RMS Flashcards
Placing the Fuel Handling Area Radiation Monitors, RIA-2316 and RIA-2317, cutout switches to the IN position will:
A. Enable automatic closure of specific Containment Isolation valves.
B. Trip the Fuel Handling Area Supply Fan, V-7, on one out of two logic.
C. Enable automatic closure of Fuel Handling Area exhaust dampers.
D. Trip the Penetration and Fan Room Fans, V-78 and V-79, on high radiation.
A. Enable automatic closure of specific Containment Isolation valves.
CORRECT - Not all containment isolation valves are affected by these monitors; only the ones associated with the fuel handling area.
Given the following conditions: • A batch release is in progress. • RIA-1113, Waste Gas Process Monitor, alarms. CV-1113, Waste Gas Surge Tank Outlet, closes and: A. Waste Gas Compressor, C-54, trips. B. CV-1123, WGDT Outlet, closes. C. Inservice Main Exhaust Fan trips. D. Standby Main Exhaust Fan starts.
B. CV-1123, WGDT Outlet, closes.
Which one of the following radiation monitors will cause an automatic actuation upon
detection of a high radiation condition?
A. RIA-0833, Service Water Monitor.
B. RIA-0915, Component Cooling Water Monitor.
C. RIA-1323, Circulating Water Monitor.
D. RIA-5211, Turbine Building Sump Monitor.
B. RIA-0915, Component Cooling Water Monitor.
Following a Loss of Coolant Accident, Radioactive Gas Effluent Monitor (RGEM) annunciator EK-0207, “STACK EFF RAD C-169 HIGH” is received in the Control Room.
Which of the following can be used to validate this alarm?
A. Both trains of the RGEM sample pumps are in service.
B. RIA-2327, High Range Monitor, meter transfers from R/hr to uC/ml.
C. RGEM transfers from Normal to High Range Noble Gas Monitor.
D. RIA-2325, Iodine and Particulate Monitor, is in service.
C. RGEM transfers from Normal to High Range Noble Gas Monitor.
Refer to the graphic below to answer the following question.
You are performing a source check of RIA-1049, Liquid Radwaste Discharge Monitor, in preparation for a release of T-91, Utility Water Tank. Which one of the following describes the operation of the check source pushbutton, including when alarm EK-1365, PROCESS LIQUID MONITORING HI RADIATION, is expected to be received on panel C-13?
A. When the CHECK SOURCE pushbutton is depressed, a test voltage is applied to
the detector that causes a detector output signal. Alarm occurs when reading has
reached the “HIGH” setpoint.
B. When the CHECK SOURCE pushbutton is depressed, a test voltage is applied to
the detector that causes a detector output signal. Alarm occurs when reading has
reached the “WARN” setpoint.
C. When the CHECK SOURCE pushbutton is depressed, a source near the detector is
unshielded, causing a detector output signal. Alarm occurs when reading has
reached the “HIGH” setpoint.
D. When the CHECK SOURCE pushbutton is depressed, a source near the detector is
unshielded, causing a detector output signal. Alarm occurs when reading has
reached the “WARN” setpoint.
C. When the CHECK SOURCE pushbutton is depressed, a source near the detector is
unshielded, causing a detector output signal. Alarm occurs when reading has
reached the “HIGH” setpoint.
During full power operations the output from East Safeguards Radiation Monitor,
RIA-181 0, has failed low and is declared inoperable.
Which of the following actions must be taken immediately?
A. Verify East Safeguards V-27A and V-27B are operable.
B. Verify West Safeguards Monitor RIA-1811 is operable.
C. Close East Safeguards Dampers PO-1810 and PO-1817.
D. Disable East Safeguards Sump Pumps P-72A and P-72B.
C. Close East Safeguards Dampers PO-1810 and PO-1817.
During a Control Room panel walkdown it is noted that the Containment Gamma Radiation Monitor RIA-2322 indication rose to 10 E3 R/hr for 3 seconds and then returned to normal. No annunciators alarmed.
This is an indication that the:
A. Containment Gamma Radiation Monitor RIA-2322 has failed.
B. Internal Electronic Check Source was performed successfully.
C. Annunciator EK-0226, “CONT GAMMA RIA-2322 FAIL” has failed.
D. External source check performed by maintenance is in progress.
B. Internal Electronic Check Source was performed successfully.
Why does the Alarm Response Procedure (ARP-8) for RIA-181 0, East Eng Safeguard Radwaste Isolation Vent Radiation Monitor, contain guidance that disallows the operators from selecting the setpoint range to the 1.0E+6 scale?
A. Because the limit setting of Technical Specification 3.3.10, Engineered Safeguards
Room Ventilation (ESRV) Instrumentation, would be exceeded.
B. This action would isolate air flow to and from East Engineered Safeguards, which
will result in the room overheating if the plant is in Mode 1.
C. This action would start P-181 0, East Engineered Safeguards Sample Pump, which
will initiate a diagnostic check of the sample flow path through RIA-181 O.
D. During a Design Basis Accident, RIA-1810 is not capable of providing an alarm
function on this scale.
A. Because the limit setting of Technical Specification 3.3.10, Engineered Safeguards Room Ventilation (ESRV) Instrumentation, would be exceeded.
Given the following:
* A liquid radwaste batch is being released.
* The following alarm then annunciates:
EK-1365, “PROCESS L1Q MONITORING HIGH RADIATION”
* The NCO verifies RIA-1049, Liquid Radwaste Monitor, in alarm.
Which one of the following automatic actions will occur?
A. A CLOSE signal is sent to both CV-1049, 3” Discharge Isolation Valve, and to CV-1051, 1” Discharge Isolation Valve.
B. P-76A, Canal Sample Pump, starts so determination can be made for manual
termination of the batch by closing MV-CRW172, Discharge to Lake.
C. The in-service Main Exhaust Fan (V-6A/V-6B) TRIPS and associated dampers CLOSE.
D. V-10, Radwaste Area Supply Fan, trips and associated dampers CLOSE.
A. A CLOSE signal is sent to both CV-1049, 3” Discharge Isolation Valve, and to CV-1051, 1” Discharge Isolation Valve.
Given the following conditions: • A batch release is in progress. • RIA-1113, Waste Gas Process Monitor, alarms. CV-1113, Waste Gas Surge Tank Outlet, closes and: A. Waste Gas Compressor, C-54, trips. B. CV-1123, WGDT Outlet, closes. C. Inservice Main Exhaust Fan trips. D. Standby Main Exhaust Fan starts.
B. CV-1123, WGDT Outlet, closes.
A liquid radwaste batch release of Utility Water Storage Tank T-91 is in progress via CV-1049, 3” Discharge Isolation. RIA-1049 reaches its high alarm setpoint and EK-1365, “Process Liquid Monitoring Hi Radiation” alarms, but CV-1049 does NOT automatically close.
Based on these conditions, you must …
A. have the release terminated by selecting handswitch for CV-1 049 to close, and
refer to EI-8, “Onsite Radiological Monitoring.”
B. I have the release terminated by closing MV-CRW172, Discharge to Lake, and refer
to EI-1, “Emergency Classification and Actions.”
C. have the release terminated by selecting handswitch for CV-1 049 to close, and
refer to EI-1, “Emergency Classification and Actions.”
D. have the release terminated by closing MV-CRW172, Discharge to Lake, and refer to EI-8, “Onsite Radiological Monitoring.”
B. I have the release terminated by closing MV-CRW172, Discharge to Lake, and refer
to EI-1, “Emergency Classification and Actions.”
During a Steam Generator Tube Rupture which of the following is an automatic action initiated by RIA-0707 Steam Generator Blowdown monitor and the basis for the action?
The monitor signals the:
A. isolation of both outer bottom blowdown valves (CV-0770, 0771) to limit the spread of contamination in the blowdown system
B. isolation of both surface blowdown valves (CV-0738, 0739) to prevent contamination from reaching chemistry’s sample panel
C. isolation of PCV-6003, Flash Tank T-29A Pressure Control to minimize Main Condenser contamination
D. trip of both S/G blowdown pumps to prevent spread of contamination from the blowdown system
A. isolation of both outer bottom blowdown valves (CV-0770, 0771) to limit the spread of contamination in the blowdown system
Placing the Fuel Handling Area Monitors RIA-2316 and RIA-2317 cutout switches to the IN position will:
A. Enable automatic closure of selected Containment Isolation valves.
B. Trip the Fuel Handling Area Supply Fan V-7 on one out of two logic.
C. Enable automatic closure of Fuel Handling Area exhaust dampers.
D. Trip the Penetration and Fan Room V-78 and V-79 on high radiation.
A. Enable automatic closure of selected Containment Isolation valves.
The plant is nearing the end of a long production run with elevated PCS activity due to
a failed fuel rod. Operators note a rising sump trend along with elevated counts on the
Containment Gas monitor. The crew enters ONP 23.1 for a PCS leak and the reactor
is manually tripped. During the immediate actions of EOP-1 the NCO at the controls
notes that EK-1363 “CONTAINMENT HI RADIATION” has annunciated.
Based on this alarm which of the following accounts for the above conditions and
describes any required actions?
A. At least one containment radiation monitor has gone into WARNING. Ensure containment is isolated
B. At least one containment radiation monitor has gone into ALARM. No manual actions are required
C. At least one containment radiation monitor has gone into ALARM. Ensure containment is isolated
D. At least two containment radiation monitors have gone into ALARM. No manual actions are required
C. At least one containment radiation monitor has gone into ALARM. Ensure containment is isolated
Correct - This alarm will come in when the first containment monitor goes into
alarm. Containment doesn’t automatically isolate until at least two Containment
Radiation monitors go into alarm. This is a knowledge item from EOP-1 because
an operator is expected to check the monitors when the alarm comes in and
isolate containment if necessary.
During the review of a Liquid Release Order Form HP 6.4-4 the Maximum required
release rate is recorded as 8 gpm for the Filter Waste Monitor Tank T-63. The number
of dilution water and service water pumps has remained constant since the tank=s
sample was pulled. Plant conditions are normal with all systems functioning normally.
As the Shift Manager Reviewer is it acceptable to authorize this release and why or
why not?
A. This liquid release can be authorized because the flow rate is acceptable and the Flow Control Valve will function properly
B. This liquid release shall not be authorized ONLY because the flow rate is such that the Flow Control Valve may not function properly
C. This liquid release shall not be authorized ONLY because the flow rate is such that the Radiation Monitor may not function properly
D. This liquid release shall not be authorized because the flow rate is such that the Radiation Monitor and the Flow Control Valve may not function properly
A. This liquid release can be authorized because the flow rate is acceptable and the Flow Control Valve will function properly
The Containment Isolation Actuation Signal from the Containment High Radiation Monitors RIA-1805 through 1808 is calibrated to first occur at: A. 10 E4 R/hr. B. 10 E3 R/hr. C. 10 E2 R/hr. D. 10 E1 R/hr.
D. 10 E1 R/hr.
Which one of the following radiation monitors will cause an automatic actuation upon detection of a high radiation condition?
A. RIA-OS33, Service Water Monitor.
B. RIA-0915, Component Cooling Water Monitor.
C. RIA-1323, Circulating Water Monitor.
D. RIA-5211, Turbine Building Sump Monitor.
B. RIA-0915, Component Cooling Water Monitor.
The alarm “PROCESS LIQ MONITORING HI RADIATION” annunciates due to a high
alarm condition on RIA-0707, Steam Generator Blowdown Radiation Monitor.
The following valve positions are subsequently noted:
CV-0704, Blowdown Tank Discharge to Mixing Basin:
CV-0738, ‘B’ S/G Surface Blowdown:
CV-0739, ‘A’ S/G Surface Blowdown:
CV-0770, ‘B’ S/G Bottom Blowdown:
CV-0771, ‘A’ S/G Bottom Blowdown:
CLOSED
CLOSED
CLOSED
OPEN
OPEN
Which of the following is the correct diagnosis of the above valve positions?
A. Per design. S/G sampling capability is maintained through bottom blowdown CVs, and secondary plant contamination is minimized by closing the surface blowdown CVs.
B. Per design. S/G sampling capability is lost since the surface blowdown CVs are closed. Bottom blowdown CVs remain open to allow further trending of RIA-0707.
C. NOT per design. ALL valves should be CLOSED to prevent secondary plant contamination.
D. NOT per design. ALL valves should remain OPEN to maintain full S/G sampling capability.
C. NOT per design. ALL valves should be CLOSED to prevent secondary plant contamination.
CORRECT - Closing of the valves ensures radiation release potential is minimized.
