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Category:NUREG
MONTHYEARNUREG-1437, Dfc, Site-Specific Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 2, Second Renewal, Regarding Subsequent License Renewal for Oconee Nuclear Station Units 1, 2, and 32024-02-29029 February 2024 NUREG-1437 Dfc, Site-Specific Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 2, Second Renewal, Regarding Subsequent License Renewal for Oconee Nuclear Station Units 1, 2, and 3 ML23355A1432024-01-17017 January 2024 January 17, 2024 Public Meeting Handout - Fusion Systems Rulemaking NUREG-1556, November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule2023-10-31031 October 2023 November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule ML23303A2212023-10-31031 October 2023 NUREG/BR-0096, Revision. 2, Instructions and Guidance for Completing Physical Inventory Summary Reports - NRC Form 327 Final Report NUREG-2266, Dfc, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels2023-08-31031 August 2023 NUREG-2266 Dfc, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels ML23123A3322023-06-0606 June 2023 SGI Pamphlet NUREG-1555, Dfc, Supp 1, Rev 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal2023-02-28028 February 2023 NUREG-1555 Dfc, Supp 1, Rev 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal NUREG-2183, Supplement 1, Environmental Impact Statement Related to the Operating License for the Shine Medical Isotope Production Facility Final Report2023-01-31031 January 2023 NUREG-2183, Supplement 1, Environmental Impact Statement Related to the Operating License for the Shine Medical Isotope Production Facility Final Report NUREG-2243, Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in Mckinley County, New Mexico2023-01-31031 January 2023 NUREG-2243, Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in Mckinley County, New Mexico ML22299A2382022-10-31031 October 2022 NUREG-2237, Supplement 1, Environmental Impact Statements for Holtec Internationals License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico NUREG-2248, Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina. Final Report2022-07-31031 July 2022 NUREG-2248, Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina. Final Report ML22181B0942022-07-31031 July 2022 NUREG-2237, Environmental Impact Statement for the Holtec International'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico Final Report NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance2022-07-29029 July 2022 NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance ML22175A2022022-06-30030 June 2022 NUREG/BR-0058, Rev. 5, Appendix K Monetary Valuation of Nonfatal Cancer Risk for Use in Cost-Benefit Analysis Dfc ML22175A2032022-06-30030 June 2022 NUREG/BR-0058 Dfc, Rev. 5, Appendix L Replacement Energy Costs NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material2022-03-31031 March 2022 NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material ML22042A1162022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Draft NUREG 1021, Rev 13, Operator Licensing Examination Standards for Power Reactors ML21209A9552021-07-31031 July 2021 NUREG-2239, Environmental Impact Statement for Interim Storage Partners Llc'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas Final Report ML21096A2922021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix F Data Sources - Dfc ML21096A2932021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix G Regulatory Analysis Methods and Data for Nuclear Facilities Other than Power Reactors - Dfc ML21096A2942021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix H Severe Accident Risk Analysis - Dfc ML21096A2952021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix I National Environmental Policy Act Cost-Benefit Analysis - Dfc ML21005A1532020-12-31031 December 2020 NUREG/BR-0520, State Programs at the U.S. Nuclear Regulatory Commission NUREG-2242, Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 - Draft for Comment2020-12-31031 December 2020 NUREG-2242, Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 - Draft for Comment NUREG-1556 Volume 20, Rev. 1, Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures Final Report2020-11-30030 November 2020 NUREG-1556, Vol. 20, Rev. 1, Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures Final Report NUREG-2224, Dry Storage and Transportation of High Burnup Spent Fuel2020-11-30030 November 2020 NUREG-2224, Dry Storage and Transportation of High Burnup Spent Fuel NUREG-1507, Rev. 1, Minimum Detectable Concentrations with Typical Survey Instruments for Various Contaminants and Field Conditions2020-08-31031 August 2020 NUREG-1507, Rev. 1, Minimum Detectable Concentrations with Typical Survey Instruments for Various Contaminants and Field Conditions NUREG-2216, Review Plan for Transportation Packages for Spent Fuel and Radioactive Material2020-08-31031 August 2020 NUREG-2216 Review Plan for Transportation Packages for Spent Fuel and Radioactive Material ML20178A4332020-06-30030 June 2020 NUREG-BR-0204,Revision 3, Instructions for Completing the U.S. Nuclear Regulatory Commission'S Uniform Low-Level Radioactive Waste Manifest - Final Report ML20122A2202020-05-31031 May 2020 NUREG-2239 Dfc, Environmental Impact Statement for Interim Storage Partners Llc'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas ML20321A0972020-04-30030 April 2020 Chapter 3 - Principal Design Criteria Evaluation ML20321A0892020-04-30030 April 2020 Appendix 4A - Computational Modeling Software Technical Review Guidance ML20321A0982020-04-30030 April 2020 Chapter 4 - Structural Evaluation ML20321A0992020-04-30030 April 2020 Chapter 5 - Thermal Evaluation ML20321A1002020-04-30030 April 2020 Chapter 6 - Shielding Evaluation ML20321A1012020-04-30030 April 2020 Chapter 7 - Criticality Evaluation ML20321A1022020-04-30030 April 2020 Chapter 8 - Materials Evaluation ML20321A1122020-04-30030 April 2020 Chapter 17 - Technical Specifications Evaluation ML20321A1112020-04-30030 April 2020 Chapter 16 - Accident Analysis Evaluation ML20321A1102020-04-30030 April 2020 Chapter 15 - Quality Assurance Evaluation ML20321A1092020-04-30030 April 2020 Chapter 14 - Decommissioning Evaluation (SL) ML20321A1082020-04-30030 April 2020 Chapter 13 - Waste Management Evaluation (SL) ML20321A1072020-04-30030 April 2020 Chapter 12 - Conduct of Operations Evaluation ML20321A1062020-04-30030 April 2020 Chapter 11 - Operation Procedures and Systems Evaluation ML20321A1052020-04-30030 April 2020 Chapter 10B - Radiation Protection Evaluation for Dry Storage Systems (CoC) ML20321A1042020-04-30030 April 2020 Chapter 10A - Radiation Protection Evaluation for Dry Storage Facilities (SL) ML20321A0882020-04-30030 April 2020 Appendix a - Interim Staff Guidance (ISG) Incorporated Into NUREG-2215 ML20321A0902020-04-30030 April 2020 Appendix 4B - Pool and Pool Confinement Facilities ML20321A0922020-04-30030 April 2020 Appendix 8A - Clarifications, Guidance, and Expectations to ASTM Standard Practice C1671-15 ML20321A0932020-04-30030 April 2020 Appendix 8B - Fuel Cladding Creep 2024-02-29
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MONTHYEARInformation Notice 2023-06, Emergency Telecommunication Services Changes2023-12-0606 December 2023 Emergency Telecommunication Services Changes Information Notice 2023-05, Discontinuation of U.S. NRC Recognition of the American Board of Radiology'S Certification Processes2023-11-30030 November 2023 Discontinuation of U.S. NRC Recognition of the American Board of Radiology'S Certification Processes ML22272A0472022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DRO-ISG-2023-01 Operator Licensing Programs ML22272A0492022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DRO-ISG-2023-02 Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR Part 50.54 ML22272A0512022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53- DRO-ISG-2023-03 Development of Scalable Human Factors Engineering Review Plans ML21227A0052021-12-14014 December 2021 Draft Interim Staff Guidance COL-ISG-030 Advanced Reactor Application-Environmental Considerations for Advanced Nuclear Reactor Applications That Reference the Generic Environmental Impact Statement (NUREG-2249) Information Notice 2021-02, Recent Issues Associated with Monitoring Occupational Exposure to Radiation from Licensed and Unlicensed Radiation Sources2021-08-0404 August 2021 Recent Issues Associated with Monitoring Occupational Exposure to Radiation from Licensed and Unlicensed Radiation Sources ML21089A3642021-04-20020 April 2021 Yttrium-90 Microsphere Brachytherapy Sources and Devices Therasphere and SIR-Spheres Licensing Guidance Information Notice 2020-03, Recall of Mechanical Rate of Rise and Fixed-Temperature Heat Detectors2020-11-0505 November 2020 Recall of Mechanical Rate of Rise and Fixed-Temperature Heat Detectors Information Notice 2020-01, Increased Electronic Equipment Issues After Electrostatic Cleaning2020-09-0808 September 2020 Increased Electronic Equipment Issues After Electrostatic Cleaning ML19360A1872020-03-0606 March 2020 Document 3 - Supplemental Guidance for NUREG-1556, Volume 14, Revision 1, Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Well Logging, Tracer, and Field Flood Study Licenses ML19360A1862020-03-0606 March 2020 Document 2 - Supplemental Guidance for NUREG-1556, Volume 6, Revision 1, Consolidated Guidance About Materials Licenses: Program-Specific Guidance About 10 CFR Part 36 Irradiator Licenses ML19360A1852020-03-0606 March 2020 Document 1 - Supplemental Guidance for NUREG-1556, Volume 2, Revision 1, Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Industrial Radiography Licenses ML19304B3702020-01-22022 January 2020 Gammapod Licensing Guidance Information Notice 2019-12, Recent Reported Medical Events Involving the Administration of Yttrium-90 Microspheres for Therapeutic Medical Procedure2019-12-31031 December 2019 Recent Reported Medical Events Involving the Administration of Yttrium-90 Microspheres for Therapeutic Medical Procedure ML19204A2722019-11-0808 November 2019 Yttrium-90 Microsphere Licensing Guidance Revision 10 ML19240A3842019-08-26026 August 2019 Patient Skin Contamination Events Associated with I-131 Metaiodobenzylguanidine During Neuroblastoma Treatments Information Notice 2019-07, Methods to Prevent Medical Events2019-08-20020 August 2019 Methods to Prevent Medical Events Information Notice 2019-04, Effective Cyber Security Practices to Protect Digital Assets of Byproduct Materials Licensees2019-08-14014 August 2019 Effective Cyber Security Practices to Protect Digital Assets of Byproduct Materials Licensees Information Notice 2019-06, Potential Over-Pressurization of High Specific-Activity Alpha-Emitting Radioactivity Sources2019-08-14014 August 2019 Potential Over-Pressurization of High Specific-Activity Alpha-Emitting Radioactivity Sources ML18142A7712018-06-21021 June 2018 May 2018 NMSS Report on Rgs Periodic Reviews ML18057A3042018-05-31031 May 2018 Withdrawal Q and a 2018 Information Notice 2017-02, Best Practices Concepts for Patient Release2017-05-17017 May 2017 Best Practices Concepts for Patient Release Information Notice 2016-12, Regarding Potential Absence of Required Lock Washers in Bsi Instruments, Inc. LB 7400 Series Fixed Gauges2016-10-20020 October 2016 Regarding Potential Absence of Required Lock Washers in Bsi Instruments, Inc. LB 7400 Series Fixed Gauges Information Notice 2016-12, Regarding Potential Absence of Required Lock Washers in BSI Instruments, Inc. LB 7400 Series Fixed Gauges2016-10-20020 October 2016 Regarding Potential Absence of Required Lock Washers in BSI Instruments, Inc. LB 7400 Series Fixed Gauges Information Notice 2014-14, Potential Safety Enhancements to Spent Fuel Pool Storage2014-11-14014 November 2014 Potential Safety Enhancements to Spent Fuel Pool Storage Information Notice 2013-15, Willful Misconduct / Record Falsification and Nuclear Safety Culture2013-08-23023 August 2013 Willful Misconduct / Record Falsification and Nuclear Safety Culture Information Notice 2012-17, Certified Material Test Reports and Age Hardened Concrete Compressive Strength2012-09-0606 September 2012 Certified Material Test Reports and Age Hardened Concrete Compressive Strength Information Notice 2012-15, Use of Enclosures to Mitigate Leakage From Joints That Use A-286 Bolts2012-08-0909 August 2012 Use of Enclosures to Mitigate Leakage From Joints That Use A-286 Bolts Information Notice 2012-15, Use of Enclosures to Mitigate Leakage from Joints That Use A-286 Bolts2012-08-0909 August 2012 Use of Enclosures to Mitigate Leakage from Joints That Use A-286 Bolts Information Notice 2009-28, Summary of Fitness for Duty Program Performance Reports for Calendar Year 20082009-11-24024 November 2009 Summary of Fitness for Duty Program Performance Reports for Calendar Year 2008 Information Notice 2007-40, Inadequate Implementation of 10 CFR Part 21 Requirements by Vendors Who Supply Basic Components to Nuclear Power Plant Licensees2007-12-21021 December 2007 Inadequate Implementation of 10 CFR Part 21 Requirements by Vendors Who Supply Basic Components to Nuclear Power Plant Licensees Information Notice 2004-14, Use of Less Then Optimal Bounding Assumptions In Criticality Safety Analysis at Fuel Cycle Facilities2004-07-19019 July 2004 Use of Less Then Optimal Bounding Assumptions In Criticality Safety Analysis at Fuel Cycle Facilities Information Notice 2004-14, Use of Less Then Optimal Bounding Assumptions in Criticality Safety Analysis at Fuel Cycle Facilities2004-07-19019 July 2004 Use of Less Then Optimal Bounding Assumptions in Criticality Safety Analysis at Fuel Cycle Facilities Information Notice 2003-22, Heightened Awareness for Patients Containing Detectable Amounts of Radiation from Medical Administrations2003-12-0909 December 2003 Heightened Awareness for Patients Containing Detectable Amounts of Radiation from Medical Administrations Information Notice 2002-24, Potential Problems with Heat Collectors on Fire Protection Sprinklers2002-07-19019 July 2002 Potential Problems with Heat Collectors on Fire Protection Sprinklers Information Notice 2001-03, Incident Reporting Requirements for Radiography Licensees2001-04-0606 April 2001 Incident Reporting Requirements for Radiography Licensees Information Notice 2000-19, Implementation of Human Use Research Protocols Involving U.S. Nuclear Regulatory Commission Regulated Materials2000-12-0505 December 2000 Implementation of Human Use Research Protocols Involving U.S. Nuclear Regulatory Commission Regulated Materials Information Notice 1999-16, Federal Bureau of Investigation'S Nuclear Site Security Program1999-05-28028 May 1999 Federal Bureau of Investigation'S Nuclear Site Security Program Information Notice 1998-10, Probable Misadministrations Occurring During Intravascular Brachytherapy with Novoste Beta-cath System1998-03-0909 March 1998 Probable Misadministrations Occurring During Intravascular Brachytherapy with Novoste Beta-cath System Information Notice 1998-09, Collapse of an Isocam II, Dual-Headed Nuclear Medicine Gamma Camera1998-03-0505 March 1998 Collapse of an Isocam II, Dual-Headed Nuclear Medicine Gamma Camera Information Notice 1997-58, Mechanical Integrity of In-SITU Leach Injection Wells & Piping1997-07-31031 July 1997 Mechanical Integrity of In-SITU Leach Injection Wells & Piping Information Notice 1997-57, Leak Testing of Packaging Used in Transport of Radioactive Material1997-07-30030 July 1997 Leak Testing of Packaging Used in Transport of Radioactive Material Information Notice 1997-55, Calculation of Surface Activity for Contaminated Equipment & Materials1997-07-23023 July 1997 Calculation of Surface Activity for Contaminated Equipment & Materials Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program1994-03-25025 March 1994 Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed1994-03-18018 March 1994 Regulatory Requirements When No Operations Are Being Performed Information Notice 1993-69, Radiography Events at Operating Power Reactors1993-09-0202 September 1993 Radiography Events at Operating Power Reactors Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations1993-05-0707 May 1993 Notifications, Reports, and Records of Misadministrations Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer1993-01-0707 January 1993 Investigation and Reporting of Misadministrations by the Radiation Safety Officer Information Notice 1992-62, Emergency Response Information Requirements for Radioactive Material Shipment1992-08-24024 August 1992 Emergency Response Information Requirements for Radioactive Material Shipment 2023-12-06
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DOCUMENT 2 Supplemental Guidance for NUREG-1556, Volume 6, Revision 1, Consolidated Guidance About Materials Licenses: Program-Specific Guidance About 10 CFR Part 36 Irradiator Licenses
8.10.4 Occupational Dosimetry Regulations: 10 CFR 19.13, 10 CFR 20.1201, 10 CFR 20.1207, 10 CFR 20.1208, 10 CFR 20.1501(c), 10 CFR 20.1502, 10 CFR 36.55 Criteria: The requirements for occupational dosimetry are shown in Table 8-5.
Discussion: The regulations in 10 CFR 36.55(a) require that irradiator operators shall wear a personnel dosimeter that is processed and evaluated by an accredited National Voluntary Laboratory Accreditation Program (NVLAP) processor while operating a panoramic irradiator or while in the area around the pool of an underwater irradiator. The National Institute of Standards and Technology maintains a directory of laboratories that are NVLAP-accredited at http://ts.nist.gov/standards/scopes/dosim.html. Regulations in 10 CFR 36.55(b) require, in part, that other individuals who enter the radiation room of a panoramic irradiator shall wear a dosimeter, which may be a pocket dosimeter.
The requirements for most individuals are described in Table 8-5. Note that in accordance with 10 CFR 20.1207, the annual occupational dose limits for minors are 10 percent of the annual dose limits specified for adult workers. Also, 10 CFR 20.1208 requires the licensee to ensure that the dose equivalent to the embryo/fetus during the entire pregnancy, due to the occupational exposure of a declared pregnant woman, does not exceed 0.5 rem [5 mSv].
Other individuals who perform certain nonroutine operations (e.g., source loading, unloading, and repositioning, troubleshooting the control console, clearing stuck source racks, investigating and remediating removable contamination and leaking sources, (re)installing source cables, and any other activity during which personnel could receive radiation doses exceeding NRC limits) are likely to exceed 10 percent of the limits shown in Figure 8-7 (see Appendix G, Information Needed to Support Applicants Request to Perform Nonroutine Operations). Applicants also will be required to provide dosimetry (whole body and perhaps extremity monitors) to individuals performing such services.
When personnel monitoring is needed, most licensees use film badges, thermoluminescent dosimeters (TLDs), or optically stimulated luminescence dosimeters (OSLDs) that are supplied by a National Voluntary Laboratory Accreditation Program (NVLAP)-accredited processor. The exchange frequency for film badges is at least monthly because of technical concerns about film fading. The exchange frequency for TLDs and OSLDs is at least quarterly. Personnel dosimeters that do not require processing must be evaluated at least quarterly.
For personnel dosimeters that require processing, applicants should verify that the processor is NVLAP accredited. Consult the NVLAP accredited processor for its recommendations for exchange frequency and proper use. The National Institute of Standards and Technology maintains a directory of laboratories that are NVLAP-accredited at http://ts.nist.gov/standards/scopes/dosim.html.
Some workers (e.g., package handlers, shipping personnel, and custodial personnel) may work near the irradiator but are not likely to exceed 10 percent of the limits. Refer to Appendix K of this NUREG for guidance for demonstrating that an unmonitored individual will not exceed 10 percent of the limits.
Table 8-5. Requirements for Occupational Dosimetry Type of When Dosimetry Must Irradiator Category of Personnel Type of Dosimetry Be Worn Panoramic Irradiator operators Film, TLD, or OSLD When operating irradiator Personnel dosimeter Underwater Irradiator operators Film, TLD, or OSLD When in area Personnel dosimeter around pool Panoramic Other individuals, Pocket dosimeter, film, When entering or in including visitors (for TLD, or OSLD or radiation room groups of visitors, it is Personnel dosimeter sufficient for two to be monitored)
All Anyone who could Pocket dosimeter, film, As directed by the RSO, receive, in a year, a TLD, or OSLD or based on radiation dose in excess Personnel dosimeter 10 CFR 20.1502 of 10% of the allowable limits, as shown in Figure 8-8.*
- The licensee must maintain, for inspection by the NRC, documentation demonstrating that unmonitored individuals are not likely to receive, in a year, a radiation dose in excess of 10 percent of the allowable limits, as shown in Figure 8-8.
Dose Limits for Adult Radiation Worker (10 CFR 20.1201)
Figure 8-7. Annual Dose Limits for Adult Radiation Workers
Total effective dose equivalent (TEDE) equals the effective dose equivalent (for external exposures) plus the committed effective dose equivalent (for internal exposures).
Response from Applicant: Provide the following:
- A statement that: Film, TLD, or other dosimetry devices are processed and evaluated by an NVLAP-accredited processor.
- A statement that: Film, TLD, or other personnelPersonnel dosimetry devices that require processing will be exchangedreplaced and evaluated at the required frequency and. Personnel dosimetry devices that do not require processing will be evaluated at the required frequency. Personnel dosimetry devices will be assigned to and worn by irradiator personnel.
- A statement that: Other individuals, including visitors, entering a radiation room will be provided dosimetry in accordance with regulatory requirements.
Suggested Format for Providing Information Requested in Items 5 through 11 of U.S. Nuclear Regulatory Commission Form 313 Item Description No Title and Criteria Yes Attached 10 RADIATION SAFETY PROGRAM (CONTINUED)
Survey Instruments
- Submit alternative calibration procedures for NRC review. []
Radiation Monitors
- Describe the type of monitors used to meet the []
requirements of 10 CFR 36.23(c); 10 CFR 36.29, and 10 CFR 36.59(b).
Material Receipt and Accountability
- Submit a description of procedure(s) for ensuring []
material accountability.
OR A statement that: We will develop, implement, and maintain procedures for ensuring accountability of licensed materials at all times.
AND A statement declaring that: We will comply with the NSTS []
reporting requirements as described in 10 CFR 22.2207.
Occupational Dosimetry Provide the following:
- A statement that: Film, TLD, or other dosimetry devices []
are processed and evaluated by an NVLAP-accredited processor.
- A statement that: Film, TLD, or other []
personnelPersonnel dosimetry devices that require processing will be replaced and evaluated at the required frequency and. Personnel dosimetry devices that do not require processing will be evaluated at the required frequency. Personnel dosimetry devices will be assigned to and worn by irradiator personnel.
- A statement that: Other individuals, including visitors, []
entering a radiation room will be provided dosimetry in accordance with regulatory requirements.
The red-line addition noted above is on Page C-10 in Appendix C of NUREG-1556, Volume 6, Revision 1
The red-line, strike-out noted below is on Page I-4 in Appendix I of NUREG-1556, Volume 6, Revision 1 Personnel Radiation Protection A. Are as-low-as-is-reasonably-achievable (ALARA) considerations incorporated into the radiation protection program? [10 CFR 20.1101(b)]
B. Is documentation kept showing that unmonitored individuals receive 10 percent of the limit? [10 CFR 20.1502(a)]
C. Did unmonitored individuals activities change during the year that could put them over 10 percent of the limit?
D. If yes to C above, was a new evaluation performed?
E. Is external dosimetry provided to individuals, as required by 10 CFR 36.55, Personnel Monitoring, and to individuals likely to receive >10 percent of the limit, including minors?
Note that, in accordance with 10 CFR 20.1207, the annual occupational dose limit for minors is also 10 percent of the annual dose limits specified for adult workers.
- 1. Irradiator operators: Is the dosimetry supplier National Voluntary Laboratory Accreditation Program, approved? [10 CFR 20.1501(c)] Are the dosimeters exchangedreplaced monthly for film badges and quarterly for thermoluminescent dosimeters (TLDs) and optically stimulated luminescent dosimeters (OSLDs)?
Note: The RSO may specify more frequent dosimeter evaluation and dosimeter replacementDosimeter change-out frequency should be specified by the RSO based on exposure history of the facility.
- 2. Are dosimeters evaluated at least quarterly for personnel dosimeters that do not require processing?
- 3. Are dosimetry reports reviewed by the RSO upon receipt?
- 4. Are dosimeters provided to persons who enter the radiation room of a panoramic irradiator? [10 CFR 36.55(b)]
- 5. Are annual checks of accuracy of pocket dosimeters performed?
[10 CFR 36.55(b)]
- 6. Are the records NRC forms or the equivalent? [10 CFR 20.2104(d),
10 CFR 20.2106(c)]
- a. NRC Form 4 Cumulative Occupational Exposure History completed?
The strike-out noted below is on Page K-1 in Appendix K of NUREG-1556, Volume 6, Revision 1
Guidance for Demonstrating that Unmonitored Individuals Are Not Likely to Exceed 10 Percent of the Allowable Occupational Dose Limits Dosimetry is required for individuals likely to receive in a year, from sources external to the body, a dose in excess of 10 percent of the applicable regulatory limits in Title 10 of the Code of Federal Regulations (10 CFR) 20.1201, Occupational dose limits for adults. However, irradiator operators are required by 10 CFR 36.55(a) to wear a personnel dosimeter that is processed and evaluated by an accredited National Voluntary Laboratory Accreditation Program processor while operating a panoramic irradiator or while in the area around the pool of an underwater irradiator. As discussed in Item 8.10.4, these personnel dosimeters may be film badges, thermoluminescent dosimeters (TLDs) or optically stimulated luminescence dosimeters.
Also, other individuals who enter the radiation room of a panoramic irradiator must wear a dosimeter, which may be a pocket dosimeter. When groups of visitors enter the radiation room, at least two people must wear dosimeters. In those instances where pocket chambersdosimeters are used instead of film badges or TLDspersonnel dosimeters, a check of the response of the dosimeters to radiation must be made at least annually. Acceptable dosimeters must read within plus or minus 30 percent of the true radiation dose. To demonstrate that dosimetry is not required for other workers, a licensee needs to have available, for inspection, an evaluation to demonstrate that its workers are not likely to exceed 10 percent of the applicable annual limits.
The most common way that individuals might exceed 10 percent of the applicable limits is by performing work near the irradiator shield or areas of cable or equipment penetration of the shield of the irradiator. However, for most irradiators, even these activities result in the individual receiving minimal doses. A licensee will need to evaluate the doses that its workers might receive in performing these tasks to assess whether dosimetry is required. The evaluation may be completed by carefully measuring the dose rates when the source is in the irradiate position, using techniques similar to those described in Appendix L of this NUREG. An evaluation of the actual time workers spend in the area can provide the information needed to estimate the annual dose of the workers.
The applicable total effective dose equivalent (whole body) limit is 50 millisievert (mSv) [5 rems]
per year, and 10 percent of that value is 5 mSv [500 millirems] per year.
Example: A careful measurement of the highest dose rate at the face of the shield of a panoramic irradiator is found to be 0.015 mSv/hr (millisievert per hour) [1.5 mrem/hr]. An individual is expected to spend no more than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per week in the area near the shield.
Based on the dose rate, assuming the source is continuously in the irradiate position while the work is being performed, the annual dose is expected to be less than 2.34 mSv [234 mrem]
(i.e., 3 hr/wk x 1.5 mrem/hr x 52 wk/yr). Based on the above specific information, no dosimetry is required if the individual performs work in the area less than 6.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per week.