Sro Rps

Front 1

Question 1: To open a Reactor Trip breaker, the undervoltage coil _____________ and/or the shunt coil ______________.

Back 1

Answer 1: de-energizes, energizes

Front 2

Question 2: Which train of reactor protection controls Reactor Trip bypass breaker "B"?

Back 2

Answer 2: "A"

Front 3

Question 1: What affect does the loss of an instrument bus have on the reactor protection system?

Back 3

Answer 1: One protection channel and one RPS power supply de-energizes. If the lost bus is NN01 or NN04 the respective slave relays will be de-energized.

Front 4

Question 2: 125 VDC Power System bus NK01 supplies power to which Reactor Trip and/or Reactor Trip bypass breakers?

Back 4

Answer 2: "A" Reactor Trip and Reactor Trip bypass breaker.

Front 5

For each of the following excore nuclear instrumentation Reactor Trips, match it with the corresponding accident type for which it is designed to protect against: A. Power Range, Neutron Flux High Setpoint

Back 5

Over-power

Front 6

For each of the following excore nuclear instrumentation Reactor Trips, match it with the corresponding accident type for which it is designed to protect against: B. Power Range, Neutron Flux Low Setpoint

Back 6

Startup accident

Front 7

For each of the following excore nuclear instrumentation Reactor Trips, match it with the corresponding accident type for which it is designed to protect against: C. Power Range, Neutron Flux, High Positive Rate

Back 7

Rod ejection accident

Front 8

For each of the following excore nuclear instrumentation Reactor Trips, match it with the corresponding accident type for which it is designed to protect against: D. Power Range, Neutron Flux, High Negative Rate

Back 8

Multiple rod drop accident

Front 9

For each of the following excore nuclear instrumentation Reactor Trips, match it with the corresponding accident type for which it is designed to protect against: E. Intermediate Range High Flux Trip

Back 9

Startup Accident

Front 10

For each of the following excore nuclear instrumentation Reactor Trips, match it with the corresponding accident type for which it is designed to protect against: F. Source Range High Flux Trip

Back 10

Startup Accident

Front 11

Question 2: For each of the following terms, identify it as being contained in the calculation of the setpoint for OT?T, OP?T, or BOTH: Power level Pressure TAVG Delta-I Temperature rate Lead-Lag TAVG

Back 11

Answer 2: Power level - BOTH Pressure - OT?T TAVG - OP?T Delta-I - BOTH Temperature rate - OP?T Lead-Lag TAVG - OT?T

Front 12

Question 3: The reactor is operating at 100% with all systems in a normal lineup with control rods in manual. State the effect each event below will have on the OT?T setpoint for Channel II. Answer with INCREASE, DECREASE, or NO CHANGE. No explanation required. A. Power Range Channel 42 lower detector fails to zero. B. BB PT-456 Pressurizer pressure transmitter fails high. C. Auctioneered High Tavg unit fails high. D. Reactor power is reduced to 50% with normal pressure and temperature

Back 12

Answer 3: A. Decrease B. Increase C. No Change D. Increase

Front 13

Question 1: List the four functions of P-4.

Back 13

Causes turbine trip when Reactor Trips Causes MFWIS if TAVG low Allow operator block of auto SIS after 60 sec delay Arms steam dumps in PLANT TRIP mode

Front 14

Question 2: List the 5 functions that are automatically enabled on increasing power by P-7.

Back 14

Answer 2: Pressurizer pressure - low Pressurizer water level - high Reactor coolant flow - low Undervoltage RCPs Underfrequency RCPs

Front 15

Question 1: In the reactor protection system, do the input relays energize or de-energize to actuate?

Back 15

Answer 1: de-energize

Front 16

Question 2: In its most basic sense, what is multiplexing?

Back 16

Answer 2: Transmitting a large amount of data over a few electrical conductors.

Front 17

List the three subsystems of the Reactor Makeup System.

Back 17

Answer 1. The Reactor Makeup Water System The Boric Acid System The Reactor Makeup Water Control System

Front 18

Match the Reactor Makeup Control System component to its description. A. RMWST

Back 18

150,000 gallons

Front 19

Match the Reactor Makeup Control System component to its description. B. Rx MU Water Transfer Pump

Back 19

150 gpm

Front 20

Match the Reactor Makeup Control System component to its description. C. Boric Acid Tank

Back 20

26,000 gallons

Front 21

Match the Reactor Makeup Control System component to its description. D. Boric Acid Batching Tank

Back 21

Includes an agitator

Front 22

Match the Reactor Makeup Control System component to its description. E. Boric Acid Transfer Pump

Back 22

75 gpm

Front 23

Match the Reactor Makeup Control System component to its description. F. Blending Tee

Back 23

Located upstream of BG FT-111

Front 24

Match the Reactor Makeup Control System component to its description. G. BGFCV0110A

Back 24

Controls boric acid flow rate

Front 25

Match the Reactor Makeup Control System component to its description. H. BGFCV0111A

Back 25

Controls makeup water flow rate

Front 26

Match the Reactor Makeup Control System component to its description. I. BGHV8104

Back 26

Emergency borate

Front 27

Question 1. What advantage over the Dilution mode is provided by the Alternate Dilute mode of operation and how is this accomplished?

Back 27

Answer 1. The Alternate Dilute mode allows dilution water to get to the RCS faster. This is because makeup water is aligned both to the top and bottom of the VCT.

Front 28

Question 2. List the actions required by the control room operator to initiate Emergency Boration.

Back 28

Answer 2. 1. Open Emergency Boration Control valve (BG HV-8104). 2. Start at least one Boric Acid Transfer pump. 3. Verify flow on the Emergency Boration Flow meter.

Front 29

Question 1. What is the design purpose of the BTRS? What is it actually used for?

Back 29

Answer 1. By design; the BTRS was to vary RCS boric acid concentration for reactivity control during load follow operations, without generating large volumes of radioactive liquid waste. Because load follow is not used by WCGS, the BTRS is used at EOL when boron concentrations are low to minimize wastewater volume.

Front 30

Question 2. (T/F) When reducing RCS boron concentration, the BTRS heats the coolant before it enters the ion exchanger resin bed.

Back 30

Answer 2. False

Front 31

Question 1. List four scenarios that have the potential of causing an uncontrolled RCS dilution.

Back 31

Answer 1. 1. Plant cooldown following SG tube rupture with back filling of an idle RCS loop. 2. Shutting down RCP prior to borating RCS to refueling boron concentration. 3. Loss of off-site power during post-refueling dilution to criticality. 4. Discharging an SI Accumulator that has lower boron concentration than RCS.

Front 32

Question 2. What would be the consequence if chemicals were added to the RCS using to SYS BG-207, Adding Chemicals To The Reactor Coolant System, when the plant is in Mode 6?

Back 32

Answer 2. This is a violation of Technical Specifications by opening up a valve that is required to be closed in Mode 6 to prevent dilution of the RCS.

Front 33

Q. What are the functions of the RCS?

Back 33

A. 1. Transfer heat generated in the reactor core and by the RCP's to the S/Gs. 2. Barrier between the fuel and the environment.

Front 34

Q. What reactivity functions are performed by the reactor coolant?

Back 34

A. 1. Moderates neutrons 2. Solution for boric acid 3. Reflects neutrons

Front 35

Q. What is the function of the RCS loops?

Back 35

A. Contain and transport the coolant between the RV and the S/Gs.

Front 36

Q. What is the function of the S/Gs?

Back 36

A. Transfer heat from the primary side to the secondary side and produce dry, saturated steam.

Front 37

Q. What indication is available to detect a leaking PORV?

Back 37

A. An RTD is strapped on the tailpipe of the PORV. A temperature increase could indicate a leaking PORV

Front 38

Q. How can the contents of the PRT be cooled?

Back 38

A. By recirculation through the RCDT HX or by spraying cold RMW in to the tank and pumping out to the RHUTs.

Front 39

Q. Which of the following connections extends into the RCS coolant flowpath? A. Hot leg sample connections on loop 1 & 3. B. RHR hot leg suction connections on loops 1 & 4. C. ECCS cold leg injection in all 4 loop cold legs. D. CVCS letdown from loop 3 crossover leg.

Back 39

A. A, Hot leg sample connections on loop 1 & 3 extend into the RCS.

Front 40

Q. How does the design of the reactor coolant system help support the formation of natural circulation cooling?

Back 40

A. S/Gs (heat sink) are located above the reactor vessel (heat source).

Front 41

Q. How is a vacuum established on the RCS prior to normal fill & vent?

Back 41

A. An air driven eductor is used to pull a vacuum on the RCS.