ML112060573
| ML112060573 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/21/2011 |
| From: | Division of Reactor Safety II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-321/11-301, 50-366/11-301 | |
| Download: ML112060573 (78) | |
Text
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- it2c NRC SRO REFERENCES SRO EXAM 34AB-B21-002-i, RWL Corrections, Attachment 3 c 2.
UI EOP Graphs hA - Core Spray Pump NPSHLimnit Above 146 inches
çç 3.
Ui EOP Graphs hR - Core Spray Pump NPSH Limit Below 146 inches
(,5 4.
34S0-N40-OO1-1, Att. 1, Operating Limnits For Generator Voltage Regulator in Automatic 7, 5.
Unit 1 TS 3.1.3 Control Rod Operability 6.
NMP-EP-iiO-GLO2, Figure 3-Cold Initiating Condition Matrix, SYSTEM Columns with Notes W 7.
Unit 1 HCTL Limit Curve (Graph 2) 8.
NMP-EP-i1O-GLO2, Figure 1 - Fission Product Barrier Matrix
$ 9.
Unit 2 LCO 3.1.7, Standby Liquid Control (SLC) System
ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet US. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date:
Facility/Unit:
Region:
I II X Ill IV Reactor Type: W CE BW GE X 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
4 J 4 4 3 U J J
(.)
L) 1J J
J J
tJ J J
a
- a o-o u
j u u
Ui 9p9op C
HLT-06 RO NRC EXAM
- 1. 201002A2.03 001 Unit 1 is at 15% power and is performing a reactor startup.
Control Rod 30-31 has an Insert limit of 04 and a Withdraw limit of 08.
o All rods in this group are at position 04.
When the NPO withdraws the control rod, the rod begins DRIFTING OUT past position 06.
ROD ROD Ill OUT MOVEMENT CONTROL Which ONE of the choices below completes both of the following statements?
When rod 30-31 reaches position 10, the Rod Movement Control Rod Out white light will be lAW 34AB-Cl1-004-1, Mispositioned Control Rods, a reactor scram required.
A. illuminated; is NOT B. extinquished; is NOT C extinquished; is D. illuminated; is 1
HLT-06 RO NRC EXAM
Which ONE of the choices below completes the condition that will indicate rod 38-27 is UNCOUPLED?
Position indication on the Four-Rod display will AND the Red Full-Out light will be A. indicate 49; illuminated B. indicate 49; extinguished C. be blank; illuminated D be blank; extinguished 2
HLT-06 RO NRC EXAM
- 3. 201006A4.02 001 Unit 1 was operating at 100% RTP when an event occurred requiring a manual scram. The OATC inserted the scram and observed ALL White RPS Scram Group lights remaining ILLUMINATED.
Which ONE of the choices below completes the following statements concerning the Rod Worth Minimizer (RWM)?
In order to determine Rod Status using RWM, the RWM Confirm Shutdown display screen pushbutton, depressed to confirm rod status.
Two (2) minutes later, the RWM Confirm Shutdown display screen indicates the following:
All Rods In NO Shutdown YES Rods Not Full-In 18 Based on these indications, ALL control rods inserted to at least position 02.
A MUST be; are B. MUST be; are NOT C.
is NOT required to be; are D. is NOT required to be; are NOT 3
HLT-06 RU NRC EXAM
- 4. 203000A2.13 001 A Unit 1 Reactor startup is in progress with reactor pressure 400 psig.
At 10:00 a LOCA signal is received causing Reactor pressure to decrease 50 psig per minute.
Which ONE of the following states when the lEl 1-FO15A, RHR injection valve, will automatically start opening and JAW 31E0-EOP-l 14-1, Preventing Injection Into The RPV From Core Spray And LPCI, how RHR A Loop injection can be prevented?
lEl 1-FO15A will automatically start opening At 10:04, WITHOUT overriding ANY interlocks, RHR A Loop injection can be prevented by A. ONLY after reactor pressure is less than 370 psig; EITHER tripping RHR pumps OR closing 1E1 1-FO17A, RHR injection valve B.
ONLY after reactor pressure is less than 370 psig; tripping RHR pumps ONLY C.
IMMEDIATELY; EITHER tripping RHR pumps OR closing 1E1 1-FO17A, RHR injection valve D IMMEDIATELY; tripping RHR pumps ONLY 4
HLT-06 RO NRC EXAM
- 5. 203000K5.01 001 Unit 2 has experienced a LOCA.
0 2B Loop of RHR is injecting in the LPCI mode to maintain RWL o A leak develops on the flange of 2E1 l-FO17B, RHR Injection valve o When both B Loop RHR pumps are secured, 2E1 l-FO5OB, RHR Injection Check valve, sticks in the OPEN position Which ONE of the following completes both statements?
The water leaking from 2E1 l-FO17B will be leaking into Containment.
Closing 2E 11 -FO 1 SB, RHR Injection valve, isolate the reactor water leaking from 2E1 l-FO17B flange.
A.
Secondary; will NOT B Secondary; will C.
Primary; will D. Primary; will NOT S
HLT-06 RO NRC EXAM
- 6. 205000A4.12 001 Unit 2 is in Mode 4 with 2B RHR pump in Shutdown Cooling. Preparations are in progress to warm the B Loop of Recirc and then start the 2B Recirc pump.
The following temperatures currently exist:
Reactor Coolant 180°F 2W Recirc Suction 135°F lAW 34S0-B3l-00l-2, Reactor Recirculation System, with the above temperatures, which ONE of the following completes both statements?
The temperature difference between the reactor coolant inside the idle loop to be started and the coolant in the reactor pressure vessel WiTHIN limits.
2W Recirc loop Suction temperature will be monitored on panel A. is NOT; 2H1 1-P602 B.
is NOT; 2H1 l-P601 C.
is; 2H1 1-P601 D is; 2H1 l-P602 6
HLT-06 RO NRC EXAM
- 7. 206000A4.10 001 lAW 34S0-E41-001-2, High Pressure Coolant Injection (HPCI) System, Turbine speed is REQUIRED to be maintained above a MINIMUM of rpm, during prolonged operation, to prevent A.
1500; Turbine exhaust check valve chattering B.
1500; cycling of the 2E41-C002-3, Aux Oil Pump, ON and OFF C 2000; Turbine exhaust check valve chattering D. 2000; cycling of the 2E41-C002-3, Aux Oil Pump, ON and OFF 7
HLT-06 RO NRC EXAM
- 8. 209001K5.01 001 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.
8
HLT-06 RO NRC EXAM
- 9. 211000K6.04 001 Unit 1 is experiencing an ATWS.
A malfunction occurs while closing 1E21-FOO5A, Core Spray Injection valve.
The valve motor shorts out, resulting in a loss of its respective Motor Control Center (MCC).
Which ONE of the following completes both of these statements?
The de-energized MCC is 1R24-
, Reactor Bldg. MCC.
With this condition, available to inject boron.
A SOil; ONLY one SBLC pump remains B. SOli; BOTH SBLC pumps remain C.
S012; ONLY one SBLC pump remains D. S012; BOTH SBLC pumps remain 9
HLT-06 RO NRC EXAM
- 10. 212000A3.02 001 Unit 1 is at 100% RTP.
o The lB RPS MG Set trips o The Power Source Select switch (1H1 1-P610) is then placed in the ALT At position o No additional operator actions are taken Which ONE of the choices below completes the following statement?
After 5 seconds, based on these conditions, of the RPS Scram Relays (K14s) are DE-ENERGIZED and the A RPS bus will be A. ALL; de-energized B ALL; energized C. ONLY HALF; energized D. ONLY HALF; de-energized 10
HLT-06 RO NRC EXAM
- 11. 215003A1.06 001 Unit 1 is in Startup with IRM 1A indicating 95 on range 4. ALL other IRMs are reading between 15 and 75 on range 4.
With IRIvI 1A indicating 95 on range 4, annunciator(s) will be in the alarm condition.
Once IRM 1A is placed on range 5, the will be illuminated.
A.
603-22 1, IRM UPSCALE and 603-203, IRM BUS A UPSCALE TRIP OR INOP; IRM 1A Drawer UPSC amber light on 1H1 1-P606 B.
603-221, IRM UPSCALE and 603-203, WM BUS A UPSCALE TRW OR INOP; IRM 1A benchboard UPSC amber light on 1H1 1-P603 C.
603-221, IRM UPSCALE, ONLY; IRM 1A benchboard UPSC amber light on lHl 1-P603 D 603-221, IRM UPSCALE, ONLY; 1RM 1A Drawer UPSC amber light on lHl l-P606 11
HLT-06 RO NRC EXAM
- 12. 215003K5.O1 OO Unit 1 is in Mode 2 with a startup in progress with IRM lG reading 20 on Range 2.
o The voltage at IRM iG detector begins to gradually decrease o The FINAL voltage at the detector is one (1) VDC.
Which ONE of the following completes the statement below for TRIvI 1G detector?
As the voltage at IRM lG detector decreases, the HIGHEST indication, listed below, that an IRM Rod Block will occur at is and the FINAL expected plant response isa A 10/125 of scale; rod block with a half scram B.
5/125 of scale; rod block ONLY C.
5/125 of scale; rod block with a half scram D.
10/1 25 of scale; rod block ONLY 12
HLT-06 RO NRC EXAM
- 13. 215004A3.01 001 Unit 2 is in a refueling outage.
o Reactor Mode Switch position REFUEL o SRM Shorting Links REMOVED SOURCE RANGE MONITOR LEVEL A
B C
0 2C51-R600A 2C51-R600B 2C51.R600C 2C51-R600D 24!48V0C CAB 2A 24142V0C CAB 28 24MBVDC CAB 2A 24148V0C CAB 28 io6 c
1o6 c
io6 c
o 0
=
0 io-1o-u 10 i
N N
N N
10 T
T 10-T 10 T
S S
S E
S p
p p
p E
E
£ 2
£ 1o2 R
10 R
10 R
10 R
101_
S S
10 S
S E
£ E
E 100 1001 100 C
io N
N N
0 101_
0 0
A SRM detector failure results in the indication as shown in this figure.
With NO operator action, based on these conditions, what is the expected status of RPS Channel A and B?
RPS Channel A expected to be tripped.
RPS Channel B expected to be tripped.
A.
is NOT; is NOT B.
isNOT; is C is; is D.
is; is NOT 13
HLT-06 RO NRC EXAM
- 14. 215005K3.01 001 Unit 2 is operating at 100% power with the B APRM bypassed.
The B and C PRNM Two-Out-Of Four Trip Modules (2/4 Voters) subsequently experiences a power failure and DE-ENERGIZES.
Which ONE of the choices below completes the following statements concerning the status of the RPS buses?
A half-scram be generated in RPS Bus A.
A half-scram be generated in RPS Bus B.
A will; will B.
will; will NOT C. will NOT; will D. will NOT; will NOT 14
HLT-06 RO NRC EXAM
- 15. 217000K1.01 001 Unit 2 RCIC is operating in Full Flow Test Mode when a malfunction causes 2E51-F029, Torus Suction, valve to fully open.
Which ONE of the following completes both statements?
2E51-FOlO, CST Suction, will 2E51-F022, Test Line To CST, will A. automatically close; remain open B.
automatically close:
automatically close C. remain open; remain open remain open; automatically close 15
HLT-06 RO NRC EXAM
- 16. 218000K2.O1 001 Which ONE of the following completes both statements concerning Unit 2 ADS Logic A?
The NORMAL power supply to ADS Logic A is BACKUP power supply to ADS Logic A.
A.
2R25-SOOl, 125 VDC Cabinet 2A 2R25-S002, 125 VDC Cabinet 2B, is the B 2R25-SOOl, 125 VDC Cabinet 2A There is NO C.
2R25-S002, 125 VDC Cabinet 2B; 2R25-SOOl, 125 VDC Cabinet 2A, is the D.
2R25-S002, 125 VDC Cabinet 2B, There is NO 16
HLT-06 RO NRC EXAM
- 17. 219000A1.09 001 Unit 2 experienced an event which resulted in the following conditions:
At 11:00, o Torus water level is 140 inches o HPCI maintaining RWL at 20 inches o Suppression Pool Cooling is in service At 11:10, o Torus water level is 105 inches o HPCI maintaining RWL at 20 inches o Suppression Pool Cooling is in service Which ONE of the following completes these statements?
At 11:10, Torus Air temperature will be changing and Torus Air temperature can be monitored on panel A.
approximately the same rate as at 11:00; 2Hl l-P650 B.
approximately the same rate as at 11:00; 2H1 1-P602 C.
at a significantly faster rate than at 11:00; 2Hl l-P602 D at a significantly faster rate than at 11:00; 2H1 1-P650 17
HLT-06 RO NRC EXAM
- 18. 223002G2.4.3 001 Which ONE of the following completes the statement concerning the Unit 2 SRV control switches?
A dot has been placed above the SRV control switches to indicate that this Av yellow; valve is on the Post-Accident Monitoring (PAM) Instrumentation list B. yellow; is a Group 2 Isolation valve C. blue; valve is on the Post-Accident Monitoring (PAM) Instrumentation list D. blue; is a Group 2 Isolation valve 18
HLT-06 RO NRC EXAM
- 19. 230000K2.02 001 Unit 1 experiences a Loss of Offsite power.
o 4160V 1G is the ONLY 4160V bus that is ENERGIZED.
Which ONE of the following RHR pumps can be used for Torus Spray?
A. RHR pump 1A B RHR pump lB C. RHR pump 1C D. RHRpumplD 19
HLT-06 RO NRC EXAM
Which ONE of the following completes both statements?
Torus BULK AVERAGE temperature indication be monitored on the Primary Display of SPDS.
The LOWEST listed Torus temperature requiring entry into the Abnormal (AB) Procedure for elevated Torus temperature is A. can; 100°F B. can NOT; 100°F C can; 96°F D. can NOT; 96°F 20
HLT-06 RO NRC EXAM
- 21. 239002K1.05 001 The Normal pneumatic supply to the Unit 2 Drywell is lost.
After performing section 7.3.1, Emergency Nitrogen Supply Operation, of 34S0-P70-OO1-2, Drywell Pneumatics System, which ONE of the following is the MAXIMUM number of SRVs that will be supplied Nitrogen from the Emergency Nitrogen Bottles?
A. two (2)
B five (5)
C. seven (7)
D. eleven (11) 21
HLT-06 RO NRC EXAM
- 22. 245000K1.04 001 With Unit 2 at 35% RTP, which ONE of the following completes both statements?
(Limit your response ONLY to direct valve input to RPS Logic, NOT plant integrated response.)
The MINIMUM number of Turbine Control Valves (TCV) that will DIRECTLY cause at least a RPS HALF (1/2) Scram from a TCV Fast Closure Trip is The MINIMUM number of Turbine Stop Valves (TSV) that will DIRECTLY cause a RPS FULL Scram from a TSV Closure is A. two(2);
three (3)
B. two(2);
two (2)
C one(1);
three (3)
D. one(1);
two (2) 22
HLT-06 RO NRC EXAM
Which ONE of the following completes both statements?
To INCREASE Condensate flow through the SJAE, the 2N21-F007, SJAE Bypass AOV, is throttled in the direction.
This action will result in INLET pressure to the Condensate Demineralizers A.
closed; increasing By closed; decreasing C.
open; increasing D.
open; decreasing 23
HLT-06 RO NRC EXAM
- 24. 259001K6.01 001 Unit 2 is operating at 15% RTP with 2N21-Flll, Feedwater Startup Level Control Valve, controlling Reactor Water Level (RWL), when a loss of Plant Air pressure occurs.
Which ONE of the following describes the response of 2N21-Fl 11 when its air supply pressure decreases to 40 psig?
2N21-Fl1l will A. failOPEN B.
fai1CLOSED 0 fail AS-IS D. continue to control RWL 24
HLT-06 RO NRC EXAM
- 25. 259002K3.02 001 Unit 2 is operating with reactor power at 85%.
The Reactor Water Level Control system is in normal alignment for this power level.
Which ONE of the following statements describes the Feedwater system response to a blown fuse in the power supply to the Feedwater Master Controller?
A. Control of the 2A RFPT will transfer to the Speed Setter.
B.
Control of the 2B RFPT will transfer to the Speed Setter.
C The 2A RFP M/A Station will control RWL in automatic.
D. The 2B RFP M/A Station will control RWL in automatic.
25
HLT-06 RO NRC EXAM
- 26. 259002K3.07 001 Unit 2 is operating at 100% RTP with the following RWL indications:
o 2C32-R606A, GEMAC, indication: +/-37.0 o 2C32-R606B, GEMAC, indication: +36.6 o 2C32-R606C, GEMAC, indication: +36.9 Subsequently, the REFERENCE leg for RWL intrument 2C32-R606A developes a significant leak.
With NO operator actions, which ONE of the choices below describes the INiTIAL response of BOTH the RWL indicator 2C32-R606B AND the speed of the RPFTs to this reference leg leak?
INITIALLY, BOTH, the indication on RWL instrument 2C32-R606B will and the RFPTs speed will A DECREASE DECREASE B. DECREASE INCREASE C. INCREASE DECREASE D. INCREASE INCREASE 26
HLLO6 RO NRC EXAM
- 27. 261000K4.04 001 Which ONE of the following Standby Gas Treatment System components removes radioactive particulates as small as 0.3 microns or larger in size A. Prefilter B HEPA Filter C. Demister D. Activated Charcoal Bed 27
HLT-06 RU NRC EXAM
- 28. 262001A2.01 001 Unit 2 is operating at 50% RTP with 4160 VAC 2E, 2R22-S005, powered from Startup Auxilary Transformer (SAT) 2C.
Subsequently, the Unit 2 Main Turbine trips.
Which ONE of the following completes the statements concerning the Station Service Buses?
After the Main Generator trips, the MAXIMUM number of Station Service Buses that will be energized is At this time, 34SU-R22-O01-2, 4160V AC System Operation, can be used to MANUALLY re-energize 4160V Buses A zero (0);
2C and 2D B.
zero (0);
2A and 2B C.
two(2);
2C and 2D D. two(2);
2A and 2B 28
HLT-06 RO NRC EXAM
Which ONE of the choices below completes the following statement concerning the lB RPS Motor Generator (MG) Set and the RPS Equipment Protection Circuit Breakers?
With NO additional operator actions, when power is restored to 600 V 1D, the lB RPS MG Set AUTOMATICALLY re-start AND the RPS Equipment Protection Circuit Breakers 52-3B and 52-3D are expected to be in the condition.
A.
will NOT; reset (closed)
B.
will; reset (closed)
C will NOT; tripped (open)
D.
will; tripped (open) 29
HLT-06 RO NRC EXAM
- 30. 263000K4.02 001 Unit 2 is at 100% power when the following occurs:
o Panel 2H1 l-P65 1 indications:
JAW 34AB-R22-00l-2, Loss Of DC Buses, which ONE of the following completes BOTH of the following statements?
If the NPO places the RFPT 2A Reset-Trip control switch to TRIP, RFPT 2A will When the Main Generator output breakers (PCBs) are opened, the Start-Up supply breakers to 4160 V Station Service Buses 2A-2D, automatically close.
A. trip; will B.
trip; will NOT C.
continue to operate; will D continue to operate; will NOT 30
HLT-06 RO NRC EXAM
- 31. 264000K1.04 001 Unit 1 and Unit 2 are experiencing a TOTAL loss of Off-Site power.
The Diesel Gen lB Keylock control switch is in the REMOTE UNIT 1 position.
Subsequently, Unit 2 receives a LOCA signal.
Which ONE of the following identifies the Emergency Bus being powered from, and the cooling water supply to, lB Emergency Diesel Generator (EDG)?
lB EDG is powering 4160 V Emergency Bus and is receiving cooling water from A.
iF; 2P41-C002, Standby Diesel Service Water Pump B.
iF; Unit 1 Division 1 Plant Service Water C 2F; 2P41-C002, Standby Diesel Service Water Pump D.
2F; Unit 1 Division 1 Plant Service Water 31
HLT-06 RO NRC EXAM
- 32. 264000K6.08 001 Unit 2 is performing an Emergency Diesel Generator (EDG) surveillance.
The 2A EDG is running with its mode switch in TEST, but NOT tied to its bus.
At this time, the normal breaker to 4160 VAC bus 2E trips open.
Which ONE of the following is the status of EDG 2A and 4160V bus 2E?
A. EDG 2A REMAINS in TEST mode and 4160V bus 2E swaps to its alternate power supply.
B. EDG 2A COMES out of TEST mode and EDGt 2A ties to 4160V bus 2E.
C. EDG 2A COMES out of TEST mode and 4160V bus 2W swaps to its alternate power supply.
D EDG 2A REMAINS in TEST mode and 4160V bus 2E is de-energized.
32
HLT-06 RO NRC EXAM
- 33. 271000K4.09 001 Unit 2 is at 4% RTP with the Off Gas mode switch in AUTO t
, when the Off Gas Post-Treatment radiation monitors, 2D1 l-K615A and 2D1 1-K615B, increase to just above the HIGH alarm setpoint.
Which ONE of the following is the Off Gas component that receives a signal to close?
A. 2N62-F057, Offgas Stack Inlet Valve B. 2N62-F042, Offgas Inlet to Adsorber Valve C.
2N62-F085, Offgas Holdup Line Drain Valve D 2N62-F043, Offgas Adsorbers Bypass Valve.
33
HLT-06 RO NRC EXAM
- 34. 272000A3.01 001 Unit 2 is operating at 15% power when an event occurs resulting in the following alarms/condition:
o MAIN STEAM LINE RADIATION HIGH (60 1-425) o MAIN STEAM LINE RADIATION HIGH-HIGH/INOP (603-125) o Main Steam Line radiation levels are 6,000 mRem/hr and increasing o Crew suspects fuel element failure A NPO responding to the above conditions, observes the following valves are OPEN:
o 2B21-F022A-D & F028A-D, MSIVs o 2B31-F019 & 2B31-F020, Reactor Recirculation Sample Valves Which ONE of the following identifies whether ALL automatic actions have occurred and the required action(s) JAW 34AB-B21-001-1, Main Steam Line High Radiation or Suspected Fuel Element Failure.
All automatic actions occurred and the operator is required to A have NOT; scram the reactor and then close the MSIVs B.
have NOT; perform a fast reactor shutdown JAW 34GO-OPS-014, Fast Reactor Shutdown, and then close the MSIVs.
C.
have; scram the reactor and then close the MSIVs D. have; perform a fast reactor shutdown lAW 34G0-OPS-014, Fast Reactor Shutdown, and then close the MSIVs.
34
HLT-06 RO NRC EXAM
- 35. 288000G2.1.32 001 Unit 2 is operating at 100% power.
The Reactor Building Ventilation system is in service with the following alignment:
o 2T41-COO7A, Rx Bldg Vent Exhaust Fan: Running o 2T41-COO7B, Rx Bldg Vent Exhaust Fan: Danger Tagged out of service o 2T41-COO1A, Rx Bldg Supply Fan: Running o 2T41-COO1B, Rx Bldg Supply Fan: Standby lAW 34S0-T4l-005-2, Reactor Building Ventilation System which ONE of the choices below completes the following statements?
If the control switch for 2T4l-COOIB, Rx Bldg Supply Fan is placed in the Run position, 2T41-COO1B, Rx Bldg Supply Fan START.
If 2T41-COO7A, Rx Bldg Vent Exhaust Fan trips, the running Rx Bldg Supply Fan(s)
TRIP automatically.
A.
will; will B.
will; will NOT C will NOT; will D.
will NOT; will NOT 35
HLT-06 RO NRC EXAM
- 36. 290001K3.01 001 Unit 2 is operating at 100% RTP with the following conditions:
o U2 Refueling Hatch installed o 2A 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 2D1 1-K609A-D, RX. Bldg. Contaminated Area Radiation increase to 20 mr/hr 10:10 The Supply breaker for 2R24-S012, 600 V MCC, trips OPEN With NO operator action, which ONE of the following predicts how the Rx. Bldg. monitored radioactive release rate and Rx. Bldg differential pressure (dP) will be affected?
At 10:08, the Rx. Bldg. Stack release rate will be than at 10:04.
At 10:15, the Unit 2 Rx. Bldg. dP will be approximately A. lower; the same as at 10:08; B. higher; the same as at 10:08; C. higher; 0.0 inches water D lower; 0.0 inches water 36
HLT-06 RO NRC EXAM
- 37. 295001AK1.01 001 Unit 2 is operating with both Recirc Pumps operating at 60% speed.
The H2A ASD trips.
Given these current conditions, which ONE of the following completes both parts of this statement?
ACTUAL Total Core Flow equals ()
- and, ACCURATE Total Core Flow be read directly from the Total Core Flow recorder on 2H1 1-P603.
A.
A jet pump flow pj (+) B jet pump flow; can NOT B.
B jet pump flow minus (-) A jet pump flow can NOT C.
A jet pump flow p (+) B jet pump flow; can D B jet pump flow minus (-) A jet pump flow; can 37
HLT-06 RO NRC EXAM
- 38. 295002AK1.04 001 Unit 2 is operating at 14% power with RFPT 2A operating at 3600 rpm.
The following indications are observed:
o Inlet Flow to Stack 80 scfm and slowly rising o Steam Seal header pressure 0 psig o Condenser Vacuum 20.0 in.Hg vacuum and slowly heading to 0 in. Hg vacuum Which ONE of the following identifies the required operator action JAW 34AR-650-125-2, Steam Seal Press Low, and the RFPT status when Main Condenser vacuum reached 20 in. Hg vacuum?
A. Start the mechanical vacuum pump; The RFPT will still be in service.
B.
Start the mechanical vacuum pump; The RFPT will have tripped.
C. Throttle open 2N33-F004, Steam Seal Feed Vlv Bypass; The RFPT will still be in service.
D Throttle open 2N33-F004, Steam Seal Feed Vlv Bypass; The RFPT will have tripped.
38
HLT06 RO NRC EXAM
o Reactor pressure is 50 psig o lB Emergency Diesel Generator fails to start and can NOT be recovered o 1A RHR pump is Danger Tagged out of service Which ONE of the following completes both statements?
Core Spray will be injecting from RHR will be injecting from A BOTH Divisions (Loops);
ONLY one Division (Loop)
B. ONLY one Division (Loop);
ONLY one Division (Loop)
C. BOTH Divisions (Loops);
BOTH Divisions (Loops)
D. ONLY one Division (Loop);
BOTH Divisions (Loops) 39
HLT-06 RO NRC EXAM
- 40. 295004AK3.02 001 Unit 2 is operating at 100% Reactor Power when the following alarm occurs:
o 125/250V BATTERY GND FAULT, 65 1-127 JAW 34AB-R42-001-0, Location Of Grounds and 34AR-65l-127-2, which ONE of the following is the resistance value which will require isolation of loads and the reason for this isolation?
A resistance value of will require isolation of loads since a A. 22,000 OHMS, personnel or equipment hazard could occur if a second ground develops B 8,000 OHMS, personnel or equipment hazard could occur if a second ground develops C.
22,000 OHMS; single ground frequently results in spurious equipment operation D.
8,000 OHMS; single ground frequently results in spurious equipment operation 40
HLT-06 RO NRC EXAM
- 41. 295005G2.4.34 001 An event occurs requiring the Main Control Room to be evacuated.
NO operator actions were performed prior to leaving the Control Room.
Which ONE of the following completes both statements concerning locally tripping the Unit 2 Main Turbine and the Turning Gear Oil Pump (TGOP) operation?
The Main Turbine will be tripped locally by depressing After the Main Turbine reaches zero (0) rpm, without any additional operator actions, the Main Turbine bearings receive adequate lubrication from the TGOP.
A. EITHER ONE of the Trip pushbuttons; will B.
EITHER ONE of the Trip pushbuttons; will NOT C.
BOTH Trip pushbuttons simultaneously; will NOT D BOTH Trip pushbuttons simultaneously; will 41
HLT-06 RO NRC EXAM
- 42. 295006G2.4.1 001 Unit 2 is operating at 70% power when a transient occurs.
Current plant conditions:
o Reactor water level
+8 inches (lowest level reached) o Reactor pressure 1080 psig (highest pressure reached) o Drywell pressure 1.2 psig (highest pressure reached) o Torus water level 149.5 inches (highest level reached)
Which ONE of the following completes both of these statements?
Entry conditions have been met or exceeded Emergency Operating Procedure (EOP) flow chart(s).
JAW 34AB-C7 1-001-2, Scram Procedure 11
, performance of the RC-1, RC-2 and placards are required IMMEDIATE actions.
A ONLY for the Reactor Controls (RC);
RC-3 B. ONLY for the Reactor Controls (RC);
TC-1 C.
for BOTH the RC and Primary Containment (PC);
RC-3 D. for BOTH the RC and Primary Containment (PC);
TC-1 42
HLT-06 RO NRC EXAM
- 43. 295007AK2.03 001 Unit 2 is at 100% power with RHR B Loop in Torus Cooling.
A transient occurs resulting in the following conditions:
o Drywell pressure 3.5 psig o Reactor pressure 490 psig o Reactor level
-40 inches With NO Operator actions, which ONE of the following describes how 2E1 1-F048B, Hx Bypass Vlv, will respond to these conditions, and the HIGHEST listed reactor pressure at which RHR will inject?
2E1 1-F048B will and RHR will be injecting with reactor pressure at A. automatically OPEN; 250 psig B.
remain CLOSE; 250 psig 0 automatically OPEN; 150 psig D. remain CLOSE; 150 psig 43
HLT-06 RO NRC EXAM
- 44. 2950 16AA 1.04 001 The control room has been abandoned and 31RS-OPS-001-2, Shutdown From Outside Control Room, is being implemented.
o 2R25-S004, 125 VDC Cabinet 2D is DE-ENERGIZED o 2R25-5006, 125 VDC Cabinet 2F is DE-ENERGIZED o 4160 VAC Emergency Bus breakers are required to be LOCALLY manually operated at the switchgear lAW 3 1RS-OPS-001-2, Shutdown From Outside Control Room, 4160 VAC Emergency Bus breakers require disabling of the DC Undervoltage Trip Device in order to close their respective 4160 VAC pump breakers?
A ONLY 2F B. ONLY2E&2F C. ONLY 2E & 2G D. ALL (2E, 2F & 2G) 44
HLT-06 RO NRC EXAM
- 45. 295018AK1.O1 001 Unit 2 is operating at 100% power with RBCCW pumps 2A and 2B in service.
o 2C 600 VAC switchgear deenergizes and can NOT be restored.
Which ONE of the following completes these statements?
The Standby RBCCW pump automatically start.
RBCCW flow inside the Drywell the flow before the 2C 600 VAC switchgear tripped.
A. will NOT; remains approximately the same as B.
will; remains approximately the same as C will NOT; will be lower than D. will; will be lower than 45
HLT-06 RO NRC EXAM
- 46. 295019AA2.01 001 Unit 2 is operating at 100% RTP when a malfunction occurs on the Interruptible Essential Instrument Air Header causing this header to decrease to 45 psig.
If NO operator action is taken, which ONE of the following choices correctly states how the plant will respond to this instrument air pressure reduction?
The Non-Essential Instrument Air Header Isolation Valve (2P52-F015) will and the Outboard MSTVs will A close and remain closed; remain open B.
close and remain closed; drift closed C.
continuously cycle open and closed; remain open D. continuously cycle open and closed; drift closed 46
HLT-06 RO NRC EXAM
- 47. 295021G2.4.8 001 Unit 2 is Shutdown with the following conditions:
o Reactor pressure is 80 psig and slowly lowering o 2D RHR pump is in Shutdown Cooling (SDC)
An event occurs on Unit 2 with the following:
o The Supply breaker to 600 V Bus 2D trips and can NOT be re-closed o 3 1EO-EOP-010-2, RC RPV Control (Non ATWS), is in progress o RWL is 5 increasing i per minute (lowest level reached -10)
Given these conditions, which ONE of the following completes both statements?
JAW 34AB-R23-001-2, Loss of 600 Volt Emergency Bus, energizing 600 VAC bus 2D using the 4160/600V 2CD Transformer is In order to return SDC to service, the Group Isolation Reset switches required to be placed in the Gr. 2/5 position.
A. NOT allowed; are NOT B.
NOT allowed; are C.
allowed; are NOT D allowed; are 47
HLT-06 RO NRC EXAM
- 48. 295022AK3.02 001 Unit 2 is operating at 100% RTP when a High Drywell pressure scram signal is received.
Which ONE of the following describes the response of the Control Rod Drive Mechanisms (CRDM) to the High Drywell pressure scram signal?
FINAL CRDM temperatures are expected to NO Operator actions occur.
A significantly increase (>100°F)
B.
significantly decrease (>100°F)
C.
slightly increase (<10°F)
D. slightly decrease (<10°F) 48
HLT-06 RO NRC EXAM
- 49. 295023AA2.02 001 Fuel movement is in progress on Unit 1.
Currently a fuel bundle is on the Main Grapple.
o The Main Grapple is in the Normal Up position Subsequently, the Unit 1 Main Steam line plugs fail causing the Reactor Cavity and Fuel Pool water levels to decrease.
Which ONE of the following completes these statements?
lAW 34AB-G4l-002-l, Decreasing Rx Well/Fuel Pool Water Level, the grappled fuel bundle can be placed in-core location.
When water level drops to the Main Steam lines, the fuel seated in the Fuel Pool racks will_______
A.
into any; still be covered B.
ONLY in its proper; be uncovered C.
into any; be uncovered D ONLY in its proper; still be covered 49
HLT-06 RO NRC EXAM
- 50. 295024EK2.01 001 Which ONE of the following completes both statements concerning a High Drywell pressure signal to the HPCI System?
The LOWEST listed Drywell pressure that will cause HPCI to initiate is After HPCI starts, the Standby HPCI Pump Room Cooler will start A 1.9 psig; as soon as 2E41-FOOl, Steam Supply valve, opens B.
l.9psig; ONLY after the HPCI room temperature increases above the start setpoint C.
2.1 psig; as soon as 2E41-FOOl, Steam Supply valve, opens D. 2.1 psig; ONLY after the HPCI room temperature increases above the start setpoint 50
HLT-06 RO NRC EXAM
- 51. 295025EK3.02 001 JAW 34S0-B31-0O1-2, Reactor Recirculation System, the reason the Recirculation Pumps Trip at a high reactor pressure setpoint of
, is to reduce the challenge to the integrity of the Reactor Coolant Pressure Boundary during A 1170 psig; an ATWS condition B.
1150 psig, an ATWS condition C.
ll7Opsig; a Generator Load Reject condition D.
1150 psig, a Generator Load Reject condition 51
HLT-06 RO NRC EXAM
- 52. 295026EA1.01 001 Unit 1 experienced a transient which resulted in the following plant conditions:
3%
-180 inches compensated (level band -155 to -185) 800 psig 1.5 psig 125 °F lAW 34S0-E11-010-1, Residual Heat Removal System, which ONE of the following choices completes the statements concerning opening 1E1 1-F024A, Full Flow Test Line Vlv and 1E1 1-F028A, Torus Spray or Test Vlv and placing Torus Cooling in service?
To OPEN 1E1 1-F024A and 1E1 1-F028A; the Containment Spray Vlv Control switch REQUIRED to be placed in the MANUAL position and the Cnmt Spray Vlv Cntl 2/3 Core Ht Permis switch in the MANUAL OVERRD position.
Reference Provided A is; is REQUIRED to be placed B.
is; is NOT C.
is NOT; is NOT D.
is NOT; is o Reactor power o RPV Water Level o RPV pressure o Drywell pressure o Torus temperature 52
HLT-06 RO NRC EXAM
- 53. 295028EK3.06 001 Unit 2 experienced a loss of Instrument Air resulted in a reactor scram.
The following conditions exist:
o Reactor power 3% (all control rods did NOT fully insert) o RPV Pressure 1110 psig, slowly increasing o RWL
-110 inches, stable o ADS Inhibit Switches INHIBIT position o RHR pumps ONLY 2A running o Drywell (DW) Pressure 3.0 psig, increasing at 0.5 psilminute o DW Temperature 370°F, slowly increasing After the above conditions have existed for ten (10) minutes, the NPO places the ADS INHIBIT switches to the NORMAL position and NONE of the ADS valves OPEN.
Based on the conditions above, the MOST likely listed reason the ADS valves did NOT open is that A. Instrument Air to the ADS valves has been lost B DW Temperature is above the design criteria C.
oniy one RHR pump is in operation D. RWListoohigh 53
HLT-06 RO NRC EXAM
- 54. 295029EA2.03 001 Which ONE of the following completes these statements?
The method of containment water level determination changes from Torus water level instrumentation to 31E0-EOP-105-2, Primary Containment Water Level Determination, when Torus water level goes above
. (Select the LOWEST level that applies)
Differential pressure readings used to determine Containment water level will be read from A. 285 inches; locally installed pressure gauges B.
285 inches; Drywell to Torus dp indicators, 2T48-R635, (2H1 1-P654) 0 300 inches; locally installed pressure gauges D. 300 inches; Drywell to Torus dp indicators, 2T48-R635, (2H1 1-P654) 54
HLT-06 RO NRC EXAM
- 55. 295030EK2.03 001 An event has occurred on Unit 1 resulting in the following conditions:
o Torus Water Level 148 inches o Torus Water Temperature 230°F o Torus Pressure 12 psig Subsequently the following occurs at the listed times; 10:00 Core Spray is injecting at 3000 gpm 10:10 Torus level DECREASES to 144 inches 10:15 Core Spray flow is INCREASED to rated 10:20 Torus pressure DECREASES to 1.0 psig due to Drywell Sprays Which ONE of the following listed times is the EARLIEST time that entry into the UNSAFE area of the Core Spray Pump NPSH Limit Graph occurs?
Reference Provided A.
10:00 B 10:10 C.
10:15 D.
10:20 55
HLT-06 RO NRC EXAM
- 56. 295031EA2.01 001 Which ONE of the following actuations, occurring due to low RWL, is the indication of the LOWEST RWL achieved during a transient on Unit 2?
A. Recirc Pump Speed Limiter #4.
B. RPS K14 Scram Relays de-energizing C. ARI valves automatically opening.
D Recirc Pumps tripping 56
HLT-06 RO NRC EXAM
- 57. 295033EK1.02 001 Unit 2 is in Mode 5 with solvent based painting in progress at the ATTS Panel area of the Main Control Room.
Subsequently, a fuel handling accident causes the following Area Radiation Monitors to INCREASE to 22 mr/br:
o 2D21-K6O1A, Reactor Head Laydown Area o 2D21-K6O1M, Spent Fuel Pool And New Fuel Storage With the above conditions present, and JAW 3450-Z41-OOl-l, Control Room Ventilation System, which ONE of the following is the REQUIRED MCREC mode of operation?
A. Normal Mode B. Isolation Mode C Pressurization Mode D. Purge Mode 57
HLT-06 RO NRC EXAM
- 58. 295034G2.2.39 001 UNIT 2 is operating at 100% RTP when I&C personnel report that ALL 2D1 1-K609A-D, Reactor Building Vent Exhaust radiation monitors, will NOT provide a trip signal, due to a calibration error.
JAW TS 3.3.6.2, Secondary Containment Isolation Instrumentation, which ONE of the following is the MINIMUM REQUIRED TS action to be completed within one hour of receiving this report?
M restore isolation capability B.
isolate the penetration flow paths C.
declare all 4 Standby Gas Treatments mop D. declare associated Secondary Containment Isolation Valves mop 58
HLT-06 RO NRC EXAM
- 59. 295036EA1.04 001 Unit 2 is operating at 100% RTP when a leak occurs in Secondary Containment (SC) requiring entry into 31E0-EOP-014-2, SC Secondary Containment Control! RR Radioactivity Release.
Subsequently, a loss of Instrument Bus 2A occurs.
The Shift Supervisor directs the NPO to monitor SC water and radiation levels.
Which ONE of the choices below completes the following statements?
SC radiation levels be monitored by using area radiation monitoring (ARM) instrumentation located in the Main Control Room.
Personnel to determine that Max Normal SC Water level has been exceeded.
A.
can NOT; can use the Main Control Room SC sump alarms by themselves B can NOT; must be dispatched LOCALLY C.
can; can use the Main Control Room SC sump alarms by themselves D.
can; must be dispatched LOCALLY 59
HLT-06 RO NRC EXAM
- 60. 295037EK1.01 001 During an ATWS, in order to avoid exceeding the Heat Capacity Temperature Limit (HCTL) graph, the SRO has ordered reactor pressure to be lowered to 700 psig using SRVs.
Which ONE of the following describes the reactor power response IMMEDIATELY upon opening the SRVs and why?
A. Reactor power will INCREASE due to the DECREASED reactor coolant temperature.
B. Reactor power will INCREASE due to the INCREASED water level inside the core.
C. Reactor power will DECREASE due to the DECREASED core inlet sub-cooling.
D Reactor power will DECREASE due to the INCREASED voiding in the core.
60
HLT-06 RO NRC EXAM
- 61. 295038EA1.03 001 The following annunciator is in the alarm condition for 2D1 l-K605, Service Water Liquid Radiation Monitor:
601-407, Service Water Effluent Radiation High Which ONE of the following completes these statements?
The system being monitored by this detector is This flowpath AUTOMATICALLY isolate due to this High radiation signal.
A.
RHR Service Water (RHRSW) will NOT B Plant Service Water (PSW) will NOT C.
RHR Service Water (RHRSW) will D.
Plant Service Water (PSW) will 61
HLT-06 RO NRC EXAM
- 62. 300000K2.O1 001 Which ONE of the choices below identifies the correct power supplies for the Unit 2 Station Service Air Compressors?
SSAC 2A SSAC 2C A. 600V 2D 600V 2A B.
600V 2C 600V 2BB C 600V 2C 600V 2A D. 600V 2D 600V 2BB 62
HLT-06 RO NRC EXAM
- 63. 400000G2.1.30 001 Unit 2 is operating at 100% RTP when alarm 650-248, RBCCW Surge 1k Level Low Or Excess Leakage, is received.
lAW 34AR-650-248-2, which ONE of the following completes the statement concerning the RBCCW surge tank timer indication and where the operator will reset the RBCCW surge tank timer?
The RBCCW surge tank counter will indicate and once the system is repaired, the operator will reset the timer at the panel.
A.2; 2H21-P350 B.
2; 2H1 1-P650 C.0; 2H1 1-P650 D 0; 2H21-P350.
63
HLT-06 RO NRC EXAM
- 64. 600000AK2.04 001 The plant is operating at 30% power when a fault in the Unit 1 Main Transformer results in the transformer exploding with a subsequent fire.
o 651-114, Main XFMR Fault Pressure Alarm is received o Fire Alarm (65 1-160) on Unit 1 P651 panel is received Which ONE of the following is the status of the Unit 1 Reactor and the 4160 VAC Station Service transfer logic?
4/3/ (
The reactor automatically scram 4iimed4a+e4yafter the explosion occurs AND 4160 VAC Station Service transfer logic allow a transfer to the Startup Auxiliary Transformers, when needed.
A will; will B.
will; will NOT C.
will NOT; will D. will NOT; will NOT 64
HLT-06 RO NRC EXAM
- 65. 700000AA2.01 001 Unit 1 is operating at 100% power.
Unit 2 is in Refuel Mode.
Following a grid disturbance, the following Unit 1 conditions exist:
o Generator H2 pressure 55 psig o Generator Megawatts 930 MWe o Generator Megavars
+ 400 MVARs o 230 KV switchyard voltage 231 kV Based on the requirements of 34AB-S1 1-001-0, Operation With Degraded Voltage, which ONE of the following choices correctly completes BOTH parts of this statement?
Based on the existing conditions, the 230 kV switchyard voltage is currently than the normal MINIMUM voltage AND the Unit 1 Main Generator is operating the limits of the Generator Capability Curve.
Reference Provided A. less; within B less; outside C.
greater; within D. greater; outside 65
HLT-06 RO NRC EXAM
- 66. G2.1.8 001 Unit 2 is operating at 100% RTP.
JAW 34S0-B31-001-2, Reactor Recirculation System, which ONE of the following describes the MINIMUM qualification and the coordination requirements for changing Recirc Pump t A
speed locally?
A. A qualified Systems Operator can ONLY perform the speed adjustment if a Senior Reactor Operator is present at the local ASD A FPC Cabinet.
B A licensed Nuclear Plant Operator can ONLY perform the speed adjustment if in constant communication with the Main Control Room.
C.
A qualified Systems Operator can ONLY perform the speed adjustment if a Nuclear Plant Operator is present at the local ASD A FPC Cabinet.
D. A licensed Nuclear Plant Operator can ONLY perform the speed adjustment if a Senior Reactor Operator is present at the local ASD A FPC Cabinet.
66
HLT-06 RO NRC EXAM
- 67. G2.1.20 001 During the execution of 3 1EO-EOP-OlO-2, RPV Control (Non-ATWS), which ONE of the following is the correct action when Anticipating Emergency Depressurization?
A. Open Safety Relief Valves to maintain cooldown rate < 100°F per hour.
B.
Open ALL ADS Safety Relief Valves to depressurize irrespective of the cooldown rate.
C.
Open Main Turbine Bypass Valves to maintain cooldown rate < 100°F per hour.
D Open ALL Main Turbine Bypass Valves to depressurize irrespective of the cooldown rate.
67
HLT-06 RO NRC EXAM
- 68. G2.2.13 001 JAW NMP-AD-003-001, Tag Standards, which ONE of the following completes these statements?
Danger tags AND tags are BOTH allowed to be hung (co-exist) on a single component.
While these tags co-exist, the tag should be placed on top.
A. Caution; Caution B Caution; Danger C. Operating Permit; Operating Permit D. Operating Permit; Danger 68
HLT-06 RO NRC EXAM
- 69. G2.2.21 001 Given the following:
1E1 1-FO17A, RHR Injection valve was declared INOPERABLE for preventative maintenance (PM).
Following the PM, operators performed the stroke test on 1E1 1-FO17A lAW 34SV-El 1-002-1, RHR Valve Operability.
The stroke test data is shown below:
lAW 34SV-El 1-002-1, which ONE of the following describes the timing and status of 1E1 l-FO17A?
To time this valve OPEN, the NPO will START the stopwatch when the Based on the above data, 1E1 1-FO17A be IMMEDIATELY declared OPERABLE.
A. control switch is placed to OPEN; can B. red light FIRST illuminates; can C control switch is placed to OPEN; can NOT D. red light FIRST illuminates; can NOT; 69
HLT-06 RO NRC EXAM
- 70. G2.3.11 001 Which ONE of the following is the BASIS for restarting the Turbine Building (TB) Ventilation when executing 3 1EO-EOP-014-2, SC Secondary Containment Control
- RR Radioactivity Release Control?
Restarting the TB Ventilation AND assures a release from the TB Ventilation System is monitored prior to exiting the A. maintains equipment operability; Reactor Building Stack B preserves personnel accessibility; Reactor Building Stack C. maintains equipment operability; Main Stack D. preserves personnel accessibility; Main Stack 70
HLT-06 RO NRC EXAM
- 71. G2.3.12 001 lAW 31G0-OPS-005-O, Primary Containment Entry, the MAXIMUM reactor power at which radiological conditions will allow a NORMAL Primary Containment Entry to occur is A. IRMRange5 B. 7%RTP Cb/ 1O%RTP D.
15%RTP 71
HLT-06 RO NRC EXAM
- 72. G2.3.13 001 Two NPOs are required to enter a Locked High Radiation area room to perform a tagout.
The NPOs will be accompanied by a Health Physics (HP) Technician (Tech).
lAW 62RP-RAD-016-O, Control Of High Radiation Areas, which ONE of the choices below completes the following statements?
The keys to the Locked High Radiation area room can be issued from After exiting the Locked High Radiation Area, the door can be verified secure by A the HP Office ONLY one of the NPOs B.
the HP Office ONLY the HP Tech ONLY C. either the the HP Office OR the Work Control Center; one of the NPOs D. either the the HP Office OR the Work Control Center; the HP Tech ONLY 72
HLT-06 RO NRC EXAM
- 73. G2.4.16 001 Unit 2 has experienced a complete loss of offsite power (LOSP).
The following conditions exist on Unit 2:
o ONLY 4160 VAC bus 2G is energized o Torus pressure is currently 11 psig and rising 1.0 psig per minute Which ONE of the following completes these statements?
With the above conditions, actions in the takes precedent over actions in any other procedure.
34AB-R22-003-2, Station Blackout procedure, will be EXITED when a MINIMUM of 4160V Emergency buses are energized on Unit 2.
A. 34AB-R22-003-2, Station Blackout procedure; two (2)
B. 34AB-R22-003-2, Station Blackout procedure; three (3)
C EOP procedures; two (2)
D. EOP procedures; three (3) 73
HLT-06 RO NRC EXAM
- 74. G2.4.4 001 Unit 2 is conducting a HPCI Pump Operability Surveillance.
o At 14:00 Torus Bulk average water temperature is 94°F, increasing at 0.5°F/minute.
Based on the current trend, which ONE of the following is the EARLIEST listed time that entry into 3lEO-EOP-012-2, PC Primary Containment, is REQUIRED?
A.
14:03; B 14:13; C.
14:23; D.
14:33; 74
HLT-06 RO NRC EXAM
- 75. G2.4.5 001 Of the procedure types listed below, which ONE would provide the DETAILED guidance for notifying state and local agencies in the event of a Fuel Handling accident that resulted in a radioactive release?
A. 34AB-J 11, Irradiated Fuel Damage During Handling NMP-EP, Nuclear Management Procedures for Emergency Preparedness C. 31E0-EOP, Emergency Operating Procedures D. NMP-RP, Nuclear Management Procedures for Radiation Protection End of test 75