Добавил:
Опубликованный материал нарушает ваши авторские права? Сообщите нам.
Вуз: Предмет: Файл:
01 POWER ISLAND / Overview of Light Water.docx
Скачиваний:
0
Добавлен:
01.04.2025
Размер:
8.88 Mб
Скачать

  1. Control rod drive system instrumentation

In the control rod drive system, appropriate process instrumentation is provided for the driving water system, the scram accumulators, the scram discharge volume, and the control rod positions.

Measured items of the control rod drive system include driving pump outlet pressures, filter pressure drops, differential pressures between the reactor pressure and driving water pressures, drive header flows, control rod drive temperatures, accumulator nitrogen gas pressures, accumulator leakage flow rates, and scram discharge volume water level. Alarm annunciation is actuated for low driving pump inlet pressure, high filter pressure drop, low accumulator nitrogen gas pressure, high accumulator leakage flow rate, and high scram discharge volume water level. Hie reactor shutdown system is initiated at a suitably high water level of the scram discharge volume, since too high a water level of the scram discharge volume may jeopardize scram capability. Control rod positions are measured with reed switches in the indicator tube installed in the center area of the control rod drive, and indicated as well.

In an ABWR plant, since there is the motor- driven fine motion control rod drive system (FMCRD), control rod motion is measured with a synchro directly connected to the motor, and control rod positions thus obtained are used in the rod control and information system.

  1. Primary containment vessel (PCV) atmosphere instrumentation

The main measured items of the PCV are pressures, temperatures, humidities, hydrogen and oxygen concentrations, and radiation levels. Pressures, temperatures and oxygen concentrations in the PCV are continuously measured, and indicated or recorded. Hydrogen concentrations, oxygen concentrations and radiation levels in the PCV are also measured and recorded following a LOCA event. In addition, drywell temperatures, suppression pool water levels and temperatures are continuously measured, and indicated or recorded. Alarm annunciation is actuated for high drywell pressure, high oxygen concentration and high hydrogen concentration. The reactor shutdown

system and the ESFs are initiated at higher drywell pressure. Erroneous trip actuation caused by drain water in the instrumentation line should be avoided, though the set point for this drywell pressure trip maybe low enough for an erroneous trip. With respect to the suppression pool, alarm annunciation is actuated for low water level, high water level, high water temperature, high oxygen concentration and high hydrogen concentration. Nitrogen supply flow to the PCV is continuously measured and recorded.

  1. Leak detection system instrumentation

Coolant leakage from the reactor coolant pressure boundary is measured and indicated. High leakage flow actuates alarm annunciation.

  1. Other instrumentation

In the standby liquid control (SLC) system, levels and temperatures of borated water in the boron injection tank and pump outlet pressures are measured. Alarm annunciation is actuated for low tank level, etc. In the LPCS and the RHR, pump outlet pressures and flows are measured and indicated. Pump outlet pressures and flows are also measured and indicated with respect to the RCIC and the HPCS.

  1. Radiation monitoring system

The radiation monitoring system consists of process radiation monitoring systems, area radiation monitoring systems, environmental monitoring systems, and radiation survey devices; and has the following functions.

  1. To detect abnormal radioactivity in each system and each area of the plant, and provide alarm annunciation.

  2. To monitor radioactive materials that are controlled and released to the area around the site.

  3. The containment atmospheric radiation monitoring system monitors radiation inside the PCV, and has appropriate redundancy and independency to monitor even in accident conditions.

  1. Process radiation monitoring systems

The process radiation monitoring systems continuously measure radiation, provide relevant recording and indication in the MCR and the radioactive waste (radwaste) disposal system

NSRA, Japan

2-76

Chapter 2 Systems of BWR Nuclear Power Plants

control room, and it initiates alarm annunciation if a measured value exceeds the limit

The main process radiation monitoring systems are described below. An example layout of process radiation monitors is shown in Figure 2.6.15, and typical process radiation monitors are shown in Table 2.6.4.

  1. Containment atmospheric radiation monitoring system

Radiation in the PCV area is monitored to grasp the effectiveness of the radiation barrier against radioactive materials in accident conditions. Ion chambers are used for detectors.

  1. Stack monitor

Radioactive gases released from the stack are monitored. Scintillation (Nal) counters and ion chambers are used for detectors. Iodine filters, particle filters and tritium collectors are installed to continuously capture, periodically collect and measure radioactive iodine, particulate radioactive materials and tritium.

  1. Off-gas Monitor

Radioactive gases are monitored in the exhaust from the steam jet air ejectors (SJAEs) before and after passing through the rare gas holdup

equipment. Ion chambers are used for detectors at the former location and scintillation (Nal) counters at the latter.

  1. Gland steam condenser and vacuum pump exhaust radiation monitor

Radioactive gases discharged from the vacuum pump are monitored. Scintillation (Nal) counters are used for detectors.

  1. Main steam line radiation monitor

Fission products leaked from fuel are monitored, and a reactor scram signal is initiated if rapid increase in radiation is detected. Ion chambers are used for detectors.

  1. Reactor building heating ventilating and air conditioning system (HVAC) exhaust monitor Radioactive gases are monitored in the reactor

building exhaust from the reactor building HVAC system. The standby gas treatment system (SGTS) is initiated when excessive radioactivity is detected. Solid state detectors are used.

  1. Off-gas treatment system area exhaust radiation monitor

Radioactive gas is monitored in the exhaust from the off-gas treatment system. Solid state detectors are used.

Reactor building

Reactor building annex

Figure 2.6.15 Layout of process radiation monitors

2-77

NSRA, Japan

Table 2.6.4 Process radiation monitors (example)

Radiation Monitor

Detector Type

Measuring Range

Main steam line radiation monitor

Ion chamber

1013tol0*A

Off-gas monitor

Ion chamber

IO13 to 105 A

Scintillation counter

10'1 to 106 cps

Off-gas linear radiation monitor

Ion chamber

Oto3.3 x 103A

Gland steam condenser and vacuum pump exhaust monitor

Scintillation counter

101 to 106 cps

Refueling area exhaust radiation monitor

Solid state

10n to 10 mSv/h

Off-gas treatment system area exhaust radiation monitor

Solid state

10'* to 1 mSv/h

Reactor building II VAC exhaust monitor

Solid state

101 to 1 mSv/h

SGTS exhaust radiation monitor

Ion chamber

10I3tol0*A

Scintillation counter

101 to 106 cps

Stack monitor

Ion chamber

10-13 to Iff6 A

Scintillation counter

Iff1 to 10G cps

Reactor building closed cooling water system radiation monitor

Scintillation counter

101 to 106 cps

HPCS diesel generator cooling water radiation monitor

Scintillation counter

Iff1 to 106 cps

liquid waste treatment system drain radiation monitor

Scintillation counter

0 to 3.3 x 101 cps

Drywell drain radiation monitor

Ion chamber

1013 to 10* A

Containment atmospheric radiation monitor

Ion chamber

Iff2 to 105Sv/h

Leak detection system dust radiation monitor

Scintillation counter

Iff1 to 106 cps

  1. SGTS exhaust radiation monitor

Radioactive gases in the exhaust from the SGTS are monitored during normal operation and in accident conditions. Ion chambers and scintillation (Nal) counters are used for detectors. Iodine filters and particle filters are installed to capture, collect and measure radioactive iodine and particulate radioactive materials.

  1. Liquid waste treatment system drainage radiation monitor

Radioactivity is monitored in the drainage released from the liquid waste treatment system. Scintillation (Nal) counters are used for detectors.

  1. Reactor component cooling water system radiation monitor

Radioactivity leakage to the cooling water is monitored for safety-related and non-safety-related reactor system components and the radwaste treatment system. Scintillation (Nal) counters are used for detectors.

  1. Area radiation monitoring systems

The area radiation monitoring systems are installed inside the associated buildings to monitor external radiation dose rate. Solid state detectors are used. The area radiation monitoring systems are mainly installed in the MCR, the

radwaste treatment system control room, the refueling platform and the turbine generator operating floor. Table 2.6.5 shows typical area radiation monitors.

  1. Environmental monitoring systems

The following radiation monitoring systems are provided to perform environmental monitoring around the plant site.

  1. Fixed radiation monitoring system

Monitoring posts are installed around the site boundary to monitor external radiation dose rate continuously.

  1. Environmental samples measuring system

Dust samplers are installed around the site boundary to continuously catch radioactive materials in the air. Measuring systems are also installed to measure the radioactive material concentration of environmental samples such as water, food and soil around the plant

  1. Radioactivity monitoring vehicles

Radioactivity monitoring vehicles, which carry gamma ray survey meters, dust samplers and iodine monitors, are available to measure external radiation dose rate around the site and radioactive material concentration in the air.

NSRA, Japan

2-78

Chapter 2 Systems of BWR Nuclear Power Plants

Table 2.6.5 Area radiation monitors (example)

Radiation Monitor

Detector Type

Measuring Range

Reactor building radiation monitor

Solid state

104 to 1 mSv/h

103 to 10 mSv/h

102 to 102 mSv/h

1 to 104 mSv/h

Turbine building radiation monitor

Solid state

10’ to 1 mSv/h

10"3 to 10 mSv/h

Monitor building radiation monitor

Solid state

104 to 1 mSv/h