Press Release
Hamaoka Nuclear Power Station Reactor No. 3 Undergoes Periodic eスポーツベッティング
November 26, 2010Chubu Electric Power Co.,Inc.
Chubu Electric will begin the 17th regular eスポーツベッティング of Hamaoka Nuclear Power Station, Reactor No. 3 (boiling water reactor; rated output 1,100 MW) on November 29, 2010.
The periodic eスポーツベッティング, including power adjustments, is scheduled to last about five months.
During the periodic eスポーツベッティング, the reactor, cooling system equipment, containment structure, steam turbine equipment and so on will undergo eスポーツベッティング, and 172 of the total 764 fuel assemblies will be replaced.
Attachment
Attachment1
Major Inspections and Work Performed During Regular eスポーツベッティング at Hamaoka Nuclear Power Station Reactor No. 3
1. Major inspections
a. Reactor
eスポーツベッティング of reactor pressure vessel, structures inside reactor and fuel
b. Reactor cooling system equipment
eスポーツベッティング of pipes, heat exchangers, pumps and valves
c. Measurement and control system equipment
eスポーツベッティング of control rod drive system, eスポーツベッティング and calibration of various measurement devices
d. Radiation control equipment
eスポーツベッティング and calibration of various radiation control measurement devices
e. Reactor containment equipment
Seal testing of reactor building, containment equipment
f. Steam turbine equipment
Overhaul eスポーツベッティング of steam turbine equipment, disassembly and eスポーツベッティング of main valves, eスポーツベッティング of auxiliary equipment
g. Other
eスポーツベッティング of scrapped equipment, fuel equipment, emergency backup generator equipment, electrical equipment, etc.
2. Major work
a. Of the total 764 fuel assemblies, some 172 are to be replaced.
b. Air purge pipes will be positioned in the reactor isolation cooling system as reactor pressure vessel head spray pipes.*1
c. The control unit for the automatic switching unit*2 for the control rod drive mechanisms will be replaced, and there will also be a detailed eスポーツベッティング of its ancillary equipment.
*1 The reactor pressure vessel head spray pipes in the reactor isolation cooling system are pipes that spray cooling water from the top of the reactor pressure vessel to cool steam, in order to efficiently cool the reactor pressure vessel when the plant shuts down.
*2 The automatic switching unit for the control rod drive mechanisms is a device that attaches and detaches the drive mechanisms used to insert and withdraw the control rods.
The control rod drive mechanisms are positioned in the lower part of the reactor pressure vessel, and are replaced by remote control using the automatic switching unit.