7620 U-005-307.12 .HEALTH PHYSICS 'MANUAL OF GOOD PRACTICES FOR URANIUM FACILITIES - (USED AS A REFERENCE IN OU 3 RIIFSIPP APPENDIX A) 06100188 EGG-25301UC-41 INEL USDOE 450 REPORT AUG 3 M8 EGG-2530 UC-41 C*1 Department of Energy Health Physics Manual of Good Practices for Uranium Facilities Bryce L. Rich, Chairman Stuart L. Hinnefeld Clayton R. Lagerquist W. Gary hlansfield Leo H. Munson Edgar R. Wagner E. J. Vallario, D 0 E Project Man a g er I June 1988 Prepared for the U.S. Department of Energy Assistant Secretary for Environment, Safety, and Health U nder Contract DE-AC07-761 D 0 1570 EGG-2530 uc-41 Health Physics Manual of Good Practices for Uranium Facilities Bryce L. Rich, Chairman Stuart L. Hinnefelda Clayton R. Lagerquistb W. Gary Mansfield' Leo H. Nlunsond Edgar R. Wagnere E. J. Vallario, DOE Project Manager June 1988 Prepared for the U.S. Department of Energy Assistant Secretary for Environment, Safety, and Health Under Contract DE-AC07-761D01570 a. Westinghouse Materials Company of Ohio, FMPC, Cinclnnati, OH. b. Rockwell International, Rocky Fiats Plant, Golden, CO. c. University of California, Lawrence Livermore National Laboratory, Livermore, CA. d. Batteiie Memorial Institute, Pacific Northwest Laboratory, Richland, WA. e. Martin Marietta Energy Systems Inc., Portsmouth Gaseous Dlffusion Plant, Piketon Idaho National Engineering Laboratory EG&G Idaho, Inc. Idaho Falls, Idaho 83415 ACKNOWLEDGMENTS The authors recognize the contrlbutlons of many persons who provlded technlcal revlew, comments and encouragement In the preparatlon of thls manual. We are partlcularly grateful for and wlsh to recognize the extra effort and dedlcat!on demonstrated by those llsted below. E. J. Vallarlo, Offlce of Nuclear Safety, U.S. Department of Energy (DOE) for his foreslght ln recognlzlng the need for the manual and hls continued support and gujdance. Technical Revlew Group for detalled and constructlve comments. M. S. Slngh, Lawrence Llvermore Natlonal Laboratory J. N. P. Lawrence, Los Alamos Natlonal Laboratory J. 8. Hunt, Martin Marrletta Energy Systems, Y-12 R. E. Yoder, Sclence Appllcatlon Internatlonal Corp; Speclflc members of the DOE Expert Group on Internal Doslmetry and other contrlbutors who provlded extra personal effort In tlmely and detalled technlcal support to assure accuracy and conslstency In developlng Section 6, "Internal Dose Control". R. M. Hall, Chalrman DOE Expert Group on Internal Doslmetry, Savannah River Plant J. S. Bogard, Oak Ridge Natlonal Laboratory W. 0. Faqrman, Argonne Natlonal Laboratory R. 8. Falk, Rocky Flats Plants 0. R. Flsher, Paclflc Northwest Laboratory T. R. La'Bone, Savannah River lant J. N. P. Lawrence, Los Alamos National Laboratory E. 1. Lessard, Brookhaven Nat onal Laboratory M. J. Sula, Paclflc Northwest Laboratory d. 0. Foulke, U.S. Department of Energy I. I' - .- A. N. Tschaeche, Westinghouse Idaho Nuclear Co. R. E. Wllson, Westlnghouse Idaho Nuclear Co. for his assistance In developing Section 8 on Nuclear Criticality Control. Specific members of the EG&G Idaho Technlcal Publications Department are recognized for extra effort In assuring a tlmely and quality product. Special thanks and recognltlon are due to: E. E. Bybee for assuming a major role In productlon of the manual through professional competency In technical edltlng and coordlnatlon of the support effort . B. D. Renberg for competency and extra effort In text processlng support . S. C. Hall for efficiency and quality graphic art support. ! i '5620 FOREWORD Historically from the health perspective, uranium has been-considered more of a heavy metals than a radiological hazard. The phrase "its only uranium" was heard frequently throughout the nuclear industry. This early perspective resulted primarily from the relatively low specific activity of uranium and the fact that while kidney damage of a chemical origin was observed in laboratory animal 5 administered uranium compounds, radiological toxicity at similar levels had not been demonstrated. However, the revisions to biokenetic models for the evaluation of radiation exposure as contained in t ICRP Publication 26 and 30 have resulted in a decrease in the annual limit of intake for uranium. This, coupled with recent chaqges in our understanding of the biological behavior and health significance of uranium along with technology advances for control 1 ing, monitoring, and evaluating potential exposures of workers make it apparent that greater attention can and must be placed on controlling uranium contamination in the workplace. The "Health Physics Manual of Good Practices for Uranium Facilities" should prove to be extremely useful in providing information on design and implementa- tion of radiation protection programs consistent with current standards and state-of-the-art technology. It is expected that this manual will serve as a guide in the evaluation of needed upgrade programs for older facilities as well as in the development of radiation protection programs for newer facilities. The working group responsible for the development of this document was comprised of teciirlical experts with extensive appl ierl health pqysics experience. It was peer reviewed by DOE and DOE contractor personnel as well as experts in other sectors of the nuclear industry. We want to express our appreciation to both the working groups and the individuals who reviewed the document. This dedicated effort and the application of this Guide will indeed result in a significant contribution to the radiation protection of workers in the uranium industry. @< I Edward Acting Director Radiological Controls Division Office of Nuclear Safety f iii 1620 ACRONYMS ACGIH American Conference of Governmental Industrlal Hyglenlsts ALARA as low as reasonably achlevable AL I annual llmlt on Intake AMAD actlvlty medlan aerodynamlc dlameter ANSI American National Standards Institute AVL IS atomlc vapor 'laser Isotope separatlon AWWA American Water Works Assoclatlon BZ breathlng zone sampler C AH contlnuous alr monltor CEDE commltted effectlve dose equlvalent CFR Code of Federal Regulatlons CPVC chlorine polyvlnyl chloride DAC derived alr concentratlon DBA deslgn-basls accldent DBE deslgn-basis earthquake DBF deslgn-basls flre DE dose equlvalent DOE U.S. Department of Energy DO0 Department of Defense DOT Department of Transportatlon DTPA dlethylenetrlamlnepenta-acetic acld EA environmental assessment EDTA ethylene dlamlne tetracetlc acld EIS environmental Impact statement ECS Emergency Control Station E PA U.S. Envfronmental Protectlon Agency E PZ emergency plannlng zone ERDA Energy, Research, and Development Adminlstratlon FMPC feed materlal productlon center GAS general area sampler GDP Gaseous Olffuslon Plant GI gastro intestinal IV GM Geiger-Mueller GSD geometric standard devlatlon HEPA high-efficiency partlculate air HPGE hyperpure germanium HQ headquarters IAEA International Atomic Energy Agency ICRP International Comlssion on Radio1 ica-l P tec tlon IEC International Electrotechnlcal Commlsslon LLNL Lawrence Livermore Natlonal Laboratory MPC maximum permissible concentratlon MSHA Mining Safety Health Admlnistratlon NAD nuclear accident dosimeter/dosimetry NAWAS National Warning System NCRP National Council on Radiatlon Protection and Measurements NCS nuclear critlcality safety NEPA National Environmental Policy Act NFPA National Fire Protection Association N I OSH National Institute of Occupational Safety and Health NOAA National Oceanic and Atmospheric Administration NRC U.S. Nuclear Regulatory Commlsslon NRRPT National Registry of Radiation Protectlon Technologlsts NUREG Nuclear Regulatory Report OBE operating basis earthquake OSHA Occupational Safety and Health Administration t PAS personal air sampler PC protective clothing PMF probable maximum flood PSAR preliminary safety analysis report PRR protective response recomendatlon QA quality assurance RCG radioactivity concentratlon guide RCRA Resource Conservatlon and Recovery Act RU recycled uranlum SOD system design description I STEL short term exposure ltmlt ! 1 I TE tlssue equlvalent TL thermoluminescent TL D thermolumlnescent doslmeter TLU threshold llmlt values UNH uranyl nitrate USGS United States Geologlc Service VHE very highly enrlched WBC whole body count I Vl . P.. 7620 CONTENTS ACKNOULEDGMENTS ....................................................... I FOREWORD .............................................................. 111 ACRONYMS .............................................................. Iv SECTION 1 INTRODUCTION ............................................. 1-1 SECTION 2 PROPERTIES AND RELATIVE HAZARDS .......................... 2-1 SECTION 3 DOE FACILITIES, PROCESSES AND EXPERIENCES ................ 3-1 SECTION 4 RADIATION PROTECTION MANAGEMENT .......................... 4-1 SECTION 5 CONTAMINATION CONTROL .................................... 5-1 SECTION 6 INTERNAL DOSE CONTROL .................................... 6-1 SECTION 7 EXTERNAL DOSE CONTROL .................................... 7-1 SECTION 8 NUCLEAR CRITICALITY CONTROL .............................. 8-1 SECTION 9 WASTE MANAGEMENT ......................................... 9-1 SECTION 10 EMERGENCY PREPAREDNESS ................................... 10-1 SECTION 11 DECONTAMINATION AND DECOMMISSIONING ...................... 11-1 SECTION 12 SITING OF URANIUM FACILITIES ............................. 12-1 SECTION 13 FACILITY DESIGN .......................................... 13-1 Vii SECTION 1 INTROOUCTION CONTENTS 1. INTROOUCTION ....................................................