**NRC INSPECTION MANUAL**	IRAB

INSPECTION MANUAL CHAPTER 1245 APPENDIX B

# GENERAL PROFICIENCY-LEVEL TRAINING AND QUALIFICATION JOURNAL

Effective Date: 05/18/2023

ContentsIntroduction	1Required General Proficiency Training Courses	1General Proficiency Individual Study and On-the-Job Activities:	1(ISA-General-1) Quality Assurance Program for Power Reactors	4(ISA-General-1a) Construction QA Program Requirements (Construction Inspectors only)	6(ISA-General-2) CAP (for power reactor and construction inspectors only)	8(ISA-General-3) Technical and Regulatory Issues (for power reactor & construction only)	9(ISA-General-4) Safety Culture	12(OJT-General-1) Emergency Drill/Exercise Observation (for power reactor & construction)	16General Proficiency-Level Signature Card and Certification	19Form 1: General Proficiency-Level Equivalency Justification	F1-1Attachment 1: Revision History for IMC 1245 Appendix B	Att1-1

Issue Date: 05/18/23	1	1245 App B

# Introduction

You may complete the General Proficiency requirements together with the Technical Proficiency requirements for your specific inspector classification.

# Required General Proficiency Training Courses

NOTE: You DO NOT have to finish Appendix A before taking the courses below. It is RECOMMENDED that you complete the Effective Communication for NRC Inspectors course before the Gathering Information for Inspectors through Interviews course.

· “Effective Communication for NRC Inspectors,” (instructorled course in the Talent Management System (TMS))

· “Gathering Information for Inspectors through Interviews,” (instructorled course in TMS)

· “Media Training Workshop,” (instructorled course in TMS)

· Technical training in TMS (Web-based, course numbers listed in ISA 3)

NOTE: It is RECOMMENDED that you complete Appendix A and receive Basic Inspector Certification before beginning the courses listed below.

Before signing up for any course, be sure that you have checked and meet any prerequisites.

These courses should be completed in the order listed:

· Root Cause/Incident Investigation Workshop (G-205)

· Field Techniques and Regulatory Processes (G-103)

# General Proficiency Individual Study and On-the-Job Activities:

The individual study activities are knowledge and comprehension-based exercises that are designed to direct and focus your efforts as you begin reviewing documents that will be important to the performance of your job. Each study activity begins with a “purpose” statement informing you of why the activity is important and how it relates to the job of an inspector. The “level of effort” has been noted so that you have an idea of how much effort should be expended in completing the activity. (Of course, the times are estimates. You may need a little more or a little less time.) The “evaluation criteria” are listed up front so that you will review them first and better understand what you are expected to achieve as a result of completing the activity. Use the evaluation criteria to help you focus on what is most important. The “tasks” outline the things you must do to successfully address the evaluation criteria.

The General Proficiency on the job activity is designed to increase your understanding of an important NRC function (event response) by requiring you to perform more challenging application-based level tasks. Similar to the individual study activities, the on-the-job activities begin with a “purpose” statement informing you of why the activity is important and how it relates to the job of an inspector. The “level of effort” has been noted so that you have an idea of how much effort should be expended in completing the activity. (Of course, the time is an estimate. You may need a little more or a little less time.) The “evaluation criteria” is listed up front so that you will review them first and better understand what you are expected to achieve as a result of completing the activity. Use the evaluation criteria to help you focus on what is most important. The “tasks” outline the things you must do to successfully address the evaluation criteria. 

Issue Date: 05/18/23	1	1245 App B

Individual Study Activity

(ISA-General-1) Quality Assurance Program for Power Reactors

PURPOSE:

This activity will provide you with a working knowledge of the contents of Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Processing Plants,” to Title 10 of the *Code of Federal Regulations* (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities,” industry standards, and the associated licensee programs and documents that collectively establish the basis for the licensee’s quality assurance (QA) program. This activity will provide you with an understanding of how the QA program prevents, identifies, and mitigates Counterfeit, Fraudulent, and Suspect Items (CFSI) risks. [C3]

Note that QA program requirements for construction inspectors are addressed in ISA-1a of this appendix. QA program requirements for research and test reactors are addressed in IMC 1245 Appendix C5, ISA-RT-1, under ANSI/ANS 15.8 and RG 2.5.

COMPETENCY AREA:	INSPECTION

LEVEL OF EFFORT:	14 hours

REFERENCES:

1. Appendix B to 10 CFR Part 50

2. 10 CFR Part 21

3. Regulatory Guide (RG) 1.28, “Quality Assurance Program Criteria”

4. RG 1.33, “Quality Assurance Program Requirements”

5. Licensee QA program documentation

6. Regulatory Information Summary 2015-08, “Oversight of Counterfeit, fraudulent, and Suspect Items in the Nuclear Industry” [C3]

7. Electric Power Research Institute (EPRI) Technical Report (TR)-1019163, “Plant Support Engineering: Counterfeit, Fraudulent and Substandard Items- Mitigating the Increasing Risk,” Revision 1, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14245A079). [C3]

EVALUATION CRITERIA:

At the completion of this activity, you should be able to do the following:

1. Discuss the general content of Appendix B to 10 CFR Part 50 and the 18 criteria contained in the appendix.

2. Describe the relationship between the plant license, the final safety analysis report (FSAR), the plant technical specifications, and Appendix B to 10 CFR Part 50.

3. Outline the key elements of an effective QA program, and the licensee’s implementation of those elements at your reference site.

4. Discuss which key elements of a licensee’s QA program will support prevention, identification, and mitigation of CFSI risks. [C3]

TASKS:

1. Review and discuss the 18 criteria of Appendix B with your supervisor or qualified inspector and communicate an understanding of their content and general application to field inspections.

2. Review the regulations that require a QA program. Review industry standards related to QA. Find where the FSAR, technical specifications, and plant license address QA. Review a licensee QA program and the implementing procedures.

3. Review the regulations and guidance that address CFSI and be able to define CFSI. Review NRC and EPRI guidance in Reference 6 and 7 on CFSI and be able to discuss the relationship between a substandard basic component and CFSI. [C3]

4. At a site, gain a general understanding of the licensee’s QA program through a combination of discussions with a qualified resident inspector and review of assessments/reports prepared by the licensee QA organization.

5. Meet with your supervisor or a qualified inspector to discuss any questions that you may have as a result of this activity and demonstrate that you can meet the evaluation criteria listed above.

6. Discuss how NRC regulations governing reporting, establish criteria for reporting events to the NRC within a specified amount of time.

DOCUMENTATION: 	General Proficiency Qualification Signature Card Item ISAGeneral1

(ISA-General-1a) Construction Quality Assurance Program Requirements (Construction Inspectors only)

PURPOSE:

The purpose of this activity is to familiarize inspectors with the regulatory provisions that require licensees to have a quality assurance program. In addition to inspections that support the determination that Inspections, Tests, Analysis, and Acceptance Criteria (ITAAC) have been met, additional inspections will be needed to provide assurance that the licensee's processes for oversight of construction activities are effective. The successful implementation of a comprehensive QA program by the licensee will be an important indicator of the licensee's ability to manage the various activities associated with a large construction project. This activity will highlight the relationship between Part 52 and the requirements in Part 50 that relate to quality assurance.

COMPETENCY AREA:	INSPECTION

LEVEL OF EFFORT: 	20 hours

REFERENCES: 	

1. 10 CFR Part 50, Appendix B, “A Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants”

2. Inspection Procedure (IP) 35007, “Quality Assurance Program Implementation During Construction”

3. IP 35017, “Quality Assurance Implementation Inspection”

4. 10 CFR 50.55, "Conditions of Construction Permits" (Note: the applicable provisions of 10 CFR 50 have been incorporated into Part 52 by reference and not all the requirements of part 50.55 pertaining to construction permits will apply to Part 52)

5. RG 1.28, “A Quality Assurance Program Criteria (Design and Construction)”

6. ASME NQA-1, “A Quality Assurance Requirements for Nuclear Facility Application Issue”

7. NUREG-1055, "Improving Quality and the Assurance of Quality in the Design and Construction of Nuclear Power Plants, (A Report to Congress), March, 1987"

EVALUATION CRITERIA:

At the completion of this activity, and as determined by the supervisor, inspectors should be able to:

1. Explain how 10 CFR Part 50 requirements are invoked by 10 CFR Part 52.

2. Identify the Appendix B criteria and describe how an inspection would verify that they are correctly implemented during construction activities.

3. Discuss when applicants or licensees have to implement Appendix B requirements and which inspection procedures are used at the various stages.

4. Discuss the American National Standards (ANSI) and American Society of Engineers (ASME) guidance that is endorsed by RG 1.28 and explain the exceptions to the guidance (contained in RG 1.28) which are required to be met in order for a licensee or vendor to use the endorsement.

5. Describe the applicability of ASME NQA-1 and explain the content of the various parts.

6. Discuss the conclusions of NUREG-1055 and describe how the recommendations have been addressed in new construction both within the NRC and the Industry.

TASKS:

1. Read 10 CFR 52.17, 52.47, and 52.79 to determine the requirements to apply quality assurance.

2. Review 10 CFR Part 50, Appendix B and Inspection Procedures 35007 and 35017. Compare the criteria with the inspection attributes in the IPs and pay particular attention to the IP guidance.

3. Review RG 1.28 and focus on the additions and modifications to ANSI/ASME NQA-1 identified in section C, “Regulatory Position."

4. Review ASME NQA-1.

5. Read NUREG-1055 and note the root causes for past construction problems.

6. If able, participate on a programmatic NRC QA inspection (this can also satisfy the inspection training requirements for IMC 1245 Appendix C-15 OJT-1, Construction Inspection Accompaniment).

7. Meet with your supervisor, mentor, or a qualified construction inspector to discuss any questions you may have as a result of this activity. Discuss the answers to the questions listed under the Evaluation Criteria section of this study guide with your supervisor.

DOCUMENTATION: 	General Proficiency-Level Qualification Signature Card Item ISAGeneral-1a.

(ISA-General-2) Corrective Action Program (for power reactor and construction inspectors only)

PURPOSE:

This activity will provide you with a working knowledge of the licensee programs and documents that were established to meet the requirements for an effective problem identification and corrective action program, as outlined in Criterion XVI of Appendix B to 10 CFR Part 50.

COMPETENCY AREA:	INSPECTION

LEVEL OF EFFORT:	20 hours

REFERENCES:

1. IP 71152, “Problem Identification and Resolution”

2. IP 35007, “Quality Assurance Program Implementation During Construction and PreConstruction Activities” (construction inspectors only)

3. Site-specific documents that describe the licensee’s corrective action program

4. Criterion XVI of Appendix B to 10 CFR Part 50

EVALUATION CRITERIA:

At the completion of this activity, you should be able to discuss the principal steps in your reference site’s corrective action program (CAP) with respect to identification of a condition adverse to quality through final resolution.

TASKS:

1. At your reference site, gain a general understanding of the licensee’s CAP through a combination of discussions with a qualified resident inspector and attendance at routine CAP meetings.

2. Using IP 71152 (IP 35007, Appendix 16 for construction inspectors) for guidance, review a sample of about six issues entered into the licensee’s CAP within the past month and compare the licensee’s actions with regulatory requirements. Discuss the resolution of the issues with the resident inspector. This review should include the resolution of potential operability issues, if available.

3. Meet with your supervisor or a qualified operations resident inspector (or qualified construction resident inspector for construction inspectors) to discuss any questions that you may have as a result of this activity and demonstrate that you can meet the evaluation criteria listed above.

DOCUMENTATION:	General Proficiency Qualification Signature Card Item ISAGeneral2

(ISA-General-3) Technical and Regulatory Issues (for power reactor and construction inspectors only)

PURPOSE:

This activity will familiarize you with several power reactor related events and subject areas that significantly impacted the domestic nuclear power industry.

COMPETENCY AREA:	INSPECTION

LEVEL OF EFFORT:	Various

REFERENCES:

1. NRC produced technical training courses:

a. Effects of Corrosion course in TMS

b. Fukushima Lessons Learned course in TMS

2. INPO produced videos:

a. Browns Ferry Fire (ML15070A065)

b. Crystal River 3 Loss of Instrument Power (ML15070A069)

c. Davis Besse Loss of Feed (ML15070A078)

d. LaSalle 2 Scram on High Neutron Flux (ML15070A083)

e. Nine Mile Point 1 Turbine Damage During Torsional Test (ML15070A094)

f. Oconee 3 Letdown Storage Tank Inadvertently Drained (ML15070A102)

g. Salem Marsh Grass and Non-Conservative Decision-Making Leads to Scram and Pressure Control Issues (ML15070A103)

h. Salem Anticipated Transient without a Scram (ML15070A113)

i. Chernobyl Accident - Excerpt from "The Special Characteristic of Nuclear Power" (ML15070A126)

j. TMI Accident - Excerpt from "The Special Characteristics of Nuclear Power" (ML15070A128)

k. Vogtle 1 Station Blackout (ML15070A133)

Note: the above videos are INPO proprietary information for NRC internal use only, not for public distribution or viewing.

3. NUREG 1789, “10 CFR Part 52 Construction Inspection Program Framework Document,” Appendix B (construction inspectors only)

4. NRC Bulletin 2011-01, “Mitigating Strategies”

5. Near Term Report and Recommendations for Agency Actions Following the Events in Japan. (ML1186A950)

6. Mitigation Strategies Order EA-12-049. (ML12054A735)

7. Reliable Hardened Containment Vents Order EA-13-109. (ML13130A06)

8. Spent Fuel Pool Instrumentation Order EA-12-051 (ML12056A044)

9. SECY-15-0137, “Proposed Plans for Resolving Open Fukushima Daiichi Tier 2 and 3 recommendations,” (ML15254A006)

10. SECY-16-0144, “Proposed Resolution of Remaining Fukushima Daiichi Tier 2 and 3 Recommendations,” (ML16286A586)

11. https://www.nrc.gov/about-nrc/cfsi/guidance.html [C3]

12. Regulatory Information Summary (RIS) 2015-08, “Oversight of Counterfeit, Fraudulent, and Suspect Items in the Nuclear Industry” [C3]

EVALUATION CRITERIA:

At the completion of this activity, you should be able to do the following:

1. Discuss the general topical matters presented in the NRC and INPO Web-based training and exhibit a basic knowledge of the technical/regulatory issues and their application to the NRC.

2. Discuss the construction inspection lessons learned documented in SECY-06-0114 Enclosures 1 and 2, and in NUREG 1789, Appendix B (construction inspectors only).

3. Discuss the actions the NRC took in response to the Fukushima Daiichi event regarding mitigating strategies. (For C-1 and C-2 Inspectors and C-10 Examiners only.)

TASKS:

1. Watch and complete all of the NRC and INPO produced Web-based training courses/videos that are referenced above. (For C-1 and C-2 Inspectors and C-10 Examiners only.) (Other inspector types only need to watch and complete the four NRC produced courses.)

2. Gain a general understanding of the technical/regulatory issues and their applications to the NRC. Regarding the Fukushima information, be able to discuss, the accident, and regulatory actions the NRC took to minimize the possibility of a similar event occurring at domestic nuclear plant sites (for C-1 and C-2 Inspectors and C-10 Examiners only).

3. Discuss the purpose of Severe Accident Management Guidelines (SAMGs), when they would be used, and their relationship to the Fukushima accident (for C-1 and C-2 Inspectors and C-10 Examiners only).

4. Review the guidance on the website in Reference 11 and discuss the implications of the NRC regulatory framework related to CFSI on your inspection program. [C3]

5. Meet with your supervisor or a qualified inspector to discuss any questions that you may have as a result of this activity and demonstrate that you can meet the evaluation criteria listed above. [C1]

DOCUMENTATION:	General Proficiency Qualification Signature Card Item ISA-General-3

(ISA-General-4) Safety Culture

PURPOSE:

This activity will provide you with a working knowledge of the NRC safety culture initiative and how it is addressed in the Reactor Oversight Process (ROP) and Construction Reactor Oversight Process (cROP).

COMPETENCY AREA:	INSPECTION

LEVEL OF EFFORT:	20 hours

REFERENCES:

For power reactor inspectors:

1. Safety Culture ROP Training. (http://papaya.nrc.gov/safetyculture/index.html)

2. “Review of the Columbia Space Shuttle Accident,” computer-based training found in TMS.

3. Inspection Manual Chapters 0305, “Operating Reactor Assessment Program,” 0310, “Aspects Within the Cross-Cutting Areas,” and 0611, “Power Reactor Inspection Reports”

4. IPs 40100, “Independent Safety Culture Assessment Follow-up”, 71152, “Problem Identification and Resolution”; 95001, “Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area”; 95002, “Supplemental Inspection Procedure for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area”; 95003, “Supplemental Inspection Procedure Repetitive Degraded Cornerstone or Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input”; 71153, “Follow up of Events and Notices of Enforcement Discretion”; 93800, “Augmented Inspection Team”; and 93812, “Special Inspection”

5. SECY-06-122, “Safety Culture Initiative Activities to Enhance the Reactor Oversight Process and Outcomes of the Initiatives” at***http://www.nrc.gov/reading-rm/doc-collections/commission/secys/2006/secy2006-0122/2006-0122scy.pdf**(ML061320282)*

6. “Safety Culture Policy Statement and Federal Register Notice” (ML11146A047)

7. Safety Culture Case Study User Guide (ML11195A32) and Educational Material (http://www.nrc.gov/about-nrc/safety-culture/sc-outreach-edu-materials.html)

8. NUREG-2165, “Safety Culture Common Language”

9. IP 93100; “Safety Conscious Work Environment Issue of Concern Followup”

For research and test reactor inspectors:

1. Safety Culture ROP Training (http://papaya.nrc.gov/safetyculture/index.html)

2. “Review of the Columbia Space Shuttle Accident,” computer-based training module, a case study in safety culture, found in TMS.

3. Review of the Safety Culture Case Study User Guide (ML11195A32) and Educational Material (http://www.nrc.gov/about-nrc/safety-culture/sc-outreach-edu-materials.html)

For construction inspectors:

1. Safety Culture ROP Training (Note that the treatment of safety culture in the cROP is essentially the same as the treatment of safety culture in the ROP) (http://papaya.nrc.gov/safetyculture/index.html)

2. “Review of the Columbia Space Shuttle Accident,” computer-based training module, a case study in safety culture, found in TMS.

3. Review of the Safety Culture Case Study User Guide (ML11195A32) and Educational Material (http://www.nrc.gov/about-nrc/safety-culture/sc-outreach-edu-materials.html)

4. IPs 35007, Appendix 16, “Inspection of Criterion XVI – Correction Action”; 40100, “Independent Safety Culture Assessment Follow-up”, 90001, “Construction Regulatory Response Column Inspections”; 90002, “Construction Degraded Performance Column Inspections”; 90003, “Construction Multiple/Repetitive Degraded Cornerstone Column Inspections”; “Augmented Inspection Team”; and 93812, “Special Inspection”

5. Safety Culture Policy Statement and Federal Register Notice (ML11146A047)

6. NUREG-2165, “Safety Culture Common Language)

7. IMC 0613, Appendix F, “Construction Cross-Cutting Areas and Aspects”

EVALUATION CRITERIA:

At the completion of this activity, you should be able to discuss general safety culture aspects and the graded ROP (cROP for construction inspectors) approach to recognizing potential weaknesses in licensee safety culture and taking appropriate agency actions.

TASKS:

1. Review referenced Safety Culture Training and inspection procedures.

2. Define safety culture and safety conscious work environment (SCWE) and discuss why they are important, how they are different, and how they support each other.

3. Explain the relationship of the cross-cutting areas with the safety culture aspects. (For power reactor and construction inspectors only.)

4. Discuss how the causes and cross-cutting aspects would be identified and documented for several current or hypothetical inspection findings. (For power reactor and construction inspectors only.)

5. Review the Safety Culture Policy Statement. Discuss the nine traits listed in that policy along with the cross-cutting aspects listed in IMC 0310, and the corresponding examples found in NUREG-2165. The construction cross-cutting aspects are listed in IMC 0613, Appendix F for construction inspectors)

6. Discuss the agency’s graded approach to dealing with potential safety culture issues as licensee performance declines.

7. Meet with your supervisor, a qualified operations resident inspector, or a qualified Safety Culture Assessor (or a qualified construction resident inspector for construction inspectors) to discuss any questions that you may have as a result of this activity and demonstrate that you can meet the evaluation criteria listed above. [C2]

DOCUMENTATION:	General Proficiency Qualification Signature Card Item ISAGeneral4

General ProficiencyOn-the-Job Activities

(OJT-General-1) Emergency Drill/Exercise Observation (for power reactor and construction inspectors only)

PURPOSE:

The conduct of an emergency drill/exercise allows the licensee to assess emergency response performance and the effective correction of previously identified weaknesses. It permits the evaluation of the level of quality of emergency response training, emergency plan implementing procedures, facility and equipment readiness, personnel performance, organizational and management changes, and communications equipment readiness. This activity will permit you, the observer, to realize the scope of involvement of your particular discipline during a declared emergency at a nuclear power facility.

Note that observations of drills for research and test reactors are addressed in IMC 1245, Appendix C5, OJT-RT-1.

COMPETENCY AREAS:	REGULATORY FRAMEWORKINSPECTION

LEVEL OF EFFORT:	24 hours

REFERENCES:

1. IP 71114.01, “Exercise Evaluation”

2. IP 71114.06, “Drill Evaluation”

3. IP 71114.07, “Exercise Evaluation - Hostile Action (HA) Event”

4. IP 71114.08, “Exercise Evaluation – Scenario Review”

5. Section IV.F of Appendix E, “Emergency Planning and Preparedness for Production and Utilization Facilities,” to 10 CFR Part 50

6. 10 CFR 50.47(b)

EVALUATION CRITERIA:	

At the completion of this activity, you should be able to do the following:

1. Discuss the Federal guidance for drill/exercise observations as described in IP 71114.01, IP 71114.06, IP 71114.07, and IP 71114.08.

2. Identify activities that will occur with regard to your discipline during the performance of an emergency drill/exercise.

3. Discuss the NRC and licensee processes for documenting and handling weaknesses and deficiencies identified during a drill/exercise.

4. Discuss the NRC’s method of evaluating licensee performance during an emergency drill/exercise to determine whether it has met the planning standards of 10 CFR 50.47(b).

5. Discuss the NRC’s method for evaluating licensee performance during a drill/exercise to determine whether it has demonstrated the capability of providing reasonable assurance that adequate protective measures can be taken in the event of a declared emergency.

NOTE: Whenever possible, observe a drill or exercise at a site and focus on activities related to your technical discipline.

TASKS:	

1. Review IP 71114.01, IP 71114.06, IP 71114.07, and IP 71114.08 to identify the inspection attributes provided for drill/exercise performance evaluations. Discuss any questions with a senior emergency preparedness inspector.

2. Review the regulatory requirements with regard to emergency preparedness contained in 10 CFR 50.47(b) and section IV.F of Appendix E to 10 CFR Part 50.

3. Obtain an emergency drill/exercise schedule for the applicable region. Coordinate your observation of an upcoming emergency drill/exercise with your supervisor, applicable regional senior emergency preparedness inspector, and site senior resident inspector. If possible, observe the drill at the site.

4. Become familiar with the applicable licensee emergency plan and implementing procedures. In particular, review those instructions for your discipline’s activities and involvement during a declared emergency and develop an understanding of their successful implementation.

5. Review IP 71114.07 to identify the inspection attributes provided for exercise scenario reviews. Obtain and review a copy of the applicable licensee’s emergency drill/exercise scenario. Identify activities that will occur with regard to your discipline during the performance of the emergency drill/exercise and note the licensee expectations for success versus failure.

6. Perform an independent observation of an emergency drill/exercise. Observe activities at several of the licensee emergency response facility locations, if possible (e.g., control room, operations support center, technical support center, emergency operations facility, joint information center, field activities). Take care not to interfere with licensee performance or evaluation of the drill/exercise. Do not prompt licensee participants or evaluators or provide your observations or conclusions regarding weaknesses or deficiencies during drill/exercise performance. Findings must be held confidential until after the formal licensee critique.

7. During performance of the drill/exercise, note any possible weaknesses and/or deficiencies you observe. To aid in future discussions, obtain documentation of licensee activities during questionable performance.

8. Based on your observations, form an opinion as to whether the licensee has still met the planning standards of 10 CFR 50.47(b) in spite of any deficiency or weakness.

9. Based on your observations, form an opinion as to whether the licensee has demonstrated the capability of providing reasonable assurance that adequate protective measures can be taken in the event of a declared emergency.

10. Discuss your emergency drill/exercise observations and opinions with the lead NRC inspector and provide your recommendation on whether licensee demonstrated the capability of providing reasonable assurance that adequate protective measures can be taken in the event of a declared emergency and if it has met the planning standards of 10 CFR 50.47(b).

11. Meet with your supervisor and/or a qualified senior emergency preparedness inspector to discuss any questions that you may have as a result of this activity and demonstrate that you can meet the evaluation criteria listed above.

DOCUMENTATION:	General Proficiency Qualification Signature Card Item OJTGeneral1

General Proficiency-Level Signature Card and Certification

Supervisor’s CertificationFor Basic Inspector Qualification	Signature/Date_____________________________

This signature card and certification must be accompanied by the appropriate Form 1, Basic Level Equivalency Justification, if applicable. (The electronic signature card, which is located on the Digital City SharePoint website is also acceptable.) Record completion in TMS by sending a request to TrainingSupportResource@nrc.gov.

Copies to:	InspectorSupervisor

Form 1: General Proficiency-Level Equivalency Justification

Supervisor’s Recommendation 	Signature/Date____________________________

Division Director’s Approval		Signature/Date____________________________

Copies to:	Inspector		Supervisor

Issue Date: 05/18/23	F1-1	1245 App B

	Attachment 1: Revision History for IMC 1245 Appendix B

Issue Date: 05/18/23	Att1-1	1245 App B