ML121280562
| ML121280562 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/07/2012 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML121280562 (89) | |
Text
Name:
HL-17 NRC Exam Student Test
IIL-17 NRC Exam 1.
Unit 1 initial conditions:
- Reactor power is 100%, all control systems in normal alignment.
- An IRCS pressure control malfunction reduces RCS pressure to 2120 psig.
- Tavg is constant.
- A turbine runback initiates.
Current conditions:
- Control rods are inserting in automatic.
- Tavg is 4.0°F > Tref.
Which one of the following is the initiating event (based on the INITIAL conditions),
and the current expected rod speed, considering only the temperature deviation (based on the CURRENT conditions)?
Initiating Event Current Rod Speed A. OP delta T runback 8 steps per minute B. OP delta T runback > 8 steps per minute C. CT delta T runback 8 steps per minute D. CT delta T runback > 8 steps per minute Page 1 of 75
HL-17 NRC Exam 2.
Initial conditions:
- Unit 1 is maintaining 70% power.
- Control rods are in Automatic.
- Control bank D starts to step out continuously.
- The OATC places rods in Manual.
Current conditions:
- Rods continue to step out.
Per 18003-C, Rod Control System Malfunction, the NEXT procedural step states A. check Rod Motion STOPPED.
B. place the Rod Motion Switch in hold.
C. commence an Emergency Boration.
D. trip the Reactor and go to 19000-C, E-O, Reactor Trip or Safety Injection.
Page 2 of 75
HL-17 NRC Exam 3.
Initial conditions:
- ACCW pump # 1 is running.
- ACCW pump # 2 is in standby.
Current sequence of events:
- Safety Injection occurs.
- 2 minutes later, RAT lA experiences a fault.
- DG1A energizes 1AAO2.
- SI has NOT been reset.
Based on the current conditions, which one of the following correctly describes the status of the ACCW pumps after the DG1A load sequence is complete, if no operator actions occur?
ACCW Pump # 1 ACCW Pump #2 A. OFF OFF B. RUNNING OFF C. OFF RUNNING D. RUNNING RUNNING Page 3 of 75
HL-17 NRC Exam 4.
Unit 1 is at 100% power:
- 120 gpm letdown is in service.
- ACS Boron Concentration is 860 ppm.
- Letdown Hx temperature element TE-0130 fails 5°F below normal setpoint.
Which one of the following correctly completes the statement below?
In response to the failure above, an inadvertent ACS 41 ) will occur, and per the annunciator response procedure, the OATC will manually 2). TV-0130 to control letdown temperature.
_(1)_ _(2)_
A. boration open B. boration close C. dilution open D. dilution close Page 4 of 75
VOSTLE WRITTEN EXAM 2012-301 QUESTION / RESPONSE DOCUMENTATION FOR USE BY APPLICANT Applicant Asking Questi 1 on:
Time Question Asked: 1193 Question Number:
ii Question Being Asked: DOES Ce$âotc-ei bc 4enipercKre e/ea,prH TC-Oi3 F.J1s St bkHow 4oriilczI ise 1
,i-I4-- fl ,fleu1 re 0 130 is recA&Mcf lower finp 4 4iq, CCCk4cti 1-enip, P
L 1 60 i,cAiqi- S coaiple4c /Vc y
4 i For TV-oi3o I, FOR USE BY PROCTOR Response To Applicant:
im2rL .M 4 p
7 Jgpmpfr-TSr f&tti7Z&.
PAn 2 1e nJtuftJ ,iJAc,t6 fOlZ fl-flo 1k lhf(6y 1;:
Time Response Provided To Applicant:
Proctors Initials: -I Applicants Initials:
HL-17 NRC Exam 5.
Initial conditions:
- Unit us at 90% power.
- CVCS letdown flow is 75 gpm.
- RCS boron concentration is 492 ppm.
- 1 HS-1 1 2A VCT HUT LETDOWN DIVERT is in the VCT position.
Current conditions:
- A NEW CVCS cation bed demin is to be placed in service and is to be flushed to the Recycle Holdup Tank.
- 1 HS-1 1 2A VCT HUT LETDOWN DIVERT is placed in the HUT position.
- The valve FAILS to reposition.
- The cation bed demin flush is initiated.
Based on the indications above, which one of the following will occur?
A. RCS Tavg will rise.
B. RCS pressure lowers.
C. Letdown flow rises above 75 gpm.
D. RCS lithium and cesium concentrations rise.
Page 5 of 75
HL-17 NRC Exam 6.
Which one of the following correctly completes the following statements?
The RHR system is being placed in service for a plant startup, the OATC has started TWO CCW pumps and will verify CCW flow stabilizes at(l).
Per 13011-1, Residual Heat Removal System, the limit for placing the CCW system in service to the RHR Pump Seal Coolers is (2). system temperature.
_( 1 ) 2)
A. 5500 gpm 150°F B. - 5500 gpm 225°F C. 9000 gpm 150°F D. - 9000 gpm 225°F Page 6 of 75
HL-17 NRC Exam 7.
Which one of the following correctly completes the following statement?
The High Head Safety Injection flow path for (1 ) physically flows through the Boron Injection Tank (BIT) and the main control boards (QMCBs) have a BIT flow indicator on 2)
_(1 )
A. unit 1 both unit 1 and unit 2 B. unit 1 unit 1 only C. unit 2 both unit 1 and unit 2 D. unit 2 unit 2 only Page 7 of 75
HL-17 NRC Exam 8.
Initial conditions:
- Unit 1 is solid plant.
- PRZR bubble is being drawn per 12001-C, Unit Heatup to Hot Shutdown.
Current conditions:
- A transient results in an RCS pressure spike.
- ALB12-E03 PRZR REL TANK HI TEMP illuminates Which one of the following correctly completes the statement below?
The RHR pump (1 ) relief valve lifting caused the PRT High Temperature and per 13004-1, Pressurizer Relief Tank Operation, the FASTEST way to cooldown the PAT is using 2).
A. (1) discharge (2) spray from RMWST and drain to the RCDT B. (1) discharge (2) recirculation through the RCDT heat exchanger C. (1)suction (2) spray from RMWST and drain to the RCDT D. (1)suction (2) recirculation through the RCDT heat exchanger Page 8 of 75
HL-17 NRC Exam 9.
Given the following:
- Unit 1 is at 8.5% power, plant startup in progress.
- An automatic Reactor trip occurs.
- The crew is stabilizing the plant per 19001-C, ES-O.l Reactor Trip Response.
Which one of the following initiated the Reactor trip?
A. Pressurizer Pressure - Low B. Pressurizer Pressure - High C. Pressurizer Water Level - High D. Reactor Coolant Pump Underfrequency Page 9 of 75
HL-17 NRC Exam 1
Initial conditions:
- CCW pumps 111 and # 5 are running.
- All other CCW pumps are in standby.
Current conditions:
- An automatic Safety Injection occurs with NO loss of offsite power.
Based on the current conditions, which one of the following will be the correct status of the CCW pumps following the completion of the load sequencer, and no additional operator actions occur?
Train A Train B A. only 2 pumps running only 2 pumps running B. only 2 pumps running all 3 pumps running C. all 3 pumps running only 2 pumps running D. all 3 pumps running all 3 pumps running Page 10 of 75
HL-17 NRC Exam Em.
0 Initial conditions:
- Pressurizer Code Safety Temperature Indicator, TI-0466, is rising.
- PRT level, temperature, and pressure are rising.
Current conditions:
- Reactor trip and SI have occurred.
- RCS pressure is 1330 psig and lowering.
- No CCPs are running or available.
- SIP B is running, SIP A is tripped.
- The crew is performing 19010-C, E-l Loss of Reactor or Secondary Coolant and are at the step for checking SI Termination Criteria.
Which one of the following is the required action to take at this time and the reason?
A. Leave RCPs running, forced circulation is required for adequate heat removal without any CCPs available.
B. Leave RCPs running, RCP Trip Criteria do NOT apply at this time.
C. Trip the RCPs, to prevent excessive depletion of RCS inventory.
D. Trip the RCPs, due to loss of seal injection flow.
Page 11 of 75
HL-17 NRC Exam 12.
Current conditions:
- RCS pressure is 2235 p51g.
- PRT pressure is 40 psi 9
- PRZR Safety Valve C is leaking by to the PRT.
- Safety Valve leakage has been determined to be 1.2 gpm.
Which one of the following correctly completes the following statement?
The approximate tailpipe temperature of the safety valve will be (1 ) °F and per Tech Spec 3.4.13, the RCS Operational Leakage limit 42)_ being exceeded.
_(1 )
A. 268 is B. 268 is NOT C. 287 is D. 287 is NOT Page 12 of 75
HL-17 NRC Exam 13.
Initial conditions:
- Unit 1 is operating at 100% steady state power.
- All control systems in AUTOMATIC.
- One group of Pressurizer back-up heaters has been manually energized.
- 1 PS-455F, PRZR PRESS CNTL SELECT is selected to CH 455/456 position.
Current conditions:
- Controlling PRZR pressure channel, 1 PT-455, fails low.
Based on the current conditions, which one of the following states the IMMEDIATE effect the 1 PT-455 failure will have on the remaining PRZR Backup (B/U) heaters and PRZR PORV Block valves?
Remaining B/U Heaters PORV Block Valves A. energize shut B. energize remain open C. remain off shut D. remain off remain open Page 13 of 75
HL-17 NRC Exam 14.
Initial conditions:
- Unit 1 is at 4% power.
- NCP is in service.
- CCP B is in AUTO.
Current conditions:
- RAT 18 switcher trips open.
- DG1B re-energizes 1BAO3.
- The Reactor remains at 4% power.
Based on the current conditions, if no operator actions occur, which one of the following is correct regarding the charging pump status at the completion of the load sequence?
NCP CCPB A. running running B. running stopped C. stopped running D. stopped stopped Page 14 ot 75
HL-17 NRC Exam n5.
Which one of the following correctly states the MINIMUM coincidences for the Low Fluid Oil Pressure and Turbine Stop Valve Closure that will result in a Reactor Trip from Turbine Trip with Reactor power at 48%?
Low Fluid Oil Pressure < 580 psig Turbine Stop Valve Closure < 96.7% open A. 2of3 30f4 B. 2of3 4of4 C. 2of4 3of4 D. 2of4 4of4 Page 15 of 75
HL-17 NRC Exam 16.
Unit one is at 100% power.
A short circuit occurs in the CONTROL section of the Pressurizer Master Pressure Controller (PIC-455).
Based on the above condition, the input to the Reactor PROTECTION System will NOT be affected due to the use of A. isolation devices B. de-energize to actuate bistables C. auctioneering circuits D. energize to actuate bistables Page 16 of 75
HL-17 NRC Exam 17.
Initial conditions:
- Unit 2 is at 6% power.
- Feedwater control has just been transferred from AFW to the Bypass Feed Regulation Valves.
- All AFW pumps have just been aligned to standby readiness.
Current conditions:
- Steam Generator # 3 Narrow Range level indications as follows:
ChI ChIl Chill ChIV 82.4% 81.4% 81.7% 84.2%
- Both MFPT TRIP annunciators illuminate.
- No AFW pumps are currently running.
Based on the current conditions, which one of the following correctly completes the following statement?
The AFW system status is A. expected, no AFW actuation setpoint has been exceeded B. NOT expected, BOTH MDAFW pumps and the TDAFW pump should have started C. NOT expected, BOTH MDAFW pumps should have started. The TDAFW pump should NOT have started D. expected, the AFW actuation signal is blocked under the current conditions per 12004-C, Power Operation (Mode 1)
Page 17of 75
HL-17 NRC Exam 18.
conditions:
Initial
- Unit us in Mode 3.
- All RCPs are in service.
Current conditions:
- RCP # 1 trips due to a faulty relay.
After the plant stabilizes and when starting RCP #1 after repair, the RCP oil lift pump handswitch blue light 41 ) indicate that the lift oil pressure has been greater than 600 psig for TWO minutes.
The interlock associated with this must be met in order to close the IRCP breaker.
_( 1 )
A. does NOT 1E B. does 1E C. does NOT non-i E D. does non-1E Page 18 of 75
HL-17 NRC Exam 19.
Initial conditions:
- Unit 1 is at 2.0 X 1 Q3 % power and stable.
Current conditions:
- The CONTROL POWER circuit breaker on the signal processor for SR / IR channel 1 N31 / 1 N35 trips.
- The green control power light on the front of the signal processor EXTINGUISHES.
Based on the current conditions, which one of the following is/are the annunciator window(s) that will be LIT, (if any)?
NIS HI FLUX SOURCE NIS HI FLUX IR RANGE REACTOR TRIP REACTOR TRIP A. LIT NOT LIT B. NOT LIT LIT C. LIT LIT D. NOT LIT NOT LIT Page 19 of 75
HL-17 NRC Exam 20 Given the following plant conditions:
- Unit 1 is at 100%.
- Power is lost to the bistables for Containment Pressure Channel II (P-936).
Which one of the following indicates the MINIMUM number of ADDITIONAL channels required to INITIATE an actuation signal on Hi-i and Hi-3 Containment Pressure?
Hi-i Hi-3 A. 1 1 B. 1 2 C. 2 1 D. 2 2 Page 20 of 75
HL-17 NRC Exam 21.
Given the following:
- A spurious SI has occurred on Train B.
- Train B SI has NOT been reset.
- A total LOSP has occurred.
- Both DGs have started and tied to the 1 E Emergency Buses.
Assuming no operator actions, which one of the following is the correct indication of the status of all the Train B CNMT Cooler LOW Speed fans?
Train B HVAC panel CNMT Coolers CNMT Coolers Train B QMCB MLB Lights Handswitch Lights A. LIT red lights LIT B. LIT green lights LIT C. OFF red lights LIT D. OFF green lights LIT Page 21 of 75
HL-17 NRC Exam CL Initial conditions:
- Unit 1 is at 100% power.
- CCP lA is running.
- The NCP is in standby.
Current conditions:
- CCP 1A trips on Overcurrent.
Which one of the following correctly completes the following statement?
The action(s) of TR LCO 13.1.5, Charging Pumps-Operating, is(are)(1) and the action(s) of TR LCO 13.1.3, Boration Flow Paths Operating, is(are)_(2)__.
_(1)_ _(2)_
A. required required B. required NOT required C. NOT required required D. NOT required NOT required Page 22 of 75
VOGTLE WRITTEN EXAM 2012-301 QUESTION / RESPONSE OOCUMENTATION FOR USE BY APPLICANT Applicant Asking Question:]
Time Question Asked:
Question Number:
t Question Being Asked:
FOR USE BY PROCTOR Response To Applicant:
2AjingQ
&wiyj:
-Ccf a/WI. OPeRAUtE 5 NO17ZwJM/
1
( uUlt
) h4iJostui4J ixi A-To.
Time Response Provided To App)icant:
Proctors Initials:
Applicants Initials:
HL-17 NRC Exam 23.
Initial conditions:
- Unit 1 is in Mode 4.
- CCW pump # 6 is running in single pump operation.
Current conditions:
- CCW pump # 6 trips.
Which one of the following correctly describes components that have ALL lost CCW flow?
A. 1A RHR Hx and 1A RHR pump seal cooler IA RHA pump motor cooler did NOT lose CCW flow B. 1 B RHA Hx and 1 B RHR pump seal cooler 1 B RHR pump motor cooler did NOT lose CCW flow C. 1A RHR Hx, 1A RHR pump seal cooler, and 1A RHR pump motor cooler
HL-17 NRC Exam 24.
Initial conditions:
- 14806B-1, Train B Containment Spray Pump 1ST and Response Time Test, is being performed.
- HV-9001 B, CNMT SPRAY PUMP B DISCH ISOLATION has been verified closed.
Current conditions:
- Containment Spray Pump B has been started.
Containment Spray Pump B motor will be cooled by 41 )
and the recirculation flow path to the RWST j2)......
2)
A. CCW is required to be manually valved in B. CCW is NOT required to be manually valved in C. NSCW is required to be manually valved in D. NSCW is NOT required to be manually valved in Page 24 of 75
HL-17 NRC Exam 25.
Initial conditions:
- ACCW pump # 2 is in service.
- All other systems in normal alignment.
Current conditions:
- NSCW Train B is shutdown due to a leak on the discharge header.
Which one of the following correctly completes the following statement?
ACCW pump # 2 motor 41 ) cooling and the ACCW loads 2). cooling.
).... _(2)_
A. has lost have lost B. has lost still have C. still has have lost D. still has still have Page 25 of 75
VOSTLE WRITTEN EXAM 2012-30 1 QUESTION I RESPONSE DOCUMENTATION FOR USE BY APPLICANT Applicant Asking Question:
Time Question Asked: O 53 Question Number: 2 5 Question Being Asked is -u-i-is jecnojJ ,4Si(LNç, u- Acc mo,tC L°
£fltc ?4A\(B CøOLJJJ4 w4re2_ iF) 1UL-rlAeAIF-CoOL.tNt;, 14A-S &Eii tz,Sf It TNt cycrE-- ri-i Ar Co bL5 Tl4tM M..Go, c. A iyL!pJ NSL.-ki iN fVICG FOR USE BY PROCTOR Response To Applicant:
-AJSCuJ lfl-i,ii 51 75 7t,J 672t4C6 Time Response Provided To Applicant:
/O23D Proctors Initials:
Applicants lnitiaIs:
HL-17 NRC Exam Unit 1 has tripped from 78% power.
C - 1 NAA is de-energized.
- 1 NAB remains energized.
Which one of the following pumps WILL be running, assuming no operator actions?
A. Condensate Pump # 1 B. Condensate Pump # 2 C. Reactor Coolant Pump # 3 D. Reactor Coolant Pump # 4 Page 26 of 75
HL-17 NRC Exam Following a LOCA, the Emergency Director has directed Post-LOCA Hydrogen Purge System to be placed in service to reduce CNMT H 2 concentration per 13130-1, Post-Accident Hydrogen Control.
Valves listed as follows:
- 1-1508-U4-012, POST LOCA PURGE CTB ISO VALVE [(Equip Bldg roof (Dog House)]
HV-2624A and 1HV-2624B, CTB POST LOCA PURGE EXH IRC ISO VLVS Per 13130-1, _(1)_ will be opened FIRST and in order for the UO to open 1-HV-2624A or B, _(2)_ will have to be reset.
A. (1) 1-1508-U4-012 (2) CIA B. (1) 1-1508-U4-012 (2) CVI C. (1) 1-HV-2624A orB (2) CIA D. (1) 1-HV-2624A orB (2) CVI Page 27o1 75
HL-17 NRC Exam 28.
Initial conditions:
- An ATWT has occurred on Unit 2 at EOL conditions.
- 19211-C, FR-S.1 Response to Nuclear Power Generation/ATWT is in progress.
- Attempts to establish Emergency Boration have been unsuccessful.
Current conditions:
- Step 23 to Check Reactor power is being performed.
- Reactor power indicates 6%.
- RCS temperature is slowly rising.
- RCS pressure is 2285 psig.
Based on current conditions, per 19211-C, the operators will 1)__ the RCS heatup and with Reactor power at the current level the crew will 2).._.
A. (1) allow (2) initiate actions of other Function Restoration Procedures in effect which do NOT cool down or otherwise add positive reactivity to the core B. (1) allow (2) open PORVs to reduce RCS pressure to 2185 psig to raise charging flow C. (1)stop (2) open PORVs to reduce RCS pressure to 2185 psig to raise charging flow
- 0. (1) stop (2) initiate actions of other Function Restoration Procedures in effect which do NOT cool down or otherwise add positive reactivity to the core Page 280(75
HL-17 NRC Exam 29.
Initial conditions:
- Fuel shuffle in progress in the Spent Fuel Pools.
Current conditions:
- An irradiated assembly is dropped in the Unit 1 Spent Fuel Pool.
- The SRDC indicates HIGH radiation on FHB Effluent Radiation Monitors, A-RE-2532A(B) and A-RE-2533A(B).
- The FHB HVAC system responds as designed.
The crew enters 18006-C, Fuel Handling Event and is at the step to verify proper FHB Post Accident Exhaust Filtration Unit alignment.
Which one of the following is correct regarding the operator actions to take, per 18006-C, and the reason for the actions?
A. Stop one unit, this limits the offsite dose release.
B. Start an additional unit, this limits the offsite dose release.
C. Stop one unit, this limits airborne concentrations in the FHB atmosphere.
D. Start an additional unit, this limits airborne concentrations in the FHB atmosphere.
Page 29 of 75
HL-17 NRC Exam 30.
Unit 2 is shutting down from 100% Rated Thermal Power in response to a steam generator tube leak per 18009-C, Steam Generator Tube Leak.
Charging flow has been adjusted to maintain PRZR level.
With no additional adjustments to charging being made, which one of the following correctly states the trend of the estimated leak rate during the power reduction and the reason for the trend?
Estimated leak rate will as power is reduced.
A. lower, because RCS pressure to leaking SG pressure difference lowers B. lower, because air ejector flow rate would lower thereby lowering the indication on 2RE-Q81Q SJAE Exhaust Rad Monitor C. remain the same, because air ejector flow rate remains constant thereby the indication on 2RE-0810 SJAE Exhaust Pad Monitor remains constant D. remain the same, because N-16 gamma production is independent of power, thereby the indication on 2RE-0724 N-16 Rad Monitor remains constant Page 3Oct75
HL-17 NRC Exam 31.
1 is at 100% power.
Unit Maintenance testing of the Main Steam Safety valves is in progress.
The following test results are obtained for the valve lift settings:
1 PSV-3002 1205 psig 1PSV-3011 1210 psig 1 PSV-3022 1160 psig NO valve lift setting adjustments have been made.
Based on this data, which one correctly completes the following statement?
A total of 41) Main Steam Safety Valve(s) is(are) not within the allowable lift settings and the MAXIMUM Allowable Power Range Neutron Flux High Trip Setpoint per Tech Specs is 42)_____
REFERENCE PROVIDED A. One 71%
B. One 51%
C. Two 71%
D. Two 51%
Page 31 of 75
HL-17 NRC Exam 32.
Given the following plant conditions:
- Unit 1 is at EOL.
- A Reactor Startup is being planned.
- The Estimated Critical Condition (ECC) calculation predicts criticality at 100 steps on Control Bank D.
Which one of the following conditions will result in critical rod height being HIGHER than the value predicted by the ECC?
For your answer, consider that no operator actions are taken to mitigate or compensate for the below events.
A. A dilution of 500 gallons is performed.
B. Aux Feedwater flow is RAISED to all SGs.
C. A Post Maintenance Test results in the closure of all MSIVs.
D. A Reactor startup to occur 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after unit shutdown from 100% power.
Page 32 of 75
VOSTLE WRITTEN EXAM 2012-301 QUESTION? RESPONSE DOCUMENTATION FOR USE BY APPLICANT Applicant Asking Question:
Time Question Asked: 06&i Question Number: 3 Z Question Being Asked: LJi4r , ii( rIME SI.JCE çI..JTDOLJ e JlA7 Po$I CEJEL r0e ,7,C 1 oi6I.
C J rcP cALcuLA r,o4 FOR USE BY PROCTOR Response To Applicant:
- 1k flAc7c!z 7% 75flftJ 9 p4siv&
A ,Mm vrüp nn joo7. foul CL A Fg /DO Zy ITA.oy o/6RMiOsJ..
Time Response Provided To Applicant:
/0W Proctors Initials:
Applicants InitiaIsf
> -U 11
-o C Or!> 1 CD 0 C D -c 0 Cr - CD Ct 0
-n -
-_-1_______ 1: C CD C
- 0 %
C , N C 0 D) C H Cr Cl) - 5 r U N -
c D Cl) m
° a m m a: H z cr >
C a:
-, 0 30 I 9?
S D
-u D > H CD 0 I U? CD >
0 > Cr) -o H 0 CD - 0 -t m C) - r C, C CD C z
- CD
-1 a CD C-) m 0 K I 0 z >
r 2
-I
£0 0
VP c -
0 1
tn
- 5
-L.
I N N
I C C
in N N CD H
A N 0 z
-4 I
m
-- CD
-S -s N
-S -U CT 0 N. z
-S CD
- S -) m
- C 0
C-)
-N C N
-s )
C m z
H H
0 z
HL-17 NRC Exam 33.
Initial conditions:
- Unit 1 is at 100% power.
Current conditions:
- Reactor power is 100.4% and slowly rising.
- ACS pressure is 2212 psi 9 and slowly lowering.
- Turbine load is 1200 MWe and lowering.
- Containment pressure is 1.4 psig and rising.
- Containment temperature is 117.5°F and rising.
Which one of the following correctly completes the following statement?
A _j1) break is the event in progress and per 18008-C, Secondary Coolant Leakage, the FIRST action the operators will perform is to _(2)_.
2)..
A. steamline reduce turbine load B. steamline manually insert rods C. feedline reduce turbine load D. feedline manually insert rods Page 33 of 7$
HL-17 NRC Exam fl34.
r Unit 1 initial conditions:
- Power is 100%.
- Steam Dumps are in the Tavg mode.
Current conditions:
- Main Turbine automatically trips.
- Reactor Trip Breaker A opens.
- Reactor Trip Breaker B is CLOSED and cannot be opened.
Based on the current conditions, which one of the following correctly completes the following statement, if no other operator actions are performed?
RCS Tavg will be controlled at(1) due to Steam Dumps controlling on the _j2) controller.
fll ) 2)
A. 559°F plant trip B. 559°F load reject C. 557°F plant trip D. 557°F load reject Page 34 of 75
HL-17 NRC Exam 35.
Initial conditions:
- Unit 2 is at 55% power ramping up at 3% per hour.
- Condenser vacuum is lowering.
- ALB19-B04, TURB COND VAC LO alarms.
- 18040-C, Partial Loss of Condenser Vacuum, actions are in progress.
Current conditions:
- Power has been reduced to 45%.
- Condenser vacuum is 22.35 in Hg and lowering.
Based on the current conditions, a manual Reactor trip _41 )__ required by 18040-C, and the Steam Dumps 2) operate.
(1 ).... (2)
A. is will B. is will NOT C. is NOT will D. is NOT will NOT Page 35 of 75
HL-17 NRC Exam 36.
c: Unit 1 is at 1OO% power.
On a spurious Train A SI actuation, (1 ).... will trip and on a SG # 1 NR Hi-Hi Level, with all other SG NP levels in the normal band,
- 2) will trip.
(1 )
A. MFPT A only MFPT A only B. MFPT A only both MFPTs C. both MFPTs MFPT A only D. both MFPTs both MFPTs Page 36 of 75
HL-17 NRC Exam 37.
Initial conditions:
- A Loss of All AC power (station blackout) occurs on Unit 1.
- Power has been restored to 1AAO2.
- 1 BAO3 is de-energized.
- 19101-C, ECA-O.l Loss of All AC Power Recovery Without SI Required is in effect.
Current conditions:
- ALL SC pressures are 965 psig and stable.
- CETCs are 567°F and stable.
- Subcooling is 69°F and stable.
- RCS Hot leg temperatures are 563°F and stable.
- RCS Cold leg temperatures are 542°F and stable.
Which one of the following correctly completes the following statement?
Per 19101-C, natural circulation 41)_ occurring and based on the current conditions, automatic ARV operation is possible from SC ARVs 2) fll )_
A. is 2and3 B. is land4 C. is NOT 2and3 D. isNOT 1 and4 Page 37of 75
HL-17 NRC Exam
- 38. -____
Given the following:
- Following an LOSP, 19001-C ,ES-O.l Reactor Trip Response, is in progress.
- RCS pressure is 2045 psig.
- PSMS indicates BAD.
- ACS WA Hot leg Temperatures are as follows:
Loop 1 574°F Loop 2 572°F Loop 3 572°F Loop 4 577°F
- ACS WA Cold leg Temperatures are as follows:
Loop 1 553°F Loop 2 552°F Loop 3 552°F Loop 4 550°F
- CETCs are 580°F.
The expected subcooling value for the PSMS monitors is A 60°F B 63°F C 66°F D. 77°F Page 38 of 75
HL-17 NRC Exam fl39.
Given the following:
- DG1 B is running for the monthly surveillance.
- A loss of 125V DC 1E bus 1BD1 occurs.
Depressing the DG1 B Pull-to-Run / Push-to-Stop pushbutton _41 )__ shut off the fuel.
The DG1B output breaker is required to be opened using the LOCAL breaker (2)
A. will NOT TRIP pushbutton B. will NOT handswitch C. will TRIP pushbutton D. will handswitch L
Page 39 of 75
HL-17 NRC Exam 40.
Initial conditions:
- Unit 1 is operating at a steady state power level of 90%.
- All feedwater control systems in automatic.
Current conditions:
- STM GEN 2 FLOW MISMATCH annunciator illuminates.
- MFRV for Loop 2 is modulating in the OPEN direction.
Which one of the following channel failures caused the MFRV response?
A. S/G pressure transmitter failed low.
B. S/C feed flow transmitter failed high.
C. SIC steam flow transmitter failed high.
D. S/G narrow range level transmitter failed high.
Page 40 of 75
HL-17 NRC Exam Initial conditions:
MDAFW pump A is in automatic.
- MDAFW pump A mini-flow valve red light is LIT, green light is out on the ZLB on the QMCB.
- MDAFW pump B is in automatic.
- MDAFW pump B mini-flow valve is in LOCAL control on Shutdown Panel B with the red light LIT, green light out on the handswitch.
Current conditions:
- An AFW actuation starts both MDAFW pumps.
- AFW flows have risen to 300 gpm per SG.
Two minutes later, if an operator were monitoring at each location, which one of the following describes the light indications for the mini-flow valves for each of the MDAFW pumps?
MDAFW A mini-flow ZLB MDAFW B mini-flow handswitch on OMCB on Shutdown Panel B A. green light lit, red light lit green light out, red light lit B. green light lit, red light lit green light lit, red light out C. green light lit, red light out green light out, red light lit D. green light lit, red light out green light lit, red light out Page 41 of 75
I-IL-17 NRC Exam 42.
Initial conditions:
- The Unit 1 TDAFW pump has a mechanical overspeed trip during pump startup.
- TDAFW Pump Trip Throttle Valve handswitch (1 HS-1 5111) indicates green and amber.
Current conditions:
- 1 HS-1 5111 green light only is lit.
Based on the current conditions, the amber light EXTINGUISHED when the A. mechanical trip linkage was manually reset B. 1 HS-1 5111 was taken to the closed position C. motor operator reached the full closed position D. motor operator reached the 80% closed position Page 42 of 75
HL-17 NRC Exam 43.
Initial conditions:
- Unit 1 is at 100% power.
- All Train A required equipment is in service.
Current conditions:
- A loss of RAT A occurs.
- DG1A starts and re-energizes 1AAO2.
- The crew enters 18031-C, Loss of Class 1 E Electrical Systems.
Per 18031-C, which one of the following components will require a manual start to align to the emergency bus?
A. Containment Cooling Fans Train A B. Reactor Cavity Cooling Fan # 1 C. ACCWPump#1 D. SFP Pump A Page 43 of 7$
HL-17 NRC Exam fl44.
Initial conditions:
- Unit 1 is in Mode 3 due to a loss of both trains of NSCW.
- A leaking Train A NSCW load has been isolated.
- Crew determines Train A NSCW can be restarted in single pump operation.
Current conditions:
- 131 50A-1, Train A Nuclear Service Cooling Water System, Section 4.4.9, Train A NSCW Single Pump Operation (Abnormal) is being performed.
- ACCW HX valves have been throttled to their prestart positions.
Which one of the following is/are the NSCW Train A load(s) that must be ISOLATED prior to the restart of one NSCW pump?
A. Component Cooling Water heat exchanger B. Diesel Generator Jacket Water heat exchanger C. Control Building Engineered Safety Features Chiller D. Containment Auxiliary Cooler and Reactor Cavity Cooler Page 44 of 75
HL-17 NRC Exam 45.
Unit 1 is at 100% power.
- A loss of 1 25V DC distribution panel 1 AD1 1 occurs.
Which one of the following correctly completes the following statement?
DG1A .j1) be started, and if DG 1 A was running prior to the loss of 1 AD1 1, the stop pushbuttons on the QEAB
..j2) stop the DG.
.(j)......
A. can will NOT B. can will C. can NOT will NOT D. can NOT will Page 45 of 75
> -o H -n 0 o zi > T1 t -, . -
CD 0 C 0 0 0 CO I C) -o CO C, a a H
- C 0 g C
_/ 0 5* r 0 0 Cl) 0 Ci) m
- __.- m ci, m -%
0 z 0 Z
H 0 :z: CD C CO D C I 0 0 3g CD -o cm 0 H
-D CD > -u H or -u -D 2 Co CO
- 0 m 0 - x- 0 r z C) CD C C) N 0 4 C, m 0 - -
z R H C
NJ 1 C N)
C:)
C I
I 0
-4 C
N m (I)
H N 0 L z I
rn U)
-o 0
z Cl)
N m C
0 C-)
C m
z H
H 0
z
HL-17 NRC Exam 46.
Initial conditions:
Unit 2 is in Mode 3, normal operating temperature and pressure.
- CCP B is in service.
Current conditions:
- 125V DC bus 2BD1 is inadvertently de-energized.
Which one of the following correctly completes the following statement?
CCP B U )_ be shutdown from the QMCB, and CCP B breaker will (2) if a fault occurs on the pump motor.
A. can trip open B. can remain closed C. can NOT trip open D. can NOT remain closed Page 46 of 75
HL-17 NRC Exam 47.
Current conditions at full power:
- A problem with DG1 B starting air system has occurred.
To meet LCQ 3.8.3, Diesel Fuel Oil, Lube Oil, Starting Air, and Ventilation, a MINIMUM of j1 ) psig air receiver pressure must be available on a MINIMUM of DG1B starting air receiver(s).
41 )
A. 175 both B. 175 one C. 210 both D. 210 one Page 47°f 75
HL-17 NRC Exam 48.
Initial conditions:
- Both units are at full power.
Current conditions:
- Unit 1 is losing instrument air pressure.
- Unit 2 instrument air pressure is normal.
- Four air compressors total on BOTH units are running.
(one air compressor on Unit 1, three air compressors on Unit 2)
Which one of the following correctly completes the following statement?
Per 18028-C, Loss of Instrument Air, the Units instrument air headers (1) allowed to be cross-tied and if the cross-tie occurs, isolation of the Unit 2 instrument air header from Unit 1 instrument air header is required at a Unit 2 instrument air pressure of 42)_.
A. (1)are (2) 80 psig B. (1)areNOT (2) 95 psig C. (1)areNOT (2) 80 psig D. (flare (2) 95 psig Page 48 of 75
HL-17 NRC Exam Which one of the following correctly completes the following statement?
The Neutron Flux Low Range (Extended Range) monitor is located on Remote Shutdown Panel _(1) and if a fire results in a Unit 1 control room evacuation, per 18038-1, Operation From Remote Shutdown Panels, the Test / Status Control Switch in the Control Building is required to be placed to the (2)position.
(1 )
A. Train A Local B. Train A App R C. Train B Local D. Train B App R Page 49 of 75
HL-17 NRC Exam 50.
Given the following conditions:
- Transfer of Gas Decay Tank # 2 contents to Gas Decay Tank # 4 is in progress.
- Auxiliary Bldg HVAC is in service.
- High radiation alarms are received on the following Rad monitors:
1 RE-0039A Waste Gas Decay Tank Radiogas 1 RE-0039B Waste Gas Compressor & Catalytic Recombiner Radiogas-iRE-i 2442C Plant Vent Radiogas Particulate (Low Range)
Based on the given conditions, which one of the following correctly completes the following statement?
The Auxiliary Bldg HVAC will (1) and per procedure 17100-C, ARP for the Process and Effluent Radiation Monitoring System, the operators are required to A. (1) automatically trip (2) manually start the Piping Penetration Units B. (1) automatically trip (2) continue to monitor the radiation monitors. No additional actions with regards to Auxiliary Building HVAC are required C. (1) remain running (2) manually secure all Auxiliary Bldg HVAC D. (1) remain running (2) continue to monitor the radiation monitors. No additional actions with regards to Auxiliary Building HVAC are required Page 50 of 75
HL-17 NRC Exam Given the following:
- Unit 1 is in Mode 5 and Containment cleanup in progress following a substantial primary coolant leak.
- A high rad trash container will be moved through the Containment personnel air lock.
- The container is staged at the entrance to the open airlock 15 feet away from 1 RE-0004 Containment Hatch area rad monitor.
- 1 RE-0004 is reading 5 mr/hr.
- For your answer, consider that all of the 1 RE-0004 reading is due to the high rad trash container.
- During transport, the minimum distance from the container to 1 RE-0004 is 2 feet.
The distances listed above include any difference in height from the container to the radiation monitor detector. Consider the container a radiation point source.
Based on these conditions, which one of the following correctly identifies the MAXIMUM reading 1 RE-0004 will indicate during movement of the container through the air lock?
A. 2109 mr/hr B. 361 mr/hr C. 281 mr/hr D. 38 mr/hr Page 51 at 75
HL-17 NRC Exam fl2.
Given the following:
- An SO is preparing to flush RE-0018 following a pulse test in a field of 15 mr/hour prior to releasing a Waste Monitor Tank.
- The operators exposure limit is 7.5 mrem.
- The job task will take 20 minutes to perform.
How many mrem below his exposure limit will the operator be?
A. 1.25 mrem B. 2.50 mrem C. 5.00 mrem D. 7.50 mrem Page 52o1 75
HL-17 NRC Exam 53.
Initial conditions:
- The crew is performing 19221-C, FR-C.l Response To Inadequate Core Cooling.
- Safety Injection flow to the RCS can NOT be established.
Current conditions:
- The crew is depressurizing the SGs to depressurize the RCS.
- Atmospheric Relief Valves (ARVs) are being used for the depressurization.
Which one of the following correctly completes the following statements?
While depressurizing the SGs to 200 psig, ARV QMCB controllers will be _j1 )...........
and later, while depressurizing the SGs to atmospheric pressure, ARV controllers will be A. (1) throttled as needed to maintain a cooldown rate of < 100°F/hr in the cold legs (2) throttled as needed to maintain a cooldown rate of < 100°F/hr in the cold legs B. (1)throttled as needed to maintain a cooldown rate of < 100°F/hr in the cold legs (2) full open C. (1) full open (2) throttled as needed to maintain a cooldown rate of < 100°F/hr in the cold legs D. (1) full open (2) full open Page 53 of 75
HL-17 NRC Exam 54.
Given the following conditions:
- The plant is in Mode 3.
- Circulating Water Pump # 1 is running.
- A worker has fallen into the Circulating Water flume.
Which one of the following is correct regarding:
(1) required handswitch(es) to operate to Emergency stop the Circ Water pump, and (2) Circulating Water system response?
A. (1) Turn Emergency Trip Circ Water Pmp-1 to the Trip Permissive position.
(2) Circulating Water Pump 1 immediately trips.
B. (1) Turn Emergency Trip Circ Water Pmp-1 to the Trip Permissive position.
(2) Discharge valve travels to 70% closed, then Circulating Water Pump It 1 trips.
C. (1) Hold Emergency Trip Circ Water Pmp-1 in the Trip Permissive position AND turn Circ Water Pump 1 normal handswitch to the Stop position.
(2) Circulating Water Pump 1 immediately trips.
D. (1) Hold Emergency Trip Circ Water Pmp-1 in the Trip Permissive position AND turn Circ Water Pump 1 normal handswitch to the Stop position.
(2) Discharge valve travels to 70% closed, then Circulating Water Pump # 1 trips.
Page 54 of 75
HL-17 NRC Exam 55.
Initial conditions at full power:
- CCP B is in service.
Current conditions:
- A valve misalignment has resulted in a loss of NSCW cooling to the ACCW system.
- The crew has entered 18022-C, Loss of Auxiliary Component Cooling Water.
- Letdown has been isolated.
Which one of the following RCP components will reach its temperature limit the soonest for this event, AND includes the correct setpoint that requires a RCP trip per 18022-C?
A. RCP motor bearing; 195°F B. RCP motor bearing; 230°F C. RCP seal water inlet; 195°F D. RCP seal water inlet; 230°F Page 55 of 75
HL-17 NRC Exam 56.
r Initial conditions:
- Unit 1 is at 100% power.
- The Main Generator is operating at 1215 MW and 40 MVAIRs lagging.
- Main Generator hydrogen pressure is 60 psig.
Current conditions:
- A grid disturbance causes the Main Generator to go to 1200 MW and 400 MVARs lagging.
- The crew is performing 1801 7-C, Abnormal Grid Disturbances / Loss of Grid Section A Degraded Grid Conditions.
- The UO is at the step to maintain the generator within the limits of the Reactive Capability Curve.
Per 18017-C, which one of the following is the action (if any) the UO will perform?
REFERENCE PROVIDED A. No action required.
B. Establish 1215 MW using the INCREASE LOAD pushbutton on the Main Turbine Control Panel.
C. Establish 200 MVARS lagging using the RAISE touchscreen button on EX2100 Excitation Control Screen.
D. Establish 200 MVARS lagging using the LOWER touchscreen button on EX2100 Excitation Control Screen.
Page 56 of 75
HL-17 NRC Exam 57.
A Safety Injection has occurred on Unit 1.
At 10:00:
- 1 HV-9378, INSTR AIR CNMT ISO VLV has closed.
At 10:40:
- CIA has been reset.
- The UO attempts to open 1 HV-9378.
- 1 HV-9378 will NOT open.
Based on the present plant configuration, which one of the following valves inside Containment will fail OPEN?
A. 1 HV-0780, RX CAVITY AND CNMT SUMPS DISCH HDR ISO IRC B. 1HV-8141A, RCP SEAL LEAKOFF ISOLATION C. 1 HV-7126, RCDT VENT ISO VLV TO GWPS D. 1HV-8145, PZR AUX SPRAY VALVE Page 57o! 76
l-IL-17 NRC Exam 58.
A Halon Suppression System Fire Alarm has occurred for Control Building Level A.
C Which one of the following correctly completes the following statement?
The primary computer location for receipt of this alarm is 1).
and a MINIMUM of 2) detectors is required for the system to actuate.
..(1 ).... _(2)_
A. Main Contro Room three B. Main Control Room two C. Clearance & Tagging three D. Clearance & Tagging two Page 58 of 75
HL-17 NRC Exam 59.
Which one of the following correctly completes the following statement?
An automatic Containment Isolation Phase A (CIA) is DIRECTLY actuated by U) and the circuitry logic allows the CIA signal to be reset 2)__.
A. U) Containment Hi-i only (2) independently of any other safeguards actuation signal B. (1) Containment Hi-i only (2) only after SI has been reset C. (1) any automatic SI signal (2) independently of any other safeguards actuation signal D. (1) any automatic SI signal (2) only after SI has been reset Page 59 of 75
HL-17 NRC Exam 60.
You are performing a lineup verification for valves in various positions.
In accordance with NMP-OS-002. Verification Policy, for each case below, which one of the following is the correct method of verification?
A. Case A valve is required to be closed.
Method - Leave valve as is, use local valve stem or positioner indications to verify the valve position.
B. Case - A valve is required to be throttled 2 turns open.
Method Turn valve in the closed direction, count turns to ensure correct, re-open the valve 2 turns.
C. Case - A valve is found not in the required lineup position.
Method - Align valve in the required position, notify the SS after the valve is properly aligned, do NOT continue until SS permission to continue the line-up is obtained.
D. Case - A valve position cannot be determined by local observation.
Method - Leave valve as is, use remote handswitch light indications to verify the valve position.
Page 60 of 75
HL-17 NRC Exam 61.
Given the following:
- Unit 1 Control Room is being evacuated due to a fire.
- The crew is fully staffed.
In accordance with 18038-1, Operation From Remote Shutdown Panels, the (1) will be dispatched to Shutdown Panel C (TDAFW Pump Room) and the PREFERRED method of communications to coordinate in plant activities with personnel outside the control room is via 2)..
A. (1) Systems Operator (2) bridge phone extension 3145, codes 123# or 234#
B. (1) Unit Operator (2) bridge phone extension 3145, codes 123# or 234#
C. (1) Systems Operator (2) sound powered telephones (red box)
D. (1) Unit Operator (2) sound powered telephones (red box)
Page 61 of 75
HL-17 NRC Exam 62.
Given the following:
- Time=0700.
- 1 2003-C, Reactor Startup (Mode 3 to Mode 2) is in progress.
- SR NIS counts are 400 cps and increasing slowly.
- The 1IM projects criticality to occur below the insertion limit.
- 1/M value is at 0.08.
- Time=0707.
- The OATC has inserted control bank rods 770 pcm.
- After all rod motion stops, SR NIS counts are 300 cps and increasing slowly.
- Time=0730.
- No rod motion has occurred since 0707.
- SR NIS counts have stabilized at 680 cps.
Which one of the following correctly completes the below statements?
In accordance with 12003-C, at 0730 the audio count rate 1)..... required to be in service.
In accordance with 12003-C, at 0730 a manual reactor trip (2) required.
A. (1)is (2) is B. (1)is (2) is NOT C. (1) is NOT (2) is NOT D. (1) is NOT (2) is Page 62 of 75
HL-17 NRC Exam 63.
Which one of the following correctly completes the statement below?
Per 00354-C, Maintenance Scheduling, a(n) is NOT a Mitigating System Performance Index (MSPI) monitored equipment.
A. Centrifugal Charging Pump B. Nuclear Service Cooling Water Pump C. Containment Cooler D. Emergency Diesel Generator Page 63 of 75
HL-17 NRC Exam 64.
Which one of the following correctly completes the statement below?
j1 ).. has local-remote transfer switches for the Diesel Generator Fuel Oil Transfer Pumps that are physically located at (2)..
(1 )
A. Unit 1 480V 1E bus 1BBF B. Unit 2 480V 1E bus 2BBF C. Uniti Unit 1 Shutdown Panel B D. Unit 2 Unit 2 Shutdown Panel B Page 64 of 75
HL-17 NRC Exam 65.
Initial conditions:
- Unit 1 is at 100% power.
- A Steam Generator Tube Rupture occurs on SG # 3.
Current conditions:
- 19030-C, E-3 Steam Generator Tube Rupture is in progress.
- The crew is performing the actions to isolate SG # 3.
Which one of the following correctly completes the following statement?
The ruptured SG ARV controller setpoint is adjusted to approximately _(1 )_
and the reason for this adjustment is to _(2)_.
A. (1)ll2Opsig (2) minimize radiation releases through the ARV and prevent lifting of SG safeties B. (1)lleOpsig (2) minimize radiation releases through the ARV and prevent lifting of SG safeties C. (1)ll2Opsig (2) promote thermal stratification and prevent an uncontrolled SG depressurization through the rupture D. (1)ll6Opsig (2) promote thermal stratification and prevent an uncontrolled SG depressurization through the rupture Page 65 of 75
HL-17 NRC Exam 66.
Core offload is in progress during a refueling outage.
- CNMT area rad monitors RE-002 and RE-003 HIGH radiation alarms illuminate.
- 18006-C, Fuel Handling Event is entered.
Which one of the following correctly completes the following statement?
Per 93300-C, Conduct of Refueling Operations, the OATC _j1 )__ have the authority to suspend core alterations and per 18006-C, Fuel Handling Event, the Containment evacuation page announcement will instruct personnel to 42).
_(2)
A. does report to the Control Building HP Control Point for radiological monitoring B. does exit CNMT and remain in the vicinity until radiological monitoring and accountability are complete C. does NOT report to the Control Building HP Control Point for radiological monitoring D. does NOT exit CNMT and remain in the vicinity until radiological monitoring and accountability are complete Page 66 of 75
HL-17 NRC Exam 67.
Given the following on Unit 1:
- Steam Generator # 2 is ruptured.
- ARV # 2 is lifting and steam is blowing toward the Control Room OSA Intake.
- Control Room Air Intake monitors 1 RE-12116 and 1RE-12117 are in HIGH alarm.
Which one of the following correctly completes the following statement?
Per 13301-1, CBCR Normal HVAC and Emergency Filtration System, the Control Room crew will verify the Control Room HVAC is in the ..j1 ). Mode of operation and (2) ESF Chiller(s) will automatically start.
_(1)_
A. Isolation both B. Isolation only Train B C. Recirculation (Filtration) both D. Recirculation (Filtration) only Train B Page 67of 75
HL-17 NRC Exam 68.
Given the following:
- A preplanned maintenance activity is taking place that has caused multiple control room annunciators.
- The alarms have NOT previously been identified and flagged.
- The responding operator acknowledges the alarms, announces the alarms as expected and the reason.
Per NMP-OS-007-OO1, Conduct of Operations Standards and Expectations, which one of the following is correct?
For the expected annunciators, subsequent recurring alarms associated with this activity 41 ) require announcement and for the expected annunciators, annunciator response procedure compensatory actions required to be performed.
(1)
A. do are B. do are NOT C. do NOT are D. do NOT are NOT Page 68 of 75
HL-17 NRC Exam 69 Initial conditions A loss of all AC power has occurred.
- 1AAO2 has been re-energized by DG1A when an emergency trip of the DC occurs.
Current conditions:
- The UO directs the System Operator at DG1A to start the DG by depressing the Emergency Stop Reset pushbutton.
- DG1A starts when the Emergency Stop Reset pushbuffon is depressed.
- This was the ONLY action the System Operator had to take to start the DC, NO other actions had previously been taken.
Which one of the following annunciators correctly reflects the condition that caused the DG1A emergency trip?
A. DG1A TRIP GEN DIFF B. DG1A TRIP OVERSPEED C. DG1A TRIP LOW PRESS LUBE OIL D. DG1A TRIP HI TEMP JACKET WATER Page 69 of 75
HL-17 NRC Exam 70.
Initial conditions:
- The crew is performing 1901 2-C, ES 1.2 Post LOCA Cooldown and Depressurization.
- Reactor Trip Breakers are OPEN.
- SI has been RESET.
- RCS pressure is 1900 psig and slowly lowering.
- Low Steam Line Pressure SI/SLI has just been BLOCKED.
- All SG pressures are 800 psig and slowly lowering.
Current conditions:
- A main steam line ruptures inside Containment.
Which one of the following ESF functions will automatically actuate (if any)?
A. Containment Hi-i SI only.
B. High Steam Pressure Rate SLI only.
C. BOTH Containment Hi-i SI and High Steam Pressure Rate SLI.
D. NEITHER Containment Hi-i SI nor High Steam Pressure Rate SLI.
Page 70 of 75
HL-17 NRC Exam 71.
Initial conditions:
- The crew is performing 19112-C, ECA 1.2 LOCA Outside Containment.
Current conditions:
- RCS pressure is 1500 psig.
Which one of the following correctly completes the following statement?
The FIRST system to be isolated from the RCS to attempt leak isolation is j1),
and the instrument that will be used to determine isolation of leak is A. (1)S1 (2) PFRZP pressure B. (1)RHR (2) RCS WR pressure C. (1)S1 (2) RCS WA pressure ID. (1)RHR (2) PRZR pressure Page 71 of 75
HL-17 NRC Exam H2. -
Initial conditions:
- 19231-C, FR-Hi Response to Loss of Secondary Heat Sink is in progress.
- RCS Bleed and Feed has been initiated.
Current conditions:
- One SIP is running.
- The CCPs and other SIP are NOT available.
- One PRZR PORV is open.
- The other PORV is NOT available.
Per 19231-C, which one of the following correctly completes the following statement?
One SIP running is 1) for the RCS Feed path and one PRZR PORV open is 42)_ for the RCS Bleed path.
For the purposes of this question, adequate as defined by procedure 19231-C means that 19231-C will NOT direct further adjustments to the RCS Feed or Bleed path.
(1 )_
A. adequate adequate B. adequate NOT adequate C. NOT adequate adequate D. NOT adequate NOT adequate Page 72 of 75
HL-17 NRC Exam 73.
19241-C, FR-P.l Response to Imminent Pressurized Thermal Shock Condition, has been entered on Unit 1.
- A one hour soak is required.
Which one of the following correctly completes the statement below?
The soak allows thermal gradients to be reduced, thus reducing corresponding _(1) stresses on the Reactor vessel inner wall and it a cooldown is required AFTER the soak, the MAXIMUM cooldown rate per 19241-C is 2) in any 60 minute period.
A. (1) compressive (2) <50°F B. (1) compressive (2) <100°F C. (1)tensile (2) < 50°F D. (1) tensile (2) < 100°F Page 73 of 75
HL-17 NRC Exam 74*
From the choices below, which one of the following is the FIRST major action to attempt to perform per 19111-C, ECA-l .1 Loss of Emergency Coolant Recirculation?
A. Depressurize the SOs to cooldown and clepressurize RCS.
B. Depressurize the RCS to minimize P05 subcooling.
C. Initiate RCS cooldown to cold shutdown.
D. Increase I Conserve RWST inventory.
Page 74 of 75
HL-17 NRC Exam Per 19200-C, F-O Critical Safety Function Status Trees, the MINIMUM setpoint where an ORANGE condition on Containment based on Emergency Sump level will occur is A. 101 inches B. 105 inches C. 109 inches D. 113 inches Page 75of 75
MSSVs 3.7.1 C 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)
LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and Table 3.7.1-2.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS TE Separate Condition entry is allowed for each MSSV.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MSSVS A.1 Reduce power to less 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable, than or equal to the applicable % RTP listed in Table 3.7.1-1.
AND A.2 Reduce the Power Range 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Neutron Flux-High trip setpoint to less than or equal to the applicable
% RTP listed in Table 3.7.1-I.
(continued)
Vogtle Units 1 and 2 3.7.1-1 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
MSSVs 3.7.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
OR B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> One or more steam generators (SG) with four or more MSSVs per SC inoperable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 NOTE Only required to be performed in MODES 1 and 2.
Verify each required MSSV lift setpoint per In accordance with Table 3.7.1-2 in accordance with the Inservice the Inservice Testing Testing Program. Following testing, lift settings Program shall be within +/- 1%.
Vogtle Units 1 and 2 3.7.1-2 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)
Maximum Allowable Power Range Neutron Flux High Trip Setpoint with Inoperable Main Steam Safety Valves MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH NUMBER OF INOPERABLE TRIP SETPOINT MSSVs PER STEAM GENERATOR (% RTP) 1 71 2 51 3 31 Vogtle Units 1 and 2 3.7.1-3 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)
Main Steam Safety Valve Lift Settings VALVE NUMBER LIFT SETTING STEAM GENERATOR (psig + 2%, -3%)
- 1 #2 #3 #4
- 1. PSV3001 PSV3O11 P5V3021 PSV3O31 1185 psig
- 2. P5V3002 P5V3012 P5V3022 PSV3032 1200 psig
- 3. PSV3003 PSV3O13 PSV3023 PSV3033 1210 psig
- 4. PSV3004 PSV3O14 P5V3024 PSV3034 1220 psig
- 5. P5V3005 P5V3015 PSV3025 PSV3035 1235 psig Vogtle Units 1 and 2 3.7.1-4 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
- Approved By Procedure Number Rev J.B. Stanley Vogue Electric Generating Plant 18017-C 9 Date Approved ABNORMAL GRID DISTURBANCES/LOSS OF 08/22/20 1 1 GRID FIGURE 1 Sheet 1 of 1 REACTIVE CAPABILITY CURVE A
0) a CU
-j CL:
CU
-J V
U OO 4Cc £0) ieoo noo 140: 1600 12cc I MWatt! (Red operatir punt irdicaas regatve watts)
Printed April 12, 2012 at 09:12
HL-17 NRC Exam Examination KEY
-Answers 001A3JI -
2 OOIAAI.02 I B 3 003K2.02 I A 4 004A2.21 1 A 5 004K3.06 I A 6 005A1.03 I C 7 006012.4 1 A 8 007A206 I C 9 007EG2.4.2 I B ID 008A308 I C Ii 008AK3.04 I C 12 0101(5.02 I D 13 0101(6.03 I B 14 01lK2.0I I A IS 012K1.06 I B 16 0121(4.09 I A 17 013A4.0l I C 18 0I5AK2.I0 I C 19 01502.4.45 I B 20 016K1.091 B 21 022A4.0l I A 22 022AG2.2.42 I D 6 24 025AK2.03 I 026A1.06 I B
C 25 026AA1.03 I D 26 0621(2.01 I D 27 028A2.02 I B 28 029EK1.0l 1 A 29 036AK3.03 I A 30 037AK1.02 I A 31 03902.1.25 I C 32 039K5,08 I C 33 O4OAAI201 A 34 0411(3.02 I B 35 051AA2.02 I B 36 054AA2.02 I D 37 055EA2.02 I B 38 056AK1.03 1 A 39 058AK3.0I I C 40 059K408 I C 41 061A3.04 I c 42 0611(6.02 I A 43 062A211 I D 44 062AA2.03 I D 45 063K30I I B 46 063K4.04 I D Page? of2
HL-17 NRC Exam Examination KEY Answers ID 0 064K6.07 I D 48 065AK3.04 I A 49 068AA2.IO I D 50 071A1.06 1 D 51 072K5.02 I C 52 073K5.03 I B 53 074EA125 I D 54 075K4.OI I C 55 076K1.09 I A 56 077AK1.02 I D 57 078K3.OI I B 58 0R6A4.06 I B 59 103K1.08 I C 60 02.1.29 I D 61 G2.I.8 I C 62 02.2.1 I B 63 02.2.17 I C 64 G2.2.3 I B 65 02.3.111 B 66 G2.3.I3 I B 67 02.3.14 I C 68 02.4.3! I C 9 02.4.46 I C 70 WEO3EK2.l I B 7! WEO4EAI.3 I B 72 WEO5EK2.1 I B 73 WEO8EK3.4 I C 74 WE! IEG2.4.6 I D 75 WE!5EG2,I.32 B Page 2of2