker exposures could occur, it 

is reasonable to assume that construction workers would have been monitored for external radiation 

exposure either directly if warranted or indirectly through the area monitoring dosimeters. Therefore, 

the potential for undocumented external radiation exposures to the PuFF construction workers is very 

unlikely. 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 17 of 54

 

Internal exposure to PuFF construction workers from airborne contamination from the NBL line and 

the Alloy Line was unlikely due to routine, consistent air sampling and contamination monitoring.

• Airflow between regulated and clean areas was routinely checked and documented to show 

the air was moving from clean into regulated areas.

• Daily, weekly, and quarterly contamination monitoring was performed and documented. 

Levels were appropriately compared to clean zone and regulated zone guides. Stepoff pads 

between clean and regulated areas were monitored daily and compared to clean zone guides.

• Routine air sampling was performed at many locations within the building and counted for 

alpha activity. Samples were collected generally daily with continuous sampling; the next 

sample beginning immediately after the previous one. 

• In the Radiation Survey Logsheets used to document health physics coverage for special, 

short-term activities, the ongoing activity was documented along with the air concentration and 

the level of protective clothing being worn by the workers. 

• For air filter samples results that have been located, analyses of the routine air concentrations

for locations in the PuFF construction area, the adjacent corridors, and within the rooms that 

contained the NBL line and the Alloy Line all showed air concentrations at the 95th percentile 

to be below both the plutonium concentration guide, 2 × 10-12 μCi/cm3

, and the neptunium 

concentration guide, 4 × 10-12 μCi/cm3

. 

• For all locations, the 50th percentiles were close to zero, which would be expected if the 

greatest majority of air samples contained no long-lived alpha activity.

• The highest air concentration of any sample in the PuFF construction area or adjacent 

corridors was below the plutonium and neptunium concentration guides with the greatest 

majority of results well below these limits. 

From the air sample data and site documents obtained and reviewed, there appears very little 

likelihood that the construction workers building the PuFF facility in Building 235-F between 1973 and 

1977 would have received inadvertent, unmonitored internal or external exposures.
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 18 of 54

REFERENCES

Author unknown, 1982, untitled letter to Bill Goldsmith (Oak Ridge National Laboratory), February 24. 

[SRDB Ref ID: 68942]

Brown, K. T., 2012, “Documents Requested for Special Exposure Cohort Petition Evaluation,” letter 

with 1973-1974 radiation survey log sheets to Office of Compensation Analysis and Support 

(National Institute for Occupational Safety and Health), Savannah River Nuclear Solutions, 

Aiken, South Carolina, May 17. [SRDB Ref ID: 114646]

Brown, K. T., 2016a, “Documents Requested for Special Exposure Cohort Petition Evaluation,” letter 

with 1975 air sample results to Office of Compensation Analysis and Support (National 

Institute for Occupational Safety and Health), Savannah River Nuclear Solutions, Aiken, South 

Carolina, March 22. [SRDB Ref ID: 153800]

Brown, K. T., 2016b, “Documents Requested for Special Exposure Cohort Petition Evaluation,” letter 

with 1976 air sample results to Office of Compensation Analysis and Support (National 

Institute for Occupational Safety and Health), Savannah River Nuclear Solutions, Aiken, South 

Carolina, March 22. [SRDB Ref ID: 153801]

Brown, K. T., 2016c, “Documents Requested for Special Exposure Cohort Petition Evaluation,” letter 

with 1977 air sample results to Office of Compensation Analysis and Support (National 

Institute for Occupational Safety and Health), Savannah River Nuclear Solutions, Aiken, South 

Carolina, March 22. [SRDB Ref ID: 153806]

Brown, K. T., 2016d, “Documents Requested for Special Exposure Cohort Petition Evaluation,” letter 

with 1974 air sample results to Office of Compensation Analysis and Support (National 

Institute for Occupational Safety and Health), Savannah River Nuclear Solutions, Aiken, South 

Carolina, April 15. [SRDB Ref ID: 154342]

DOE (U.S. Department of Energy), 1996, Highly Enriched Uranium Working Group Report on 

Environmental, Safety and Health Vulnerabilities Associated with the Department's Storage of 

Highly Enriched Uranium, Volume II: Number 6, Savannah River Site Working Group and Site 

Assessment Team Reports, DOE/EH-0525, Office of Environment, Safety and Health, 

Washington, D.C., December. [SRDB Ref ID: 22035]

DuPont (E. I. du Pont de Nemours and Company), 1966, Personnel Monitoring, DPSTS-RH-0.07, 

Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 89198, p. 2]

DuPont (E. I. du Pont de Nemours and Company), 1969, Works Technical Department Report for 

February 1969, DPSP 69-1-2, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

89198, p. 2]

DuPont (E. I. du Pont de Nemours and Company), 1971, Bioassay Control, DPSOL 193-302, Rev. 5, 

Aiken, South Carolina, September 1. [SRDB Ref ID: 124941]

DuPont (E. I. du Pont de Nemours and Company), 1973a, Works Technical Department Report for 

November 1973, DSPS 73-1-11, Savannah River Plant, Aiken, South Carolina, November. 

[SRDB Ref ID: 68034]

DuPont (E. I. du Pont de Nemours and Company), 1973b, photograph of worker readying to pour 

concrete, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 157040]
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 19 of 54

DuPont (E. I. du Pont de Nemours and Company), 1973c, photograph of roof above the PuFF Facility 

in Building 235-F, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 157041]

DuPont (E. I. du Pont de Nemours and Company), 1973d, photograph of additional work on the roof 

of Building 235-F, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 157042]

DuPont (E. I. du Pont de Nemours and Company), 1973e, photograph of glovebox housing area 

during construction, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 157037]

DuPont (E. I. du Pont de Nemours and Company), 1973–1974, collection of air sampling results, 

Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 114648]

DuPont (E. I. du Pont de Nemours and Company), 1974a, Savannah River Plant Radiation & 

Contamination Control, DPSOP 40, Rev. 46, Savannah River Plant, Aiken, South Carolina. 

[SRDB Ref ID: 86188, p. 211]

DuPont (E. I. du Pont de Nemours and Company), 1974b, Works Technical Department, Report for 

January 1974, DPSP 74-1-1, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72893]

DuPont (E. I. du Pont de Nemours and Company), 1974c, Works Technical Department, Report for 

February 1974, DPSP 74-1-2, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72894]

DuPont (E. I. du Pont de Nemours and Company), 1974d, Works Technical Department, Report for 

March 1974, DPSP 74-1-3, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72895]

DuPont (E. I. du Pont de Nemours and Company), 1974e, Works Technical Department, Report for 

April 1974, DPSP 74-1-4, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72896]

DuPont (E. I. du Pont de Nemours and Company), 1974f, Works Technical Department, Report for 

May 1974, DPSP 74-1-5, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72897]

DuPont (E. I. du Pont de Nemours and Company), 1974g, Works Technical Department, Report for 

July 1974, DPSP 74-1-7, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72898]

DuPont (E. I. du Pont de Nemours and Company), 1974h, Works Technical Department, Report for 

August 1974, DPSP 74-1-8, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72899]

DuPont (E. I. du Pont de Nemours and Company), 1974i, Works Technical Department, Report for 

September 1974, DPSP 74-1-9, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72900]

DuPont (E. I. du Pont de Nemours and Company), 1974j, Works Technical Department, Report for 

December 1974, DPSP 74-1-12, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72901]
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 20 of 54

DuPont (E. I. du Pont de Nemours and Company), 1974k, photograph of concrete removal in 

glovebox housing area, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

157035]

DuPont (E. I. du Pont de Nemours and Company), 1974l, Health Physics Statistics, 200 Areas 1974, 

Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 68421, p. 13]

DuPont (E. I. du Pont de Nemours and Company), 1975a, Radiation Exposure Control, Special 

Hazards Bulletin 7, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 86188, 

p. 61]

DuPont (E. I. du Pont de Nemours and Company), 1975b, Works Technical Department, Report for 

April 1975, DPSP 75-1-4, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72902]

DuPont (E. I. du Pont de Nemours and Company), 1975c, Works Technical Department, Report for 

July 1975, DPSP 75-1-7, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72903]

DuPont (E. I. du Pont de Nemours and Company), 1975d, Works Technical Department, Report for 

August 1975, DPSP 75-1-8, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72904]

DuPont (E. I. du Pont de Nemours and Company), 1975e, Works Technical Department, Report for 

October 1975, DPSP 75-1-10, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72905]

DuPont (E. I. du Pont de Nemours and Company), 1975f, Works Technical Department, Report for 

November 1975, DPSP 75-1-11, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72906]

DuPont (E. I. du Pont de Nemours and Company), 1975g, Works Technical Department, Report for 

December 1975, DPSP 75-1-12, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72907]

DuPont (E. I. du Pont de Nemours and Company), 1975h, photograph of completed glovebox 

housing, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 157047]

DuPont (E. I. du Pont de Nemours and Company), 1975i, photograph of construction of a support 

room, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 157049]

DuPont (E. I. du Pont de Nemours and Company), ca. 1975, photograph of workers on the neptunium 

billet line, Building 235-F, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

153958]

DuPont (E. I. du Pont de Nemours and Company), 1976a, Works Technical Department, Report for 

January 1976, DPSP 76-1-1, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72908]

DuPont (E. I. du Pont de Nemours and Company), 1976b, Works Technical Department, Report for 

March 1976, DPSP 76-1-3, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72909]
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 21 of 54

DuPont (E. I. du Pont de Nemours and Company), 1976c, Works Technical Department, Report for 

June 1976, DPSP 76-1-6, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72910]

DuPont (E. I. du Pont de Nemours and Company), 1976d, Works Technical Department, Report for

July 1976, DPSP 76-1-7, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72911]

DuPont (E. I. du Pont de Nemours and Company), 1976e, Works Technical Department, Report for 

August 1976, DPSP 76-1-8, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72912]

DuPont (E. I. du Pont de Nemours and Company), 1976f, Works Technical Department, Report for 

September 1976, DPSP 76-1-9, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72913]

DuPont (E. I. du Pont de Nemours and Company), 1976g, photograph of duct work in construction 

area, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 157044]

DuPont (E. I. du Pont de Nemours and Company), 1976h, photograph of room construction, 

Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 157045]

DuPont (E. I. du Pont de Nemours and Company), 1976i, photograph of room construction 

demonstrating safety awareness and hazard markings, Savannah River Plant, Aiken, South 

Carolina. [SRDB Ref ID: 157046]

DuPont (E. I. du Pont de Nemours and Company), 1977a, Works Technical Department, Report for 

April 1977, DPSP 77-1-4, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72914]

DuPont (E. I. du Pont de Nemours and Company), 1977b, Works Technical Department, Report for

May 1977, DPSP 77-1-5, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72915]

DuPont (E. I. du Pont de Nemours and Company), 1977c, Works Technical Department, Report for 

June 1977, DPSP 77-1-6, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72916]

DuPont (E. I. du Pont de Nemours and Company), 1977d, Works Technical Department, Report for 

July 1977, DPSP 77-1-7, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 

72917]

DuPont (E. I. du Pont de Nemours and Company), 1980, Premature Penetration Boring Concrete 

Floor, SI-80-8-109, Savannah River Site, Aiken, South Carolina, August 22. [SRDB Ref ID: 

129629]

DuPont (E. I. du Pont de Nemours and Company), 1983, Air Flow Survey, Building 235-F, First Level, 

Savannah River Site, Aiken, South Carolina, September 8. [SRDB Ref ID: 152102, p. 259]

DuPont (E. I. du Pont de Nemours and Company), 1986a, 235-F Routine Air Sample Results, 

Savannah River Site, Aiken, South Carolina, December 22. [SRDB Ref ID: 153784, p. 58]
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 22 of 54

DuPont (E. I. du Pont de Nemours and Company), 1986b, Air Sample Calculations, DPSOL 193-306, 

Rev. 4, Savannah River Site, Aiken, South Carolina, November 17. [SRDB Ref ID: 86221, 

p. 105]

NIOSH (National Institute for Occupational Safety and Health), 2014, Savannah River Site Special 

Exposure Cohort Petition Evaluation, Radiological Monitoring for Neptunium, Division of 

Compensation Analysis and Support, Cincinnati, Ohio, February. [SRDB Ref ID: 130638]

ORAUT (Oak Ridge Associated Universities Team), 2014, collection of information on PuFF, 

plutonium, and neptunium processes, Oak Ridge, Tennessee, May 1. [SRDB Ref ID: 137394]

Taylor, G. A., and M. A. Phifer, 2012, Building 235-F GoldSim Fate and Transport Model, SRNL-STI2012-00504, Rev. 0, Savannah River Nuclear Solutions, Savannah River National Laboratory, 

Aiken, South Carolina, September 14. [SRDB Ref ID: 128545]

WSRC (Westinghouse Savannah River Company), 1990, Hazard Analysis of the Radionuclide 

Releases from the Actinide Billet Line, SRL-MRG-90-9032, Savannah River Site, Aiken, South 

Carolina, November 28. [SRDB Ref ID: 129640]
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ATTACHMENT A 

SELECTED BUILDING 235-F AIR CONCENTRATIONS

LIST OF FIGURES

FIGURES TITLE PAGE

A-1 Construction area air concentrations, February 12, 1974, to December 28, 1976 .................. 24

A-2 Clean Corridor East air concentrations, January 4, 1974, to January 31, 1977 ...................... 24

A-3 Regulated Corridor (107F) air concentrations, January 4, 1974, to January 31, 1977 ............ 25

A-4 Room 107A air concentrations, December 28, 1973, to January 28, 1977............................. 25

A-5 Room 107D air concentrations, December 31, 1973, to January 31, 1977............................. 26

A-6 Room 107B air concentrations, December 31, 1973, to January 31, 1977............................. 26

A-7 Room 160 air concentrations, December 31, 1973, to January 31, 1977 ............................... 27

A-8 Room 162 air concentrations, December 31, 1973, to January 31, 1977 ............................... 28
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 24 of 54

ATTACHMENT A 

SELECTED BUILDING 235-F AIR CONCENTRATIONS (continued)

1E-16

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

Dec-73 Jul-74 Feb-75 Aug-75 Mar-76 Sep-76

μCi/cc

Construction Area

Figure A-1. Construction area air concentrations, February 12, 1974, to December 28, 1976. 

No results exceeded the administrative limit of 2 × 10-12 μCi/cm3

. 

1E-16

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

Dec-73 Jul-74 Feb-75 Aug-75 Mar-76 Sep-76

μCi/cc

Clean Corridor East

Figure A-2. Clean Corridor East air concentrations, January 4, 1974, to January 31, 1977. No 

results exceeded the administrative limit of 2 × 10-12 μCi/cm3

. 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 25 of 54

ATTACHMENT A 

SELECTED BUILDING 235-F AIR CONCENTRATIONS (continued)

1E-16

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

Dec-73 Jul-74 Feb-75 Aug-75 Mar-76 Sep-76

μCi/cc

Regulated Corridor

Figure A-3. Regulated Corridor (107F) air concentrations, January 4, 1974, to January 31, 

1977. No results exceeded the administrative limit of 2 × 10-12 μCi/cm3

. 

1E-16

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

Dec-73 Jul-74 Feb-75 Aug-75 Mar-76 Sep-76

μCi/cc

107A - NBL Production

Figure A-4. Room 107A air concentrations, December 28, 1973, to January 28, 1977. 

Four results exceeded the administrative limit of 2 × 10-12 μCi/cm3

. These had the following notations 

on the air sample forms:

• On 07/16/1974, 6.38E-12: “Air activity to 400 x 10-12 acpm/cc air during glove change.” 

• On 11/08/1974, 1.04E-11: “Glove Ruptured. Floor cont. to 1 x 105 trans.” 

• On 03/27/1975, 1.15E-11: “Glove rupture on 4-12 shift.” 

• On 02/02/1976, 3.55E-12: “High air activity during glove change. 165 x 10-12 uCi/ml.” 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 26 of 54

ATTACHMENT A 

SELECTED BUILDING 235-F AIR CONCENTRATIONS (continued)

1E-16

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

Dec-73 Jul-74 Feb-75 Aug-75 Mar-76 Sep-76

μCi/cc

107D - NBL Maintenance

Figure A-5. Room 107D air concentrations, December 31, 1973, to January 31, 1977. No 

results exceeded the administrative limit of 2 × 10-12 μCi/cm3

. 

1E-16

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

Dec-73 Jul-74 Feb-75 Aug-75 Mar-76 Sep-76

μCi/cc

107B - NBL

Figure A-6. Room 107B air concentrations, December 31, 1973, to January 31, 1977. No 

results exceeded the administrative limit of 2 × 10-12 μCi/cm3

. 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 27 of 54

ATTACHMENT A 

SELECTED BUILDING 235-F AIR CONCENTRATIONS (continued)

1E-16

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

Dec-73 Jul-74 Feb-75 Aug-75 Mar-76 Sep-76

μCi/cc

160 - Alloy Line Production

Figure A-7. Room 160 air concentrations, December 31, 1973, to January 31, 1977.

Three results exceeded the administrative limit of 2 x 10-12 μCi/cc. These had the following notations 

on the air sample forms:

• On 03/05/1974: 1.07E-11 and 2.59E-12, “Hut work. Change panel in CAB #2, Rm 162.”

• On 08/13/1974: 2.82E-12, there was no note.
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 28 of 54

ATTACHMENT A 

SELECTED BUILDING 235-F AIR CONCENTRATIONS (continued)

1E-16

1E-15

1E-14

1E-13

1E-12

1E-11

1E-10

1E-09

Dec-73 Jul-74 Feb-75 Aug-75 Mar-76 Sep-76

μCi/cc

162 - Alloy Line Maintenance

Figure A-8. Room 162 air concentrations, December 31, 1973, to January 31, 1977.

Thirteen results exceeded the administrative limit of 2 x 10-12 μCi/cc. These had the following 

notations on the air sample forms:

• On 03/05/1974, 3.19E-12, “Hut work. Change panel in CAB #2, Rm 162.”

• On 04/01/1974, 3.11E-12, “Survey of room & impactor air samples revealed no reason for 

activity.”

• On 05/09/1974, 4.70E-12, “No decay on 72 hour count.”

• On 06/28/1974, 2.23E-12, “Const. remove alloy line exhaust.”

• On 07/01/1974, 1.36E-11, “Fr. Cont. remove exhaust duct.”

• On 07/23/1974, 7.66E-12, “Bagging out equipment ingots & waste.”

• On 10/17/1974, 1.74E-10 and 2.66E-11, “Room contaminated during glove change.”

• On 10/22/1974, 2.61E-12, “Decon work being done.”

• On 03/13/1975, 6.39E-12, there was no note.

• On 12/08/1976, 3.91E-11 and 3.11E-12, “Rm on mask during 24 hour sampling period (glove 

changes and decon).”

• On 12/9/1976, 2.50E-12, “Waste removal & decon work.”
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 29 of 54

 

ATTACHMENT B 

AIR MONITORING QUALITY ASSURANCE REPORT

August 26, 2016

Sampling Plan 1: Air Sample Master 235-F 1973-1975 SRDB 114648.xlsx

All Fields Plan

Fields

Page # Time On Pu 6-hour count

Start Date Time Off Pu 24-hour count

Stop Date Volume Corr.

Location Conv Factor LT

Sample Type Background Pu E-12

Job Description Pu Initial Count

Sampling Plan

N = 100,623

AQL = 2.5%

LTPD = 5% 

α = 0.025 (producer’s risk or ORAUT risk)

β = 0.025 (consumer’s risk or DCAS risk)

n = 873

Results

6 errors / 873 checked = 0.69%

We are at least 95% confident that the transcription error rate for the SRS air monitoring dataset in SRDB 

114648 is between 0.25% and 1.49%.

Evaluation

The transcription error rate interval for this SRS air monitoring dataset is entirely below 5%. There is no issue 

with the transcription error rate.
Document No. ORAUT-RPRT-0080 Revision No. 02 Effective Date: 02/07/2017 Page 30 of 54

ATTACHMENT B 

AIR MONITORING QUALITY ASSURANCE REPORT (continued)

Sampling Plan 2: Air Sampling Results 235-F 041816_rev1 1974-1975 SRDB 153801.xlsx

All Fields Plan

Fields

Page # Time On Pu 6-hour count

Start Date Time Off Pu 24-hour count

Stop Date Volume Corr.

Location Conv Factor LT

Sample Type Background Pu E-12

Job Description Pu Initial Count

Sampling Plan

N = 85,595

AQL = 2.5%

LTPD = 5% 

α = 0.025 (producer’s risk or ORAUT risk)

β = 0.025 (consumer’s risk or DCAS risk)

n = 873

Results

2 errors / 985 checked = 0.20%

We are at least 95% confident that the transcription error rate for the SRS air monitoring dataset in SRDB 

153801 is between 0.03% and 0.73%.

Evaluation

The transcription error rate interval for this SRS air monitoring dataset is entirely below 5%. There is no issue 

with the transcription error rate.

Note: The number of cells checked exceeds the number required by the sampling plan. When the original Excel 

spreadsheet was converted to a CSV file, the converted file contained several hundred completely blank rows of 

data. The sampling plan chose 114 of these blank rows, which needed to be replaced by rows with actual data 

in them. When the new cells were randomly selected, more than 114 were drawn and checked. The only 

consequence of this is that the interval with 985 checked is slightly narrower than an interval with 873 checked.
Document No. ORAUT-RPRT-0080 Revision No. 02 Effective Date: 02/07/2017 Page 31 of 54

ATTACHMENT B 

AIR MONITORING QUALITY ASSURANCE REPORT (continued)

Sampling Plan 3: Air Sampling Results 235-F 1974 Rev1 SRDB 114643.xlsx

All Fields Plan

Fields

Date On Volume of Air 24-hour count

Time On Conv. Factor CP

Date Off Initial Count Daily Release

Time Off 6-hour count Page #

Sampling Plan

N = 636

AQL = 2.5%

LTPD = 5% 

α = 0.025 (producer’s risk or ORAUT risk)

β = 0.025 (consumer’s risk or DCAS risk)

n = 375

Results

2 errors / 375 checked = 0.53%

We are at least 95% confident that the transcription error rate for the SRS air monitoring dataset in SRDB 

114643 is between 0.31% and 1.42%.

Evaluation

The transcription error rate interval for this SRS air monitoring dataset is entirely below 5%. There is no issue 

with the transcription error rate.
Document No. ORAUT-RPRT-0080 Revision No. 02 Effective Date: 02/07/2017 Page 32 of 54

ATTACHMENT B 

AIR MONITORING QUALITY ASSURANCE REPORT (continued)

Sampling Plan 4: M270-11451-HP5F-1-P007 Air Monitoring Data 235-F 1974-1976 SRDB 154342.xlsx

All Fields Plan

Fields

Date On Cfm (sampling) 6-hour count

Time On CF 24-hour count

Date Off C.P. Cp

Time Off Initial Count Ident

Cfm (exhaust)

Sampling Plan

N = 17,511

AQL = 2.5%

LTPD = 5% 

α = 0.025 (producer’s risk or ORAUT risk)

β = 0.025 (consumer’s risk or DCAS risk)

n = 821

Results

15 errors / 821 checked = 1.83%

We are at least 95% confident that the transcription error rate for the SRS air monitoring dataset in SRDB 

154342 is between 1.05% and 2.96%.

Evaluation

The transcription error rate interval for this SRS air monitoring dataset is entirely below 5%. There is no issue 

with the transcription error rate.
Document No. ORAUT-RPRT-0080 Revision No. 02 Effective Date: 02/07/2017 Page 33 of 54

ATTACHMENT B 

AIR MONITORING QUALITY ASSURANCE REPORT (continued)

Sampling Plan 5: Air Sample Data 235-F 1975-1976 SRDB 153800.xlsx

All Fields Plan

Fields

Page # Time Off Background

Start Date Volume Pu Initial Count

Stop Date Corr. Pu 6-hour count

Location Plutonium Impactor RaTn Pu 24-hour count

Sample Type Conv Factor LT

Job Description Plutonium Impactor CORR PuE-12

Time On

Sampling Plan

N = 88,046

AQL = 2.5%

LTPD = 5% 

α = 0.025 (producer’s risk or ORAUT risk)

β = 0.025 (consumer’s risk or DCAS risk)

n = 873

Results

4 errors / 873 checked = 0.46%

We are at least 95% confident that the transcription error rate for the SRS air monitoring dataset in SRDB 

153800 is between 0.13% and 1.17%.

Evaluation

The transcription error rate interval for this SRS air monitoring dataset is entirely below 5%. There is no issue 

with the transcription error rate.
Document No. ORAUT-RPRT-0080 Revision No. 02 Effective Date: 02/07/2017 Page 34 of 54

ATTACHMENT B 

AIR MONITORING QUALITY ASSURANCE REPORT (continued)

Sampling Plan 6: Air Sampling Results 235-F final 1976-1977 SRDB 153806.xlsx

All Fields Plan

Fields

Loc Code Sample Type Pu 6-hour count

Page # Job Description Pu 24-hour count

Start Date Volume LT

Stop Date Pu Scaler Con. Factor Pu E-12

Time On Background Plutonium Impactor RaTn

Time Off Pu Initial Count Plutonium Impactor CORR

Location

Sampling Plan

N = 65,455

AQL = 2.5%

LTPD = 5% 

α = 0.025 (producer’s risk or ORAUT risk)

β = 0.025 (consumer’s risk or DCAS risk)

n = 849

Results

1 error / 849 checked = 0.12%

We are at least 95% confident that the transcription error rate for the SRS air monitoring dataset in SRDB 

153806 is between 0.0031% and 0.65%.

Evaluation

The transcription error rate interval for this SRS air monitoring dataset is entirely below 5%. There is no issue 

with the transcription error rate.
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 35 of 54

 

ATTACHMENT C 

PROBABILITY PLOTS OF AIR CONCENTRATIONS

LIST OF FIGURES

FIGURE TITLE PAGE

C-1 Air concentrations against standard normal quantiles, construction areas and Room 

107C ......................................................................................................................................36

C-2 Air concentrations against standard normal quantiles, Clean Corridor East ........................... 37

C-3 Air concentrations against standard normal quantiles, Regulated Corridor............................. 37

C-4 Air concentrations against standard normal quantiles, Room 107A........................................ 38

C-5 Air concentrations against standard normal quantiles, Room 107D........................................ 38

C-6 Air concentrations against standard normal quantiles, Room 107B........................................ 39

C-7 Air concentrations against standard normal quantiles, Room 160 .......................................... 39

C-8 Air concentrations against standard normal quantiles, Room 162 .......................................... 40
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 36 of 54

ATTACHMENT C 

PROBABILITY PLOTS OF AIR CONCENTRATIONS (continued)

In these graphs, calculated air concentrations are plotted against standard normal quantiles. These 

were calculated using models with a normal section that covers negative values and small positive 

values and a lognormal section that covers higher values. Red dots are air concentrations; the black 

line is the fit to the data. The straight part of the black line is the normal section of the model and the 

curved part is the lognormal section. 

Provided on the graphs are statistical values resulting from the models:

• f is the fraction of the model that is fit with the normal distribution. 

• mu is the mean of the normal distribution. 

• sd is the standard deviation of the normal distribution.

• GM is the geometric mean of the lognormal distribution.

• GSD is the geometric standard deviation of the lognormal distribution.

• N is the number of results for that location; the number of red dots in the plot.

Figure C-1. Air concentrations against standard normal 

quantiles, construction areas and Room 107C.
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 37 of 54

ATTACHMENT C 

PROBABILITY PLOTS OF AIR CONCENTRATIONS (continued)

Figure C-2. Air concentrations against standard normal 

quantiles, Clean Corridor East.

Figure C-3. Air concentrations against standard normal 

quantiles, Regulated Corridor.
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 38 of 54

ATTACHMENT C 

PROBABILITY PLOTS OF AIR CONCENTRATIONS (continued)

Figure C-4. Air concentrations against standard normal 

quantiles, Room 107A.

Figure C-5. Air concentrations against standard normal 

quantiles, Room 107D.
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 39 of 54

ATTACHMENT C 

PROBABILITY PLOTS OF AIR CONCENTRATIONS (continued)

Figure C-6. Air concentrations against standard normal 

quantiles, Room 107B.

Figure C-7. Air concentrations against standard normal 

quantiles, Room 160.
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 40 of 54

ATTACHMENT C 

PROBABILITY PLOTS OF AIR CONCENTRATIONS (continued)

Figure C-8. Air concentrations against standard normal 

quantiles, Room 162.
 

Document No. ORAUT-RPRT-0080 Revision No. 0

0 Effective Date: 02/07/2017 Page 41 of 54

ATTACHMENT D 

NEPTUNIUM BILLETS FABRICATED DURING THE DESIGN AND CONSTRUCTION OF THE PuFF

Table D-1 chronicles the fabrication of 283 neptunium billets and documents concurrent design and construction progress for the PuFF

from November 1973 to July 1977. 

Table D-1. Neptunium billet fabrication during design and construction, 1973 to 1977. 

Date Reference Production activity Percentage of design and construction progress

Nov-73 ORAUT 

2014

7 Mark 53A compact 

billets from 15.6 kg Np.

First mention in Works Technical Reports DPSP-73-1-11 (DuPont 1973a). Design work in 

progress to provide for production of disks and spheres, and for iridium encapsulation of spheres 

(also for dismantling spheres). Date to open given as January 1976.

Designed to have nine shielded cells, six using cabinets, on first floor. Auxiliary equipment on 

second floor. Design limit: 0.5 mrem/hr for continuous exposure, 5 mrem/hr for intermittent.

Dec-73 ORAUT 

2014

13 Mark 53A compact 

billets from 8.4 kg Np.

Design about 50% complete. Foundation for two of the columns in east-west wall prepared. 

Support for two process rooms was strengthened, portions removed.

Shielding by 21 in. of limonite concrete in front and 12 in. on sides. Utility cabinets shielded by 

4 in. H2O. Processing to be done with manipulators.

Jan-74 DuPont 

1974b

5 Mark 53A compact 

billets from 6.0 kg Np. 

Design about 54% complete. Embedded conduit installed. Framing and other preparatory work 

for pouring the cell foundation continuing. Stripping of roof covering in progress in preparation for 

installing the concrete exhaust-air duct on top of Building 235-F. New HEPA filter housings and 

plenums are being assembled on second floor; these will service the Np and billet lines in addition 

to the PuFF facility.

Np billet line cleansed for production of Mark 22A (Pu-242) billets.

Feb-74 DuPont 

1974c

7 Mark 53A compact 

billets from 8.4 kg Np; 

no reject compacts.

Design about 60% complete. Installation of embedded conduit and pouring of the concrete base 

pad under the cells completed. Concrete walls of trench under Cells 1 through 5 poured, and 

framing for the remainder of the trench walls essentially complete. Pouring of the concrete base 

for the exhaust-air duct on top of 235-F begins, and excavation for the air duct to the new F-Area 

sand filter in progress.

Mar-74 DuPont 

1974d

5 Mark 53A compact 

billets from 6.0 kg Np; 

no reject compacts.

Design 65% complete. Foundation for the cells completed, and repouring of the first-level floor is 

imminent. Concrete exhaust-air duct atop Building 235-F about 60% complete. Pouring of pad for 

building- supply fans and air-conditioning equipment complete (outside world), and underground 

electrical conduit from the new substation installed.

Apr-74 DuPont 

1974e

4 Mark 53A compact 

billets from 4.8 kg Np; 

no reject compacts.

Design 65% complete; construction about 12% complete. Pouring of first floor completed, and 

steel base plate for the front-shield wall installed. Front shield wall (21-in.-thick limonite concrete) 

will be poured in Central Shops and installed in sections after cells installed. Framing in progress 

for the back shield wall (14.5-in.-thick limonite concrete), which will be poured in place. Concrete 

exhaust duct atop 235-F about 80% complete, and transition duct (from rectangular duct to circular 

underground pipe) poured.

May-74 DuPont 

1974f

No NpO2 was available 

for fabrication of 

compact billets.

Design 67% complete; construction about 15% complete. Framing for rear shield walls, including 

installation of doors and window frames, continues. Removal of high hats on second floor in 

progress; this area will be used for auxiliary equipment. Concrete exhaust duct atop Building 

235-F 90% complete.
ATTACHMENT D

NEPTUNIUM BILLETS FABRICATED DURING THE DESIGN AND CONSTRUCTION OF THE PuFF (continued)

Document No. ORAUT-RPRT-0080 Revision No. 0

0 Effective Date: 02/07/2017 Page 42 of 54

Date Reference Production activity Percentage of design and construction progress

Jun-74 ORAUT 

2014

14 Mark 53A compact 

billets from 16.8 kg Np; 

no reject compacts.

Design 73% complete. Forms for limonite concrete shield constructed. Rear wall for Cell 9 

poured. Upgrading of vent ducts for Cell 9 poured. Upgrading of vent ducts on second floor 70% 

complete. Removal of first bay underway.

Jul-74 DuPont 

1974g

11 Mark 53A compact 

billets from 13.2 kg Np; 

no reject compacts. 

Special samples taken 

from Al-NpO2 blend to 

determine if the NpO2

and Al powders were 

blended adequately in 

the Z-type blender. 

Samples of powder 

from the dies were 

taken to see if the blend 

was segregating during 

subsequent handling.

Design 77% complete; construction 20% complete. Pouring of limonite concrete for all cell rear 

walls completed, and upgrading of the ventilation ducts on second level of 235-F complete. Final 

concrete pour for the exhaust duct on the roof made.

Aug-74 DuPont 

1974h

No NpO2 was available 

for fabrication of 

compact billets.

Design 83% complete; construction 24% complete. Liners for six rune cells received, but the 

interior finish did not meet plant requirements. New building supply fan and air-conditioning 

equipment installed. Both high hats in the second level floor removed, and structural steel 

supports for the new floor in this area installed.

Sep-74 DuPont 

1974i

8 Mark 53A billets from 

9.6 kg Np; 1 reject 

compact.

Design 87% complete; construction 25% complete.

Oct-74 ORAUT

2014

19 Mark 53A compact 

billets from 22.8 kg Np.

Design 87% complete; construction 27% complete. 7-ft-diameter underground duct to connect to 

235-F exhaust to 294-F filter installed. Earth backfill completed. Six stainless-steel cell liners 

refinished.

Nov-74 ORAUT

2014

15 Mark 53A billets 

from 18 kg Np.

Design 90% complete; construction 27%. Remaining three cell lines completed.

Dec-74 DuPont 

1974j

15 Mark 53A billets 

from 18 kg Np; 

1 reject compact.

At year end, design 98% complete; construction 29% complete. Design and construction 

completion schedules remain the same as forecast in November (July 1975 for design and 

February 1976 for construction).

Jan-75 ORAUT

2014; 

Author 

unknown 

1982

None indicated Design 99% complete; construction 36% complete. Two 2- by 7-ft walls cut through east wall of 

235-F for air-supply ducts to process area.
ATTACHMENT D

NEPTUNIUM BILLETS FABRICATED DURING THE DESIGN AND CONSTRUCTION OF THE PuFF (continued)

Document No. ORAUT-RPRT-0080 Revision No. 0

0 Effective Date: 02/07/2017 Page 43 of 54

Date Reference Production activity Percentage of design and construction progress

Feb-75 ORAUT

2014

None indicated Design complete; construction 45% complete. Hot-press and vacuum pumps installed behind 

Cell 4. Main line glove cabinet installations finished. Concrete poured to complete second floor.

Apr-75 DuPont 

1975b

8 Mark 53A compact 

billets from 9.6 kg Np; 

no reject compacts. 

Five billets in Building 

235-F of 20% Pu-240 

for the Mark 41 

development run. The 

tubes have been cut 

and packaged in 

Building 235-F and sent 

to JB-Line for plutonium 

recovery.

Construction 55% complete. Installation of all sections of radiation shield wall in front of east and 

west cell lines completed. Manipulator through-tubes for all cells installed, aligned, and tackwelded. Inlet-ventilation ducts containing reheat steam coils installed on the second floor and 

connected to the primary heat exchanger outside Building 235-F. Rear shielding windows 

installed in all cells.

May-75 ORAUT

2014

None indicated Construction 60% complete. Top sections of radiation shields poured, completing east and west 

cell lines. Service panels and hydraulics installed.

Jun-75 ORAUT 

2014

None indicated Construction 65% complete. Three process furnaces installed. HP monitoring system blowers 

installed. Metallography Laboratory cabinets installed. Instrumentation cells installed.

Jul-75 DuPont 

1975c

12 Mark 53A compact 

billets from 14.4 kg Np; 

no reject compacts.

Construction 70% complete.

Aug-75 DuPont 

1975d

8 Mark 53A compact 

billets with 9.6 kg Np.

Construction 75% complete. Centorr representatives operating the hot press to demonstrate it 

meets specifications. During pressure tests, graphite ram extensions and a graphite lower ram 

clamp fractured. Installation of manipulator through-tubes begun in Cells 1 through 5. Wiring for 

cell consoles and for the halon fire protection system completed. Equipment transfer lock into 

Cell 6 and the liquid waste glovebox installed.

Oct-75 DuPont 

1975e

11 Mark 53A compact 

billets from 13.2 kg Np 

as oxide; no reject 

compacts.

Construction is 85% complete. Helium purifier installed, but an improper welding procedure was 

used and it would be necessary to cut and reweld 10 welds. Satisfactory leak tests made on all 

cells. Testing of the attached gloveboxes underway.

Nov-75 DuPont 

1975f

NpO2 powder was not 

available for 

processing.

Construction 92% complete. Construction schedule for facility completion and turnover changed 

from February to April 1976.

Dec-75 DuPont 

1975g

7 Mark 53A compact 

billets from 8.4 kg Np 

as oxide; no reject 

compacts.

Construction 96% complete. Repair of substandard welds at fittings in copper lines in the argon, 

helium, and air-monitoring systems about 75% complete. Dye checks indicate excessive porosity 

in some new welds. These areas ground out and rewelded as discovered.
ATTACHMENT D

NEPTUNIUM BILLETS FABRICATED DURING THE DESIGN AND CONSTRUCTION OF THE PuFF (continued)

Document No. ORAUT-RPRT-0080 Revision No. 0

0 Effective Date: 02/07/2017 Page 44 of 54

Date Reference Production activity Percentage of design and construction progress

Jan-76 DuPont 

1976a

9 Mark 53A compact 

billets from 10.8 kg Np; 

no reject compacts; 3 

batches of NpO2

returned to HB-Line for 

recalcination because 

of high weight loss 

(more than 0.5%).

Construction 97% complete. Construction schedule for facility completion and turnover changed 

from May to July because of the design and installation of the cell pressure relief devices. All cell 

bulk shielding windows installed.

Mar-76 DuPont 

1976b

15 Mark 53A compact 

billets from 18.0 kg Np; 

no reject compacts.

Construction remains 97% complete. On March 12, construction work suspended until design of 

the cell pressure relief devices is complete. Beneficial occupancy of cells and first-floor equipment 

assumed by Operations on March 12.

Jun-76 DuPont 

1976c

7 Mark 53A compact 

billets from 8.4 kg Np; 

no reject compacts.

No work during this month.

Jul-76 DuPont 

1976d

13 Mark 53A compact 

billets from 15.6 kg Np; 

no reject compacts.

Construction remains 97% complete. On July 12, construction resumed in the PuFF Facility. The 

following work necessary to complete the facility (completion forecast for November 1) includes 

installation of pressure vacuum relief devices for inert gas cells.

Aug-76 DuPont 

1976e

10 Mark 53A compact 

billets from 12.0 kg Np; 

no reject compacts.

Construction work, installation of pressure vacuum relief devices for inert gas cells continues.

Sep-76 DuPont 

1976f

8 Mark S3A compact 

billets from 9.6 kg Np; 

no reject compacts.

Construction remains 97% complete. Remaining work scheduled for completion by November. 

Exhaust ventilation from process cabinets and rooms changed to discharge into new roof tunnel 

leading to the F-Area sand filter.

Dec-76 ORAUT

2014

None indicated Construction 99% complete. Ventilation system being tested. Some modifications being made.

Jan-77 ORAUT

2014

None indicated Construction completed.

Feb-77 ORAUT

2014

None indicated Acceptance test set for March 8, 1977. Ventilation system accepted in February. In-line alpha 

monitor being tested.

Mar-77 ORAUT

2014

None indicated Separations took occupancy on March 8, 1977. A few welds "still to be made." Procedures being 

prepared.

Apr-77 DuPont 

1977a

16 Mark 53A billets 

from 19.2 kg Np; 

1 reject compact.

Preparations for startup continued. Equipment run-in and continuity checks started.
ATTACHMENT D

NEPTUNIUM BILLETS FABRICATED DURING THE DESIGN AND CONSTRUCTION OF THE PuFF (continued)

Document No. ORAUT-RPRT-0080 Revision No. 0

0 Effective Date: 02/07/2017 Page 45 of 54

Date Reference Production activity Percentage of design and construction progress

May-77 DuPont 

1977b

15 Mark 53 A billets 

from 180 kg Np; 

1 reject compact.

Test runs for PuO2 started in Cell 1. Test welding on iridium in helium atmosphere started in 

Cell 6.

Jun-77 DuPont 

1977c

16 Mark 53A billets 

from 19.2 kg Np; 

no reject compacts; 

20.148 kg NpO2 sent to 

Building 235-F in 

21 batches.

Cold runs with ThO2 as stand-in for PuO2 continued. Nine ball-mill runs made and six pellets 

cold-pressed and sized into shards. Three Th02 spheres successfully hot-pressed.

Jul-77 DuPont 

1977d

5 Mark 53 A billets 

from 6.0 kg Np; 

1 reject compact.

Cold runs with ThO2 as a stand-in for PuO2 completed. Processing of 238PuO2 began on July 23. 

All major equipment and the argon supply for operation of the vacuum-pressure mounting system 

have been installed in Building 235-F PuFF Metallography Facility.
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 46 of 54

 

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS

LIST OF FIGURES

FIGURES TITLE PAGE

E-1 Worker readying to pour concrete, April 4, 1973 .................................................................... 47

E-2 Roof above the PuFF Facility in Building 235-F, April 4, 1973................................................ 48

E-3 Additional work on the roof of Building 235-F, April 4, 1973 ................................................... 49

E-4 Glovebox housing area during construction, December 11, 1973........................................... 50

E-5 Concrete removal in glovebox housing area, April 4, 1974..................................................... 51

E-6 Completed hot cell structure, February 26, 1975.................................................................... 52

E-7 Construction of a support room, February 26, 1975 ............................................................... 52

E-8 Duct work in construction area, November 20, 1976 .............................................................. 53

E-9 Room construction, November 20, 1976 ................................................................................ 54

E-10 Room construction demonstrating safety awareness and hazard markings, November 

20, 1976................................................................................................................................. 54
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 47 of 54

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS (continued)

The following photographs show the PuFF facility in various stages of development. As shown, the 

construction areas were clean with little to no debris. There are no radiation barriers or signs in the 

photographs, which indicates they were not radiation or contamination areas. The workers in 

Figures E-1 and E-4 appear to be in regular rather than protective clothing.

Figure E-1. Worker readying to pour concrete, April 4, 1973 (DuPont 1973b). Note that the worker 

does not appear to be wearing protective clothing for the prevention of radioactive contamination

(DPSPF 17880-4). 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 48 of 54

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS (continued)

Figure E-2. Roof above the PuFF Facility in Building 235-F, April 4, 1973 (DuPont 1973c). 

Maintenance access and exhaust piping were installed later (DPSPF 17880-11). 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 49 of 54

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS (continued)

Figure E-3. Additional work on the roof of Building 235-F, April 4, 1973 (DuPont 1973d) (DPSPF 

17880-12). 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 50 of 54

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS (continued)

Figure E-4. Glovebox housing area during construction, December 11, 1973 (DuPont 1973e). Note 

that the worker does not appear to be wearing protective clothing for the prevention of radioactive 

contamination (DPSPF 17564-8). 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 51 of 54

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS (continued)

Figure E-5. Concrete removal in glovebox housing area, April 4, 1974 (DuPont 1974k) (DPSPF 

17508-7). 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 52 of 54

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS (continued)

Figure E-6. Completed hot cell structure, February 26, 1975 (Du Pont ca. 1975h) (DPSPF 18813-23). 

Figure E-7. Construction of a support room, February 26, 1975 (DuPont 1975i) (DPSPF 18813-28). 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 53 of 54

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS (continued)

Figure E-8. Duct work in construction area, November 20, 1976 (DuPont 1976g). Note the duct to 

other parts of the building is closed off (DPSPF 18678-4). 
Document No. ORAUT-RPRT-0080 Revision No. 00 Effective Date: 02/07/2017 Page 54 of 54

ATTACHMENT E 

CONSTRUCTION AREA PHOTOGRAPHS (continued)

Figure E-9. Room construction, November 20, 1976 (DuPont 1976h). It is not clear what this 

particular room was used for. Note the clean conditions in the work area (DPSPF 18678-11). 

Figure E-10. Room construction demonstrating safety awareness and hazard markings, November 

20, 1976 (DuPont 1976i) (DPSPF 18678-24).