ML18047A475

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IMC 1245 Appendix D2 Inservice Inspection Advanced-Level Training
ML18047A475
Person / Time
Issue date: 08/23/2018
From: Alexander Schwab
NRC/NRR/DIRS/IRGB
To:
Schwab A
Shared Package
ML18047A106, ML18226A266 List:
References
CN 18-029, DC 18-011
Download: ML18047A475 (27)
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NRC INSPECTION MANUAL IRGB INSPECTION MANUAL CHAPTER 1245, APPENDIX D2 INSERVICE INSPECTION ADVANCED-LEVEL TRAINING Effective Date: 08/23/2018

Table of Contents INTRODUCTION ........................................ 1 OBJECTIVES OF ADVANCED-LEVEL TRAINING ............................... 1 REQUIRED TRAINING COURSES ..................................... 2 ISI GUIDANCE DOCUMENTS ............. 2 ISI INSPECTOR INDIVIDUAL STUDY ACTIVITIES ......... 6 Topic: (ISA-ISI-1) ASME Code Sections and Code Cases ........................................ 7 Topic: (ISA-ISI-2) Industry Initiatives for Material Degradation .................................. 9 Topic: (ISA-ISI-3) Reactor Pressure Vessel Head Penetrations .............................. 11 Topic: (ISA-ISI-4) Boric Acid Corrosion Control ....................................................... 12 Topic: (ISA-ISI-5) Steam Generator Examinations ........................................... ...13 ISI INSPECTOR ON-THE-JOB ACTIVITIES ADVANCED ISI TRAINING15 Topic: (OJT-ISI-1) NDE and Welding Inspection ..................................................... 16 Topic: (OJT-ISI-2) Reactor Pressure Vessel Penetrations Volumetric Inspection and Boric Acid Corrosion Control Program ........................................................... 19 Topic: (OJT-ISI-3) Steam Generator Tube Inspection ............................................. 21 ISI INSPECTOR ADVANCED-LEVEL SIGNATURE CARD23 FORM 1: ISI INSPECTOR ADVANCED-LEVEL EQUIVALENCY JUSTIFICATION..24 REVISION HISTORY SHEET FOR IMC 1245 APPENDIX D2..Att1-1 Issue Date: 08/23/18 i 1245 Appendix D2

Introduction Completion of the Reactor Engineering Inspector Technical Proficiency Qualification journal is strongly recommended before beginning activities or courses in this advanced-level training.

You may complete the General Proficiency requirements contained in Appendix B and the Technical Proficiency requirements in C-2 together with requirements in this training standard.

Completion of Inservice Inspection (ISI) Advanced Level Training is recommended for inspectors leading inservice inspections and for other inspectors conducting ISI inspection activities. Inspectors with demonstrated experience may be grandfathered in the completion of this journal, as determined by the appropriate branch chief.

Objectives of Advanced-Level Training Inservice inspection (ISI) programs are designed to identify service-induced degradation that might lead to leakage or result in the loss of integrity of a structure, system or component (SSC). Since a variety of inspection techniques can be used to assess the structural and leakage integrity of a SSC, an NRC inspector should have a general knowledge of the various techniques that can be used.

The objectives of this advanced voluntary training are:

To ensure the inspector is knowledgeable of the requirements pertaining to the ISI of nuclear power plant structures, systems and components (SSCs).

To ensure the inspector is knowledgeable about ISI techniques such that he/she can determine whether the techniques used are adequate to detect potential degradation that may be affecting that SSC.

To ensure the inspector is knowledgeable of staff positions and industry guidance related to ISI.

After completion of this training, the inspector should be capable of:

Developing informed questions such that he/she can perform effective and efficient inspections.

Communicating the finding of their inspections effectively and efficiently with management and with headquarters staff.

Reliably identifying ISI issues that should be brought to the attention of more senior regional inspectors or technical experts in Headquarters.

It is not the intent of this training standard to make the inspector an expert in assessing the structural and leakage integrity of each SSC in the plant.

Issue Date: 08/23/18 1 1245 Appendix D2

Required Training Courses

1. Nondestructive Examination (NDE) Technology and Codes (NRC Course E-306)
2. ASME Code Section XI - Inservice Inspection (PD-192)
3. E-118, Welding Technology and Codes (preferred)

OR

[ASME Code Section IX - Welding and Brazing Qualifications (Course ASME PD-190) AND ASME Practical Welding Technology Course (ASME Course PD-359)]

Additional training recommended to be completed within two years of qualification:

1. An advanced corrosion course
2. A fracture mechanics course
3. A quality assurance course
4. An advanced course(s) in ultrasonic examination that would count toward the training hours and course materials of the ASNT Recommended Practice SNT-TC-1A and/or ANSI/ASNT CP-189 guidelines for certification as a Level II ultrasonic examiner. Training course(s) should focus on ultrasound for nuclear weld examinations and substantially cover application of phased array ultrasound techniques and Section XI Appendix VIII qualified techniques.
5. An advanced course(s) in eddy current testing that would count toward the training hours and course materials of the ASNT Recommended Practice ASNT SNT-TC-1A and/or ANSI/ASNT CP-189 guidelines for certification as a Level II eddy current examiner. Training course(s) should focus on steam generator and heat exchanger tubing and include interpretation of data to meet the standards for a Qualified Data Analyst (QDA) in accordance with the EPRI S/G Examination Guidelines, Appendix G, for certification as a Level IIA QDA.
6. An advanced course(s) in radiographic examination that would count toward the training hours and course materials of the ASNT Recommended Practice SNT-TC-1A and/or ANSI/ASNT CP-189 guidelines for certification as a Level II in radiography. Training should focus on radiographic film interpretation for pipe and vessel welds.

ISI Guidance Documents The following include current and historical guidance documents applicable to inservice inspection activities. As such, many of these documents can be used as further reference and guidance for implementing the most up to date inspection procedures and regulatory requirements.

Inspection Procedures 49001 Inspection of Erosion-Corrosion/Flow Accelerated-Corrosion Monitoring Programs 50001 Steam Generator Replacement Inspection 50002 Steam Generators 50003 Pressurizer Replacement Inspection 55050 Nuclear Welding General Inspection Procedure 55100 Structural Welding General Inspection Procedure Issue Date: 08/23/18 2 1245 Appendix D2

55150 Weld Verification Checklist 57050 Nondestructive Examination Procedure Visual Examination 57060 Nondestructive Examination Procedure Liquid Penetrant 57070 Nondestructive Examination Procedure Magnetic Particle 57080 Nondestructive Examination Procedure Ultrasonic Examination 57090 Nondestructive Examination Procedure Radiographic Examination 61715 Verification of Containment Integrity 61720 Containment Local Leak Rate Testing 62002 Inspection of Structures, Passive Components, and Civil Engineering Features at Nuclear Power Plants 62003 Inspection of Steel and Concrete Containments at Nuclear Power Plants 70307 Containment Integrated Leak Rate Test - Procedure Review 70313 Containment Integrated Leak Rate Test 70323 Containment Leak Rate Test Results Evaluation 71111.08 Inservice Inspection Activities 71111.22 Surveillance Testing 73051 Inservice Inspection - Review of Program 73052 Inservice Inspection - Review of Procedures 73754 Preservice Inspection - Non-destructive Examination 73753 Inservice Inspection 73755 Inservice Inspection - Data Review and Evaluation 73756 Inservice Testing of Pumps and Valves Temporary Instructions (TIs) 2515/150, Revision 3: Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles (NRC Order EA-03-009) 2515/172: Reactor Coolant System Dissimilar Metal Butt Welds Inspection Manual Part 9900 Technical Guidance Mechanical: Steam Generator Tube Primary-to-Secondary Leakage ASME III & XI: Code Interpretations, Use of Engineering Judgment, Flaw Evaluation ASME IX: Welder Qualification ASME XIA: System Pressure Tests RG158: Qualification of Personnel Involved with Inspections SGTube: Steam Generator Plugs and Sleeving Repairs Issue Date: 08/23/18 3 1245 Appendix D2

Inspection Manual Chapter 0326, Operability Determinations & Functionality Assessments for Conditions Adverse to Quality or Safety Industry Guidance NEI 03-08 The Material Initiative Code Case N-770-x MRP-117: Materials Reliability Program Inspection Plan for Reactor Vessel Closure Head Penetrations in U.S. PWR Plants MRP 146 Management of Thermal Fatigue in Normal Stagnant Non-Isolable Reactor Coolant Lines MRP 192 Assessment of Residual Heat Removal Mixing Tee Thermal Fatigue in PWR Plants MRP 227 PWR Internals and Evaluation Guidelines MRP 228 Inspection Standard for PWR Internals BWRVIP-03: TR-105696-R9 Revision 9: BWR EPRI Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines BWRVIP-160: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2006 Update EPRI Steam Generator Management Program: Pressurized Water Reactor Steam Generator Examination Guidelines, most recent revision EPRI Steam Generator Integrity Assessment Guidelines, most recent revision ISI Requirements 10 CFR 50.55a ASME Code (Section II, III, V, and XI)

Standard Technical Specifications 3.0 incorporated with TSTF-449 Vol 1, B 3.4.20, and Section 5.5.9 (Steam Generator Program)

Standard Technical Specifications 3.0 incorporated with TSTP-449 Vol 2, B 3.4.20 10 CFR 50 Appendix A (GDC: 14, 30, 32) and B Regulatory Guides 1.14 Reactor Coolant Pump Flywheel Integrity 1.26 Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants 1.31 Control of Ferrite Content in Stainless Steel Weld Metal 1.34 Control of Electroslag Weld Properties 1.35 Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments 1.35.1 Determining Prestressing Forces for Inspection of Prestressed Concrete Containments 1.43 Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components 1.44 Control of the Use of Sensitized Stainless Steel 1.45 Reactor Coolant Pressure Boundary leakage Detection Systems 1.50 Control of Preheat Temperature for Welding of Low-Alloy Steel 1.65 Materials and Inspections for Reactor Vessel Closure Studs 1.71 Welder Qualification for Areas of Limited Accessibility 1.83 Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes 1.84 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III 1.85 Materials Code Case Acceptability 1.90 Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons Issue Date: 08/23/18 4 1245 Appendix D2

1.94 Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants 1.116 Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems 1.121 Bases for Plugging Degraded PWR Steam Generator Tubes 1.147 Inservice Inspection Code Case Acceptability ASME Section XI, Division 1 1.150 Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations 1.163 Performance-Based Containment Leak-Test Program 1.178 An Approach for Plant-Specific Risk-Informed Decisionmaking: Inservice Inspection of Piping 1.193 ASME Code Cases Not Approved for Use Staff positions/observations - Refer to the References Section of Inspection Procedure 71111.08, Inservice Inspection Activities Issue Date: 08/23/18 5 1245 Appendix D2

ISI Inspector Individual Study Activities Issue Date: 08/23/18 6 1245 Appendix D2

Advanced ISI Training Topic: (ISA-ISI-1) ASME Code Sections and Code Cases

Purpose:

The purpose of this ISA is to acquaint you with the organization and requirements pertaining to the ISI program contained in the ASME Code, applicable code cases, and 10 CFR 50.55a.

Competency Area: INSPECTION AREA TECHNICAL EXPERTISE REGULATORY FRAMEWORK Level Of Effort: 50 Hours

References:

1. ASME Section II, III, V, IX, XI
2. Regulatory Guide 1.147
3. Regulatory Guide 1.84
4. Regulatory Guide 1.193
5. Regulatory Guide 1.26
6. 10 CFR 50.55a
7.Section XI Code Case N-513-x
8. Generic Letter 90-05
9. Inspection Manual Chapter 0326, Operability Determinations & Functionality Assessments for Conditions Adverse to Quality or Safety Evaluation Criteria: Upon completion of the tasks in this activity, you will be asked to demonstrate your understanding of Section XI of the ASME Code, 10 CFR 50.55a, and other pertinent references as they pertain to the following:
1. The scope of 10 CFR 50.55a.
2. The process for licensees to obtain approval for relief from ISI requirements and the use of code cases.
3. Submission of a licensees ISI program to NRR.
4. The role of the Authorized Nuclear Inspector/Authorized Nuclear Inservice Inspector.
5. The three types of non-destructive examinations used during ISI and the specific techniques that fall under each of these categories.
6. The differences between a Level I, Level II, and Level III examiner.
7. The repair and replacement requirements contained in ASME Section XI article IWA-4000 (or IWA-7000 as applicable).

Issue Date: 08/23/18 7 1245 Appendix D2

8. The various types of system pressure tests and the general requirements associated with them including the examinations performed during these tests and their limitations.
9. The records and reports that must be submitted in accordance with ASME Section XI article IWA-6000 and 10 CFR 50.55a.
10. The Quality Group Classifications identified in Regulatory Guide 1.26 and the nuclear class 1, 2, and 3 classifications identified in ASME Section XI.
11. Describe the general organization of ASME Section XI Subsection IWB, IWC, IWD, IWE, IWF, and IWL and the materials/components to which these requirements apply.
12. The use of Section XI Appendix VIII qualified UT techniques, the relationship between Appendix VIII and the Performance Demonstration Initiative (PDI),

and how to determine when Appendix VIII requirements are applicable.

13. Temporary non-Code repairs.
14. The difference between a code of record and a code of construction.
15. Inspection Manual Chapter 0326, Operability Determinations & Functionality Assessments for Conditions Adverse to Quality or Safety Tasks: 1. Review the Table of Contents and Introduction for each ASME section II, III, V, IX and XI.
2. Review ASME Section XI Glossary (Article IW-9000), particularly definitions of indication, imperfection, flaw, discontinuity, defect, relevant condition, Authorized Nuclear Inservice Inspector.
3. Review Regulatory Guides 1.147, 1.84, 1.193, and 1.26 (quality group classifications).
4. Review Section XI Appendix VIII and 10 CFR 50.55a requirements pertaining to the use of Appendix VIII.
5. After reviewing the references in sufficient detail to perform adequately in accordance with the requirements of the Evaluation Criteria, meet with your supervisor, or the person designated to be your resource for this activity to discuss the answers to the questions listed in the Evaluation Criteria.

Documentation: ISI Inspector Advanced-Level Signature Card Item ISA-ISI-1 Issue Date: 08/23/18 8 1245 Appendix D2

Advanced ISI Training Topic: (ISA-ISI-2) Industry Initiatives for Material Degradation

Purpose:

The purpose of this ISA is to acquaint you with various industry initiatives that address material degradation mechanisms, inspection programs and techniques that evaluate degradation and techniques for mitigating the effects of material degradation.

Competency Area: INSPECTION AREA TECHNICAL EXPERTISE Level Of Effort: 50 Hours

References:

1. Code Cases N-770-x, N-729-x and N-722-x
2. BWR Vessel and Internal Program (BWR VIP) listed in the ISI Guidance Documents Section
3. NEI 03-08 The Material Initiative
4. MRP 146 Management of Thermal Fatigue in Normal Stagnant Non-Isolable Reactor Coolant Lines
5. MRP 192 Assessment of Residual Heat Removal Mixing Tee Thermal Fatigue in PWR Plants
6. MRP 227 PWR Internals and Evaluation Guidelines
7. MRP 228 Inspection Standard for PWR Internals Evaluation Criteria: Review the references in sufficient detail to demonstrate:
1. Understanding of industry initiatives in regards to study and mitigation of material degradation mechanisms.
2. Understanding of examination guidelines for reactor pressure vessels and internals.
3. Describe industry operating experience with PWSCC, IGSCC and erosion/corrosion and flow accelerated corrosion.

Tasks: 1. Review Code Cases N-770-x, N-729-x and N-722-x

2. Review BWR VIPs listed in the reference listing.
3. Review NEI 03-08.

Issue Date: 08/23/18 9 1245 Appendix D2

4. Review MRP 146, MRP 192, MRP 227 and MRP 228.
5. Meet with your supervisor, or the person designated to be your resource for this activity to discuss any questions you may have as a result of this activity and to demonstrate that you can meet the evaluation criteria for this activity.

Documentation: ISI Inspector Advanced-Level Signature Card Item ISA-ISI-2 Issue Date: 08/23/18 10 1245 Appendix D2

Advanced ISI Training Topic: (ISA-ISI-3) Reactor Pressure Vessel Head Penetrations

Purpose:

The purpose of this ISA is to acquaint you with the history of reactor pressure vessel head penetration degradation, regulatory requirements for inspection, and inspection techniques employed during reactor pressure vessel head inspections.

Competency Area: INSPECTION AREA TECHNICAL EXPERTISE ASSESSMENT AND ENFORCEMENT Level Of Effort: 50 Hours

References:

All the documents listed in the ISI Guidance Documents Section are appropriate for this activity as well as those specifically listed below in the Tasks Section.

Evaluation Criteria: Review the references in sufficient detail to demonstrate:

1. Knowledge of the requirements for inspection of Reactor Pressure Vessel Heads for PWRs.
2. Capabilities and limitations of ultrasonic inspections systems.
3. Basic understanding of various inspection techniques used by licensees in inspection of Reactor Pressure Vessel Heads for PWRs.

Tasks: 1. Review NRC Order EA-03-009 Revision 1.

2. Review Section XI code case N-729-x and 10 CFR 50.55a(g)(6)(ii)(d).
3. Obtain and review RPVH Penetration information from the ISI Best Practices website (http://www.internal.nrc.gov/RES/projects/ISI/).
4. Review and discuss with an ISI inspector NUREG/CR-5985/PNL-8919, Evaluation Of Computer-Based Ultrasonic Inservice Inspection Systems.
5. Review MRP-117: Materials Reliability Program Inspection Plan for Reactor Vessel Closure Head Penetrations in U.S. PWR Plants.
6. Meet with your supervisor, or the person designated to be your resource for this activity to discuss any questions you may have as a result of this activity and to demonstrate that you can meet the evaluation criteria for this activity.

Documentation: ISI Inspector Advanced-Level Signature Card Item ISA-ISI-3 Issue Date: 08/23/18 11 1245 Appendix D2

Advanced ISI Training Topic: (ISA-ISI-4) Boric Acid Corrosion Control

Purpose:

The purpose of this ISA is to acquaint you with the inspection activities contained in Inspection Procedure 57050, Visual Testing Examination, and with the NRC staff and industry positions related to the boric acid corrosion control program.

Competency Area: INSPECTION AREA TECHNICAL EXPERTISE ASSESSMENT AND ENFORCEMENT Level Of Effort: 50 Hours

References:

1. Inspection Procedure 57050, Visual Testing Examination
2. EPRI Boric Acid Corrosion Guideline
3. As listed in the Tasks Section below.

Evaluation Criteria: Review the references in sufficient detail to demonstrate:

1. Knowledge of inspection procedures and industry guidance concerning boric acid inspection programs.
2. Knowledge of effects of boric acid corrosion and susceptible penetrations on the reactor vessel head.
3. Describe industry operating experience with boric acid corrosion (including the Davis-Besse event).

Tasks: 1. Review and discuss with an experienced ISI inspector, WCAP 15988-NP, Generic Guidance for an Effective Boric Acid Inspection Program for Pressurized Water Reactors.

2. Review and discuss with an experienced ISI inspector, GL-88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants.
3. Complete the on-line training course entitled Effects of Corrosion. This course is accessed through the NRC Training and Development web site.
4. Meet with your supervisor, or the person designated to be your resource for this activity to discuss any questions you may have as a result of this activity and to demonstrate that you can meet the evaluation criteria for this activity.

Documentation: ISI Inspector Advanced-Level Signature Card Item ISA-ISI-4 Issue Date: 08/23/18 12 1245 Appendix D2

Advanced ISI Training Topic: (ISA-ISI-5) Steam Generator Examinations

Purpose:

The purpose of this ISA is (1) to familiarize you with inspection activities in Inspection Procedure 71111.08, Inservice Inspection Activities, and (2) to familiarize you with NRC staff and industry positions related to the inspection of steam generator tubes.

Competency Area: INSPECTION AREA TECHNICAL EXPERTISE ASSESSMENT AND ENFORCEMENT Level Of Effort: 50 Hours

References:

As listed in the Tasks Section below.

Evaluation Criteria: Review the references in sufficient detail to demonstrate:

1. Knowledge of inspection procedures and industry guidance concerning steam generator inspection programs.
2. Knowledge of the factors and conditions that cause degradation of steam generator tubes.
3. Guidelines and standards used to evaluate degraded steam generator tubes.
4. Acceptable repair techniques for steam generator tubes.

Tasks 1. Review and discuss with an experienced ISI inspector, EPRI Pressurized Water Reactor Steam Generator Examination Guidelines.

2. Review and discuss with an experienced ISI Inspector, EPRI Steam Generator Integrity Assessment Guidelines.
3. Review and discuss with an experienced ISI Inspector the Standard Technical Specifications applicable to steam generator tube inspections.
4. Review and discuss with an experienced ISI Inspector, IP 71111.08 sections associated with steam generator inspections.
5. Review and discuss Inspection Manual Chapter 0609, Appendix J, with an experienced inspector.
6. Meet with your supervisor, or the person designated to be your resource for this activity to discuss any questions you may have as a result of this activity and to demonstrate that you can meet the evaluation criteria for this activity.

Issue Date: 08/23/18 13 1245 Appendix D2

Documentation: ISI Inspector Advanced-Level Signature Card Item ISA-ISI-5 Issue Date: 08/23/18 14 1245 Appendix D2

ISI Inspector On-the-Job Activities Issue Date: 08/23/18 15 1245 Appendix D2

Advanced ISI Training Topic: (OJT-ISI-1) NDE and Welding Inspection

Purpose:

The purpose of this OJT is to acquaint you with the organization and requirements pertaining to the ISI program contained in the ASME Code and applicable code cases.

Competency Area: INSPECTION AREA TECHNICAL EXPERTISE PROBLEM ANALYSIS ASSESSMENT AND ENFORCEMENT COMMUNICATION INSPECTION Level Of Effort: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />

References:

All the references used in the ISAs and those listed in the ISI Guidance Documents Section are appropriate for this activity. Most of the efforts in this OJT will rely on licensee procedures and related regulatory documents (Technical Specifications, Orders, FSAR, etc.). Any references used other than licensee procedures will be used to determine the regulatory stance that has been historically applied by the NRC for a given situation. References selected should support the actual inspection efforts.

Evaluation Criteria:

1. Describe required elements of an ISI program and be able to identify what interval and period the licensee is in at the time of the OJT.
2. Identify the NDE samples required by IP 71111.08, and describe key elements of each type of NDE inspection identified in ASME Section XI.
3. Describe the capabilities and limitations of the NDE inspections you observed (specific technique limitations and/or limitations due to component design or location), and identify the advantages and disadvantages of each.
4. Describe the licensees indication evaluation process and whether the indications were evaluated in accordance with the procedure requirements and industry and NRC guidance.
5. Describe the licensees flaw acceptance criteria.
6. Describe the ASME Code requirements utilized by the licensee in its welding process:
a. The interaction between Sections II, III, IX, and XI where welding is concerned.

Issue Date: 08/23/18 16 1245 Appendix D2

b. The difference between Essential, Supplementary Essential, and Non-Essential variables, and how to identify what each is for a welding process.
c. Similarities and differences between qualification of a welder/weld operator and qualification of a weld procedure.
7. Discuss the use of ASME Section II and the licensees quality assurance program as it pertains to control of material in the welding process.
8. Choose a relief request submitted by the licensee within the last year pertaining to welding activities and discuss the following:
a. Exceptions requested by the licensee
b. Use of code cases within the relief request
c. The NRCs Safety Evaluation Report Tasks: 1. Review the licensees ISI Program (ASME Section XI program).
2. Review a sample of the licensees NDE procedures for commonly used NDE techniques:
a. UT - PDI qualified
b. UT - other than PDI qualified
c. PT
d. MT
e. VT-1
f. VT-2
g. VT-3
3. Observe the calibration of an UT system.
4. Review a copy of the licensees Written Practice, and verify that qualifications for a sample of NDE Technicians are adequate for the following forms of NDE:
a. UT - PDI qualified
b. UT - non-PDI qualified
c. PT
d. MT
e. VT-1
f. VT-2
g. VT-3
5. Observe the licensees performance of several different NDE activities and compare the activities against licensee procedures.
6. Compare recordable indications to IWX-3000 or applicable acceptance criteria and verify if the licensee dispositioned the indications appropriately in accordance with ASME Code requirements.

Issue Date: 08/23/18 17 1245 Appendix D2

7. Review welding packages for completeness. Verify WPS/PQRs against the ASME Code.
8. Review recent corrective action documents related to welding and NDE.
9. Meet with your supervisor, or the person designated to be your resource for this activity to discuss any questions you may have as a result of this activity and to demonstrate that you can meet the evaluation criteria for this activity.

Documentation: ISI Inspector Advanced-Level Signature Card OJT-ISI-1 Issue Date: 08/23/18 18 1245 Appendix D2

Advanced ISI Training Topic: (OJT-ISI-2) Reactor Pressure Vessel Penetrations Inspection and Boric Acid Corrosion Control Program

Purpose:

The objective of this OJT is to prepare the inspector to review and evaluate a licensees performance in assessing the condition of the vessel head penetrations. This OJT will familiarize the inspector with (1) inspection activities in Inspection Procedure 71111.08, Inservice Inspection Activities, and (2) NRC staff and industry positions related to the inspection of vessel head penetrations.

Competency Area: INSPECTION AREA TECHNICAL EXPERTISE PROBLEM ANALYSIS ASSESSMENT AND ENFORCEMENT COMMUNICATION INSPECTION Level Of Effort: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />

References:

All the references used in the ISAs and those listed in the ISI Guidance Documents Section are appropriate for this activity. Most of the efforts in this OJT will rely on licensee procedures and related regulatory documents (Technical Specifications, Orders, FSAR, etc.). Any references used other than licensee procedures will be used to determine the regulatory stance that has been historically applied by the NRC for a given situation. References selected should support the actual inspection efforts.

Evaluation Criteria: Upon completion of this OJT, you should be able to:

1. Describe industry experience with vessel head degradation.
2. Describe the scope and extent of the inspections including the inspections of the weld and nozzle base material.
3. Describe the requirements for performing examinations of the vessel head penetrations including personnel and technique qualification.
4. Describe the capabilities and limitations of the inspections performed.
5. Describe the licensees indication evaluation process and whether the indications were evaluated in accordance with the procedure requirements and industry and NRC guidance.
6. Describe the licensees flaw acceptance criteria and repair process.

Issue Date: 08/23/18 19 1245 Appendix D2

Tasks 1. Read the references in sufficient detail to perform adequately in accordance with the requirements of the Evaluation Criteria.

2. Perform the tasks outlined in the RPVH section of IP 71111.08.
3. Observe an NDE technician perform data acquisition.
4. Review electronic data results with an NDE analyst.
5. Review the licensees head susceptibility calculations (both effective degradation years and reinspection years).
6. Review at least two licensee boric acid evaluations.
7. Conduct a boric acid walk-down.
8. Review a licensees boric acid program.
9. Review corrective action documents related to boric acid.
10. Meet with your supervisor, or the person designated to be your resource for this activity to discuss any questions you may have as a result of this activity and to demonstrate that you can meet the evaluation criteria for this activity.

Documentation: ISI Inspector Advanced-Level Signature Card Item OJT-ISI-2 Issue Date: 08/23/18 20 1245 Appendix D2

Advanced ISI Training Topic: (OJT-ISI-3) Steam Generator Tube Inspection

Purpose:

The objective of this OJT is to prepare the inspector to review and evaluate licensees performance in assessing the condition of the steam generator tubes.

This OJT will familiarize the inspector with (1) inspection activities in Inspection Procedure 71111.08, Inservice Inspection Activities, and (2) NRC staff and industry positions related to the inspection of steam generator tubes.

Competency Area: INSPECTION AREA TECHNICAL EXPERTISE PROBLEM ANALYSIS ASSESSMENT AND ENFORCEMENT COMMUNICATION INSPECTION Level Of Effort: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />

References:

All the references used in the ISAs and those listed in the ISI Guidance Documents Section are appropriate for this activity. Most of the efforts in this OJT will rely on licensee procedures and related regulatory documents (Technical Specifications, Orders, FSAR, etc.). Any references used other than licensee procedures will be used to determine the regulatory stance that has been historically applied by the NRC for a given situation. References selected should support the actual inspection efforts.

Evaluation Criteria: Upon completion of this OJT, you should be able to:

1. Describe industry experience with steam generator tube degradation.
2. Describe the requirements for performing examinations of the steam generator tubes including personnel and technique qualification.
3. Describe the capabilities and limitations of the inspections performed.
4. Describe the licensees indication evaluation process and whether the indications were evaluated in accordance with the procedure requirements and industry and NRC guidance.
5. Describe the licensees flaw acceptance criteria and repair process.
6. Describe the licensees last operational assessment and identify how it influenced the length of operation in between steam generator inspections as well as the type and extent of inspections planned for the current outage.
7. Review corrective action documents related to SG tube examinations.

Issue Date: 08/23/18 21 1245 Appendix D2

8. Describe the licensees condition monitoring assessment. If it was not complete at the time of the inspection, discuss the licensees plans/expectations for the condition monitoring assessment based on inspection results to date.

Tasks: 1. Monitor an NDE Technician during data acquisition.

2. Review electronic data results with an NDE analyst.
3. Review the licensees steam generator degradation assessment.
4. Review the last steam generator operational assessment conducted by the licensee.
5. Review the licensees condition monitoring assessment.
6. Review the licensees repair criteria for degraded tubes.
7. Meet with your supervisor, or the person designated to be your resource for this activity to discuss any questions you may have as a result of this activity and to demonstrate that you can meet the evaluation criteria for this activity.

Documentation: ISI Inspector Advanced-Level Signature Card Item OJT-ISI-3 Issue Date: 08/23/18 22 1245 Appendix D2

ISI Inspector Advanced-Level Signature Card Employee Supervisor's Inspector Name: __________________________________

Initials/Date Signature/Date A. Training Courses E-306, Nondestructive Examination (NDE) Technology and Codes ASME Code Section XI - Inservice Inspection (PD-192)

E-118, Welding Technology and Codes (preferred)

OR

[ASME Code Section IX - Welding and Brazing Qualifications (Course ASME PD-190) AND ASME Practical Welding Technology Course (ASME Course PD-359)]

B. Individual Study Activities ISA-ISI-1 ASME Code Sections and Code Cases ISA-ISI-2 Industry Initiatives for Material Degradation ISA-ISI-3 Reactor Pressure Vessel Head Penetrations ISA-ISI-4 Boric Acid Corrosion Control ISA-ISI-5 Steam Generator Examinations C. On-the-Job Training Activities 1)

OJT-ISI-1 NDE and Welding Inspection 2) 3)

OJT-ISI-2 RPVH Penetrations Volumetric Inspection 1)

OJT-ISI-3 Steam Generator Tube Inspection 2)

Note that for OJTs 1 and 3 there are multiple initials/signature lines. The intent is for the inspector to accompany a minimum of 3 inservice inspections for NDE and Welding activities, and a minimum of 2 steam generator inspections. At least one inspection accompaniment for volumetric examination of RPVH penetrations should be completed.

Note that all training courses are one week, except for E-306, which is two weeks.

Supervisors signature indicates successful completion of all required courses and activities listed in this training standard.

Supervisors Signature_____________________________________Date:___________

Issue Date: 08/23/18 23 1245 Appendix D2

Form 1: ISI Inspector Advanced-Level Equivalency Justification Identify equivalent training and experience for which the Inspector Name: __________________________________

inspector is to be given credit A. Training Courses E-306, Nondestructive Examination (NDE) Technology and Codes ASME Code Section XI - Inservice Inspection (PD-192)

E-118, Welding Technology and Codes (preferred)

OR

[ASME Code Section IX - Welding and Brazing Qualifications (Course ASME PD-190) AND ASME Practical Welding Technology Course (ASME Course PD-359)]

B. Individual Study Activities ISA-ISI-1 ASME Code Sections and Code Cases ISA-ISI-2 Industry Initiatives for Material Degradation ISA-ISI-3 Reactor Pressure Vessel Head Penetrations ISA-ISI-4 Boric Acid Corrosion Control ISA-ISI-5 Steam Generator Examinations C. On-the-Job Training Activities 1) 2)

OJT-ISI-1 NDE and Welding Inspection 3)

OJT-ISI-2 RPVH Penetrations Volumetric Inspection 1)

OJT-ISI-3 Steam Generator Tube Inspection 2)

Note that for OJTs 1 and 3 there are multiple initials/signature lines. The intent is for the inspector to accompany a minimum of 3 inservice inspections for NDE and Welding activities, and a minimum of 2 steam generator inspections. At least one inspection accompaniment for volumetric examination of RPVH penetrations should be completed.

Supervisors signature indicates successful completion of all required courses and activities listed in this training standard.

Supervisors Signature_____________________________________Date:___________

Issue Date: 08/23/18 24 1245 Appendix D2

Attachment 1 Revision History Sheet for IMC 1245 Appendix D2 Commitment Accession Description of Change Description of Comment Resolution Tracking Number Training and Closed Resolution Number Issue Date Required and Feedback Form Change Notice Completion Date Accession Number (Pre-Decisional, Non-Public Information)

N/A ML090360523 Initial issuance None ML091590710 07/08/09 CN-09-017 N/A ML15177A330 This revision updates format and adds training, as None ML15195A203 10/21/15 recommended, on ultrasonic examination, eddy Closed FF:

CN 15-020 current testing, and radiographic examination to more 1245D2-1940 completely define an expert level of knowledge. ML15078A281 N/A ML18047A475 This revision updates references, as well as offers None ML18065A660 08/23/18 flexibility in completing some of the training Closed FF:

CN 18-029 requirements, by offering the option to take E-118 in 1245D2-2257 lieu of PD-190 and PD-359. ML18134A060 1245D2-2302 ML18226A257 Issue Date: 08/23/18 Att1-1 1245 Appendix D2

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