ML051610368
| ML051610368 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/31/2005 |
| From: | Valos N NRC/RGN-III/DRS/OLB |
| To: | Exelon Nuclear |
| References | |
| 50-254/05-301, 50-265/05-301 | |
| Download: ML051610368 (76) | |
Text
QUESTION 001 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295001K301 QUESTION Unit 1 was operating at 100% reactor power when the 1B Reactor Recirc pump tripped.
All systems responded as designed to this event.
Complete the following statement regarding the INITIAL Reactor water level response.
Indicated reactor water level will __(1)__ due to the __(2)__.
a.
(1)
INCREASE (2) collapse of steam voids b.
(1)
DECREASE (2) lack of coolant velocity to sweep voids into the steam separator c.
(1)
INCREASE (2) displacement of water by increased steam voiding d.
(1)
DECREASE (2) activation of the feedwater Level Control scram profile ANSWER c.
QCOP 0202-21, Unit 1 Reactor Recirculation system Shut Down of One pump MEMORY BANK
QUESTION 002 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295003A104 QUESTION The following annunciators are received:
901-8 A9 125 V BATTERY CHARGER 1 TRIP 901-8 A10 250 V BATTERY CHARGER 1 TRIP 901-8 A5 480V SWGR BREAKER TRIP BUS 19 "live bus" mimic light is out.
Assume no operator action.
After 10 minutes, Turbine building bus 125 VDC bus 1A:
a.
remains energized from the Unit ONE 125 VDC battery.
b.
remains energized from the 1A 125VDC battery charger.
c.
is de-energized.
d.
remains energized from the Unit TWO 125 VDC battery.
ANSWER a.
REFERENCE QOP 6900-02 MEMORY BANK EXPLANATION:
The Unit 1 125 VDC distribution remains energized from the battery when the charger is lost. Bus 19 (MCC19-2) powers Unit 1 125 VDC Charger 1.
QUESTION 003 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295004A203 QUESTION Based on these indications from the 901-8 panel, which statement below best describes the status of the DC electrical distribution system?
Note: The alarm setpoint needles are not shown.
a.
The 250 VDC Battery Charger is malfunctioning.
b.
AT LEAST one Battery Charger on BOTH 24/48 VDC systems is malfunctioning.
c.
ALL DC system voltages are NORMAL d.
The 125 VDC Battery Charger is malfunctioning.
ANSWER d.
QCOS 6900-01, DC Lesson Plan HIGHER NEW EXPLANATION:
125VDC battery voltage must be >125.9VDC but is reading < 120 VDC.
QUESTION 004 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295005 2.1.28 QUESTION Unit 1 was operating at 100% power when the Main Generator tripped on a loss of field.
Which of the following lists components that receive a trip signal directly from the 86 device?
a.
Stator Water Cooling pumps, Main Turbine and Main Generator Field Breaker b.
Stator Water Cooling pumps, Main Generator Field Breaker, GCB 3-4 and OCB 4-6 c.
Stator Water Cooling pumps, Main Turbine, OCB 1-11 and OCB 10-11 d.
Hydrogen Seal Oil pump, Main Turbine and Main Generator Field Breaker ANSWER a.
Lesson plan LN-6000 page 15 of 35 MEMORY NEW EXPLANATION:
The Unit 1 86 device trips the main turbine, stator water pumps, generator field breaker and output OCBs 6-7 and 7-8.
QUESTION 005 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295006K101 QUESTION Unit had been on-line for 345 days. At time 0910 an electrical transient resulted in a severe level transient; Reactor Level is -62 inches, stable It is now 0925.
Which of the following systems would most closely match the expected decay heat removal needs AND be available at this time?
a.
Main Turbine Bypass valves b.
CRD c.
RCIC d.
RWCU ANSWER c.
REFERENCE UFSAR 5.4-21 HIGHER NEW EXPLANATION:
RCIC designed to remove decay heat 10 minutes after scram with isolation from Main condenser CRD system flow is not sufficient to remove decay heat Main Turbine Bypass Valves are not available due to the Group I isolation
@ -59" RWCU is not available due to the Group III isolation @ 0"
QUESTION 006 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295016K203 QUESTION An ammonia spill near the plant has caused several Control Room operators to become nauseated.
After donning SCBA air packs, the Operators should verify that the Control Room Ventilation System is __(1)__.
If the Control Room Ventilation alignment can NOT be assured, and the ammonia concentration is INCREASING, the Operators should __(2)__.
a.
(1) in SMOKE PURGE (2) enter QOA 0010-05, PLANT OPERATION WITH THE CONTROL ROOM INACCESSIBLE b.
(1) in SMOKE PURGE (2)
REMOVE the SCBA masks, THEN DON breathing air masks c.
(1)
ISOLATED (2)
REMOVE the SCBA masks, THEN DON breathing air masks d.
(1) ISOLATED (2) enter QOA 0010-05, PLANT OPERATION WITH THE CONTROL ROOM INACCESSIBLE ANSWER d.
REFERENCE QOA 5750-13, TOXIC AIR OR SMOKE IN THE CONTROL MEMORY NEW EXPLANATION:
In response to ammonia, the CR HVAC should ISOLATE. Operators do not remove the SCBA masks and THEN don breathing air masks. They keep the same mask on, but connect a breathing air LINE to the regulator of the SCBA.
QUESTION 007 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295018K306 QUESTION Foreign material has partially covered the tube sheet at the inlet to the on-line Stator Water heat exchanger.
Complete statement below describing the system response, including the reason for the automatic actions.
The temperature control valve, throttling __(1)__, will reposition, to permit more flow __(2)__
the heat exchanger.
a.
(1) Service Water (2) through b.
(1) Service Water (2) around c.
(1) Stator Water (2) around d.
(1) Stator Water (2) through ANSWER d.
REFERENCE Lesson Plan LIC-5300, Generator Auxiliaries MEMORY NEW EXPLANATION:
The temperature control valve for the stator water system is a heat exchanger bypass valve on the stator water side. This is different from many other systems, where the TCV is usually located on the heat exchangers service water outlet.
QUESTION 008 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295019K207 QUESTION Unit 2 is at 100% power with all condensate demins in service when an instrument air line ruptures in the Turbine building.
Assume:
No operator actions taken Reactor Power and Level are so far unaffected.
With regards to the Condensate System:
The instrument air loss will cause hotwell level to _______
a.
RAISE and total flow through the Condensate Demins to INCREASE.
b.
LOWER and total flow through the Condensate Demins to INCREASE.
c.
LOWER and total flow through the Condensate Demins to DECREASE.
d.
RAISE and total flow through the Condensate Demins to DECREASE.
ANSWER b.
REFERENCE QOA 4700-06, TOTAL LOSS OF INSTRUMENT AIR Lesson Plans LIC-3200, LN-5500 HIGHER NEW EXPLANATION:
Hotwell level control valves for makeup and reject are air operated. The REJECT valves fail OPEN while the makeup valves fail CLOSED. The condensate demin A-G flow control valves fail AS-IS on a loss of instrument air. The H demin FCV fails OPEN. This, combined with the fact that the reject valves come off AFTER the condensate demins, will cause total demin flow to INCREASE.
QUESTION 009 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295021A102 QUESTION Unit TWO (2) has been shutdown and decay heat was being removed via the 2A RHR Loop in Shutdown Cooling. The 2B loop of RHR is tagged out and drained.
The 2A RHR pump tripped and actions were initiated to restore Shutdown Cooling. Before an RHR pump could be started, Reactor pressure INCREASED to 130 psig.
Which of the following actions, if any, must be taken to reestablish Shutdown Cooling? (may not describe ALL required actions.)
a.
Reactor pressure must be reduced to < 100 psig, ONLY.
b.
The Containment Cooling Permissive (S-17) keylock switch must be placed in the ON position, AND the Group II isolation logic must be reset.
c.
Nothing must be done, SDC will operate under present conditions.
d.
Reactor pressure must be reduced to < 100 psig AND the Group II isolation logic must be reset.
ANSWER d.
REFERENCE QCOA 1000-02 MEMORY BANK EXPLANATION:
When Rx Pressure increases above the SD Cooling isolation setpoint, (100 psig) it must be reduced BELOW the setpoint AND the isolation has to be reset to restore SDC.
QUESTION 010 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295023A203 QUESTION During refueling operations a mechanical failure in the mast results in an irradiated bundle dropping onto the fuel racks and being damaged.
Which one of the following will increase resultant contamination levels?
a.
Fuel pool temperature being at the HIGH end of the normal band.
b.
Fuel pool temperature being at the LOW end of the normal band.
c.
Skimmer surge tank level being at the LOW end of its normal band.
d.
Skimmer surge tank level being at the HIGH end of the band.
ANSWER a.
REFERENCE QCOA 1900-02 MEMORY NEW EXPLANATION:
High temperature water will release more radioactive material into the atmosphere. Skimmer surge tank level does not affect release of material since skimmer surge tank level does not directly affect fuel pool level.
QUESTION 011 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295024A108 QUESTION Unit 1 was operating at 100% power when at 10:15:00 a.m., a LOCA occurred inside the Drywell.
All automatic actions occurred, but NO high pressure injection systems are available.
At 10:20:00, the following conditions existed:
Rx Level
-59" slowly lowering Rx Pressure 900 psig slowly lowering DW Pressure 10.0 psig rising Torus Pressure 9.0 psig rising It is now 10:21:00 and conditions have changed:
Rx Level
-70" slowly lowering Rx Pressure 875 psig slowly lowering DW Pressure 2.0 psig rapidly lowering Torus Pressure 2.0 psig rapidly lowering No operator actions have been taken.
Which statement below describes how ADS will respond?
a.
ADS will initiate at 10:28:30.
b.
ADS will NOT automatically initiate because DW pressure is BELOW the initiation setpoint.
c.
ADS will NOT automatically initiate because low pressure ECCS pumps are NOT injecting.
d.
ADS will initiate at 10:21:50.
ANSWER d.
REFERENCE QCAN 901(2)-3 B-13 HIGHER NEW EXPLANATION:
at 10:20, ADS initiation logic started the 110 second timer because level was at -59", DW pressure was >2.5# and an RHR pump was running (auto started at 2.5 psig.) When DW pressure falls below 2.5# one minute later, this DOES NOT reset the ADS timer. Thus ADS will initiate at 10:21:50.
10:28:30 would be correct IF the 2.5# signal automatically reset, but it does not.
Low pressure ECCS pumps only need to be RUNNING, not INJECTING to satisfy ADS logic.
QUESTION 012 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295024 2.1.27 QUESTION Which malfunction below, were it to occur during a LOCA, would be MOST LIKELY to cause containment failure?
Consider each malfunction, independently, as the ONLY malfunction.
Assume that NO operator action is taken in response to the malfunction.
a.
The 3A Target Rock Valve bellows has a hole in it.
b.
The Low Pressure Drywell Spray Interlock FAILS to actuate with sprays in operation.
c.
The Reserve Auxiliary Transformer TRIPS and the U1 EDG fails to start.
d.
Two Torus-to-DW vacuum breakers stick in the CLOSED position.
ANSWER b.
REFERENCE EPG Bases HIGHER NEW EXPLANATION:
The containment spray low pressure interlock activates when DW pressure exceeds 2.5 psig. When DW sprays are initiated it will close the spray valves when DW pressure is reduced to 1 psig. A failure of the interlock could result in air being drawn into the containment, reducing the pressure suppression capability. Also, the containment could exceed its design negative pressure.
Design Bases assumes a LOOP with a LOCA.
A hole in the Target Rock valve bellows will not prevent automatic action on pressure.
Only 9 of 12 Torus to DW vacuum breakers are required to be operable as long as all 12 are closed.
QUESTION 013 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295025K102 QUESTION Unit 2 has experienced a Severe Accident. It has been determined that the reactor core has relocated to the vessel bottom head and is NOT submerged. The core has NOT breached the RPV.
Which of the following would INCREASE the likelihood of the core breaching the RPV?
a.
FLOODING the DW b.
INCREASING RPV pressure c.
INITIATING DW sprays d.
INJECTING with Core Spray ANSWER b.
REFERENCE Lesson plan SAMG-01 pages 8 and 10 of 19 MEMORY NEW EXPLANATION:
With the core relocated to the vessel bottom head the reactor vessel metal will heat up. An increase in reactor pressure will increase the possibility of RPV failure. Injection of any system that can contact the dispersed fuel will remove heat that would have been passed to the vessel wall. Additionally drywell sprays and flooding will cool the external vessel walls reducing the likelihood of rupture.
QUESTION 014 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295026K206 QUESTION Torus water temperature rises from 75°F to 95°F over several weeks due to summer heat.
Which of the following describes the effect of the rise in torus water temperature?
a.
The INCREASE in torus airspace would result in LOWER post-LOCA peak drywell pressure.
b.
The DECREASE in torus water level would result in LOWER available NPSH for the ECCS pumps.
c.
The DECREASE in torus airspace would result in HIGHER post-LOCA peak drywell pressure.
d.
QQ 25424(1480)><<The INCREASE in torus water level would result in HIGHER available NPSH for the ECCS pumps.
ANSWER c.
REFERENCE UFSAR page 6.2-2 HIGHER NEW EXPLANATION:
The increase in torus water temperature would cause the volume of water to increase and the volume of the air space to decrease. This would result in higher peak pressures during a LOCA. The resultant level increase would not change the mass of water so the available NPSH would not change.
QUESTION 015 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295028K304 QUESTION Drywell pressure and temperature are rising slowly due to unknown causes.
Drywell Pressure is 1.45 psig Drywell Temperature is 182°F Which of the following statements describes whether or NOT the Drywell Coolers should be operated and the reason?
a.
Drywell coolers SHOULD be operated because they will have LESS impact on continued plant operation than other methods of Drywell temperature reduction.
b.
Drywell Coolers SHOULD be operated because they remove MORE heat than ALL other methods of Drywell temperature reduction.
c.
Drywell coolers SHOULD NOT be operated because they are REQUIRED to be TRIPPED.
d.
Drywell Coolers SHOULD NOT be operated because CONTAINMENT VENT and PURGE will control Drywell pressure AND temperature.
ANSWER a.
REFERENCE EPG Bases MEMORY NEW EXPLANATION:
Drywell Coolers have LESS impact on plant operations than other, more significant actions taken in the QGA's (like sprays) but they DO have an impact. Containment Venting is not counted upon to reduce Drywell temperature.
QUESTION 016 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295030A102 QUESTION The following conditions exist following a scram.
Reactor Pressure is at 600 psig - decreasing All Control Rods inserted.
Reactor Level is -125 in. - decreasing Torus Level is 10.5 ft. - decreasing Drywell pressure 13.2 psig - rising Torus pressure 12.0 psig. - rising RCIC should be __(1)__ because __(2)__
a.
(1) immediately TRIPPED (2) the steam exhaust discharging into the Torus WILL cause the PCPL to be exceeded.
b.
(1) immediately TRIPPED (2) it should have automatically tripped.
c.
(1) allowed to inject (2) the steam exhaust discharging into the Torus will NOT cause the PCPL to be exceeded.
d.
(1) allowed to inject (2)
ALL trips are bypassed.
ANSWER c.
REFERENCE BWROG EPGs/SAGs Appendix B MEMORY NEW EXPLANATION:
From EOP Bases
QUESTION 017 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295031A204 QUESTION An ATWS is in progress on Unit 2:
ALL ADS valve key-lock switches are in "Manual".
RHR systems are injecting at rated flow.
Reactor level was steady at -150 inches when ALL RPV level indications went upscale over a one minute period.
ALL Acoustic Monitor AMBER AND GREEN lights are LIT and RED lights are EXTINGUISHED.
Reactor pressure is 15 psig and DECREASING.
Which of the following statements describes core cooling status and the basis for the description?
a.
Core cooling IS assured because core submergence is confirmed by the increasing Reactor water level trend.
b.
Core cooling IS assured because RHR flow is at rated.
c.
Core cooling IS assured because sufficient steam flow is confirmed by the decreasing Reactor pressure.
d.
Core cooling is NOT assured because neither core submergence or sufficient core flow can be assured.
ANSWER d.
REFERENCE QCAP 0200-10, QGA 101 HIGHER BANK EXPLANATION:
No indication provided that reactor level has been flooded to the Main Steam Lines (submergence) Using QGA 101, the candidate will determine that there is NOT enough steam flow (ADS valves closed)
Spray cooling is not assured because only RHR is injecting, (Core spray not injecting during an ATWS)
QUESTION 018 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295037 2.1.30 QUESTION Unit 1 was operating at 100% power when all Reactor Feedpumps tripped.
Reactor Manual scram pushbuttons A AND B were depressed Mode Switch was placed in SHUTDOWN ALL APRM Downscale lights are EXTINGUISHED FOUR RPS lights (on the LEFT) are ILLUMINATED FOUR RPS lights (on the RIGHT) are EXTINGUISHED ALL individual, blue scram lights are EXTINGUISHED The NEXT action to be taken should be:
a.
Dispatch an Operator to the REACTOR BUILDING to VENT the scram air header.
b.
At the 901-3 panel, RUN the Reactor Recirc pumps to MINIMUM SPEED c.
At the 901-5 panel, ARM and DEPRESS the ARI pushbuttons.
d.
INSIDE the 901-15 AND 901-17 PANELS, REMOVE the scram fuses.
ANSWER c.
REFERENCE Strategies for Successful Transient Mitigation rev 11a. QGA 101 HIGHER MODIFIED EXPLANATION:
Strategies for Successful Transient Mitigation, upon indication of failure to scram direct the NSO to actuate ARI AND run the reactor recirc pumps to minimum, HOWEVER the ORDER of the steps in QGA 101, requires ARI actuation FIRST. Other distracters, pull fuses and vent the scram air header are not performed until after QCOP 300- 28 is directed, later in QGA 101.
QUESTION 019 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295038K101 QUESTION Performing the actions of QGA 400 Radioactivity Release Control will...
a.
SACRIFICE Turbine Building habitability to protect members of the general public.
b.
MAINTAIN habitability in the reactor building to facilitate accident response.
c.
MINIMIZE the potential increase of the risk of cancer in members of the general public.
d.
PREVENT radioactive releases from affecting areas outside the site fence.
ANSWER c.
REFERENCE EPG pages 2-9-1 and 2-9-6 MEMORY NEW EXPLANATION:
QGA 400 limits the release of radioactivity to the general public requiring a blowdown before release rates reach the General Emergency level. TB equipment is not a concern. It maintains habitability in the TB not RB.
QUESTION 020 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 600000K201 QUESTION With the Fire Water system in standby lineup, which ONE of the following situations would cause an automatic start of BOTH Fire Diesels?
Do NOT assume any additional malfunctions.
a.
Spurious actuation of the sudden pressure relay on T-22 b.
Smoke detector actuation in the Simulator c.
Heat sensor actuation in the U2 Emergency Diesel Generator Room d.
A spurious closure signal to MO 1/2 3906, FIRE PROT SW SPLY VLV ANSWER a.
REFERENCE Lesson plan LN-4100 MEMORY NEW EXPLANATION:
Activation of a transformer sudden pressure relay deluges the transformer, which would cause a low pressure to be detected at BOTH fire diesels, which would auto-start. Fire in the EDG room activates a Carbon dioxide deluge. A fire in the Simulator activates a HALON deluge. MO 1/2 3906 is NORMALLY closed, and even if it were not, there is a MANUAL valve normally open, to keep the fire header pressurized.
QUESTION 021 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295008.AA2.05 QUESTION Given:
Unit 2 was operating at 50% reactor power when it scrammed due to a loss of EHC After the scram RPV water level was at 35" and LOWERING with feed flow indication of ZERO when ALL Reactor Feed Pumps TRIPPED due to a faulty low suction pressure switch At -40" RPV water level, the NSO restarted the A RFP and manually OPENED the B Main FRV At 42" the B Main FRV was manually CLOSED with its controller Two minutes later the NSO notes that RPV water level is 55" and the A RFP is TRIPPED What caused RPV level to reach this level?
a.
Decay heat is affecting the water injected by the NSO.
b.
LOW pressure ECCS pumps are injecting.
c.
The FWLC system is holding the A Main FRV OPEN.
d.
HIGH pressure ECCS pumps are injecting.
ANSWER a.
REFERENCE QCOP 1000-05 HIGHER NEW EXPLANATION:
Relatively cool feedwater will swell when it is heated. Level did not drop low enough to start the HP ECCS systems. The digital FW scram profile would be deactivated two minutes after the scram and due to level being high. With RPV water level at 35" and lowering when the RFPs tripped, the A FRV would be closed. When the RFPs tripped the FRV go into manual and position does not change.
QUESTION 022 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295010K303 QUESTION Which of the following describes the reason for monitoring Drywell radiation levels during accident situations with elevated Drywell pressure?
Drywell Rad Monitor readings are used by Control Room Operators to determine _____
a.
that fission product barriers may have failed.
b.
if the core is submerged.
c.
offsite release rate.
d.
if the Reactor is shutdown following a scram.
ANSWER a.
REFERENCE EP-AA-1006 App. 3, QGA 500-4 Lesson Plan MEMORY NEW EXPLANATION:
Drywell radiation is used by the Site Emergency Director (Shift Manager) to determine that fission products may have failed. No procedures exist for Operators to determine power, water level, or offsite release rates based upon DW radiation monitor readings.
QUESTION 023 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295014K207 QUESTION You are the Unit 1 NSO and notice the following indications:
Reactor power on the APRMs is slowly rising.
Main Generator load is rising.
Which of the following would account for this set of indications?
a.
- 2 Main Turbine Bypass Valve OPEN b.
1D3 Extraction Bypass Valve CLOSED c.
LP Heater String Bypass Valve CLOSED d.
1A1 Heater level HIGH ANSWER d.
REFERENCE QCOA 3500-01 HIGHER MODIFIED EXPLANATION:
A high level in an A heater causes the LP heater string isolation valves to close and the LP heater string bypass to open. Causing FW temperature to drop, causing the indications shown for power increase. The Turbine bypass valve opening, would cause FW temperature to drop, but would also cause Generator load to drop. The other choices represent normal valve positions and would not cause FW temperature to drop.
QUESTION 024 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295015K301 QUESTION QCGP 2-3, REACTOR SCRAM directs the NSO, under some circumstances, to place the RWM mode switch to "BY".
This action, when performed under those circumstances, bypasses __(1)__, to allow rods to be
__(2)__.
a.
(1) the RPIS INOP block (2)
INSERTED b.
(1) the TIMER MALFUNCTION block (2)
SELECTED c.
(1) rod INSERT blocks (2)
INSERTED d.
(1) rod SELECT blocks (2)
SELECTED ANSWER c.
REFERENCE Lesson plan LIC-0207, page 33 of 46 MEMORY BANK EXPLANATION:
Bypassing the RWM allows inserting CR's. Insertion would otherwise be prevented because of INSERT blocks.
QUESTION 025 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295022K102 QUESTION Unit 1 is starting up following a maintenance outage. At 0730, Reactor pressure is 700 psig when the B CRD pump trips. Charging header pressure drops to 700 psig.
At 0750, while preparations are being made to start the A CRD pump, four accumulator alarms are received.
TWO of the Control Rods with accumulator alarms are at position 48, ONE is at position 24, and ONE is at position 00 What actions are required?
a.
IF the listed conditions still exist at 0810, THEN BYPASS the RWM and INSERT the rods with accumulator alarms to position 00.
b.
IF the listed conditions still exist at 0810, THEN PLACE the Reactor Mode switch in SHUTDOWN.
c.
IMMEDIATELY PLACE Reactor Mode switch in SHUTDOWN.
d.
IMMEDIATELY BYPASS the RWM and INSERT the rods with accumulator alarms to position 00.
ANSWER c.
REFERENCE QCOA 0300-01 HIGHER MODIFIED EXPLANATION:
With reactor pressure <900 psig, charging water pressure <940 psig and accumulator low pressure alarms lit for 2 control rods not at position 00 the correct action is to immediately place the Reactor Mode switch to SHUTDOWN. Bypassing the RWM and inserting the rods with accumulator alarms is not procedurally directed.
QUESTION 026 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 295032A102 QUESTION While executing actions in QGA 100 the US determined that HPCI is needed for core cooling.
Ten seconds after starting, HPCI alarm 901-3 E11, HPCI TURBINE RUPTURE DISC HIGH PRESSURE came in and immediately CLEARED.
Currently the following conditions exist:
HPCI is injecting at 3500 gpm 901-3 C12, HPCI STEAM LINE HIGH DP is LIT 901-3 F12, HPCI PUMP AREA HI TEMP is LIT 901-3 H2, AREA HI TEMP STEAM LEAK DETECTION is LIT HPCI room temperature is 175°F and RISING slowly Which of the following is true concerning HPCI operation and what actions should be taken?
a.
HPCI should have tripped but NOT isolated. Immediately TRIP HPCI and leave the isolation valves OPEN.
b.
HPCI should have isolated. Immediately ISOLATE HPCI.
c.
HPCI piping MAY have ruptured. Let HPCI CONTINUE to inject until visual verification of a leak can be obtained.
d.
HPCI should have isolated. Let HPCI CONTINUE to inject until it is no longer needed for adequate core cooling.
ANSWER b.
REFERENCE QCAN 901(2) C-12 MEMORY NEW EXPLANATION:
The answer is correct because the hi d/p QCAN says verify automatic actions occur (Group IV isolation). The QGAs do not allow bypassing the high D/P isolation.
QUESTION 027 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 500000 2.1.02 QUESTION During the execution of the QGAs the US has ordered the ANSO to vent the containment due to high hydrogen concentrations. The US has stated that it is "OK to exceed release rate limits".
Currently torus level is 25 feet and torus pressure is 27 psig.
Complete the following statement.
The ANSO should FIRST attempt to vent the......
a.
drywell through the hardened vent.
b.
drywell through the reactor building vents.
c.
torus through the reactor building vents.
d.
torus through the hardened vent.
ANSWER d.
REFERENCE QCOP 1600-13 HIGHER NEW EXPLANATION:
With torus level below 30' the torus must be vented. With torus pressure greater than 25 psig the hardened vent is the required flowpath.
QUESTION 028 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 203000K103 QUESTION Unit 1 is operating at 75% reactor power when the jockey fill pump trips and cannot be restarted.
Which of the following is the correct operator action with regards to the Unit 1 RHR system?
a.
Align RHR pump suction to the CCSTs.
b.
Align clean demin to the discharge piping of the jockey fill pump.
c.
Align condensate transfer to the discharge piping of the jockey fill pump.
d.
Perform the vent verification surveillance every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ANSWER c.
REFERENCE QCOP 1400-03, QCAN 901(2)-3 B-15 MEMORY NEW EXPLANATION:
The backup to Jockey fill is condensate transfer.
QUESTION 029 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 205000K201 QUESTION With the U-1 EDG OOS a LOCA and loss of offsite power occurred on Unit 1. The ANSO started and loaded the U-1 SBO to Bus 14-1.
Which RHR pumps are available for shutdown cooling?
a.
All.
b.
A and B only.
c.
None.
d.
C and D only.
ANSWER a.
REFERENCE QOM 1-6500-T04 and T06 HIGHER NEW EXPLANATION:
If all automatic actions occurred the 1/2 EDG would load to Bus 13-1 making A and B available. With the SBO on 14-1 C and D are available.
QUESTION 030 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 206000K302 QUESTION After 320 days of full power operation, Unit 2 scrammed due to a total loss of EHC pressure.
The ANSO started HPCI for pressure control with a flowpath from the CCSTs back to the CCSTs.
While monitoring the ECCS systems the ANSO sees all four RHR pumps and both Core Spray pumps automatically start on a VALID signal.
At the time of the LP ECCS pump start, conditions were as follows:
RPV water level 35" and STEADY RPV pressure 885 psig and LOWERING at 2 psig per minute.
What is the expected RPV pressure response over the next several minutes?
RPV pressure will...
a.
LOWER THEN RAISE until the Turbine Bypass valves OPEN.
b.
CONTINUE TO LOWER at the same rate then rapidly LOWER to approximately 50 psig.
c.
CONTINUE TO LOWER at the same rate.
d.
LOWER THEN RAISE until the relief valves OPEN at their pressure setpoint.
ANSWER d.
REFERENCE QCOP 2300-06 and QCOA 2300-01 HIGHER NEW EXPLANATION:
All low pressure ECCS pumps starting indicates 2.5 psig was reached in the DW. That will cause HPCI to receive an autostart signal. When it does, the test return valves 1-2301-10 and 15 will close and it will line-up and inject and then trip on high level. The initial injection will cause pressure to drop but HPCI will soon trip on high level causing pressure to rise until the relief valves open. TBVs are unavailable due to the loss of EHC. 2.5 psig in the DW alone will not cause an ADS initiation.
QUESTION 031 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 209001K410 QUESTION With the unit operating at full power, what is the sequence required to time the Core Spray injection valves 1-1402-24A(B) and 1-1402-25A(B)?
a.
Close the 1-1402-25, open and close the 1-1402-24 and then open the 1-1402-25.
b.
Close the 1-1402-24, open and close the 1-1402-25 and then open the 1-1402-24.
c.
Close and open the 1-1402-24 then open and close the 1-1402-25.
d.
Close and open the 1-1402-25 then open and close the 1-1402-24.
ANSWER b.
REFERENCE QCOS 1400-02 MEMORY NEW EXPLANATION:
An interlock prevents the 24 and 25 from being open at the same time when Rx pressure is >325#. Normally the 24 is open and the 25 is closed.
QUESTION 032 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 211000K503 QUESTION Unit 1 was operating at full power when the Main Turbine tripped. When the reactor scrammed several rods failed to insert.
Under which of the following instances will the reactor stay shutdown under ALL conditions?
a.
Two control rods at position 06 and one at position 48 with no Boron injected.
b.
12 control rods at position 06 and the SBLC tank level has dropped from 89% to 60%.
c.
Two control rods at position 48 with the IRMs on Range 7 and no Boron injected.
d.
12 control rods at position 48 and the SBLC tank level has dropped from 89% to 32%.
ANSWER d.
REFERENCE EPG B-6-49 QGA 101 HIGHER NEW EXPLANATION:
The reactor will stay shutdown if all rods are inserted to position 04 or further, One rod at position 48, or the CSBW injected (55% tank level change). SDM is not identified as such in the QGAs but requires knowledge of the EPGs.
QUESTION 033 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 212000K602 QUESTION Which of the following would be a possible impact of APRM #4 indicating lower than actual reactor power?
a.
RBM #7 may enforce rod blocks EARLIER than required.
b.
RBM #8 may enforce rod blocks EARLIER than required.
c.
APRM #4 High High may send trips to RPS EARLIER than required.
d.
OPRM #4 and #6 may NOT send trips to RPS when required.
ANSWER d.
REFERENCE Lesson plan LIC-0756 page 4 of 24 MEMORY NEW EXPLANATION:
An APRM indicating lower than actual will cause a portion of the OPRM system to enable at a higher power level than required. APRM #4 indicating lower than actual will cause RBM #8 to enforce rod blocks at a power level higher than required. An APRM indicating lower than actual will cause the APRM hi-hi scram to come in at a power level higher than required.
QUESTION 034 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 215003A103 QUESTION Which of the following would cause a 1/2 or Full Reactor Scram?
a.
The IRM #18 Mode Selector Switch in STANDBY with the Reactor Mode Switch in STARTUP/HOT STANDBY.
b.
The C Inboard and Outboard MSIVs FULL CLOSED with Reactor power at 23%.
c.
Turbine Stop Valves #1 and #2 FULL CLOSED with Reactor power at 23%.
d.
SRM #21 High-High with the reactor Mode Switch in STARTUP/HOT STANDBY and all 4 shorting links INSTALLED.
ANSWER a.
REFERENCE QCAN 901(2)-5 C-15 MEMORY NEW EXPLANATION:
The IRM mode switch not in operate with the reactor mode switch not in run causes a 1/2 scram. TSV is bypassed below 38.5% power SRM hi-hi trips are bypassed by the installation of the shorting links 1 isolated MSL will not cause a 1/2 or full scram
QUESTION 035 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 215004.A2 03 QUESTION Unit 2 is shutting down for a refueling outage. When the SRMs were inserted, the OUT light for SRM 22 position extinguished but the IN light never lit. The bulbs were replaced with no change in indication. The IN lights for all other SRMs are lit.
Predict the impact, if any, given indications will have on the refueling and, if there is an impact, state what must be done to correct it.
a.
The refueling MAY continue but fuel CANNOT be moved in the associated quadrant. Prevent fuel moves in the associated quadrant until SRM 22 is within Tech Spec limits.
b.
The refueling CANNOT continue since no fuel moves are allowed. Prevent fuel moves until the SRM LCO is satisfied.
c.
The refueling MAY continue and fuel moves MAY be performed in all quadrants because the remaining SRMs satisfy the SRM LCO.
d.
The refueling MAY continue and fuel moves MAY be performed in all quadrants since SRM 22 satisfies its LCO requirements.
ANSWER a.
REFERENCE TS 3.3.1.2, QCFHP 0100-01 HIGHER NEW EXPLANATION:
With SRM 22 not full in the core, the SRM LCO is not satisfied. Core alterations are not allowed for a quadrant unless there is an operable SRM located in the quadrant.
QUESTION 036 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 215005A302 QUESTION The Unit 2 NSO receives an LPRM High alarm. When the condition clears, how is the indication cleared at:
(1) full core display?
(2) 902-37 panel?
a.
(1) automatically (2) automatically b.
(1) automatically (2) manually c.
(1) manually (2) automatically d.
(1) manually (2) manually ANSWER b.
REFERENCE Lesson plan LIC-0703 p.14 of 64 MEMORY NEW EXPLANATION:
The annunciator and high light on the full core display will reset automatically. The back panel indication must be reset with a pushbutton.
QUESTION 037 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 217000A103 QUESTION Given:
A Group I isolation and reactor scram has occurred RCIC was manually started and is injecting at 400 gpm No other high pressure injection is available ADS has been inhibited The ANSO is cycling ADS valves to maintain reactor pressure 800-1000 psig Reactor vessel level is 38" and rising at 1" per minute With no additional operator action, predict the response of reactor water level.
Reactor water level will...
a.
continue to rise to the height of the main steam lines.
b.
rise to 48" then drop until recovered by low pressure ECCS systems.
c.
rise to 48", drop to 44" and then rise.
d.
rise to 48", drop to -59" and then rise.
ANSWER d.
REFERENCE QCOA 1300-01 MEMORY NEW EXPLANATION:
RCIC will trip at 48" then automatically restart and inject at -59"
QUESTION 038 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 217000A407 QUESTION Unit 2 has experienced a transient. The ANSO is controlling pressure with relief valves. While monitoring PI 2-1340-6, TURBINE INLT PRESS, the ANSO notes that the indication is 700 psig and LOWERING at 2 psig per minute. When the ANSO opens a relief valve the rate of pressure decrease on the PI 2-1340-6 TURBINE INLT PRESS does NOT change.
Which one of the following could be the cause for the pressure indication?
a.
Inboard MSIVs being CLOSED b.
The RCIC turbine running c.
RCIC turbine exhaust pressure of 30 psig d.
RCIC room temperature of 180°F ANSWER d.
REFERENCE M-50 sheet 1, QCOA 1300-01, QCOP 1300-02 HIGHER NEW EXPLANATION:
170 deg F in the RCIC room will isolate the steam line thus isolating the pressure indication. 30 psig RCIC turbine exhaust pressure will trip but not isolate RCIC. RCIC steam line taps off before the inboard MSIVs.
RCIC turbine operation will not cause turbine inlet pressure to continue to drop.
QUESTION 039 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 218000 2.1.28 QUESTION The 1-203-3B, ADS RELIEF VALVE, Keylock Switch is in OFF.
Predict how the 1-203-3B valve will respond to reactor pressure rising to 1125.
The 1-203-3B will...
a.
remain CLOSED.
b.
OPEN then CLOSE at approximately 60 psig.
c.
OPEN then CLOSE at approximately 940 psig.
d.
OPEN then CLOSE at approximately 1070 psig.
ANSWER a.
REFERENCE LIC-0203, QCOP 0203-01 MEMORY NEW EXPLANATION:
With the keylock switch in off for the ADS valves they will not function as relief valves. The valve will remain closed. If the switch were in Auto the valve would open then close at approximately 1070 psig. 940 psig is the number listed in the QGAs to lower reactor pressure to if ADS valves are cycling. Valves remain open until approximately 60 psig on an ADS actuation.
QUESTION 040 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 223002K113 QUESTION Unit 1 is operating at 100% power with TIP machine B inserting into the core in preparation for a scan when a reactor scram occurs. Reactor water level drops to -10". Ten seconds later, Reactor water level is 0" and RISING.
What is the response of the TIP system to the level transient?
a.
The TIP Shear Valve fires, cutting the detector cable and sealing the TIP tubing.
b.
The TIP detector is withdrawn to the in-shield position and the TIP Ball Valve closes.
c.
The TIP will continue to insert and perform its trace.
d.
The TIP detector is withdrawn until Reactor water level rises above 0", it then re-inserts.
ANSWER b.
REFERENCE QCAP 0200-10 Att D MEMORY NEW EXPLANATION:
A group II isolation signal (0") shifts the TIPs into reverse withdrawing them back in shield and closing their ball valves. The signal seals in and does not reset when level is recovered. Shear valves are not automatic actuating.
QUESTION 41 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 239002K201 QUESTION A TOTAL loss of 125VDC has occurred on UNIT 2.
What is the effect on the UNIT 1 ADS valve solenoids?
a.
The normal power supply is UNAVAILABLE but the reserve is AVAILABLE.
b.
Both the normal and reserve power supplies are AVAILABLE.
c.
Both the normal and reserve power supplies are UNAVAILABLE.
d.
The normal power supply is AVAILABLE but the reserve is UNAVAILABLE.
ANSWER d.
REFERENCE QOM 1-6300-T06 and QOM 1-6900-03 MEMORY NEW EXPLANATION:
The normal power supply is from the Unit 1 125vdc RB panel and the reserve is from 125vdc TB Bus 1B-1 which is fed from the Unit 2 DC system.
QUESTION 042 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 239002A307 QUESTION The Unit 1 NSO is monitoring RPV water level after a Group I isolation occurred from full reactor power.
Several minutes after the Group I, indicated RPV water level rises 12" for several seconds then returns to a level slightly lower than before.
What could have caused the indicated level transient?
a.
Reference leg FLASHING b.
Reference leg NOTCHING c.
One or more ADS valves OPENING then CLOSING on their pressure setpoint d.
One or more Turbine Bypass valves OPENING then CLOSING due to pressure set ANSWER c.
REFERENCE QCOP 0201-11 and 12, lesson plan L-QGA100 p. 57 MEMORY NEW EXPLANATION:
ADS valve opening will cause an increase in indicated level due to increased voiding. When the valves close the voids collapse and level will be lower due to the inventory loss. Reference leg flashing will cause indicated level to rise but it will not return to normal. Notching is indicated by an indicated level increase of at least 9" that does not return to normal for at least 5 minutes. The Group I isolation will prevent the turbine bypass valves from opening.
QUESTION 043 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 259002K307 QUESTION Unit 1 is at full power with FWLC in 3-element with a setpoint of 30" when the B RFP flow transmitter signal drops by 2 Mlbm/hr over 3 minutes.
How will RPV water level respond over the next 5 minutes?
a.
Drop to the low level reactor scram setpoint.
b.
Rise until the RFPs trip.
c.
Rise then return to 30".
d.
Drop and then return to 30".
ANSWER c.
REFERENCE Lesson plan LIC-0600 ppg 76, 77 HIGHER NEW EXPLANATION:
DFWLC is a level dominant system. Initially the system will see an underfeed condition and open FRVs to correct it. After a time the level dominance will take over and return level to 30".
QUESTION 044 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 261000K402 QUESTION Two hours ago a LOCA occurred on Unit 1. The US has ordered the ANSO to swap SBGT trains. When the trains were swapped the 1/2 7504B TURB BLDG CLG AIR DMPR did NOT reposition.
Which of the following describes the adverse effect of this failure?
a.
Excess flow through the A train may result in damage to internal components.
b.
Inadequate flow through the B train may result in the release of radioactive iodine.
c.
Excess flow through the B train may result in damage to internal components.
d.
Inadequate flow through the A train may result in the release of radioactive iodine.
ANSWER b.
REFERENCE Lesson plan LF-7500 HIGHER NEW EXPLANATION:
Initially the B train will autostart. Swapping trains will put A on and secure B. The cooling damper allows backflow through the off line charcoal adsorber to remove decay heat and prevent a release of radioactive iodine. Overall flow will not change through the trains.
QUESTION 045 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 262001.K5.01 QUESTION When paralleling the main generator to the grid QCGP 1-1 tells the operator to adjust the voltage regulator 'to bring incoming volts slightly higher than running volts'.
Why is that done and when should the voltage be compared?
To ensure the main generator picks up...
a.
VARS. It is compared when the synchroscope is at the 12 o'clock position.
b.
MWe. It is compared when the synchroscope is at the 12 o'clock position.
c.
MWe. It can be compared regardless of synchroscope position.
d.
VARS. It can be compared regardless of synchroscope position.
ANSWER a.
REFERENCE Lesson plan BWR/Components/Chapter 5 and QCGP 1-1 page 77 MEMORY NEW EXPLANATION:
If incoming volts are higher than running reactive load (VARS) will be picked up upon synchronization. Real load (MWe) is picked up by ensuring the synchroscope is running in the fast direction. Voltages can only be checked when the two power supplies are in synch.
QUESTION 046 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 262001A209 QUESTION Given:
Unit 1 scrammed due to receipt of a LOCA signal Alarm 901-8 G12 4KV BUS 14-1 VOLTAGE DEGRADED is LIT NO other unexpected alarms are lit Bus 14-1 voltage is 3890VAC Bus 14 to Bus 14-1 current is 300 amps Predict the impact of the above conditions and state what actions should be taken to correct them.
a.
Bus 14-1 should have tripped on overcurrent. IMMEDIATELY OPEN the Bus 14 to Bus 14-1 crosstie breaker and VERIFY the EDG starts, but does NOT load.
b.
In five minutes, Bus 14-1 will load shed and the Unit 1 EDG will autostart.
Transfer Bus 14 back to T-11. If voltage CANNOT be restored verify after 5 minutes, VERIFY Bus 14-1 load sheds and the U1EDG starts and loads.
c.
Bus 14-1 should have tripped on undervoltage. IMMEDIATELY OPEN the Bus 14 to Bus 14-1 crosstie breaker and verify the EDG starts and loads.
d.
In five minutes, Bus 14-1 will load shed and the Unit 1 EDG will autostart.
IMMEDIATELY OPEN the Bus 14 to Bus 14-1 crosstie breaker and VERIFY the EDG starts AND loads.
ANSWER c.
REFERENCE TS 3.3.8.1, QCOA 6500-13, QOA 900-8 G-12 HIGHER NEW EXPLANATION:
The bus has reached its second level undervoltage setpoint. If no LOCA signal is present the bus will trip after a 5 minute time delay. With a LOCA signal present the 5 minute timer is bypassed and the Bus should trip immediately. The absence of any additional unexpected alarms indicates the Bus should not have tripped on overcurrent.
QUESTION 047 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 262002K603 QUESTION If the Unit 1 ESS inverter would fail what would be supplying power to the ESS Bus?
a.
Bus 18 b.
Bus 26 c.
Bus 17 d.
MCC 18-2 ANSWER c.
REFERENCE MEMORY NEW EXPLANATION:
Both the 250vdc and Bus 18 power supplies comes through the inverter.
If it would fail the static switch would swap to Bus 17 for Unit 1 (Bus 26 for Unit 2). If the static switch fails MCC 18-2 would supply power.
QUESTION 048 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 263000A101 QUESTION Unit 1 was operating at full power when a loss of offsite power occurred. Current conditions are as follows:
RPV water level is 25" and STEADY DW pressure is 4 psig and STEADY HPCI was trip-latched when DW pressure was 1.7 psig and RISING RCIC running and injecting Which one of the loads listed below will have the greatest impact on the discharge rate of the Unit 1 Safety Related 250VDC battery?
a.
Main Turbine Emergency Bearing Oil pump b.
HPCI Emergency Oil pump c.
HPCI Auxiliary Oil pump d.
RCIC Barometric Condenser Condensate pump ANSWER c.
REFERENCE QOM 1-6300-T08, QCOA 2300-01 HIGHER NEW EXPLANATION:
At 2.5 psig in the DW, HPCI will receive an autostart signal causing the the HPCI aux oil pump to start. It is a large load off the DIv I (Unit 1) essential battery. The HPCI EBOP is a large load on the battery but will not be running. If HPCI had been allowed to autostart before it was trip-latched the EBOP would be running. The main turbine EBOP will be running but is a load on the NON-essential 250VDC battery. The RCIC barometric condenser condensate pump will be running but is a load on the DIV II (Unit 2) battery.
QUESTION 049 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 264000K601 QUESTION Unit 1 is operating at full power when the B Starting Air Receiver for the Unit 1 EDG ruptures.
How will the EDG start capabilities be impacted by this failure?
If a start signal is received, the EDG will...
a.
start in the required time frame.
b.
NOT receive any starting air.
c.
receive starting air but the EDG start time will be longer than required.
d.
receive starting air but it will be insufficient to start the EDG.
ANSWER a.
REFERENCE UFSAR 9.5.6 MEMORY NEW EXPLANATION:
A rupture of 1 of the 4 receivers will cause two of them to depressurize.
A check valve is designed to keep the other 2 at pressure. One pair will start the EDG in its required time.
QUESTION 050 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 264000A205 QUESTION You are the NSO performing QCOS 6600-42, Unit 2 Diesel Generator Load Test. The EDG is running loaded in parallel with the normal feed when the normal feed breaker opens.
Predict the impact of this transient and state what actions must be done to correct the situation.
a.
EDG load will potentially exceed the limit due to the speed droop setting. Slowly adjust the speed droop to zero while monitoring EDG loading.
b.
The LOCA load shed will NOT occur potentially overloading the EDG. Manually trip all nonessential loads, place the speed droop to zero and allow the EDG to remain loaded.
c.
The undervoltage load shed will NOT occur potentially overloading the EDG.
Place the EDG output breaker in PTL, set the speed droop to zero, adjust EDG frequency and voltage then place the EDG output breaker to AUTO.
d.
EDG load will be reduced potentially causing it to overspeed. Using the governor control switch lower load to 900 kw.
ANSWER c.
REFERENCE HIGHER NEW EXPLANATION:
During times when the EDG is in parallel with normal feed if the normal feed breaker trips the EDG may become overloaded due to the absence of the undervoltage load shed. The operator forces the load shed by opening the output breaker and setting the controls to a standby condition. While the potential exists for overspeed no direction is given to reduce load on the EDG. ECCS pump will not autostart on an undervoltage condition.
QUESTION 051 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 300000 2.1.27 QUESTION Which of the following is a use for the Instrument Air system?
a.
To sparge the SBLC tank before sample b.
As breathing air c.
A backup to Drywell Pneumatics with the DW deinerted d.
To purge the offgas piping after a unit scram ANSWER c.
REFERENCE QCOP 1600-08 MEMORY NEW EXPLANATION:
During times when the drywell is deinerted, instrument air is valved in to backup the drywell pneumatics system. Sparge air is used to purge the offgas piping. Service air is used to sparge SBLC and as breathing air.
QUESTION 052 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 400000A401 QUESTION Given:
RBCCW pumps 1A and 1/2C were running 1/2C was being fed from Bus 29 Unit 1 received an ECCS signal from high drywell pressure The US has directed you to start the previously running RBCCW pumps.
What must you do to start the pumps?
a.
Bypass the LOCA signal and verify the 1A RBCCW pump restarts. The 1/2C RBCCW pump is still running.
b.
Bypass the LOCA signal and manually restart the 1A RBCCW pump. The 1/2C RBCCW pump is still running.
c.
Bypass the LOCA signal and manually restart both the 1A and 1/2C RBCCW pumps.
d.
Manually restart both the 1A and 1/2C RBCCW pumps.
ANSWER b.
REFERENCE Lesson plan LF-3700 page 15 HIGHER MODIFIED EXPLANATION:
The 1A and B RBCCW pumps load shed on a LOCA signal and must be manually restarted when the signal is clear or bypassed. The 1/2C load sheds on when the Unit feeding it experiences a LOCA signal, in this case Unit 2.
QUESTION 053 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.2.22 QUESTION Given:
Unit 1 is at eight percent reactor power with the Rx Mode Switch in STARTUP/HOT STANDBY Unit 2 has all rods in with the RX Mode Switch in SHUTDOWN Both Units are at 880 psig reactor pressure Bus 31 is DEENERGIZED and CANNOT be reenergized With regards to the SSMP system, the LCO is met on...
a.
Unit 1 only.
b.
both units.
c.
Unit 2 only.
d.
neither unit.
ANSWER d.
REFERENCE TS 3.7.9 HIGHER NEW EXPLANATION:
SSMP is required in Mode 1 and Modes 2 and 3 with steam dome pressure above 150 psig. In the question Unit 1 is in Mode 2 and Unit 2 is in Mode 3. Both Units require SSMP to be operable so neither meet the LCO.
COMMENT:
No KA exists for the SSMP system. System was added to random selection process, following discussion with lead examiner, in accordance with per ES 401-1, note 3. Generic K/A 2.2.22, Knowledge of limiting conditions for operations and safety limits. Proposed worth: RO: 3.4, SRO: 4.1
QUESTION 054 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 201002K601 QUESTION Unit 2 is operating at 50% reactor power when a total loss of ESS occurs. An NLO reports the ESS Bus is damaged and CANNOT be re-energized. Subsequently the STA reports the Unit is operating in ICA Region II.
Which of the following is the appropriate response?
a.
Select and insert the CRAM rods using Emergency Rod In since the Rod Movement Control Switch has no power.
b.
Insert a manual scram since control rods CANNOT be selected.
c.
Select and insert the CRAM rods using the Rod Movement Control Switch since the RMCS is NOT affected.
d.
Insert a manual scram since the Rod Motion Control Timer has no power.
ANSWER b.
REFERENCE QCOA 6800-03, QCOA 0280-01 HIGHER NEW EXPLANATION:
With a loss of ESS the rod select matrix has no power so control rods cannot be selected for movement and RPIS is lost. Per QCOA 0280-01, if RPIS is lost and control rod insertion is required, a manual scram must be inserted.
QUESTION 055 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 201003.A1.03 QUESTION With Unit 1 at full power the NSO selects a control rod for withdrawal. The move is from position 12 to position 24.
The NSO positions the Rod Out Notch Override switch to NOTCH OVERRIDE and the Rod Motion Control switch to ROD OUT. When the control rod reaches position 21, the NSO releases both switches.
What is the expected CRD Drive Water Flow response from the time the switches are initially moved until they are released?
The drive water flow will go from 0 gpm to...
a.
4 gpm to 0 gpm.
b.
4 gpm to 2 gpm to 0 gpm.
c.
2 gpm to 4 gpm to 0 gpm.
d.
2 gpm to 0 gpm.
ANSWER 2546 5(14 19)>
b.
REFERENCE Lesson plan LF-0302 HIGHER NEW EXPLANATION:
2 gpm is required to withdraw a control rod and 4 gpm is required to insert a control rod. During a withdraw signal the control rod receives an insert signal first to release the collet fingers then a withdraw signal.
QUESTION 056 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 201006A405 QUESTION Given:
A Unit 1 reactor startup is in progress.
The NSO just completed rod step 22.
You are asked to verify rod step 22 is at target out.
You note that on the RWM rod G-9 is RED in color and indicates position 32.
Why is the control rod position indication red and can the rod be moved with the RMCS?
Control rod G-9 has...
a.
a substitute position entered and CANNOT be inserted OR withdrawn.
b.
been withdrawn past its target out position and can be inserted ONLY.
c.
been selected out of sequence and CANNOT be inserted OR withdrawn.
d.
been taken OOS and can be inserted ONLY.
ANSWER b.
REFERENCE Lesson plan LIC-0207 MEMORY BANK EXPLANATION:
A red position on the RWM indicates a rod withdrawn past its target out position. The rod can only be inserted to correct the mispositioning.
Substitute positions are yellow, OOS rods are light blue, rods selected out of sequence are white.
QUESTION 057 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 204000K103 QUESTION Unit 1 was operating at full power when DW pressure began to rise requiring a manual scram.
After the reactor scram the RWCU system isolated. The crew has determined that the DW pressure rise was caused by a leak in the A feedwater header. The MO 1-3205A, 1A RX FW INLT VLV, was CLOSED and DW pressure STOPPED rising.
The following lists the current conditions:
RBCCW and DW coolers are running DW pressure is 2.8 psig and lowering slowly Reactor pressure is 825 psig and steady Reactor water level is 30" and steady If the ISOL VLV RESET switch on the 901-5 panel is taken to INBD and OUTBD can the RWCU system be restarted? If yes, what will be the effect? If no, why not?
a.
Yes, DW pressure will rise.
b.
Yes, there will be excessive thermal stress to the B FW piping.
c.
No, adequate flow cannot be obtained due to the MO 1-3205A being closed.
d.
No, a Group III isolation signal is still present.
ANSWER a.
REFERENCE M-15 sheet 1, M-47 sheet 1, M-50 sheet 1 HIGHER NEW EXPLANATION:
The RWCU system discharges into the A FW header. The indications given lead the operator to the fact that A FW header is ruptured inside the drywell between the wall and the check valve upstream of the vessel.
Starting the system would pump reactor water into the vessel through the leak. RWCU ties into the RCIC discharge piping and then to A FW header. No isolation signal still exists. The discharge of RWCU enters downstream of the 3205A
QUESTION 058 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 215002A202 QUESTION Unit 2 is operating at 80% power. The Unit 2 NSO is withdrawing control rods during a reactor startup when the signal from flow converter #1 is lost to the RBM system ONLY.
Predict the effect of this failure and state the actions that must be taken to continue control rod withdrawal?
a.
RBM #7 trip setpoints are NON-CONSERVATIVE. Bypass RBM #7.
b.
RBM #7 trip setpoints are CONSERVATIVE. Bypass RBM #7.
c.
RBM #8 trip setpoints are NON-CONSERVATIVE. Bypass RBM #8.
d.
RBM #8 trip setpoints are CONSERVATIVE. Bypass RBM #8.
ANSWER b.
REFERENCE QCAN 901(2)-5 A-7 HIGHER NEW EXPLANATION:
With a flow signal of 0 from FC #1 to the RBM system, RBM #7 trip setpoint will be set conservative causing a rod out block. RBM 8 will be unaffected. If the flow converter failed high, the trip setpoints would be non-conservative and no rod out block would occur.
QUESTION 059 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 219000K109 QUESTION Given:
Unit 1 has experienced a transient requiring entry into QGA 500-1 Torus water temperature is 103°F and RISING at 1°F every 10 minutes Reactor pressure is 14 psig and LOWERING at 1 psig per minute Drywell temperature is 290°F and RISING at 5°F per minute Drywell and torus pressures are 6 psig and rising at 1 psig every 10 minutes Flow on B loop of RHR is SPLIT between torus cooling and drywell sprays Flow on A loop of RHR is injecting into the vessel The 1-1001-19B, RHR XTIE, valve is closed RPV level is -120" and RISING at 1" per minute Which of the following effects could happen sooner if torus cooling flow was RAISED on B loop of RHR?
a.
The drywell may exceed its design pressure.
b.
The reactor core may become uncovered.
c.
Reactor water level instruments may become unavailable.
d.
Torus pressure may go negative cycling the DW to Torus vacuum breakers.
ANSWER c.
REFERENCE M-39 sheet 1 HIGHER NEW EXPLANATION:
Raising torus cooling flow will lower drywell spray flow which will raise the rate of increase for DW temp and may cause reference leg flashing. With the vessel depressurized the containment will not exceed its design pressure. With the 1001-19B closed injection rate into the vessel will not change. Lowering torus temperature will not cycle DW to torus vacuum breakers.
QUESTION 060 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 234000 2.1.28 QUESTION The Unit 1 refueling platform is traveling in the reverse direction over the Unit 1 reactor core with the main hoist loaded. The Reactor Mode Switch is in REFUEL.
What limitations would there be on the refueling platform if the Refueling Interlock Check pushbutton in the Aux Electric Room was depressed?
Bridge reverse motion would be...
a.
STOPPED and the main hoist CAN be lowered.
b.
STOPPED and the main hoist CANNOT be lowered.
c.
ALLOWED and the main hoist CANNOT be lowered.
d.
ALLOWED and the main hoist CAN be lowered.
ANSWER b.
REFERENCE QCFHP 0100-03 HIGHER BANK EXPLANATION:
With the U1 bridge near or over the U1 core and the main hoist loaded, a rod being withdrawn (or in this case simulated to be withdrawn) causes a reverse motion block and prevents the main hoist from being lowered.
Forward motion is allowed to clear the interlock. If the U1 bridge is near or over the U2 core forward motion is prevented but reverse motion is allowed.
QUESTION 061 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 241000A302 QUESTION A startup is in progress on Unit 2. The ANSO preparing to roll the main turbine has determined that a MEDIUM startup rate is appropriate. The ANSO depresses the MEDIUM pushbutton at the EHC panel at 0407 and verifies the turbine begins accelerating.
Which of the following would indicate the turbine is accelerating at the proper rate?
a.
360 rpm at 0413 b.
450 rpm at 0412 c.
480 rpm at 0411 d.
540 rpm at 0410 ANSWER b.
REFERENCE QCGP 1-1 page 72 HIGHER NEW EXPLANATION:
A medium startup rate is 90 rpm/minute.
QUESTION 062 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 245000.K4.03 QUESTION Unit 2 is operating at full power with all generator parameters normal.
How will the loss of BOTH the Main Seal Oil and Emergency Seal Oil pumps affect main generator casing pressure?
Main generator casing pressure will...
a.
<NOT change because the combination of the generator mechanical seals and oil remaining in the seals will prevent leakage.
b.
NOT change because the Steam Seal System is still in service.
c.
DECREASE due to leakage past the seals and stabilize near turbine bearing oil pressure.
d.
DECREASE to atmospheric pressure due to the loss of all seal oil flow.
ANSWER c.
REFERENCE Lesson plan LIC-5300 page 41 of 49 HIGHER NEW EXPLANATION:
On a loss of both the main and emergency seal oil pumps the turbine bearing oil header will supply seal oil (approximately 25 psig). The mechanical seals and residual oil will not prevent all leakage. All seal oil flow is not lost oils comes from the turbine oil system. The steam seal system is for turbine seals not generator seals.
QUESTION 063 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 272000K201 QUESTION Unit 2 is operating at 100% reactor power when the B Main Steam Line radiation monitor loses power.
Which of the following power supplies has been lost.
a.
RPS A b.
RPS B c.
ESS d.
Instrument Bus ANSWER c.
REFERENCE QOA 7000-01 MEMORY NEW EXPLANATION:
The A and C main steam line rad monitors are fed from RPS A. B and D are fed from ESS.
QUESTION 064 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 290001K301 QUESTION The plant was operating at 75% power when a transient occurred resulting in an elevated fission product release. The following conditions exist:
The 1-1735A, RX BLDG VENT CH A, high light is LIT The 1-1735B, RX BLDG VENT CH B, high light is EXTINGUISHED The ANSO checks the status of the RB vents and finds the vent fans running and the isolation dampers open with 1/2 B SBGT train running.
Considering only the above conditions what, if anything, should be done and why?
a.
STOP the 1/2 B SBGT train because running it in conjunction with the RB vents may cause damage to the train.
b.
TRIP the RB supply and exhaust fans and CLOSE the isolation dampers to prevent an unfiltered release of radioactive particles.
c.
Leave both systems RUNNING to ensure the Secondary Containment pressure remains negative.
d.
TRIP the RB supply and exhaust fans and leave the isolation dampers OPEN to ensure all effluent is processed through SBGT.
ANSWER b.
REFERENCE QCAN 901-3 G3 and lesson plan LNF-5750 page 22 of 108 HIGHER MODIFIED EXPLANATION:
A high light on the RB vent rad monitor indicates the setpoint for the RB vent isolation and SBGT autostart has been reached. The operators are trained on a setpoint in mr/hr vs. light indication. Either A or B being high or both being low will cause a full isolation (fans tripped isolation dampers closed)
QUESTION 065 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 290002K505 QUESTION Unit 2 is in an outage performing the Vessel In-Service Leak Test after 22 EFPY of operation.
The following lists SOME of the parameters recorded during the test:
Time Rx Pressure Rx Metal Temp 1200 600 psig 150 degrees°F 1230 800 psig 140 degrees°F 1300 1025 psig 140 degrees°F 1330 1025 psig 135 degrees°F 1400 1025 psig 135 degrees°F 1430 1025 psig 130 degrees°F 1500 1025 psig 130 degrees°F Which one of the following statements is correct concerning the Reactor Coolant System?
a.
RPV pressure vs. temperature limits have been violated and the reactor requires pressure reduction immediately.
b.
RPV pressure vs. temperature limits have been violated and the reactor requires pressure reduction within 30 minutes.
c.
RPV pressure vs. temperature limits are within specifications.
d.
RPV pressure vs. temperature limits are satisfied but the reactor requires heatup to complete the test.
ANSWER a.
REFERENCE QCOS 0201-08, TS 3.4.9 QCOS 0201-08 attachment B provided HIGHER BANK EXPLANATION:
Per QCOS 0201-08 Attachment B the pressure vs. temperature curve has been violated. Per TS 3.4.9, with the reactor in a Mode other than 1, 2 or 3, immediate action must be taken to restore parameters within limits.
QUESTION 066 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.1.11 QUESTION Which of the following conditions require Tech Spec actions to be taken in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less?
a.
One inservice RPS EPA inoperable.
b.
Reactor steam dome pressure of 1006 psig.
c.
Reactor vessel water level of -140".
d.
Shutdown Margin NOT within limits in Mode 2.
ANSWER b.
REFERENCE TS 3.4.10 MEMORY NEW EXPLANATION:
Steam dome pressure high requires action within 15 minutes. Reactor vessel level low requires action in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. 1 inservice EPA inop requires actions in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. 2 would require actions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. SDM not within limits requires actions in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if in Mode 1 or 2, immediately if in Mode 3.
QUESTION 067 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.1.14 QUESTION A faulty card in the digital recirc system caused reactor power to drop by 620 MWth in 1 minute.
Currently reactor power is 36% and core flow is 52 Mlb/hr.
What action is required FIRST?
a.
Immediately scram the reactor.
b.
Initiate an Issue Report.
c.
Notify Chemistry and BPO.
d.
Insert control rods to exit ICA Region II.
ANSWER c.
REFERENCE QCGP 3-1 QCOP 0202-13 Attachment B page 1 of 2 provided HIGHER NEW EXPLANATION:
A load drop of 20% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> requires Chemistry to obtain reactor coolant samples. Misreading the Quad Cities power to flow map would lead the operator to believe an immediate scram or load drop with recircs is required. While an issue report is appropriate, it is not the first thing that should be done.
QUESTION 068 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.2.11 QUESTION Which of the following items requires a 50.59 Screening?
a.
Thermal overloads removed from a breaker that are specified on an OOS.
b.
A tygon hose installed on a water drop to fill a cleaning bucket.
c.
A blocking device installed on a safety valve to prevent inadvertent opening with NO pre-approved procedure.
d.
An electrical jumper placed in a component's start circuit as part of a pre-approved surveillance procedure to prevent inadvertent auto start.
ANSWER c.
REFERENCE CC-AA-103 HIGHER BANK EXPLANATION:
A gagging device on a safety valve will change how the system operates.
If part of an approved procedure the %0.59 evaluation will already be completed.
QUESTION 069 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.2.22 QUESTION Which of the following conditions would indicate a Safety Limit has been violated?
a.
Reactor bottom head pressure of 1350 psig.
b.
Reactor steam dome pressure of 800 psig, core flow at 12% of rated and MCPR of 1.08.
c.
Reactor vessel water level of -135".
d.
Reactor steam dome pressure of 780 psig, core flow at 8% of rated and reactor power of 22%.
ANSWER b.
REFERENCE TS 2.1 Safety Limits MEMORY NEW EXPLANATION:
With pressure >785 and flow >10% the least limiting MCPR value is
>1.09 (Unit 2 with 2 recirc loops in operation). RPV pressure SL is based on Steam Dome pressure not bottom head. RPV level must be above TAF (-142). With steam dome pressure <785 or core flow <10% power must be <25%
QUESTION 070 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.2.24 QUESTION IMD is performing a test of the RPV steam dome pressure switches. Tech Specs allow 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to test each switch.
The following times show the sequence of the testing.
0800, IMD begins testing 0815, the first switch is valved out 0900, testing of the first switch is complete 0920, the second switch is valved out 0945, the second switch exceeds its allowable trip setting 1000, it is determined that the switch needs replacement and all testing is stopped Which of the following identifies the time the LCO should be entered for the second switch?
a.
0920 b.
0945 c.
1000 d.
1520 ANSWER b.
REFERENCE TS LCO 3.0.2 HIGHER BANK EXPLANATION:
The switch must be declared inoperable at the time of discovery that it does not meet the LCO. 0920 corresponds to the time the instrument was valved out 1000 corresponds to when it is determined that the switch cannot be brought within tolerance 1520 corresponds to the time the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowance would runout if the instrument had not been found to be broken.
QUESTION 071 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.3.11 QUESTION Containment hydrogen concentration is 5% and containment oxygen concentration is 4%.
What additional condition is necessary to allow primary containment venting?
a.
Nitrogen purge of the Drywell must be initiated and maximized.
b.
Off-site release rates are expected to stay below Tech Spec LCO limits.
c.
Drywell sprays must be initiated.
d.
Reactor water level must be above the Group II isolation setpoint.
ANSWER b.
REFERENCE QGA 200-5 MEMORY BANK EXPLANATION:
Per QGA 200-5 venting can only be performed with the listed H2 and O2 concentrations until the TS LCO release rate is exceeded. Purge can be started AFTER venting is begun. Drywell sprays are not needed at these concentrations. Group II level isolation is directed to be bypassed by the QGAs.
QUESTION 072 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.3.02 QUESTION Which of the following approaches to performing a job should be used based on ALARA considerations for total collective dose?
a.
Two individuals installing temporary shielding in a 90 mrem/hr field for 20 minutes and then performing the job in a 12 mrem/hr field for 20 minutes.
b.
One individual performing the job in a 90 mrem/hr field for 60 minutes.
c.
Two individuals performing the job in a 90 mrem/hr field for 20 minutes.
d.
One individual installing temporary shielding in a 90 mrem/hr field for 40 minutes and then performing the job in a 12 mrem/hr field for 60 minutes.
ANSWER c.
REFERENCE RP-AA-400 HIGHER MODIFIED EXPLANATION:
The lowest combined dose would be 2 people doing the job for 20 minutes.
QUESTION 073 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.3.10 QUESTION Unit 1 is holding load at 100% power.
Offgas radiation has risen to the point that alarm 901-3 C2, OFF GAS HIGH HIGH RADIATION has come in for both channels.
If offgas radiation levels continue to rise what action(s) should be taken?
a.
Hold reactor power constant until the cause of the elevated radiation readings can be determined.
b.
Perform an emergency load drop to within the capacity of the turbine bypass valves and trip the main turbine.
c.
Depress the OFF GAS TRIP LOGIC RESET and verify one light on at the OFF GAS RELAY TEST JACK.
d.
Isolate the offgas system, scram the reactor and close the MSIVs.
ANSWER d.
REFERENCE QCOA 1700-04 MEMORY NEW EXPLANATION:
Offgas hi-hi rads will isolate the offgas system. Procedurally the operator must scram and isolate the offgas system and MSIVs. Holding power constant is correct until offgas hi-hi rads comes in. A rapid load drop can worsen the high radiation and tripping the turbine will not reduce offgas rads. The operator is directed to reset the 15 minute timer only if the hi-hi rad alarm was due to a spike.
QUESTION 074 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.4.8 QUESTION Unit 1 was operating at 80% power when T-12 tripped. The crew entered and is carrying out the actions of QOA 6100-01, Loss of Transformer 12 During Power Operation. Several minutes later the reactor scrammed due to a spurious Group I isolation and the crew entered QCGP 2-3 Reactor Scram.
The following conditions exist:
Reactor water level is being maintained between 0" and 48" with HPCI.
A cooldown is in progress with ADS valves, reactor pressure is 825 psig.
Torus temperature is 97°F and rising.
Neither EDG started automatically or manually.
No other actions have been taken to restore electrical power.
Which of the following actions are required?
a.
Exit QOA 6100-01, continue with the actions of QCGP 2-3 and enter QGA 200 Secondary Containment Control. Do NOT enter any other Q(C)OAs.
b.
Continue with the actions of QOA 6100-01 and QCGP 2-3 and enter QGA 200 Secondary Containment Control and QCOA 6100-04 Station Blackout.
c.
Exit QOA 6100-01 and QCGP 2-3 and enter QGA 200 Secondary Containment Control. Do NOT enter any other Q(C)OAs.
d.
Continue with the actions of QOA 6100-01 and QCGP 2-3 and enter QGA 200 Secondary Containment Control and QCOA 6100-03 Loss of Offsite Power.
ANSWER d.
REFERENCE Lesson Plan L-QGAINT, QCOA 6100-03 HIGHER NEW EXPLANATION:
QCGPs QOAs and QGAs may all be performed concurrently. After the scram QCOA 6100-03 should be performed in conjunction with QOA 6100- 1. Higher order due to the need to evaluate blackout status. Unit is not blacked out because the 4kv crossties have not been attempted.
QGA 200 is entered on 95 deg in the torus.
QUESTION 075 EXAM DATE 2005/05/02 FACILITY 254 - QUAD CITIES STATION REACTOR TYPE BWR-GE3 EXAM LEVEL R
K/A 2.4.24 QUESTION Unit 2 was operating at 75% power when a complete loss of TBCCW occurred.
When the RO inserted a manual scram, 38 control rods did NOT insert.
Given the above conditions, which of the following lists loads that should be secured at this time?
a.
EHC pumps, Circulating Water pumps and CRD pumps b.
Reactor Feedwater pumps, Condensate pumps and Sparge Air compressors c.
Reactor Feedwater pumps, EHC pumps and Circulating Water pumps d.
Condensate pumps, Sparge Air compressors and CRD pumps ANSWER c.
REFERENCE QCOA 3800-03 MEMORY NEW EXPLANATION:
QCOA 3800-03 directs tripping the RFPs, EHC and Circulating water pumps. It does not direct tripping the CRD pumps if all control rods are not at position 00. Sparge air compressors are shared pieces of equipment but receive cooling water from Unit 1.