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GB/T 36041-2018Monitoring criteria for variable important to safety in nuclear power plants for pressurized water reactors (English PDF)

压水堆核电厂安全重要变量监测准则

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Issued by

SAMR; SAC

Level / Type

National · Recommended

Issue date

March 15, 2018

Implementation date

October 1, 2018

Scope

GB/T 36041-2018 is the English-translated version of 压水堆核电厂安全重要变量监测准则.

GB/T 36041-2018 is the Chinese guide to monitoring the variables important to safety in pressurized water reactor nuclear power plants. It sets the principles for choosing these variables and the basic requirements for the layout, characteristics and qualification of the instruments that monitor them.

Clauses cover monitoring requirements in general and then the core and control rod positions, the reactor coolant system, the secondary loop, containment, the spent fuel pool, the component cooling water system, radiation inside the plant and severe accidents.

It applies to the design of safety monitoring systems for PWR plants and may be used as a reference for innovative PWR designs. It relies on standards for accident monitoring, radiation monitoring, single failure and equipment qualification. It was issued on 15 March 2018 and has applied since 1 October 2018.

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Document preview — GB/T 36041-2018

National Standard of the People's Republic of China

ICS
27.120.20
Classification
F 83

Issued by: State Administration for Market Regulation; Standardization Administration of the PRC

Contents

  • Preface
  • 1 Scope
  • 2 Normative references
  • 3 Terms and Definitions
  • 4 Safety Critical Variables Monitoring Requirements
  • 5 Core and Control Rod Position Monitoring
  • 6 Reactor Coolant System Monitoring
  • 7 Two-loop system monitoring
  • 8 Containment System Monitoring
  • 9 Spent Fuel Storage Tank Monitoring
  • 10 Equipment Cooling Water System Monitoring
  • 11 In-plant radiation monitoring
  • 12 Severe accident monitoring

Foreword

This standard was drafted in accordance with the rules given in GB/T 1.1-2009.

1 Scope

This standard stipulates the principles for determining the important safety variables of PWR nuclear power plants and the basics of the layout, characteristics, and appraisal of monitoring instruments. Claim.

This standard applies to the design of an important safety monitoring system for PWR nuclear power plants. Innovative PWR nuclear power plants can be used as reference.

2 Normative references

The following documents are indispensable for the application of this document. For dated references, only dated versions apply to this document. For undated references, the latest version (including all amendments) applies to this document.

GB/T 5204 Nuclear Power Plant Safety System Periodic Test and Monitoring

Characteristics and test methods of thermometers in reactor core and main coolant circuit of nuclear power plant GB/T 7166

GB/T 8995 nuclear reactor neutron fluence rate measurement core instrument

GB/T 12726.1 Nuclear power plant safety - Important instrumentation accidents and post-accident radiation monitoring - Part 1. General requirements

GB/T 12726.3 Nuclear power plant safety - Important instrumentation accidents and post-accident radiation monitoring - Part 3. High-range area gamma continuous monitoring Measuring equipment

GB/T 12726.4 Nuclear power plant safety-related instrumental accidents and post-accident radiation monitoring - Part 4. Inside or downstream of process flow tubes Radioactive continuous monitoring equipment

GB/T 12727 Nuclear Power Plant Safety Grade Electrical Equipment Appraisal

GB/T 13626 single failure criterion applied to nuclear power plant safety system

GB/T 13627 Guidelines for Accident Monitoring Instruments for Nuclear Power Plants

GB/T 13632 Supervising the measurement requirements for adequate cooling of pressurized water reactor cores

GB/T 15474 Classification of Safety Instruments and Control Functions for Nuclear Power Plants

EJ/T 561 Guidelines for Safe Shutdown Design of PWR Nuclear Power Plants

EJ/T 1180 Design Guidelines for Fixed Radiation Monitoring System of Pressurized Water Reactor Nuclear Power House

NB/T 20026 General Requirements for Safety Critical Instrumentation and Control Systems for Nuclear Power Plants

NB/T 20053 Nuclear Power Plant Safety Important Electrical, Instrumentation and Control Equipment Installation Requirements

NB/T 20060 Nuclear Power Plant Safety Critical Instrumentation and Control System Isolation Criteria

NB/T 20061 Human Factors Engineering Application in Nuclear Power Plant Systems, Equipment and Facilities

NB/T 20068 Critical Safety Instruments and Control Systems for Nuclear Power Plants Addressing Common Cause Failures

NB/T 20069 Nuclear Power Plant Safety Important Instrument Channel Performance Monitoring Test

NB/T 20071 Power Requirements for Nuclear Power Plant Safety Important Instrumentation and Control Systems

NB/T 20072 Nuclear Power Plant Safety System Instrumentation Setpoint Determination and Maintenance

NB/T 20148 Nuclear Power Plant Safety Important Instrument Resistance Thermometer

NB/T 20228 Sensitive Components and Sensor Type Tests for Safety Critical Instrumentation and Control Systems in Nuclear Power Plants

NB/T 20254 Nuclear Power Plant Reactor Coolant System Leak Detection Guidelines

NB/T 20255 Guidelines for the Design and Installation of Important Instrumentation Safety Lines for Nuclear Power Plants

NB/T 20318 Nuclear Power Plant Safety Instrument Pressure Transmitter

......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 15 pages — is available in the English PDF.

Referenced standards

Normative references

EJ/T 561 · EJ/T 1180

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