Term
|
Definition
| The ability or capacity to do work through conversion of a physical property. |
|
|
Term
| What is the unit of measurement for energy. |
|
Definition
| Ft-lb.;BTU;Volt and Joule |
|
|
Term
|
Definition
| Energy expended as a result of a force displacing an object. |
|
|
Term
| What is the unit of measurement for work. |
|
Definition
|
|
Term
|
Definition
| The time rate of doing work. |
|
|
Term
| What is the unit of measurement for Power. |
|
Definition
| Horse Power, BTU/Hr, Watt |
|
|
Term
| List the five requirements for a thermodynamic cycle. |
|
Definition
| Heat Source, Heat Sink, Working Substance, Pump, Engine. |
|
|
Term
|
Definition
|
|
Term
|
Definition
|
|
Term
|
Definition
| Medium throuh which energy is transfered. |
|
|
Term
|
Definition
|
|
Term
|
Definition
| Takes work out of a system |
|
|
Term
|
Definition
| Physics that involves the study of the movement of heat. |
|
|
Term
| List the three major energy sources used to generate electricity in order from highest percentage to lowest percentage |
|
Definition
1.Fossil Fuel 2.Nuclear 3.Hydroelectric |
|
|
Term
| List the four requirements for a nuclear reactor |
|
Definition
1.Fuel 2.Coolant 3.Moderator 4.Control Material |
|
|
Term
|
Definition
| Thermal light water reactor that produces steam in the core without the use of a steam generator and has no secondary system. Water is boiled within the core. |
|
|
Term
|
Definition
| Thermal light water reactor that employs the use of a secondary system to produce steam and allows minimal boiling in the core. |
|
|
Term
| List the differences between a BWR and a PWR |
|
Definition
BWR- No secondary system; Control rods inserted into the bottom of the core
PWR-Primary and secondary system; control rods are inserted from the top of the core |
|
|
Term
| Name the three major buildings at a nuclear power site. |
|
Definition
1.Reactor Containment Building 2.Fuel Handling Building 3.Mechanical Electrical Auxiliaries Building |
|
|
Term
| Describe an atom in terms of its components and relative locations, charges, and mass. |
|
Definition
Proton- (+1); Located in nucleus; 1.67 E-27 kg *lighter than neutron*
Neutron-(0); Located in nucleus; 1.67 E-27Kg *Heavier than proton*
Electron-(-1);Located in orbit around Nucleus; 1/2000th mass of a neutron\proton |
|
|
Term
| Describe a fission event in terms of the reactants and resultant products |
|
Definition
| An incident thermal neutron comes in contact with a U-235 atom. The U-235 atom splits or fissions into two parts called the fission fragments or daugther products. An additional 2.5 neutrons, radiation, and energy is also generated. |
|
|
Term
| List the two categories in which fission neutrons are classified |
|
Definition
1.Kinetic energy 2.Time of birth |
|
|
Term
| Which set of neutrons are classified by Kinetic Energy |
|
Definition
|
|
Term
| Which set of neutrons are classified by their Time of Birth |
|
Definition
|
|
Term
| T/F) All neutrons are born fast? |
|
Definition
|
|
Term
| Define the following terms in relation to neutron classification and/or energies: Fast, Slow, Thermal, Prompt, and Delayed. |
|
Definition
Fast->=.1MeV Slow-<=1eV Thermal-.025eV Prompt-~2MeV;Birth within 10E-14 sec Delayed-~.5MeV; Birth after 10E-58 sec of fission. Average 12.5 sec after fission |
|
|
Term
| List the neutron interactions which cause it to lose energy. |
|
Definition
|
|
Term
| Define, subcritical, critical, supercritical in terms of K-effective and neutron population. |
|
Definition
1.Supercritical-Keff >1.00;Increasing neutron population 2.Critical-Keff=1.00;Steady neutron population 3.Subcritical-Keff<1.00;Decreasing neutron population |
|
|
Term
| List the functions of the Reactor Vessel and Internals System. |
|
Definition
M.A.G.I.C. 1. Maintain a region for power production 2.Absorb static and dynamic loads 3. Guide coolant flow 4.Provide for instrumentation and control components 5.Contain the fuel and structural assemblies in the smallest volume possible |
|
|
Term
| State the purpose of the Reactor Vessel. |
|
Definition
| Provides Pentrations for Instrumentation, Contains the Reactor Core and Support Equipment in the smallest volume, Transfers the load of the Reactor Vessel and Internals to the Containment Building |
|
|
Term
| State the purpose of the Vessel Head |
|
Definition
| Provides penetrations for instumentation and Control Components, Forms the Upper Portion of the Pressure Boundary, Can be removed to allow for Refueling and Maintenance |
|
|
Term
| State the purpose of the Lower Internal Assembly |
|
Definition
Supports the core *Absorbs static and dynamic loads Provides lower instrumentation guides, Permits transition from Round Barrel to Squared-off Periphery of the Core |
|
|
Term
| State the purpose of the Upper Internals Assembly |
|
Definition
| Support for Instrumetntation and Control Components, Aligns the fuel assemblies, Lateral Support of fuel assemblies |
|
|
Term
| List the four parts of a fuel assembly |
|
Definition
1.Bottom Nozzle 2.Top Nozzle 3.Grud Assembly 4.Fuel Rods |
|
|
Term
| Describe the reactor coolant flow path through the vessel |
|
Definition
| Coolant enters through the nozzles; travels down the annulus between the core barrel and vessel wall, some flow is diverted between neutron pad and core barrel; continues between radial support members into lower vessel head plenum among tie plates and instrumentation guides; turns upward through lower core support plate and through fuel assemblies; coolant exits the core passing through the upper core support plate; enters the upper internals area; coolant is directed to outlet (hot leg) nozzles and enters the Reactor coolant system piping. |
|
|
Term
| How much coolant flows through the vessel to cool the fuel rods, and how much flow bypasses |
|
Definition
91.5% flows completey through the vessel to cool the fuel
8.5% bypasses to cool other components of the reactor vessel |
|
|
Term
| State the two functions of the RCS |
|
Definition
1.Transport heat from the Reactro to the S/Gs, where it is transferred to Main Steam
2.Acts as a boundary to protect against possible fission products released from the fuel. |
|
|
Term
| What are the four major components in the RCS |
|
Definition
1.Reactor Vessel and internals 2.Steam Generators 3.Reactor Coolant Pumps 4.Pressurizer |
|
|
Term
| What are the major assemblies which comprise the Reactor Vessel and Internals System. |
|
Definition
1.Reactor Vessel 2.Vessel Head 3.Lower Internals Assembly 4.Upper Internals Assembly |
|
|
Term
| What is the purpose of the Steam Generators |
|
Definition
1.Transfer heat fronm the RCS to produce steam for the Main Steam System
2.Remove decay heat from the RCS during shutdown conditions
3.Main heat sink for the Reactor during accident conditions |
|
|
Term
| What is the purpose of the Reactor Coolant Pumps |
|
Definition
| Ensure adequate coolant flow rate through the reactor core and S/Gs for sufficient heat transfer |
|
|
Term
| What is the purpose of the Pressurizer |
|
Definition
| Maintains RCS pressure above saturation pressure for the RCS temp. |
|
|
Term
| Describe the RCS flowpath between the major components |
|
Definition
| Heated coolant from the reactor core enters the hot leg piping, coolant then enters steam generators and transfers heat, coolant exits the steam generators and enters the intermidiate leg piping, the coolant then enters the suction of the RCP, after discharge from the RCP, the coolant then enters the cold leg piping and from there enters the Reactor vessel where the process is repeated in a cycle |
|
|
Term
| List the three different plant conditions when the S/Gs are used to remove heat from the RCS |
|
Definition
1.Power Generation 2.Cool-down during shutdown 3.Accident Conditions |
|
|
Term
| State the four functions of the CVCS |
|
Definition
1.Maintains required water inventory in the RCS 2.Maintains seal water injection flow to the RCP 3.Controls Reactor Coolant water chemistry conditions, activity level and soluble chemical neutron absorber concentration 4.Provides means for filling, draining and pressure testing the RCS |
|
|
Term
| List at least four systems that interface with the CVCS |
|
Definition
1.Boron Thermal Regeneration System 2.REactor Make-Up Water 3.Residual Heat Removal 4.Reactor Coolant Pumps 5.Component Cooling Water |
|
|
Term
| Describe the flowpath of the CVCS |
|
Definition
| Coolant enters in from the intermediate leg of loop charlie. then it flows through the shell side of the regenerative heat exchanger, then to a letdown orifice, then through the tube side of the let down heat exchanger, then to a letdown pressure control valve, then to the mixed bed demineralizers, then to a reactor coolant filter, and into the volume control tank, after the volume control tank the coolant enters the suction of the charging pumps which has its speed controlled by a control valve linked to pressurizer level, the coolant then flows through the regenerative heat exchanger and is directed back into the cold leg of loops alpha and charlie. |
|
|
Term
| What is the flow path of the Seal Water flow |
|
Definition
| A portion of the charging flow of the CVCS is directed to the RCP through a Seal Injecter Filter, about 3gpm flows up the pump shaft and supplies the number 2 seal or eaves the pump via the no.1 seal. The number 1 seal flow discharges to a common header, exits the containment and then passes through the Seal Water Return Filter and the Seal Water Heat Exchanger to the suction of the charging pumps, or by an alternate path to the volume control tank. |
|
|
Term
| What are the three uses of the Positive-Displacement Charging Pumps |
|
Definition
1.*mainly* used to hydrostatically test the RCS 2.Reactor Coolant Pump seal injection flow 3.Boration capability for an abnormal condition when both Centrifugal Charging Pumps are out of service (through the RCP Seals) |
|
|
Term
| List the functions of the Residual Heat Removal System |
|
Definition
1.Removes decay heat from the core via the RCS in modes 4,5, and 6
2. Proivides a flow path to transfer water between the Refueling Water Storage Tank and the Refueling Cavity
3.Cools Emergency Core Cooling recirculation water |
|
|
Term
| List the two major components of the RHRS and STATE their location |
|
Definition
1.Pumps;RCB 2.Heat Exchangers;RCB |
|
|
Term
| Describe the flow path of the RHR system. |
|
Definition
| Hot leg, Pump, Heat Exchanger, Cold Leg |
|
|
Term
| List the four systems which interface with the RHRS |
|
Definition
1.Reactor Coolant System-Cooled by RHR 2.Emergency Core Cooling System-Cooled by recirculation water 3.Component Cooling Water-RHR Heat Sink 4.CVCS- Letdown path for RHR |
|
|
Term
| List the three functions of the Reactor Containment Building |
|
Definition
1.Protects the RCS and other components located inside the RCB from site environmental conditions including earthquakes and tornadoes 2.Proctects the public against the release of radioactive material in the unlikely event of a LOCA 3.Serves as a biological shield against high levels of radiation released during normal power operations and possible accidents. |
|
|
Term
| List the three RCB support systems |
|
Definition
1.Containment Isolation System 2.Containment Combustible Gas Control System 3.Containment Heat Removal System |
|
|
Term
| Describe the personnel acces penetrations to the RCB |
|
Definition
1.Personnel Access Hatch-Located in MAB. Equipped with an airlock which is a welded assembly with double dorrs located at the 68' elevation 2.Auxiliary Airlock- Located outside. An alternate airlock with double doors located at the 37' elevation 3.A 24' diameter hatch for large equipment access located at the 68' elevaltion |
|
|
Term
| State the function and location of the primary and secondary shield walls |
|
Definition
1.Primary Shield Wall- 7 foot thick located around the Reactor Vessel. Provides a biological barrior to radiation for personnel and supports the Reactor Vessel 2.Secondary Shield Wall-3.5 foot thick. Provides radiation shielding and provides a missle barrier and support for major system components in the RCS |
|
|
Term
| State the function of the Containment Spray System |
|
Definition
| Controls RCB temperature and pressure during a Steam Break or LOCA by condensing Steam present in the RCB |
|
|
Term
| State the functions of the Reactor Operator and the Automatic Control and Protection System |
|
Definition
1.Ensure safe reactor operations. 2.Protect the workers, general population, and the environment in the event of an accident |
|
|
Term
| Define "poison" in relation to reactor control |
|
Definition
| Any material that will absorb a neutron and prevent that neutron from causing fission |
|
|
Term
| State the two main poisons used for reactor control |
|
Definition
1.Boric Acid 2.Control Rods |
|
|
Term
| List the five special characteristics of the Automatic Protection System |
|
Definition
1.Diverse 2.Redundant 3.Independent 4.Fail Safe 5.Testable |
|
|
Term
| State the primary means of reactor protection |
|
Definition
|
|
Term
|
Definition
| Two or more different methods are used to determine the smae condition |
|
|
Term
|
Definition
| Usually two or more detection devices are used to monitor the same plant condition. Means that two or more devices are doing the same thing |
|
|
Term
|
Definition
| The two or more redundant devices are physically and electrically independent from each other such that they cannot interface with the other's ability to monitor the given condition. |
|
|
Term
|
Definition
| Minimizes the possibility of not being able to place the reactor in a safe condition |
|
|
Term
|
Definition
| designed to allow one portion of the system at a time to be tested without causing or preventing a protective action from occurring |
|
|
Term
| State the functions of Engineered Safety Features |
|
Definition
| Protect the workers, general population, and the environment by controlling and limiting the release of fission products and radiation to within the specifications set by federal regulation |
|
|
Term
| State the functions of the Emergency Core Cooling Systems |
|
Definition
1.Provide core cooling water in the event that a LOCA following a break in the RCS 2.Provide shutdown capability during accident conditions |
|
|
Term
| List the three fission product barriers, in order, that protect the environment from an uncontrolled release of radioactive material to the atmosphere |
|
Definition
1.Fuel Cladding 2.Reactor Coolant System 3.Reactor Containment Building |
|
|
Term
| List the nine systems which comprise the ESF systems |
|
Definition
1.Containment Isolation System 2.Containment Heat Removal 3.Containment Combustible Gas Control 4.Control Room/EAB Ventilation 5.Fuel Handling Building HVAC 6.Aux Feed Water 7.HHSI 8.LHSI 9.Safety Injection Accumulators |
|
|
Term
| List the Four ESF SUPPORT systems |
|
Definition
1.Essential Cooling Water 2.Essential Cooling Water Pond 3.Component Cooling Water 4.ESF Diesel Generators |
|
|
Term
| State the location of the ECCS major components |
|
Definition
1.HHSI & LHSI pumps with some piping and valves in FHB 2.SI Accumulators located inside RCB 3.The remainder of the equipment is located in RCB |
|
|
Term
| The three fission product barriers, in order, are |
|
Definition
| Fuel Clad, RCS, Reactor Containment Building |
|
|
Term
| The Cold Leg Recirculation flow of the ECCS taks a suction on the _______ and discharges to an RCS ________ leg |
|
Definition
|
|
Term
| The Hot Leg Recirulation flow of the ECCS takes a suction on the _______ and discharges to a RCS______ Leg |
|
Definition
|
|
Term
| The Cold Leg Injection flow of the ECCS takes a suction on the _______ and discharges to an RCS ______ Leg |
|
Definition
| Refueling Water Storage Tank, Cold |
|
|
Term
| List the three components that make up the Fuel Handling System |
|
Definition
1.Refueling Machine 2.Fuel Handling Machine 3.Transfer Cart |
|
|
Term
| List three makeup water sources to the Spent Fuel Pool which would dilute the bron concentration and state the souce which should always be available |
|
Definition
1.Refuleing Water Storage Tank- Borated Reactor Makeup Grade Water 2.Reactor Makeup Water Storage Tank-Dilutes Boron concentration *Always Available* 3.Demineralized Water System |
|
|
Term
| State the makeup source to the Spent Fuel Pool which should be used to increase boron concentration |
|
Definition
| Refueling Water Storage Tank |
|
|
Term
| List three functions of the Spent Fuel Pool Cooling and Cleanup System |
|
Definition
1.Limits pool temperature to 120F 2Filters impurities to improve clarity 3.Removes impurities to limit radiation dose to personnel to 2.5 mrem/hr during normal operations and 10 mrem/hr during refueling |
|
|
Term
| List four cranes used in the Fuel Handling System |
|
Definition
1.Containment Building Polar Crane 2.Refueling Machine 3.Fuel Handling Machine 4.Fuel Handling Overhead Crane |
|
|
Term
| List tree significant differences between rapid refueling and "normal" refueling |
|
Definition
Rapid Refueling: 1.disconnects a minimum number of items 2.minimizes the number of separate crane lifts 3.Minimizes the number of operator checks |
|
|
Term
| State the function of the ECW system |
|
Definition
| Supply cooling water to safety during normal plant operations, as well as accident conditions |
|
|
Term
| List the three major components cooled by ECW |
|
Definition
1.Engineered Safety Features Diesel generators 2.CCW Heat Heatexchanger 3.Essential Chiller |
|
|
Term
| List the two functions of the Component Cooling Water |
|
Definition
1.Proved cooling water for removal of heat from ESF and non-ESF componentss during all plant operation modes 2.Provide an intermediate fluid barrier between potentially radioactive systems and the ECW system to reduce the possibility of leakage of radioactive contaminants to the outsidee environment |
|
|
Term
| Describe the ESF flow path of the CCW |
|
Definition
| Surge tank, pump suction, Heat exchanger, various ESF components, pump suction |
|
|
Term
| Describe the Non ESF flow path of the CCW |
|
Definition
| Pump, common supply header, various loads, pump |
|
|
Term
| List the ESF components cooled by CCW |
|
Definition
1.RHR Heat Exchanger 2.Reactor Containment Fan Coolers |
|
|
Term
| Explain the term "Ultimate Heat Sink" |
|
Definition
| Refers to the Essential Cooling Pond acting as the final heat sink for the reactor core in an accident |
|
|
Term
| List the three types of radioactive waste processed at nuclear power plants |
|
Definition
|
|
Term
| State the three methods for processing liquid waste |
|
Definition
1.Filtration 2.Demineralization 3.Evaporation |
|
|
Term
| Name the three radionuclides of concern in the Gaseous Waste Processing System |
|
Definition
|
|
Term
| What are the four system interfaces of the RHR system |
|
Definition
1.Reactor Coolant System-cooled by rhr
2.Emergency Core cooling system- recirc water cooled
3.Component cooling water- cools rhr heat exchanger
4.Chemical and volume control system- letdown path for RHR |
|
|
Term
| List the two major components of the RHR system and state their locations |
|
Definition
| The RHR heat exchanger and the RHR pumps. Both are located in reactor containment outside the biowall |
|
|
Term
| How many trains of ECW are available for each unit? |
|
Definition
|
|
Term
| State the purpose of the aux feedwater system? |
|
Definition
| Provides adequate cooling to the steam generators in the event of a loss of normal feedwater |
|
|
Term
| What is the purpose of the main steam porv? |
|
Definition
| Releases heat to the atmosphere when the main condensor is unavailable. |
|
|
Term
| What is the purpose of the MISVs |
|
Definition
| serve as a safety function to limit uncontrolled flow of steam fromt he S/Gs in the event of a break in the steam system |
|
|
Term
|
Definition
| System provided for the Turbine Generator System combines solid-state electronics with high pressure hydraulics to operate the major valves in the Main Turbine, and low pressure oil for operation of the mechanical overspeed trip device |
|
|
Term
| State the purpose of the Gland Seals |
|
Definition
| provides a means to prevent air inleakage at points where the rotor penetrates the outer cylinders. |
|
|
Term
| State the purpose of the Turbine lube oil system |
|
Definition
| supplies lubrication to the turbine bearings. |
|
|
Term
| State the two functions of the main steam system |
|
Definition
Transport the steam from the Steam Generators (SG) to components and systems outside the Reactor Containment Building (RCB)
Provide a heat transfer flowpath from the Reactor Coolant System (RCS) during normal, cooldown, and accident conditions |
|
|
Term
| What is the purpose of a main steam isolation |
|
Definition
To minimize the effects of a rupture of a steamline
To Prevent excessive cooldown of the Reactor Coolant System (RCS). |
|
|
Term
| State the 2 functions of the main turbine |
|
Definition
Convert thermal energy into roational mechanical energy
Provide extraction steam for feedwater heating |
|
|
Term
| State the function of the condensate system |
|
Definition
| provides the required flow of makeup water at rated temperature and pressure to satisfy the suction flow requirements of the feedwater pumps. |
|
|
Term
| Describe the condensate/feedwater flowpath (13 systems in the feedwater flowpath) |
|
Definition
| Main condensor, Condensate pumps, Condensate polishing, Gland steam condensor, DA level control valves, LP feedwater heaters, deaerator, feedwater booster pumps, SGFPs, LP feedwater heaters, FRVs, FWIVs, S/Gs |
|
|
Term
| What is the function of the deaerator and DA storage tanks |
|
Definition
Remove Oxygen and Non-Condensable gases from the Feedwater Preheat the Feedwater Provide Net Positive Suction Head (NPSH) for the Feedwater Booster Pumps (FWBP) |
|
|
Term
| What is the function of the aux feedwater system |
|
Definition
| 2.1 Provide a source of feedwater to the Steam Generators when the Main Feedwater System or the Residual Heat Removal (RHR) System is not available. |
|
|
Term
| State the functions of the circ water system |
|
Definition
Supplies cooling water from the reservoir to the main condenser.
CWS piping routes open loop auxiliary cooling water system return and essential cooling water pond blowdown to the reservoir. |
|
|
Term
| What are the three basic requirements for an electrical generator |
|
Definition
| conductor, magnetic field, general motion |
|
|
Term
| What is the main generators stator, its function, and how is it cooled |
|
Definition
Stator : stationary winding through which electric current is induced by the rotating field windings
Function - collect the induced current and provide a circuit path to the output of the generator (output bushings)
Stator is cooled by Stator Cooling Water |
|
|
Term
| What is the main gererator's rotor, what is its function, and what is it cooled by |
|
Definition
Rotor : directly couple to the shaft of the Main Turbine and rotates at 1800 rpm synchronous speed (or 60hz)
Function - supply a regulated, rotating DC field to induce voltage, and resultant current flow in the generator stator windings
Rotor is cooled by the hydrogen gas |
|
|
Term
| What is the function of the generator exciter |
|
Definition
| Controls generator output voltage by varying the current to the generator rotating field windings |
|
|
Term
| What is the ESF Electrical system function |
|
Definition
| Provides reliable electrical power to ensure functioning of components and systems essential to all modes of plant operations including emergency shutdown |
|
|
Term
| What is the function of the ESF diesel generator? |
|
Definition
| SUPPLY ELECTRICAL POWER TO THE ENGINEERED SAFETY FEATURES (ESF) BUSES IN THE EVENT OF A LOSS OF OFFSITE POWER (LOOP) |
|
|
Term
| Define an off-normal condition |
|
Definition
an abnormal operating condition usually caused by plant equipment malfunction (typically minor and doesnt usually result in a reactor trip) |
|
|
Term
| Define an emergency condition? |
|
Definition
| An operating which causes or indicates the need to protect the reactor by initiating a reactor trip |
|
|
Term
| Define an accident condition |
|
Definition
| An operating condition which releases or has the potential to release radioactive fission products to the environment. |
|
|
Term
| What are the 4 levels of emergency classification at STP in order of least significance to most significant? |
|
Definition
1.Notification of unusal event 2.Alert 3.Site area emergency 4.General emergency |
|
|
Term
| What are the three purposes of the tech specs? |
|
Definition
They establish what the power limits are for the core and what automatic protective settings must exist to limit core and system operation to within design limits.
They spell out the lowest level of performance for safety-related equipment and their surveillance (testing) requirements in order to mitigate accident conditions
They also define Administrative procedures and personnel which are required to ensure safe operation of the plant. |
|
|