ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation

Page 1 of 27

Document Title:

Pinellas Plant – Site Description

Document Number: ORAUT-TKBS-0029-2 

Revision: 01

Effective Date: 10/04/2006

Type of Document: TBD

Supersedes: Revision 00

Subject Experts: Marquis P. Orr and Paul J. Demopoulos

Approval: Signature on File Approval Date: 09/05/2006

Paul J. Demopoulos, Document Owner

Approval: Signature on File Approval Date: 09/06/2006

John M. Byrne, Task 3 Manager

Approval: Signature on File Approval Date: 09/05/2006

Edward F. Maher, Task 5 Manager

Concurrence: Signature on File Concurrence Date: 10/03/2006

Kate Kimpan, Project Director

Approval: Brant A. Ulsh Signature on File for Approval Date: 10/04/2006

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

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

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 2 of 27

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

01/18/2005 00-A New technical basis document for the Pinellas Plant – site 

description. Initiated by Marquis P. Orr.

04/05/2005 00-B Incorporates internal review comments. Initiated by Mark D. Notich.

05/20/2005 00-C Incorporates NIOSH review comments. Initiated by Mark D. Notich.

08/01/2005 00-D Deletes discussions that were not pertinent to dose reconstruction, 

deletes information on the radioactive decay processes for certain 

radionuclides, and deletes other information deemed extraneous by 

NIOSH. Initiated by Marquis P. Orr.

08/05/2005 00 First approved issue. Initiated by Marquis P. Orr.

10/04/2006 01 Approved Revision 01 to make changes according to the public 

outreach meetings of 09/2004 and 11/2005 and claimant 

communications. Added required language from NIOSH in the 

Introduction. Incorporates internal formal review comments, 

including adding the pilot plant information at the end of section 2.2. 

Added a Purpose and Scope, Sections 2.1.1 and 2.1.2. Incorporates 

NIOSH formal review comments. This revision results in no change 

to the assigned dose and no PER is required. Training required: As 

determined by the Task Manager. Initiated by Paul J. Demopoulos.
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 3 of 27

TABLE OF CONTENTS

SECTION TITLE

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

PAGE

4

2.1 Introduction ..............................................................................................................................5

2.1.1 Purpose.........................................................................................................................7

2.1.2 Scope............................................................................................................................7

2.2 Site Activities and Processes ...................................................................................................7

2.3 Site Products..........................................................................................................................16

2.3.1 Equipment...................................................................................................................16

2.3.2 Radioactive Materials ..................................................................................................20

2.3.3 Waste Disposal ...........................................................................................................23

2.4 Site Equipment.......................................................................................................................24

References ........................................................................................................................................26

LIST OF TABLES

TABLE TITLE

2-1 Functions and sizes of site buildings ........................................................................................

PAGE

9

2-2 RMMAs in Building 100.......................................................................................................... 11

2-3 Annual radionuclides released from Pinellas Plant stacks in curies........................................ 21

2-4 Chronology of unusual events................................................................................................ 22

2-5 Radiation-producing equipment.............................................................................................. 25

LIST OF FIGURES

FIGURE TITLE

2-1 Location of Pinellas Plant in Pinellas County, Florida...............................................................

PAGE

6

2-2 Aerial photograph of Pinellas Plant ..........................................................................................8

2-3 Site map...................................................................................................................................8

2-4 Building 100-300 with second floor mezzanines and offices................................................... 10

2-5 Boom box and collection container......................................................................................... 13

2-6 Layout of Building 400............................................................................................................ 14

2-7 Layout of Building 800............................................................................................................ 15

2-8 Neutron tube tritium loading manifold..................................................................................... 17

2-9 Firing tubes and the boom box configuration.......................................................................... 18

2-10 Spin tester..............................................................................................................................19
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 4 of 27

ACRONYMS AND ABBREVIATIONS

AEC Atomic Energy Commission (forerunner to DOE & NRC)

C.F.R. Code of Federal Regulations 

CPE Ceramic Product Engineering

DOE U.S. Department of Energy 

GE General Electric

HEPA high efficiency particulate air 

keV kilovolt-electron, 1,000 electron volts

LANL Los Alamos National Laboratories

MMSC Martin Marietta Specialty Components, Inc.

RMMA radioactive material management area 

RTG radioisotopically-powered thermoelectric generator

SECS Stack Effluent Control System

SNL Sandia National Laboratory

TRS Tritium Recovery System

U.S.C. United States Code
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 5 of 27

2.1 INTRODUCTION

Technical basis documents and site profile documents are not official determinations made by the 

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

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

dose reconstructions at particular sites or categories of sites. They will be revised in the event 

additional relevant information is obtained about the affected site(s). These documents may be used 

to assist NIOSH staff in the completion of the individual work required for each dose reconstruction.

In this document the word “facility” is used as a general term for an area, building, or group of 

buildings that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “Department of Energy [DOE] facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act [EEOICPA; 42 U.S.C. § 7384l(5) and (12)]. 

EEOICPA defines a DOE facility as “any building, structure, or premise, including the grounds upon 

which such building, structure, or premise is located ... in which operations are, or have been, 

conducted by, or on behalf of, the Department of Energy (except for buildings, structures, premises, 

grounds, or operations ... pertaining to the Naval Nuclear Propulsion Program)” [42 U.S.C. § 

7384l(12)]. Accordingly, except for the exclusion for the Naval Nuclear Propulsion Program noted 

above, any facility that performs or performed DOE operations of any nature whatsoever is a DOE 

facility encompassed by EEOICPA.

For employees of DOE or its contractors with cancer, the DOE facility definition only determines 

eligibility for a dose reconstruction, which is a prerequisite to a compensation decision (except for 

members of the Special Exposure Cohort). The compensation decision for cancer claimants is based 

on a section of the statute entitled “Exposure in the Performance of Duty.” That provision [42 U.S.C. § 

7384n(b)] says that an individual with cancer “shall be determined to have sustained that cancer in the 

performance of duty for purposes of the compensation program if, and only if, the cancer ... was at 

least as likely as not related to employment at the facility [where the employee worked], as 

determined in accordance with the POC [probability of causation1

As noted above, the statute includes a definition of a DOE facility that excludes “buildings, structures, 

premises, grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 (42 

U.S.C. 7158 note), pertaining to the Naval Nuclear Propulsion Program” [42 U.S.C. § 7384l(12)]. 

While this definition contains an exclusion with respect to the Naval Nuclear Propulsion Program, the 

section of EEOICPA that deals with the compensation decision for covered employees with cancer 

[i.e., 42 U.S.C. § 7384n(b), entitled “Exposure in the Performance of Duty”] does not contain such an 

exclusion. Therefore, the statute requires NIOSH to include all occupationally derived radiation 

exposures at covered facilities in its dose reconstructions for employees at DOE facilities, including 

radiation exposures related to the Naval Nuclear Propulsion Program. As a result, all internal and 

external dosimetry monitoring results are considered valid for use in dose reconstruction. No efforts 

are made to determine the eligibility of any fraction of total measured exposure for inclusion in dose 

reconstruction. NIOSH, however, does not consider the following exposures to be occupationally 

derived:

] guidelines established under 

subsection (c) ...” [42 U.S.C. § 7384n(b)]. Neither the statute nor the probability of causation 

guidelines (nor the dose reconstruction regulation) define “performance of duty” for DOE employees 

with a covered cancer or restrict the “duty” to nuclear weapons work.

• Radiation from naturally occurring radon present in conventional structures

 

1 The U.S. Department of Labor is ultimately responsible under the EEOICPA for determining the POC. 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 6 of 27

• Radiation from diagnostic X-rays received in the treatment of work-related injuries

Section 2.2 describes site processes and activities including facilities, Section 2.3 describes the site’s 

products, and Section 2.4 lists the equipment with radioactive components on the site. 

The Pinellas Plant is in central Pinellas County, Florida, on 40.4 hectares (99.9 acres) in Section 13, 

Township 30S, Range 15E, of the Tallahassee Meridian (Figure 2-1). Pinellas County is in the westcentral part of peninsular Florida. It is bounded on the north by Pasco County, on the east by 

Hillsborough County and Tampa Bay, and on the west and south by the Gulf of Mexico. 

Figure 2-1. Location of Pinellas Plant in Pinellas 

County, Florida (FDOT 2004).

The site is bordered on the east by Belcher Road (Pinellas County Road 27), on the south by Bryan 

Dairy Road (Pinellas County Road 135), and on the west by a spur of the Seaboard Coastline 

Railroad. The area is surrounded by light industry and warehouse operations. The closest residential 

area is approximately 400 meters (1,300 feet) from the plant. 

The area around the Pinellas Plant is characterized as urban land consisting of high-density 

residential developments, commercial buildings, streets, highways, parking lots, and other types of 

development (USDA 2004, p. 8). Figure 2-2 is an aerial photograph from 1992 that shows the 

proximity of residential and commercial development around the Pinellas Site. 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 7 of 27

2.1.1

This technical basis document (TBD) represents a specific support mechanism concerning 

documentation of facilities and processes that manufactured neutron generators and other 

components for nuclear weapons. The manufacture of neutron generators required equipment, 

facilities, and expertise that could be applied to a variety of specialty components. 

Purpose

2.1.2

The site profile provides supporting technical data to evaluate the total Pinellas occupational radiation 

dose that may reasonably be associated with the worker’s radiation exposure. This dose results from 

exposure to external and internal radiation sources in Pinellas facilities.

Scope

The site description gives some general information on where some of the processes occurred and 

some details of the processes. This may include when the processes occurred and details of the 

devices produced. For example, neutron generators are described in the TBD as consisting of a 

miniaturized linear ion accelerator assembled with pulsed electric power supplies. The ion accelerator, 

or neutron tube, required ultra-clean, high-vacuum technology; hermetic seals between glass, 

ceramic, glass-ceramic, and metal materials; and high-voltage generation and measurement 

technology. Pinellas manufactured only neutron generators for its first 10 years of operations.

2.2 SITE ACTIVITIES AND PROCESSES

The Pinellas Plant (Figure 2-3) has approximately 70,195 square meters (755,584 square feet) under 

roof on its 40.4 hectares (99.9 acres). The plant was constructed in 1956 by the General Electric 

Corporation (GE) for the development and production of nuclear generators for the nation’s nuclear 

weapons programs. The Atomic Energy Commission (AEC) (predecessor of the U.S. Department of 

Energy) purchased the Pinellas Plant from GE in 1957, and contracted them to operate the site from 

its startup in 1957 until May 31, 1992. In June 1992, Martin Marietta Specialty Components, Inc. 

(MMSC) took over operation of the facility and served as the managing and operating contractor until 

the site was shut down in September of 1994 (DHRS 1994, p. 1). As part of the DOE program to 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 8 of 27

Figure 2-2. Aerial photograph of Pinellas Plant (FAS 2004). 

Figure 2-3. Site map (DOE 2002).
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 9 of 27

promote commercial uses of the site; DOE sold most of the Pinellas Plant to the Pinellas County 

Industry Council on March 17, 1995 (DOE 1995, p. iii). 

DOE has an ongoing environmental restoration program for an 8-hectare (20-acre) plot in the 

northeast corner of the facility and another 1.8-hectare (4.5-acre) area near the northwest corner of 

the site. Both of these areas have groundwater contamination caused by previous storage and 

disposal of drummed waste and construction debris that contained solvents and volatile organic 

compounds. Remediation of these sites is being addressed under a Federal Resource Conservation 

and Recovery Act (RCRA) permit that includes corrective action requirements and cleanup under 

Florida State Superfund statutes (DOE 1997, p. 1). 

The initial mission of the Pinellas Plant was the manufacture of neutron generators and other 

components for nuclear weapons. The manufacture of neutron generators required equipment, 

facilities, and expertise that could be applied to a variety of specialty components. As a consequence, 

DOE expanded the Pinellas Plant mission to produce multiple electronic and support components for 

other DOE programs. These components included thermal and long-life ambient temperature 

batteries, specialized shock-absorbing foam supports, ferroelectric- and glass-ceramic encapsulation 

materials, and Radioisotopically-powered Thermoelectric Generators (RTGs). Part of the expansion 

included relocation of a similar production facility from Milwaukee, Wisconsin, to Pinellas during the 

1966-1967 timeframe.

Pinellas Plant 

The Pinellas Plant contains multiple structures and support facilities within the controlled area. 

Table 2-1 lists the floor space and function of each building, and the following sections discuss each 

building. 

Table 2-1. Functions and sizes of site buildings. 

Building Function

Area

Square meters Square feet

Building 100/300 – 1st Floor Offices, Production, Laboratory 42,271 455,000

– 2nd Floor Offices, Utilities 9,625 103,600

– Mezzanines Offices 6,317 68,000

 Total Building 100 Area 58,213 626,600

Building 200 Product Quality Assurance Testing 1,505 16,200

Building 400 RTG Assembly and Testing 1,375 14,800

Building 500 Utilities, Deionized Water Plant 1,691 18,200

Building 550 Wastewater Neutralization 204 2,200

Building 600 Chemical Storage 669 7,200

Building 700 Maintenance Bldg., Fire Dept. 464 5,000

Building 710 Maintenance Storage Shed 36 384

Building 800 Linear Accelerator Facility a 334 3,600

Building 900 Fire Training 65 700

Building 1000 and 1040 Waste Storage & Management 790 8,500

Building 1010 New Container Storage 232 2,500

Building 1100 Special Storage 37 400

Building 1200 Security 2,722 29,300

Building 1400 Remote Receiving 669 7,200

Building 1500 and 1600 School, Child Day Care 1,189 12,800

 Site Total 70,195 755,584

Source: DOE (1995a, p. 3-3).

a. The LINAC was operated in building 100 in room 161 for 2 years prior to moving to building 800.
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Building 100

Building 100 was the initial plant building. During DOE ownership of the Pinellas Plant, Building 100 

provided space for manufacturing, engineering, and administrative support services. Figure 2-4 

shows the layout of Building 100.

351

350

349

348

307 310

352

309

353

336

330 347

306

Building 300

139

116

110

109 111

114

131128 130

149

125 122

134

133

121

126

108

138

140

141

142

146 145 143

117

112

194 195

124 105

118

193 192

104

152

151

163 162

161

160

159

183 182

184

185

175

181

180

158

157

155 164

150

154

153

176

174

103 106

119

170

Building 100

104

103

152

151

118

102

105

106

190 189

172 173

171

113 129

135

137

136

132

147

148

115

040405_03_TB

Figure 2-4. Building 100-300 with second floor mezzanines and offices (DOE, 1994).

Radioactive materials in Building 100 were used in the production, manufacture, storage, and testing 

of various weapons components. Multiple areas were considered Radioactive Material Management 

Areas (RMMAs), which indicated the possible presence of unconfined radioactive materials or 
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emissions (DOE 1995a, p. 5-2; DOE 1991, pp. 2, 3, 11, and 13). Table 2-2 lists these areas in 

Building 100. 

Table 2-2. RMMAs in Building 100. 

Room/Area Name Activity

107 Tube Assembly Vacuum tube manufacturing & coating

108 Tube Exhaust and Test Vacuum tube evacuation and testing

109 Product Analysis Magnetic and radioactive gas leak checking

113 Mezz Health Physics Laboratory Instrument calibration & check sources

132 Mezz Fan Room Stack effluent control & tritium recovery 

157/158 Gas Analysis Laboratory Hydrogen isotope analysis

176 Radioanalytical Laboratory Radiological Laboratory, tritium recovery

182-C Tube Assembly Vacuum tube development and testing

182-G Tube Exhaust Vacuum tube development and testing

191 CPE Hood Room Ceramic product testing facility

Source: DOE (1995a, p. 5-3). 

Area 107 was the assembly area for neutron tubes. A neutron tube is the main subassembly of the 

neutron generator. The neutron tube is a high vacuum tube similar in operation to a miniature linear 

ion accelerator (DOE 1990, p. 14). Tube manufacturing required clean-room conditions and used 

specialized vacuum-sealing technologies and metal spray deposition equipment (PDN 763). Section 

2.3.1 of this document provides additional information on the production of neutron tubes. 

Area 108 was the primary tritium handling area at Pinellas. Pure tritium gas was received from the 

DOE Savannah River Site in standard LP50 containers and transferred to depleted uranium beds for 

storage. Overall tritium use at Pinellas was generally low with an average yearly inventory of 

approximately 15 grams (0.53 ounces) (PDN 748, p. 94). Using an activity of 9,640 curies per gram, 

the average yearly inventory of tritium was approximately 144,600 curies. There have been 

indications that maintenance workers were asked to reset tritium radiation area alarms in area 108 

without the use of respirators during power outages. This occurred with no negative pressure for the 

glove boxes (ORAUT-2004-0127). 

The major tritium activity in Area 108 was production loading of neutron tubes and other components 

with tritium. The assemblies were loaded with tritium through a hydriding process in which the 

assemblies were evacuated and filled with tritium gas and the tritium was captured by a thin film of 

metal on the inside of the tube. Initial test firing of the neutron generators occurred in Area 108. 

Other activities in Area 108 included mass spectrometer analysis of gas samples and maintenance of 

the spent uranium storage beds for use and disposal. Most tritium was stored and used in Area 108 

(PDN 748, p. 94). 

Area 109 contained product testing and product analysis facilities for neutron tubes and completed 

neutron generators. Manufactured components were tested for operability and vacuum-sealed 

components were checked for leakage in Area 109. Part of the neutron generator testing included 

test firing of the devices and leak testing. Initial leak testing used helium and Freon leak-checking 

systems. In 1963 the Pinellas Plant began using 85Kr in Radiflo® leak test equipment for leak 

checking of the vacuum tubes (PDN 763). 

Area 113M was on the second floor of Building 100 and housed the check sources and calibration 

laboratory for Health Physics instruments. 
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Area 132M was on the second floor of Building 100 and housed the central exhaust fan room. It 

contained the Stack Effluent Control System (SECS) from 1960 until 1982 when that system was 

replaced by the Tritium Recovery System (TRS) (Weaver 1993, p. 3). 

Area 157/158 contained the gas analysis laboratory. This area was used for tritium target sample 

preparation for the linear accelerator in Building 800 and mass spectrometer analysis of completed 

components for tritium content. Most of the activities in Area 157/158 were completed inside 

ventilated laboratory hoods that exhausted through the west exhaust stack. 

Area 182 was the vacuum tube development engineering section. It was used to engineer, design, 

fabricate, and test prototype vacuum tubes for neutron generators and other components. Areas 

182-C and 182-G were considered RMMAs due to the small quantities of tritium used in vacuum tube 

development. Area 182 was exhausted via the west main stack on Building 100. 

Area 191/192 was the ceramic product engineering (CPE) section. Minor levels of tritium were used 

in the production and development of specialty ceramic components. 

The Radioanalytical Laboratory was installed in 1966 in Area 176 on the southwest corner of Building 

100. It housed the TRS from 1982 until plant shutdown in 1992. The TRS recovered tritium from the 

plant ventilation stacks and converted it to tritium oxide for dilution and disposal. 

Building 100 has two exhaust stacks. The west main stack exhausted 770 cubic meters per minute 

(27,200 cubic feet per minute) from the west side of Building 100. The stack is 1.5 meters (5 feet) in 

diameter and 30.5 meters (100 feet) high (DOE 1983, p. 2-18). The east main stack exhausted 1,140 

cubic meters per minute (40,240 cubic feet per minute) from the east side of Building 100. The stack 

is 2.4 meters (8 feet) in diameter and 21 meters (70 feet) high (DOE 1983, p. 2-18). During plant 

operation, both stacks exhausted tritium and 85Kr from the vacuum tube exhaust, test, and assembly 

areas. Both stacks were equipped with continuous samplers to monitor the exhaust stream. An 

additional 12 sampling stations were located around the plant perimeter. All measured discharges of 

tritium and 85Kr were well below DOE and U.S. Environmental Protection Agency standards, and no 

plutonium release was ever detected during manufacturing or decontamination (MMSC 1995, p. 3-2). 

Section 2.3.2 provides additional information on the annual tritium and krypton releases. 

In 1988 a modernization task force conducted a detailed radiological survey of Building 100 to identify 

the level and extent of radiological contamination. A June 17, 1988 survey showed smearable tritium 

contamination in approximately 13 percent of Building 100. The maximum reading was 1×108

disintegrations per minute per 100 square centimeter smear on the interior of an exhaust hood in Area 

108. The average reading throughout the building was less than 220 disintegrations per minute per 

100 square centimeters (Author unknown 1988a, Bldg. 100/300 survey). 

Building 200 

Building 200 was built in stages between 1959 and 1978; it covers approximately 1,505 square 

meters (16,200 square feet). The building was used for destructive testing of neutron generators and 

other components manufactured at Pinellas (Author unknown 1988a, Bldg. 200 survey). Destructive 

testing included shock, vibration, and explosive tests. 

Destructive testing included shock, vibration, and explosive tests

About 5 neutron generators at one time were functionally tested. This involved destruction of the units 

by explosive detonation, resulting in fragments of the units as well as other materials. The units were 

typically packed in urethane foam which also fragmented, adding to the radioactive waste. The 

Styrofoam was rigid and ranged from pieces to grain sized. Styrofoam was also used as a spacer to 
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locate the generators in relation to the measurement instrument. There were also instrumentation 

cables and connectors which became part of the waste.

For the “Boom Boxes”, a special treated plywood barrier was installed inside of the chamber doors to 

deflect some of the detonation. They were rotated 90 degrees after each generator test, allowing for 

four tests. Particles of the generator would imbed into these boards. 

The radioactive waste would have been comprised of the generator remains, Styrofoam pieces and 

particulates, plywood, cables and connectors. This would be collected in the container as shown in 

Figure 2-5. (ORAUT-2005-0272) 

Figure 2-5. Boom box and collection 

container (ORAUT-2006-0163). 

The modernization task force completed a radiological survey of building 200 in 1988 to identify the 

general level of radiological contamination and perform an initial decontamination cost estimate. The 

June 1988 survey showed less than 5 percent of Building 200 contaminated with tritium. The 

maximum contamination level was 1×104 disintegrations per minute per 100 square centimeter smear 

inside a testing chamber, and the average contamination was less than 220 disintegrations per minute 

per 100 square centimeters (Author unknown 1988a, Bldg. 200 survey). The final characterization 

report in 1997 found that radioactive waste and tritium was present inside the building but did not 

identify specific contamination levels or types of radioactive waste; the report found that all quantities 

were less than reportable amounts required by 40 C.F.R. pt. 355 or 40 C.F.R. pt. 302.4 (Author 

unknown 1996a, p. 3). 

During operation the building exhaust system maintained negative pressure on three testing 

chambers (boom boxes) and a single radiological waste drum. The ventilation system passed 

through high-efficiency particulate air (HEPA) filters before being exhausted from the building roof 

(MMSC 1995, p. 5-4). The stack exhausted 36.8 cubic meters per minute (2,300 cubic feet per 

minute). It stands 17.7 meters (58 feet) tall and is 30.5 centimeters (12 inches) in diameter. 

Building 400

Building 400 was first built in 1968 for development and testing activities. It was expanded in 1978 

and again in 1986. The facility was used to assemble and test the Radioisotopically-powered 

Thermoelectric Generator (RTGs) from 1975 until 1992. Operating cells on the north side of the 

building were used for equipment testing and not involved with the production of RTGs. Figure 2-6 is 

a layout of building 400. 
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Figure 2-6. Layout of Building 400 (DOE, 1982, pg. 9).

The first receipt of plutonium heat sources for the RTG assemblies was on November 4, 1975, when 

seven heat sources totaling approximately 54.4 grams (1.9 ounces) of 238Pu and 13.6 grams (0.48 

ounces) of 239Pu were received from Sandia National Laboratories (SNL) (PDN 764). When 

production of RTG devices ceased in 1990, all unused plutonium heat sources were shipped off the 

site. During 1994 the building was fully decontaminated and released for use by a commercial tenant. 

The final decontamination survey found indoor radon levels to be below the action levels of the Indoor 

Radon Abatement Act. Other radiological surveys of the building showed residual radiation levels 

below free release limits (MMSC 1995, p. 4-1). 

Building 800

Building 800 housed a 200-keV ion accelerator. The accelerator was used to accelerate deuterium 

ions into various tritium targets to measure neutron output (MMSC 1995, p. 5-5). The accelerator was 

operated in building 100, room 161 for about 2 years prior to being moved to building 800 (ORAUT2005-0273). The building ventilation system exhausted 38 cubic meters per minute (1,350 cubic feet 

per minute) through a 25- by 33-centimeter (10- by 13-inch) exhaust stack that extends 6.3 meters 

(20.8 feet) above the ground (DOE 1983, p. 2-18). 

A radiological survey in 1988 identified a maximum reading of 1×108 disintegrations per minute on a 

smear from inside the accelerator, and the average contamination was less than 220 disintegrations 

per minute per 100 square centimeters. Less than 5 percent of the building area was considered 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 15 of 27

contaminated (Author unknown 1988a, Bldg. 800 survey sheet). Figure 2-7 shows the layout of 

Building 800. 

Figure 2-7. Layout of Building 800 (MMSC, 1993, pg. 5).

Building 1000

Building 1000 was used to store low-level solid radioactive waste, solidified waste oil, and used 

equipment (MMSC 1995, p. 5-5). Waste material was stored in the building until a sufficient quantity 

was collected either for shipment to a DOE-approved disposal facility or to be sold for scrap. 

A radiological survey completed in 1988 identified low levels of contamination in up to 75 percent of 

the radiological waste storage bay. The maximum measured contamination was less than 220 

disintegrations per minute per 100 square centimeters (Author unknown 1988a, Bldg. 800 survey 

sheet). 

During the time period from August 1, 1956, through July 31, 1957, the General Electric Company 

leased a building, located at 2300 26th North Avenue, St. Petersburg, Florida. The building had a total 

of 20, 000 square feet. During the lease period, operations utilizing tritium were performed in a 350 

square foot hood room.

When construction of the Pinellas Plant was completed, operations were terminated at the leased 

building and the hoods were transferred to the Pinellas Plant for continued use. Under the direction of 

the Health Physics group at the Pinellas Plant the liquid waste and the exhaust ventilation systems 

were disassembled, packaged and shipped to Savannah River for burial and the room was 
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decontaminated to the minimum detectable radioactivity level of 50 dpm/ 100 cm2 as measured by 

surface swipes. In addition to the hood room, surveys were performed throughout the entire building. 

These surveys revealed no detectable contamination. The building was then released for public use. 

(Forest 1974)

2.3 SITE PRODUCTS

2.3.1

The Pinellas Plant was built in 1956 and began operation in 1957 to manufacture neutron generators 

for atomic weapons. Because of the specialty manufacturing techniques required, the plant’s mission 

was expanded to include manufacturing and testing of other special components for nuclear weapons 

and electronic components for use in extreme environments. Tritium was the primary radioactive 

isotope used in the Pinellas Plant for the full life of the facility. Thimble-sized plutonium capsules were 

used as a heat source in the manufacture of RTG assemblies from 1974 to 1990. Krypton-85 was 

used for leak-testing neutron generators after 1963, and the facility used multiple radioactive sources 

for instrument calibration and laboratory activities (PDN 748, p. 94). The 200-keV ion accelerator in 

Building 800 was another potential source for exposure to ionizing radiation. In addition, 

manufacturing operations at the Pinellas Plant required the use of 32 radiation emitting devices such 

as electron beam welders and X-ray inspection equipment. Section 2.4 contains additional 

information on the radiation emitting equipment used at the Pinellas Plant. The primary products of 

the Pinellas Plant that required the use of radiological materials included neutron generators, RTGs, 

and neutron detectors as described in the following sections.

Equipment

Neutron Generators

Pinellas manufactured neutron generators from 1957 until 1994. The main subassembly of the 

neutron generator is the neutron tube, which is a high-vacuum tube that operates much like a 

miniature linear ion accelerator. Initial design and development of the vacuum tubes occurred in 

Areas 181 and 182 of Building 100. Normal production of the tubes took place in Areas 107, 108, 

109, and 126. 

The neutron tube manufacturing process required spray coating the inside of a glass tube with a thin 

metal film such as titanium or the rare earth element erbium. The tube was then attached to a glass 

manifold vacuum system under an exhaust hood. The normal arrangement had two tubes on each 

system and four systems under each hood. There were 20 hoods in Area 108, but not all of the 

hoods were used all of the time (GE 1990, p. 2). 

As shown in Figure 2-8, the system contained two vacuum pumps and a quartz glass manifold to 

which deuterium and tritium beds and the metal-coated neutron tubes were attached. A roughing 

vacuum pump was used for the initial system evacuation. A mercury diffusion pump reduced system 

pressure to a near perfect vacuum as measured on a mercury U-tube manometer. Once the system 

reached vacuum, valves isolated the manifold and the tritium and deuterium beds were heated to 

flood the system with tritium and deuterium gas. After the required exposure time, the beds were 

allowed to cool, which caused the hydrogen gas to be reabsorbed (GE 1990, p. 1). 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 17 of 27

091504_01_TB

Glass Manifold

#1 Valve

Deuterium

Bed

Tritium

Bed Diffusion Pump

Mercury

Manometer

Neutron

Generator Tubes

Vacuum Pump

Exhaust

Figure 2-8. Neutron tube tritium loading manifold. 

When the manometer showed zero system pressure the operator would use a mobile pulse tank to 

test the functionality of the neutron tubes still attached to the manifold. The pulse tank would cause 

the neutron tube to fire a brief burst of neutrons. Tubes that functioned correctly were removed using 

a torch to melt the glass manifold connection, seal the neutron tubes, and cut them free of the 

manifold (GE 1990, p. 1). 

Tritium release to the environment occurred during removal of neutron-generating tubes and 

maintenance of the system. Vacuum pump seal oil would become contaminated with tritium gas, 

tritium oxide, and mercury vapors. The interior of the glass manifold would become coated with 

grease containing tritium and deuterium. The pumps and valves were removed periodically to a 

separate hood area to be cleaned and repaired while the glass manifold was cleaned with solvents to 

remove accumulated greases. The occasional breakage of a neutron tube would cause floor and 

hood contamination from the fine metal hydride powder that coated the inside of the tube (GE 1990, 

p. 2). 

Improved management control of the hydride process and replacement of the mercury manometer 

with vacuum gauges in 1959 and 1960 significantly reduced the amount of tritium released to the 

environment. Additional reduction resulted after installation of the SECS, which used heated copper 

wire in the exhaust stream to convert tritium gas to tritium oxide. Chillers and demisters condensed 

and collected the vapor, and that liquid was routed to underground tanks for dilution and discharge 

(GE 1990, p. 3). 

After manufacture, the neutron generator was leak tested. Initial leak testing used helium or Freon for 

leak detection. In 1963 the Radiflo leak-testing units were converted to use 85Kr (PDN 748, p. 94). 

The neutron tube assembly area was exhausted through a ventilation system that vented a total of 

802.5 cubic meters per second (28,340 cubic feet per minute) from two exhaust stacks in the building 

roof. An exhaust stack alarm was activated when the discharge exceeded 60 microcuries per cubic 

meter for more than two minutes (Ward, p. 2). 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 18 of 27

Building 200 was used to test the operability of the neutron generators under extreme conditions. 

These quality assurance tests included destructive testing of the units inside test chambers known as 

boom boxes. The ventilation system for Building 200 passed through HEPA filters before exhausting 

out the building roof. 

There were several types of equipment used to functional test neutron generators. This depended on 

the end use of the generator (ORAUT-2005-0272). 

Firing Tubes with Boom Box containers 

This equipment was mounted on and through a wall. See Figure 2-9.Then the neutron generator was 

wired and assembled in a urethane foam fixture and inserted in a “firing tube.” The tube was closed 

and the area where the firing tubes were located was cleared then the generator detonated. On the 

far side of the wall (in the secured room), a steel “Boom Box” was mounted. This contained the 

detonation. The top of the boom box was connected to a duct system. The bottom was a funnel shape 

that had a sliding trap door in it. After the detonation, a plastic bag was placed in a standard office 

trash can placed under the boom box. The firing tube was opened and a rammer inserted to push any 

debris out of the tube into the boom box. The boom box’s trap door was opened, and the main access 

door opened as well. Any surviving debris was brushed down using a standard dust pan brush. The 

bag was tied and stored in case any further examination was needed. The test technicians may not 

have used any protective wear, neither gloves, dust masks, or respirators. 

Figure 2-9. Firing tubes and the boom box configuration

(ORAUT-2005-0272). 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 19 of 27

Spin Testing in an Enclosed Fixture

This equipment basically looked like a big top loading washing machine as shown in Figure 2-10. It 

was located inside the secured room. The neutron generator was wired and assembled in a hard 

plastic material fixture and inserted in a heavy aluminum fixture. The very heavy lid on the top of the 

equipment was closed. People left the secured room, and the neutron generator was detonated. After 

the test, the equipment was opened, the fixture removed, and the debris contents (generator and 

plastic fixture pieces) manually pried out on a work bench and placed in a plastic bag. There was no 

direct vent for this equipment other than the room’s ventilation.

Design of the “Boom Boxes”

The boom boxes were constructed of steel, about 1/8 to 1⁄4 inch thick. They were of welded 

construction. The hinged doors swung up to access the area to be cleaned (neutron generator 

debris). On the back side of the door, the plywood panel was mounted in a simple frame. The door 

was flat sheet metal with about a 1/8 inch gasket cemented to the inside to make contact with the 

boom box face. It was by no means an airtight fit. The door was not latched down, but held in place by 

elastic cords. On top of each chamber there was an exhaust duct about 4 X 8 inches that joined 

together then went up to the exhaust system. The sliding door on the bottom was of a guillotine 

design.

There were two complete testing systems, each having instrumentation, firing tubes, and boom boxes. 

Each system had two firing tubes (large and small), and on the back side of the wall a boom box was 

located. The boom box had two compartments (chambers), two access doors, and two sliding 

trapdoors, all of which was aligned behind each firing tube. The boom box was actually one large 

welded unit and had a permanent steel barrier between each compartment (ORAUT-2005-0272). 

Radioisotopically-powered Thermoelectric Generators

RTGs are batteries that use a silicon-germanium thermopile to convert the thermal energy of decaying 

plutonium oxide into electricity. Each RTG is capable of generating about 25 milliwatts of electrical 

power at 2 volts for more than 25 years. They power a multitude of devices from remote airport 

runway markers to heat sources in satellites. 

RTG contain a heat source in the form of a small amount 

of plutonium oxide encapsulated in a thimble-size, triplesealed container (DOE 1983, p. 2-7). The capsules were 

manufactured at Los Alamos National Laboratories (LANL) 

or Sandia National Laboratory (SNL) and shipped to the 

Pinellas Plant. No unencapsulated plutonium or plutonium 

oxide was used at Pinellas, and no record could be found 

to indicate that the plutonium capsules were breached or 

opened at Pinellas. 

Pinellas manufactured the RTGs in Building 400 from 1975 

until 1990. The facility was able to produce approximately 

50 units per month and production rarely exceeded 500 

units per year (Author unknown 1988b, p. 4). Production 

was stopped and all plutonium, with the exception of 

calorimetric sources and small instrument calibration 

check sources, was removed from the plant in February 

1991. No releases of plutonium from Pinellas Plant 

operations have been detected in the environment (PDN Figure 2-10. Spin tester (ORAUT-2006-0163).
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 20 of 27

764). 

Neutron Detectors

Neutron detectors were small electronic assemblies used in joint test assemblies to verify the output 

of a neutron generator during actual tests. The neutron detectors were used to verify operability of 

the weapon system without initiating a nuclear explosion (DOE 1990, p. 15). These components were 

manufactured in Building 100 and tested using the linear accelerator in Building 800. 

Other Products

In addition to the products discussed, the Pinellas Plant produced other special mechanical and 

electronic devices and test equipment for a variety of DOE and General Electric applications. These 

components included long-life batteries, high-speed switching circuits, and specially designed 

capacitors. These products did not require direct use of radioactive isotopes for their manufacture, 

and this document does not cover them further. 

2.3.2

Tritium

Radioactive Materials

Tritium gas was stored in beds of depleted uranium metal at the Pinellas Plant. The uranium and 

tritium join to form uranium tritide, which allowed large quantities of ultra-pure tritium to be stored in a 

small volume at normal temperature and pressure. A search of plant records indicated that, from the 

start of plant operation in 1957 until November 1993, the total amount of tritium received by Pinellas 

was 234.1 grams (8.3 ounces), which, at 9,640 curries per gram, is 2.26×106 curies. The total amount 

of tritium shipped, as product, waste, or material returned to the DOE, was 164.6 grams (5.8 ounces) 

or 1.6×106 curies. The amount calculated to have decayed away was 58.4 grams (2 ounces; 562,976 

curies), and the amount released into wastewater or air was 11.1 grams (0.4 ounces; 107,000 curies) 

(PDN 765, p. 1). 

Exposure to tritium oxide is the prime consideration when assessing tritium dose because the body 

does not retain gaseous tritium very well, whereas tritium oxide is readily absorbed, which causes a 

continuous radiation exposure until eliminated by normal water excretion (DOE 1983, p. 2-10). 

Krypton-85

Very small quantities of Krypton-85 were used in two of the Radiflo leak detection units at Pinellas 

from 1963 until 1994. The Radiflo leak detection units were housed in separate rooms and 

surrounded by ventilation shrouds. Each shroud was connected to ductwork that exhausted 93.4 

cubic meters per minute (3,300 cubic feet per minute) to the east main exhaust stack (DOE 1990, 

p. 3). 

Carbon-14

Between 1979 and 1983 a very small quantity of 14C was discharged to the atmosphere through the 

Pinellas Plant stacks. The total amount discharged between 1979 and 1983 was approximately 

3x10−4 curries. The annual discharges of 14C are shown in Table 2-3. No specific information was 

available to identify the plant activities that resulted in the release of the 14C. 

Atmospheric Discharges of Tritium, Krypton-85, and Carbon-14

The majority of the atmospheric releases of tritium, 85Kr, and 14C were through the four exhaust stacks 

on Buildings 100, 200, and 800. Table 2-3 lists the releases of these radionuclides between 1956 and 

1992. 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 21 of 27

Releases Due to Unusual Events 

Other releases of radionuclides during operation of the Pinellas Plant have been identified. These 

were caused by accidents, operator errors, or similar unplanned events. Table 2-4 lists a chronology 

of some of the unusual events and the resultant radiological releases (if known) at the Pinellas Plant 

from startup through 1982. 

Plutonium 

The first recorded receipt of plutonium at the Pinellas Plant was on January 18, 1957, when a single 

7-gram (0.25-ounce) 238Pu calibration source was received to calibrate Health Physics monitoring 

equipment. Plutonium for RTG production did not arrive on site until November 4, 1975 when seven 

sealed sources totaling 54.4 grams of 238Pu arrived from SNL. The RTG production operation at 

Pinellas Plant used small sealed sources of plutonium produced by LANL or SNL. Each sealed 

source contained about 9 grams (0.3 ounce) of a four-to-one mixture of 238Pu and 239Pu. The last 

plutonium, with the exception of calibration check sources, was removed from Pinellas Plant in 

February 1991 (PDN 764, Item 7). 

The plutonium sources at Pinellas were enclosed in a triple metal encapsulation. These units were 

never opened. The sealed capsules were used as heat sources for the RTGs manufactured in 

Building 400 (DOE 1983, p. 2-11). 

Plutonium-238 has a half-life of 87.74 years, and 239Pu has a half-life of 24,110 years. Both emit 

alpha particles, gamma photons, and neutrons. The principal hazard from these isotopes is from 

alpha particle emission from quantities retained in the body. Plutonium oxide is relatively insoluble 

and, if ingested, is not readily retained in the body. The primary source of body deposition is by 

inhalation of respirable particles. 

Table 2-3. Annual radionuclides released from Pinellas Plant stacks in curies. 

Year

Tritium 

gas

Tritium 

oxide Krypton-85 Carbon-14 Comments

1956 Plant under construction

1957 6,660 140 First tritium operations in June 1957

1958 31,920 580

1959 41,070 1330

1960 6,265 435 Process changed to reduce tritium loss. SECS installed. 

1961 504 306

1962 611 249

1963 179 103 4 Kr-85 first used in Radiflo leak test units

1964 233 57 47

1965 50 100 153

1966 325 385 49

1967 1,994 213 70 Milwaukee group moved to Pinellas Plant

1968 1,586 215 202

1969 3,275 297 55

1970 587 465 44

1971 694 374 12

1972 111 222 16 Gas laboratory connected to SECS

1973 74 318 1

1974 155 202 4

1975 154 165 1

1976 101 176 12

1977 129 161 18

1978 132 156 5

1979 128 206 5 1.0 E-4

1980 140 209 2 1.0 E-4 Tritium stack air monitoring installed in Building 800

1981 222 195 4 5.0 E-5 Pinellas County sewer system began sampling for tritium
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 22 of 27

Year

Tritium 

gas

Tritium 

oxide Krypton-85 Carbon-14 Comments

1982 227 257 8 4.0 E-5 TRS replaced SECS in September

1983 259 152 11 1.0 E-5

1984 96 206 2

1985 111 149 5.3

1986 33 161 4.6

1987 68 138 38

1988 132.2 124.1 30

1989 43.7 60 12.9

1990 35.5 60.5 12.1

1991 23 88 3.58

1992 8 31.7 10

Source: DOE, 1994, pg. 27. 

Depleted Uranium

Tritium was stored in one of several uranium hydride flasks, each storage flask containing 50 grams 

(1.8 ounces) of depleted 238U powder in a stainless-steel cylinder 25 millimeters (1 inch) in diameter 

by 152 millimeters (6 inches) long. The tritium bonds with the depleted uranium metal to form 

uranium tritide, which is stable at room temperature but can be decomposed by heating to release 

ultra-pure tritium. The uranium beds can be hydrided and dehydrided many times under appropriate 

conditions without loss of efficiency. The depleted uranium metal was fully contained inside the 

storage flask, and no information could be found to indicate that depleted uranium metal was released 

during plant operations (Ward, p. 12). 

Unused depleted uranium “chucks” or small pieces measuring less than 1⁄4” were fabricated from a 50 

gram piece for the loading of the tritium storage tubes. The machinist apparently kept this material for 

several minutes in his pocket upon transfer to the machine shop (ORAUT-2004-0127). No uranium 

bioassay analysis was conducted at Pinellas. 

Table 2-4. Chronology of unusual events. 

Date Description

Curies 

released

11-1957 Neutron generator output measured at 10 millirem/pulse at 2.5 cm (1 inch). 

12-1957 Raytheon X-ray units found to contain 10 nanocuries of Co-60

12-10-57 Operator error in reading manometer in Room 18 458

2-11-58 Error estimating amount of tritium remaining in charging system in Room 18 1,253

7-8-58 Glass system breakage in Room 22 280

3-7-58 Glass system breakage in Room 18 567

8-16-58 Operator error with tritium loader valve position – Room 21 780

8-18-58 Glass manifold breakage – Room 21 1,180

2-10-59 Operator error in valve positioning – Room 8 286

6-4-59 Personnel error working on SECS test system – Room 21 753

6-18-59 Excess air released from tritium loading system 423

1-1960 Operator error – stopcock left open on tritium loading system 40

2-5-60 Glass manifold broke from strain 72

2-11-60 Operator error – stopcock left open on tritium loading system 308

7-8-60 Broken sample bulb 6.8

9-1963 Krypton-85 first used in Radiflo leak testing units

2-1964 E-beam welder found reading 250 millirem/hr at startup – shielded to 4 millirem/hr.

2-4-65 Explosion during cold trapping of krypton 38

12-1965 X-ray diffraction unit found leaking – new shielding installed

5-1966 SECS cold water removal problems 252

1-27-67 Glove box vacuum pump oil degassed 32

4-1967 HP surveying new X-ray machine received 1.6-rad exposure. Shielding installed.
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 23 of 27

1-17-68 Faulty relay in Radiflo unit No. 1 – vented krypton-85 when placed in manual 129

2-1969 Leaking flange at absorption pump in Area 108 8

2-3-69 Equipment failure – Radiflo valve did not seat properly – Kr-85 vented 20

9-1969 X-ray unit in Area 155 found leaking to 1.6 rad/hr

12-28-70 SECS column saturated due to air leak in Area 108 117

3-12-71 Copper gasket uncovered in Room 18 hood – high internal dose 7.3

10-9-71 Radiflo Unit No. 1 – Krypton-85 storage tank leak 6.1

10-21-71 Tritium release from improperly baked evaporator system in Area 182D 129

4-1972 Area contaminated from liquid discharge in Area 182D 1.5

5-1972 Hand exposure from XRE X-ray emission unit No. 7R during cleaning 

8-3-72 Leaking absorption pump 12

1-31-75 Improper valve closure on uranium bed 150

2-10-75 Absorption pump leak – Area 182D 42

Source: GE (1990, pp. A-1 to B-8).

Calibration Sources

Pinellas used multiple calibration sources for checking and calibrating plant instrumentation. These 

items were maintained in the Health Physics Laboratory in Area 113 of Building 100. While the exact 

inventory of radioactive sources varied, most sources were sealed microcurie (1×10-6) check sources 

of radioactive isotopes such as 137Ce, 238,239Pu, 60Co, 14C, and 90Sr (PDN 765, pp. 1–6). 

2.3.3

Liquid Radioactive Waste

Waste Disposal

Four types of liquid waste were generated during plant operation: Sanitary, industrial, chemical and, 

potentially, tritium-contaminated waste. Before 1982, sanitary wastes were processed by an onsite 

sewage treatment facility and mixed with neutralized industrial waste in the west pond. Chemical 

drain lines from inside the plant routed industrial waste to an onsite treatment facility where it was 

chemically neutralized and pumped to the west pond. Water from the west pond was sprayed on a 

10-acre irrigation field. A subsurface drain system under the 10-acre field collected liquids and routed 

them to the east pond. Liquid in the east pond was sampled and periodically discharged to a Pinellas 

County drainage pipe and roadside ditch that drained into Cross Bayou Canal and Tampa Bay (DOE 

1983, p. 2-14). 

It is possible that tritium-contaminated liquid waste generated during operations and tritium oxide from 

the TRS was piped to a group of three underground holding tanks in the health physics area outside 

the southwest corner of Building 100. The liquid was sampled and discharged if the radioactive 

content was below the limits specified in Chapter XI of DOE Order 5480.1. Liquids with higher 

concentrations of tritium were incorporated into a solid for offsite burial. Effluent discharge from the 

holding tanks was pumped to the west pond where it mixed with the sanitary and industrial wastes 

discussed earlier (DOE 1983, p. 2-13). 

Solid Radioactive Waste

The majority of radioactive waste from the site consisted of tritium-contaminated classified 

components. These components were packaged and shipped to a DOE-controlled site for disposal. 

Small quantities of radioactive liquids were solidified with absorbing compounds and included with the 

solid radioactive waste (DOE 1983, p. 2-21). 

Gaseous Radioactive Waste

Gaseous radioactive effluents were produced and released during the operation of the Pinellas Plant. 

Gaseous tritium, tritium oxide, 85K, and a very a small quantity of 14C were the only identified releases. 

The four main discharge points were the two exhaust stacks on Building 100 and the single exhaust 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 24 of 27

stacks on Buildings 200 and 800. During the initial years of plant operation tritium releases were as 

high as 42,400 curies per year. Installation of the SECS in 1960 reduced tritium emissions to less 

than 1,000 curies per year, and installation of the TRS in 1982 further reduced tritium emissions to 

less than 500 curies per year. 

2.4 SITE EQUIPMENT 

Exposure to radioactive isotopes was not the only source of ionizing radiation at the Pinellas Plant. 

Many pieces of production equipment used at the Pinellas Plant were capable of producing radiation. 

Table 2-5 lists the locations of radiation generating equipment on the Pinellas Plant site. 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 25 of 27

Table 2-5. Radiation-producing equipment.

a

Location Quantity Type ID Number

107 2 X-Ray Emission (XRE) Units CCN87103, CCN99591

114 2 Industrial X-Ray Units MN87904, MN87851

114 1 Faxitron X-Ray Corp MN87243

114 1 TFI X-Ray Television None found

127 1 Inspector Unit None found

138 1 Electron Beam Welder MN62183

161B 2 X-Ray Diffraction (XRD) Units MN86640, MN86641

140/141 1 Electron Beam Welderb 140/141

161B 1 Micro X-Ray Diffraction (XRD) Unit MN86747

161B 1 Electron Microprobe MN86607

161B 1 Energy Dispersive Analyzer (EDA) MN86475A

162 2 Scanning Electron Microscope (SEM) MN94109, MN94225

162 1 Transmission Electron Microscope (TEM) MN94168

163 1 X-Ray Thickness Gage MN550042

164 1 Cabinet X-Ray Unit CCN91407

175 1 X-Ray Diffraction (XRD) Unit CN87952

176 1 X-Ray Emission (XRE) Unit None found

192B 1 Sedigraph MN94285

193N 1 Scanning Electron Microscope (SEM) MN91992

194E 1 Picker (Cabinet X-Ray Unit) MN87042

300 2 Electron Beam Welder MN61660, MN76803

300 1 Phillips (Cabinet X-Ray Unit) MN87810

300 2 Faxitron X-Ray Corp MN088001, MN099915

400 2 Electron Beam Welder MN61346, None found

400 1 Cabinet X-Ray Unit MN63294

899 1 Ion Accelerator

Warehouse 1 X-Ray Television None found

Source: PDN (1022); Author unknown (1986, p. 1).

a. Neutron generators produced for use in nuclear weapons are not listed in this table and may have been 

found throughout the plant. 

b. (ORAUT-2005-0274). 
Document No. ORAUT-TKBS-0029-2 Revision No. 01 Effective Date: 10/04/2006 Page 26 of 27

REFERENCES

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0292, June 17 (Project Document Number 240001018). 

Author unknown, 1988b, Radiological Dose from RTGs, Pinellas Plant, October (Project Document 

Number 240001025). 

Author unknown, 1996a, Characterization Report: Building 200 West, Pinellas Plant, March 22, 

Accession Number 434-97-0481 (Project Document Number 240001284). 

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Company, Neutron Devices, St. Petersburg, Florida. 

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Specialty Components, Inc., February 22, Accession Number 434-97-0438 (Project Document 

Number 240001103).