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1997 Enforcement Sanctions for Deliberate Violations of NRC Employee Protection Requirements In98004

1999 Enforcement Sanctions for Deliberate Violations of NRC Employee Protection Requirements In00004

2008 Emergency Response Guidebook

A Compendium Of Dose Estimates For Many Radiopharmaceuticals NUREG 6345

A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys (pre-published draft) NUREG 1505

A Radon Guide for Tenants

Acceptable Approach for Controlling and Calibrating Radiation Detection Instruments TPP99-04

Acceptable Approach for Controlling and Determining Individual Internal Exposures to Radioactive Material TPP00-1

Acceptable Approach for Controlling and Labeling Radioactive Material DOE TPP 2000 05

Acceptable Approach for Controlling Individual Doses Inside the Controlled Area, but Outside of Radiological Areas and Radioactive Material Areas TPP99-03

Acceptable Approach for Developing Air Concentration Values for Controlling Exposures to Tritiated Particulate Aerosols and Organically-Bound Tritium TPP99-02

Acceptable Approach for Developing Air Concentration Values for Controlling Exposures to Special Tritium Compounds

Acceptable Approaches to Developing Sealed Radioactive Sources and Posting and Labeling Requirements for Special Tritium Compounds (STCs)

Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program (Draft DG-8009, Proposed Revision 1, published 12/1991) RegGuide 8.9

Acceptable Programs for Respiratory Protection (Draft DG-8022, Proposed Revision 1, issued 7/1998) RegGuide 8.15

Acceptance for Referencing, RADMAN Topical Report (WMG-102, as Revised) HPPOS288

Access authorization for licensee personnel 10 CFR Part 25

Access Control at Nuclear Facilities In86027

Access Control to High Radiation Areas - Turkey Point HPPOS014

Access Control to High Radiation Areas at Nuclear Power Plants HPPOS234

Access Controls for Spent Fuel Storage Pools HPPOS245

Accidental Disposal of Radioactive Materials In90014

Accidental Radiation Overexposures to Personnel Due to Industrial Radiography Accessory Equipment Malfunctions In91023

Accidental Radioactive Contamination of Human Food and Animal Feeds:Recommendations for State and Local Agencies

Accuracy of Bioassay and Environmental Sampling Results In94081

Accuracy of Information Provided to NRC During the Licensing Process In94047

Administrative claims under Federal Tort Claims Act 10 CFR Part 14

Advance Notice of Directive for DOE M 461.A-X, Packaging and Transfer of Materials of National Security Interest Manual

Advisory committees 10 CFR Part 7

AHCPR's Sample Letters for Communicating Mammography Results to Women

Air Intrusion into BWR Primary Systems HPPOS107

Air Sampling in the Workplace (Draft OH 905-4 published 10/1979) (Draft DG-8003, Proposed Revision 1, published 9/1991) RegGuide 8.25

Air Sampling in the Workplace NUREG 1400

Airborne Thorium From Welding HPPOS255

Aircraft at "Particular Location" 10 CFR 31.5(c)(9) HPPOS137

Airflow Measurement and Control for Supplied-Air Respirators HPPOS118

ALARA Levels for Effluents from Materials Facilities (Draft DG-8013 published 10/1992) (Draft DG-8016, Proposed Revision 1, published 12/1995) RegGuide 8.37

ALARA Training for Technical Support Personnel DOE-HDBK-1110-97

Allowable Contamination Limit for Thorium-natural HPPOS149

Alternate Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites In89013

Alternative Method of Disposal for Contaminated Plastic Test Tubes HPPOS300

Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors RegGuide 1.183

Alternative Standards (11/1/99)

American Board of Radiology "Certifications" HPPOS287

An Approach For Plant-Specific Risk-informed Decisionmaking Inservice Inspection of Piping (Draft DG-1063 issued 10/97) RegGuide 1.178

An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance (Draft DG-1064 issued 6/97) RegGuide 1.176

An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing (Draft DG-1062 issued 6/97) RegGuide 1.175

An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications (Draft DG-1065 issued 6/97) RegGuide 1.177

An Approach for using Probabilistic Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis (Draft DG-1061 issued 6/97) RegGuide 1.174

An Overview of Mixed Waste

Angell Memorial Animal Hospital, Boston, MA; Release to Unrestricted Area of Animals Containing Iodine-131HPPOS286

Annual fees for reactor operating licenses, and fuel cycle licenses and materials licenses, including holders of certificates of compliance, registrations, and quality assurance program approvals and government agencies licensed by NRC. 10 CFR Part 171

ANO - Units 1 & 2 - Radiochemistry Personnel Qualifications HPPOS096

Antitrust and Financial Review RegGuide, Division 9

Apparent Falsification of State of Connecticut Weight Certificates In90036

Apparent Unauthorized Use of Byproduct Material, Resurrection Hospital, Chicago, Illinois 3.8 License Conditions HPPOS156

Applicability of 10 CFR 20.203(c) to Plants With Standard Technical Specifications HPPOS180

Applicability of 10 CFR 20.303(d) to Disposable Diapers Contaminated with Tc-99m. HPPOS034

Applicability of 10 CFR 21 to Consulting Firms Providing Training In85101

Applicability of 10 CFR 50 Appendix B to Chemicals and Reagents HPPOS213

Applicability of 10 CFR Part 21 to Nonlicensees In87033

Applicability of Access Controls for Spent Fuel HPPOS016

Applicability of Federal Regulations to NRC Licensees Transfer of Radiative Materials to DOE for Shipment HPPOS208

Applicability of Generic Letter 82-12 to Radiation Protection Staff HPPOS173

Applicability of Notification Requirement to Non-Power Reactors,10 CFR 50.72 HPPOS174

Applicability of Regulatory Position 1.3 of Regulatory Guide 8.32 to Nuclear Reactor Facilities HPPOS233

Applicability of State Regulations on NRC Inspectors HPPOS054

Applicability of the General Rule per Title 10 Code of Federal Regulations art 835 (10 CFR 835) Section 835.3 for Protective Forces Personnel TPP 99-0-1

Application of 10 CFR 40.13(c)(1)(vi) HPPOS029

Application of the Financial Assurance Requirement in 10 CFR 30.35, 40.36, and 70.25 to Waste Brokers Located in Agreement States HPPOS309

Applications of Bioassay for I-125 and I-131 RegGuide 8.20

Applications for Type A Licenses of Broad Scope (Errata published 7/1984) (Draft FC 408-4, Proposed Revision 2, published 2/1985) (Draft DG-0005, Second Proposed Revision 2, published 10/1994) RegGuide 10.5

Appointment of Radiation Safety Officers and Authorized Users Under 10 CFR Part 35 In02028

Approval of Respiratory Protective Devices 42 CFR 84

Assessing And Managing Risk Before Maintenance Activities at Nuclear Power Plants RegGuide DG-1082

Assessment of Intakes of Radioactive Material by Workers In82018

Atomic Spectroscopy: A Compendium of Basic Ideas, Notation, Data, and Formulas

Attempted Extortion - Low Enriched Uranium In79002

Attention to Liquid Dilution Volumes in Semiannual Radioactive Effluent Release Reports HPPOS099

Audible-Alarm Dosimeters (Draft OH 804-4 published 8/1979)

Authority of Agreement States Concerning Their Licensees Working at DOE Facilities HPPOS197

Authority to Penalize Willful False Exposure of Personnel Monitoring Device and Other Hoaxes HPPOS176

Authority to Receive Returned Waste Originally Generated Under an NRC License, Westinghouse Electric Corporation HPPOS274

Authorization of Employee Eating and Drinking Areas in Labs at Veterans Administration Medical Center, Martinez, California HPPOS318

Authorizations Under 10 CFR 40.22, General License HPPOS200

Authorized Contents of Spent Fuel Casks In99029

Authorized Users' Supervision of Medical Programs HPPOS145

Automatic Dental Film Processors (October 2000)

Auxiliary Building Ventilation System at Zion Nuclear Power Station HPPOS323

Availability of FDA-Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine In88015

Averaging of Radiation Levels Over the Detector Probe Area HPPOS013

Avoidance of Mischaracterization of Effect of Certain Communications to Licensees HPPOS057

Background as a Residual Radioactivity Criterion for Decommissioning (August 1994)

Beam Quality: Total Filtration and Half-Value Layer (October 2001)

Blind Spiking of Personnel Dosimeters and the Inspection Program HPPOS224

Blocking, Bracing, and Securing of Radioactive Materials Packages in Transportation In87031

BNL Wallet Cards

Boeing Company Request Concerning Depleted Uranium Counterweights HPPOS206

BP International Limited Request for an Exemption from 10 CFR 20.202(c) HPPOS268

Brachytherapy Incidents Involving Treatment Planning Errors In95039

Brachytherapy Source Management In91002

Breakdowns in Contamination Control Programs In80022

Broad-Scope Licensees' Responsibilities for Reviewing and Approving Unregistered Sealed Sources and Devices In99024

Building a New Home: Have You Considered Radon?

Building Radon Out: A Step-by-Step Guide on How to Build Radon-Resistant Homes (April 2001)

Buildup of Enriched Uranium in Effluent Treatment Tanks In82021

Buildup of Enriched Uranium in Ventilation Ducts and Associated Effluent Treatment System In85031

Burial of Patients With Permanent Implants HPPOS030

Buying a New Home: How to Protect Your Family From Radon

Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I RegGuide 1.109

Calculation of Surface Activity for Contaminated Equipment and Material In97055

Calibration Problems - Eberline Instrument Model 6112B Analog Teletectors In84075

Cancer Risk Coefficients for Environmental Exposure to Radionuclides, FGR 13

Capintec Instruments, Inc., Request for Definition of Sealed Source HPPOS311

Categorizing and Transporting Low Specific Activity Materials and Surface Contaminated Objects NUREG 1608

Certification of gaseous diffusion plants 10 CFR Part 76

Characteristic x-ray energies

Chart of the Nuclides

Chemical Reactions with Radioactive Waste Solidification Agents In88008

Chemical/Biological/Radiological Incident Handbook

Chemistry and Radiation Protection Technician Training and Qualifications HPPOS067

Chemistry Technician Training and Qualifications HPPOS062

Citizens Guide to NRC, Rev. 3 NUREG 0010

Citizen's Guide to Radon

Clarification of Regulatory Requirements for Packaging of Uranium Hexafloride (UF6) for Transportation In90027

Clarification of 10 CFR 35.50(b)(1) HPPOS280

Clarification of 10 CFR 40.22, Small Quantities of Source Material In93014

Clarification of 10 CFR 50.72 with respect to Maine Yankee HPPOS101

Clarification of Certain Requirements for Exclusive-Use Shipments HPPOS085

Clarification of Certain Requirements for Exclusive-Use Shipments of Radioactive Materials In80032

Clarification of Conditions For Waste Shipments Subject To Hydrogen Gas Generation In84072

Clarification of Emergency Plan Exercise Requirements In82044

Clarification of Generic Letter 81-38, "Storage of Low Level Radioactive Wastes at Power Reactor Sites" HPPOS239

Clarification of Nuclear Power Plant Staff Working Hours HPPOS253

Clarification of Regulatory Guide 1.21, Section C.10, "Sensitivity" HPPOS122

Clarification of Regulatory Guide 1.8 on Qualification of Radiation Protection HPPOS020

Clarification of Requirements for Exclusive-Use Shipments of Radioactive Materials HPPOS084

Clarification of Requirements for Fabrication and Export of Certain Previously Approved Type B Packages In86086

Clarification of Scope of Quality Assurance (QA) Programs for Transport Packages Pursuant to 10 10 CFR 50, Appendix B HPPOS060

Clarification of Scope of Quality Assurance Programs for Transport Packages Pursuant to 10 CFR 50, Appendix B In84050

Clarification of Several Aspects of Removable Radioactive Surface Contamination Limits for Transport Packages HPPOS064

Clarification of Several Aspects of Removable Radioactive Surface Contamination Limits for Transport Packages In85046

Clarification of Several Aspects Relating to Use of NRC-Certified Transport Packages In83010

Clarification of the 11 Criteria of NUREG-0737 on Postaccident Sampling System (PASS) Capability HPPOS011

Clarification of Transportation Requirements Applicable to Return of Spent Radiopharmacy Dosages From Users to Suppliers In89074

Clarification of Transportation Requirements Applicable to Return of Spent Radiopharmacy Dosages From Users to Suppliers In89074

Clarification on 10 CFR 19.11a, "Posting of Notices to Workers" HPPOS228

Classification of Transportation Emergencies In93007

Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety NUREG 6407

Commercial Nuclear Power Plants: Emergency Preparedness Planning

Commercial Storage at Power Plant Sites of Radwaste Not Generated by the Utility HPPOS092

Community Memorial Hospital, Toms River, NJ, Regarding Exemption from 10 CFR 35.75(b) HPPOS314

Comparison of Effective Dose Equivalent (ICRP 30), Effective Dose (ICRP 60), and Total Body Dose for 62 Radiopharmaceutical Procedures

Compendium of EPA-approved Analytical Methods for Measuring Radionuclides in Drinking Water

Compliance Guidance: Mammography Facility Survey and Medical Physicist Qualification Requirements Under MQSA (11/6/2000)

Compliance Guidance: Preparing for MQSA Inspections (5/5/99)

Compliance Guidance: The Mammography Quality Standards Act Final Regulations; Quality Assurance Documentation

Compliance Guidance: The Mammography Quality Standards Act Final Regulations Document #1 (3/19/99)

Compliance Guidance: The Mammography Quality Standards Act Final Regulations Document #2 (2/25/2000)

Compliance Guidance: The Mammography Quality Standards Act Final Regulations: Document #4 (5/23/2001 - date of Federal Register notice)

Compliance Guidance: The Mammography Quality Stands Act Final Regulations Motion of Tube-Image Receptor Assembly

Compliance Program for Field Compliance Testing of Cabinet X-ray Equipment (CP 7386.004); Final Guidance for Industry and FDA Staff (February 2001)

Compliance with 10 CFR Part 20 for Airborne Thorium In96018

Compliance With New Decommissioning Rule In90016

Compliance with the General License Provisions of 10 CFR Part 31 In87037

Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, as Amended In87015

Compressed Gas Cylinder Missile Hazards In91037

Computed Tomography Fluoroscopy (February 2001)

Concerning Protection Factor for Respirators, Footnote g of Appendix A to 10 CFR 20 HPPOS225

Concurrence on Release of Facility, Schering Plough Corporation, Release of a Facility for Unrestricted Use HPPOS277

Confidentiality of Exercise Scenarios In89046

Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1055 issued 8/1996) RegGuide 1.169

Conformance With DOE Laboratory Accreditation Program Requirements TPP95-07

Consideration of Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits HPPOS223

Consideration of NRC Independent Measurement Samples as "Research" Pursuant to 49 CFR 175.700(c) and 172.204(c)(4) HPPOS161

Consolidated Guidance About Materials Licenses: Vol. 1: Program-Specific Guidance About Portable Gauge Licenses NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 2: "Program-Specific Guidance About Industrial Radiography Licenses" NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 3: Applications for Sealed Source and Device Evaluation and Registration NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 4: Program-Specific Guidance About Fixed Gauge Licenses NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 5: "Program-Specific Guidance About Self-Shielded Irradiator Licenses" NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 6: Program-Specific Guidance About 10 CFR Part 36 Irradiator Licenses NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 7: Program-Specific Guidance About Academic, Research and Development, and Other Licenses of Limited Scope NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 9: "Program-Specific Guidance About Medical Use Licenses" NUREG 1556 October 2002

Consolidated Guidance About Materials Licenses: Vol. 10: Program-Specific Guidance About Master Materials Licenses NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 11: Program-Specific Guidance About Licenses of Broad Scope NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 12: "Program-Specific Guidance About Possession Licenses for Manufacturing and Distribution"

Consolidated Guidance About Materials Licenses: Vol. 13: "Program-Specific Guidance About Commercial Radiopharmacy Licenses

Consolidated Guidance About Materials Licenses: Vol. 14: Program-Specific Guidance About Well Logging, Tracer, and Field Flood Study Licenses NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 15: Program-Specific Guidance About About Changes of Control and About Bankruptcy Involving Byproduct, Source, or Special Nuclear Material Licenses NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 16: Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Licenses Authorizing Distribution to General Licensees NUREG 1556

Consolidated Guidance About Materials Licenses: Vol. 17: "Program-Specific Guidance About Licenses for Special Nuclear Material of Less Than Critical Mass" (Nov. 2000)

Consolidated Guidance About Materials Licenses: Vol. 18: "Program-Specific Guidance About Service Provider Licenses" (November 2000)

Consolidated Guidance About Materials Licenses: Vol. 19: Guidance For Agreement State Licensees About NRC Form 241 "Report of Proposed Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore Waters" and Guidance For NRC Licensees Proposing to Work in Agreement State Jurisdiction

Consolidated Guidance About Materials Licenses:Vol. 20: Guidance About Adminsing Procedures (December 2000)

Consolidated NMSS Decommissioning Guidance, NUREG 1757 V. 1, Rev. 2 (September 2006)

Consolidated NMSS Decommissioning Guidance, NUREG 1757 V. 2, Rev. 1 (September 2006)

Consolidated NMSS Decommissioning Guidance, NUREG 1757 V. 3 (2003)

Constants

Constraint on Releases of Airborne Radioactive Materials to the Environment for Licensees other than Power Reactors (Draft DG-8016 published 12/1995) RegGuide 4.20

Consumer's Guide to Radon Reduction

Contaminated Lead Products In97050

Contaminated Radiography Source Shipments In85007

Contaminated Soil at Big Rock Point HPPOS042

Contamination of Breathing Air Systems In85006

Contamination of Nonradioactive System and Resulting Possibility for Unmonitored, Uncontrolled Release to Environment In91040

Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to the Environment HPPOS079

Contamination of The Auburn Steel Company Property With Cobalt-60 In83016

Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e) RegGuide 1.181

Continental Airlines, On-the-Job Training of radiographers HPPOS276

Continuous Communications Following Emergency Notification In87058

Continuous Supervision of Irradiators In85001

Control And Surveillance of Portable Gauges During Field Operations In02030

Control of High Radiation Areas per Title 10, CFR, Part 835.502 TPP 97-01

Control of Hot Particle Contamination at Nuclear Power Plants In87039

Control of Radiation Levels in Unrestricted Areas Adjacent to Brachytherapy Patients In82033

Control of Radioactively Contaminated Material HPPOS071

Correction for Sample Conditions for Air and Gas Monitoring In82049

Corrections for Sample Conditions for Air and Gas Monitoring HPPOS088

Cracked Insertion Rods on Troxler Model 3400 Series Portable Moisture Density Guages In96052

Criminal History Record Information In98005

Criminal Prosecution of Licensee's Former President for Intentional Safety Violation In89002

Criminal Prosecution...Former Radiation Safety Officer Who...Directed an Unqualified Individual to Perform Radiography In86054

Criteria and procedures for determining eligibility for access to restricted data or national security information or an employment clearance 10 CFR Part 10

Criteria and procedures for determining eligibility for access to or control over special nuclear material 10 CFR Part 11

Criteria and procedures for emergency access to non-federal and regional low-level waste disposal facilities 10 CFR Part 62

Criteria for Digital Computers in Safety Systems of Nuclear Power Plants (Draft IC 127-5 published 3/1983) (Draft DG-1039, Proposed Revision 1, 1 01/1996 published 5/1995) RegGuide 1.152

Criteria for Establishing a Tritium Bioassay Program (Draft OP 713-4 published 6/1983) RegGuide 8.32

Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants ,Rev. 1, aka FEMA-REP-1 (1980) NUREG 0654

Addenda to NUREG 0654 Addenda - The citations contained in the Addenda replace the outdated citations referred to in Revision 1 to NUREG-0654/FEMA-REP-1. The page, section, and footnote, as appropriate, are given for each original citation. These addenda do not include any citation that is still valid.

Criteria for Protective Action Recommendations For General Emergencies In83028

Criteria for Safety Systems (Draft I C 609-5 published 12/1982) (Draft DG-1042, Proposed Revision 1, published 11/1995) RegGuide 1.153

Criteria for the certification and re-certification of the Waste Isolation Pilot Plant's compliance with the 40 CFR Part 191 disposal regulations

Criteria in NUREG Are Not Substitutes for Regulations HPPOS074

Criterion for Triggering a Review under 10 CFR 50.80 for Non-Owner Operator Service Companies RegGuide DG-1086

CT System Survey "More than just MSAD"

Cumulative Occupational Dose History NRC Form 4

Damping Values for Seismic Design of Nuclear Power Plants RegGuide 1.61

Darkroom Fog

Darkroom Safelights - One Easy Lesson

Debt collection procedures 10 CFR Part 15

Decay Data from BNL - NUDAT

Decision Methods for Dose Assessment to Comply With Radiological Criteria for License Termination, DRAFT NUREG 154

Decommissioning of Nuclear Power Reactors RegGuide 1.184

Decontamination Limits for Americium-241 HPPOS183

Deep Dose Equivalent Gamma Ray Constants (mSv/hr per MBq at 1 meter) Data from Unger and Truby ORNL RSIC-45/R1, 1982

Defacing Labels to Comply With 10 CFR 20.1094(b) In97003

Defective Emergency Use Respirator In83021

Defects Observed in Panasonic Model 801 and Model 802 Thermoluminescent Dosimeters In82042

Deficiencees in Licensee Submittals Regarding Terminology For Radiological Emergency Action Levels in Accordance With The New Part 20 In97034

Deficiencies in the Testing of Nuclear-Grade Activated Charcoal In87032

Deficiencies in Upgrade Programs for Plant Emergency Operating Procedure In86064s1

Deficiencies in Upgrade Programs for Plant Emergency Operating Procedure In86064s1

Definition of Unplanned Release HPPOS254

Definition of Waste Gas Storage Tank Radioactivity Limits HPPOS004

Definitions of Radiographer and Radiographer's Assistant, 10 CFR 50.72HPPOS187

Degradation of Boraflex Neutron Absorber in Spent Fuel Pool Storage Racks In95038

Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 In96014

Degree of Proof Necessary in a Regulatory Enforcement Action HPPOS112

Delayed Access to Safety-Related Areas and Equipment During Plant Emergencies In86055

Deliberate Circumventing of Station Health Physics Procedures In84059

Denial of Access to Current Low-Level Radioactive Waste Disposal Facilities In90075

Dental Device for the Normalization and Monitoring of Intraoral Film Processing Systems

Dental devices

Department of the Interior, Salt Lake City, UT; Apparent Request to Store Low-Level Waste for Decay for a Time in Excess of Five Years HPPOS278

Depleted Uranium – Technical Brief (2006)

Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels RegGuide 7.6

Design and Fabrication Code Case Acceptability--ASME Section III, Div 1 RegGuide 1.84

Design Limitations of Gaseous Effluent Monitoring Systems In86030

Determination of Radiation Exposure from Dosimeters HPPOS186

Determination of Teletherapy Timer Accuracy In80033

Developing a Technique Chart for a CT System Why is it Important?

Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1059 issued 8/1996) RegGuide 1.173

Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components RegGuide 1.122

Diagram of SI unit relationships with caption

Diagram of SI unit relationships without caption

Directory of State and Federal Agencies Involved with the Transportation of Radioactive Material (October 2001)

Discrete Event Simulation as a Risk Analysis Tool for Remote Afterloading Brachytherapy, Vol. 1 NUREG 5362

Disposal of Americium Well-Logging Sources In89034

Disposal of Byproduct Material Used for Certain In Vitro Clinical or Laboratory Testing. HPPOS169

Disposal of Exempt Quantities of Byproduct Material HPPOS190

Disposal of Exempt Quantities of Radioactive Material HPPOS043

Disposal of high-level radioactive wastes in geologic repositories 10 CFR Part 60

Disposal of Liquid Waste into Arctic Ocean HPPOS271

Disposal of Sludge from Onsite Sewage Treatment Facilities at Nuclear Power Stations In88022

Disposal of Solid Scintillation Media HPPOS295

Disposal Requirements for Specific and Exempt Licensed Smoke Detectors HPPOS150

Dissolved Noble Gases in Liquid Effluents and Compliance With Technical Specifications HPPOS212

Distribution of Products Irradiated in Research Reactors HPPOSO95

Distribution of Sources and Devices Without Authorization In97089

DOE Fundamentals Handbook Nuclear Physics And Reactor Theory Volume 1 Of 2 DOE-HDBK-1019/1-93

DOE Fundamentals Handbook Nuclear Physics And Reactor Theory Volume 2 Of 2 DOE-HDBK-1019/2-93

DOE Handbook Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities Volume II – Appendices DOE-HDBK-3010-94

DOE Handbook Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities Volume I - Analysis Of Experimental Data DOE-HDBK-3010-94

DOE Handbook Primer on Tritium Safe Handling Practices DOE-HDBK-1079-94

Doe Handbook Tritium Handling and Safe Storage DOE-HDBK-1129-99

DOE Shipping Activity

Doe Standard Radiological Control DOE-STD-1098-99

Domestic licensing of production and utilization facilities 10 CFR Part 50

Domestic licensing of source material 10 CFR Part 40

Domestic licensing of special nuclear material 10 CFR Part 70

Dose-Area Product (DAP) (October 2001)

Dose Assignment for Workers in Non-Uniform Radiation Fields In83059

Dose Calibrator Quality Control In89012

Dose Calibrator Quality Control In93010

Dose-Rate Instruments Underresponding to the True Radiation Fields In90044

DOT Reply to NRC Request for Clarification on Ex Post Facto Declarations by Shippers of Radioactive Materials HPPOS063

Early site permits; standard design certifications; and combined licenses for nuclear power plants 10 CFR Part 52

Effective Date for Radiographer Certification and Plans for Enforcement Discretion In99022

Effective Use of Radiation Safety Committees to Exercise Control Over Medical Use Program In90071

Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation In96041

Effects of RCRA LDR Regulations on Mixed Waste Management

Effluent Radiation Monitor Calibrations HPPOS040

Effluent Reporting Requirement Per 10 CFR 20.405(a), "Reports of Overexposures and Excessive Levels and Concentrations HPPOS052

Electrical Component Failure Due to Degradation of Polyvinyl Chloride Wire Insulation In94078

Electronic Calibration of Survey Instruments HPPOS279

Ellis Fischel State Cancer Hospital - Violation of 10 CFR 19.16(c) HPPOS123

Emergency Access to Low-Level Radioactive Waste Disposal Facilities In91065

Emergency Communication System Monthly Test In85044

 

Emergency Planning and Preparedness for Nuclear Power Reactors (Revision 1 to this guide entitled "Emergency Planning for Nuclear Power Plants" was withdrawn--see 45 FR 69610, 10/21/1980.) (Draft DG-1022, Proposed Revision 3, published 2/1992) RegGuide 1.101

Emergency Response Exercises In87054

Emergency Response Information Requirements for Radioactive Material Shipments In92062

Emergency Worker Doses In84040

Emergency-Use Respirator Material Defect Causes Production of Noxious Gases In83067

EML Procedures Manual, 28th Edition HASL 300

Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites In95028

Employee Protection from Employers for Revealing Safety Violations HPPOS141

Employee Training and Shipper Registration Requirements for Transporting Radioactive Materials In92072

Enforceability of NRR Letter Regarding "Individuals Qualified in Radiation Protection Procedures HPPOS021

Enforcement Actions Against Medical Licensees for Willfull Failure to Report Misadministrations In86085

Enforcement Discretion by NRC Concerning Violations that are Self-Identifying HPPOS244

Enforcement Guidance Concerning "Substantial Potential" for Overexposure or Release HPPOS232

Enforcement Guidance for Container Labels, 10 CFR 20.203(f) HPPOS027

Enforcement Manual Rev. 2 NUREG 0195

Enforcement of License Conditions in Material Licenses 12.7 License Conditions HPPOS059

Enforcement of Regulatory Guides 12.7 Regulatory Guides HPPOS113

Enforcement of Safety Requirements for Radiographers In91049

Enforcement Pertaining to Unauthorized Users and Unauthorized HPPOS026

Enforcement Policy For Hot Particle Exposure - Answers to Three Questions HPPOS246

Engineering Drawings for 10 CFR 71 Package Approvals NUREG 5502

Ensuring a Capability to Evacuate Individuals, Including Members of the Public, from the Owner-Controlled Area In02014

Entry Into High Radiation Areas From Areas Which Are Not Under Direct Surveillance In83081

Environment, Safety and Health Reporting DOE Order 231.1

Environment, Safety And Health Reporting Manual M 231.1-1

Environmental and Siting RegGuide, Division 4

Environmental Assessment of Ionization Chamber Smoke Detectors Containing Americium-241

Environmental Investigations Standard Operating Procedures and Quality Assurance Manual

Environmental protection regulations for domestic licensing and related regulatory functions 10 CFR Part 51

Environmental Protection, Safety, And Health Protection Information Reporting Requirements DOE Order 5484.1

Environmental Protection, Safety, And Health Protection Standards DOE Order 5480.4

Environmental radiation protection standards for management and disposal of spent nuclear fuel, high-level and transuranic radioactive wastes

Environmental radiation protection standards for nuclear power operations

Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance DOE/EH-0173T

Environmental Samples Transportation Emergency Preparedness Drill: Checklist

Environmental Samples Transportation Emergency Preparedness Drill: Covers

Environmental Samples Transportation Emergency Preparedness Drill: Environmental Samples Drill

EPA administered permit programs: The Hazardous Waste Permit Program

EPA Assessment of Risks from Radon in Homes (June 2003)

EPA Hazmat Team Planning Guidance EPA 540/G-90/003

EPA Inspections for Compliance with NPDES Permits Issued to NRC Licensees HPPOS115

Equipment Failures at Irradiator Facilitie In94089

Errors in Dose Assessment Computer Codes and Reporting Requirements Under 10 CFR 21 HPPOS041

Errors in Dose Assessment Computer Codes and Reporting Requirements Under 10 CFR PART 21 In85052

Errors in the Use of Radioactive Iodine-131 In90059

Establishing Quality Assurance Programs for the Manufacture and Distribution of Sealed Sources and Devices Containing Byproduct Material (Draft DG-6002 published 5/1994) RegGuide 6.9

Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material (Combined Draft TP 019-4, published 6/1981, and Draft TP 020-4, published 3/1981 RegGuide 7.10

Estimating Radiogenic Cancer Risks EPA 402-R-93-076

Evaluating Occupational Dose for Individuals Exposed to NRC-licensed Material and Medical X-rays -NRC Regulatory Issue Summary 2002-06:

Evaluation of Comments on NRC Information Notice for Ophthalmic Applicators HPPOS273

Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters In86041

Event Notification In85078

Event Reporting Guidelines: 10 CFR 50.72 and 50.73 NUREG 1022

Ex Parte Communication HPPOS126

Exceptions for EcoTek, Inc., as a Decommissioning Contractor HPPOS281

Excessive Radiation Exposures to the Fingers...During Cleaning and Wipe Testing of...Sealed Sources at a...Mfg. Facility In81018

Excessive Skin Exposures Due to Contamination With Hot Particle In86023

Exemption of Thorium-Containing Scrap Under 10 CFR 40.13(c)(4) HPPOS133

Exemptions and continued regulatory authority in Agreement States and in offshore waters under section 274 10 CFR Part 150

Exemptions from 10 CFR 35.400 for Uses Not Currently Authorized for Iridium-192 Seeds Encased in Nylon Ribbon and Palladium-103 Seeds as Brachytherapy" HPPOS260

Exercise Evaluation Forms Document

Exercise Frequency In84005

Explosive Detectors for Use at Airports HPPOS196

Export and import of nuclear equipment and material 10 CFR Part 110

Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees In90009

Extended Storage of Sealed Sources In93050

External Exposure to Radionuclides in Air, Water, and Soil FGR 12

External Regulation of Department of Energy Nuclear Facilities: A Pilot Program NUREG 1708

Facility Management Responsibilities for Purchased or Contracted Services for Radiation Therapy Programs In94074

Failure of Air-Purifying Respirator Filters To Meet Efficiency Requirement In84060

Failure of Criticality Safety Control to Prevent Uranium Dioxide (UO2) Powder Accumulation In00002

Failure of Double Contingency Based on Administrative Controls Involving Laboratory Sampling and Spectroscopic Analysis of Wet Uranium Waste In99030

Failure of Intrauterine Tandem of Fletcher Suit Applicator Brachytherapy Devices During Patient Treatment In88052

Failure of Licensed Senior Operators to Classify Emergency Events Properly In89072

Failure to Follow Procedures when Working in High Radiation Areas In86044

Failure to Implement ... Biennial Medical Examinations & Notification ... Changes in Licened Operator Medical Conditions In94014

Failure to Provide Special Lenses For Operators Using Respirator or Self-Contained Breathing Apparatus During Emergency Operations In97066

Failures of High-Dose-Rate Remote Afterloading (HDR) Device Source Guide Tubes, Catheters, and Applicators In97065

False Alarms of Alarm Ratemeters Because of Radiofrequency Interference In91060

Farley 1 & 2 - 10 CFR Part 20 Exemption Request, MSA GMR-I Canister (Part No. 466220) Radioiodine Protection Factor HPPOS037

Fatality at Argentine Critical Facility In83066

Fatality at Argentine Critical Facility In83066s1

FDA Policy Guidance Help System - very powerful interactive document and information retrieval system

Federal Bureau of Investigation's (FBI) Awareness of National Security Issues and Response (ANSIR) Program In98017

Federal Environmental Monitoring Handbook

Federal Guidance Report 11; Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion

Federal Guidance Report 12; External Exposure to Radionuclides in Air Water, and Soil

Federal Guidance Report 13; Cancer Risk Coefficients for Environmental Exposure to Radionuclides

Federal Radiological Emergency Response Plan (FRERP)-Operational Plan

Fee for Services in Support, Review and Approval of State and Local Government or Licensee Radiological Emergency Plans and Preparedness

Fee for Services to Support Fema's Offsite Radiological Emergency Preparedness Program

Fees for facilities, materials, import and export licenses, and other regulatory services under the Atomic Energy Act of 1954, as amended 10 CFR Part 170

Financial protection requirements and indemnity agreements 10 CFR Part 140

Fire Protection Program for Nuclear Power Plants during Decommissioning and Permanent Shutdown RegGuide DG-1069

Fire Protection Program for Nuclear Power Plants during Decommissioning and Permanent Shutdown RegGuide DG-1069

Fitness For Duty HPPOS216

Fitness for duty programs 10 CFR Part 26

Footnote g of Appendix A to 10 CFR 20 Concerning Protection Factor for Respirators HPPOS225

Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels (Draft DG-1027 published 10/1994) RegGuide 1.162

Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m) (Draft MS 144-4 published 6/1983) (Draft DG-7001 published 7/1989) RegGuide 7.11

Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Wall Thickness Greater than 4 Inches (0.1 m) But Not Exceeding 12 Inches (0.3 m) (Draft MS 501-4 published 6/1986)(Draft DG-7002 published 7/1989) RegGuide 7.12

Frequently Asked Questions (regarding Mixed Waste)

Fuels and Materials Facilities RegGuide, Division 3

Further Guidance on Labeling HPPOS028

Gamma-ray Catalog for HPGe Detectors (Heath) Large file, will take several minutes to open.

Gamma-ray Catalog for NaI Detectors (Heath) Excellent source of basic information about gamma spectroscopy. Large file, will take several minutes to open.

Gaps in Neutron-Absorbing Material in High- Density Spent Fuel Storage Racks In87043

Gaseous Effluent Releases of Radioactive Iodine-125 and Iodine-131 in Excess of Nuclear Regulatory Commission Limits In83048

Gasket Defects HPPOS100

General domestic licenses for byproduct material 10 CFR Part 31

General Employee Radiological Training DOE-HDBK-1131-98

General Environmental Protection Program DOE Order 5400.1

General Reg Guide, Division 10

General Site Suitability Criteria for Nuclear Power Stations (DG-4003, Proposed Revision 2, published 11/1992) (DG-4004, Second Proposed Revision 2, published 2/1995) RegGuide 4.7

Generic Guidance on Preplanned Alternative Method for High Range Noble Gas Monitoring HPPOS039

Grids

Ground Water Sampling: A Workshop Summary EPA/600/R-94/205

Guidance - Use of NRC Form 4 - Listing of Exposure Periods HPPOS050

Guidance Concerning 10 CFR 20.103 and Use of Pressure Demand SCBA's HPPOS094

Guidance for Nuclear Criticality Safety Engineer Training and Qualification DOE-STD-1135-99

Guidance For Planning, Conducting and Evaluating Transportation Emergency Preparedness Tabletops, Drills and Exercises

Guidance For Planning, Conducting and Evaluating Transportation Emergency Preparedness Tabletops, Drills and Exercises

Guidance for Posting Radiation Areas HPPOS066

Guidance For Posting Radiation Areas In84082

Guidance for Request And Issuance Of Interim Notice Letters For Mammography Facilities Under The Mammography Quality Standards Act, 42 U.S.C. § 263(b) (Updated 5/27/99)

Guidance for Review of Requests for Reconsideration of Adverse Decisions on Accreditation of Mammography Facilities Under the Mammography Quality Standards Act, 42 U.S.C. § 263(b) (3/26/98)

Guidance for Submission of Requests for Reconsideration of Adverse Decisions on Accreditation of Mammography Facilities Under the Mammography Quality Standards Act, 42 U.S.C §263(b) (3/26/98)

Guidance for the Control of Radiation Hazards in Uranium Mining FGR 8

Guidance on Environmental Data Verification and Validation (G-8)EPA/240/R-02/004, (November 2002)

Guidance on Exemption/Modification Per 10 CFR 34.20 to Industrial Radiography Equipment (Source Guide Tube) HPPOS293

Guidance on Radioactive Materials in Sewage Sludge and Ash at Publicly Owned Treatment Works (Revised draft, June 2000)

Guidance on Reporting Doses to Members of the Public from Normal Operations. HPPOS140

Guidance on Setting Action Levels for Exemption for Requirement to Decontaminate Therapy Room for Unrestricted Use HPPOS321

Guidance on Test conditions for Activated Charcoal Using Methyl Iodide HPPOS069

Guidance on the Applicability of 10 CFR 70.19 to Persons Holding a Specific License HPPOS248

Guidance on the Revision of Internal Radiation Dose Estimates in Response to Updated Internal Dosimetry Methodologies

Guidance - Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies FDA (December 2001)

Guidance Regarding Physicians' Determination of Physical Qualification of Respiratory Equipment Users HPPOS061

Guidance to hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program In94023

Guidance to Users of Nycomed Amersham and North American Scientific, Inc. I-125 Interstitial Sources: Dosimetry and Calibration Changes

Guidance to Users on the Implementation of a New Single-Source Dose-Calculation Formalism and Revised Air-Kerma Strength Standard for Iodine-125 Sealed Sources In99002

Guidance: The Mammography Quality Standards Act Final Regulations - Preparing for MQSA Inspections

Guide for the Preparation of Applications for Licenses for Laboratory and Industrial Use of Small Quantities of Byproduct Material (Errata published 7/1984) RegGuide 10.7

Guide for the Preparation of Applications for Medical Use Programs (Draft FC 415-4, Proposed Revision 2, published 8/1985) (Draft DG-0002, Proposed Appendix X to Regulatory Guide 10.8, published 12/1991) (Appendix X published June 1992) (DG-0009, Proposed Supplement, published 3/1997) RegGuide 10.8

Guide for the Use of the International System of Units (SI) Special Publication 811

Guide Of Good Practices For Occupational Radiological Protection In Plutonium Facilities DOE Manuals of Good Practice DOE-STD-1128-98

Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities DOE-STD-1136-2000 (Aug. 2000)

Guide on "How Hard You Have to Look as Part of Radioactive Contamination Control Program HPPOS072

Guideline to Good Practices for Control and Calibration of Measuring and Test Equipment (M&Te) at Doe Nuclear Facilities DOE-STD-1054-93

Guideline to Good Practices for Control and Calibration of Measuring and Test Equipment (M&Te) at Doe Nuclear Facilities DOE-STD- 1054-93

Guidelines For Breastfeeding Mothers In Nuclear Medicine

Guidelines for Decontamination of Facilities and Equipment (July 1982 Revision) HPPOS044

Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems RegGuide DG-1029

Guidelines for Inservice Testing at Nuclear Power Plants NUREG 1482

Half-lives measured at NIST

Handbook of Selected Organ Doses for Projections Common in Pediatric Radiology FDA 79-8079

Handbook of Glandular Tissue Doses in Mammography FDA 85-8239

Handbook of Selected Tissue Doses for Projections Common in Diagnostic Radiology FDA 89-8031

Handbook of Selected Tissue Doses for the Upper Gastrointestinal Fluoroscopic Examination FDA 92-8282

Handbook of Selected Tissue Doses for Fluoroscopic and Cineangiographic Examination of the Coronary Arteries FDA 95 - 8289 and 95 - 8288

HASL 300

Hazardous waste management system: General

Health and environmental protection standards for uranium and thorium mill tailings

Health Concerns Related to Radiation Exposure of the Female Nuclear Medicine Patient

Health Physics Manual of Good Practices for Tritium Facilities

Health Physics Position on Posting of High Radiation Areas HPPOS242

Health Physics Position on Task Qualification of HP Technicians HPPOS238

Health Physics Position on the Controlling of Beam Ports, Thermal Columns, and Flux Traps as High Radiation Areas HPPOS235

Heritage Minerals, Inc., Possession and Transfer of Monazite-Rich Product HPPOS301

High-Efficiency Particulate Air Filter Exceeds Mass Limit Before Reaching Expected Differential Pressure In00003

High Radiation Hazards from Irradiated Incore Detectors and Cables In88063

High Radiation Hazards From Irradiated Incore Detectors and Cables In88063s1

High Radiation Hazards From Irradiated Incore Detectors and Cables In88063s2

Highlights of Recent Transport Regulatory Revisions By DOT and NRC In84014

Highly Radioactive Particle Control Problems During Spent Fuel Pool Cleanout In02003

Home Buyer's and Seller's Guide to Radon.

Human Errors That Result in Inadvertent Transfers of Special Nuclear Material at Fuel Cycle Facilities In93077

Humboldt Bay Radiation Protection Procedures 1.7 Technical Specifications HPPOS129

Identification and Characterization of Seismic Sources and Determination Safe Shutdown Earthquake Ground Motion (Draft DG-1015 issued 11/1992, Draft DG-1032, issued 2/1995) RegGuide 1.165

Identification and listing of hazardous waste

Identified Problems in Gamma Stereotactic Radiosurgery In94039

Identifying Waste Generators in Shipments of Low-Level Waste to Land Disposal Facilitie In88016

IE Position - Unduly Restricted Access of Female NRC Inspectors to Radiation Areas HPPOS055

Immediate Notification Requirement for Operating Power Reactors HPPOS065

Impact of Revision of 10 CFR Part 51 on Materials Licensing Actions" HPPOS256

Implementation Date ... Revision ... EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents In92038

Implementation of a New Constraint on Radioactive Air Effluents In97004

Implementation of Human Use Research Protocols Involving U.S. Nuclear Regulatory Commission Regulated Materials In00019

Implementation of the Deliberate Misconduct Rule In92037

Implementation of the Equal Access to Justice Act in Agency Proceedings 10 CFR Part 12

Import of Cigarette Plates Containing Source Material HPPOS201

The Importance of Accurate Inventory Controls to Prevent the Unauthorized Possession of Radioactive Material

Importance of Proper Response to Self-Identified Violations by Licensees In90001

Improper Cleaning and Decontamination of Respiratory Protection Equipment In86046

Improper Handling of Ophthalmic Strontium-90 Beta Radiation Applicators In90058

Improper Maintenance of Radiation Monitoring Systems In86042

Inadequate Calibration of TLDs Utilized to Monitor Extremity Dose at Uranium Processing and Fabrication Facilities In91030

Inadequate Operational Checks of Alarm Ratemeters In98016

Inadequate Puncture Tests For Type B Packages Under 10 CFR 71.73(c)(3) In97047

Inadvertent Shipment Of a Radioactive Source In a Container Thought To Be Empty In90056

Inadvertent Transfer of Licensed Material to Uncontrolled Locations In88007

Incident Involving Teletherapy Unit (AECL Eldorado-78) In84077

Incident Reporting Requirements for Radiography Licensees In01003

Incident Reporting Requirements for Radiography Licensees In96004

Incidents Involving the Use of Radioactive Iodine-131 In99011

includes 1910.1096 Ionizing Radiation 29 CFR Part 1910.1000 – 1910.1450

includes 1910.134 Respiratory Protection 29 CFR Part 1919.0 - 1910.999

Incomplete Draining and Drying of Shipping Cask In90066

Increased Monitoring of...Patients with Implanted Coratomic, Inc. Model C-100 & C-101 Nuclear-Powered Cardiac Pacemakers In86059

Industrial Radiography Inspection and Enforcement In88066

Information for Licensee Regarding the Chernobyl Nuclear Plant Accident In86033

Information Likely to be Requested if an Emergency is Declared In98008

Information Needed for an Antitrust Review of Initial Operating License Applications for Nuclear Power Plants (Proposed Revision 1 to Regulatory Guide 9.3) RegGuide DG-9001

Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable (Draft OH 507-4, Proposed Revision 4, published 3/1979) (Draft OP 618-4, Second Proposed Revision 4, published 5/1982) RegGuide 8.8

Installation of Fixed Gauges HPPOS305

Instructing the Supervised Individual" HPPOS303

Instruction Concerning Prenatal Radiation Exposure (Draft OP 031-4 Proposed Revision 2, published 8/1981) (Draft DG-8014, Proposed Revision 3, published 10/1994) RegGuide 8.13

Instruction Concerning Risks from Occupational Radiation Exposure (Draft OH 902-4 published 5/1980) (Draft DG-8012, Proposed Revision 1, published 12/1994) RegGuide 8.29

Instructions for Recording and Reporting Occupational Radiation Exposure Data (Draft DG-8007, Proposed Revision 1, published 11/1991) RegGuide 8.7

Instrument Setpoints for Safety-Related Systems RegGuide 1.105

Intent of the QA Testing of Respirator HEPA Filters, as Discussed in NUREG-0041 HPPOS226

Interconnection of Contaminated Systems with Service Air Systems Used as the Source of Breathing Air In79008

Interim status standards for owners and operators of hazardous waste treatment, storage, and disposal facilities

Internal Dosimetry DOE-STD 1121-98

[The] International System of Units (SI) Special Publication 330

International Transportation of Radioactive Materials

Interpretation - RG 1.33, Meaning of "Procedure Implementation ...," HPPOS128

Interpretation of 10 CFR 20.201(b), "Survey Requirements" HPPOS138

Interpretation of 10 CFR 35.33(c) Regarding Diagnostic Misadministration Reporting Threshold Levels HPPOS270

Interpretation of 10 CFR Part 40 and Certain Decommissioning Issues Regarding Fixed Contamination HPPOS284

Interpretation of the 10 CFR 30.13 Exemption HPPOS275

Interpretation of the International System of Units for the United States (Federal Register Notice)

Interpretations 10 CFR Part 8

Interpretative Letter No. 76-02, "Radiography, Agreement State Licensed Materials Aboard U.S. Ships HPPOS119

Intervals Between Physical Examinations for Respirator Users HPPOS219

Intravascular Brachytherapy Misadministrations In02016

Investigation and Reporting of Misadministrations by the Radiation Safety Officer In93004

Ionizing Radiation 29 CFR Part 1910.1096

ISCORS Assesement of Radioactivity In Sewage Sludge: Radiological Survey Results and Analysis (October 2003)

Issuance of a Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents In91072

Issuance of New Licenses for Material Use Programs" HPPOS261

Issues Associated with Use of Strontium-90 and Other Beta Emitting Radiopharmaceuticals In94070

Issues in Several U.S. Air Force Submittals Dated February 15, 1990, March 26, 1990, and October 23, 1990 HPPOS283

Job-Specific Radiological Worker Training TPP 95-06

Joint NRC/EPA Sewage Sludge Radiological Survey: Survey Design & Test Site Results: ..\NRC/MISC/sludge/nrc_epa_.pdfMain Body of Document

Joint NRC/EPA Sewage Sludge Radiological Survey: Survey Design & Test Site Results: ..\NRC/MISC/sludge/nrc_epa_.pdfAppendix A

Joint NRC/EPA Sewage Sludge Radiological Survey: Survey Design & Test Site Results: ..\NRC/MISC/sludge/nrc_epa_.pdfAppendix B

Joint NRC/EPA Sewage Sludge Radiological Survey: Survey Design & Test Site Results

Jurisdiction at Reactor Facilities" HPPOS265

Jurisdiction of Mobile Radwaste Units Operating at Nuclear Power Plants HPPOS078

Jurisdiction Over Low Level Waste Management at Reactor Sites in Agreement States HPPOS097

Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water ReactorsRev. 2, NUREG 1122

Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors,Rev. 2 NUREG 1123

Knowledge, Skills, and Abilities for Key Radiation Protection Positions at DOE Facilities DOE-STD-1107-97

KR-85 Hazards From Decayed Fuel In90008

kVp Ranges for Various Routine Exams

Labeling Requirements for Transporting Multi-Hazard Radioactive Materials In91035

Land disposal restrictions

Lead Exposure from Dental Films Stored in Lead-Lined Table-top Containers - FDA Public Health Notification:

Lead Shielding Attached to Safety Related Systems Without 10 CFR 50.59 Evaluations HPPOS091

Lead Shielding Attached to Safety-Related Systems Without 10 CFR 50.59 Evaluations In83064

Leak Testing F Packaging Used in The Transport of Radioactive Material In97057

Leak Testing Iodine-125 Sealed Sources in Lixi, Inc. Imaging Devices and Bone Mineral Analyzers In86095

Leakage Tests on Packages for Shipment of Radioactive Materials RegGuide 7.4

Leaking and Dislodged Iodine-125 Implant Seeds In80035

Legal Interpretation of the Misadministration Reporting Requirements as Applied to the Incident at Tripler Army Medical Center HPPOS297

Lessons Learned from Maintenance Rule Baseline Inspections NUREG 1648

Letter Dated February 6, 1978 ... Regarding Redistribution of Backlighted Dials HPPOS136

License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning In90038s1

License Condition, "... Used by or Under the Supervision of HPPOS025

License Requirement for Facilities Repairing Contaminated Equipment HPPOS132

License Requirements Which Stipulate Specific Individuals HPPOS182

Licensee Control of Contracted Services Providing Training In85088

Licensee Response to Indications of Tampering, Vandalism, or Malicious Mischief In96071

Licensee Violations of NRC Regulations, Which Led to Medical Diagnostic Misadministrations In88053

Licensee's Request for an Exemption to 10 CFR 35.49(a) HPPOS308

Licensees' Responsibilities Regarding Reporting and Follow-Up Requirements for Nuclear-Powered Pacemakers In98012

Licensee's Responsibility for Shipment of Waste and Radioactive Materials HPPOS194

Licenses and radiation safety requirements for irradiators 10 CFR Part 36

Licenses and radiation safety requirements for well logging 10 CFR Part 39

Licenses for industrial radiography and radiation safety requirements for industrial radiographic operations 10 CFR Part 34

Licensing for Crushing of Uranium Ore per 10 CFR 40.4(k) 3 HPPOS184

Licensing of Depleted Uranium Shielding for Use in Possessing of Mo-99/Tc-99m Generator HPPOS191

Licensing of Dial Painting Activities by Jewelers and Watch Repairers HPPOS142

Licensing of Industrial Radiographers at NRC Licensed Operating Reactors and Reactor Construction Sites HPPOS207

Licensing of Low-Level Radioactive Waste Storage by Materials and Fuel Cycle HPPOS264

Licensing of Nuclear Materials for Use on the High Seas and in Antarctica HPPOS198

Licensing of Reactor Facilities Prior to Issuance of Operating License HPPOS120

Licensing requirements for land disposal of radioactive waste 10 CFR Part 61

Licensing requirements for the independent storage of spent nuclear fuel and high-level radioactive waste 10 CFR Part 72

Licensing Status of Titanium Bearing Ores and Waste Products From Titanium Dioxide Manufacturing HPPOS202

Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste In89027

Limiting Access Authorizations In86091

Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion FGR 11

Literature Review and Assessment of Plant and Animal Transfer Factors Used in Performance Assessment Modeling (September 2003)

Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material (Draft MS 527-4, Proposed Revision 1, published 7/1987) (Draft MS 804-4, Second Proposed Revision 1, published 9/1988) RegGuide 7.8

Locking of Radiography Exposure Devices In93005

Loose Phosphor in Panasonic 800 Series Badge Thermoluminescent Dosimeter (TLD) Elements In85042

Los Alamos Radiation Monitoring Handbook (2001)

Loss and Theft of Unsecured Licensed Material In89035

Lost Iridium-192 Source Resulting in the Death of Eight Persons in Morocco In85057

Lost or Stolen Gauges In88002

Lost or Stolen Radioactive Sources Involved in Transportation HPPOS153

Low Flow (Minimal Drawdown) Ground-Water Sampling Procedures (April 1996)

Low Specific Activity (LSA) Materials Transportation Emergency Preparedness Drill – no rad release: Checklist

Low Specific Activity (LSA) Materials Transportation Emergency Preparedness Drill – no rad release: Covers

Low Specific Activity (LSA) Materials Transportation Emergency Preparedness Drill – no rad release: LSA without RAD Release Document

Low Specific Activity (LSA) Materials Transportation Emergency Preparedness Drill: Checklist

Low Specific Activity (LSA) Materials Transportation Emergency Preparedness Drill: Covers

Low Specific Activity (LSA) Materials Transportation Emergency Preparedness Drill: LSA with RAD Release Document

Lower Limit of Detection (LLD) for Potentially Contaminated Oil HPPOS221

Lower Technical Specification Limit of Detection for Liquid Effluents HPPOS171

Low-Level Radioactive Waste Burial Criteria In80024

Low-Level Radioactive Waste Scaling Factors HPPOS081

Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 In86020

Low-Level Radioactive Waste Scaling Factors, HPPOS081

Maintaining Film Processing Quality in Low Volume Processors

Maintenance of Teletherepy Units In89060

Malfunction of a Dry-Storage, Panoramic, Gamma Exposure Irradiator In85036

Malfunction of Lockbox on Radiography Device In88018

Malfunction of Source Retraction Mechanism in Cobalt-60 Teletherapy Treatment Units In99027

Mammography

Mammography Equipment Evaluations under MQSA's Final Regulations (5/8/2001)

[The] Mammography Quality Standards Act Final Regulations Inspection Questions (11/8/99)

Management Attention to the Establishment and Maintenance of a Nuclear Criticality Safety Program In90063

Management of Wastes Contaminated With Radioactive Materials ("Red Bag" Waste and Ordinary Trash) In91003

Management of Wastes Contaminated with Radioactive Materials In99033

Management Weaknesses Resulting in Failure to Comply With Shipping Requirements for Special Nuclear Material In97042

Manual of Respiratory Protection Against Airborne Radioactive Material (January 2001)

Map of Equivalent Thorium-232 Concentrations for the Conterminous U.S

Map of Equivalent Uranium-238 Concentrations for the Conterminous U.S

Map of Estimated Potassium Concentrations for the Conterminous U.S

Map of Estimated Total Gamma Exposure for the Conterminous U.S.

Map of Radon Potential for the Conterminous U.S.

Marking, Handling, Control, Storage and Destruction of Safeguards Information In88049

Material Control and Accounting for Uranium Enrichment Facilities Authorized To Produce Special Nuclear Material of Low Strategic Significance (Draft DG-5002 published 2/1991) RegGuide 5.67

Material control and accounting of special nuclear material 10 CFR Part 74

Materials and Plant Protection RegGuide, Division 5

Materials Code Case Acceptability--ASME Section III, Div 1 RegGuide 1.85

Materials Licensees: Lack of Management Controls over Licensed Programs In88010

[The] Meaning of "... May Have Caused or Threatens to Cause ..." in 10 CFR 20.403 HPPOS236

Meaning of the Expression "Dose Equivalent Xe-133" in the Technical Specifications HPPOS102

Medical Evaluation of Licensed Personnel for Nuclear Power Plants (Draft OL 401-5, Third Proposed Revision 2, published 11/1984) (Draft DG-1068, Proposed Revision 3, published 2/1997) RegGuide 1.134

Medical Examination for Licensed Operators In91008

Medical Management of Radiological Casualties Handbook D. Jarrett (1999)

Medical Messages Index

Medical Misadministrations Caused by Failure to Properly Perform Tests on Dose Calibrators for Beta-and-Low Energy Photon-Emitting Radionuclides In02019

Medical Misadministrations Caused by Human Errors Involving Gamma Stereotactic Radiosurgery (Gamma Knife) In00022

Medical Surveillance for Respirator Users HPPOS117

Medical use of byproduct material 10 CFR Part 35

Medical use of Strontium-90 Eye Applicators: New Requirements for Calibration and Decay Correction In02017

Memorandum of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 FR 43950, October 31, 1988) In88100

Method for Estimating Effective Dose Equivalent from External Radiation Sources Using Two Dosimeters RIS 04-01

Methods and Tools for Estimation of the Exposure of Terrestrial Wildlife to Contaminants (October 1997)

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors RegGuide 1.111

Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions (pre-published draft) NUREG 1507

Misadministration at Hutzel Hospital, Detroit, MI HPPOS304

Misadministrations to Patients Undergoing Thyroid Scans In85061

Misapplication of Generic Emergency Operating Procedures (EOP) Guidelines In83030

Misuse of Flashing Lights for High Radiation Area Controls In88079

Mixed Nuclide Classification HPPOS289

Model Standards and Techniques for Control of Radon in New Residential Buildings

Molybdenum Breakthrough From Technetium-99m Generators In84085

Monitoring and Reporting External Exposures of Individuals Monitored at Different Sites in a Year DOE TPP 2000 2

Monitoring and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Fuel Processing and Fabrication Plants and Uranium Hexafluoride Production Plants (Draft CE 401-4, Proposed Revision 1, published 9/1984) (Errata published 8/1986) RegGuide 4.14

Monitoring at Nuclear Power Plants for Contamination by Radionuclides that Decay by Electron Capture HPPOS250

Monitoring Criteria and Methods To Calculate Occupational Radiation Doses (Draft DG-8010 published 2/1992) RegGuide 8.34

Monitoring of Airborne Radioactivity TPP -95-01

Monitoring of Radioactive Release Via Storm Drains HPPOS007

Monitoring the Effectiveness of Maintenance at Nuclear Power Plants (Draft DG-1020 published 11/1992) (Draft DG-1031, Proposed Revision 1, published 6/1994) (Draft DG-1051, Proposed Revision 2, published 8/1996) RegGuide 1.160

MPI Pharmacy Services, Inc., License Amendment Regarding Authorized HPPOS282

Multi-Agency Radiation Site Survey and Investigation Manual (MARSSIM) (Final Report) NUREG 1575

National emission standards for hazardous air pollutants

National Institutes of Health, Bethesda, Maryland, Regarding Exemption from 10 CFR 35.315(a)(7) HPPOS316

National Institute for Occupational Safety and Health Respirator User Notice: Special Precautions for Using Certain Self-Contained Breathing Apparatus Air Cylinders In00007

National primary drinking water regulations

National primary drinking water regulations implementation

National Radon Proficiency Program Guidance on Quality Assurance (program ceased in 1998)

National Secondary drinking water regulations

NESHAPS Inspection Manual (August 2002)

Neutron Capture Prompt Gammas listed by energy (html)

Neutron Capture Prompt Gammas listed by energy with yields

Neutron Capture Prompt Gammas listed by energy without yields (pdf)

Neutron Capture Prompt Gammas listed by target (html)

New and Innovative Technologies for Mixed Waste Treatment August 1997

New Exposures Limits for Airborne Uranium and Thorium In92034

New Modalities to be Regulated under 10 CFR 35.1000 - NRC Regulatory Issue Summary 2002-19

New NRC Reactor Inspection and Oversight Program, Rev. 1 NUREG 1649

New Reporting Requirements for Contamination Events at Medical Facilities (10 CFR 30.50) In91086

New Training Rule for Nuclear Power Plant Personnel HPPOS325

NIOSH Respirator User Notices, "Inadvertent Separation of the MMR From the Facepiece of MSA Company MMR SCBA and Status" In94035

NMSS Guidance to Manufacturers Regarding Labeling of Gas and Aerosol Detectors HPPOS159

No License is Required for a Person to Receive Exempt Quantity Byproduct Material HPPOS131

Nondiscrimination in Federally assisted Commission programs 10 CFR Part 4

Nonmetallic Thermal Insulation for Austenitic Stainless Steel RegGuide 1.36

Non-Power Reactor Emergency Event Response In92079

Nonrepresentative Sampling of Contaminated Oil In83033

Notice To Employees Standards For Protection Against Radiation (Part 20); Notices; Instructions And Reports To Workers;
Inspections (Part 19); Employee Protection
NRC Form 3

Notices, instructions and reports to workers: inspection and investigations 10 CFR Part 19

Notifications and Reports to Individuals HPPOS215

Notifications to the NRC Operations Center and Reporting Events in Licensee Event Reports In85027

Notifications, Reports, and Records of Misadministrations In93036

NRC Enforcement Policy - NRC Licensed Individual In79020

NRC Inspection Manuals

NRC Licensed Facilities Requesting to Name a Consultant Physicist as Its Full-Time Radiation Safety Officer HPPOS307

NRC On-Scene Response During a Major Emergency In86018

NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments In93030

NRC/EPA Draft Mixed Waste Storage Guidance 1995

NRC's Jurisdiction at U.S. Armed Forces Bases Abroad HPPOS199

Nuclear Criticality Safety In89024

Nuclear Criticality Safety Standards for Fuels and Material Facilities (Draft DG-3013 published 1/98) (Guide Withdraws Regulatory Guides 3.1, 3.4, 3.43, 3.45, 3.47, 3.57, 3.58, 3.68, 3.70 and 8.12) RegGuide 3.71

Nuclear Incident at Three Mile Island In79016

Nuclear Material Control and Accountability of Non-Fuel Special Nuclear Material at Power Reactors In88034

Nuclear Power Plant Instrumentation for Earthquakes (Draft MS 140-5,Proposed Revision 2, published 7/1981) (DG-1016, the Second Proposed Revision 2, published 11/1992) (DG-1033, the Second Proposed Revision 2, published 2/1995) RegGuide 1.12

Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations (Draft RS 110-5 published 7/1980) (Draft OL 402-5, Proposed Revision 1, published 11/1984) (Draft DG-1043, Proposed Revision 2, published 6/1995) (Draft DG-1080, Proposed Revision 3 published 8/1999) RegGuide 1.149

Nuclear Power Plant Simulation Facilities For Use in Operator Training And License Examinations (Proposed Rev. 3 to Regulatory Guide 1.149) RegGuide DG-1080

Nuclear Power Plant Staff Working HPPOS024

Nuclear Reactor Safety Design Criteria DOE Order 5480.30

Nuclear Safety Analysis Report DOE Order 5480.23

Nuclide Decay Data in MIRD Format from the National Nuclear Data Center at BNL

Obtaining Approval for Disposing of Very-Low-Level Radioactive Waste - 10 CFR Section 20.302 In83005

Obtaining Exposure Records for Controlling Exposures of Individuals Monitored at Different Sites in a Year DOE TPP 2000 3

Occupational Dose Record For A Monitoring Period NRC Form 5

Occupational Health RegGuide, Division 8

Offsite Medical Services In86098

Onsite Burial by Material Licensees" HPPOS258

Operability of Radiological Monitoring Instruments TPP95-03

Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Is Reasonably Achievable RegGuide 8.10

Operation and Use of Alarm Dosimeters at Nuclear Power Plants HPPOS328

Operational Controls to Guard Against Inadvertent Nuclear Criticality In99031

Operational Health Physics Training (Moe) ANL-88-26 large file, will take several minutes to open

Operator Licensing Examination Standards for Power Reactors, Rev. 8 NUREG 1021

Operator Licensing Requalification Examinations at Nonpower Reactors In87022

Operators' licenses 10 CFR Part 55

OSHA Interpretation: Beards and Tight-Fitting Respirators HPPOS116

Overexposure of Diver During Work in Fuel Storage Pool HPPOS002

Overexposure of Diver During Work in Fuel Storage Pool In82031

Overexposure of Driver in PWR Refueling Cavity In84061

Overexposures in PWR Cavities In82051

Packages and Shipping Containers: BMI-1

Packages and Shipping Containers: GNS-16

Packages and Shipping Containers: IF-300

Packages and Shipping Containers: Model-2000 Transport Package

Packages and Shipping Containers: NAC-LWT

Packages and Shipping Containers: NLI-1/2

Packages and Shipping Containers: TN-8L

Packages and Shipping Containers: Transuranic Packaging Transporter-Model II (TRUPACT-II)

Packaging and Transfer of Materials of National Security Interest Manual DOE M 461.1-X

Packaging and transportation of radioactive material 10 CFR Part 71

Packing Greater Than Type A Quantities of LSA Radioactive Material for Transport HPPOS080

Particulate Sampling Line Bend Radii HPPOS006

Performance of NRC-Licensed Individuals While on Duty In85053

Performance standards for ionizing radiation emitting products

Performance-Based Containment Leak-Test Program (Draft DG-1037 published 2/1995) (Errata to NEI 94-01 published 3/1996) RegGuide 1.163

Perimeter Intrusion Alarm Systems (Draft SG 479-4, Proposed Revision 2, published 5/1979)(Draft DG-5007, Proposed Revision 3, published 4/1996) RegGuide 5.44

Periodic Testing of Electric Power and Protection Systems (DG-1028, Proposed Revision 3, published 9/1994) RegGuide 1.118

Personnel Injuries Resulting From Improper Operation of Radwaste Incinerators In90020

Personnel Monitoring Requirements for an NRC/Agreement State Licensed Contractor Working at a Part 50-Licensed Facility HPPOS047

Personnel Selection, Qualification, And Training Requirements For Doe Nuclear Facilities DOE Order 5480.20a

Physical protection of plants and materials 10 CFR Part 73

Physical Qualification of Individuals to Use Respiratory Protective Devices In84024

Planned Special Exposures (Draft DG-8008 published 12/1991) RegGuide 8.35

Policy and Standard Operating Procedures When Mammography Facilities in States that have Accreditation Bodies Intend to Change Accreditation Bodies (5/15/98)

Policy Guidance Concerning Use of Xenon-133 in Saline HPPOS319

Portable Moisture / Density Gauges: Recent Incidents of Portable Gauges Being Stolen or Lost In87055

Portable Moisture/Density Gauges: ...Incidents and Common Violations of Requirements for Use, Transportation, & Storage In86067

Portable Moisture-Density Gauge User Responsibilities During Field Operations In93018

Possible Environ Effect of Reentry of COSMOS 1900 and Request for Licensee Radioactivity Measurements In88071

Possible Loss of Emergency Notification System Due to Loss of A C Power In85077

Posting Criteria for Radiological Areas TPP95-02

Posting of Entrances to a Large Room or Building as a Radiation HPPOS036

Posting of Notices to Workers HPPOS158 10 CFR 20.303(d) - Disposal by Release Into Sanitary Sewerage HPPOS157

Posting of Notices to Workers, Clarification on 10 CFR 19.11a HPPOS228

Posting per 10 CFR 34.42 and Surveys per 10 CFR 20. HPPOS296

Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems In93006

Potential Error in Manual Brachytherapy Dose Calculations Generated Using a Computerized Treatment Planning System In94065

Potential Hazards Due to Volatilization of Radionuclides In00016

Potential Problems Associated With Loss of Electrical Power in Certain Teletherapy Units In97064

Potential Problems With Worn or Distorted Hose Clamps on Self-Contained Breathing Apparatus In89047

Potential Radioactive Leakage to Tank Vented to Atmosphere In91056

Potential Safety Issue Regarding the Shipment of Fissile Material In96063

Potentially Significant Equipment Failures Resulting from Contamination of Air-Operated Systems In81038

Power Reactors RegGuide, Division 1

Practical Guide for Ground-Water Sampling

Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions (Draft DG-1017 issued 11/1992, Draft DG-1034 issued 2/1995) RegGuide 1.166

Preparation Of Soil Sampling Protocols: Sampling Techniques And Strategies EPA/600/R-92/128

Preparation of Supplemental Environmental Reports for Applications To Renew Nuclear Power Plant Operating Licenses (Supersedes DG-4002) RegGuide DG-4005

Prior Years Exposure Records TPP 95-04

Probable Misadministrations Occurring During Intravascular Brachytherapy with the Novoste Beta-Cath System In98010

Problems ... Emergency Ventilation Systems for Near-Site ... Emergency Operations Facilities & Technical Support Centers In92032

Problems Experienced Loading and Unloading Spent Nuclear Fuel Storage and Transportation Casks In97051

Problems Involved in Monitoring Dose to the Hands Resulting from the Handling of Radiopharmaceuticals In03012

Problems Resulting in Erroneously High Reading With Panasonic 800 Series Thermoluminscent Dosimeters In85081

Problems With Access Authorization Programs In91059

Problems with Emergency Preparedness Respiratory Protection Programs In98020

Problems with Silver Zeolite Sampling of Airborne Radioiodine In86043

Problems... Emergency Ventilation Systems for Near-Site ... Emergency Operations Facilities & Technical Support Centers In92032

Processing Material License Applications Involving Change of Ownership" HPPOS257

Processing of Transportation Enforcement Cases Based on Third Party Data Collected by Agreement State Agencies HPPOS058

Processor Sensitometric Control

Products RegGuide, Division 6

Program fraud civil remedies 10 CFR Part 13

Prompt Reporting to NRC of Significant Incidents Involving Radioactive Material In88032

Proposed amendments to 40 CFR Part 61, Air Emission Standards for Radionuclides In89037

Proposed DOE O 461.X, Defense Programs Packaging and Transportation DOE O 461.X

Proposed DOE O 461.X, Defense Programs Packaging and Transportation

Proposed Guidance for Calibration and Surveillance Requirements to Meet Item II.F.1 of NUREG-0737 HPPOS001

Protection Against Malevolent Use of Vehicles at Nuclear Power Plants (Draft DG-5006 issued 11/1993) RegGuide 5.68

Protocol for Accompaniment on NRC Inspections HPPOS108

Public records 10 CFR Part 9

Q&A "Decay in storage" is one means of waste disposal authorized in the revised Part 20 [10 CFR 20.2001(a)(2)]. How can "decay in storage" be used for wastes (a) at nuclear power plants and (b) at materials facilities?

Q&A (a) 10 CFR 20.1301(a)(2) requires that the dose in any unrestricted area from external sources does not exceed 2 millirem "in any one hour." Since this is not an instantaneous limit, can the licensee operate at levels much higher than 2 millirem per hour for a very short period of time (e.g., 90 millirem /hr for 1 minute, then no dose for the rest of the hour)? (b) If so, how is the 2 mrem in any one hour inspectable? 10 CFR 20.1301

Q&A (a) Are licensees required to provide instruction on the procedures for declaring her pregnancy to an occupationally exposed woman if she does not enter a restricted area? (b) Is it necessary to monitor all (occupationally exposed) declared pregnant women?

Q&A (a) Are records maintained by nuclear power plants that satisfy the requirements of 10 CFR Part 50, Appendix I, and related regulatory guidance sufficient to demonstrate compliance with the requirements of 20.2107? (b) If not, what additional records are required?

Q&A (a) Are there no limits on airborne radioactivity concentrations in the controlled area, other than de facto limits for public dose to keep dose rates less than 2 mrem in an hour? (b) Would stack effluents creating temporary airborne radioactivity concentrations greater than DAC levels in the controlled areas be allowed, as long as the public dose criteria of 10 CFR 20.1301 are met? (c) It appears that these areas would not need to be "posted" or 10 CFR 20.1201

Q&A (a) Can a cardiologist who performs both nuclear cardiology and cardiac catheterization use a planned special exposure (PSE) to perform an emergency cardiac catheterization on the last day of the licensee's monitoring year if his annual exposure as of December 30 is 4.9 rem? It is expected that he will receive greater than 100 mrem during the procedure. (b) Could the same cardiologist perform multiple cardiac catheterization as PSEs 10 CFR 20.1003

Q&A (a) Does Part 20 apply to emergency response personnel such as city fire fighters? (b) If Part 20 does apply, would the radiation dose received by the workers be considered to be an occupational dose or a public dose?

Q&A (a) Does the revised Part 20 require that meters be calibrated? (b) If so, is the calibration frequency specified?

Q&A (a) For nuclear power facilities does conformance with Regulatory Guides 8.8 and 8.10 fully meet the requirements of 20.1101(b) regarding ALARA programs? (b) If not, does the NRC plan to update these Regulatory guides to conform to new requirements?

Q&A (a) If a worker is exposed to an external source such that his head is the maximally exposed area of the body, are the doses to the head limiting, since the head is not included under the definition of "extremity?" (b) What is the annual dose limit to the head, assuming no other internal or external dose?

Q&A (a) If the annual limit to the head is five rem deep dose equivalent, what is the purpose of the 15 rem eye dose equivalent? (b) How can a person receive 15 rem eye dose equivalent without exceeding the annual TEDE limit?

Q&A (a) If the individual had not been monitored at his previous employer while receiving an occupational dose (i.e., the dose there had been determined not likely to exceed 10% of the limits), and the current employer, Licensee Z, determines in advance that the worker's annual dose for both licensees will exceed 10% (although the dose at Licensee Z will not exceed 10%), must Licensee Z monitor for external dose? (b) If the individual worked for 10 CFR 20.1502 10 CFR 20.2104

Q&A (a) In compliance with 10 CFR 20.2104(a)(2), what constitutes an acceptable attempt to obtain a record of the lifetime dose for a worker? (b) Since there are no limits for lifetime doses (other than planned special exposures), and lifetime dose reports to workers are not required, why must licensees go to the expense of obtaining and recording these doses?

Q&A (a) Is any special TLD monitoring of eye dose equivalent required? (b) Do TLDs for eye dose measurement need to be physically located near the eye? 10 CFR 20.1003 10 CFR 20.1201

Q&A (a) Licensees may apply under 10 CFR 20.1301(c) to operate at a higher annual dose limit of 500 millirem to individual members of the public. How long will this 500 millirem limit apply to the licensee? (b) Can a licensee apply for an authorization to operate at this higher limit indefinitely?

Q&A (a) Must gauge licensees perform a survey of each gauge package (if the package is labeled with a DOT label) for contamination and radiation levels upon receipt of the package? (b) What surveys must a licensee perform during routine operation where portable gauges are transported daily from site to site, then returned to a storage location? 10 CFR 20.1906

Q&A (a) The roentgen (R) is not defined or used in revised Part 20; however, many survey instruments and computer records show dose rates in terms of "mR/h" or "R/h." Will these survey instrument face pieces and computer forms have to be changed when revised Part 20 is implemented? (b) Most radiation instrumentation is currently calibrated in units of roentgens rather than rads. A roentgen of x- or gamma-radiation in the energy range of 0.1 - 3 MeV produces 0.96 rad in 10 CFR 20.1003

Q&A (a) Under 10 CFR 20.1904, what is a container? (b) How big can a container be? (c) Can a room be considered a container? (d) Is a transportation cask a container when it is not being transported? (e) Are vehicles (e.g., trailer of a tractor-trailer) containers? 10 CFR 20.1904

Q&A (a) When a package is properly labeled for transport, shipping papers are still in effect, and a transporter has accepted responsibility for control of the package, do posting and labeling requirements remain in effect while the package is on licensee property outside of the radiologically controlled area? (b) Does the shipment have to be posted in the protected area? 10 CFR 20.1902 10 CFR 20.1903 10 CFR 20.1904

Q&A (a) Who is responsible for monitoring a representative from a service company while the individual is on-site at a licensee's facility performing duties that may result in an occupational dose from sources owned/possessed by the licensee? (b) Where should the results of the monitoring be maintained? 10 CFR 20.1502

Q&A ..\NRC/Q&A/005.pdfWho is responsible for regulating radium - the State or NRC? 10 CFR 20.1001 10 CFR 20.1002

Q&A ..\NRC/Q&A/006.pdfWhat if an NRC licensee hires a DOE employee who earlier in the year received an internal exposure of less than 5 rems annual effective dose equivalent, but greater than 5 rems committed effective dose equivalent? 10 CFR 20.1201

Q&A ..\NRC/Q&A/014.pdfAre Design Basis Accident criteria (doses) changed by the revised Part 20? 10 CFR 50 Appendix A

Q&A 10 CFR 19.12 requires training (instruction) of workers who enter a restricted area. Do individuals receiving occupational doses in controlled areas need training?

Q&A 10 CFR 20.1003 defines the shallow-dose equivalent as the dose equivalent at a tissue depth of 0.007 cm. (a) Does this mean that the dose to the skin of the whole body is the sum of the non-penetrating dose equivalent (beta and low energy photons) and the deep dose equivalent? (b) Is it proper to calculate the extremity dose by summing the dose equivalent measured on an extremity dosimeter (which may only be worn for part of the monitoring period)

Q&A 10 CFR 20.1003 defines tissue monitoring depths of 0.007, 0.3, and 1 cm for shallow, eye, and deep-dose, respectively; (a) Is it important to measure at (or extrapolate the measurements to) these exact depths? (b) could the eye and deep-dose both be determined at 0.3 cm?

Q&A 10 CFR 20.1101(b) requires licensees to use, to the extent "practicable," procedures and engineering controls based upon sound radiation protection principles to achieve doses that are ALARA. The ALARA concept emphasizes dose-reduction techniques that are reasonable considering costs. However, "practicable" may imply something that has been proposed and seems feasible but has not

Q&A 10 CFR 20.1101(c) requires a periodic (at least annual) review of the radiation protection program as defined in 20.1101(a). 10 CFR 20.1101(a) refers to 10 CFR 20.2102 for recordkeeping requirements. (a) Does the use of the word "audit" in 10 CFR 20.2102(a) require records for all audits that are performed in addition to the periodic review? (b) Are the reviews required by 10 CFR 20.1101(c) also considered to be audits that are subject to the 10 CFR 20.1101

Q&A 10 CFR 20.1101(c) requires that each licensee "periodically (at least annually) review the radiation program content and implementation." A nuclear power plant has many reviews and audits (including quality assurance audits) of various aspects of their radiation protection programs during a year and reviews are on a schedule that covers all phases of the program on a 2-3-year review cycle. Is this acceptable to the NRC?

Q&A 10 CFR 20.1201 (a)(2)(ii) states a limit of "A shallow-dose equivalent of 50 rem (0.50 Sv) to the skin or to any extremity." (a) Can a person receive 50 rem shallow dose equivalent to the skin of the lower arm (extremity) and 50 rem shallow dose equivalent to the upper arm (non-extremity), without having an overexposure? (b) Can a person receive 50 rem shallow dose equivalent to the left upper arm, then the same dose to the right upper arm, 10 CFR 20.1003 10 CFR 20.1201

Q&A 10 CFR 20.1201(b) refers to "doses received during accidents, emergencies, and . . . ." Is there any difference between an "accident" and an "emergency"?

Q&A 10 CFR 20.1202(d) requires licensees to evaluate and, to the extent practical, account for intakes through wounds or skin absorption. What type of "evaluation" is appropriate for determining absorption through the skin from skin contamination, and at what "practical level" should it be accounted for? For what nuclides, using what criteria can absorption be neglected under a certain threshold, such as less than 10K, 100K of skin

Q&A 10 CFR 20.1204(g) provides that when a mixture of radionuclides in air exists, licensees may disregard certain radionuclides in the mixture if the licensee uses the total activity of the mixture in demonstrating compliance with the dose limits in section 20.1201 and if certain other conditions are met. How can a licensee both disregard certain radionuclides and use the total activity?

Q&A 10 CFR 20.1206 permits a planned special exposure (PSE) only if the alternatives that might avoid the higher exposure are unavailable or impractical. Under certain conditions, the collective dose for a task could be reduced if it could be performed by one worker receiving a PSE, rather than by a series of several workers each receiving a dose less than the limit. Under these conditions would the NRC consider the alternative of using the series of

Q&A 10 CFR 20.1206 states that workers who will receive a planned special exposure (PSE) must be informed regarding the risk from the radiation exposure that is expected to be received. Radiation risk coefficients presently available are applicable to large populations and are not recommended for risk assessment for a small number of people. The coefficients are not applicable to individual doses as small as PSEs. How are nuclear power plant licensees expected to

Q&A 10 CFR 20.1206(e) says that licensees may not authorize PSEs for workers whose doses from previous PSEs and all "doses in excess of the limits" exceed certain limits. (a) What and whose limits apply? (b) Does the actual limit (e.g. 3 rem/quarter, 1.25 rem/quarter, etc.) apply, or does the equivalent annual limit apply? (c) Do doses from non-licensed sources (e.g., x-ray sources) that were in excess of the facility's limits apply, 10 CFR 20.1001 10 CFR 20.1206 10 CFR 20.2104

Q&A 10 CFR 20.1301(a)(2) requires that the "dose" in any unrestricted area from external sources not exceed 2 mrem in any one hour. Which of the many "doses" in new Part 20 is "the dose" in 20.1301(a)(2). 10 CFR 20.1003

Q&A 10 CFR 20.1302 provides two options for demonstrating compliance with the annual dose limit, in 10 CFR 20.1301, for members of the public. How does 10 CFR 20.1302(b)(2), the second option, provide demonstration of compliance with the annual dose limit for members of the public who are in a controlled area? 10 CFR 20.1003

Q&A 10 CFR 20.1302(b)(2)(ii) refers to "the dose from external sources." (a) What are "external sources"? (b) Are both (1) shine from the facility or from stored contaminated materials and sources, as well as (2) cloud shine from effluents to be included?

Q&A 10 CFR 20.1501(b) requires the licensee to ensure that instruments and equipment used for quantitative radiation measurements are calibrated periodically; however, there is no corresponding requirement in old Part 20. Does this new requirement mean that the accuracy and frequency of such calibrations that have been found acceptable by the NRC in the past will not be acceptable under the revised Part 20?

Q&A 10 CFR 20.1501(c) requires a dosimetry processor to be NVLAP accredited. DOE also has an accreditation program. Do DOELAP-accredited processors meet the requirements of 10 CFR 20.1501(c)?

Q&A 10 CFR 20.1601 requires control of access to high radiation areas. It provides an exception for access to hospital areas with patients containing radioactive material, "provided that there are personnel in attendance . . ." who will take certain specified precautions. (a) Does a nursing station within line-of-site of a patient's room satisfy the requirement? (b) Does a nursing station controlling access to a ward, but not in the 10 CFR 20.1601

Q&A 10 CFR 20.1601(a)(1) says that the control devices must cause the radiation level to be reduced "upon entry." (a) Must the devices preclude authorized or unauthorized entry? (b) At what point must the control devices activate, when a person passes the final 30 cm before, or entry itself?

Q&A 10 CFR 20.1602 gives requirements for control for access to very high radiation areas, and has no exemption clause. 10 CFR 20.1003 defines a very high radiation area. (a) Are teletherapy rooms or fixed/field radiography facilities, with beams that can deliver in excess of 500 rad in 1 hour at 1 meter, very high radiation areas? (b) Do the requirements in 20.1602 apply to teletherapy rooms or fixed/field radiography facilities? 10 CFR 20.1003

Q&A 10 CFR 20.1603(a), Footnote 2, exempts a nuclear power plant from the requirements of 20.1603 unless a non-self-shielded irradiator is used at the reactor. (a) If the source used for the calibration of high-radiation instruments is non-self-shielded, and the absorbed dose at 1 meter distance could exceed 500 rads in 1 hour, is the source an irradiator? (b) Do the provisions of 20.1603 (a) apply?

Q&A 10 CFR 20.1703(a)(3)(iii) requires that respirators be tested for operability immediately prior to each use. How is this to be done?

Q&A 10 CFR 20.1903(a) gives exemptions to posting "caution signs" under certain conditions. Since 10 CFR 20.1902 specifies "danger" signs, instead of caution signs, (e.g., "grave danger, very high radiation area"), do the exemptions in 10 CFR 20.1903 apply to these "danger" areas as well? 10 CFR 20.1902

Q&A 10 CFR 20.1904(a), Labeling containers, indicates in a parenthetical statement that "the radionuclides(s) present" may now be intended to be a part of the information required to be included on labels. In reply to comments on this rule, the preamble (56 FR 23380, first column) provides a special interpretation for nuclear power plant licensees as to acceptable methods for compliance for labeling fission and activation product containers. Taken

Q&A 10 CFR 20.1906(a) gives specific requirements for packages containing radioactive material in excess of Type A quantities; it is not followed by the word "and." 10 CFR 20.1906(b) appears to apply to all packages as containing radioactive material, or labeled packages that are crushed, wet, or damaged. Is it a correct statement that 10 CFR 20.1906(b) requirements have nothing to do with Type A quantities, and that (a) and (b) are independent 10 CFR 20.1906

Q&A 10 CFR 20.2101(b) requires the licensee to make a clear distinction among the dose quantities entered on the records and gives examples of the following different dose quantities: total effective dose equivalent, shallow dose equivalent, eye dose equivalent, deep dose equivalent, committed effective dose equivalent. Does this mean (for example) that the dose rates measured during surveys of external radiation fields must be recorded in

Q&A 10 CFR 20.2102(a) requires the use of the units curie, rad, rem, including multiples and subdivisions, on records required by Part 20. May a licensee continue to use roentgen-based units (e.g., R, mR, R/h, mR/h) in exposure control, radiation survey, and instrument and dosimeter calibration records without conversion to rad or rem, provided that assessed doses for individuals are recorded in units of rad or rem? 10 CFR 20.1003 10 CFR 20.2101 10 CFR 34.21 10 CFR 34.24 10 CFR 34.33

Q&A 10 CFR 20.2104(c) states in three places that licensees may accept or obtain dose data from the most recent employer. The most recent employer may not be the licensee at whose facility the worker was most recently exposed. Will it be permissible to accept or obtain the data from the most recent facility at which the worker was exposed? (Small contractors often do not have the data. Nuclear power plant licensees in general would much prefer to continue

Q&A 10 CFR 20.2104(c)(1) states that a licensee may accept, as a record of the occupational dose that the individual received during the current year, a written signed statement from the individual. If this was done and the statement is false, would a resulting exposure greater than 5 rem in the year be considered an overexposure and a violation?

Q&A 10 CFR 20.2104(e)(1) prorates the 5-rem annual limit on the total effective dose equivalent at a rate of 1.25 rems per quarter for each quarter for which records were unavailable but includes no similar provisions for the other annual limits (individual organs, eye, skin, extremities). Is similar proration required for doses covered by the other limits? 10 CFR 20.1201

Q&A 10 CFR 20.2110 requires adequate safeguards against tampering with and loss of records. For data stored in electronic systems, what safeguards are acceptable?

Q&A 20.1502(a)(2) and (b)(2) say that monitoring is required for declared pregnant women "...likely to receive, in 1 year,..." a dose in excess of 10 percent of the applicable limits for the embryo/fetus. (a) What year does this refer to? (b) Since the gestation period is 9 months (and since monitoring would begin after the declaration, which may be several months into a pregnancy), why does the regulation use a year? (c) The licensee badges a declared 10 CFR 20.1003

Q&A A "Note" added to the answer to Question 126 clarifies the answer with respect to nuclear power plants. Does this clarification also apply to non-power reactor facilities?

Q&A A health care worker serves in a dual nuclear medicine and radiology position. The worker wears a dosimeter on the waist and a dosimeter at the collar. During fluoroscopy procedures, which is the primary source of exposure, the worker wears a lead apron that covers the waist dosimeter, but not the collar dosimeter. Over the course of a year, the worker receives a dose of 5.2 rem as measured by the collar dosimeter and 1.7 rem as measured by the

Q&A A licensee (e.g., radiographer, moisture density gauge operator, well logger) has a source that the licensee transports to temporary job sites in a licensee-owned vehicle. 10 CFR 20.1906(f) exempts the licensee from doing contamination surveys during routine operations, but does not exempt the licensee from performing surveys for radiation levels. (a) When must the licensee perform such surveys (i.e., when is the package "received")? Is it only after returning 10 CFR 20.1906

Q&A A licensee authorizes a "planned special exposure" in accordance with 10 CFR 20.1206 and the doses to the involved individuals are fortuitously much lower than anticipated. In retrospect, a planned special exposure authorization was unnecessary. May the doses be assigned as "routine" doses on the Form 5 rather than recorded as planned special exposure doses? 10 CFR 20.1206

Q&A A licensee is required to provide individual monitoring for each occupationally exposed individual who is likely to receive, in a year, a dose in excess of 10% of the applicable limits in 10 CFR 20.1201, 10 CFR 20.1207, or 10 CFR 20.1208. Must a licensee account for the exposure that an individual may receive at another licensee's facility, if that worker transfers to another licensed facility during the monitoring year, when determining if it is likely

Q&A A licensee makes a prospective determination that adult workers in Department W are not likely to receive doses in excess of 10% of the limits from external sources, so external dosimetry is not required by 20.1502. The workers in Department W complain when their TLD badges are taken away, so the licensee decides to leave them badged, but not to demonstrate compliance with the occupational dose limits of the revised Part 20. (a) If an inspector finds 10 CFR 20.1502

Q&A A licensee monitors a worker for both external and internal exposure under 20.1502, but the internal exposure for the year is less than 10% of the dose limit. Does the licensee add it to the external exposure? 10 CFR 20.1202

Q&A A nuclear medicine technologist becomes contaminated with I-131 which results in an internal uptake of iodine. She continues to breast-feed her baby. Is the licensee responsible for controlling the dose to the baby as a member of the public in an unrestricted area? If so, what are the dose limits? 10 CFR 20.1201

Q&A After implementation of the revised 10 CFR Part 20, should nuclear power plant licensees report total effective dose equivalent (TEDE) or deep dose equivalent (DDE) as the "whole body dose" for annual reports submitted in accordance with reactor technical specifications and Regulatory Guide 1.16? Regulatory Guide 1.16

Q&A Alarm setpoints for many radiation monitors are based on 10 CFR 20 Appendix B concentrations. Will these new changes require numerous ODCM changes, setpoint change requests, and procedure changes? 10 CFR 20 Appendix B NRR Generic Letter 89-01

Q&A Although it is extremely unlikely, long-lived residual radioactive material in the body of a female worker from her previous employment could deliver a dose exceeding the limit to a subsequently conceived embryo/fetus. For example, a former DOE worker who had been involved in an accident could have a large americium or plutonium body burden. 10 CFR 20.1208 makes no special provision for this eventuality. What action would the NRC expect

Q&A Although Question 385 does not refer to any particular class of licensee (e.g., power reactor, non-power reactor, materials), the answer to the question mentions only power reactor licensees and material licensees. Does the answer to this question also apply to non-power reactor or fuel cycle licensees?

Q&A An individual works concurrently at Licensees W, X, Y, and Z. All four licensees make a prospective determination that external doses will not exceed 10% of the limits at their own facility. Must any of the licensees monitor for external dose?

Q&A Appendix B contains only one derived air concentration (DAC) value for each radionuclide. The DAC provided in Appendix B is derived from the more limiting of the stochastic or the non-stochastic annual limit on intake (ALI). In Regulatory Guide 8.34 (Section 3.3) the NRC provides guidance that the stochastic DAC should be used, in preference to the non-stochastic DAC, to calculate the committed effective dose equivalent (CEDE). This 10 CFR 20.1003 10 CFR 20.1502

Q&A Are licensees required by 10 CFR 19.13 to report to individuals the results of monitoring performed but not required under 10 CFR 20.1502? 10 CFR 19.13 states that radiation exposure data shall be reported to the individual, and that "the information reported shall include data and results obtained pursuant to Commission regulations, orders or license conditions, as shown in records maintained by the licensee pursuant to Commission regulations. 10 CFR 19.13

Q&A Are licensees required to advise personnel of the provisions for declaring pregnancy, who enter a restricted area, but do not "work in or frequent" any restricted area (e.g., visitors on tours)?

Q&A Are radiographers exempt from posting at a temporary field site, under 10 CFR 20.1903(a), since they perform radiography in each area less than 8 hours, attend the material to prevent exposure of individuals in excess of the limits (i.e., have clear sight over the designated area and are in constant attendance), and control the area (i.e., tell individuals to leave if they come too close to the source)? 10 CFR 20.1903

Q&A Are students and volunteers subject to the occupational dose limits? For example, nuclear medicine students, or "candy stripers" that transport nuclear medicine patients or perform volunteer work in a nuclear medicine department. 10 CFR 20.1003

Q&A Are the noble gas ("submersion") DACs based on a dose of 5 rem per year or 50 rem per year? Is the submersion dose calculated at a depth of 1000 mg/square cm or 7 mg/square cm?

Q&A Are the results of dose monitoring of minors and declared pregnant woman performed in accordance with 20.1502 required to be reported to NRC as part of the annual reporting of individual monitoring results? (b) If so, are the records of dose to the embryo/fetus, which may differ from records of dose to the declared pregnant woman, required to be submitted as part of the annual reporting of individual monitoring results? It would seem 10 CFR 20.1208 10 CFR 20.1502

Q&A As long as no credit is taken for the protection provided by the respiratory protection equipment, the old Part 20, in 10 CFR 20.103(c), allows licensees to use this equipment without meeting the requirements of 10 CFR 20.103(c)(1) through 20.103(c)(4), inclusive. Has this "loophole" in the old Part 20 been closed in the revised Part 20?

Q&A Assume a licensee has defined its compliance year as January 1, 1993 to December 31, 1993. What is the mechanism to change its definition of year? For example, the licensee wants to monitor from January 31, 1994 to January 30, 1995, how should it account for the lost days January 1 - 30, 1994? Is it acceptable to prorate the doses?

Q&A At a nuclear power plant, the individual asked to approve a planned special exposure (PSE) will need to believe that the alternatives are impractical or unavailable before doing so. But he or she must recognize that the NRC inspector who later reviews the PSE report may not agree, possibly leading to a notice of violation for an overexposure. If the individual at the nuclear power plant chooses to request it from the Region, can a decision be

Q&A At power reactor facilities, when the reactor is at power, very high radiation areas (due to neutron and N-16 gamma radiation fields) can exist inside the primary containment. At some facilities, these areas inside containment are not readily locked, without substantial plant modifications to make them lockable. In recognition of this situation, the following controls are planned to meet the requirements of 10 CFR 20.1602 as it relates to a 10 CFR 20.1003

Q&A Automated personnel contamination monitors ("portal monitors") are used at nuclear power plants to detect radioactive surface contamination on the skin and clothing of workers. The alarm setpoints for these monitors are maintained very low to detect low levels of surface contamination and hot particles. Implementation of the "respirator ALARA rule," [10 CFR 20.1702 and 20.1703(b)(1)] may result in intakes of radioactive material by workers that

Q&A Background 10 CFR 20.2104 states that for each individual for whom monitoring is required, the licensee must: 1.) Determine the occupational radiation dose for the current year; and 2.) Attempt to obtain the records of lifetime cumulative occupational radiation dose. "Records of

Q&A Before implementing all of the provisions of the revised Part 20, would a licensee be in violation of 10 CFR 20.1008(a) if the licensee voluntarily adopted the provisions of 10 CFR 20.1208 for protection of the embryo/fetus? 10 CFR 20.1008

Q&A Can a female worker legally declare pregnancy if she does not yet have documented medical proof? 10 CFR 20.1003

Q&A Can a licensee allow radiation levels of 5 mR or more in one hour in an area without limiting access to the area? 10 CFR 20.1003

Q&A Can a licensee require its workers to routinely take potassium iodide (KI) when handling large quantities of radioiodine and take credit for the reduction in occupational dose that results from the use of the KI?

Q&A Can a radiography licensee consider an individual's exposure, received during a source retrieval, as a planned special exposure if an approved generic procedure for source retrieval is on file? Assume that this procedure addresses all the administrative and recordkeeping requirements of 10 CFR 20.1206.

Q&A Can biological material be defined better in 20.2003? For example, is all organic material biological material? Can animal fats be released to the sewer?

Q&A Can the results of bioassays alone be used to determine if the licensee must sum internal and external doses under Part 20?

Q&A Can the surveys of radiographic exposure devices performed under 10 CFR 34.43(b) and (c) be used to show compliance with 10 CFR 20.1906(f)? If so, is it sufficient to document the survey once, to satisfy both requirements? 10 CFR 20.1906 10 CFR 34.43

Q&A Can you have radiation levels in excess of 2 millirem in one hour or 100 millirem per year in a controlled area if the public is not allowed to enter the area?

Q&A Current computer codes, such as LADTAP and GASPAR, calculate individual organ doses for comparison against individual organ dose limits in 10 CFR 50 Appendix I and/or Technical Specifications. Will the codes have to be modified to convert whole body and organ doses to effective dose equivalents?

Q&A Detectable, minor intakes may result for some individuals who do not wear respirators during specific radiological work activities for the purpose of maintaining the total effective dose equivalent (TEDE) as low as is reasonably achievable (ALARA), as required by regulation. Such resulting intakes may involve substantial follow-up activities in terms of bioassay, internal dose assessment, and responses to various monitor alarms (e.g., hand-held

Q&A Do 10 CFR 20.2104(a), 10 CFR 20.2104(d) and Footnote 4 to 20.2104(d) mean that a licensee must "backfit" effective dose equivalents (EDE) for individuals who were occupationally exposed before implementation of the revised Part 20? 10 CFR 20.2104

Q&A Do licensees have discretion regarding the form and applicability of additional posting and barriers for individual high radiation areas (HRAs) that are located within a larger area posted and barricaded (e.g., with a locked door) as an HRA or inside a posted HRA control point? If licensees must post and barricade such individual HRAs at each area's entrance, then "double posting" results. Double posting has long been a concern due to the 10 CFR 20.1601

Q&A Do licensees have to post controlled areas (outside the restricted area) as airborne radioactivity areas if derived air concentrations (DAC) are exceeded? 10 CFR 20.1003

Q&A Do NRC regulations allow a declared pregnant woman to "undeclare" her pregnancy? If so, does this withdrawal of a previous declaration of pregnancy also oblige the licensee to withdraw restrictive measures and enhanced monitoring established solely to comply with related embryo/fetus dose limits?

Q&A Do posting requirements apply to the hospital room of a hospitalized nuclear medicine patient if the patient received less than 30 mCi and the dose rate at 1 meter is greater than 5 mrem/hr?

Q&A Do the requirements of 10 CFR 20.1703(a) apply to respiratory protection equipment that is to be used only in emergencies?

Q&A Does the definition of a "member of the public" mean "all" individuals? If so why is the exception statement added to the definition?

Q&A Does the footnote to 10 CFR 20.1203 mean that DAC-hours, and not measurements of external dose (using personal dosimeters), should be used for determining worker exposures to noble gases?

Q&A Does the requirement of 10 CFR 20.2101(a) to use the unit curie (for activity) mean that it will not be permissible to record the results of contamination surveys in units of disintegrations per minute (dpm) or mrad smearable?

Q&A Does the term "per unit intake" in Footnote 1 to 20.1202 refer to one event or to the entire monitoring period?

Q&A Does the word "also" as used in 20.1202(c) mean intake by oral ingestion and inhalation, or oral ingestion and external exposure? 10 CFR 20.1202

Q&A Does the word "applicable" in the phrase "applicable ALI(s)" in 10 CFR 20.1502(b)(1) mean that the stochastic ALI(s) [SALI(s)] should be used? It is noted that 10 CFR 20.1502(b) requires the licensee to monitor the occupational intake and assess the committed effective dose equivalent. We believe that the answer to this question should be yes, if a licensee is operating under XT 707 02/07/95 Question 47: Will the NRC pr preparation of applications pursuant to 10 CFR 20.1204(c)(2) for approval to adjust DAC or ALI values to reflect the actual physical and chemical characteristics of airborne radioactive materials (e.g., aerosol size distribution or density)?

Q&A Dose rates are used to establish posting requirements for radiation areas, high radiation areas, and very high radiation areas. 10 CFR 20.1601(a)(1), "Control of Access to High Radiation Areas," refers to a "deep-dose equivalent" in describing when a control device should be provided to reduce radiation doses below 0.1 rem in one hour, thus implying that the "dose equivalent" in the definition of a "high radiation area" is the "deep dose equivalent" [at 10 CFR 20.1003

Q&A During 1993, the licensee performed a prospective dose evaluation, and decided not to measure internal dose. In 1994, the licensee again evaluates the internal dose and finds that the threshold for monitoring is exceeded and begins monitoring. Nothing in the facility (engineering controls or productivity levels) has changed. The licensee accounts for the internal dose contribution when calculating TEDE for 1994. Must the licensee go back and adjust TEDE for

Q&A During 1993, there may be radiation workers transiting between licensees that have, and have not, implemented the revised Part 20. (a) In the case of a worker whose dose was monitored earlier in the year at a licensee that has implemented the revised Part 20 and is now in processing at a licensee that has not implemented the revised Part 20: (1) Should "whole body dose" be taken as the "total effective dose equivalent" (TEDE) or as the "deep

Q&A For control of access to very high radiation areas, will physical barriers be needed to preclude unauthorized access?

Q&A For power reactors, the Technical Specification instantaneous release rate limits are based on old Part 20 doses and concentrations (relative to an implied 500 mrem/yr limit). Will changes in the Technical Specifications and ODCMs be required as a result of the explicit 100-mrem/yr limit in the revised Part 20?

Q&A FSARs for Part 50 power reactor licensees typically contain multiple references to current 10 CFR Part 20 concepts and terminology, primarily with regard to describing aspects of the radiation protection program. Updating of these references would be editorial in nature, without any health and safety benefit, but would nevertheless divert resources from potentially more significant matters. Additionally, these changes would be submitted to 10 CFR Part 50

Q&A How are annual average concentrations (AAC) to be calculated, and is it acceptable for nuclear power plants to use this AAC in lieu of instantaneous limits (as currently required by the operating license) which are derived from NUREG-0133?

Q&A How are nuclear power plant licensees to identify the "potential" hazard using air sampling techniques as specified in 10 CFR 20.1703(a)(3)(i)? (Air sampling is only useful in hazard identification after radioactive material becomes airborne).

Q&A How are occupational dose limits applied in regard to the revised Part 20 definition of "year"? The purpose of this question is to obtain additional clarification of the intent and application of the "year" as it is defined in the revised Part 20 and discussed previously in Question 40. Apparently, licensees may establish a year that is other than January 1 through December 31 (e.g., Question 40 addresses a year that is from January 31 of one year

Q&A How does the U.S. Supreme Court decision in the case of United Auto Workers (UAW) vs Johnson Controls affect the NRC requirement in 10 CFR 20.1208, "Dose to an embryo/fetus," and the guidance in Regulatory Guide 8.13, "Instruction Concerning Prenatal Exposure?" 10 CFR 20.1208

Q&A How is the dose from radon considered? What about technologically enhanced radon at a licensed facility? [Note: Technologically enhanced natural radiation sources have been defined as "truly natural sources of radiation . . . which would not occur without (or would be increased by) some technological activity not expressly designed to produce radiation." Reference: T.F. Gesell and H.M. Prichard, Health Physics 28, 361-366, April 10 CFR 20.1001 10 CFR 20.1002

Q&A How should demonstration be made of compliance with the 2 mrem in an hour limit [10 CFR 20.1301(a)(2)]? Is it adequate, for a nuclear power plant, to demonstrate compliance by having effluent control (trip) systems that prevent effluent releases from exceeding the limits on the instantaneous release rates, and by performing periodic surveys during radioactive material storage and movements?

Q&A How will licensees handle cases where occupationally exposed workers inform the licensee that they are concurrently being exposed (and/or monitored) at another facility, but refuse to name the other facility? (Note that if the worker is under contract, the other facilities may be competitors of the licensee). 10 CFR 20.1201

Q&A How will the revised Regulatory Guides be used in determining acceptability of a licensee's implementation of the revised Part 20?

Q&A If a license condition ties the licensee to a section in the old Part 20 and there is no corresponding section in the revised Part 20, does the requirement in the old Part 20 stay in effect after implementation of the revised Part 20.

Q&A If a licensee controls exposure to members of the public using the new Part 20.1302(b)(2) at the boundary of the unrestricted area, how does a licensee ensure that members of the public inside the controlled area do not exceed this limit?

Q&A If a licensee implements the revised Part 20 in July, 1993, is the licensee required to go back and evaluate internal dose for the purpose of determining total effective dose equivalent for the year? 10 CFR 20.1202

Q&A If a package containing radioactive material is to be shipped, and marking the package as low specific activity (LSA) is the only U.S. Department of Transportation (DOT) warning requirement, is labeling under 10 CFR 20.1904(a) required? 10 CFR 20.1904

Q&A If a worker formerly monitored at the licensee's facility as a "declared pregnant woman," requests that her exposure records be forwarded to her current employer, should related embryo/fetus dose records also be forwarded if not specifically requested? 10 CFR 19.13

Q&A If a worker who has been exposed to internal sources under Department of Energy Order 5480.11 comes to work at an NRC-licensed facility, will the worker's committed and committed effective dose equivalents need to be calculated for a fifty-year period by the licensee? DOE Order 5480.11 only requires a one-year dose commitment calculation. 10 CFR 20.1204 10 CFR 20.2104

Q&A If an individual is monitored several times during a year by the same licensee (e.g., during two monitoring periods separated in time), how should the monitoring period(s) be designated in the annual individual monitoring report required by 10 CFR 20.2206 (i.e., on the NRC Form 5 or equivalent)? Due to the possible limitations in the format and structure in licensee's computerized occupational dose recordkeeping systems, it seems that there should

Q&A If an individual receives an intake of Class Y material in September and, pursuant to 10 CFR 20.1204(d), the licensee waits 7 months to record the dose (March), what year should the dose be recorded?

Q&A If an NRC licensee employs an individual formerly employed at a DOE lab and that individual's DOE lab dose record shows a CEDE of more than 5 rems (but within DOE limits) must the NRC licensee consider this an overexposure and reduce this individual's planned special exposure allowance accordingly? 10 CFR 20.1206 10 CFR 20.1206

Q&A If irradiated hardware, suspended (e.g., on a lanyard) in the spent fuel pool, is potentially reading greater than 500 rads/hour at one meter (i.e., if it were removed from the pool), does access to this hardware require posting and control as a Very High Radiation Area? 10 CFR 20.1003 10 CFR 20.1601

Q&A If the declared pregnant woman's estimated date of conception encompasses a previous period of employment at another licensee's facility, what assumptions should be made by the current licensee for compliance purposes under each of the following conditions? a. Until records are received from the previous licensee; 10 CFR 20.1208

Q&A If the employer has been informed, in writing, by a female worker that she is pregnant, and the employer is not the licensee (e.g., the employer is a contractor to the licensee), may the employer notify the licensee of the declaration of pregnancy to establish applicability of 20.1208, Dose to an Embryo/Fetus, or must the woman herself make the declaration to the licensee? 10 CFR 20.1003

Q&A In 10 CFR 20.1201(a)(1) does "annual limit" for dose(s) mean the limit on doses received in a "year" as defined in 10 CFR 20.1003? 10 CFR 20.1003

Q&A In 10 CFR 20.1301(a)(2), does ". . . 0.002 rem (0.02 mSv) in any one hour" apply to the dose in any single hour or can it apply to the average over a discrete period of time.

Q&A In 20.1902, posting of areas is based upon "dose equivalent." Is this "deep," "shallow," "lens of eye," "total effective" or some combination of the above? 10 CFR 20.1003

Q&A In a respiratory protection program what records are needed of evaluations that demonstrate compliance with the requirement for maintaining the total effective dose equivalent ALARA? For example, must such an evaluation be made each time an individual is to wear a respirator? 10 CFR 20.1101

Q&A In complying with the 10 CFR 19.13(c) report request, is it acceptable to report on a Form-4 dose received in the current year as one monitoring period and dose received in prior years as another monitoring period even if the prior years monitoring period exceeds one year?

Q&A In determining the "eye dose equivalent," can credit be taken for shielding provided by eyeglasses/safety glasses?

Q&A In evaluating the use of respirators to limit intakes, in addition to determining the total effective dose equivalent (TEDE), should the evaluation and subsequent decision on whether to use respirators also consider industrial safety hazards associated with wearing respirators? For example, added effort increasing the probability of heat stress, limited range of vision while climbing, or difficulty of maneuvering readily while working 10 CFR 20.1702

Q&A In evaluating whether to require the use of respirators to limit intakes, it is found that wearing a respirator will likely increase the total effective dose equivalent (TEDE). However, the workers request that they be allowed to wear respirators to limit intakes, despite the results of the evaluation. With regard to NRC regulation, what discretion may the licensee exercise in this circumstance? 10 CFR 20.1702

Q&A In general, do established respirator effectiveness programs at nuclear power plants meet the intent of the regulation in providing assurances of the effectiveness of chosen respiratory protection? 10 CFR 20.1502 10 CFR 20.1703

Q&A In general, the nuclear power industry has concluded that workers are not likely to exceed 10% of the annual limit on intake, and therefore internal dose monitoring would not be required. However, some nuclear power plant licensees plan to continue internal dose monitoring and record and report monitoring results on a voluntary basis. (a) If the results of both voluntary monitoring of the committed effective dose equivalent (CEDE) and required

Q&A In order to terminate a declaration of pregnancy, i.e., due to termination of the pregnancy or otherwise, must the female worker inform the licensee or employer in writing? 10 CFR 20.1003

Q&A In regard to 91 (previously answered in the third set of QAs;), can NIOSH approved respiratory equipment which makes use of a combination particulate filter and iodine sorbent with a protection factor for particulates be used in a mixed particulate and iodine atmosphere to limit intakes? This practice would seem valid for equipment that is NIOSH approved and has a protection factor for particulates. 10 CFR 20.1702

Q&A In supporting a conclusion that individual monitoring of internal occupational dose is not required [10 CFR 20.1502(b)] and, therefore, that summing of internal and external dose is not required [10 CFR 20.1202(a)], what is considered to be acceptable for bioassay frequency, DAC-hour administrative limit, and whole-body counting minimum testing level? 10 CFR 20.1202 10 CFR 20.1502 10 CFR 20.1703

Q&A In the answer to Question 379, the NRC addressed the issue of whether noble gases should be included in assessing the requirement to post an area as an airborne radioactivity area. This is intended to obtain further clarification with regards to the two separate provisions that require posting of airborne radioactivity areas. The first provision requires posting of areas in which concentrations of airborne radioactive materials 10 CFR 20.1003 10 CFR 20.1502

Q&A In the definition of individual monitoring devices, is there any reason electronic monitoring devices are not mentioned?

Q&A In this example, an individual has worked at the licensee's facility earlier in the current year and was required to be monitored because the individual accessed a high radiation area. During this period, the individual's monitored dose did not exceed 10% of a limit. Now the individual is performing other work at the licensee's facility in the restricted area, but no longer has access to high radiation area. An evaluation based on the individual's new job 10 CFR 20.1502

Q&A In this example, it has been determined that an individual is not likely to exceed 5 rems shallow dose equivalent from any sources with the possible exception of dose from hot particles. There is a potential that exposure to an individual from a hot particle may occur and that the dose to the individual from a hot particle, should it occur, may potentially exceed 5 rems shallow dose equivalent. In this circumstance, may the potential dose resulting

Q&A In this example, it has been determined that an individual will receive less than 100 mrems in a year while in the controlled area, and the individual has therefore been classified as a member of the public while in the controlled area. The individual also accesses and performs work in the restricted area. In evaluating whether the individual requires monitoring in the restricted area, may the evaluation be limited to only the dose likely to 10 CFR 20.1003

Q&A Individuals performing assigned duties are often exposed to small amounts of radiation from plant effluents at licensees' sites under normal operating conditions. (a) If these individuals are likely to receive, or have already received, in excess of 10% of an occupational dose limit from external sources, does the licensee have to determine, record, and report doses from the effluents to comply with the revised Part 20? (b) If so, what are the

Q&A In-vivo measurements for an incoming worker could indicate that the worker's internal dose, as determined and recorded by the preceding licensee, was incorrect. What action would the NRC expect the current licensee to take

Q&A Is a licensee required to provide dosimeters to an individual during a planned special exposure (PSE) that would only be worn during the PSE? 10 CFR 20.1206 10 CFR 20.2105

Q&A Is it acceptable for regulatory purposes that occupational dose data that are being provided on a voluntary basis (i.e., the results of dose monitoring provided that is not required by regulation) be recorded and reported only in part? The purpose in asking this question is to establish whether or not the revised Part 20 provides the flexibility for licensees to record and report the results of "monitoring performed but not required" without

Q&A Is it necessary to document that employees have been advised of their annual doses? Is it sufficient to let employees see the results of the monitoring? Does posting doses on a bulletin board in a common area, each month, fulfill this requirement?

Q&A Is it permissible under 10 CFR Part 20 for a licensee to have a controlled area that is controlled for purposes of radiation protection but that is not a restricted area?

Q&A Is it possible to obtain copies of revised NRC "inspection modules" for inspection for compliance with the revised regulation? How may these be obtained?

Q&A Is it time to update Regulatory Guide 1.109 and its corresponding codes due to the updated dose conversion factors in the revised Part 20?

Q&A Is the licensee required to advise personnel of the provisions for declaring pregnancy, who work in the controlled area, have been classified as "members of the public," and do not "work in or frequent" any restricted area?

Q&A Is the licensee required to use the most accurate method for determining compliance with dose limits or is it allowable to use any one of the acceptable methods (assuming the acceptable method yields the lower dose)?

Q&A Is the spent fuel pool, when containing irradiated fuel, required to be posted and controlled as a Very High Radiation Area under any of the following circumstances: a. When there are no activities underway involving the spent fuel pool? b. When underwater manipulation of irradiated fuel or other irradiated hardware is underway? 10 CFR 20.1003 10 CFR 20.1602

Q&A It appears that some of the oral ingestion ALIs in Appendix B of 10 CFR 20 are sometimes associated with the wrong chemical forms; is this the case?

Q&A Licensee A questions a new employee about outside employment. The employee states that he is only working at that facility. After 3 months, the employee starts working, in the evenings, at another licensed facility (Licensee B). The employee does not tell A about B; therefore, Licensee A does not take the exposure received by the employee at facility B into account when he calculates the employees annual total effective dose equivalent (TEDE).

Q&A Licensees are required to "reduce the dose that an individual may be allowed to receive in the current year by the amount of occupational dose received while employed by any other person." How should this provision be applied to dose categories required to be monitored by the current licensee, for which the individual's dose report (e.g., NRC Form 5) from previous employment during the current year at another licensee's facility indicates "NR" (not 10 CFR 20.1201 10 CFR 20.2104

Q&A Licensees are required to "secure from unauthorized removal or access" licensed materials in storage, and to "control and maintain constant surveillance" of licensed materials not in storage, in controlled or unrestricted areas. The following questions relate to the security and control of licensed materials in controlled areas only, i.e., the questions are not intended to address unrestricted areas: 10 CFR 20.1003 10 CFR 20.1801 10 CFR 20.1802

Q&A Many existing reactor Technical Specifications require commercial power plant licensees to provide statistical personnel dose summary to NRC annually. The old Part 20 contained provisions for such reports, but no corresponding requirement carried over to the revised rule. Why? 10 CFR 20.2206

Q&A May the codes "ND" (not detectable), "NR" (not required), and "NC" (not calculated) be used more generally in the radiation dose data blocks on the NRC Forms 4 and 5 than is implied by the instructions on the forms? The purpose in asking this question is to clarify the guidance for filling out the forms provided in the regulatory position and in the instructions on the reverse side of the NRC Forms 4 and 5. The Form 5 instructions appear to limit 10 CFR 20.2104 10 CFR 20.2106

Q&A Must bioassay be performed for a worker who, without respiratory protection, is likely to receive an intake in excess of the applicable ALI(s) but who is not likely to receive such an intake with respiratory protection? 10 CFR 20.1502

Q&A Must doses received in excess of the limits that were in effect before implementation of the revised Part 20 be subtracted from the 25-rem lifetime allowance for planned special exposures to obtain the total remaining dose available for planned special exposures? 10 CFR 20.1201 10 CFR 20.1206 10 CFR 20.2104

Q&A Note 2 of Appendix B provides criteria for determining the appropriate derived air concentration (DAC) for a mixture of radionuclides where "the identity of each radionuclide in the mixture is not known, but it is known that certain radionuclides are not present in the mixture." In 20.1204, Determination of Internal Exposure, provisions are made to disregard the concentration of any radionuclide that is less than 10% of its DAC so 10 CFR 20 Appendix B 10 CFR 20.1202

Q&A NRC Form 5 (Item No. 10) provides for listing of specific radionuclides in intakes that contribute to the recorded committed effective dose equivalent (CEDE). When determining the CEDE only significantly irradiated organs need be included in the calculations [10 CFR 20.1202(b)(3)]. An organ is considered to be significantly irradiated if the product of the weighting factor and committed dose equivalent, per unit intake, is greater than 10 CFR 20.2106 10 CFR 20.2206

Q&A NRC Form 5 (Item No. 10) provides for reporting of individual radionuclides involved in an intake. How does the NRC plan on using this data (i.e., what is the NRC's purpose in collecting this data)? 10 CFR 20.2106 10 CFR 20.2206

Q&A NRC Form 5 (Item No. 10B) includes the symbol "V", which is not defined in Regulatory Guide 8.7, Revision 1. (a) Does the "V" signify "vapor" as used in Federal Guidance Report No. 11? (b) If so, how is this lung clearance class to be applied in operational air sampling and internal dosimetry programs? 10 CFR 20.2106 10 CFR 20.2206

Q&A NRC Form 5 (Item No. 20) provides for the signature of the licensee's authorized representative responsible for the data and is not noted as "optional" as is the licensee signature block on NRC Form 4. Appendix A of Regulatory Guide 8.7, Rev. 1, "Instructions for Recording and Reporting Occupational Radiation Exposure Data," provides for the licensee to sign the transmittal letter for electronic transmission of exposure data to the NRC and 10 CFR 20.2106 10 CFR 20.2206

Q&A NRC Form 5 (Item No. 21, "Comments") implies that dose from a "hot particle" should be added to the shallow dose equivalent, maximum extremity (SDE, ME - Block 14). However, IE; Notice 90-48 states that "hot particle exposure will not be added to skin doses from sources other than hot particles." (a) Should hot particle doses be added to the shallow dose equivalent as implied? (b) If so, should this dose be subtracted from the applicable dose 10 CFR 20.2106 10 CFR 20.2206

Q&A Nuclear power plant licensees are required to meet the criteria in 10 CFR 50 Appendix I and 40 CFR 190 with regards to maintaining doses to individual members of the public ALARA. Related Regulatory Guides (e.g., 1.21, 1.109, and 4.1) describe programs which are acceptable to the NRC staff to demonstrate compliance with 10 CFR 50 Appendix I and 40 CFR 190 criteria. Specific requirements for monitoring, sampling, dose calculation and 10 CFR 20.1301

Q&A Nuclear power plant licensees are required to meet the quality assurance criteria in 10 CFR Part 50 Appendix B. Regulatory Guide 1.33 describes a program acceptable to the NRC staff to demonstrate compliance with 10 CFR 50 Appendix B requirements and includes guidance regarding the documentation, use of procedures and periodic review of radiation protection programs. Does commitment to and conformance with 10 CFR Part 50 Appendix B and Regulatory

Q&A Part 20 requires that "labelled packages" be monitored. Is it correct to assume that only packages with White I, Yellow II, or Yellow III labels must be monitored, and that marked packages (LSA or radioactive markings) are not required to be monitored?

Q&A Part 50 license standard technical specifications define "Dose Equivalent I-131" as "...that concentration of I-131 (microcurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present..." and "the thyroid dose conversion factors used for this calculation shall be those listed in NRC Regulatory Guide 1.109." (a) After implementation of the revised 10 CFR Part 20,

Q&A Pertaining to 19, will 10 CFR 50 Appendix I and Technical Specifications have to be modified to reflect a total effective dose equivalent (TEDE)? 10 CFR 50 Appendix I

Q&A Question 373 concerns the minimum requirements for height and access restrictions of barriers used to prevent entry to locked high radiation areas (HRAs) and very high radiation areas (VHRAs) at nuclear power plants. Does this question and answer also apply to non-power reactors? 10 CFR 20.1601

Q&A Question 397 concerns a reporting requirement in "reactor technical specifications." Does this , and the answer provided, apply to non-power reactors?

Q&A Questions 376 and 389 in section 10 CFR 20.2001 concern the use of the "decay in storage" option of 10 CFR 20.2001(a)(2) at nuclear power plants and at materials facilities. However, it is not clear whether or not these questions and answers also apply to non-power reactor facilities. How can this option be used at non-power reactor facilities?

Q&A Regulatory Guide 8.25 (Section C.1.7) states that "to determine whether the concentration exceeds the DAC over the short term, the sample collection time should not exceed one hour. Shorter sample collection times may be used if desired, but they are not required." a.) Does this section mean to imply that the duration of a work zone air sample should not exceed one hour if it may be used to determine whether an area needs to be posted or 10 CFR 20.1902

Q&A Regulatory Guide 8.36, "Radiation Dose to the Embryo/Fetus," (Section C.1.3) states that "the determination of external dose should include all occupational exposures of the declared pregnant worker since the estimated date of conception."(a) If declared pregnant worker has received occupational dose during this pregnancy while working for a previous licensee, is it intended that the dose from the previous licensee be obtained and included in estimating

Q&A Regulatory Guide 8.7 (Section C.2.2) states that "if during the course of the year the dose to date for the year exceeds 1 rem CEDE [committed effective dose equivalent] or the individual receives an overexposure in another dose category, the CDE [committed dose equivalent] to the maximally exposed organ must be calculated, recorded and reported." If an individual arriving from work at another (previous) licensee's facility within the current 10 CFR 20.1502

Q&A Relative to 10 CFR 20.1101, radiation protection programs, what would a typical radiography licensee have to do beyond what that licensee is doing now?

Q&A Reports of planned special exposures (PSEs) are required by 10 CFR 20.2204 to be submitted within 30 days of the PSE to the NRC Regional Office. Complete records of PSEs are required to be maintained in accordance with 10 CFR 20.2105 and the monitoring results for PSEs should be recorded on NRC Form 5 or equivalent in accordance with the guidance in Regulatory Guide 8.7, Revision 1. (a) Are the PSE dose reports also required to be submitted to 10 CFR 20.1206 10 CFR 20.2204 10 CFR 20.2206

Q&A Representatives of the nuclear power industry are concerned that the additional terms provided in the revised rule to describe the "real estate" in and around commercial power plants seems to be overlapping. This could lead to confusion. Access to these various areas may also affect the category to which individuals working within these areas are assigned. At nuclear power plants, either the "protected area" or "radiation controlled area" may serve as the 10 CFR 20.1003

Q&A Representatives of the nuclear power industry have expressed a concern regarding 10 CFR 20.1502, which requires licensees to monitor individual internal or external doses for each individual likely to exceed 10% of the applicable annual limit. Licensees are required to maintain records of individuals for whom monitoring was required under 20.1502 [ 20.2106(a)]. The handling of internal doses at less than 10% of the limit is of particular 10 CFR 20.1502

Q&A Section 20.105(a) of 10 CFR Part 20 provides for Commission authorization of radiation levels in unrestricted areas based on a criterion of 500 millirems in one year to an individual in such areas. Does such an authorization for radiation levels in an unrestricted area that could result in a dose to a member of the public in excess of 100 millirems in a year continue under 10 CFR 20.1301(c)? In other words is this considered an "exemption" as 10 CFR 20.1008

Q&A Should radioactive noble gas concentrations be excluded (a) with regard to evaluating and posting Airborne Radioactivity Areas and (b) in determining Derived Air Concentration-hours (DAC-hours)? The definition of Airborne Radioactivity Area refers to areas where airborne radioactivity concentrations exceed the DAC values or where an individual could exceed 12 DAC-hours in a week. DAC is defined as the "concentration of a specific 10 CFR 20.1003

Q&A Should the Radiation Protection Program be a stand-alone document or can it be the sum of many documents or manuals (e.g., a requirement for HP audits included as part of a QA audit program document)?

Q&A Since the posting requirements are all in terms of deep dose equivalent, what requirements should be followed when posting for low energy beta radiation? 10 CFR 20.1901

Q&A Since the technical specification "exemptions" for nuclear power reactors already apply to locking of high radiation areas, does this "exemption" continue to apply pursuant to 10 CFR 20.1008(d) if a 45-cm (18-inch) survey distance is specified (in technical specifications) versus the rule's 30-cm distance (10 CFR 20.1601(a))? 10 CFR 20.1601 10 CFR 20.1602

Q&A Some licensees have established administrative dose control levels or guidelines, below regulatory dose limits, as a tool to support supervisory and management involvement in dose minimization. Procedures commonly describe certain review actions to be taken at successive dose levels, with a higher level of management involvement at higher dose levels. If an administrative dose control level or guideline is exceeded without all of the described actions

Q&A Some Part 50 power reactor licensees have developed "weighted" or "effective" derived air concentration (DAC) values for airborne mixtures of radionuclides, on the basis that the mixtures are well known and relatively stable, as demonstrated through periodic analysis of primary sources (e.g., reactor coolant and other process fluids), airborne and removable contamination samples, and waste streams (i.e., 10 CFR 61 analysis). These 10 CFR 20 Appendix B 10 CFR 20.1203 10 CFR 20.1204 10 CFR 20.1501 10 CFR 20.1502

Q&A Standard Technical Specification (STS) 6.12 for nuclear power reactors provides methods for control of access to high radiation areas that are alternatives to the methods specified in a CFR Part 20. Power reactor licensees that have adopted this technical specification are required to provide additional controls for access to high radiation areas with dose rates greater than 1 rem/h in addition to the controls required for access to high 10 CFR 20.1601 10 CFR 20.1602

Q&A Table 1004(b).2 does not include entries for "cold" neutrons, (e.g., 7 x 10E-9 MeV neutrons) which are used in experiments at some research reactor facilities. What values of the quality factor, Q, and the fluence per unit dose equivalent should be used for "cold" neutrons?

Q&A The "Class" column of 10 CFR 20 Appendix B covers inhalation, but does not refer to ingestion. When there are two ALIs for ingestion, how do these relate to the "Class," since they really were based upon the f1 value for gut absorption? (Note: The f1 value is the fractional uptake from the small intestine to blood). 10 CFR 20 Appendix B

Q&A The Appendix B tables of the revised Part 20 include ALIs and DACs for daughter radionuclides, in contrast to the Appendix B tables in the "old" Part 20, which do not include these daughter radionuclides. For example, ALIs and DACs for rubidium-88 and cesium-138 are listed. Are the listed ALIs and DACs expected to be considered separately with regard to posting and other requirements in the revised Part 20?

Q&A The conforming amendment to 10 CFR 50.73(a)(2) states that reports submitted in accordance with 10 CFR 50.73(a)(2)(viii) also meet the effluent release reporting requirements of 10 CFR 20.2203(a)(3). However, 10 CFR 20.2203(a)(3) requires reporting of concentrations in an unrestricted area of 10 times any applicable limit in Part 20 while 10 CFR 50.73(a)(2)(viii) requires reports of airborne or liquid effluent releases that exceed 10 CFR 20.2203

Q&A The definition of a very high radiation area (10 CFR 20.1003) and the requirement for control of access to very high radiation areas specify an absorbed dose of 500 rads in an hour. Is this a deep dose, a shallow dose, or an eye dose? 10 CFR 20.1003

Q&A The Department of Energy (DOE) does not assign a 50-year dose commitment in the year of intake for its workers exposed to internally deposited radioactive material. The internal dose is assigned on an annual basis. Will commercial nuclear power plant licensees be required to assess internal 50-year dose commitment for workers coming from DOE facilities? Some radionuclides encountered at DOE facilities may be beyond the normal 10 CFR 20.1204

Q&A The dose limits for an individual member of the public as specified in 10 CFR 20.1301 are specified in terms of rem. Since rem is an absorbed dose, must an individual be present for the dose limit to apply? 10 CFR 20.1301

Q&A The following question concerns OMB approval of the information collection requirements of the revised Part 20. Section 20.1008 indicates that licensees shall implement the provisions of all sections of revised Part 20 on or before January 1, 1993 and that if a licensee chooses to implement revised Part 20 before then, the licensee shall implement all provisions of revised Part 20 not otherwise exempted by subsection 20.1008(d). However, 10 CFR 20.1008

Q&A The following question relates to the requirements of 10 CFR 20.2104(a)(2), 10 CFR 20.2104(c), and 20.2104(d) concerning records of lifetime cumulative occupational dose. Assuming that (1) the licensee has obtained, by electronic media, a printed report (or reports) containing the Form 4 information on an individual's lifetime cumulative dose, (2) the individual who received the dose signed Form 4, or equivalent, in accordance with 10 CFR 20.2104(d), and (3)

Q&A The following questions concern the relationship of emergency plans for nuclear power plants to 10 CFR 20.1001 ("Purpose") and 10 CFR 20.1101 )"Radiation Protection Programs"). (a) To what extent do radiation protection programs need to be established such that during emergency conditions, the revised Part 20 can be complied with? (b) For example, in order to comply with the new EPA "Manual of Protective Actions For Nuclear Incidents" October 15, 1991, do germanium 10 CFR 20.1001

Q&A The following questions refer to the selection and use of a half-mask face piece, as described in Appendix A, "Protection Factors for Respirators": a. Footnote "g" of Appendix A states that "this type of respirator is not satisfactory for use where it might be possible (e.g., if an accident or emergency were to occur) for ambient airborne concentrations to reach instantaneous values 10 CFR 20

Q&A The following s concern the requirements of 10 CFR 20.1502 as applied to nuclear power plants. (a) Since the nuclear power industry has had few intakes approaching the 10% criteria for adding internal and external doses, is the historical record of intakes plus the establishment of a corporate (licensee) policy to limit intakes to less than 10% of an ALI sufficient to exclude a

Q&A The licensee initially was required to monitor internal dose. The results indicate that monitoring is not required, i.e., levels are positive but less than 10% of the allowable limits. Can the measured internal dose values be ignored? If yes, will the licensee be in noncompliance if it sums internal and external doses?

Q&A The NRC Form 5 (Item No. 8) provides for entry of multiple NRC license numbers. Some licensees may hold multiple licenses and provide common monitoring (e.g., a single set of dosimeters) for personnel working under any or all of the licenses. In such cases, it is proposed that only a single NRC Form 5 would be generated for each individual, listing all licenses under which they were monitored under 20.1502. Is this acceptable to satisfy 10 CFR 20.2106 10 CFR 20.2206

Q&A The revised 10 CFR 20 includes a new provision that allows disposal of licensed material "...by decay in storage..." What criteria should be used in implementing this provision? Is the NRC planning to develop generic guidance for "decay in storage"?

Q&A The revised Part 20 ( 20.1003) provides definitions of "member of the public," "public dose," and "occupational dose." These definitions are not consistent with the definition of "member(s) of the public" defined (for nuclear power plants) in Generic Letter 89-01, Supplement 1 (NUREGs 1301 and 1302). Consider that typically, one would expect any individual entering the "restricted area" would 10 CFR 20.1003 NUREG-1301

Q&A The rule provides for disregarding certain radionuclides in a mixture of radionuclides in air if three conditions are met. The conditions are: a. The licensee uses the total activity of the mixture in demonstrating compliance with occupational dose limits and monitoring requirements;

Q&A The rule requires that "the assigned deep-dose equivalent... must be for the part of the body receiving the highest exposure. [The dose] may be assessed from surveys or other radiation measurements for the purpose of demonstrating compliance with the occupational dose limits, if the individual monitoring device was not in the region of highest potential exposure." In the event of a hot particle exposure to a portion of the whole body, it is

Q&A The term "not present," which is defined in paragraph 5 of the Note (concerning mixtures of radionuclides) following Appendix B of the old Part 20, is not defined in the corresponding "Note" in the revised Part 20. Does this definition from the old Part 20, which indicates when a radionuclide may be considered as not present in a mixture, continue to apply in the revised Part 20? 10 CFR 20 Appendix B

Q&A The word "external" in 10 CFR 20.1302(b)(2)(ii) refers to any radiation source which could irradiate an individual from outside the body. Since sources include both airborne radioactive materials and contained sources, the dose from airborne radioactive materials could be double-counted -- as a concentration pursuant to 10 CFR 20.1302(b)(2)(i) and as direct radiation pursuant to 10 CFR 20.1302(b)(2)(ii). In a situation where the licensee was approaching the 10 CFR 20.1301

Q&A The words, "e.g., containment or ventilation," have been added to 10 CFR 20.1701. Does this mean that increased emphasis is being placed on glove bags to do valve replacements, repacks, etc. at nuclear power plants?

Q&A There has been some confusion about the revised Part 20 requirements with respect to controlled areas and when individuals are receiving a public or an occupational dose. Before asking s involving specific exposure scenarios (in parts b, c, and d of this question), does the NRC staff have any general guidance on these topics? 10 CFR 20.1003 10 CFR 20.1101 10 CFR 20.1201 10 CFR 20.1207 10 CFR 20.1208

Q&A This question concerns demonstration of compliance with the dose limits for individual members of the public. Section 20.1302(b), in the revised 10 CFR Part 20, permits the licensee to demonstrate compliance by: 1 "Demonstrating by measurement or calculation that the total effective dose equivalent to the individual likely to receive the highest dose 10 CFR 20.1302

Q&A This question concerns radioactive effluent concentrations. 10 CFR 20.1302(b)(2) addresses the annual average concentrations, and limits on these concentrations, as they apply to members of the public. The changes published as conforming amendments to Part 2 uniformly address violations to these effluent limits as instantaneous values. While it is clear that significant instantaneous concentrations of these limits constitute a concern to public safety, the

Q&A This question concerns restricted area limitations. At some sites for nuclear power plants the restricted area has been defined as the site boundary. In some areas routine public access was available with the understanding that, should the need arise, public use of these areas could be prohibited. Examples of this type of access include fishing, visitor centers, and farming. This type of use now appears to fall within the intent of the 10 CFR 19.12 10 CFR 20.1003 10 CFR 20.1201 10 CFR 20.1206 10 CFR 20.1207

Q&A This question concerns water approaches to nuclear sites. Several sites for nuclear power plants include portions of navigable lakes or rivers within their licensed exclusion areas. Obviously, the utility does not own these areas. Would such boundaries as defined in our licenses qualify as restricted areas, controlled areas, or unrestricted areas?

Q&A This question refers to Question 95 under 10 CFR Part 19 and 81 under 10 CFR 20.1502. Clearly there is a significant population of occupationally exposed persons in unrestricted areas of whom the licensee has no knowledge. Even among their own employees, the licensed operation may be a small segment of the whole organization where license management treats the rest of the organization as general public. So presumably, the general principle of

Q&A This question refers to the answer to Question 26(b) under 20.1003. What is the basis for using a dose threshold to decide whether a person is categorized as a member of the public or as occupationally exposed? The definitions do not specify a dose threshold.

Q&A This question refers to the answer to Question 29 under 20.1302. The statement that a licensee can require members of the public to exit a controlled area at any time is not obvious, based on the published rule. A controlled area is one to which access can be limited, but that condition might exist only at certain times or under certain conditions or the access limits might be of a nature other than strict prohibition. For instance, it might be a 10 CFR 20.1003

Q&A This question refers to the answer to Question 37 in "Conforming Changes: 10 CFR Part 19." I sincerely hope that the NRC will encourage licensees to simply file a memo to the effect that these reports were done. Otherwise, the volume of paper will be ridiculous.

Q&A This question refers to the answer to Question 41 under 20.1201. This answer leaves open what is an acceptable frequency for querying monitored workers. This is only an issue of monitored workers, isn't it? In the interest of workload minimization, I suggest that an annual query/reminder along with the required annual 10 CFR 19 dosimetry report is adequate.

Q&A This question refers to the answer to Question 55 in 20.2104. (a) Despite the quoted reference, 20.2104 only refers to occupational radiation dose (why radiation when the defined term is occupational dose?), which is defined in terms of "dose." (b) The definition of dose does not include eye, shallow, or extremity doses. What is the regulatory basis for including eye, shallow, and extremity doses within the scope of 20.2104 where it is so 10 CFR 20.1003

Q&A This question refers to the answer to Question 6 20.1201. This answer does not directly answer the implied question, which is, "if a person is assessed a history of 5 rem or more for the current year, is that person permitted to receive any occupational dose?" Implied in the answer is that if monitoring is not required, that person can receive an occupational dose, presumably up to 500 mrem for 10 CFR 20.1201

Q&A This question refers to the answer to Question 84 under 20.1208. It has also been asserted that the declared pregnant woman (DPW) declaration can be prospective. Are there any limits on how frequently or how long a duration a person can declare they are in a DPW, e.g., 10 years? 10 CFR 20.1003

Q&A This question refers to the answer to Question 91 in 20.1703. Please clarify this response, as indicated below. (a) Can NRC envision any purpose by which a licensee can use respiratory protection devices without having an approved respiratory protection program, e.g., meeting the provisions of 20.1703?

Q&A This question refers to the answers to Questions 66 and 31 under 20.1003 and 20.1201, respectively, and to Question 26(d) under 20.1003. Simply designating an area as a restricted area so you can control everyone at occupational dose limits is a perversion of every radiation protection principle published. Of course, this is just my opinion. I hope NRC will revise its interpretation of this definition. 10 CFR 20.1003

Q&A Under 10 CFR 19.12, what is the minimum training that licensees must provide to visitors who will enter a restricted area (where the occupational dose limits apply)?

Q&A Under 10 CFR 20.1302(b)(2)(ii), (a) do the words, "If an individual were continually present in an unrestricted area," mean that under these provisions it should be assumed a hypothetical individual is there, or (b) should occupancy studies be made in applying this section?

Q&A Under 20.1703(d), licensees must notify the NRC Regional Director at least 30 days prior to first using respiratory protection equipment pursuant to 20.1703(a) or (b). All current respiratory protection programs have been documented under the provisions of 20.103(g) which contains equivalent language. Do licensees need to "re-notify" NRC if such notification has already taken place under the "old" Part 20?

Q&A Under what circumstances are planned special exposures permitted?

Q&A What are the applicable radiation limits in a controlled area if the licensee does not allow members of the public to enter the area? 10 CFR 20.1003

Q&A What are the minimum requirements for height and access restrictions of barriers used to prevent entry to locked high radiation areas (HRAs) and very high radiation areas (VHRAs) at nuclear power plants? 10 CFR 20.1601

Q&A What are the requirements for including dose from non-NRC-licensed sources (x-rays, accelerators, NORM) as part of occupational dose? 10 CFR 20.1001 10 CFR 20.1002 10 CFR 20.1003

Q&A What do you do about hot particles? 10 CFR 20.1201

Q&A What is the dose limit for a member of the public in a restricted area?

Q&A What is the dose limit for visitors entering a restricted area (e.g., visitors to a hospital, patients' relatives, escorted tourists)?

Q&A What is the specific scope of the reports required to be provided to workers in accordance with the various provisions of 10 CFR Part 19.13? The provisions in question are as follows: a. Part 19, 19.13(b) requires that licensees provide reports to workers annually of dose as shown in records maintained by the licensee. Is the monitoring period covered by this section 10 CFR 19.13

Q&A What monitoring period should be used in annual individual monitoring reports submitted, in accordance with 10 CFR 20.2206, following the first year of revised 10 CFR Part 20 implementation, if the period of implementation did not encompass the full year? For example, if a licensee implements the revised 10 CFR Part 20 on July 1, 1993, is the licensee required to provide annual individual monitoring reports early in 1994 that cover the entire year,

Q&A When monitoring of internal exposure is required by 10 CFR 20.1502, 10 CFR 20.1204(a) requires the licensee to take "suitable and timely" measurements. Will NRC define what is suitable and timely to avoid differences of opinion among inspectors? 10 CFR 20.1204

Q&A When will licensees be permitted to use weighting factors other than one to determine and record external whole body dose (effective dose equivalent from external sources) as the occupational dose of record?

Q&A Why does the revised Part 20 still require Form 4? 10 CFR 20.2104

Q&A Why is it that releases to sanitary sewers are not included in the dose limit for members of the public while other effluent releases are?

Q&A Why was a 2-hour half-life chosen as a time of reference for noble gases or short-lived radionuclides, as used in 10 CFR Part 20, Appendix B and its footnotes?

Q&A Why was the "controlled area" defined?

Q&A Will all of the libraries of reference data and the procedures for gamma-ray spectrometry software or appendices that contain 10 CFR Part 20 MPCs have to be changed?

Q&A Will certain materials licensees (such as teletherapy and brachytherapy licensees) be required to conduct environmental monitoring in unrestricted areas to demonstrate compliance with the new dose limit for individual members of the public? 10 CFR 20.1302

Q&A Will consultants or vendors be able to routinely come on site to do jobs under the Planned Special Exposure section of the revised Part 20 if their annual exposure becomes limiting? 10 CFR 20.1003

Q&A Will determination of the "eye dose equivalent," at a tissue depth of 300 mg/square cm, be included in the NVLAP personnel dosimetry accreditation program?

Q&A Will each NRC region hold orientation meetings for licensees on the revised regulation? When and where might these occur?

Q&A Will QA Category 1 requirements discussed in Regulatory Guide 1.26 have to be changed due to offsite dose requirements of 0.5 rem being changed to 0.1 rem in the revised Part 20?

Q&A Will Regulatory Guide 10.8 be revised to include guidance on monitoring external dose (and demonstrating compliance with the annual occupational dose limits) for health personnel working in several hospitals simultaneously? [Note: This is a common practice for physicians in Hawaii and there is no good mechanism for licensees to track where the physicians work outside the facility]

Q&A Will the annual reports that are required by power reactor technical specifications (reports that tabulate occupational exposures greater than 100 mrem/yr according to work and job functions) still be required after the revised Part 20 is implemented. 10 CFR 20.2206

Q&A Will the Emergency Action Levels (EAL) as part of the Emergency Plans have to be changed if based on the old Part 20 methodology? 10 CFR 50.47

Q&A Will the NRC provide guidance on preparation of applications pursuant to 10 CFR 20.1204 (c) (2) for approval to adjust DAC or ALI values to reflect the actual physical and chemical characteristics of airborne radioactive materials (e.g., aerosol size distribution or density)?

Q&A Will the numbering sequence of the revised regulation be changed once the "old" Part 20 expires?

Q&A Will the radiographers have to wipe test the sealed source upon receipt (10 CFR 20.1906(b)(1)) even if the manufacturer has performed a recent leak test on the source? 10 CFR 20.1906

Q&A Will the reporting criteria of 10 CFR 50.72 and 50.73 have to be changed? 10 CFR 50.72

Q&A Will workers who enter a restricted area and have been determined to require monitoring under 20.1502(a) require monitoring in the controlled area (outside the restricted area)? 10 CFR 20.1003

Q&A With 10 CFR 20.1101(b) making ALARA a requirement ("shall" instead of a "should"), does the NRC staff plan or anticipate any significant change in inspection program focus or in enforcement activity with respect to ALARA for occupational exposure at nuclear power plants?

Q&A Would a licensee be found to be in noncompliance with the limit for the dose to an embryo/fetus if, at the time the woman declared her pregnancy, the dose to the embryo/fetus exceeded 0.5 rem and the embryo/fetus subsequently received more than 0.05 rem from licensed material that was in the body of the woman before she declared her pregnancy.

Q&A Would areas periodically patrolled, but not constantly manned, be considered to fall within the exception in 10 CFR 20.2202(a)(2) and 20.2202(b)(2) for "locations where personnel are not normally stationed during routine operations, such as hot-cells or process enclosures?" For example, would these exceptions apply "if a hallway or cubicle in the reactor auxiliary becomes an airborne radioactivity area and auxiliary equipment operators make their rounds

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Radiology devices

Radionuclide Table Slope Factors - HEAST Table (April 16, 2001)

Radionuclide Table Slope Factor (Heast Table) User's Guide (April 16, 2001)

Radionuclides Notice of Data Availability Technical Support Document, March 2000

Radiopharmaceutical Vial Breakage During Preparation In94007

Radiopharmaceutical Vial Breakage During Preparation In95007

Radon - A Physician's Guide:

Radon in Schools

Radon Maps

Radon Measurement in Schools

Radon Measurement methods (brief summaries)

Radon Prevention in the Design and Construction of Schools and Other Large Buildings.

Radon Proficiency Programs

RCRA Groundwater Monitoring Draft Technical Guidance (November 1992).

Reactor site criteria 10 CFR Part 100

Recommended Approaches for Setting Radiological Control Limiting Conditions

Recent Contamination Incidences Resulting from Failure to Perform Adequate Surveys In98018

Recent Events Resulting in Extremity Exposures Exceeding Regulatory Limits In00010

Recent Events Resulting in Whole Body Exposures Exceeding Regulatory Limits In00015

Recent Failures of Control Cables Used on Amersham Model 660 Posilock Radiography Systems In97091

Recent Failures of Control Cables Used on Amersham Model 660 Posilock Radiography Systems, Supplement 1 In97091s1

Recent Findings Concerning Implementation of Quality Assurance Programs by Suppliers of Transport Packages In88062

Recent Fuel Handling Events In85012

Recent Incidents Involving Potential Loss of Control of Licensed Material In95051

Recent Incidents Resulting in Offsite Contamination In94016

Recent Medical Misadministrations Resulting from Inattention to Detail In0005

Recent Misadministrations Caused by Incorrect Calibrations of Strontium-90 Eye Applicators In96066

Recent Problems Involving the Model Spec 2-T Radiographic Exposure Device In88033

Recent Revisions to 10 CFR Part 20 and Change of Implementation Date to January 1, 1994 In93003

Recent Safety-Related Incidents at Large Irradiators In87029

Recent Safety-Related Incidents at Large Irradiators In89082

Recent Safety-Related Incidents at Large Irradiators In89082

Recent Safety-Related Incidents at Large Irradiators In91014

Recent Safety-Related Violations of NRC Require- ments by Industrial Radiography Licensees In87045

Recent Serious Violations of NRC Requirements by Medical Licensees In84027

Recent Serious Violations of NRC Requirements by Moisture Density Gauge Licensees In84026

Recent Serious Violations of NRC Requirements by Radiography Licensees In84025

Recent Serious Violations of NRC Requirements by Well-Logging Licensees In84028

Reciprocity: Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States In90015

Reconcentration of Radionuclides Involving Discharges Into Sanitary Sewage Systems Permitted Under 10 CFR 20.303 In84094

Record Retention at Ex-Licensee After a License has been Terminated HPPOS205

Records of Release of Materials from Radiological Areas TPP96-01

Redefinition of Restricted Area Boundaries to Exclude an Area to be used for Residential Quarters HPPOS251

Reducing Radon in Schools: A Team Approach.

Reducing Radon Risks

Regarding Diagnostic Misadministration Reporting Threshold Levels, Interpretation of 10 CFR 35.33(c) HPPOS270

Regarding Mediq Imaging, Inc., Providing Service to a Private Practice (Non-licensee) Located within a Hospital HPPOS320

Regarding Transfer of Control of a Corporation Holding NRC Licensees HPPOS124

Regulatory History of Mixed Waste

Regulatory Requirements When No Operations Are Being Performed In94021

Regulatory Responsibilities for Byproduct Materials in Non-Power Reactors HPPOS218

Relaxation of Definition of Source Check in Reference to Effluent Radiation Monitors HPPOS229

Release of Patients Administered Radioactive Materials (Draft DG-8015 published 6/1994) (Errata published 5/1997) RegGuide 8.39

Release of Patients Treated With Temporary Implants In92084

Reportability of Operating Event HPPOS222

Reporting Fuel Cycle and Materials Events to the NRC Operations Center In93060

Reporting Fuel Cycle And Materials Events To The Nrc Operations Center In93060s1

Reporting of Damaged Portable Moisture-Density Gauges HPPOS322

Reporting of defects and noncompliance 10 CFR Part 21

Reporting of Operating Information--Appendix A Technical Specifications (for Comment) RegGuide 1.16

Reporting of Radiological Releases In84015

Reporting Safety Concerns, Revision 1 NUREG 0240

Request for Clarification of Guidance Regarding Physicians Determination for Physical Qualification of Respiratory Equipment Users HPPOS103

Request for Collection of Licensee Radioactivity Measurements Attributed to the Chernobyl Nuclear Plant Accident In86032

Request for Collection of Licensee Radioactivity Measurements Attributed to the Chernobyl Nuclear Plant Accident In86032s1

Request for Comments on Responses to Licensee Questions on High Radiation Area Controls HPPOS237

Request for Guidance Concerning Use of NRC Certified Casks HPPOS152

Request for Interpretation of Applicability of DOT Regulations to NRC-Licensed State or Federal Entities HPPOS038

Request for Interpretation Regarding Licensee Recordkeeping HPPOS204

Request for NRR Follow-Up on Environmental Samples with Levels Greater Than FES Estimates HPPOS009

Request for Retraction of Violation by Dairyland Power Cooperative HPPOS130

Requests by Licensees that Women Inspectors Acknowledge Discriminatory Administrative Dose Limits Imposed on Them HPPOS252

Requests by Reactor Licensees That Women Inspectors Sign Statements That They are not pregnant HPPOS249

Requests to Dispose of Very Low-Level Radioactive Waste Pursuant to 10 CFR 20.302 In86090

Required Continuing Training Program for HP Professionals HPPOS247

Requirements for Import and Distribution of Neutron-Irradiated Gem In90062

Requirements for Processing Financial Assurance Submittals for Decommissioning In90038

Requirements for renewal of operating licenses for nuclear power plants 10 CFR Part 54

Requirements for Use of NRC-Approved Packages for Shipment of Type A Quantities of Radioactive Material In90082

Requirements in ANSI Standards vs. Facility Technical Specifications HPPOS109

Research and Test Reactors RegGuide, Division 2

Residual Contamination Remaining in Krypton-85 Handling System after Venting In96051

Resource Manual for Compliance Test Parameters of Diagnostic X-ray Systems (July 1999)

Respirator Coupling Nut Assembly Failures In86103

Respirator User Warning: Defective Self-Contained Breathing Apparatus Air Cylinder In84034

Respirator User Warning: Defective Self-Contained Breathing Apparatus Air Cylinders In83068

Respirator User's Notice - Use of Unapproved Subassemblies HPPOS147

Respirator Users Notice For Certain 5-Minute Emergency Escape Self-Contained Breathing Apparatus In84056

Respirator Users Notice: Defective Self-Contained Breathing Apparatus Air Cylinders In85048

Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders In86024

Respirator Users Warning for Certain 5-Minute Emergency Escape Self-Contained Breathing Apparatus In82036

Respiratory Protection 29 CFR Part 1910.134

Response to False Siren Activations In90034

Response to Inquiry Regarding Deletion of NRC Water Quality Requirements from Maine Yankee 12.9 12.13 Technical Specifications HPPOS111

Response to Questions Concerning Enforcement of 40 CFR 190, "EPA Uranium Fuel Cycle Standard HPPOS008

Response to Region II Interpretation for Control of High Radiation Areas HPPOS068

Restart of a Nuclear Power Plant Shut Down by a Seismic Event (Draft DG-1018 issued 11/1992, Draft DG-1035 issued 2/1995) RegGuide 1.167

Retrofit to Amersham 660 Posilock Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility In96053

Retrofit to Amersham 660 Posilock Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility In96053s1

Review and Approval of State and Local Radiological Emergency Plans and Preparedness

Review of Amendment Request From Boston University, 10 CFR 50.72 HPPOS209

Revised Decay-in-Storage Provisions for the Storage of Radioactive Waste Containing Byproduct Material

Revised Emergency Exercise Frequency Rule In85055

Revised Protective Action Guidance for Nuclear Incidents In92008

Revision of the Skin Dose Limit in 10 CFR Part 20 (NRC Regulatory Issue Summary 2002-10)

RPP Handbook

Rules of general applicability to domestic licensing of byproduct material 10 CFR Part 30

Rules of practice for domestic licensing proceedings and issuance of orders 10 CFR Part 2

Rupture of Americium-241 Source(s) Contained in a Well Logging Device In83032

Rupture of Cesium-137 Source Used in Well-Logging Operations In83074

Rupture of Nominal 40-Millicurie Iodine-125 Brachytherapy Seed Causing Significant Spread of Radioactive Contamination In86084

Rupture of Radwaste Tanks In79007

Safeguards on nuclear material--implementation of US/IAEA agreement 10 CFR Part 75

Safety and Security of Irradiators In83009

Safety Concerns Related to Repeated Control Unit Failures of the Nucletron Classic Model High-Dose-Rate Remote Afterloading Brachytherapy Devices In99023

Safety Defect in Gammamed 12I Bronchial Catheter Clamping Adapters In95050

Safety Evaluation of the Proposed Yankee Atomic Power Company's Modification of their Technical Specifications Relating to High Radiation HPPOS015

Safety Evaluations for Changes to Radioactive Waste Treatment System,10 CFR 20.201(b), s HPPOS086

Safety Significance and Discussion About Important matters HPPOS125

Salary offset procedures for collecting debts owed by Federal employees to the Federal government 10 CFR Part 16

Sampling Drywell Atmosphere Before a Release HPPOS170

Sampling Plans Used for Dedicating Simple Metallic/Commercial Grade Items for Use in Nuclear Power Plants RegGuide DG-1070

Scheduling of Pre-Licensing Emergency Preparedness Exercise In85041

Scope of Exemption in 10 CFR 20.303(d) for Disposal of Patient Excreta in Sanitary sewers HPPOS035

Sealed Radioactive Source Accountability and Control Guide IG 441.13

Security facility approval and safeguarding of national security information and restricted data 10 CFR Part 95

SECY-81-19 on Emergency Response Facilities HPPOS110

Segregation of Hazardous and Low-Level Radioactive Wastes In87003

Selection of Appropriate Enforcement Action for Gamma Diagnostic Laboratories, Inc. HPPOS154

Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants RegGuide DG-1076

Shipment of Contaminated Equipment Between Nuclear Power Stations In88101

Significant Finding, Big Rock Point Health Physics HPPOS023

Skylab Reentry In79018

Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1058 issued 8/1996) RegGuide 1.172

Software Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1056 issued 8/1996) RegGuide 1.170

Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants (Draft DG-1057 issued 8/1996) RegGuide 1.171

Soil and Water Contamination at Fuel Cycle Facilities In92011

Soil-to-Plant Concentration Ratios for Assessing Food-Chain Pathways in Biosphere Models

Solubility Criteria For Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 In94007

Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools In90033

Specific domestic licenses of broad scope for byproduct material 10 CFR Part 33

Specific domestic licenses to manufacture or transfer certain items containing byproduct material 10 CFR Part 32

Specific Gamma Ray Constants from Radiological Health Handbook (1970)

Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation (Draft FP 034-4 published 12/1980) (Second Draft CE 034-4 published 1/1983) (DG-3010, Proposed Revision 1, published 9/1997) RegGuide 3.54

Spent Nuclear Fuel and High-Level Radioactive Waste Transportation

Spill of Radioactively Contaminated Resin In79009

Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin RegGuide 1.72

Stabilization, Packaging, and Storage of Plutonium-Bearing Materials DOE-STD-3013-99

Staff Responses to Frequently Asked Questions Concerning Decommissioning of Nuclear Power Reactors (draft report for comment) NUREG 1628

Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities (Draft DG-3005 published 9/1990) RegGuide 3.67

Standard Format and Content for Post-Shutdown Decommissioning Activities Report RegGuide 1.185

Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites (Other than Nuclear Power Plants) (DG-5004, Proposed Revision 3, published 4/1994) RegGuide 5.52

Standard Format and Content of License Termination Plans for Nuclear Power Reactors RegGuide 1.179

Standard Review Plan for Dry Cask Storage Systems NUREG 1536

Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans NUREG 1700

Standard Review Plan for Spent Fuel Storage Facilities (Draft Report for Comment) NUREG 1567

Standard Review Plan for Transportation Packages for Radioactive Material, NUREG 1609

Standard Review Plan for Transportation Packages for Spent Nuclear Fuel (January 2000) NUREG 1617

Standard specifications for the granting of patent licenses 10 CFR Part 81

Standards applicable to generators of hazardous waste

Standards applicable to transporters of hazardous waste

Standards for owners and operators of hazardous waste treatment, storage, and disposal facilities

Standards for protection against radiation 10 CFR Part 20

Standards for the management of specific hazardous wastes and specific types of hazardous waste management facilities

Standards of performance for new stationary sources

State or Federal Regulations:Which do I use?

Statement of organization and general information 10 CFR Part 1

Statements of Intent by Government "Controlled" Entities HPPOS315

States and Territories where EPA regulates mixed waste

States and Territories with base RCRA hazardous waste program but not EPA mixed waste authorization.

States and Territories with EPA mixed waste authorization

Steam Generator Tube Integrity RegGuide DG-1074

SteriGenics International, Authorization to Increase the Limit on Pool Water Conductivity HPPOS299

Storage and Handling of Ophthalmic Beta Radiation Applicators In84043

Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use In94017

Suggested Guidance Relating to Development and Implementation of Corrective Action In96028

Supplement 1, "Fire Barrier Penetration Seals in Nuclear Power Plants" (Draft Report for Comment)" NUREG 1552

Supplemental Information on the Implementation of the Final Rule on Radiological Criteria for License Termination Federal Register Vol. 63, No. 222, 64132-64134, November 18, 1998

Supplemental Information on the Implementation of the Final Rule on Radiological Criteria for License Termination Federal Register Vol. 64, No. 234, 68395-68396, December 7, 1999.

Surface Radioactivity Values,10 CFR 835 Appendix D TPP 96-02

Surveys of Wastes Before Disposal From Nuclear Reactor Facilities In85092

Surveys of Wastes from Nuclear Reactor Facilities Before Disposal HPPOS073

Surveys, Final Rule - Effective November 20, 1981 10 CFR 20.201(b), HPPOS010

Systematic Radiological Assessment of Exemptions for Source and Byproduct Materials (June 2001)

Tables Of Radiation Absorbed Dose To The Embryo/Fetus From Radiopharmaceuticals. See Health Physics (73[5]:756-769, 1997).

Tamper-Indicating Seals for the Protection and Control of Special Nuclear Material (Draft DG-5005, Proposed Revision 1, published 1/1996) RegGuide 5.15

Technical Safety Requirements DOE Order 5480.22

Technology Shortfalls and Dose Determinations TPP 95-05

Teletherapy Events In88093

Teletherapy Unit Full