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NB/T 20001-2013Fabrication Rules for Mechanical Components of PWR Nuclear Island (English PDF)

压水堆核电厂核岛机械设备制造规范

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Issued by

NEA

Level / Type

Industry · Recommended

Issue date

June 8, 2013

Implementation date

October 1, 2013

Scope

NB/T 20001-2013 is the English-translated version of 压水堆核电厂核岛机械设备制造规范.

NB/T 20001-2013 is the Chinese standard "Fabrication Rules for Mechanical Components of PWR Nuclear Island".

Its scope clause reads: This standard specifies various requirements for identification; cutting and finishing without repair welding; forming and tolerance; assembly and alignment of welding part; heat exchanger pipe and pipe plate expanding connection; surface treatment, cleaning, flange bolt connection and heat treatment of mechanical components of PWR nuclear island within the specified range of GB/T 16702 during manufacturing process.

This standard is applicable to the manufacture of mechanical components of PWR nuclear island and the installation of on-site mechanical components of PWR nuclear island. Its clauses include terms and definitions.

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Document preview — NB/T 20001-2013

National Standard of the People's Republic of China

Replacing: EJ/T 1012-1996

Issued by: National Energy Administration of the People's Republic of China

Foreword i
1 Scope
2 Normative References
3 Terms and Definitions
4 General Provisions
5 Identification
5.1 General Requirements
5.2 Methods
5.3 Texts and Symbols
5.4 Temporary Identification
5.5 Label
5.6 Summary List of Identification
6 Cutting and Finishing without Repair Welding
6.1 Cutting
6.2 Finishing without Repair Welding
7 Forming and Tolerance
7.1 Forming
7.2 Tolerance
8 Assembly and Alignment of Welding Part
8.1 General Requirements
8.2 Assembly and Alignment Tolerance of Two-side Welding or One-side Accessible Single Side Welding Joints
8.3 Assembly and Alignment Tolerance of Welded Joints Welded at Outer Side in case of Inaccessible Internal Surface
8.4 Assembly and Alignment Tolerance of Butt Welding Head Welded Joint
8.5 Pipe and Pipeline Assembly and Alignment Tolerance
8.6 Out-of-tolerance Finishing
9 Heat Exchanger Pipe and Pipe Plate Expanding Connection
9.1 Overview
9.2 Expanding Connection
9.3 Inspection
9.4 Reworking
10 Surface Treatment
10.1 General Requirements
10.2 Chromate Finish
10.3 Manganous Phosphate Treatment (Phosphating)
10.4 Painting
10.5 Nitriding Treatment
10.6 Electrolytic Tinning and Diffusion Treatment
10.7 Cadmium Plating
10.8 Other Metal Cladding and Surface Treatment
11 Cleaning
11.1 Overview
11.2 Cleanliness Level, Work Area and On-site Work Zone of Nuclear Power Plant
11.3 Cleanliness Inspection
11.4 Contamination Prevention
11.5 Requirements for Cleaning Method
11.6 Maintenance of Cleanliness
12 Flange Bolt Connection
12.1 Overview
12.2 Procedure
12.3 Assembly Requirements
12.4 Requirements for the Lubricant
12.5 Requirements for Threads
12.6 Requirements for the Flange
12.7 Requirements for Assembling Tools
12.8 Surface Treatment for Fasteners
13 Heat Treatment
13.1 General Requirements
13.2 Heat Treatment after Forming
13.3 Post-welding Heat Treatment
13.4 Dimensional Stabilization Treatment of Unstable Austenitic Stainless Steel Piece
13.5 Bright Annealing of Austenitic Stainless Steel Pieces
Annex A (Normative) Forming Process Assessment
Annex B (Normative) Heat Exchanger Pipe and Pipe Plate Expanding Connection Process Assessment
Annex C (Normative) Test Method for Coating Film Assessment by Simulating LOCA Working Condition
Annex D (Normative) Test Method for the Influence of gamma Ray Irradiation on Coating Film
Annex E (Normative) Determination of Coating Film Decontaminability
Annex F (Normative) Cleanliness Inspection
Annex G (Normative) Water Quality
Annex H (Normative) Selection of Thermal Insulation Materials and Special Requirements for Installation
Annex I (Normative) Chemical Analysis Methods for the Contents of Chlorine, Fluorine and Sulfur
Bibliography

1 Scope

This standard specifies various requirements for identification; cutting and finishing without repair welding; forming and tolerance; assembly and alignment of welding part; heat exchanger pipe and pipe plate expanding connection; surface treatment, cleaning, flange bolt connection and heat treatment of mechanical components of PWR nuclear island within the specified range of GB/T 16702 during manufacturing process.

This standard is applicable to the manufacture of mechanical components of PWR nuclear island and the installation of on-site mechanical components of PWR nuclear island.

2 Normative References

The following referenced documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies.

GB/T 139-2008 Standard Method for Using the Ferrous Sulfat (Fricke) Dosimeter to Measure Absorbed Dose in Water

GB/T 912 Hot-rolled Sheets and Strips of Carbon Structural Steels and High Strength Low Alloy Structural Steels (GB/T 912-2008, ISO 4995: 2001, ISO 4996: 1996, NEQ)

GB/T 1766-2008 Paints and Varnishes - Rating Schemes of Degradation of Coats

GB/T 4956 Non-magnetic Coatings on Magnetic Substrates - Measurement of Coating Thickness - Magnetic Method (GB/T 4956-2003, ISO 2178: 1982 MOD)

GB/T 5270 Metallic Coatings on Metallic Substrates - Electrodeposited and Chemically Deposited Coatings - Revies of Methods Available for Testing Adhesion (GB/T 5270-2005, ISO 2819: 1980, IDT)

GB/T 7232 Terminology of Metal Heat Treatment

GB/T 8076 Concrete Admixtures

GB/T 8923-1988 Rust Grades and Preparation Grades of Steel Surfaces before Application of Paints and Related Products (ISO 8501.1: 1988, EQV)

GB/T 9271-2008 Paints and Varnishes Standard Panels for Testing (ISO 1514: 2004, MOD)

GB/T 11376-1997 Phosphate Conversion Coatings for Metals (ISO 9717: 1990, EQV)

GB/T 16702 Design Rules for Mechanical Components of PWR Nuclear Islands

GB/T 17569 Classification for the Items of Pressurized Water Reactor Nuclear Power Pants

NB/T 20002 (All Parts) Welding Code for Mechanical Components of PWR Nuclear Islands

NB/T 20003 (All Parts) Non-destructive Testing for Mechanical Components in Nuclear Island of Nuclear Power Plants

NB/T 20004 Physical and Chemical Test Methods for Materials Used in Nuclear Island Components of Nuclear Power Plants

ISO 4628.3: 1982 Paints and Varnishes - Evaluation of Degradation of Coatings - Designation of Quantity and Size of Defects, and of Intensity of Uniform Changes in Appearance - Part 3: Assessment of Degree of Rusting

3 Terms and Definitions

For the purposes of this standard, the terms and definitions given in GB/T 16702 and the following apply.

3.1 process fluid

liquid or gas with which each system or component is fully-filled during the normal operation of the nuclear power plant

3.2 thermal contraction

technology process of generating contraction distortion without adopting mechanical method during cooling the pipe fitting or pipe section after locally heating them.

3.3 corrosion resistant surface

component surface made of corrosion-resistant materials like austenitic stainless steel or nickel-based alloy and contacting or not contacting process fluid […]

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This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 83 pages — is available in the English PDF.

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Editions of NB/T 20001

Edition	Title	Revision	Status
NB/T 20001-2013	Fabrication Rules for Mechanical Components of PWR Nuclear Island	current edition	Current
EJ/T 1012-1996	Fabrication Rules for Mechanical Components of PWR Nuclear Island	previous edition	Superseded

This page sells the current edition, NB/T 20001-2013. Earlier editions are listed for reference only.

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