Discuss the Emergency Plan’s purpose, legal bases, Emergency Classifications, Protective Action Guidelines, Post Accident Sampling and Radiological Dose Assessment. Discuss the Radiation Protection Plan’s purpose, bases and its contents. Discuss the Groundwater Protection Program’s purpose, legal bases and its contents as recommended in NEI 07-07. TASKS: 1. Request or suggest a facility be designated by your supervisor or mentor. For the facility designated by your supervisor or mentor, locate a copy of the following documents and review the various sections as listed in the Evaluation Criteria section: TS RM (or site-specific equivalent) ODCM PCP Emergency Plan Radiation Protection Plan Ground Protection Plan Which license amendment(s) removed c, d, and e from the TS? Meet with your supervisor or qualified inspector to discuss any questions you may have as a result of this ISA. Discuss the answers to the questions listed the Evaluation Criteria section of this study guide with your supervisor. DOCUMENTATION: Document completion on the Health Physics Inspector Technical Proficiency Level Signature Card and Certification Item ISAHP2.
ANSI/ASME N510-1980, “Testing of Nuclear Air-Cleaning Systems,” and other revisions as applicable IE Bulletin 80-10, “Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment,” May 6, 1980 IE Circular No. 80-18, “10 CFR 50.59 Safety Evaluations for Changes to Radioactive Waste Treatment Systems,” August 22, 1980 Information Notice No. 82-43, “Deficiencies in LWR Air Filtration/Ventilation Systems,” November 16, 1982 Information Notice No. 82-49, “Correction for Sample Conditions for Air and Gas Monitoring,” December 16, 1982 Information Notice No. 13-01, “Emergency Action Level Thresholds Outside the Range of Radiation Monitors,” February 13, 2013 Information Notice No. 13-12, Improperly Sloped Instrument Sensing Lines,” July 13, 2013 Information Notice No. 13-13, “Deficiencies with Effluent Radiation Monitoring System Instrumentation,” July 12, 2013 Generic Letter 89-01, “Implementation of Programmatic Controls for Radiological Effluent TS in the Administrative Controls Section of the TS and the Relocation of Procedural Details of RETS to the ODCM or to the PCP,” January 31, 1989 Generic Letter 83-13, “Clarification of Surveillance Requirements for HEPA Filters and Charcoal Absorber Units in Technical Specifications on ESF Cleanup Systems,” March 2, 1983 EVALUATION CRITERIA: Upon completion of this ISA, the inspector should be able to: Discuss and identify effluent sampling techniques that may be used by the licensee for sampling effluents such as radioactive water, air iodine, tritium and air particulate. Describe and discuss the calibration techniques used for effluent monitoring instruments, alarm set points and typical calibration frequencies. Discuss laboratory QA/QC Policy and its implementation, including and intra-laboratory comparisons. Discus NRC expectations in this area.
Health Physics Inspector Individual Study Activity (ISA-HP-11) Significance Determination Process - Occupational Radiation Safety PURPOSE: The purpose of this ISA is familiarize you with the Occupational Radiation Significance Determination Process (SDP), explain the bases of each SDP branch, provide technical and policy references, and present practical exercises/scenarios that challenge you to use the SDP. The risk significance of inspection findings are evaluated using the SDP. COMPETENCY AREA: INSPECTION, TECHNICAL AREA EXPERTISE REGULATORY FRAMEWORK LEVEL OF EFFORT: 36 hours REFERENCES: 1. IMC 0609, Appendix C, “Occupational Radiation Safety Significance Determination Process” IMC 0308, Attachment 3, Appendix C, “Technical Basis for Occupational Radiation Safety Significance Determination Process” SDP Branch on ALARA NRC Inspection Report (50-483-0017) (ADAMS Accession Number ML003757369), and (EA-00-208, May, 2001) (ADAMS Accession Number ML011270225) NUREG-0713, Latest Rev, “Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities” Supplementary Information, 10 CFR 20 Final Rule, Subpart B, “Radiation Protection Programs,” Federal Register Vol. 56, No. 98, pages 23366-23367, May 21, 1991 (ADAMS Accession Number ML051790366) SDP Branch on Overexposure Regulatory Guide 8.38, “Control of Access to High and Very High Radiation Areas in Nuclear Power Plants,” May 2006 Nuclear Regulatory Commission Enforcement Manual SDP Branch on Substantial Potential for Overexposure (SPFO)
NUREG-1301, “Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors” “Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors” Regulatory 1.21, “Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents From Light-Water-Cooled Nuclear Power Plants,” June 2009, and other revisions as applicable Regulatory Guide 1.23, “On-site Meteorological Programs for Nuclear Power Plants,” March 2007, and other revisions as applicable or its predecessor Safety Guide 23, “Onsite Meteorological Programs,” 1972, depending on the licensee commitments Regulatory Guide 1.109, “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,” October 1977, and other revisions as applicable Regulatory 1.143, “Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants,” November 2001, and other revisions as applicable Regulatory Guide 4.15, “Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment,” July 2007, and other revisions as applicable Regulatory Guide 1.110, “Cost-Benefit Analysis for Radioactive Waste Systems for Light-Water-Cooled Reactors,” March 1976, and other revisions as applicable Regulatory Guide 1.111, “Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,” July 1977, and other revisions as applicable Regulatory Guide 1.112, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors,” March 2007, and other revisions as applicable Regulatory Guide 1.113, “Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,” April 1977, and other revisions as applicable
Revision History Commitment Tracking Number Accession Number Issue Date Change Notice Description of Change Description of Training Required and Completion Date Comment Resolution and Closed Feedback Accession Number Non-Public) N/A 10/16/06 CN 06-027 This IMC has been revised to incorporate comments from the Commission in which the term public confidence has been change to openness N/A N/A N/A 07/08/09 CN-09-017 This revision moves post-qualification and refresher training requirements out of the appendix and into Appendix D-1. N/A ML091590710 N/A ML15323A464 02/20/17 CN 17-004 This revision incorporates changes to reflect the transition from 6 baseline HP inspections to 8. N/A ML15324A264 ML16265A576