GB/T 16702.1-2025Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants — Part 1: General principle (English PDF)

Foreword

This document is in accordance with the provisions of GB/T 1.1-2020 "Guidelines for standardization work Part 1: Structure and drafting rules for standardization documents" Drafting.

This document is part 1 of GB/T 16702 "Design Specifications for Mechanical Equipment of Nuclear Island in Pressurized Water Reactor Nuclear Power Plant".

The following parts are published.

— Part 1: General;

— Part 2: Class 1 equipment;

— Part 3: Level 2 equipment;

— Part 4: Level 3 equipment;

— Part 5: Small equipment;

— Part 6: Reactor internals;

— Part 7: Equipment support;

— Part 8: Low-pressure or atmospheric pressure storage tanks.

This document partially replaces GB/T 16702-2019 "Design Specification for Mechanical Equipment of Nuclear Island of Pressurized Water Reactor Nuclear Power Plant" and GB/T 16702- Compared with 2019, in addition to structural adjustments and editorial changes, the main technical changes are as follows.

— Changed the scope of application of this document (see Chapter 1, Chapter 1 of the 2019 edition);

— Added normative references to GB/T 4960.2, HAD003/08, HAF003, HAF601, and HAF603 (see Chapter 3, 6.8.1, Chapter 7, Appendix N);

— Deleted the relevant provisions of "Handling of Non-Conformities" (see 4.2 of the 2019 edition);

— Deleted the relevant provisions of "Parts List" and "Deviation Report" (see 4.3.2.2, 4.3.6.2 of the 2019 edition);

— Added relevant requirements for "small equipment" (see 5.2.1.2, Table 1);

— Changed the relevant requirements for "weld classification" (see 5.2.4, 4.4.2.5 of the 2019 edition);

— Added the main content of "Equipment Design Specification" (see 6.1);

— Deleted "Level 1 equipment", "Level 2 equipment", "Level 3 equipment", "small equipment", "core components", "equipment support", "low pressure or normal pressure storage "Cans" (see Chapters 5 to 11 of the 2019 edition);

— Changed the material grades and their corresponding material standard numbers, performance data, allowable stress values, fatigue curve data and fatigue curves (see

1 Scope

This document specifies the general requirements for the design of mechanical equipment of nuclear island in PWR nuclear power plants.

This document is applicable to the design of mechanical equipment (pressure-bearing equipment and its supports, internal components) of nuclear island in PWR nuclear power plant.

2 Normative references

The contents of the following documents constitute the essential provisions of this document through normative references in the text. Among them, only the version corresponding to the date is applicable to this document for the referenced documents with a date; The latest version of the undated referenced document (including all amendments) is applicable to this document.

GB/T 1954 Methods of measurement for ferrite content in austenitic Cr-Ni stainless steel weld metals

GB/T 4960.2 Glossary for nuclear science and technology - Part 2: Fission reactor

GB/T 16702 (all parts) Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants

GB/T 16702.2-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 2: Class 1 components

GB/T 16702.3-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 3: Class 2 components

GB/T 16702.4-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 4: Class 3 components

GB/T 16702.5-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 5: Small components

GB/T 16702.6-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 6: Reactor vessel internals

GB/T 16702.7-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 7: Supports

GB/T 16702.8-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 8: Low pressure or atmospheric storage tanks

3 Terms and Definitions

The terms and definitions defined in GB/T 4960.2 and the following apply to this document.

4 General requirements

The design of mechanical equipment of nuclear island in PWR nuclear power plant shall be implemented in accordance with the provisions of GB/T 16702 (all parts).

The version and supplementary provisions of this document should be specified in the equipment specification and order contract, and the purchase contract prepared by the equipment manufacturer should adopt the same version of this document.

Units engaged in design activities can adopt methods different from those given in the "Informative Appendix" of this document, but they should prove in advance that they can achieve the specified purpose and abide by the provisions of the contract and ancillary documents.

8 Use of parts of GB/T 16702

Annex A (Normative) Properties of Design Materials

Annex B (Normative) Experimental Stress Analysis

Annex C(Normative) Determination of basic allowable stress limits

Annex D (Normative) Design rules for equipment subjected to external pressure

Annex E (Normative) Design of Circular Flange Bolted Connection

Annex F (Normative) Design Rules for Linear Supports

Annex G (Normative) Class 1 Container Opening Reinforcement Rules

Annex H (Informative) Fatigue Analysis of Significant Geometric Discontinuities

Annex I (Informative) Other Rules for Class I Pipeline Analysis

Annex J (informative) Relevant rules for Class D guidelines

Annex K (INFORMATIVE) Prevention of Rapid Fracture

Annex L (informative) Rules to be followed for determining usage factors

Annex M (Normative) Supplementary Requirements for Materials

Annex N (Normative) Acceptance of supporting welding filler materials and welding process qualification

Annex O (Informative) Stress Analysis Methods

Annex P (Informative) Dynamic Analysis Method

Annex Q (Informative) Design Qualification of Rectangular and Circular Section Welded Accessories on Class 1, 2 and 3 Piping

Annex R (informative) Allowable installation deviations for review after completion of piping system