KEPIC/ASME Joint Seminar

The Latest Developments of ASME Boiler and

Pressure Vessel Code Section III

Rules for Construction of Nuclear Facility Components

Christian Sanna

Director, Nuclear Codes and Standards

ASME

2017 Edition of ASME BPVC Section III

ASME BPV Code 2017 Edition

Issued July 2017

2017 Edition of ASME BPVC Section III

• Subsection NCA: General Requirements for Divisions 1 and 2

• Division 1: Class 1, 2 , 3 & MC Components, Supports, and Core Support Structures [Subsections NB, NC, ND, NE, NF, NG*]

• Division 2: Concrete Containments

• Division 3: Containment Systems for Transportation and Storage of Spent Nuclear Fuel and High-Level Radioactive Material

• Division 4: Fusion Energy Devices (in development)

• Division 5: High Temperature Reactors

Notable Changes in the 2017 Edition

ASME Boiler and Pressure Vessel Code Section III

1. Subsection NH Discontinued / Div. 5: High Temperature Reactors

• Division 1 Subsection NH, Class 1 Components in Elevated Temperature Service is now discontinued; it is not offered as part of the 2017 Edition.

• The content of Subsection NH was incorporated into BPV III, Division 5, Part HBB.

• The migration of the rules was complete in the 2015 edition, however ASME continued to offer the Subsection NH as part of the 2015 Edition.

2. Ongoing “reorganization” of Subsection NCA

• Phase 1 is complete and published in the 2017 Edition.

• Quality System requirements for Material Organizations have been moved:

o From NCA-3850 to NCA-4200 Metallic Quality System Program

Requirements

o From NCA-3950 to NCA-4300 Nonmetallic Material Manufacturer’s

and Constituent Supplier’s Quality

System Program Requirements

o From NCA-3970 to NCA-4400 Polyethylene Material Organization's

Quality System Program

2. Ongoing “reorganization” of Subsection NCA

• Phase 2 is on schedule to be published in the 2019 Edition.

o Certificate Holders requirements in NCA-3100 through NCA-3700 will be reorganized.

o The current “Certificate oriented” presentation of the requirements will be reorganized into “Requirements oriented” presentation format.

o The format will be similar to the presentation of Welding Variables requirements found in BPVC Section IX, such as in QW-250.

cont’d

3. Ongoing “reorganization” of Subsection NCA

• Phase 3 is intended to be published in the 2019 Edition in conjunction with Phase 2, or possibly in the 2021 Edition.

o Material Organization Certificate Holders requirements in NCA-3800 through NCA-3900 will be reorganized.

o Similar to NCA-3100 through NCA-3700 (Phase 2), the current “Certificate oriented” presentation of the requirements will be reorganized into “Requirements oriented” presentation format

4. Introduction of “Certifying Engineer”

• The designation of the individual tasked with certifying design documents on behalf of the Owner and N-Certificate Holder has been changed.

• The designated individual was formerly described as a “Registered Professional Engineer” registered in a state of the United States or a province of Canada. Other requirements pertaining to work experience and ASME Code knowledge applied.

4. Introduction of “Certifying Engineer”

• In the 2017 Edition, the designated individual is now a “Certifying Engineer”. The eligibility is expanded to include Chartered, Registered, or Licensed Engineers from many other jurisdictions.

• Work experience and ASME Code knowledge requirements still apply. Certain elements of the qualification that were previously non-mandatory are now mandatory.

cont’d

5. Mandatory Appendix XIII Design Based on Stress Analysis

• Appendix XIII Design Based on Stress Analysis has been entirely rewritten.

• The revision consolidates, simplifies and modernizes the “Design Based on Analysis” rules in Section III, incorporating much of the rules from NB-3200 Design by Analysis and all of Mandatory Appendix XIV Design Based on Fatigue Analysis

5. Mandatory Appendix XIII Design Based on Stress Analysis

• The goal is for Appendix XIII to be the single reference with Section III for most of the low temperature design by analysis rules for metallic materials.

• Various Section III subsections will reference Appendix XIII as much as practical.

• Mandatory Appendix XIV Design Based on Fatigue Analysis has been deleted.

cont’d

6. New Appendix XXVII Design By Analysis for Service Level D

• A new Mandatory Appendix XXVII Design By Analysis for Service Level D, was introduced. It provides design by analysis rules to evaluate components subjected to loads for which Level D Service Limits are specified.

• The Level D design rules in Appendix XXVII are provided to limit the consequences of the loads for which Level D Service Limits are specified in the Design Specification.

6. New Appendix XXVII Design By Analysis for Service Level D

• Appendix XXVII was partly derived from Non-Mandatory Appendix F, which is planned for deletion in the 2019 Edition. References to Appendix F throughout Section III have already been updated to reference Appendix XXVII.

• Level D component design rules have been transferred into their respective Section III subsections.

cont’d

7. New Div. 3 Subsection WD Class ISS Internal Support Structures

• Subsection WD establishes rules for construction of internal support structures for use in transportation (Class TC) or storage (Class SC) containments.

• Subsection WD covers the requirements for strength integrity of items, the failure or excessive deformation of which would cause loss of geometric configuration of the containment contents.

Roadmaps for Possible Future Actions

ASME BPV III Committee on Construction of Nuclear

Facility Components

• Consolidation of Conformity Assessment requirements into ASME standard CA-1.

• Consolidation of Pressure Relief requirements into BPV Code Section XIII.

• Fatigue Roadmap

oPotentially reduce excess conservatism in fatigue evaluation where appropriate, and enhance understanding of affects in the LWR environment.

oAction plan to produce alternate methods to predict crack initiation and crack growth due to cyclic loadings and maintain objective of demonstrating the design prevents a through-wall crack.

Roadmaps for Possible Future Actions

OPERATIONAL STATUS

ASME BPV III Committee on Construction of Nuclear

Facility Components

• BPV III Standards Committee convened a meeting in Busan, Korea in October 2011.

• BPV III Standards Committee and the ASME Board on Nuclear Codes and Standards held meetings and workshop in Shanghai, China in September 2016.

• BPV III Standards Committee is now considering locations for the next meeting outside of North America.

• Five International Working Groups (IWGs) support BPV Section III development: Korea, China, Argentina, Germany, India.

Operational Status: ASME BPV III Committee