ACADs (08-006) Covered Keywords Containment Isolation, actuation logic, Description Supporting Material 1.2.1.53.3.2.4.24.10.4.25.3.2.75.4.3.11.

Slides:



Advertisements
Similar presentations
COIL PIPING BEST PRACTICES
Advertisements

Generic Pressurized Water Reactor (PWR): Safety Systems Overview
ACADs (08-006) Covered Keywords Defense-in-depth, reactor protection system, solid state protection system, reactor trips, Engineered Safety Feature System.
Circulating Water System
Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions.
Nuclear Power Turkey Point Power Plant Process. Turkey Point Power Plant Built on 12, 700 acres in Homestead Opened in 1972 Cost to build both reactors.
ACADs (08-006) Covered Keywords Pressurized Water Reactor (PWR), Boiling Water Reactor (BWR), primary loop, reactivity, reactivity control, reactivity.
Issues Associated with the Development of Severe Accident Management Guidelines for CANDU Reactors Keith Dinnie Director, Risk Management Nuclear Safety.
Safety analysis of supercritical-pressure light-water cooled reactor with water rods Yoshiaki Oka April 2003, GIF SCWR Mtg. at Madison.
Thermal-Hydraulic Transient Analysis of the Missouri University Research Reactor (MURR) TRTR Annual Meeting September 17-20, 2007 Dr. Robert C. Nelson1,
LFR plant assessment against a Fukushima-like scenario Technical Workshop to Review Safety and Design Aspects of European LFR Demonstrator (ALFRED), European.
Turbine Protection and Control System
Walter G Bischoff Brunswick station Duke Energy
ACADs (08-006) Covered Keywords Components, functions, operation, Auxiliary feedwater, Startup, hot standby, plant cooldown, emergency. Description Supporting.
Overview of Incident at Fukushima Daiich Nuclear Power Station (1F) (Informal personal observations) April 2011.
EUROTRANS: WP1.5 Technical meeting, Karlsruhe, November 27 – 28, XT-ADS DHR Conceptual Design L. Mansani
ACADs (08-006) Covered Keywords BWR, main steam, piping and instrument drawing, functional operating sketch, flowpath, interrelationships, safety relief.
5.1.2 Student Book © 2005 Propane Education & Research CouncilPage 1 NFPA 58, LP-Gas Code, sets out the minimum valve and fitting requirements for propane.
Nuclear Plant Systems ACADs (08-006) Covered Keywords
NUCLEAR SAFETY Barbora Svobodová Angličtina-odborná II.
Fuel Oil Systems Fuel Oil Systems consist of: Storage Tanks Pumps
STEAM HEATING.
Emergency Power Systems
AIR QUANTITY REQUIRED TO TRANSFER HEAT IN A FORCED AIR SYSTEM In all four mechanical systems considered, the transfer of heat, either by taking it out.
Fukushima Incident Preliminary Analysis, Consequences and Safety Status of Indian NPPs Part-1 Dr. S.K.Jain Chairman & Managing Director NPCIL & BHAVINI.
1 OCCUPATIONAL EXPOSURE at JAPANESE NUCLEAR POWER PLANTS in 2005 October 12, 2006 Shigeyuki Wada Safety Information Division Japan Nuclear Energy Safety.
NFPA 31 Standard for the installation of Oil- Burning Equipment
Fukushima Nuclear Disaster Team 07: Belsheim Joshua Francis Travis He Jiayang Moehling Anthony Ziemkowski Micah 1.
1. - Condensate pump and feed pump trip! -Turbine trips! 2.
Kevin Burgee Janiqua Melton Alexander Basterash
Nuclear Thermal Hydraulic System Experiment
Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions.
Application – Identifying, Listing Equipment, and Documentation
Nuclear Power. Fission Uranium-235 Plutonium-239 Neutron 10n10n 10n10n 10n10n Strontium-90 Xenon-144.
March 11, 2011 to Present. Presentation Overview Reactor Design and FeaturesChronology of EventsCurrent Status of Each ReactorRecovery Actions Kashiwazaki-Kariwa.
Nuclear Power Plant Orientation
ERMSAR 2012, Cologne March 21 – 23, 2012 MELCOR Severe Accident Simulation for a “CAREM-like” Integral Reactor M. Caputo, J. M. García, M. Giménez, S.
Natural Convection as a Passive Safety Design in Nuclear Reactors
0 Overview of Fukushima-Accident Analysis ERMSAR 2012, Cologne (Germany) March 21 – 23, 2012 JNES Masanori FUKASAWA.
Ta’Juan Dutrieuille November 4, 2009 Period 1
Nuclear fission Nuclear fission: heavy nuclei split into two smaller parts in order to become more stable proton neutron Kr-90 nucleus U-235 nucleus energy.
Nuclear Power Plant How A Nuclear Reactor Works. Pressurized Water Reactor - Nuclear Power Plant.
I Need A Space Heating System Let’s Look At A Central Steam Plant Option.
THE FUKUSHIMA NUCLEAR ACCIDENT ON THE TECHNOLOGY DEVELOPMENT OF NEW NUCLEAR POWER PLANTS 1.IRSHAD NURHAKIM BIN NORAHIM (ME088151) 2.LEE SZE TENG (ME087909)
LOW PRESSURE REACTORS. Muhammad Umair Bukhari
Plant & Reactor Design Passive Reactor Core Cooling System
Air condition installation
Chapter No-5 STEAM CONDENSERS AND COOLING TOWERS Marks-16
EP4P03 Nuclear Power Plant Systems and Operation
Review Questions Chapter 5
Fluid Statics/Dynamics
- Condensate pump and feed pump trip!
Date of download: 10/13/2017 Copyright © ASME. All rights reserved.
Containment System (CNS)
Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.
Chapter 9 Safety Permit Systems
Date of download: 12/30/2017 Copyright © ASME. All rights reserved.
Pressurized Water Reactor
Practical experience of the Russian VVER design organization in the use of PSA for verification of compliance with single and double failure criteria.
Ch. 10 Notes Day 1 5/25/16.
Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions
NRC Event Number – Event Date
STEAM CONDENSERS AND COOLING TOWERS Marks-16
Session Name: Lessons Learned from Mega Projects
Summary of the Earthquake and Situation of the Kashiwazaki-Kariwa NPP
Compact Nuclear Simulation Analysis
- Condensate pump and feed pump trip!
Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.
THE ROLE OF PASSIVE SYSTEMS IN ENHANCING SAFETY AND PREVENTING ACCIDENTS IN ADVANCED REACTORS Moustafa Aziz Nuclear and Radiological Regulatory Authority.
Presentation transcript:

ACADs (08-006) Covered Keywords Containment Isolation, actuation logic, Description Supporting Material

2 CONTAINMENT

3 Students will understand the CONTAINMENT ISOLATION system, actuation logic and its major components TERMINAL OBJECTIVE

4 ENABLING OBJECTIVES State the purpose of the CONT system, including its importance to nuclear safety. Using a simplified diagram, identify and explain the purpose of the major components and equipment of the CONT system. Identify the modes of actuation of the CONT system, including the major component groups associated with each mode. Describe the basic interrelationships between the CONT system and other plant systems. CONTAINMENT (CONT)

5 Purposes of the CONTAINMENT (CONT) system Provide an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment, and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require.

6 CONTAINMENT (CONT) PRIMARY CONTAINMENT

MCCC - NUET 130

8 CONTAINMENT (CONT)

9 Safety Design Basis of the CONT system Shall ensure sufficient boron injected at a flowrate of at least 41.2 gallons per minute to bring the Reactor from full power to cold, Xenon-free shutdown condition. Control rods are assumed to remain in 100% rated power pattern In the event of a LOCA resulting in core damage, the operators will inject CONT to control pH in the Suppression Pool. Since there is limited leakage into Secondary Containment form Primary Containment, the amount of iodine will be limited, since it will stay in solution. This results in less dose to the public from iodine.

10 CONTAINMENT (CONT) Fermi primary containment: GE Mark I design The Drywell is normally inerted with nitrogen during power operation (prevents hydrogen/oxygen explosion). Major components are: Drywell Torus 8 vent pipes Eighty 24 inch diameter downcomer pipes

CONTAINMENT (CONT) 11 Major components of the CONT system 1.Drywell - An inverted light bulb shaped steel pressure vessel with a spherical lower portion (68 ft. diameter) and a cylindrical upper portion (39 ft. in diameter). The DW is enclosed and supported by the concrete reactor building. 2.Torus - Steel pressure vessel in the shape of a donut, located below and encircling the drywell. Diameter is 112 feet, with a cross sectional diameter of 30 ft. Contains approx. 1,000,000 gallons of water, with net air space above the water pool of approx. 128,000 ft3. 3.Vent Piping - 8 vent pipes connect DW and Torus, each is 6 feet in diameter. Vent pipes connect to a header located in the air space within the torus. Projecting downward from this header are 80 downcomer pipes terminating 3 ft. below the surface of the water in the torus pool.

12 CONTAINMENT (CONT) Pipe break inside drywell (or LOCA) would result in: Reactor water and steam would be released into the drywell. Increased DW pressure would force a mixture of nitrogen, steam, and water through the vents into pool of water in torus. Steam would condense in the suppression pool, gradually heating up the suppression pool water. Heat is removed from SP by RHR in the Torus Cooling mode.

CONTAINMENT (CONT) 13 Residual steam in the DW would create a vacuum as it cools, resulting in SP water being drawn up into downcomer piping. Vacuum breakers are installed to assure torus pressure does not exceed drywell pressure by more than 0.5 psid. This limits the water slug which would be ejected into the suppression pool on a subsequent steam blowdown.

14 CONTAINMENT (CONT) SQUIB valve

CONTAINMENT (CONT) 15 The CONT pumps are normally lined up to CONT storage tank in Standby condition When an emergency situation requires CONT, Operators start the system by placing the control room switch to "Start Sys A" or "Start Sys B" Selected pump starts Both explosive valves actuate An isolation signal is sent to RWCU System to isolate the outboard valve (F004), which trips the RWCU pumps (This is provided to prevent the removal of the CONT solution from the reactor ) Indication of proper operation of CONT by Pump run light in Control Room, Storage tank level decreasing, Loss of continuity alarm on squib valves and Check valve F006 OPEN

16 CONTAINMENT (CONT)

17 Refuel Outage system testing – including verification of Squib valve operation and flowpath EAV REACTOR Sodium Pentaborate solution FI PI Test Tank System actuated with suction lined up to test tank – verifies proper flowrate by tank level change over time

CONTAINMENT (CONT) 18 Quarterly pump / system performance testing – suction and return to CONT Test Tank EAV REACTOR Sodium Pentaborate solution FI PI Test Tank

19 Review TERMINAL OBJECTIVE Students will understand the CONT system, its major components and flowpaths CONTAINMENT (CONT)

20 Review ENABLING OBJECTIVES State the purpose of the CONT system, including its importance to nuclear safety. Using a simplified diagram, identify and explain the purpose of the major components and equipment of the CONT system. Identify the modes of operation of the CONT system, including the major components and flowpaths associated with each mode. Describe the basic interrelationships between the CONT system and other plant systems. Describe the manner in which the CONT system can shutdown the reactor in the event of failure of normal reactor controls CONTAINMENT (CONT)

21 QUESTIONS???