1 Scope
This document specifies the test purpose, test conditions, test content, acceptance criteria and test records and reports for the post-initial charge unit performance test of pressurised water reactor nuclear power plants.
This document applies to the post-initial charging unit performance test of pressurized water reactor nuclear power plants.
2 Normative references
The contents of the following documents constitute essential provisions of this document through normative references in the text. Where a reference is dated, only the version corresponding to that date is applicable to this document; where a reference is not dated, the latest version (including all amendment sheets) is applicable to this document.
NB/T 20145 Specification for the preparation of commissioning test procedures and reports for nuclear power plants
3 Terminology and definitions
The following terms and definitions apply to this document.
3.1
Commissioningcommissioning
The process of operating installed nuclear power plant components and systems and verifying that they perform in accordance with design requirements and relevant guidelines.
Note: Commissioning includes tests without and with nuclear reactions.
3.2
Initial fuel loading
The initial loading of nuclear fuel according to the core loading diagram and the monitoring of the core flux during the loading process.
3.3
Subcriticality
The state of the reactor when its effective multiplication factor K. The state of the reactor when the effective multiplication factor K is <1.
3.4
Initial criticalityinitial criticality
The first physical start-up of a reactor under thermal rated conditions to achieve criticality for a self-sustaining chain fission reaction.
3.5
Low power test
A reactor performance test conducted at a power plateau slightly above zero power.
3.6 power test
power test
A series of tests carried out under a defined power platform.
4 Purpose of the test
The purpose of the post-load unit performance test is to verify that the nuclear power plant can be operated in accordance with the design requirements and can be operated safely and continuously.
5 Test conditions
The test conditions for the post-load unit performance test mainly include:
a) Organisational structure, division of responsibilities, human resources, planning and administration have been arranged;
b) The staffing and training of personnel are in accordance with the requirements and are authorised;
c) the loading of the unit has been completed;
d) Commissioning documentation is in effect and plans are in place for the orderly and controlled performance testing of the unit after loading;
e) Data acquisition, data analysis and control functions are in accordance with the design requirements, additional data-based auxiliary analysis and decision-making tools can be provided as required;
f) Measuring instruments have been certified by qualified units and are within the validity period;
g) Spare parts, equipment, consumables and temporary facilities are available;
h) operation, maintenance and repair responsibilities during the test have been implemented; and
i) safety, security, fire-fighting, communication, first aid and emergency measures have been implemented during commissioning.
6 Test content
6.1 General principles
6.1.1 This document gives the main test items to be carried out during the sub-critical and initial critical tests, low power tests and power tests after charging.
6.1.2 Depending on the requirements of the particular design and test, the test items may be adjusted as necessary.
6.1.3 For units with new concept designs and new design characteristics, special commissioning tests (e.g. first reactor tests) shall be carried out.
6.2 Test Items
6.2.1 Sub-critical and initial criticality tests
The main test items in this phase generally include:
a) parameter calibration and operation tests of reactor protection and dedicated safety facility drive systems
b) Reactor protection channel response time measurements;
c) Operability test of the reactor control system;
d) Reactor coolant system hydrodynamic characteristics test;
e) Reactor coolant flow inertia test
f) Reactor coolant system component residual clearance measurements and displacement checks
g) Reactor coolant system leakage measurement;
h) continuous spray regulation test of the regulator;
6.2.3.2 25% power platform
The main test items of the 25% power platform generally include:
a) Power distribution measurements;
b) Off-stack flux measurement instrument scale adjustment test;
c) Reactor coolant temperature channel calibration;
d) Operability test of the reactor control system;
e) simulated rod drop and simulated bouncing rod tests (if applicable);
f) Nuclear instrumentation system protection calibration adjustment;
g) Heat balance measurement test;
h) Steam generator water level control;
i) Steam and feedwater flow measurement channel calibration;
j) Control test of steam-water separation reheater system;
k) High pressure heater commissioning test (if any);
l) Turbine shutdown and non-stacking test (if applicable);
m) Load variation test;
n) Loss of external power test (if applicable);
o) First and second circuit water chemistry control test; p) Radioactivity level measurement.
6.2.3 Power test 6.2.3.1 - 10% power plateau
The main test items for the 10% power plateau generally include:
a) Reactor coolant temperature channel calibration;
b) Operability test of the reactor control system
c) Residual gap measurement and displacement check of reactor coolant system components
d) neutron flux measurements and core power distribution checks;
e) Nuclear instrumentation system protection calibration adjustment;
f) Rod position control system tests;
g) First and second circuit water chemistry control tests
h) Regulation of first and second circuit channels;
i) Turbine nuclear steam flushing;
j) Turbine generator set start-up and grid connection tests;
k) Calibration of steam and feedwater flow measurement channels
l) Turbine overspeed protection test;
m) Feedwater control valve switching test;
n) Steam generator water level control;
o) Steam generator drainage system test (if any)
p) Normal and standby power switching (if any)
q) Loss of external power test (if any);
r) Radioactivity level measurement;
s) Ventilation performance test.
6.2.3.4 75% power platform
The main tests for the 75% power platform generally include:
a) Operability test of the reactor control system;
b) Reactor coolant temperature channel calibration;
c) Nuclear instrumentation system protection calibrations
d) Power distribution measurements;
e) Off-site flux measurement instrument scale adjustment test;
f) Heat balance measurement test;
g) Calculation of reactor coolant flow from heat balance;
h) Load variation tests (if applicable);
i) Steam and feedwater flow measurement channel calibration
j) turbine load drop test (if applicable);
k) First and second circuit water chemistry control tests;
l) Radioactivity level measurement;
m) Steam generator water level control;
n) Single line operation test of high pressure feedwater heaters (if applicable);
o) Separation test of steam and water reheater isolation (if available);
p) condenser vacuum leak rate test (if any);
q) Argon oscillation test (if any).
6.2.3.5 90% power platform
The main test items for the 90% power platform generally include:
a) Operability test of the reactor control system;
b) Reactor coolant temperature channel calibration;
c) Nuclear instrumentation system protection calibrations; and
d) Off-site flux measurement instrumentation scale adjustment test;
e) Heat balance measurement test;
7 Acceptance criteria
The operational characteristics of the structures, systems and components involved in the performance tests of the unit at each stage after charging meet the design requirements and, if necessary, can be analysed by means of data-based aids, and the unit is ready for acceptance and commissioning.
8 Test records and reports
All tests shall be recorded and test reports written in accordance with the requirements stipulated in NB/T 20145, and special reports shall be executed in accordance with relevant regulations.
Foreword
1 Scope
2 Normative references
3 Terminology and definitions
4 Purpose of the test
5 Test conditions
6 Test content
7 Acceptance criteria
8 Test records and reports
1 Scope
This document specifies the test purpose, test conditions, test content, acceptance criteria and test records and reports for the post-initial charge unit performance test of pressurised water reactor nuclear power plants.
This document applies to the post-initial charging unit performance test of pressurized water reactor nuclear power plants.
2 Normative references
The contents of the following documents constitute essential provisions of this document through normative references in the text. Where a reference is dated, only the version corresponding to that date is applicable to this document; where a reference is not dated, the latest version (including all amendment sheets) is applicable to this document.
NB/T 20145 Specification for the preparation of commissioning test procedures and reports for nuclear power plants
3 Terminology and definitions
The following terms and definitions apply to this document.
3.1
Commissioningcommissioning
The process of operating installed nuclear power plant components and systems and verifying that they perform in accordance with design requirements and relevant guidelines.
Note: Commissioning includes tests without and with nuclear reactions.
3.2
Initial fuel loading
The initial loading of nuclear fuel according to the core loading diagram and the monitoring of the core flux during the loading process.
3.3
Subcriticality
The state of the reactor when its effective multiplication factor K. The state of the reactor when the effective multiplication factor K is <1.
3.4
Initial criticalityinitial criticality
The first physical start-up of a reactor under thermal rated conditions to achieve criticality for a self-sustaining chain fission reaction.
3.5
Low power test
A reactor performance test conducted at a power plateau slightly above zero power.
3.6 power test
power test
A series of tests carried out under a defined power platform.
4 Purpose of the test
The purpose of the post-load unit performance test is to verify that the nuclear power plant can be operated in accordance with the design requirements and can be operated safely and continuously.
5 Test conditions
The test conditions for the post-load unit performance test mainly include:
a) Organisational structure, division of responsibilities, human resources, planning and administration have been arranged;
b) The staffing and training of personnel are in accordance with the requirements and are authorised;
c) the loading of the unit has been completed;
d) Commissioning documentation is in effect and plans are in place for the orderly and controlled performance testing of the unit after loading;
e) Data acquisition, data analysis and control functions are in accordance with the design requirements, additional data-based auxiliary analysis and decision-making tools can be provided as required;
f) Measuring instruments have been certified by qualified units and are within the validity period;
g) Spare parts, equipment, consumables and temporary facilities are available;
h) operation, maintenance and repair responsibilities during the test have been implemented; and
i) safety, security, fire-fighting, communication, first aid and emergency measures have been implemented during commissioning.
6 Test content
6.1 General principles
6.1.1 This document gives the main test items to be carried out during the sub-critical and initial critical tests, low power tests and power tests after charging.
6.1.2 Depending on the requirements of the particular design and test, the test items may be adjusted as necessary.
6.1.3 For units with new concept designs and new design characteristics, special commissioning tests (e.g. first reactor tests) shall be carried out.
6.2 Test Items
6.2.1 Sub-critical and initial criticality tests
The main test items in this phase generally include:
a) parameter calibration and operation tests of reactor protection and dedicated safety facility drive systems
b) Reactor protection channel response time measurements;
c) Operability test of the reactor control system;
d) Reactor coolant system hydrodynamic characteristics test;
e) Reactor coolant flow inertia test
f) Reactor coolant system component residual clearance measurements and displacement checks
g) Reactor coolant system leakage measurement;
h) continuous spray regulation test of the regulator;
6.2.3.2 25% power platform
The main test items of the 25% power platform generally include:
a) Power distribution measurements;
b) Off-stack flux measurement instrument scale adjustment test;
c) Reactor coolant temperature channel calibration;
d) Operability test of the reactor control system;
e) simulated rod drop and simulated bouncing rod tests (if applicable);
f) Nuclear instrumentation system protection calibration adjustment;
g) Heat balance measurement test;
h) Steam generator water level control;
i) Steam and feedwater flow measurement channel calibration;
j) Control test of steam-water separation reheater system;
k) High pressure heater commissioning test (if any);
l) Turbine shutdown and non-stacking test (if applicable);
m) Load variation test;
n) Loss of external power test (if applicable);
o) First and second circuit water chemistry control test; p) Radioactivity level measurement.
6.2.3 Power test 6.2.3.1 - 10% power plateau
The main test items for the 10% power plateau generally include:
a) Reactor coolant temperature channel calibration;
b) Operability test of the reactor control system
c) Residual gap measurement and displacement check of reactor coolant system components
d) neutron flux measurements and core power distribution checks;
e) Nuclear instrumentation system protection calibration adjustment;
f) Rod position control system tests;
g) First and second circuit water chemistry control tests
h) Regulation of first and second circuit channels;
i) Turbine nuclear steam flushing;
j) Turbine generator set start-up and grid connection tests;
k) Calibration of steam and feedwater flow measurement channels
l) Turbine overspeed protection test;
m) Feedwater control valve switching test;
n) Steam generator water level control;
o) Steam generator drainage system test (if any)
p) Normal and standby power switching (if any)
q) Loss of external power test (if any);
r) Radioactivity level measurement;
s) Ventilation performance test.
6.2.3.4 75% power platform
The main tests for the 75% power platform generally include:
a) Operability test of the reactor control system;
b) Reactor coolant temperature channel calibration;
c) Nuclear instrumentation system protection calibrations
d) Power distribution measurements;
e) Off-site flux measurement instrument scale adjustment test;
f) Heat balance measurement test;
g) Calculation of reactor coolant flow from heat balance;
h) Load variation tests (if applicable);
i) Steam and feedwater flow measurement channel calibration
j) turbine load drop test (if applicable);
k) First and second circuit water chemistry control tests;
l) Radioactivity level measurement;
m) Steam generator water level control;
n) Single line operation test of high pressure feedwater heaters (if applicable);
o) Separation test of steam and water reheater isolation (if available);
p) condenser vacuum leak rate test (if any);
q) Argon oscillation test (if any).
6.2.3.5 90% power platform
The main test items for the 90% power platform generally include:
a) Operability test of the reactor control system;
b) Reactor coolant temperature channel calibration;
c) Nuclear instrumentation system protection calibrations; and
d) Off-site flux measurement instrumentation scale adjustment test;
e) Heat balance measurement test;
7 Acceptance criteria
The operational characteristics of the structures, systems and components involved in the performance tests of the unit at each stage after charging meet the design requirements and, if necessary, can be analysed by means of data-based aids, and the unit is ready for acceptance and commissioning.
8 Test records and reports
All tests shall be recorded and test reports written in accordance with the requirements stipulated in NB/T 20145, and special reports shall be executed in accordance with relevant regulations.
Contents of GB/T 41576-2022
Foreword
1 Scope
2 Normative references
3 Terminology and definitions
4 Purpose of the test
5 Test conditions
6 Test content
7 Acceptance criteria
8 Test records and reports
