No. of Unit. Unit 1 Unit 2 Unit 3. Measurement method is under consideration. Reactor water level (Fuel range) Correction conducted on May 11

Similar documents
Boiling Water Reactor Systems

May 23, 2011 Tokyo Electric Power Company

IV. Occurrence and Progress of Accidents in Fukushima Nuclear Power Stations and Other Facilities

NUCLEAR ENERGY RESEARCH INITIATIVE


Why and How we Use Capacity Control

Development Study of Nuclear Power Plants for the 21st Century

THERMO KING TRUCK & TRAILER UNIT ALARM CODES THIS DOCUMENT SHOWS ALL CURRENT ALARM CODES FOR THERMO KING TRUCK AND TRAILER UNITS.

SOLVING REACTOR WATER CLEAN-UP SYSTEM ANOMALIES USING RELAP5 MOD3.3

Dynamic Behavior of BWR

The integrity evaluation of the reactor building at unit4 in the Fukushima Daiichi nuclear power station

Nuclear Energy: Nuclear Energy

15 April 2015 Nuclear Regulation Authority, Japan. 1. Overview

STEAM HEATING SYSTEM TROUBLESHOOTING GUIDE

1 DESCRIPTION OF THE APPLIANCE

Evaluation Of Hybrid Air- Cooled Flash/Binary Power Cycle

February 19, Senior Fellow, Nuclear Energy Systems & Services Division Power Systems Company

DIRECT STEAM INJECTION HOT WATER SYSTEMS FOR JACKETED HEATING

Research on the Air Conditioning Water Heater System

5. State the function of pulveriser. The pulverisers are the equipments which are used to powdered coal.

Loviisa 3 unique possibility for large scale CHP generation and CO 2 reductions. Nici Bergroth, Fortum Oyj FORS-seminar

Rev. 02. STD DEP T (Table and Figures 7.6-1, 7.6-2, 7.6-4a) STD DEP (Table and Figures 7.6-1, 7.6-2)

How To Clean Up A Reactor Water Cleanup

Laddomat Charging unit

Water for Injection (WFI) and Pure Steam Production in a Lean Manufacturing Environment. Larry Zanko Project Manager STERIS Corporation

Indoor coil is too warm in cooling mode or too cold in heating mode. Reversing valve or coil thermistor is faulty

Element D Services Heating, Ventilating, and Air Conditioning

Natural geothermal energy.

BWR Description Jacopo Buongiorno Associate Professor of Nuclear Science and Engineering

Torino Nord. Cogeneration Plant. The gas turbine. The steam generator. The Torino Nord cogeneration plant produces electricity and heat for district

INNOVATIVE SOLUTION OF DOMESTIC HEATING SPLIT TYPE SPLIT DHW INTEGRATED TYPE MONOBLOC TYPE

SECTION PACKAGED ROOFTOP AIR CONDITIONING UNITS NON-CUSTOM

How To Know If A Refrigeration System Is Efficient

How Ground/Water Source Heat Pumps Work

Black Liquor Evaporators: Design and Operation

Backup Fuel Oil System Decommissioning & Restoration Plan

Nuclear power plant systems, structures and components and their safety classification. 1 General 3. 2 Safety classes 3. 3 Classification criteria 3

Article 10 - ADMINISTRATIVE SECTION

HSE information sheet. Fire and explosion hazards in offshore gas turbines. Offshore Information Sheet No. 10/2008

LECTURE 28 to 29 ACCUMULATORS FREQUENTLY ASKED QUESTIONS

ENERGY SAVING WORT BOILING SISTEM IN BREWING FACTORY

5.2. Vaporizers - Types and Usage

Table V. Troubleshooting Checklist for Refrigeration Systems. Air or non-condensable gas in system. Inlet water warm.

Reactor imaging technology for fuel debris detection by cosmic ray muon

Waste Incineration Plants

Everline Module Application Note: Round LED Module Thermal Management

جامعة البلقاء التطبيقية

Test Code: 8297 / Version 1

BIOPOWER 5 CEX. 1 Wärtsilä 10 January 2012 Presentation name / Author

Testing methods applicable to refrigeration components and systems

AEGIS DATA CENTER SERVICES POWER AND COOLING ANALYSIS SERVICE SUMMARY

Fuel Treatment and Conditioning Systems

Yu. F. Vasyuchkov*, M. Yu. Bykova* NEW TECHNOLOGY OF GAS EXTRACTION ON THE BASE OF A COAL TO A HYDROGEN TRANSFER

Heat. Investigating the function of the expansion valve of the heat pump. LD Physics Leaflets P Thermodynamic cycle Heat pump

APC APPLICATION NOTE #112

A precision thermal mass flow sensor for (very) small liquid flows.

The Fundamentals of Thermoelectrics

(Issued 1 Dec. 1965) CRD-C METHOD OF TEST FOR THERMAL CONDUCTIVITY OF LIGHTWEIGHT INSULATING CONCRETE 1

Tour of new eircom Data Centre Blanchardstown by Dervan Engineering Consultants 11 th March 2015

COIL INPUT SCREENS. ITEM NUMBER: Always use a 1 through? In this field you might also use a dash and place quantity of coils here.

EJECTOR AIR REMOVAL SYSTEMS ENGINEERING DATA BULLETIN # PVS ARS PAGE 1 OF 5

Two-Phase Evaporative Precision Cooling Systems

C. starting positive displacement pumps with the discharge valve closed.

Roadmap towards Restoration from the Accident at Fukushima Daiichi Nuclear Power Station, TEPCO. Progress Status

Open Cycle Refrigeration System

HYBRID COMBINED CYCLE POWER PLANT

Copyright 1999 Society of Manufacturing Engineers. FUNDAMENTAL MANUFACTURING PROCESSES Die Casting NARRATION (VO): UTILIZED. NARRATION (VO): THE DIE.

Energy Recovery System for Excavators Meng (Rachel) Wang, Chad Larish Eaton Corporation

Overview of Heat Recovery Boiler Systems and Operating Costs Factors Effecting Blowdown Blowdown Heat Recovery The Energy Tank

The paper addresses the boil-off in the cryogenic industry and details the specifics of it when applied to vehicle LNG tanks.

UA-NJ Air Conditioning & Refrigeration Division Training Curriculum

USB TC-08. Temperature Logger. User's Guide. usbtc08.en r7 Copyright Pico Technology Limited. All rights reserved.

ROTEX gas hybrid heat pump. A strong team.

Introduction. Section 2. Introduction 2-1

Overview. Introduction Cooling Tower Basics Principles of Operation Types of Cooling Towers Common Applications Design Considerations

INFLUENCE OF SPEED AND LOAD ON THE ENGINE TEMPERATURE AT AN ELEVATED TEMPERATURE COOLING FLUID

Link-Up. Solid Fuel Association Guide to Central Heating.

Heating Water by Direct Steam Injection

FLUID CIRCULATION PUMP PRESSURE

I-STUTE Project - WP2.3 Data Centre Cooling. Project Review Meeting 8, Loughborough University, 29 th June 2015

Heating and air-conditioning industry

A/C refrigerant system, overview

Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 37

Steam Generator Boilers Compact Steam Boilers. Rapid Start-Up Safe in Operation

Engineering Recommendation on: Accumulators Revised Issued January 10, 1979 Page 1 of 7

Efficiency on a large scale CFB Steam Boilers

Fully Pumped Systems

Great East Japan Earthquake and the seismic damage to the NPSs

How does solar air conditioning work?

Description of functions

How To Prevent Corrosion In A Steam Electric Power Plant

SAFETY EVALUATION OF INDIAN NUCLEAR POWER PLANTS. BWRs AT TARAPUR ATOMIC POWER STATION (TAPS-1&2)

MAINTENANCE INSTRUCTIONS. Thermia Robust heat pump

Design and Test Operation Performance of 1,500 C Class Gas Turbine Combined-Cycle Power Plant:

Steam Generation Efficiency Module Blowdown Losses Section

WASHING PROCESS OF CARGO TANKS ON TANKERS FOR TRANSPORTATION OF CRUDE OIL

Development of Coal Gasification System for Producing Chemical Synthesis Source Gas

Fukushima Daini Nuclear Power Station: Progress Status Based on the Recovery Plan (As of the End of April 2013)

Redefining Spray Technology

Building New Generation Nuclear Plants Worldwide : AREVA's Experience

Transcription:

Measured correctly, by conducting correction or setting temporary instrument Deemed to be measured correctly, by trend observation and so on, in spite of not conducting correction Instrument is deemed to be sound, but not measured correctly (water filling is needed) Measurement method is under consideration No. of Unit Unit 1 Unit 2 Unit 3 Reactor water level (Fuel range) Correction conducted on May 11 Temporary instrument installed on June 22 (Function did not recover) -> Under investigation for taking measure after the temperature in PCV (Primary Containment Vessel) is improved Under investigation for taking measure after the environment of R/B (Reactor Building) and the temperature in PCV are improved. Reactor pressure Temporary instrument installed on June 4 Temporary instrument installed on June 22 (Reference value was collected) -> Under investigation for taking measure after the temperature in PCV is improved Under investigation for taking measure after the environment of R/B and the temperature in PCV are improved. Temperature around RPV (Reactor Pressure Vessel) Stable reading (for representative parts *) Stable reading (for representative parts *) Stable reading (for representative parts *) Pressure of PCV D/W (Drywell) Correction conducted on May 11 Conducted on July 15 (by the comparison with pressure indicator of N2 enclosure equipment Conducted on July 15 (by the comparison with pressure indicator of N2 enclosure equipment Water level of PCV Computable by calculating (Pressure of N2 enclosure equipment) - (D/W output), (Monitorable when water level is above the line of N2 enclosure equipment) Under consideration for deriving water level of PCV from calculating (Discharge pressure of RHR (Residual Heat Removal System) pump or CS (Core Spray) pump) - (D/W output) Under consideration for deriving water level of PCV from calculating (S/C (Suppression chamber) pressure) (D/W pressure), (Discharge pressure of RHR pump or CS pump) - (D/W output)) Water feed nozzle and lower part of pressure vessel (Unit 1 and 3: Head of lower part of pressure vessel, Unit 2: Upper head of bottom part of pressure vessel) 2

"H" side pressure changes by water level change Condensation tank (Reference level tank) It is necessary to fill water in the condensation tank to measure reactor water level Measurement range -Since pressure difference between "H" and "L" sides has the lenear relationship, water level can be measured by measuring pressure difference, which is caused by the change of hydraulic head pressure (water level change) -The value deducted by the hydraulic head pressure of condensation tank side ("L" side), corresponds to the reactor pressure "H" side " side Fuel range water level indicator Reactor pressure indicator Measurement mechanism of Reactor water level/ Reactor pressure indicator 3

Measurement range This was not measured correctly due to the water evaporation caused by the high temperature in instrumentation pipe in PCV. After cooling is processed, hereafter, it is being considered to fill water when the temperature decrease in PCV is confirmed up to the level that the water in instrumentation pipe in PCV does not evaporate. Unit 1: Correction of Reactor water level indicator (May 11) Fuel range water PI ("H" side) reactor pressure PI ("L" side) reactor pressure Measurement range Currently, Reactor water level is out of measurement range. Reactor pressure is correctly measured by installing the corrected temporary pressure indicator. level indicator For Unit 3, installation is under consideration. DPI (Reactor water level) Temporary rack Fuel range water level indicator PI ("H" side) reactor pressure PI ("L" side) reactor pressure PI: Pressure Indicator DPI (Reactor water level) Temporary rack 4

Low temperature Low temperature High temperature Metal A (eg: Copper) Metal B (eg: Constantan) Current status Although some thermal sensing device are OS/DS (failure) condition, it is considered to be working properly by evaluating in following viewpoints. Trend is monitored hereafter, and its reliability is continuously evaluated. -Same trend is indicated by comparing the circumferential direction data (spare point) and the data of adjacent thermal sensing device Thermal sensing device using the phenomenon of producing thermoelectric power by temperature difference at the contact of 2 different metals (Seebeck effect) Mechanism of Thermal sensing device (thermocouple) -Reading is stable with no outstanding values for the past one month -Indication changes in accordance with the change of water injection amount into the reactor -As shown in the figure, thermocouple has simple mechanism with limited failure modes of disconnection/short-circuit/ grounding/multi circuit failure, and so on. Trend is monitored hereafter, and its reliability is continuously evaluated. We deleted the image of thermal sensing device (thermocouple) on Feb. 21, 2012. 5

Current status Reactor building Turbine building Outdoor <Unit 1> To indicator in Main Control Room Field site PI Temporary PI To indicator in Main Control Room N2 enclosure equipment Temporary pressure indocator PCV pressure = Reading value of pressure indicator - Pressure loss Correction of field site PI was conducted on May 11. The indicator in Main Control Room is evaluated to be correctly measured, since conversion value is confirmed from field site PI, of which the correction was conducted. <Unit 2/3> It is evaluated to be correctly measured, since properness of instrument was confirmed by comparing the values of temporary PI for comparing N2 enclosure equipment (correction was conducted) and D/W pressure indicator for safety protection system, on July 15. Mechanism of measurement of PCV pressure 6

Since corrections of both D/W pressure and N2 enclosure equipment are conducted, they are correctly measured. Since correction of N2 enclosure equipment is conducted, they are correctly measured. Since there are some similar instruments, it is considered to be correctly measured. * Pressure of N2 enclosure equipment Discharge pressure of RHR/CS pump Pressure of N2 enclosure equipment Mechanism of PCV water level measurement Suppose that D/W pressure (field site pressure indicator) is gas phase part and N2 pressure is liquid part, since N2 pressure indicates the gas phase part pressure and the hydraulic head pressure of liquid, water level is theoretically calculated by deducting the gas phase part pressure. Mechanism of PCV water level measurement Suppose that N2 enclosure equipment is gas phase part and RHR discharge pressure is liquid part, since RHR/CS pump discharge pressure indicates the gas phase part pressure and the hydraulic head pressure of liquid, water level is theoretically calculated by deducting the gas phase part pressure. (S/C pressure) - (D/W pressure) is also being considered for Unit 3 7

8