Battelle Team 

Dose Reconstruction 

Project for NIOSH

Document Title: 

Site Profiles for Atomic Weapons Employers that 

Refined Uranium and Thorium 

Appendix P – Baker-Perkins– Michigan 

. 

Document Number: Battelle-TBD-6001 

Appendix P 

Revision: 0 

Effective Date: 09/14/2007 

Type of Document: TBD Appendix

Supersedes: None 

Subject Experts: R.I. Scherpelz 

Document Owner 

Approval: Signature on file Approval Date: 7/24/2007 

Robert I. Scherpelz, Staff Scientist 

Approval: Signature on file Approval Date: 7/24/2007 

Jay A. MacLellan, Battelle PNWD Task Manager 

Concurrence: Signature on file Concurrence Date: 7/24/2007 

Richard J. Traub, Staff Scientist 

Approval: Signature on file Approval Date: 9/12/2007 

James W. Neton, Associate Director of 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. Battelle-TBD-6000; 

Appendix P 

Revision No. 0 Effective Date: 09/14/2007 Page 2 

BAKER-PERKINS– MICHIGAN 

P.1 Introduction 

This document serves as an appendix to Battelle-TBD-6001 Site Profiles for Atomic 

Weapons Employers that Refined Uranium and Thorium. This appendix describes the 

results of document research specific to this site. Where specific information is lacking, 

research into similar facilities described in the body of this Site Profile is used. 

P.2 Site Description 

Baker-Perkins in Saginaw, Michigan, manufactures commercial mixers (among other 

products). Documentation demonstrates that a limited quantity of radioactive material 

was used in a test process with its mixers at its laboratory facility (a single building). 

Controls were in place during the process and post-operational decontamination was 

implemented with radiological surveys having been performed. AWE period of 

performance was five days in May, 1956. 

P.2.1 Site Activities 

On May 14-15, 1956, Baker-Perkins performed a test of its mixing equipment for NLO 

(Fernald). The tests involved mixing approximately 1-2 drums of uranium trioxide 

(orange oxide) with water and kneading the mixture with the Baker-Perkins “P” and “K” 

Ko-Kneader machines. Decontamination of the equipment was conducted on May 15-18, 

1956. The cleaning included chipping, power brushing and steaming. Air monitoring 

was conducted across the five day period (Reference #9505, page 10, 16-25).

P.2.2 Job Categories 

Each claim will be evaluated to determine the most appropriate Job Category from the list 

below. 

Plant Floor High (Involved directly in operations) 

Grinder 

Plant Floor Low (Involved in support of operations) 

Assembler 

Supervisor 

Draftsman/tester 

Clerk 

None reviewed 

P.3 Occupational Medical Dose 

No information regarding occupational medical dose specific to Baker-Perkins--Michigan 

was found. Information to be used in dose reconstructions for which no specific 

information is available is provided in ORAUT-OTIB-0006, the dose reconstruction 

project technical information bulletin covering diagnostic x-ray procedures. 

P.4 Occupational Internal Dose 

Air monitoring data were found in the Site Research database relating to occupational 

internal dose during the five days of AEC work (Reference #9505, pages 16-25). Results 
Document No. Battelle-TBD-6000; 

Appendix P 

Revision No. 0 Effective Date: 09/14/2007 Page 3 

of both breathing zone (BZ) and general area (GA) monitoring for alpha radiation (alpha 

scintillation) were reported. The geometric mean and geometric standard deviation for 

BZ monitoring were 1,210 dpm/m3

 and 4.91 respectively. The corresponding values for 

the GA samples were 92 dpm/m3

 and 5.48. There are not sufficient data on monitoring 

duration to calculate time-weighted averages. Therefore, internal doses will use the 

geometric mean of the distribution of measured exposures to represent exposure over the 

entire day. Considering the nature of the work and the types of samples taken, a “plant 

floor high” exposure would be calculated as 50% BZ and 50% GA exposure levels. 

“Plant floor low” would be calculated as 25% BZ and 75% GA exposure levels, while a 

“supervisor” would be 100% GA exposure. The “clerk” exposure would be 10% of the 

“supervisor” exposure. 

Tables P.1 and P.2 present these internal dose estimates in pCi per calendar day to be 

used for each calendar year listed. The table values should be multiplied by 73 to 

calculate internal dose estimates for a single day of the 5 day exposure period. 

P.5 Occupational External Dose 

No external dose readings were reported in the Site Research database related to 

occupational external dose during the five days of AEC work. However, it was reported 

that “at least one, but no more than two ‘drums’ of orange oxide are believed to have 

been used in the tests” (Reference #9505, page 10). Thus external dose could be 

calculated assuming a distance of five feet from two drums of orange oxide, or by the 

external dose from air concentrations of orange oxide associated with the alpha radiation 

levels reported in P.4. 

Alternatively, the Uranium Refining TBD external exposure for either “boildown and 

denitration” or “oxide reduction-tray furnace” operations could be used. Either of these 

exposures would be very favorable to the claimant as they are based upon industrial 

rather than experimental process volumes. 

Tables P.3 and P.4 present these external dose estimates in mrem per calendar day to be 

used for each calendar year listed. The table values should be multiplied by 73 to 

calculate external dose estimates for a single day of the 5 day exposure period. 

P.6 Residual Contamination 

Documentation reviewed indicates that there is little potential for significant residual 

contamination outside of the period in which weapons-related production occurred. 

P.7 References 

1. DOE Office of Health, Safety and Security, EEOICPA web site. 

http://www.hss.energy.gov/healthsafety/fwsp/advocacy/faclist/findfacility.cfm 

2. Report on Residual Radioactive and Beryllium Contamination at Atomic Weapons 

Employer Facilities and Beryllium Vender Facilities. 

http://www.cdc.gov/niosh/ocas/pdfs/tbd/rescon/rcontam1206.pdf 
Document No. Battelle-TBD-6000; Appendix P Revision No. 0 Effective Date: 09/14/2007 

Table P.1 INTERNAL DOSE PATHWAYS - Inhalation of Airborne Radionuclides Assumptions: Operational Period Daily Weighted Average Air Concentration, Plant Floor High: 1210 dpm/m3, GSD: 4.84 

General Area Air Concentration: 92 dpm/m3, GSD: 5.5 

TBD GSD Default is 5 Conversion Factor: 2.22 dpm/pCi Breathing Rate: 1.2 m^3/hour All intakes and doses assume full-time employment for the given year. 

Intakes are the geometric mean of a lognormal distribution 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Intake 

(pCi/d) GSD TBD Reference or Rese

Plant Floor High 1956 Operations 40 U234 3.15E+01 5.5 

50% BZ + 50% GA (see BZ and GA 

Plant Floor Low 1956 Operations 40 U234 1.73E+01 5.5 

25% BZ + 75% GA (see BZ and GA 

Supervisor 1956 Operations 40 U234 5.45E+00 5.5 100% GA (see text) Clerical 1956 Operations 40 U234 5.45E-01 5.5 10% GA (see text) 
Document No. Battelle-TBD-6000; Appendix P Revision No. 0 Effective Date: 09/14/2007 

Table P.2 INTERNAL DOSE PATHWAYS - Ingestion of Airborne Radionuclides Assumptions: Air Concentration to Intake Conversion Factor: 3.06E-05 (M^3/d)/(hr/y) - see 7.1.6 TBD-6000 and 8.5.3 TBD-6001 Deposition velocity: 0.00075 m/s Resuspension Factor: 1.00E-06 1/m Intakes are the geometric mean of a lognormal distribution 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Intake 

(pCi/d) GSD TBD Reference or Resea

Plant Floor High 1956 Operations 40 U234 2.94E-01 5.5 

50% BZ + 50% GA (see teBZ and GA 

Plant Floor Low 1956 Operations 40 U234 1.61E-01 5.5 

25% BZ + 75% GA (see teBZ and GA 

Supervisor 1956 Operations 40 U234 5.08E-02 5.5 100% GA (see text) Clerical 1956 Operations 40 U234 5.08E-03 5.5 10% GA (see text) 
Document No. Battelle-TBD-6000; Appendix P Revision No. 0 Effective Date: 09/14/2007 

Table P.3 EXTERNAL DOSE PATHWAYS - Whole Body Assumptions: Submersion Dose Conversion Factor: 2.462E-09 mrem/h/dpm/m^3 

Deposition velocity: 0.00075 m/s 

Contaminated Surface Dose Conversion Factor: 5.615E-10 mrem/h/dpm/m^2 All external dose from estimated exposure to Uranium Nitrate Drums 

Residual period: Assume no handling of U metal - only exposure is from residual contamination on floor and in air Dose in the table is the geometric mean of a lognormal distribution 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

External 

Whole 

Body 

(mR/d) GSD TBD Reference or Resea

Plant Floor High 1956 Operations 40 U234 1.28E+00 5 

Generic Refining TBD, Taand Denitration) 

Plant Floor Low 1956 Operations 40 U234 1.27E+00 5 Same Supervisor 1956 Operations 40 U234 1.26E+00 5 Same Clerical 1956 Operations 40 U234 4.08E-04 5 Same 
Document No. Battelle-TBD-6000; Appendix P Revision No. 0 Effective Date: 09/14/2007 

Table P.4 EXTERNAL DOSE PATHWAYS - Skin Assumptions: All assumptions from TBD-6000 Section 6.3 Operational Period: Non-penetrating dose to skin 9.0 mR/hour (hands and forearms) 2.65 mR/hour (other) 

Plant Floor High: Assume hands in contact with material 50% of time. Other skin is 100% of dose rate at Plant Floor Low: 50% of Plant Floor High Supervisor: assume 10% of Plant Floor Low for time in contact with material Clerical: assume no handling of U. Residual Period: No Residual Period Dose in the table is the geometric mean of a lognormal distribution 

Job Category Year 

Operation 

Phase Hr/Yr 

Relevant 

Nuclide 

Hands & 

Forearms 

(mR/d) 

Other Skin 

(mR/d) 

GSD TBD Ref

Plant Floor High 1956 Operations 40 U234 9.86E-01 2.90E-01 5 

Generic Refiand Denitrat

Plant Floor Low 1956 Operations 40 U234 4.93E-01 1.45E-01 5 Same Supervisor 1956 Operations 40 U234 4.93E-02 3.63E-02 5 Same Clerical 1956 Operations 0 U234 0.00E+00 0.00E+00 5 Same