ML12215A348
| ML12215A348 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/01/2012 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-321/12-301, 50-366/12-301 | |
| Download: ML12215A348 (81) | |
Text
HLT-07 RO NRC EXAM 1.201001K1.11001 The Unit 2 reactor is operating at 100% power with the following indications present on panel 2H1 1-P603:
o Charging Water Pressure 1480 psig o Cooling Water dP 0 psid o Drive Water dP Upscale o Drive Water Flow 0 gpm o Cooling Water Flow 5 gpm With the above indications, which ONE of the choices below completes the following statements?
The CRD has been fully closed.
RWCU Seal Purge flow isolated?
A. Flow Control Valve, 2C1 1-FOO2A; is B. Flow Control Valve, 2C11-FOO2A; is NOT C. Drive Water Pressure Control Valve, 2C1 1-F003, is D. Drive Water Pressure Control Valve, 2C1 1-F003, is NOT 1
HLT07 RO NRC EXAM
- 2. 202001A1.02 001 Which ONE of the choices below completes the following statements concerning monitoring Unit 2 INDIVIDUAL jet pump flows and a potential problem associated with a jet pump failure during a Loss of Coolant Accident (LOCA)?
If jet pump #3 failure were to occur during plant operation, the INDIVIDUAL failed jet pump dP can be monitored on panel A catastrophic failure of jet pump #3 will be indicated by A. 2H11-P602; a sudden INCREASE in reactor power B.
2H11-P602; a sudden REDUCTION in jet pump differential pressure C.
2H11-P619; a sudden INCREASE in reactor power D. 2H11-P619; a sudden REDUCTION in jet pump differential pressure 2
HLT-07 RO NRC EXAM
- 3. 202002K3.03 001 Unit 2 is operating at 100% RTP when a malfunction causes a Recirc runback signal to Speed Limiter #1 on BOTH Recirc Pumps.
Which ONE of the choices below completes the following statements?
While the Recirc Pumps are reducing speed, INDICATED reactor water level on 2C32-R606A, B and C, Narrow Range instruments will The FINAL Recirc Pump speed will be A. decrease; 22%
B. decrease; 33%
C.
increase; 22%
D. increase; 33%
3
HLT07 RO NRC EXAM
- 4. 203000G2.4.34 001 An event occurred on Unit 2 requiring control to be transferred to the Remote Shutdown Panel (RSDP).
o ALL Emergency Transfer Switches have been placed to the EMERGENCY Position o Subsequently, a LOCA signal is received and Reactor pressure decreases to 90 psig Which ONE of the choices below completes the following statement concerning Unit 2 RHR LPCI Injection from the RSDP?
Placing the Emergency Transfer Switches, for the RHR pump(s) controlled from the RSDP, to the EMERGENCY Position The LPCI injection path associated with the above pump(s)
A. will NOT defeat the auto start function for the pump(s);
must be MANUALLY aligned to inject into the RPV B.
will NOT defeat the auto start function for the pump(s);
will AUTOMATICALLY align to inject into the RPV C. will defeat its auto start function for the pump(s);
must be MANUALLY aligned to inject into the RPV D. will defeat its auto start function for the pump(s);
will AUTOMATICALLY align to inject into the RPV 4
HLT-07 RO NRC EXAM
- 5. 204000K4.01 001 Unit 2 is at operating at RTP when a malfunction occurs causing the following conditions:
o RWCU HX room temperature and pump room temperatures peaked at 125°F o RWCU differential flow reached 60 gpm for 30 seconds then went to 0 gpm (indicated) o Non-Regenerative HX (NRHX) outlet temperature peaked at 125°F o
2W RWCU pump cooling water temperature peaked at 145°F o The 2W RWCU pump tripped Based on these conditions, which ONE of the choices below is the reason the2B RWCU pump tripped?
The 2B RWCU pump tripped because of high A. differential flow B. pump room temperature C. pump cooling water temperature D. Non-Regenerative HX (NRHX) outlet temperature 5
HLT-07 RO NRC EXAM
- 6. 205000K5.02 001 Unit 2 is shutdown with the following conditions:
o A ioop of RHR is in Shutdown Cooling (SDC) o 2E1 1-F008, SDC Suction Vlv, is OPEN o 2E1 1-F009, SDC Suction Vlv, is OPEN o 2E1 1-FO15A, RHR Inbd Inj Vlv, is OPEN o Reactor pressure is 125 psig and steady o Subsequently, 2E1 1-F048A, Hx Bypass valve, fails full OPEN and cannot be re-closed o Reactor pressure starts increasing at 1 psig/minute Without any operator actions and based on the above conditions, which ONE of the choices below completes the following statements?
When Reactor pressure reaches 140 psig, RHR Valves, will be CLOSED.
The RHR pumps receive a trip signal as a result of these valve closures.
A. 2E1 1-F008 and 2E1 l-F009 (ONLY);
will B.
2E1 1-F008 and 2E1 1-F009 (ONLY);
will NOT C. 2E11-F008, 2E11-F009 and 2E11-FO15A; will D. 2E11-F008, 2E11-F009 and 2E11-FO15A; will NOT 6
HLT-07 RO NRC EXAM
- 7. 206000K5.06 001 The Unit 2 Shift Supervisor has established operation at the Remote Shutdown Panel due to Control Room evacuation.
Currently Unit 2 reactor water level is -30 inches and reactor pressure is 1000 psig.
The HPCI system is operating with the following parameters:
o HPCI turbine speed = 3000 rpm o HPCI pump discharge pressure = 780 psig An operator makes an adjustment locally, which results in the HPCI turbine speed increasing to 5050rpm.
After the operator makes the adjustment, which ONE of the choices below completes the following statement?
The operator is using a to monitor HPCI turbine speed and the HPCI turbine have tripped.
A. locally mounted gauge; should B. locally mounted gauge; should NOT C.
strobe tachometer; should D. strobe tachometer; should NOT 7
HLT-07 RO NRC EXAM
- 8. 209001K1.12 001 A transient has occurred on Unit 2.
At 10:00 the following conditions exist:
o Drywell pressure 0.7 psig o Reactor water level
-95 inches decreasing 2 inches/minute o Reactor pressure 500 psig decreasing 2 psig/minute o 2A Core Spray pump is MANUALLY started Which ONE of the choices below completes the following statements?
At 10:01, the number of CS/RHR Pump Room Coolers operating is At 10:05, CS/RHR Pump Room Coolers will be operating.
A. zero (0);
ONLY two (2)
B.
zero (0);
ALL four (4)
C. two (2);
ONLY two (2)
D. two(2);
ALL four (4) 8
HLT-07 RO NRC EXAM
- 9. 209001K5.O1 001 A LOCA is in progress. The 2A Core Spray pump is injecting at 1000 gpm to maintain RPV water level above the top of active fuel.
Which ONE of the following would be an indication that the 2A Core Spray pump is experiencing cavitation?
A. The motor amps are steadily increasing.
B. The pump trips due to low suction pressure.
C. The minimum flow valve intermittently opens and closes.
D. The pump discharge pressure steadily increases as flow decreases.
9
HLT-07 RO NRC EXAM
- 10. 211000K4.02 001 Unit 2 is operating at 100% RTP with the 2B SBLC pump inoperable.
o The 2B SBLC pump breaker is Danger Tagged OPEN The crew has just been tasked with performing 34SV-C41-002-2, Standby Liquid Control Pump Operability Test, for the 2A SBLC pump.
Which ONE of the choices below completes the following statement concerning the Squib Valve Continuity lights on the 2H11-P603 panel and the RWCU System?
After the operator locally starts the 2A SBLC Pump, A. two (2) Squib Valve Continuity lights on the 2H1 l-P603 panel will be ILLUMiNATED and the RWCU System WiLL isolate B.
two (2) Squib Valve Continuity lights on the 2H1 1-P603 panel will be ILLUMINATED and the RWCU System WILL NOT isolate C. ONLY one (1) Squib Valve Continuity light on the 2H11-P603 panel will be ILLUMINATED and the RWCU System WILL isolate D. ONLY one (1) Squib Valve Continuity light on the 2H1 1-P603 panel will be ILLUMINATED and the RWCU System WILL NOT isolate 10
HLT-07 RO NRC EXAM
- 11. 212000A2.08 001 Unit 2 is in Mode 4 with RHR Shutdown Cooling in service.
An event occurs causing RWL to decrease and results in the following:
o 2C32-R606A-C GEMAC
(+) 2 inches (LOWEST level reached) o Subsequently, the NPO recovers RWL to (+) 20 inches Which ONE of the choices below completes the following statements?
During this event, the RPS RWL Scram Setpoint EXCEEDED.
34AB-E1 1-001-2, Loss Of Shutdown Cooling, REQUIRED to be entered.
A. was; is NOT B.
was; is C.
was NOT; is NOT D. was NOT; is 11
HLT07 RO NRC EXAM
Which ONE of the choices below describes the affect of losing RPS Bus 2A on the LPRMs?
A. ONLY Half of the LPRMs inputs associated with APRMs 2B & 2D are still VALID.
B. ONLY Half of the LPRMs inputs associated with APRMs 2A & 2C are still VALID.
C. NONE of the LPRMs inputs associated with APRMs 2B & 2D are still VALID.
D. ALL of the LPRMs inputs associated with APRMs 2A & 2C are still VALID.
12
HLT-07 RO NRC EXAM
- 13. 215002K6.04 001 Unit 2 is operating at 100% power with a centrally located control rod selected.
o The operator bypasses APRM channel A due to bad CPU Which ONE of the choices below identifies the effect this action will have on the RBM A channel?
RBM A will automatically use the A.
C APRM channel to monitor the neutron flux in the locality of the selected rod B.
C APRM channel to determine one of the three upscale setpoints C.
D APRM channel to monitor the neutron flux in the locality of the selected rod D.
D APRM channel to determine one of the three upscale setpoints 13
HLT-07 RO NRC EXAM
- 14. 215003A1.06 001 Unit 1 is in Startup with IRM lA! indicating 50 on Range 4. ALL other IRMs are reading Mid-scale on their respective range.
The NPO momentarily positions IRM IA Range switch to Range 3 and then back to Range 4.
Which ONE of the choices below completes the following statements?
With IRM lA on Range 3, and 603-238, ROD OUT BLOCK, will be in the alarm condition.
Once IRM lA is returned to Range 4, the IRM lA will be EXTINGUISHED.
A. annunciators 603-221, IRM UPSCALE, 603-203, IRM BUS A UPSCALE TRIP OR INOP; Drawer UPSC amber light on 1H1 1P606 B.
annunciators 603-221, IRM UPSCALE, 603-203, IRM BUS A UPSCALE TRIP OR INOP; UPSC amber light on the benchboard (horizontal portion) of lHl l-P603 C. ONLY annunciators 603-221, IRM UPSCALE; UPSC amber light on the benchboard (horizontal portion) of 1H1 1-P603 D. ONLY annunciators 603-221, IRM UPSCALE; Drawer UPSC amber light on 1H1 1-P606 14
HLT-07 RO NRC EXAM
- 15. 215004K6,02 001 Unit 1 is starting up.
o Reactor Water Level
(+) 37 Inches o The reactor is critical o IRMs are all on-scale on Range 3 A loss of 24/48 VDC IB, 1R25-S016, occurs.
Which ONE of the choices below will occur as a result of this power loss?
Source Range Monitor (SRM)__________ indicator will fail A.
iC; as is B.
iC; downscale C.
lD; as is D.
iD; downscale 15
HLT07 RO NRC EXAM
- 16. 215005A1.01 001 Unit 2 is at 9% RTP when the following occurs:
o LPRM 44-21A fails UPSCALE (Inputs into APRM 2Dh) o Subsequently, Operations bypasses the failed LPRM The following represents the status of APRM 2D fiçr LPRM 44-21A is bypassed:
o Number of Level D LPRM Inputs
... 6 o Number of Level C LPRM Inputs
... 4 o Number of Level B LPRM Inputs
... 5 o Number of Level A LPRM Inputs
... 2 Which ONE of the choices below completes the following statements?
When LPRM 44-21A failed upscale, APRM 2D power indication After LPRM 44-21A is bypassed, APRM 2D is inoperable because there are too few A. remained the same; total LPRM inputs B.
remained the same; LPRM inputs per level C. increased; total LPRM inputs D. increased; LPRM inputs per level 16
HLT-07 RO NRC EXAM
- 17. 215005A4.03 001 Unit 1 is operating at 100% RTP when 603-210-1, APRM/OPRM TRIP, alarm comes in and then immediately clears due to a momentary failure of one (1) APRM.
Which ONE of the choices below completes the following statements?
With the above condition, a RPS Half Scram signal have been received.
If the APRM is bypassed, the TOTAL number of 2/4 Logic modules (Voters) that will have the associated APRMs bypass light ILLUMINATED is A. would; two (2)
B. would; four (4)
C. would NOT; two (2)
D. would NOT; four (4) 17
HLT-07 RO NRC EXAM
- 18. 216000A4.01 001 A transient has occurred on Unit 2 resulting in Reactor Water Level (RWL) decreasing.
A RWL Milestone is established at -175 inches.
Subsequently, an Emergency Depress is performed.
A Normal RWL band of (+) 32 to (+) 42 inches is established.
Which ONE of the choices below completes the following statement for determining ACCURATE RWL?
To determine when the -175 inch Milestone is reached, the NPO will be monitoring RWL at panel 2H1 1-to determine when RWL is in its Normal band.
A. P601 and then transition to the 2H1 1-P603 panel B. P601 and continue monitoring at the 2H1 1-P601 panel C. P602 and then transition to the 2H1 1-P603 panel D. P602 and continue monitoring at the 2H1 1-P602 panel 18
HLT-07 RO NRC EXAM
- 19. 217000K2.04 001 Which ONE of the choices below is the power supply to RCIC Barometric Condenser Vacuum Pump, 2E5 1 -C002-2?
A.
1251250V DC SWGR 2C, 2R22-S018 B.
125/250V DC SWGR 2D, 2R22-S019 C.
250V DC MCC 2A, Reactor Building Feeder, 2R24-S021 D.
125V DC DIST. CAB. 2D, ESS DIV I, 2R25-S 129 19
HLT-07 RO NRC EXAM
- 20. 218000K1.04 001 Unit 2 has experienced a Loss of Offsite Power (LOSP).
The following conditions existed at 15:00:
o ALL low pressure ECCS pumps have been manually started o RPV Pressure 860 psig controlled by LLS o RWL
-97 inches, decreasing at 2 inches/minute o Drywell Pressure 1.0 psig, increasing at 0.3 psi/minute o ADS Inhibit Switches Normal position Given these trends, which ONE of the following predicts the EARLIEST time that the ADS valves will have automatically OPENED?
A.
15:03 B.
15:06 C.
15:13 D.
15:15 20
HLT-07 RO NRC EXAM
- 21. 223001A3.04 001 A LOCA has occurred on Unit 2 resulting in Drywell pressure increasing to 20 psig.
Subsequently, Drywell Sprays are placed in service and Drywell pressure is reduced to 1.0 psig.
Which ONE of the choices below completes the following statements?
The Drywell I Torus Vacuum Breakers will automatically cycle while Drywell pressure is Monitoring for proper automatic operation of the Drywell / Torus Vacuum Breakers can be performed from A. increasing to 20 psig; panel 2H1 1-P602 AND locally at panel 2T48-P001 B. increasing to 20 psig; panel 2H 11 -P602 ONLY C. decreasing to 1.0 psig; panel 2H1 1-P602 AND locally at panel 2T48-P001 D. decreasing to 1.Opsig; panel 2H1 1-P602 ONLY 21
HLT-07 RO NRC EXAM
- 22. 223002K3.10 001 Unit 2 is at 100% power and the T 2A Reactor Protection System (RPS) M/G Set trips.
Which ONE of the choices below completes the following statement?
After RPS M/G Set 2A trips, the operating Reactor Water Cleanup pump A. will AUTOMATICALLY trip due to suction valve closure B.
will AUTOMATICALLY trip due to low suction pressure C. must be MANUALLY tripped due to suction valve closure D. must be MANUALLY tripped due to low suction pressure 22
HLT-07 RO NRC EXAM
- 23. 233000K2.02 001 Unit 1 is in Mode 4 with 1BI and iD Residual Heat Removal (RHR) pumps running in Shutdown Cooling with Fuel Pool Cooling Assist in service.
o A condition develops on Emergency Bus 416OVAC iF which causes it to de-energize Which ONE of the following predicts the status of the IB and iD RHR pumps?
A.
lB RHR Pump has stopped iD RHR Pump has stopped B.
lB RHR Pump is running iD RHR Pump has stopped C.
iB RHR Pump has stopped iD RHR Pump is running D.
lB RHR Pump is running iD RHR Pump is running 23
HLT-07 RO NRC EXAM
- 24. 234000K5.02 001 Unit 2 is in a refueling outage with the following conditions.
o Rx Mode Switch Locked in the REFUEL position o Control rods One control rod is fully WITHDRAWN o Main Fuel Grapple Lowered, but verified to be able to clear the cattle chute by 3 ft.
(Empty grapple move) o NO rod is selected The Refuel Bridge is over the Spent Fuel Pool and is moving toward the core to pick up the fuel bundle at position 17-42.
Which ONE of the following choices completes the following statements concerning how the refueling interlocks will respond?
With these conditions, the Refuel Bridge move to the intended core location.
When the Refuel Bridge stops, if the Grapple Raise/Lower switch is placed in the LOWER position, the Main Grapple lower.
A. will; will B.
will; will NOT C.
will NOT; will D. will NOT; will NOT 24
HLT-07 RO NRC EXAM
- 25. 239002A3.02 001 Unit 2 experienced a Group One from 100% power.
Eight (8) SRV amber lights are illuminated and B SRV is currently open with reactor pressure at 875 psig.
Which ONE of the choices below is the LOWEST reactor pressure which must have been reached to cause these conditions?
A.
1080 psig B.
ll2Opsig C.
ll3Opsig D. ll4Opsig 25
HLT-07 RO NRC EXAM
- 26. 241000A2.23 001 Unit 2 is operating at 23% reactor power.
The Main Turbine/Generator has just been tied to the grid.
Subsequently, 650-136, Vibration Alarm, is received.
Investigation reveals that Turbine Eccentricity is 3 mils and Vibration is 14 mils and has been at these values for the last 2 minutes.
Which ONE of the choices below completes the following statements?
JAW 34S0-N30-0O1-2, Main Turbine Operation, the is required to be used for monitoring Eccentricity on the Main Turbine.
To CLOSE the Main Turbine Stop Valves, the NPO will on 2H1 1-P650 panel.
A. 2N32-R609, TURBINE METAL EXPANSION/TEMP recorder; select the Close Valves button on the Control -Speed Screen B. 2N32-R609, TURBINE METAL EXPANSION/TEMP recorder; depress the Turbine Trip pushbuttons C. Human Machine Interface (HMI) Screen; select the Close Valves button on the Control -Speed Screen D. Human Machine Interface (HMI) Screen; depress the Turbine Trip pushbuttons 26
- 27. 259002A4.07 001 HLT-07 RU NRC EXAM Unit 2 is at 60% power removing the B RFPT from service with the following conditions:
o A RFPT is in Auto, controlled from the FW Master Controller 2C32-R600 o B RFPT is in Manual, as indicated below on M/A station, 2C32-R6O1B o NO other switches have been repositioned With the B RFPT controller in Manual, which ONE of the choices below completes the following statements?
The B RFPT will be used to lower B RFPT flow.
Depressing the B RFPT PF key will A. speed setter switch; lower the B RFPT setpoint by 4 inches B.
speed setter switch; change the Green bar display to Controller Output C. output lever; lower the B RFPT setpoint by 4 inches D. output lever; change the Green bar display to Controller Output RFP B M?A STATION 27
HLT-07 RO NRC EXAM
- 28. 261000A1.01 001 Unit 2 is operating at 100% RTP.
At 10:00, an event occurs resulting in Unit 2 Drywell pressure increasing to and stabilizing at 2.5 psig.
Which ONE of the choices below completes the following statements?
At 10:15, with NO operator actions, the TOTAL amount of Unit 2 SBGT System flow going to the Main Stack is expected to be between SCFM.
Unit 2 SBGT flow can be monitored on panels 2H11-P654 &
A. 3000 and 4000; 2H1 1-P657 B.
3000 and4000; 2H1 1-P700 C.
6000 and 8000; 2H1 1-P657 D. 6000 and 8000; 2H1 1-P700 28
HLT-07 RO NRC EXAM
- 29. 261000K3.02 001 Unit 2 is operating at 100% RTP with the following conditions:
o Unit 2 Refueling Hatch installed o 2A Standby Gas Treatment (SBGT) Fan is Danger Tagged out for maintenance Subsequently, the following occurs at the listed times:
10:00 A RWCU System break in the Unit 2 Reactor Building 10:05 2Dl 1-K609A-D, Rx. Bldg. Contaminated Area Radiation increase to 20 mr/hr 10:10 The Supply breaker for 2R24-S012, 600V MCC, trips OPEN With NO operator action, which ONE of the choices below predicts how the Off-site Radioactive Release Rates will be affected?
At 10:08, the Reactor Building Stack release rate will be than at 10:04.
At 10:15, the Main Stack release rate will be at 10:08.
A. higher; approximately the same as B.
higher; lower than C.
lower; approximately the same as D. lower; lower than 29
HLT-07 RO NRC EXAM
- 30. 26200 1G2.4.47 001 WHITE LIGHTS A. running, but is NOT tied to 4160 VAC 1E bus B. running and IS tied to 4160 VAC 1E bus C. NOT running, but can be manually started from the control room D. NOT running and can NOT be started from the control room A LOSP has occurred on Unit 1.
The operator notices the following indications on panel 1H1 1-P652 for 416OVAC 1E bus and its associated Diesel Generator (DG):
o LOSP 86 lockout TRIPPED o Normal and Alternate supply breakers OPEN o Auto Start System Operative light EXTINGUISHED BLUE LIGHTS (EXTINGUISHED)
VOLT SELECT 1
Which ONE of the choices below completes the following statement?
The DG associated with 416OVAC 1E bus is 30
HLT-07 RO NRC EXAM
- 31. 262002A3.01 001 Unit 2 is at 100% power when the following occurs:
o Loss of OffSite Power (LOSP) o !2A 1
? EDG fails to start Which ONE of the below choices completes the following statements?
After the LOSP, the Unit 2 Vital AC Bus will INITIALLY receive power from Three (3) hours later and without any operator actions, the Vital AC Bus automatically transfer to ANOTHER power source.
A. the Vital AC batteries; will B. the Vital AC batteries; will NOT C.
600 V Bus 2D via Vital AC battery charger; will D. 600 V Bus 2D via Vital AC battery charger; will NOT 31
HLT-07 RO NRC EXAM
- 32. 263000A2.02 001 Unit 2 is operating at 100% power, with the 2A and 2B 125/25OVDC Station Service Batteries on equalize charge.
o All Control Building Chillers and fans trip and can NOT be restored o Control Building temperatures start increasing Which ONE of the following completes both statements concerning the effect of charging the batteries with the above conditions present and any required actions to mitigate the consequences of the event?
With the above conditions, To mitigate the consequences of this event, the operator will enter A. Hydrogen concentration will rise in the battery rooms; 34AB-T41-001-2, Loss Of ECCS, MCREC Or Area Ventilation Systems and start Emergency Exhaust Fans 2Z41-C014 and 2Z41C015 B. Hydrogen concentration will rise in the battery rooms; 34SO-R42-001-2, 125 VDC AND 125/250 VDC SYSTEM, and secure all the battery chargers C. the Battery Chargers will trip when their high temperature trip setpoint is reached; 34AB-T41-001-2, Loss Of ECCS, MCREC Or Area Ventilation Systems and start Emergency Exhaust Fans 2Z41-C014 and 2Z41-C015 D. the Battery Chargers will trip when their high temperature trip setpoint is reached; 34SO-R42-001-2, 125 VDC AND 125/250 VDC SYSTEM, and secure all the battery chargers 32
HLT-07 RO NRC EXAM
- 33. 264000K4.06 001 Unit 2 is operating at 100% RTP with 34SV-R43-003-2, Diesel Generator 2C Monthly Test, in progress.
Diesel Generator 2C is loaded to 1800 kW.
Which ONE of the choices below completes the following statements concerning operation of the Speed Droop and the Load Limit knobs? (Answer each part independently of each other)
If the Speed Droop Knob on Diesel Generator 2C is slowly turned to the zero (0) position, Diesel Generator 2C shutdown.
Slowly turning the Load Limit knob on Diesel Generator 2C to the zero (0) position, A. will NOT; will completely shut off the fuel oil supply to Diesel Generator 2C B.
will NOT; will decrease the load to 0 kW and Diesel Generator 2C will continue to run C.
will; will completely shut off the fuel oil supply to Diesel Generator 2C D. will; will decrease the load to 0 kW and Diesel Generator 2C will continue to run 33
HLT-07 RO NRC EXAM
- 34. 268000A4.01 001 JAW 34SV-SUV-019-2, Surveillance Checks, and TS 3.4.4, RCS Operational LEAKAGE, which ONE of the choices below identifies the integrator used in determining UNIDENTIFIED! Leakage rate and its location?
A. Drywell Floor Drain Sump Integrator, 2G1 1-K601, located on panel 2H11-P602.
B. Drywell Floor Drain Sump Integrator, 2G1 l-K601, located on panel 2H1 l-P613.
C. Drywell Equipment Drain Sump Integrator, 2G1 l-K603, located on panel 2H11-P602.
D. Drywell Equipment Drain Sump Integrator, 2G11-K603, located on panel 2H11-P613.
34
HLT-07 RO NRC EXAM
- 35. 286000G2.4.9 001 Unit 1 experiences a LOCA and LOSP with ALL Unit 1 Emergency Diesel Generators failing to start and cannot be manually started.
The following conditions exist on Unit 1:
o Reactor water level
-160 inches, decreasing 2 inches/minute o Reactor pressure 25 psig, slowly lowering 31E0-EOP-1 10-1, Alternate RPV Water Level Control, is in progress.
With the above conditions, which ONE of the choices below completes the following statements concerning Fire Water Injection into the Residual Heat Removal (RHR) System?
JAW 31E0-EOP-1 10-1, Alternate RPV Water Level Control, the Fire System can be used for RPV injection by aligning it The MAXIMUM number of Fire Pumps that can be started is A. INDIRECTLY into the RHR System via the Condensate Transfer System piping; two (2)
B. INDIRECTLY into the RHR System via the Condensate Transfer System piping; three (3)
C. DIRECTLY into the RHR System piping; two (2)
D. DIRECTLY into the RHR System piping; three (3) 35
- 36. 295001AK2.01 001 HLT-07 RO NRC EXAM Unit 2 is operating at 73% power with both Recirc Pumps operating at 70% speed when the 2A Recirc Pump trips.
After conditions stabilize, 2B21-R613, Core Plate DpIRx Core Flow, indicates as shown on Figure 1 below:
With NO operator action, which ONE of the choices below completes the following statements?
The flow through the A Loop Jet Pumps is depicted in The % Rated Core flow indicated on Figure 1 for 2B21-R613, Core Plate DpIRx Core Flow, of actual Core flow.
A. Figure 2; is an accurate indication B. Figure 2; is NOT an accurate indication C. Figure 3; is an accurate indication D. Figure 3; is NOT an accurate indication CORE PLATE dpIRX CORE FLOW 2B21-R613 A
,eire Pump 13 Recite Pump Figure 2 Coolant Flow Direct in,,
A Recite Pump 13 Recite Pump Coolant I low
Direction Figure 3 36
HLT-07 RO NRC EXAM
- 37. 295003AK1.03 001 Unit 2 is operating at 100% RTP when the following occurs on 4160V Bus 2G:
o Normal Supply Breaker trips OPEN o Alternate Supply Breaker automatically CLOSES Which ONE of the choices below completes the following statements?
The associated Diesel Generator is expected to Three (3) minutes later, PSW flow to the Turbine Building is expected to A. remain in standby; have isolated B. remain in standby; remain in service C. have automatically started; have isolated D. have automatically started; remain in service 37
HLT-07 RO NRC EXAM
- 38. 295004G2.4.11 001 Unit 2 was operating at 100% power.
o A loss of 2R25-S002. 125VDC Cabinet 2B, occurs o Subsequently, a malfunction occurs causing 2B31-FO31B, Recirc 2B Discharge Valve, to inadvertently travel full CLOSED With the above conditions, which ONE of the choices below completes the following statements?
As 2B31-FO31B CLOSES, the 2B ASD A. will perform a Ramp Shutdown to zero rpm and then the 4160V Input Breaker must be manually OPENED from the Control Room B.
will perform a Ramp Shutdown to zero rpm and then the 4160V Input Breaker will trip OPEN C. 4160V Input Breaker will remain closed UNTIL it is manually OPENED LOCALLY D. 4160V Input Breaker will IMMEDIATELY trip OPEN 38
HLT-07 RO NRC EXAM
- 39. 295005AK3.06 001 Unit 2 was operating at 100% RTP when the following occurred:
o Startup Aux. Transformer (SAT) 2D de-energized o Reactor scrammed o Main Generator tripped Which ONE of the choices below describes the expected status of the 4160 VAC Station Service Buses 2A and 2B and why? (Assume NO operator actions have been taken).
4160V buses 2A and 2B are A. de-energized to prevent overloading SAT 2C B. de-energized to prevent paralleling out of synch power supplies C. energized from SAT 2C to keep the Main Condenser available D. energized from SAT 2C to keep forced Core flow available 39
HLT07 RO NRC EXAM
- 40. 295006AA1.01 001 Unit 2 is in a refueling outage.
o Reactor Mode Switch position REFUEL o SRM Shorting Links REMOVED A SRM detector failure results in the SRM 2A indication reading 5x10 5 CPS.
What is the expected status of the 2H11-P603 panel WHITE RPS Scram Group A and B lights?
RPS Scram Group A WHITE lights are expected to be RPS Scram Group B WHITE lights are expected to be A. EXTINGUISHED; EXTINGUISHED B. EXTINGUISHED; ILLUMINATED C. ILLUMINATED; EXTINGUISHED D. ILLUMINATED; ILLUMINATED 40
HLT-07 RO NRC EXAM
- 41. 295009AA1.03 001 Unit 1 is operating at 60% RTP with the following conditions:
o lB RFPT in service with lA RFPT on its turning gear o Both Recirculation Pump speeds are 65%
o lB RFP trips due to the running Condensate Booster pumps tripping o RWL lowered to -65 before the operator recovered RWL to +35 with HPCI Which ONE of the choices below describes the FINAL condition of BOTH Recirculation Pumps?
A. Running at #1 speed limiter B. Running at #2 speed limiter C. Running at #3 speed limiter D. Tripped 41
- 42. 295010G2.4.18 001 HLT-07 RO NRC EXAM The following conditions exist on Unit 2:
o Drywell temperature = 300°F o Drywell pressure 5 psig o Reactor = shutdown (all rods in) o RPV water level = 32 and steady GRAPH 8 DR{WELL SPRAY INITIArJON LIMIT FMatfl With the above plant conditions, which ONE of the choices below completes the following statements?
If Drywell Sprays are initiated, Primary Containment could The Unit 2 Primary Containment Design Temperature been exceeded.
A. fail from exceeding the capacity of the Torus-to-Drywell vacuum breakers; has B. fail from exceeding the capacity of the Torus-to-Drywell vacuum breakers; has NOT C. be de-inerted from opening the Reactor Bldg. to Torus vacuum breakers; has D. be de-inerted from opening the Reactor Bldg. to Torus vacuum breakers; has NOT OUt) WSSS raresseesa OOrssa
. rsarra rea rsssea 4flfl PSFSSSSSA
&cE_
/Ssarsrs
.. Sa SAFEj
°°r inn DW TEMP
(°F) 0 10 20 30 40 DRY WELL PRESSURE (psig) 42
HLT-07 RO NRC EXAM
- 43. 295013AK2.01 001 Unit 1 is operating at 90% power.
o A Safety Relief Valve (SRV) inadvertently opened causing Suppression Pool water temperature to increase o Suppression Pool water temperature reaches 102°F before operators are able to close the SRV Which ONE of the choices below describes the required Residual Heat Removal (RHR)
Suppression Pool Cooling alignment?
A. Place ONLY one loop of RHR in Suppression Pool cooling, and the RHR heat exchanger IS required to be isolated prior to starting the RHR pump.
B. Place ONLY one loop of RHR in Suppression Pool cooling, and the RHR heat exchanger IS NOT required to be isolated prior to starting the RHR pump.
C. Place ALL available RHR loops in Suppression Pool cooling, and the RHR heat exchanger IS required to be isolated prior to starting the RHR pumps.
D. Place ALL available RHR loops in Suppression Pool cooling, and the RHR heat exchanger IS NOT required to be isolated prior to starting the RHR pumps.
43
HLT-07 RO NRC EXAM
- 44. 295016AA2.07 001 The control room has been abandoned and 31RS-OPS-OO1-2, Shutdown From Outside Control Room, is being implemented.
The SS has ordered Torus Sprays to be placed in service.
Which ONE of the choices below completes the following statements?
Torus pressure can be determined using Torus Sprays can be initiated from the Remote Shutdown Panel, 2C82-POO1, ONLY in the A. SPDSintheTSC; B Loop B. SPDSintheTSC; A Loop C.
a permanently mounted gauge on the 87 level of the Reactor Building; B Loop D. a permanently mounted gauge on the 87 level of the Reactor Building; A Loop 44
HLT-07 RO NRC EXAM
- 45. 295018AK3.06 001 Unit 2 is operating at 5% power when two (2) RBCCW pumps fail and will NOT run.
The following exists:
o PSW/RBCCW Hx dP increases o The SS directs the SO to LOWER PSW/RBCCW Hx dP to 30 psid by throttling 2P41-F491, PSW Outlet Valve From RBCCW Hx JAW 34SO-P42-O0l-2, Reactor Building Closed Cooling Water System, which ONE of the following completes these statements?
To LOWER the PSW/RBCCW Hx dP, the SO will throttle 2P41-F491 in the direction.
The setpoint for 650-23 8, HX PSW/RBCCW DIFF PRESS LOW, is A. CLOSE; 7 psid B. CLOSE; 20 psid C. OPEN; 7 psid D. OPEN; 20 psid 45
HLT-07 RO NRC EXAM
- 46. 295019AA2.02 001 Unit 2 is operating at 100% power with 2P52-F565, Rx Bldg Inst N2 To Non-mt Air El 185 Isol Vlv, tagged in the closed position when the following occurs:
o Unit 2 experiences a loss of ALL Unit 2 Station Service Air Compressors o Instrument and Service Air pressure drops to zero (0) psig Which ONE of the choices below completes BOTH statements for the following ventilation dampers as their respective air pressure decreases to zero (0) psig?
2T46-FOO1A, SBGT A Fltr Inlet From Rx Bldg, valve will 2T41-F044A, Rx Bldg Inboard Isol Dmprs Inaccessible Areas Exhaust Fans Disch, valve will A. travel open; remain open B. travel open; travel closed C. remain closed; remain open D. remain closed; travel closed 46
HLT-07 RO NRC EXAM
- 47. 295020AK1.05 001 Unit 2 is operating at 100% power.
o Nitrogen (N
- 2) is being added to the Unit 2 Drywell (DW) from the Unit 1 N2 Storage Tank 34SO-T48-O022, Containment Atmosphere Control and Dilution System section 7.3.1, Alternate Primary Containment Nitrogen Makeup From CAD loop A, Unit 1 or Unit 2 N2 Storage Tank is being used to add the N 2.
o 2T48-F1 13, Nitrogen to DW isolation valve is OPEN o 2T48-F1 14, Nitrogen to DW isolation valve is OPEN o DW venting using Standby Gas Treatment is in progress o A fault in 2C71-P001, RPS Power Dist Panel results in a loss of the2A Reactor Protection System (RPS) bus o It will take 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore the 2A RPS bus If the operator stationed at the 2H1 1-P657 panel does NOT take any action, which ONE of the following describes the operational implications for the DW?
A. N2 addition to the DW will continue and a loss of DW cooling will eventually occur due to high DW pressure.
B. N2 addition to the DW will continue and DW cooling will remain in operation indefinitely.
C. N2 addition to the DW will automatically isolate and DW cooling will remain in operation indefinitely.
D. N2 addition to the DW will automatically isolate and a simultaneous loss of DW cooling will occur.
47
HLT-07 RO NRC EXAM
- 48. 295021G2.2.40 001 Unit 2 is shutdown.
BOTH Loops of RHR are operating in Parallel Shutdown Cooling (SDC) operation.
The following conditons exist:
o Rx pressure 34 psig o BOTH Rx Recirculation pumps Off o 2C RHR pump Danger Tagged out of service o 2D RHR pump Danger Tagged out of service Subsequently, an equipment malfunction causes 2E1 1-FOO6B, Shutdown Cooling Vlv, to CLOSE and CANNOT be reopened.
Which ONE of the choices below completes the following statements?
JAW Tech Spec LCO 3.4.7, Residual Heat Removal (RHR) Shutdown Cooling System -
Hot Shutdown, the MINiMUM number of REQUIRED RHR SDC Subsystems With 2E1 l-FOO6B closed, the 2B RHR pump will A.
is met; trip B.
is met; continue to run C.
is NOT met; trip D. is NOT met; continue to run 48
HLT-07 RO NRC EXAM
- 49. 295023AA1.04 001 A refueling accident occurs on Unit 2.
The following Area Radiation Monitors (ARM) red Trip Lights illuminate at Control Room ARM Panel 2D21-P600:
o 2D21-K6O1A, Reactor head laydown area o 2D21-K6O1M, Spent Fuel Pool & New Storage Which ONE of the following predicts how the Main Control Room Environmental Control (MCREC) system is affected and operation of the ARMs?
With the above conditions, the MCREC system will After mitigating actions are completed AND the above ARMs are indicating below their Trip setpoints, the ARM red TRIP lights reset.
A. remain in the Normal Mode; must be manually B. remain in the Normal Mode; will automatically C.
align to the Pressurization Mode; must be manually D. align to the Pressurization Mode; will automatically 49
HLT-07 RO NRC EXAM
- 50. 295024EA2.06 001 A steam line break inside containment has occurred on Unit 2.
o Drywell pressure is 10.5 psig and slowly increasing o Torus pressure is 10 psig and slowly increasing o Neither Drywell or Torus sprays have been initiated Which ONE of the following describes the effect of the steam line break on Torus water temperature and requires Primary Containment sprays with these conditions?
The Torus water temperature will heat up With the above conditions and at this time, Sprays are REQUIRED to be placed in service.
A. uniformly throughout the Torus due to the design of the downcomers; BOTH Drywell and Torus B. uniformly throughout the Torus due to the design of the downcomers; ONLY Torus C. directly under the area of the DW leak due to the energy being distributed directly to the Torus water in that area; BOTH Drywell and Torus D. directly under the area of the DW leak due to the energy being distributed directly to the Torus water in that area; ONLY Torus 50
HLT-07 RO NRC EXAM
- 51. 295025G2.1.27 001 Which ONE of the choices below completes the following statements?
JAW TS 3.4.3. Safety/Relief Valves (SIRVs), the SRV Safety function requires a MINIMUM of SRVs to be operable.
if reactor pressure reaches 1200 psig, the Reactor Coolant System DESIGN pressure have been exceeded.
A.
10; will B.
10; will NOT C.5; will D.5; will NOT 51
HLT-07 RO NRC EXAM
- 52. 295026EK3.04 001 An ATWS is in progress on Unit 2 with 31E0-EOP-01 1-2, RCA RPV Control (ATWS),
flowchart in progress.
Which ONE of the choices below completes the following statements?
JAW EOP definitions the reason SBLC is injected before exceeding the B11T Curve (Graph 5) is to ensure that Hot Shutdown Boron Weight is injected before exceeding the At 10% RTP, the LOWEST listed Torus temperature at which the BuT Curve (Graph 5) will be EXCEEDED is Reference Provided A. Primary Containment Pressure Limit; 120°F B. Primary Containment Pressure Limit; 125°F; C. Heat Capacity Temperature Limit; 120°F D. Heat Capacity Temperature Limit; 125°F; 52
HLT-07 RO NRC EXAM
- 53. 295028EA1.03 001 Unit 2 was at 100% power when a Steam Line break occurred inside the Drywell (DW).
The following conditions now exist:
o Drywell Pressure 8 psig o Bulk Average Drywell Temperature 265°F Which ONE of the choices below completes the following statement?
JAW 3 1EO-EOP-100-2, Miscellaneous Emergency Overrides, the2A DW Chiller A. is NOT allowed to be restarted, because this DW temperature is above the allowed winding temperature for restart of the DW Cooling Fan Motors B.
is NOT allowed to be restarted, because at this DW temperature the potential for a rupture in the DW coolers exist C.
is allowed to be restarted. The operator must first place the LOCA override switch to BYPASS and then reset the 86 Lockout relay at the DW Chiller breaker D. is allowed to be restarted. The operator must first reset the 86 Lockout relay at the DW Chiller breaker and then place the LOCA override switch to BYPASS 53
HLT-07 RO NRC EXAM
- 54. 295030EK1.02 001 Unit 2 is operating at 100% power when a Loss of Coolant Accident occurs.
The High Pressure Coolant Injection (HPCI) system is being used to control RPV water level.
o HPCI flow rate 4,000 gpm o RWL
-60 and increasing at 20 per minute o Torus level 135 inches o Torus temperature 190°F o Torus Pressure 4psig With the above conditions, SELECT the HIGHEST listed flowrate that maintains HPCI operation in the ACCEPTABLE Region of the HPCI NPSH limits?
Reference Provided A. 3,750 gpm B.
3,250 gpm C.
2,750 gpm D. 2,250 gpm 54
HLT-07 RO NRC EXAM
- 55. 295031EA1.02 001 Unit 2 was operating at 100% power, when an event occurred resulting in the following:
o Reactor water level: -45 (lowest level reached) and increasing 45 inches/minute o Reactor pressure: 900 psig and slowly decreasing o Drywell pressure: 0.8 psig and steady o Both CRD pumps tripped and can NOT be started Which ONE of the choices below completes the following statement?
Based on these conditions, with NO additional operator actions, one (1) minute later ONLY will have indication of flow to the reactor vessel.
A. HPCI and RCIC B. the Reactor Feedpumps C.
HPCI, RCIC and the Reactor Feedpumps D. RCIC and the Reactor Feedpumps 55
HLT-07 RO NRC EXAM
- 56. 295032EA1.05 001 Following a transient on Unit 2, current plant conditions are:
o Reactor water level is -20 inches, rising 5 inches/minute o Reactor pressure is 750 psig, slowly lowering Subsequently the following conditions occur:
o RCIC Room Area Cooler Temperature is 160°F o HPCI Room Area Cooler Temperature is 175°F o RCIC is injecting at 400 gpm o HPCI is injecting at 600 gpm Which ONE of the choices below completes the following statements?
With the above conditions, REQUIRED to be MANUALLY isolated.
A. ONLY the HPCI System is B. ONLY the RCIC System is C. BOTH HPCI and RCIC Systems are D. NEITHER HPCI nor RCIC Systems are 56
HLT-07 RO NRC EXAM
- 57. 295035EA2.02 001 Unit 2 is operating at 100% power with the following:
o 2T41C001A, Rx. Bldg Supply Fan, in service with 5,300 cfm flow o 2T41-COO7A, Rx Bldg Vent Exhaust Fan, in service with 6,500 cfm flow o 2T41-COO7B, Rx Bldg Vent Exhaust Fan, is tagged out Subsequently, 2T41-COO7A, Rx Bldg Vent Exhaust Fan, Trips.
With NO operator action, which ONE of the choices below completes the following statements?
After 2T4l-COO7A trips, the Rx. Bldg SUPPLY Fan flow will After 2T41C007A trips, the Offsite release rate from the Rx. Bldg Stack will A. remain at 5,300 cfm; decrease to zero (0) cpm because NO Exhaust fans are discharging to the Rx. Bldg. Stack B. remain at 5,300 cfm; decrease but remain greater than zero (0) cpm since some Exhaust fans are still discharging to the Rx. Bldg. Stack C. decrease to zero (0) cfm; decrease to zero (0) cpm because NO Exhaust fans are discharging to the Rx. Bldg. Stack D. decrease to zero (0) cfm; decrease but remain greater than zero (0) cpm since some Exhaust fans are still discharging to the Rx. Bldg. Stack 57
HLT-07 RO NRC EXAM
- 58. 295037EK2.01 001 Unit 2 was at 84% RTP when it is discovered that the Alternate Rod Insertion (ART) System will NOT perform its intended function.
Subsequently, an auto-scram signal was received.
The OATC inserted a manual scram and performed RC-1.
The following conditions currently exist:
o Reactor power is 35% RTP o The 8 white RPS Scram Group lights on 2H1 l-P603 are illuminated o Full core display blue lights are ALL extinguished With the above conditions and JAW 31E0-EOP-103-2, EOP Control Rod Insertion Methods, INDEPENDENTLY EVALUATE each of the following control rod insertion methods to determine if they will be an effective method for control rod insertion?
Placing the RPS Test Trip Logic Switches to TRIP be effective.
Venting the Scram Air Header be effective.
A. will; will B.
will; will NOT C. will NOT; will D. will NOT; will NOT 58
HLT-07 RO NRC EXAM
- 59. 295038EK1.02 001 An event has ocurred at Plant Hatch with a potential radiation release to the public.
Which ONE of the choices below completes the following statements?
The NPO will determine Projected Offsite dose using If an emergency is declared due to the high Offsite release rate, the INITIAL emergency notification to State and Local Officials is REQUIRED within a MAXIMUM of from when the emergency is declared.
A. 73EP-EIP-015-O, Offsite Dose Assessment; 15 minutes B. 73EP-EIP-O 15-0, Offsite Dose Assessment; 30 minutes C. 73EP-EIP-018-0, Prompt Offsite Dose Assessment; 15 minutes D. 73EP-EIP-018-0, Prompt Offsite Dose Assessment; 30 minutes 59
HLT-07 RO NRC EXAM
- 60. 300000K 1.02 001 Unit 2 is at 100% power with the following conditions:
o A Service Air Header break has occured o The break is greater than the capacity of the Service Air Compressors Which ONE of the choices below completes the following statements as Service Air pressure decreases?
The isolation setpoint for 2P51-F017, Turbine Building Service Air Isolation Valve, is If 2P51-F017 fails to isolate, CRD Flow Control Valves, 2C11-FOO2A & B lose pneumatic supply.
A. 70 psig; will B.
70 psig; will NOT C.
50 psig; will D. 50 psig; will NOT 60
HLT-07 RO NRC EXAM
- 61. 300000K6.04 001 Unit 2 is operating at 100% RTP with the 2P51-CO01C, Station Service Air Compressor (SSAC), in service and 2P51-COO1B, SSAC, in the Automatic Mode.
o 2P51-COOIC, SSAC, trips.
If NO operator action is taken, which ONE of the choices below completes the following statements?
The setpoint at which 2P51-COO1B, SSAC, will Automatically Start & Load is If the 2P51-COO1B, SSAC fails to Start & Load, the Outboard MSIVs (2B21-F028A-D),
are expected to A.
100 psig; remain open B.
100 psig; drift closed C.
107 psig; remain open D.
107 psig; drift closed 61
HLT-07 RO NRC EXAM
- 62. 400000K2.02 001 Unit 1 is at 100% power when the following annunciators alarm:
o 600V BUS 1D BREAKER TRIPPED, 652-318 o 600V BUS 1D UNDERVOLTAGE, 652-323 Which ONE of the following lists two components that have lost power?
A. RBCCW Pump A; RBCCW Drywell Outlet Isolation Valve, 1P42-F052 B. RBCCWPumpA; RWCU Inboard Suction Isolation Valve, 1G31-F001 C. RBCCWPumpB; RBCCW Drywell Outlet Isolation Valve, 1 P42-F052 D. RBCCWPumpB; RWCU Inboard Suction Isolation Valve, 1G3 1-FOOl 62
HLT-07 RO NRC EXAM
- 63. 500000EK3.07 001 Unit 1 has experienced an accident that results in these Primary Containment parameters:
o Hydrogen concentration.... 8%
o Oxygen concentration 7%
o Drywell (DW) pressure.... 14 psig and slowly increasing o Torus level
>300 inches With the above conditions and JAW 31E0-PCG-001-1, Primary Containment Gas Control chart, which ONE of the choices below completes the following statements?
The operator is required to vent the the containment atmosphere.
Placing Torus Sprays in service allowed.
A. DW to reduce the flammability of; is B.
DW to reduce the flammability of; is NOT C. Torus to reduce the flammability and scrub; is D. Torus to reduce the flammability and scrub; is NOT 63
HLT-07 RO NRC EXAM
- 64. 600000AK1.02 001 A fire is reported on Unit 1, in the lB Diesel Generator Room.
Which ONE of the choices below is the fire suppression system that is in this room?
A. Automatically actuated Carbon Dioxide System with a manual backup B. Automatically actuated Halon System with a manual backup C. ONLY a manually actuated Carbon Dioxide System D. ONLY a manually actuated Halon System 64
HLT-07 RO NRC EXAM
- 65. 700000AK2.07 001 BOTH units are operating at 100% power.
The Northern Control Center has notified the control room crews that 230 KV Bus voltage cannot be maintained above the normal minimum voltage.
Current 4160VAC Emergency Bus voltages are 3800 VAC.
Which ONE of the choices below completes the following statements?
To RAISE reactive load (VARS) from the HMI Screen, the operator will select lAW 34AB-S 11-001-0, Operation With Degraded System Voltage, if after 30 minutes the 4160VAC Emergency Bus voltages have not changed, a TOTAL of__________ 4160VAC Emergency Buses will be transferred to their respective Diesel Generator.
A. EX2100 then REGULATOR ADJUST and depress RAISE; two (2)
B. EX2 100 then REGULATOR ADJUST and depress RAISE; four (4)
C. PSI-LOAD then LOAD SET and depress RAISE; two (2)
D. PSI-LOAD then LOAD SET and depress RAISE; four (4) 65
HLT-07 RO NRC EXAM
- 66. G2.1.2 001 Unit 2 experiences a Loss of ALL High pressure feed.
o LPCI and Core Spray (CS) automatically initiate o RWL is being controlled by the OATC using LPCI and CS RWL is recovered to its normal band and the OATC is ready to depress the auto initiation signal reset pushbutton for RHR.
JAW 31G0-OPS-021-O, Manipulation Of Controls And Equipment, which ONE of the choices below completes the following statement?
The does NOT have the AUTHORiTY to procedurally authorize resetting the LPCI initiation signal under these conditions.
NOTE: Operator At The Controls = OATC; Balance Of Plant = BOP A. Shift Manager B. OATConUnit2 C. BOP NPO on Unit 2 D. Extra NPO on Unit 2 66
HLT-07 RO NRC EXAM
- 67. G2.1.21 001 Southern Nuclear Operating Company SOUTHERN Management Conduct of Operations Version 8.0 Nuclear I
I NMP-OS-007 COMPANY Procedure Page 1 of 51 Peer Team ChampionlProcedure Owner:
David R,Vineyard! Fleet Operations Manager! Corporate (Print: Name / Title I Site)
Original Signed by David Vineyard (Peer Team Champion/Procedure Owners Approval Signature)
/
12/08/2011 (Approval Date)
Effective Dates:
CATEGORY SECTIONS Continuous:
NONE
Reference:
NONE Information:
ALL Based on the above cover sheet, which ONE of the choices below completes the following statements?
JAW NMP-AP-001, Development and Control of Southern Nuclear Procedures, on 12/10/2011 this version of NMP-OS-007 the CORRECT version to be used by Operations.
For the indicated PROCEDURE LEVEL OF USE, placekeeping is A. was; required B. was; allowed, but NOT required C. was NOT; required D. was NOT; allowed, but NOT required Approved By:
NA Corporate 12/14/2011 FNP 12/14/2011 HNP PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP..003 12/14/2011 VEOP 67
HLT-07 RO NRC EXAM
- 68. G2.1.6 001 Which ONE of the following identifies the required communication protocol during transients JAW DI-OPS-59-896, Operations Management Expectations, Attachment 5, Strategies For Successful Transient Mitigation?
An annunciator check required prior to the SS giving a crew brief.
If during a Crew Brief, alarms 603-205 & 603-206, Reactor Vessel Level 2 Div I & Div II Trip, are received, the NPO expected to call a Time Out.
A. is; is B.
is; is NOT C.
is NOT; is D. is NOT; is NOT 68
HLT-07 RO NRC EXAM
- 69. G2.2.23 001 Which ONE of the choices below identifies a Unit 1 Tech Spec LCO condition that will require entry into a Required Action Statement (RAS)? (NOT A TRACKING RAS)
A. Torus water level is 149.5 inches in Mode 1.
B.
RCIC is mop in Mode 3 with reactor steam dome pressure at 100 psig.
C. Reactor steam dome pressure is 1052 psig in Mode 1.
D. Drywell pressure is 1.80 psig in Mode 2.
69
HLT-07 RO NRC EXAM
- 70. G2.2.37 001 An event has occurred on Unit 2 requiring entry into 31 EO-EOP-113-2, Terminating And Preventing Injection Into The RPV.
JAW step 3.1.1.1, HPCI is OFF with 2E41-C002-3, HPCI Aux Oil pump, in the PULL-TO-LOCK position.
Which ONE of the choices below completes the following statement concerning HPCI operability and Turbine Control Valve position?
lAW Tech Spec 3.5.1, HPCI is considered A. operable and the Turbine Control Valve will be fully closed B. operable and the Turbine Control Valve will be fully open C. inoperable and the Turbine Control Valve will be fully closed D. inoperable and the Turbine Control Valve will be fully open 70
HLT-07 RO NRC EXAM
- 71. G2.2.44 001 Unit 1 RHR Loop B has been placed in the Shutdown Cooling (SDC) Mode of operation with the following pump alignment:
RHR Pump lB Running in SDC Mode RHRSW Pump lB
.... Running The following alarms/conditions are received:
(601-3 14) RHR SYSTEM I ACTIVATED (60 1-234) RHR SYSTEM IT ACTIVATED Reactor Water level is -120 inches lAW 34S0-E1 1-010-1, Residual Heat Removal System, which ONE of the choices below completes the following statements concerning the status of RHR Loop B Suction Valves?
With the above conditions, 1E1 1-FOO6B, Shutdown Cooling Vlv, After 1E11-FOO6B is closed, the operator will A. must be manually CLOSED; verify 1E1 1-FOO4B, Torus Suction Vlv, has automatically opened B.
must be manually CLOSED; manually open 1E1 l-FOO4B, Torus Suction Vlv C.
will automatically CLOSE; verify 1E1 1-FOO4B, Torus Suction Vlv, has automatically opened D. will automatically CLOSE; manually open 1E1 l-FOO4B, Torus Suction Vlv 71
HLT-07 RO NRC EXAM
- 72. G2.3.13 001 An INiTIAL Drywell (DW) entry is required on Unit 1.
With Unit 1 at 8% RTP, which ONE of the choices below completes the following statements JAW 31G0-OPS-005-O, Primary Containment Entry?
The MAXIMUM reactor power allowed for this type of DW entry (INITIAL) is A Two (2) man Backup Team required to be in place for this entry.
A. lO%RTP; is B.
lO%RTP; is NOT C.
15%RTP; is D.
15%RTP; is NOT 72
HLT-07 RO NRC EXAM
- 73. G2.3.14 001 Unit 1 was at 35% power when the Hydrogen Injection System was placed in service in AUTOMATIC
- EXTERNAL mode JAW 34S0-P73-001-1, Hydrogen and Oxygen injection and Control for HWC section 7.1.2, Placing 1P73-R025, Hydrogen Controller, in EXTERNAL.
o Power is raised from 35% power to 100% power o At 100% power hydrogen flow rate indicates 40 SCFM Which ONE of the following answers both of these statements?
lAW 34S0-P73-001-l, Hydrogen and Oxygen injection and Control for HWC, hydrogen injection flow rate is the normal 100% power flow rate.
Main Steam Line radiation levels in the Steam Chase will stabilize the expected normal full power background radiation levels estabilished JAW 34GO-OPS-001-1, Plant Startup.
A. above; at B.
above; above C. below; at D. below; below 73
HLT-07 RO NRC EXAM
- 74. G2.4.26 001 Which ONE of the choices below completes the following statements concerning a fire in the Service Building Document Storage Room?
The Service Building Document Storage Room is equipped with a fire suppression system.
JAW 3OAC-OPS-003-O, Plant Operations, a MINIMUM of Fire Brigade Members must be onsite to respond to this fire.
A. Halon; five (5)
B.
Halon; three (3)
C. CO 2;
five (5)
D. CO 2;
three (3) 74
HLT-07 RO NRC EXAM
- 75. G2.4.32 001 Unit 2 was operating at 100% RTP when a loss of electrical power results in a loss of a significant number of Main Control Room annuciators and a reactor scram.
An ALERT Emergency classification is declared.
Which ONE of the choices below completes the following statement?
The LATEST time from the ALERT declaration that the INITIAL Plant Page Announcement can be made and still meet the requirements of NMP-EP-111-002, Emergency Notification Network Communicator Instructions
- Hatch, is Without additional direction from the Emergency Director, the operator is REQUIRED to make A.
15 minutes; the INITIAL Plant Page Announcement, followed by a repeat Plant Page Announcement approximately 30 minutes later B.
15 minutes; ONLY the Initial Plant Page Announcement C.
30 minutes; the INITIAL Plant Page Announcement, followed by a repeat Plant Page Announcement approximately 30 minutes later D. 30 minutes; ONLY the Initial Plant Page Announcement End of test 75
Unit 2 EOP Graph 5, BuT Curve 2.
Unit 2 EOP Graph 17A, HPCI Pump NPSH Limit, (Torus Water Level At or Above 146) 3.
Unit 2 EOP Graph 17B, HPCI Pump NPSH Limit, (Torus Water Level Below 146)
BORON INJECTION INITIATION TEMPERATURE UNIT 2 170 160 TORUS 150 WATER TEMP 140
(°F) 130 120 110 100 f%
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0 2
4 6
8 10 12 14 16 18 20 REACTOR POWER (%)
NOTE: May use SPDS Emergency Displays in place of this Graph.
240-230-230-Torus 220-Temp
(°F) 210-200-190-HPCI PUMP NPSH LIMIT (Torus Water Level At or Above 146)
NOTE: May use SPDS Emergency Displays in place of this Graph.
Suppression Chamber Pressure.
- Safe operating region is below the applicable pressure line.
UNIT 2 rj4rj4 At or Above 10_psig*
Below 10 psig*
Below 5 psig*
SAFE 180-170-I 0
500 1000 1500 2000 2500 3000 3500 4000 4500 5000 HPCI FLOW (gpm)
240 230-220-Torus Temp 210-(°F) 200-190-180-170-HPCI PUMP NPSH LIMIT (Torus Water Level Below 146) 5u0 1000 1500 2000 25OO UNIT 2 3000 3500 4000 4500 5000 HPCI FLOW (gpm)
NOTE: May use SPDS Emergency Displays in place of this Graph.
Suppression Chamber Pressure.
- Safe operating region is below the applicable pressure line.
At or Above 10 psig UNSAFE
- VA.
Below 10 psig*
Below 5 psig*
4 16&
- SAFE U
HLT-07 RO NRC EXAM Answers ID 0
1 201001K1.11 I
D 2
202001A1.02 I D
3 202002K3.03 I C
4 203000G2.4.34 I C
5 204000K4.O1 1
C 6
205000K5.02 1
A 7
206000K5.06 I C
8 209001K1.12 I D
9 209001K5.O1 1
C 10 211000K4.021 D
ii 212000A2.08 I B
12 212000K3.03 1
D 13 215002K6.04 I B
14 215003A1.06 I B
15 215004K6.02 I D
16 215005A1.O1 I D
17 215005A4.03 I D
18 216000A4.01 1
A 19 217000K2.04 I C
20 218000KI.04 I B
21 223001A3.04 1 C
22 223002K3.10 1 A
23 233000K2.02 I B
24 234000K5.02 I D
25 239002A3.02 1 C
26 241000A2.23 I D
27 259002A4.07 I D
28 261000A1.01 1
C 29 261000K3.02 I D
30 262001G2.4.47 I A
31 262002A3.01 I B
32 263000A2.02 I A
33 264000K4.06 I A
34 268000A4.01 1 B
35 286000G2.4.9 I A
36 295001AK2.01 1 C
37 295003AK1.03 1 D
38 295004G2A.1l I C
39 295005AK3.06 1 A
40 295006AA1.01 I A
41 295009AA1.03 1 D
42 295010G24.18 I D
43 295013AK2.01 I D
44 295016AA2.07 1 A
45 295018AK3.06 1 C
46 295019AA2.02 1 B
47 295020AK1.05 1 A
Answers ID 0
48 295021G2.2.40 I C
49 295023AA104 I C
50 295024EA2.06 1 B
51 295025G2.1.27 1 B
52 295026EK3.04 1 D
53 295028EA1.03 I B
54 295030EK1.02 I C
55 295031EA1.02 1 C
56 295032EA1.05 I A
57 295035EA2.02 1 D
58 295037EK2.01 I A
59 295038EK1.02 1 C
60 300000K1.02 I B
61 300000K6.04 I A
62 400000K2.02 I C
63 500000EK3.07 1 B
64 600000AK1.02 1 A
65 700000AK2.07 I A
66 G2.1.21 B
67 G2.1.21 I D
68 G2.1.6 1 A
69 G2.2.23 1 D
70 G2.2.37 1 C
71 G2.2.44 I B
72 G2.3.13 I A
73 G2.3.14 I B
74 G2.4.26 1 A
75 G2.4.32 I A
SECTION 1 (75 items) 75.00