ML111090206
| ML111090206 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  (DPR-067, NPF-016) |
| Issue date: | 04/18/2011 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| 50-335-/11-301, 50-389/11-301 | |
| Download: ML111090206 (83) | |
Text
Site-Specific RO Written Examination Applicant Information Name:
Date: 3/17/11 Facility/Unit: St. Lucie Plant Region:
I LI II III El IV El Reactor Type: W El CE BW [I GE El Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own.
I have neither given nor received aid.
Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent
ROl Unit 1 is performing a startup with the following:
Reactor power is 17%
Main Generator output is 60 Mwe The running DEH pump trips and the standby pump started when DEH header pressure indicated 900 psia.
Which ONE of the following states the expected plant indication?
A.
Reactor power indicates 17%, Main Generator indicates 60 Mwe.
B.
Core mimic CEA display amber lights are ALL illuminated.
C. Reactor power indicates 17% with SBCS controlling temperature. Main Generator indicates 0 Mwe.
D. Trip Circuit Breaker (TCB) lights indicate WHITE 1
R02 Given the following conditions:
- Unit 1 is at 45% power and stable.
- A 5 gpm break from the upper instrument tap of Pressurizer (Pzr) Level transmitter, LT-i ii ox, occurs.
Assuming no operator action, which ONE of the following describes the response of LI-i 11 OX?
LI-i ii OX Channel X Pzr Level indication will begin to_(i)____ as a result of the zP cell element between the reference and variable leg sensing a (2)
A. i)lower
- 2) higher tiP due to VARIABLE leg pressure lowering B. i)lower
- 2) lower tiP due to REFERENCE leg pressure lowering C. 1) increase
- 2) lower tiP due to REFERENCE leg pressure lowering D. i)increase
- 2) higher tiP due to VARIABLE leg pressure lowering 2
R03 Unit I has the following post trip indications:
A Differential Current Bus Lockout has occurred on the,B3 4.16kv bus Pressurizer level is 12% lowering Pressurizer pressure is 1780 psia lowering CET is 520°F stable Cortainmet Pressure is 0.2 psig stable SG A and ?B are 930 psia and slowly lowering Safety / PORV tailpipe temperatures are 140-150°F SJAE readings indicate 3.2 E-07 pCi/cc.
Upon the trip the following annunciator came in:
B SAFEGUARDS PUMP ROOM SUMP LEVEL HIGH-HIGH LA-2 (NO operator actions have been taken)
Based on the above conditions, enter:
A.
1 -EOP-04, SGTR B.
1-EOP-09, LOOP C.
1-EOP-03, LOCA D.
1-EOP-05, ESDE 3
R04 Unit I has tripped. On the trip, a loss of the 1AI 6.9 KV bus occurred. 1-EOP-02, Reactor Trip Recovery was entered.
While in 1-EOP-02, Reactor Trip Recovery the crew has lowered RCS pressure to between 1800 and 1850 psia.
Which ONE of the following states:
1.
the basis for this RCS pressure LOWER limit.
2.
the bases for the RCS pressure UPPER limit.
A.
- 1. The LOWER limit ensures Figure 1A, RCS pressure temperature curve stays within acceptable range
- 2. The UPPER limit is based on maintaining the lower RCP seal cavity below 300°F.
B.
- 1. The LOWER limit is based on providing a margin above SIAS actuation setpoint
- 2. The UPPER limit is based on maintaining the lower RCP seal cavity below 300°F.
C.
- 1. The LOWER limit is based on providing a margin above SIAS actuation setpoint
- 2. The UPPER limit ensures RCP controlled bleedoff flow meets minimum requirement.
D
- 2. The UPPER limit ensures RCP controlled bleedoff flow meets minimum requirement.
4
R05 Unit 2 is in Mode 3. Due to Pressurizer level control problems, charging and letdown was secured at 2:15 pm. The following conditions are noted:
RCS temperature is 532° F RCS pressure is 2250 psia RCP controlled bleedoff is 1.1 gpm per pump Pressurizer level is 33%
Last RCS leak rate was 0.05 gpm.
Assuming no auto or Operator actions, which ONE of the following states the APPROXIMATE time that the Pressurizer will be at the minimum Tech. Spec. limit?
A. 3:01 pm B. 3:31 pm C. 3:37 pm D. 3:46 pm 5
R06 Unit 1 is on SDC in reduced inventory condition. The SDC system is aligned and operating in accordance with 1-NOP-Ol.04, RCS Reduced Inventory And Mid-Loop Operation.
lAW 1-NOP-Ol.04, RCS Reduced Inventory And Mid-Loop Operation, which ONE of the following states the LPSI pump that is in STANDBY and the reason for this standby lineup?
A.
IA LPSI pump. V3483, 1A LOOP SDC return to 1A LPSI pump relief has the potential to lift at a higher pressure than 1 B LPSI pump.
B.
1A LPSI pump. Due to suction piping arrangement, LPSI Pump 18 will experience adverse suction conditions before LPSI Pump IA.
C.
1 B LPSI pump. V3468, 1 B LOOP SDC return to 18 LPSI pump relief has the potential to lift at a higher pressure than IA LPSI pump.
D.
1 B LPSI pump. Due to suction piping arrangement, LPSI Pump 1A will experience adverse suction conditions before LPSI Pump 18.
6
R07 Given the following conditions on Unit 2:
The CCW system has developed a leak LA-lO, CCW SURGE TANK COMPARTMENT A LEVEL LOW, is locked in LB-b, CCW SURGE TANK LEVEL HIGH/COMPARTMENT B LEVEL LOW, alarmed but subsequently clears.
- 1) What COW system loads are affected?
- 2) What actions need to be performed to restore COW to that load?
A.
- 1) Fuel Pool Heat Exchanger
- 2) Place the B train N Header valve control switches to CLOSE then OPEN B.
- 1) Fuel Pool Heat Exchanger
- 2) Place the A train N Header valve control switches to CLOSE then OPEN C.
- 1) Letdown Heat Exchanger
- 2) Place the A train N Header valve control switches to CLOSE then OPEN D.
- 1) Letdown Heat Exchanger
- 2) Place the B train N Header valve control switches to CLOSE then OPEN 7
R08 Given the following conditions on Uniti:
The unit is operating at 100% power.
PlC-Ill OX, Pressurizer (Pzr) pressure controller is selected.
Pzr pressure is being maintained at 2250 psia with Pzr Backup Heaters Bi, B2, and B5 ON with a 10% output to the Pzr Proportional Heaters.
The Output on PIC-I1IOX begins to slowly drift HIGH due to a malfunction of PT-IIIOX.
Which ONE of the following describes the response of the OUTPUT on HIC1 100, Main Spray controller AND the effect on actual Pzr pressure?
(Assume no Operator actions)
HIC-1100 output_(1)____
Actual Pzr pressure _(2)_____
A.
- 1) rises
- 2) rises B.
1)rises
- 2) lowers C. 1)lowers
- 2) lowers D. 1)lowers
- 2) rises 8
R09 Unit I has a loss of feedwater event at 100% power. The unit DID NOT TRIP when trip conditions were met.
For the initial onset of the event, which ONE of the following will be the LARGEST contributor of negative reactivity insertion and why? (assuming no Operator actions)
The reactivity added by the increase in the:
A. fuel temperature. For the above event as the fuel temperature increases, this value becomes lower per °F.
B. fuel temperature. For the above event as the fuel temperature increases, this value becomes higher per °F.
C. moderator temperature. For the above event the core is under moderated resulting in this value becoming higher per °F.
U. moderator temperature. For the above event the core is over moderated resulting in this value becoming less per °F.
9
RO 10 Unit I was operating at 100% power when the Steam Jet Air Ejector radiation monitor was trending up but has not reached the alarm setpoint. The crew has entered 1-AOP-08.02, Steam Generator Tube Leak. No other radiation monitors have an increasing trend.
One minute later, the Reactor tripped.
During performance of 1-EOP-01, Standard Post Trip Actions, the suspected SG tube leak escalated to a 400 gpm SG tube rupture.
While in 1-EOP-01, which ALARM would annunciate FIRST to indicate WHICH Steam Generator has a SG tube rupture?
A. Main Steam line radiation monitor.
B. Steam Jet Air Ejector radiation.
C. Steam Generator level high.
D. Steam Generator blowdown radiation.
10
ROll Unit 1 has experienced an Excess Steam Demand event on the 1 B SG and has entered I -EOP 05, Excess Steam Demand with the following:
1A SG T 0
fd is 500°F 1 B SC T 0
Id is 240° F I B SG indicates 0 Wide Range 1A ADV is currently in automatic The US has directed you to stabilize RCS temperature. lAW Operations Department Policy, OPS-539, RCS Cooldown Guidance which ONE of the following states how RCS temperature is controlled and the basis for this manipulation?
A.
Maintain IA ADV in auto and adjust setpoint to 25 psia steam pressure.
This will maximize Safety Injection flow to regain Pressurizer level to within the RCS Inventory control safety function criteria.
B.
Maintain IA ADV in auto and adjust setpoint to 25 psia steam pressure.
This will limit the RCS heatup which could result in exceeding the RCS subcooling limit.
C. Place 1A ADV in manual, fully open, then adjust the auto setpoint to 25 psia steam pressure and place in automatic. This will maximize Safety Injection flow to regain Pressurizer level to within the RCS Inventory control safety function criteria.
D. Place 1A ADV in manual, fully open, then adjust the auto setpoint to 25 psia steam pressure and place in automatic. This will limit the RCS heatup which could result in exceeding the RCS subcooling limit.
11
R012 Unit I is at 45% power with the following conditions:
I B AFW Pump is out of service.
IA Main Feedwater pump is out of service.
The following alarm is received:
125V DC BUS lAB UV A-60 Shortly after the alarm, the lB Main Feedwater pump trips and cannot be restarted.
Which ONE of the following actions are taken in 1 -EOP-O1, Standard Post Trip Actions as a direct result of the above conditions?
A.
Align the lAB DC bus to the 1C or ID DC bus.
B.
Align the lAB Battery Charger to the lAB DC bus.
C.
Maintain current DC alignment with ALL RCPs running.
D.
Secure ONE RCP in EACH loop.
12
R013 Given the following conditions:
Unit 2 is in 2-EOP-1O, Station Blackout receiving power via the Station Blackout Crosstie, to the 2AB 4.16KV bus to the 2A3 4.16KV bus from the IA Emergency Diesel Generator WHICH IS THE ONLY RUNNING UNIT 1 DIESEL.
Which ONE of the following states when / if the 2A Intake Cooling Water Pump can be started?
The 2A Intake Cooling Water pump can:
A.
be started if Unit 1 has determined sufficient load (KW) capacity is available on the 1A Diesel Generator.
B.
be started if Unit I has determined sufficient amperage capacity is available on the station blackout crosstie breaker.
C.
NOT be started due to the potential for exceeding the station blackout crosstie breaker amperage limits.
D.
NOT be started due to the potential for exceeding the 1A Diesel loading (KW) limits.
13
ROI4 Unit 2 has the following Intake Cooling Water (ICW) system alignment at 100% power:
2A and 2B ICW pumps are running.
2AB 4.16KV bus is aligned to the 2B3 4.16KV Bus.
The 2C ICW pump was just started on the 2B ICW header for surveillance testing and the 2B ICW pump has yet to be stopped. A loss of offsite power occurs and both Diesel Generators start and load on the bus.
Which ONE of the following states the response of the 2C and 2B ICW pumps?
2B lOW Pump will:
A.
automatically restart as the Diesel loads sequence on the bus.
2C lOW pump will NOT automatically restart and CANNOT be manually restarted.
B.
NOT automatically restart but CAN be manually started.
2C ICW pump will automatically restart as the Diesel loads sequence on the bus.
C. NOT automatically restart and CANNOT be manually restarted.
2C ICW pump will automatically restart as the Diesel loads sequence on the bus.
D. automatically restart as the Diesel loads sequence on the bus.
2C ICW pump will NOT automatically restart but CAN be manually started.
14
R015 The 120 VDC input breaker spuriously opened.
20 Instrument bus Inverter trouble alarm annunciates Which ONE of the following would be expected as a result of this malfunction?
The 2C Instrument bus:
A.
remains energized from the 480 VAC alternate source through the maintenance bypass bus.
B.
remains energized from the 120 VAC alternate source directly to the Instrument bus.
C. becomes de-energized. The Instrument bus should be re-energized by placing the 120 VAC manual bypass switch to the Bypass Source to Load position.
D. becomes de-energized. The Instrument bus should be re-energized by closing the 480 VAC MOO input breaker to the maintenance bypass bus.
15
RO 16 Unit I is at 100% power with the 1C ICW pump out of service. The IA ICW pump trips and cannot be restored.
As Turbine Cooling Water temperature rises, which ONE of the following would require entry into 1-AOP-22.0I, Rapid Downpower?
A.
Main Generator COLD gas temperature indicates 49°C B.
Main Generator HOT gas temperature indicates 100°C C. IA Main Feedwater pump bearing temperature indicates 190°F D. Turbine bearing oil temperature indicates 160°F 16
R017 Unit 1 is at 100% power when a large Instrument air leak occurs. The crew has implemented 1-AOP-1 8.01, Instrument Air Malfunction. If Instrument air continues to degrade, which ONE of the following states the HIGHEST pressure that requires the Unit to be manually tripped AND which procedure will be implemented AFTER 1-EOP-01 Standard Post Trip Actions?
A. 74 psig, 1-EOP-02, Reactor Trip Recovery B. 59 psig, 1-EOP-02, Reactor Trip Recovery C. 74 psig, 1-EOP-09, Loss of Offsite Power/Loss of Forced Circulation D. 59 psig, 1-EOP-09, Loss of Offsite Power/Loss of Forced Circulation 17
R018 Given the following conditions on Unit 1:
Reactor power is 100%.
Unit 2 is off-line due to a Short Notice Outage.
Switchyard Voltage has lowered from 242kV to 237kV due to a high load demand on the grid.
Based on the above noted conditions, the DRCO would observe Main Generator _(1 )_
If switchyard voltage continued to lower, the FIRST Main Generator OVER-EXCITATION protection action would be _(2)_.
A. 1) MEGAWATTS and VARS RISING
- 2) automatically swapping to the DC Voltage Regulator which will maintain the field current at a preset limiting position.
B.
- 1) VARS RISING ONLY
- 2) automatically swapping to the DC Voltage Regulator which will maintain the field current at a preset limiting position.
18
R019 Given the following conditions on Unit 1:
The reactor is at 3.0 E-4% power following a start up from a two week forced outage.
Critical start up data is being recorded by the RO.
CEA group 7 was at 108 withdrawn when they were withdrawn to 113 (Assume no operator action)
Actual reactor power will rise A. and RCS Temperature will remain stable until reaching the POAH B. and RCS Temperature will continually rise upon reaching the Power Range C. until the reactor trips due to High SUR D. until the reactor trips due to VHPT 19
R020 Unit 2 is at 100% power. Pressurizer level Channel X is selected.
Pzr Channel X Level LowLow level alarmed at 27% indicated level (actual level is 63%)
Assuming NO Operator actions which ONE of the following states the number of Charging pumps running and the expected high level alarm?
A.
Three Charging pumps running. Pressurizer high level alarm at 73%.
B.
Two Charging pumps running. Pressurizer level alarm at 67%.
C.
Three Charging pumps running. Pressurizer level alarm at 67%.
D.
Two Charging pumps running. Pressurizer high level alarm at 73%.
20
R021 Given the following conditions on Unit 1:
Reactor power is 11% power The turbine is being rolled for a start up The condenser has developed a small vacuum leak Condenser back pressure is 2.7 inches of Hg. and slowly rising The crew has entered 1-AOP-12.O1, Loss of Condenser Vacuum Which ONE of the following states:
The MINIMUM backpressure setpoint at which the SBCS becomes unavailable and the basis for this setpoint?
A.
8 of Hg. absolute, protect low pressure turbine blades from resonance cracking B.
12 of Hg. absolute, protect low pressure turbine blades from resonance cracking C.
8 of Hg. absolute, protect main condenser from overpressure D.
12 of Hg. absolute, protect main condenser from overpressure 21
RO 22 Unit 1 is performing a Liquid Release of the 1A Waste Monitor Tank when the following alarm is received:
LIQUID WASTE RAD HIGH N-37 Liquid release flow control valve, FCV-6627X indicates open and will not close from the RTGB.
lAW 1-AOP-06.02, Uncontrolled Release Of Radioactive Liquids which ONE of the following is a required SUBSEQUENT Operator action?
A. At the 1A Waste Monitor Storage Tank, stop the IA Waste Monitor pump AND at the CCW platform lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
B. At the 1A Waste Monitor Storage Tank, close FCV-6627X AND at the CCW platform lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
C. From the Liquid Waste Control panel, close FCV-6627X AND at the Waste Monitor Storage Tanks, stop the Waste Monitor pump associated with the liquid release.
D. From the Liquid Waste Control panel, stop the IA Waste Monitor pump AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
22
RO 23 The following conditions exist on Unit 1:
The unit is in a refueling outage with a core offload in progress.
The Spent Fuel Handling Machine (SFH) is transporting a spent fuel assembly, which has been used for 3 refueling cycles, from the fuel transfer canal to the Spent Fuel Pool (SFP).
The spent fuel assembly came into contact with transfer gate wall Gas bubbles are reported to be rising rapidly to the fuel transfer canal surface and bursting.
The FHB EFFLUENT Radiation monitor AND the Spent Fuel Pool Transfer Canal AREA RADIATION MONITOR indications are in ALARM due to the release of(1)
. The FHB ventilation system (2).
A.
- 1) beta and gamma radiation
- 2) is in its NORMAL alignment B.
- 1) gamma radiation ONLY
- 2) is in its NORMAL alignment C.
- 1) beta and gamma radiation.
- 2) has re-aligned to the Shield Building Ventilation filter train D. 1)gammaONLY.
- 2) has re-aligned to the Shield Building Ventilation filter train.
23
RO24 Unit 1 is implementing 1-EOP-15, Functional Recovery with the following:
A Loss of Offsite Power (LOOP) has occurred.
1A Steam Generator (SG) has experienced a Steam Generator Tube Rupture (SGTR).
1 B SG has an Excess Steam Demand outside the Containment upstream of the Main Steam Isolation valves.
1A SG pressure is 850 psia.
lB SG pressure is 454 psia.
Neither SG has been isolated.
Which ONE of the following states:
- 1) When the Containment Isolation Safety Function will be met?
- 2) Bases for meeting the Safety Function A.
- 1) When 1-EOP-99 Appendix R, Steam Generator Isolation is complete on the 1 B SG AND the 1A SG is capable of being steamed ONLY to the condenser.
- 2) Steaming to the condenser contains the radiological effluents.
B.
- 1) When 1-EOP-99 Appendix R, Steam Generator Isolation is complete on thel B SG AND the 1A SG is capable of being steamed to the condenser OR the atmosphere.
- 2) The 1A SG is the least affected SG and has the capability to remove heat by steaming to atmosphere or condenser.
C.
- 1) When 1-EOP-99 Appendix R, Steam Generator Isolation is complete on BOTH SGs AND Once Through Cooling is initiated.
- 2) Both SGs are considered faulted and should be isolated.
D.
- 1) When 1-EOP-99 Appendix R, Steam Generator Isolation is complete on the 1A SG AND the lB SG has blown dry.
24
R025 Given the following conditions on Unit 2:
The Unit has experienced a LOCA with multiple ECCS failures.
Safety injection flow does NOT meet Figure 2 The crew is performing actions contained in 2-EOP-15, Functional Recovery Plant conditions are now:
REP CET indicate 539° F and constant.
RCS TH 0t temperatures are 51 9°F and constant.
RCS T 0
jd temperatures are 512°F and constant.
RCS pressure indication is 870 psia.
Which ONE of the following states the status of RCS subcooling and Natural Circulation?
A. RCS is 9°F subcooled, Single phase Natural Circulation is NOT met.
B. RCS is 11°F superheat, Two phase Natural Circulation IS met.
C. RCS is 9°F subcooled, Single phase Natural Circulation IS met.
D. RCS is 11°F superheat, Two phase Natural Circulation is NOT met.
25
R026 Unit 1 is performing a natural circulation cooldown in accordance with 1-EOP-03 using the ADVs with the following conditions:
RCS pressure is 140 psia and lowering.
Rep CET temperature is 335°F and constant.
Hot leg temperature is 325°F and constant.
Cold leg temperature is 320°F and lowering.
Reactor Vessel Head temperature is 353°F and constant.
Aux. spray valve SE-02-03 is open and Aux. spray valve SE-02-04 is closed.
Which ONE of the following states the required actions?
Throttle:
A. open the ADVs further and close SE-02-03.
B. open the ADVs further and open SE-02-04.
C. close the ADVs and close SE-02-03.
D. close the ADVs and open SE-02-04.
26
R027 Unit 2 was tripped from 100% power due to LOOP.
The following conditions exist during 2-EOP-01, Standard Post Trip Actions:
ADVs are in service in AUTO/AUTO set to 900 psia RCS Tave is 530° F and stable Auxiliary Feedwater was throttled after AFAS actuation SG Pressures are 880 psia and stable Then a SIAS occurred due to lowering pressurizer pressure Following SIAS actuation, which ONE of the following states the Operator actions that is performed to ensure RCS Heat Removal is maintained within limits?
A. Throttle closed AFW header valves to both SGs.
B.
Place ADVs in AUTO / MANUAL.
C. Reduce ECCS flow by throttling HPSI valves.
D. Close the MSIVs.
27
R028 Given the following conditions on Unit 1:
Reactor power is 100%.
The Containment Instrument Air Compressors are out of service.
MV-i 8-1, Instrument Air Containment isolation valve closes and cannot be re-opened.
Which ONE of the following Reactor Coolant Pump motor indications would be expected?
A. Increasing RCP Controlled Bleedoff Temp B. Increasing motor stator temperatures.
C. Decreasing CCW flow to motor oil coolers.
D. Decreasing Upper I Lower oil reservoir levels.
28
R029 Unit 1 is in Mode 5. RCS level is 30 feet 6 inches with RCP seal injection in service. Two Charging pumps are in service with the IA LPSI pump filling the RCS.
The Charging Loop isolation valves are as follows:
SE-02-01, IBI Loop Charging Isol is OPEN SE-02-02, 1A2 Loop Charging Isol is CLOSED A short circuit causes SE-02-01, 1 BI Loop Charging Isol to fail closed.
Which ONE of the following states the effect of SE-02-01 closing on the RCP seals?
Seal injection flow has:
A.
decreased which could cause contaminants to enter the seal cartridge as the RCS level is raised.
B.
decreased which could result in the seal cavity not filling completely.
C.
increased which could result in excessive vapor seal leakoff flow.
D.
increased which could result in extreme seal damage.
29
R030 Unit 1 is on SDC. The Pressurizer is being cooled and has just gone solid. RCS pressure is 75 psia.
In accordance with 1-GOP-305, Reactor Plant 000ldown - Hot Standby To Cold Shutdown, which ONE of the following describes:
- 1. How the Letdown valve controller PIC-2201 will be configured for solid plant operations:
PIC-2201, Ltdn Pressure controller will be in:
AND
- 2. If HCV-3657, SDC Temp Control, were throttled closed, what response would need to occur to maintain pressure constant?
A. 1)AUTO.
- 2) Letdown pressure control valves PCV-2201P and PCV-2201Q will OPEN.
B. 1)AUTO.
- 2) Letdown pressure control valves PCV-2201P and PCV-2201Q will CLOSE.
C. 1)MANUAL.
- 2) Manually OPEN Letdown pressure control valves PCV-2201 P and PCV 2201Q.
D. 1)MANUAL.
- 2) Manually CLOSE Letdown pressure control valves PCV-2201P and PCV 2201Q.
30
RO 31 Unit 1 has just placed IA LPSI pump on SDC with the following:
RCS temperature is 320°F RCS pressure is 262 psia HCV-3657 SDC TEMP CONTROL is open 100%
FCV-3306 SDC RETURN FLOW is open 25%
Instrument air to the RAB is lost due to a ruptured air header line.
Which ONE of the following states the expected response?
LPSI amps will:
A. increase, RCS temperature will decrease.
B. decrease, RCS temperature will increase.
C. increase, RCS temperature will increase.
D. decrease, RCS temperature will decrease.
31
R032 Unit I Is experiencing a Large Break LOCA and Is Implementing 1-EOP-15, Functional Recovery with the following:
RWTlevells8feet.
MI EGGS pumps are avaIlable Due to equipment problems, RAS preparation steps are unable to be performed.
WhIch ONE of the followIng states the possible effects of not being able to perform the RAS preparation steps?
A Containment cooling may be jeopardized.
B. Containment sump pH limit may be jeopardized.
C. HPSI Pumps NPSH may be jeopardIzed.
D. LPSI Pumps may not stop on RAS.
32
R033 Unit 2 has tripped from 100% power due to a Main Generator Lockout. Shortly after the trip, the ROD noticed:
Quench Tank pressure is 58 psig and rising Pressurizer level is 41% and rising Pressurizer pressure is 1720 psia and lowering rapidly RCS temperature is 530°F V1201 has 5 led lights lit Which ONE of the following contingency actions would the crew take while in EOP-01, Standard Post Trip Actions?
A. Trip one ROP in each loop.
B. Stop the running Charging pumps.
- 0. Close PORV block valves.
D. Reset AND energize Pressurizer heaters.
33
RO 34 Unit 1 is at 100% power. The 1A Component Cooling water (CCW) pump is to be removed from service. The 1C CCW is to be aligned to replace the IA CCW pump.
Which ONE of the following states the MINIMUM electrical lineup required to meet the Technical Specification requirements for the CCW pump?
A.
ONLY the lAB 4.16 KV bus aligned to the 1A3 4.16KV bus.
B. The lAB 4.16 KV bus aligned to the 1A3 4.16KV bus and the lAB 480V bus aligned to the 1A2 480V bus.
C. The lAB 4.16 KV bus aligned to the 1A3 4.16KV bus, lAB 480V bus aligned to the 1A2 480V bus and the lAB DC bus aligned to the IA DC bus.
D. lAB 4.16 KV bus aligned to the 1A3 4.16KV bus, lAB 480V bus aligned to the 1A2 480V bus, lAB DC bus aligned to the 1A DC bus. IA Emergency Diesel Generator operable.
34
R035 Unit 1 is operating at 50% power. The Pressurizer was placed on recirculation lAW i-GOP-i 01, Reactor Operating Guidelines During Steady State and Scheduled Load Changes.
PlC-i 1 OOX is selected for Pressure control. PT-il OCX fails HIGH.
Assuming NO Operator action, which ONE of the following states the response of the Proportional and Backup heaters?
Proportional heaters are:
A. at MINIMUM output. Backup heaters are de-energized.
B. de-energized. Backup heaters are de-energized.
C. at MINIMUM output. Backup heaters stay at the position prior to the failure.
D. de-energized. Backup heaters stay at the position prior to the failure.
35
R036 Given the following indications on Unit I during an up power.
Channel D Variable High Power (VHP) reset pushbutton has just been depressed.
Channel D AT Power indicate 57%
Channel D Nuclear Power indicates 55%
Assuming no Operator actions, which ONE of the following states the power level at which Channel D will trip?
A.
66.61%
B.
64.61%
C.
61%
D.
59%
36
RO 37 Unit 1 is performing a startup with the following:
Reactor power is 10%
Turbine is latched SBCS is in service RPS Channel A Startup rate has failed high and is yet to be bypassed.
Both SG pressures are 900 psia Which ONE of the following will result in the crew entering 1-EOP-01, Standard Post Trip Actions?
A.
Startup rate spikes to 1.6 DPM on the B channel.
B.
DEH pump trips and the backup will not start.
C. HCV-08-1A, A MISV fails closed. A SG pressure increases to 950 psia.
D.
MB Instrument bus becomes de-energized.
37
R038 Unit I is experiencing a Loss of Coolant Accident (LOCA) and has entered I -EOP-03, LOCA with the following conditions:
Pressurizer pressure is 1580 psia and lowering Containment pressure is 5.5 psig and rising Containment radiation is 8 R/hr and rising ONLY SIAS has actuated Which ONE of the following states response of the Engineered Safety Feature Actuation System (ESFAS) and the expected Operator actions lAW 1-EOP-03, LOCA?
A. The ESFAS system is responding as expected. Verify proper operation of pumps and valves.
B. The ESFAS system is responding as expected. Manually actuate CIAS AND CSAS in anticipation of imminent automatic actuation.
C. CIAS should have actuated automatically. Manually actuate CIAS.
D. CIAS and CSAS should have actuated automatically. Manually actuate CIAS and CSAS.
38
R039 Unit 1 is in 1-EOP-03, LOCA, with the following:
Pressurizer pressure is 980 psia 1A HPSI did not start and cannot be started IA and lB LPSI pumps are operating All Charging pumps are operating Which ONE of the following states the expected Safety Injection flow?
References provided A.
530 gpm B. 400 gpm C. 330 gpm D. 220 gpm 39
RO 40 Unit 2 has experienced a LOCA. RCS pressure is 1580 psia and the crew has entered 2-EOP-03, LOCA.
On the trip, feeder breakers to MCC 2B9 tripped.
Which ONE of the following states the RUNNING Containment Fan Coolers?
A.
C and D Containment Fan Coolers.
B.
A and C Containment Fan Coolers.
C. A and B Containment Fan Coolers.
D.
B and D Containment Fan Coolers.
40
R041 Unit 2 has tripped from 100% power. Fifteen minutes post trip the following conditions are observed:
Containment temperature is 130°F Containment Pressure is 3.8 psig Which ONE of the following describes the status of the Containment Coolers 1)
PRIOR to the event and
- 2) AFTER the above stated conditions A.
- 1) Three Coolers running in FAST speed
- 2) Three Coolers running in FAST speed B.
- 1) Four Coolers running in FAST speed
- 2) Four Coolers running in SLOW speed C.
- 1) Three Coolers running in FAST speed
- 2) Four Coolers running in SLOW speed D.
- 1) Four Coolers running in FAST speed
- 2) Four Coolers running in FAST speed 41
R042 Given the following conditions on Unit 1:
The unit has experienced a Large Break Loss of Coolant Accident.
Prior to the event RWT level was 36.5 feet.
RAS occurred about 20 minutes ago.
1A Containment Spray (CS) pump AND the 1A and lB High Pressure Safety Injection (HPSI) pumps have indications of oscillating amps, header pressure and flow.
Which ONE of the following states:
- 1) The expected current Containment sump level.
- 2) The FIRST REQUIRED Operator action in accordance with l-EOP03 for the conditions noted above.
(references provided)
A.
1) 23.75 feet 2)
Stop the HPSI pumps B.
1) 23.75 feet 2)
Stop the CS pump C.
1) 24.00 feet 2)
Stop the HPSI pumps D.
1) 24.00 feet 2)
Stop the CS pump 42
R043 Unit 1 is experiencing a large break loss of coolant accident and is implementing 1-EOP-03, LOCA with the following:
The IA Containment Spray pump is out of service.
The IA HPSI pump is out of service.
All Containment Coolers are running.
RAS has occurred and the 1 B Containment Spray pump tripped and cannot be restarted.
Which ONE of the following states the status of Core cooling AND Containment cooling.
A.
- 1) Core cooling CANNOT be maintained.
- 2) Containment cooling CAN be maintained.
B.
- 1) Core cooling CAN be maintained.
- 2) Containment cooling CAN be maintained.
C.
- 1) Core cooling CANNOT be maintained.
- 2) Containment cooling CANNOT be maintained.
D.
- 1) Core cooling CAN be maintained.
- 2) Containment cooling CANNOT be maintained.
43
R044 Given the following conditions Unit us at 3% power following a Short Notice Outage.
Prior to that, the unit had been on line for 200 days.
RCS temperature is being controlled with Atmospheric Dump Valves (ADVs) in automatic.
The Main Steam Isolation valves are closed.
A manual Reactor trip is inserted due to loss of Instrument air.
Following the trip, a Loss of Offsite Power (LOOP) occurs.
Which ONE of the following states how RCS Heat Removal will be controlled?
While implementing EOP-09 LOOP, RCS Heat Removal will be controlled by:
A. the Main Steam Safeties cycling until local control is established using 1-EOP-99, Appendix U, Local Operation of Unit 1 Atmosphere Dump valves.
B. the Main Steam Safeties cycling until Instrument air is restored using 1-AOP-18.01, Instrument Air Malfunction.
C. placing the ADV controllers in manual I manual closed until local control is established using 1-EOP-99, Appendix U, Local Operation of Unit 1 Atmosphere Dump valves.
D. placing the ADV controllers in manual I manual closed until Instrument air is restored using 1-AOP-18.01, Instrument Air Malfunction.
44
RO 45 Given the following:
Unit 1 is at 60% power The 1A MEW pump trips Which ONE of the following describes the expected plant response before the Reactor and Turbine Trip on Low SIG Level?
Pressurizer Pressure will:
A.
Increase, because the RCS delta T power increases.
B.
Increase, because the RCS temperature increases due to elevated Steam Generator temperatures.
C. Decrease, because the increased boiling rate in the Steam Generator tube bundle region decreases Tavg.
D. Decrease, because the Steam Generator level initially increases, causing a contraction of the RCS inventory.
45
R046 Unit 1 has been at 100% power for 282 days. If the Unit lost all Main Feedwater and tripped on low SG level, which ONE of the following states the MINIMUM Auxiliary Feedwater capacity to remove decay heat, cool the primary and allow the SG level to recover?
One motor driven Auxiliary Feedwater Pump with a total of
_________gp flow and running 30 minutes after the event.
A.
350 4
B. 350 2
C.
150 2
D.
150 0
46
R047 Which ONE of the following will result in a:
- 1) Bus Lockout on the 1A2 4.16KV bus?
And
- 2) The result of the bus lockout?
A.
- 1) Degraded voltage condition.
B.
- 1) Degraded voltage condition.
- 2) 1A Diesel Generator starts but its output breaker DOES NOT CLOSE on the 1A3 4.16KV bus.
C.
- 1) Differential current between phases.
- 2) 1A Diesel Generator starts and its output breaker CLOSES on the 1A3 4.16KV bus.
D.
- 1) Differential current between phases.
- 2) 1A Diesel Generator starts but its output breaker DOES NOT CLOSE on the 1A3 4.16KV bus.
47
R048 On the 6.9KV busses, the AUTOMATIC transfer from the I to the 2 is considered a 3 transfer.
A.
- 1. Auxiliary Transformers
- 2. Startup Transformers
- 3. Live Bus B.
- 1. Startup Transformers
- 2. Auxiliary Transformers
- 3. Fast Dead Bus C.
- 1. Auxiliary Transformers
- 2. Startup Transformers
- 3. Fast Dead Bus D.
- 1. Startup Transformers
- 2. Auxiliary Transformers
- 3. Live Bus 48
R049 Unit I A Diesel Generator is running fully loaded during a surveillance. A loss of 125V DC power to the IA Diesel Voltage and Governor control occurs.
Which ONE of the following states the effect of losing the above DC power?
The IA Diesel will:
A.
continue to run fully loaded but will not respond to Operator demands for load changes.
B.
continue to run at minimum load due to the governor failing to its lowest setting.
C.
trip on mechanical overspeed.
D.
trip on loss of excitation.
49
R050 The Unit 2 SNPO has reported the following local Emergency Diesel Generator alarm on the 2A Diesel. All the air receivers indicate 138 psig.
STARTING AIR PRESS LOW 5-1 While investigating the alarm the SNPO also noticed the air dryer desiccant system indicated RED.
Which ONE of the following states the status of the 2A Diesel?
The air pressure is:
A. sufficient to start the Diesel. The Air Dryer indicating RED is considered NOT FUNCTIONAL.
B. sufficient to start the Diesel. The Air Dryer indicating RED is considered FUNCTIONAL.
C. NOT sufficient to start the Diesel. The Air Dryer indicating RED is considered NOT FUNCTIONAL.
D. NOT sufficient to start the Diesel. The Air Dryer indicating RED is considered FUNCTIONAL.
50
R051 Unit 1 Diesel Generator fuel oil storage tanks have been severely damaged due to tornados on site. BOTH Unit 1 fuel oil storage tanks have been breached and contain no oil.
Unit 2 Diesel Generator fuel oil storage tanks were unaffected.
Which ONE of the following states the MAXIMUM Diesel Generators that can be run and the MAXIMUM run time for the above condition?
A.
All Diesel Generators fully loaded for a period of three (3) days.
B.
All Diesel Generators fully loaded for a period of seven (7) days.
C.
One (1) Diesel generator fully loaded on each Unit for a period of seven (7) days.
D.
One (1) Diesel generator fully loaded on each Unit for a period of three (3) days.
51
R052 Given the following conditions:
Both Units are in Mode 1.
On Unit 1, l&C is performing a Response Time Test, in accordance with 1-SMI-26.57D, Calibration of Control Room Outside Air Intake Radiation Monitor RIS 26-87 (SB train located in the South Outside Air Intake Duct).
Which ONE of the following describes the response of the Control Room Emergency Ventilation System (CREVS) when the check source value reaches the high-high alarm setpoint on RIS 26-87?
A.
ONLY Unit 1 B train CREVS goes to the recirc mode with ONLY the South Outside Air Intake Duct isolated B.
ONLY Unit 1 B train CREVS goes to the recirc mode with the North AND South Outside Air Intake Ducts isolated C.
BOTH Unit 1 AND Unit 2 B train CREVS goes to the recirc mode with ONLY the South Outside Air Intake Ducts isolated D.
BOTH Unit I AND Unit 2 B train CREVS goes to the recirc mode with the North AND South Outside Air Intake Ducts isolated 52
R053 At 100% power, on Unit if two Intake Cooling Water Pumps are electrically aligned AND operating on the same electrical bus in Mode 1, the associated must be declared inoperable.
A.
One (1), Diesel Generator B. One (1), Off-Site Power Source C. Two (2), Diesel Generator D. Two (2), Off-Site Power Source 53
R054 Given the following conditions on Unit 2:
The 20 Instrument Air Compressor is out of service. The 2D Air Compressor trips. A manual Reactor trip was initiated due to low Instrument Air pressure.
2-EOP-01 has been completed with the diagnostic flow chart indicating that a Steam Generator Tube Rupture (SGTR) is in progress.
Instrument Air pressure is now 20 psig and lowering.
A cooldown has been performed with Reactor Coolant System (RCS) Hot Leg and Cold leg temperatures indicating 509°F and 505 °F respectively.
- 1) Which ONE of the following describes the current status of HCV-08-IA, Main Steam Isolation valve AND
- 2) What actions (if any) would be required to close HCV-08-1A while performing 2-EOP-99, Appendix R Isolation of the 2A Steam Generator (SG)?
A. 1) CLOSED due to loss of instrument air to the valve.
- 2) No further action is required.
B. 1)OPEN.
- 2) No further action is required.
D. 1) OPEN.
- 2) HCV-081A can only be closed LOCALLY using 2-EOP-99, Appdx l,MSIV Local Closure.
54
RO 55 Unit I is operating at 100% power. PT-07-2A, Containment Pressure transmitter failed high and has yet to be bypassed. A loss of the MD instrument bus occurs.
Which ONE of the following defines ALL the ESFAS signals that will actuate?
A.
CIAS, CSAS, MSIS and SIAS B. CSAS,SIAS C. CIAS, MSIS and SIAS D. CIAS,SIAS 55
R056 Unit I is in 1-EOP-O3, LOCA with a LOOP and the 1A Emergency Diesel Generator out of service. Pressurizer pressure is 1350 psia. It is ten (10) minutes into the event.
Which ONE of the following states the suction source for the Charging Pumps?
A. Volume Control Tank B.
Refueling Water Tank C. Boric Acid Makeup Tanks via the Gravity feeds V-2508 and V-2509.
D. Boric Acid Makeup Tanks via the Emergency Borate valve V-2514.
56
R057 Unit 1 is at 100% power with the following RPS indications:
Two (2) K relays K1 and K2 are de-energized.
Two (2) logic matrix relays open.
Channel A Wide Range Nuclear channel indicating 0.
Channel A Linear Range Nuclear channel indicating 0.
Which ONE or the following states the failure that has caused the above condition and the status of the RPS Trip Circuit Breakers (TCBs)?
A loss of:
A.
A Instrument bus. Four (4) TCBs are open.
B.
A Instrument bus. Two (2) TCBs are open.
C.
A CEA MG set. Four (4) TCBs are open.
D.
A 125V DC bus. Eight (8) TCBs are open.
57
R058 Unit 1 is at 100% power steady state.
Steam Generator (SG) level control transmitter LT-9005, IA SG NR Level transmitter failed low.
No Operator actions have been taken when transmitter LT-9013A, lA SG Safety Channel level transmitter failed low.
Main Feedwater Regulating Valve (MFRV) controller and the SG low level RPS channel A bistable A. goes to manual; goes to trip.
B. goes to manual; stays in its current state.
C. stays in its current operational mode; goes to trip.
D. stays in its current operational mode; stays in its current state.
58
R059 Unit I has tripped from 100% power and has entered 1-EOP-03, LOCA with the following conditions:
Prior to the trip the A QSPDS was out of service When 1-EOP-03 was entered, an electrical malfunction resulted in the B QSPDS becoming out of service.
All RCPs are off Which ONE of the following states ALL the Safety Functions that will NOT be able to be ASSESSED due to the status of the QSPDS system?
A.
RCS Inventory Control and RCS Heat Removal B.
RCS Inventory Control and Core Heat Removal C. RCS Heat Removal and Core Heat Removal D. RCS Pressure Control, Core Heat Removal and RCS Heat removal.
59
R060 Unit 2 is in 2-EOP-03, LOCA. Pressurizer pressure is 1580 psia.
Spent fuel pool temperature will continue to rise until:
A.
CCW N header isolation valves are taken to CLOSE and then OPEN. SIAS reset NOT required.
B. the CCW MOVs to / from the Fuel Pool heat exchangers are opened from the A or B essential headers by taking the switches to SIAS OVERRIDE OPEN.
C. SIAS is reset and the CCW MOVs to / from the Fuel Pool heat exchangers are opened from the A OR B essential headers by taking the switches to LOCKED CLOSED and return to OPEN.
D. SIAS is reset AND the CCW N header isolation valves are taken to CLOSE and then OPEN.
60
R061 Unit 2 is in refueling operations performing a full core offload.
lAW 2-AOP-26.02, Area Radiation Monitors and/or 2-AOP-26.O1, Process Radiation Monitors, which ONE of the following radiation monitors, if it were to fail high, would immediately require fuel handling operations to stop after the fuel bundle has been placed in a safe condition?
A.
CIAS area monitor RR-263 B. Containment Process Particulate and Gas monitor RC-26-25 C. Spent Fuel area monitor RIM-26-7 D. Spent Fuel process monitor RR-26-2 61
RO62 Unit 1 has implemented 1-AOP22.O1, Rapid Downpower due to a Main Feedwater control problem. The Unit was at 97% power when the Operator noticed the following light illuminated on the DEH panel:
Trans(fer) relay 24 V Monitor lAW 1-AOP-22.03, DEH Turbine Control System, which ONE of the following states the status of DEH control and how the down power will be controlled.
DEH will:
A. be in Operator Auto. Place DEH in Manual. The Governor Valves will be in SINGLE VALVE CONTROL.
B. be in Operator Auto. Place DEH in Manual. The Governor Valves will be in SEQUENTIAL VALVE CONTROL.
C. have swapped to Turbine Manual, the Governor Valves will be in SINGLE VALVE CONTROL.
D. have swapped to Turbine Manual, the Governor Valves will be in SEQUENTIAL VALVE CONTROL.
62
RO 63 Unit 1 is at 52% power performing an up power to 100% with the following:
1A and 1 B Main Feedwater pumps are running.
IA and 1C Condensate pumps are running.
The 1C Condensate pump trips. Steam Generator levels are 63% and slowly lowering.
Which of the following states:
1.
the plant response 2.
the procedure to be implemented The I B Main Feedwater Pump will trip:
A.
- 1) as a DIRECT result of the IC Condensate pump tripping.
- 2) 1-AOP-09.04, Feedwater, Condensate, And Heater Drain Pump Abnormal Operations.
B.
- 1) as a DIRECT result of the IC Condensate pump tripping.
- 2) 1-AOP-09.01, Feedwater Control System Abnormal Operations.
C.
- 1) on low suction pressure.
- 2) 1-AOP-09.04, Feedwater, Condensate, And Heater Drain Pump Abnormal Operations.
D.
- 1) on low suction pressure
- 2) 1-AOP-09.01, Feedwater Control System Abnormal Operations.
63
R064 Unit I is performing a Gas release of the IA Gas Decay Tank.
Which ONE of the following will result in an AUTOMATIC termination of this release?
A. Waste Gas discharge radiation monitor, blue fail light is illuminated.
B.
Plant Vent Exhaust monitor channel O1O5 goes into HIGH alarm.
C. The running RAB Supply fan, HVS-4A trips.
D. The running RAB exhaust fan, HVE-1 CA trips.
64
R065 Unit 1 is operating at 85% power with IA1, 1BI andlB2 Circulating Water Pumps (CWP) running.
In preparation to increase power to 100%, the Operator starts the 1A2 CWP.
Three (3) minutes after starting the 1A2 CWP the 1 B2 CWP trips.
Which ONE of the following states ALL the CWPs that will be running?
A.
1AI and IB1 CWPs B.
1A1 and 1A2 CWPs C.
1A2 and 1B1 CWPs D. IAI, 1A2, and 1BI, CWPs 65
R066 You are the RO at the controls when the following unexpected alarm is received:
PZR CHANNEL X LEVEL HIGH/LOW H-i 9 In accordance with Operations Department Policy, OPS-522, Annunciator Response, which ONE of the following states the correct order to respond to this alarm?
A. Silence the alarm, acknowledge the alarm then announce what the alarm is to the Unit Supervisor.
B. Silence the alarm, announce what the alarm is to the Unit Supervisor then acknowledge the alarm after the Unit Supervisor responds.
C. Announce the alarm to the Unit Supervisor, silence the alarm after US responds then acknowledge the alarm.
D. Announce the alarm to the Unit Supervisor, acknowledge the alarm after the Unit Supervisor responds then silence the alarm.
66
R067 Given the following conditions:
Unit 1 is in Mode 5 with Shutdown Cooling in service.
Current RCS Boron concentration is 1635 ppm.
An evolution is to be performed that will lower the RCS boron concentration to1595 ppm.
Which ONE of the following states the MINIMUM Shutdown Cooling flow necessary in accordance with procedural and Tech Spec requirements to perform the above evolution?
A. 4117GPM B. 3670 GPM C. 3000 GPM D.
1000 GPM 67
RO 68 Both Units are operating at 100% power with the following shift complement:
OneSM Two USs (one per Unit)
Four ROs (two per Unit)
Two SNPOs (one per Unit)
Two N P0s(one per Unit)
Two ANPOs (one per Unit)
One STA All individuals from above, normally assigned to the fire brigade are qualified as their position dictates.
One of the SNP0s suddenly becomes very ill and has left to go home.
lAW Operations Department Policies, 0PS201, Shift Compliment and OPS-207, Fire Brigade, what actions, if any, must be taken to ensure minimum shift compliment and minimum fire brigade compliment?
A. The SNPO position MUST be filled within two (2) hours to meet the minimum shift complement. The minimum fire brigade complement IS still met.
B. The SNPO position MUST be filled within two (2) hours to meet the minimum shift complement and the minimum fire brigade complement.
C.
No action is required. The minimum shift complement IS still met and the minimum fire brigade complement IS still met.
D. The minimum shift complement IS still met. The fire brigade complement must be filled within two (2) hours.
68
RO 69 Unit 1 is in Mode 1
- 1) Which ONE of the following parameters is considered an input to a Technical Specification SAFETY LIMIT and what system is CREDITED to prevent exceeding the SAFETY LIMIT associated with this parameter?
- 2) Which ONE of the following states the Technical Specification ACTION if the SAFETY LIMIT is exceeded?
A.
- 2) Be in Hot Standby with RCS pressure within its limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
B.
- 1) High TCOId, Main Steam Safety Valves.
- 2) Be in Hot Standby within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
C.
- 2) Reduce RCS pressure to within its limit within 5 minutes D.
- 1) High TCOtd, Main Steam Safety Valves.
- 2) Reduce T 00 1d to within its limit within 5 minutes 69
R070 Unit 1 is at 100% power. Which ONE of the following will result in entering a Technical Specification action statement?
A.
Performing 1A Emergency Diesel Generator monthly surveillance with the Diesel synchronized to the bus.
B.
Performing IA Auxiliary Feedwater pump surveillance.
C. Removing the 1A OR the IAA Battery Charger from service.
D.
Isolating a PORV by closing its block valve.
70
R071 Which one of the following MANUAL operator actions, if not performed prior to the receipt of a Recirculation Actuation Signal (RAS), could result in an unmonitored radioactive release to the environment?
A.
Unit 1 / Removing power inhibit from SI recirc valves.
B.
Unit 2 / Aligning ECCS sumps to the reactor cavity sump.
C.
Unit 1 / Isolating Low Pressure Safety Injection pump manual recircs.
D.
Unit 2 / Isolating Containment Spray pump manual recircs.
71
R072 Unit I is at 100% power MOL. The IA Charging pump is running and the RCO is preparing to start the 1 B Charging pump.
lAW 1-NOP-02.02, Charging And Letdown, which ONE of the following states the proper coordination with Health Physics (HP) and the reason for this coordination?
Notify HP:
A. when the I B Charging pump has been started so they can monitor for increasing radiation levels in the Charging pump cubicle.
B. when the 1 B Charging pump has been started so they can monitor for increasing radiation levels in the letdown area.
C. of the pending start. Allow approximately 15 minutes to verify no personnel in the area of letdown piping, as this area could exceed 1000 mr/hr.
D. of the pending start. Allow approximately 15 minutes to verify no personnel in the Charging pump cubicle as this area could exceed 100 mr/hr.
72
R073 While performing Standard Post Trip actions on Unit 2 you notice the following on the PC-li:
Main Steam Line Monitor indicates MAGENTA SJAE Monitor indicates YELLOW Which ONE of the following states the status of the above monitors?
A.
Main Steam Line Monitor has experienced a communications failure.
SJAE Monitor is in the ALERT range for activity.
B.
Main Steam Line Monitor has experienced an equipment failure.
SJAE Monitor is in the ALERT range for activity.
C.
Main Steam Line Monitor has experienced an equipment failure.
SJAE Monitor is in the HIGH range for activity.
D.
Main Steam Line Monitor has experienced a communication failure.
SJAE Monitor is in the HIGH range for activity.
73
R074 Which ONE of the following Security events REQUIRE a manual trip of BOTH Units and entry into the Emergency Plan lAW O-AOP-72.O1, Response To Security Events A.
Vehicle bomb detonation in Owner Controlled Area B.
Breach of Protected Area by unauthorized personnel C. A Credible Insider Threat D. Armed intruders are within the Protected Area fence 74
RO 75 The Unit 1 control room has been evacuated due to a fire. All RCO, US and SNPO actions have been performed lAW 1-ONP-100.02, Control Room Inaccessibility Appendix A through D. A cooldown to SDC is to be initiated from the Hot Shutdown Panel.
lAW 1-ONP-1 00.02, Control Room Inaccessibility, which ONE of the following states how Shutdown margin and RCS shrinkage makeup will be maintained during the cooldown?
Charging pump suction is:
1.
aligned to the for Shutdown Margin control, THEN 2.
the for shrink makeup A.
- 1. BAMTs
- 2. RWT B.
1.BAMTs
C. 1.VCT
D. 1.VCT
- 2. RWT 75
REVISION NO.:
PROCEDURE TITLE:
PAGE:
38 APPENDICES / FIGURES I TABLES / DATA 122 of 159 PROCEDURE NO.:
SHEETS 2-EOP-99 ST. LUCIE UNIT 2 0
0)
RCS Pressure Range Required QSPDS Subcooled Margin Reading (Rep CET) 2250 psia to 1000 psia 40 to 180°F 1000 psia to 500 psia 50 to 170°F Less than 500 psia 80 to 160°F FIGURE IA RCS PRESSURE TEMPERATURE (Page 1 of 1)
(Containment Temperature Less Than or Equal to 200°F)
CAUTION The RCP NPSH curve assumes one pump is operating in each loop. RCP instrumentation should be monitored for seal and pump performance in accordance with 2-EOP-99, Table 13.
2400 2200 2000 1800 V
1600 Maximum 0
C.
01 UI 1400 RCP NPSH Requirement 1
1200 V
1000 800 V
800 400 200 0
Minimum Subcooled Lnctues nUtrument Uncortalntjts 0
100 200 300 400 500 Inticated RCS Temperature (F) 600 700 800 PCPW3POUrO
REVISION NO.:
PROCEDURE TITLE:
PAGE:
38 APPENDICES I FIGURES / TABLES I DATA 123 of 159 PROCEDURE NO.:
SHEETS 2-EOP-99 ST. LUCIE UNIT 2 FIGURE lB RCS PRESSURE TEMPERATURE (Page 1 of 1)
(Containment Temperature Greater Than 200°F)
CAUTION The RCP NPSH curve assumes one pump is operating in each loop. RCP instrumentation should be monitored for seal and pump performance in accordance with 2-EOP99, Table 13.
2400
..N21L An OerotorAid has been pbced in the Unit 2 Control Room RCO desk. lArry rvi&on to this section of the procedure shell verify the vahdfty olttro Operator Aid and, if charres ore necessary, notify the EOP Coordinator.)
2200
Acceptoble Range 2000 1800 Maximum Subcooled*
S 1600 1400 1
0 1200.
\\,
5,
.1 1
C-I 1
1000 Mtntmum RCPNPSH Sb Id° Requirement°
.1 U cooe 800
/
600 400 irreludes Instrument UnCertainties 200 0
0 100 200 300 400 500 600 700 800 Indicated ROS Temperature (F)
p R
E S
S U
z E
R P
R E
S S
U R
E REVISION NO.:
PROCEDURE TITLE:
PAGE:
38 APPENDICES / FIGURES I TABLES / DATA 124 of 159 PROCEDURE NO.:
SHEETS 2-EOP-99 ST. LUCIE UNIT 2 FIGURE 2 SAFETY INJECTION FLOW VS. RCS PRESSURE (Page 1 of 1) 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0
p S
a TOTAL SAFETY INJECTION FLOW (gpm)
(PIQPSEOP99/F2IRevO,
REVISION NO.:
PROCEDURE TITLE:
PAGE:
38 APPENDICES / FIGURES I TABLES I DATA 127 of 159 PROCEDURE NO.:
SHEETS 2-EOP-99 ST. LUCIE UNIT 2 RWT LEVEL (FEET)
FIGURE 5 RWT LEVEL VS. CONTAINMENT SUMP LEVEL (Page 1 of 1) 40 35 30 25 20 15 10 5
0 NOTE
This curve indicates the relationship N
between containment surnp level
\\
increase and RWT decrease during N
safety injection and containment spray N
operation. Use Containment Water Level ide Range) Ll7-13Aor N:
Ll-07-13B instruments with this figure.
\\
\\N \\
H 23.5 FTASSUMED N
\\N\\
FOR HPSINPSH N
N
\\\\
N N\\
N N
N
\\ \\
N N
N\\
N N
N\\
N N
\\LN N
N N
N
.11 I
I I
I
\\lN N
1 5 710 15 17 19 20 21 22 23 24 CONTAINMENT SUMP LEVEL (FEET)
(P/OPSI2-EOP-99/Fig.5iRev.1/tff)
St. Lucie 2011-301 RD additional references:
Steam Tables
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I C,
NCD cz tO x
1)
I C) 1)0