IR 05000338/2002301
| ML023100248 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/14/2002 |
| From: | Ernstes M Division of Reactor Safety II |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| 50-338/02-301, 50-339/02-301 | |
| Download: ML023100248 (154) | |
Text
Draft Submittal (Pink Paper)
NORTH ANNA EXAM 2002-301 50-338 AND 50-339 JUNE 6 AND JUNE 10- 25, 2002 DRAFT Reactor Operator/Senior Reactor Operator Written Exam
1. 001A3.05 001/T2G1/T2G1/ROD CONTROL/C/A 3.5/3.5/MINA0230I/C/RA/LM The Rod Control Startup Reset push-buttons are inadvertently depressed while Unit 1 is at 100% powe Which one of the following describes the control room indication(s) and alarm(s) that will change as a result of this action?
A. The Rod Banks A/B/C/D Low Limit and Low Low Limit the step counters will go to the full-out positio B. The Non-Urgent Failure alarm will annunciate and the full-out positio C! The Rod Banks A/B/C/D Low Limit and Low Low Limit the step counters will go to zer D. The Non-Urgent Failure alarm will annunciate and the Rod Deviation/Sequence Alarm will annunciate.
MCS Time:
I alarms will annunciate and step counters will go to the alarms will annunciate and Computer Alarm Power Tilt Points:
1.00 Version:
0 1 2 34 5 6 7 8 9 Answer: CDDAAAABAC Scramble Range: A - D RO Tier:
Key Word:
Source:
Test:
T2GI ROD CONTROL M
C Tuesday, November 05, 2002 03:19:17 PM SRO Tier:
Cog. Level:
Exam:
Misc:
T2G I C/A 3.5/ NA02301 RA/LM
2. 001AK 1.03 001/T1G2/T lG1/ROD CONTROL/C/A 3.9/4.0/M/NA02301/C/RA/LSM/SC A. Correct B. Pressurizer level would not increase C. Reactor power would lower D. Would not effect pressurizer Original question:
ID: 2892 Points: 1.00 The unit is at 90% power with the turbine in IMP-OUT. If a continuous control rod withdrawal occurred, which one of the following items would NOT be a consequence? Pressurizer level increase Reactor power increasing Reactor Coolant System Tavg/Tref deviation Rod control urgent failure Answer:
D MCS Time:
I RO Tier:
Key Word:
Source:
Test:
Points:
1.00 TIG2 ROD CONTROL M
C Version:
0 1 234567 Answer: ACCBABCA SRO Tier:
Cog. Level:
Exam:
Misc:
C B Scramble Range: A - D TIGI C/A 3.9/ NA02301 RA/LSM/SC
Tuesday, November 05, 2002 03:19:17 PM The unit is at 90% power with the turbine in IMP-OU The following conditions occur Pressurizer level is increasing Reactor power is increasing Reactor Coolant System Tavg/Tref deviation alarm is li Which one of the following has occurred?
AO a continuous control rod withdrawal has occurre B. a main steam leak has occurre C. selected impulse pressure channel has failed lo D. B LoopTc has failed hig. 001G2.1.12 001//TIGI/TS BASIS/C/A 2.9/4.0/NEW/NA02301/S/RA/LSM/SC Tuesday, November 05, 2002 03:19:17 PM The LCO for Technical Specification 3.1.4 Rod Group Alignment Limits reads as follows:
LCO 3. All shutdown and control rods shall be OPERABL AND Individual indicated rod positions shall be within 12 steps of their group step counter demand positio NOTE When THERMAL POWER is less than or equal to 50% RTP, the indicated position of each rod as determined by its individual rod position indicator may be within 24 steps from its group step counter demand position for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This NOTE is not applicable for control rods known to be greater than 12 steps from the rod group step counter demand positio Which one of the following is the basis for this note?
A' To allow stabilization of known thermal drift in the individual rod position indicator channel B. To ensure that local power density increases due to a misaligned RCCA will not cause the core design criteria to be exceede C. This represents the time necessary for determining the actual unit SDM and, if necessary, aligning and starting the necessary systems and components to initiate boratio D. To allow the determination of hot channel factors and to ensure that the shutdown margin is within limits within one hour.
Rod Group Alignment Limits B 3. BASES North Anna Units 1 and 2 B 3.1.4-5 Rev 0 (Draft 2), 09/18/00 LCO The LCO has been modified by a Note. The Note permits a wider tolerance on indicated rod position for a maximum of one hour in every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to allow stabilization of known thermal drift in the individual rod position indicator channel This thermal soak time is available both for a continuous one hour period or several discrete intervals as long as the total time does not exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and the indicated rod position does not exceed 24 steps from the group step counter demand position. This allowance applies to the indicated position of the rod, not its actual position. If the actual position is known to be greater than 12 steps from the group step counter demand position, the Conditions and Required Actions of the specification must be followe Reduction of power to 75% RTP ensures that local LHR increases due to a misaligned RCCA will not cause the core design criteria to be exceede Power operation may continue with one RCCA OPERABLE but misaligned, provided that SDM is verified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> represents the time necessary for determining the actual unit SDM and, if necessary, aligning and starting the necessary systems and components to initiate boration. Since the core conditions can change with time, periodic verification of SDM is required. A Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient to ensure this requirement continues to be me MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ADACDCCBAA Scramble Range: A - D RO Tier:
SROTier:
TIGI Key Word:
TS BASIS Cog. Level: C/A 2.9/ Source:
NEW Exam:
NA02301 Test:
S Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:17 PM
4. 001K2.05 001/T2G1//RPS MOTORS/M 4.2/4.2/NEW/NA02301/R/RA/LM/SC What are the sources of power for the RPS motor generator sets?
The rod drive motor generator sets receive power from which one of the following?
Station service 480-volt busses:
A. A and C on unit 1 and B and C on unit BY B and C on unit 1 and A and C on unit C. A only on unit 1 and C only on unit D. C only on unit 1 and B only on unit 2.
REF: Lesson Plan for Rod Control System (65) page 20 9/24/01 OBJ: 2.3.4a Distractor A - Incorrect B - Correct Distractor C - Incorrect Distractor D - Incorrect MCS Time:
I Points:
RO Tier:
Key Word:
Source:
Test:
T2G I RPS MOTORS NEW R
Tuesday, November 05, 2002 03:19:18 PM Station service 480 volt bus B and C supply MG 2.1.U-1 MG 2.1.U-1 is not supplied from Station service 480 volt bus A MG 2.2.U-2 is not supplied from Station service 480 volt bus B 1.00 Version:
0 1 23456789 Answer: BCACADAADB Scramble Range: A - D SRO Tier:
Cog. Level:
M 4.2/ Exam:
NA02301 Misc:
RA/LM/SC
5 002K6.02 001/T2G2/T2G2/RCP TRIP/M 3.6/3.8/BANK/NA02301/C/RA/GWL Bank Question. North Anna Exam Bank. Question # 378 Lesson Plan Reactor Coolant System. #38 Objective MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CDCDAACCCA RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
RCP TRIP Cog. Level:
M 3.6/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/GWL Scramble Range: A - D Tuesday, November 05, 2002 03:19:18 PM-Unit 2 is holding at 20% Power for Chemistr "B" Reactor Coolant Pump Trip Which one of the following correctly describes how steam flow and water level in the
"B" Steam Generator respond initially to the trip of the "B" Reactor Coolant Pump?
A. steam flow increases, level increase B. steam flow decreases, level increase Cf steam flow decreases, level decrease D. steam flow increases, level decreases.
6. 003A4.02 001/T2GI/T2G1/LOSP/C/A 4.3/4.5/NEW/NA02301/C/RA/LM/SC Unit I is operating at 100 % power. Off site power is lost, however, the EDGs start and load. Which one of the following conditions support(s) or indicate(s) Natural Circulation flow is occurring within the RCS?
A. RCS hot legs are at saturation temperature for S/G pressur BY RCS subcooling based on Core exit TCs are 30 degrees C. RCS Tave is INCREASING D. Pressurizer level is DECREASING and RCS Tave is INCREASING REF: Reactor Trip or Safety Injection, EOP 1-E-0 Revision 27 OBJ: 12484 Distractor A - Incorrect - RCS hot leg temperatures stable or decreasing would support or indicate Natural Circulation flow occurrin B - Correct Distractor C - Incorrect - RCS Tave increasing by itself is not clear support or indicate Natural Circulation flow occurring Distractor D - Incorrect - PZR level decreasing and RCS Tave increasing is not support or indication of Natural Circulation flow occurrin MCS Time:
I Points:
1.00 Version:
0 1 234 5 67 8 9 Answer: BCCDBCACDC Scramble Range: A - D RO Tier:
T2GI SRO Tier:
T2GI Key Word:
LOSP Cog. Level: C/A 4.3/ Source:
NEW Exam:
NA02301 Test:
C Mise:
RA/LM/SC Tuesday, November 05, 2002 03:19:18 PM
7. 003AK3.04 001/T 1G2/T 1G1/ROD DROP/C/A 3.8/4.1/NEW/NA02301/C/RA/LSM/SC Unit 1 is at 60 % power when an oscillator in the Rod Control logic cabinet fails during rod movemen You receive a ROD CONTROL URGENT FAILURE alarm. Power to all of the stationary and movable coils have dropped to zero. No other logic or electrical failures have occurred. Which one of the following is your required action?
A! Enter E-0, Reactor Trip or Safety Injectio B. Enter AP-11.2, Dropped Ro C. Enter AP-1.1, Continuous Rod Motio D. Enter AP-11.3, Control Rod out of Alignmen Enter E-0 because all rods will drop MODULE NCRODP-65 multiplexing erro The regulation and phase failures feed a common detector card, referred to as the failure detector card. A phase or regulation failure indicates that the CRDM coil(s)
may be overheating, a thyristor supplying power to a CRDM is faulty, or one of the three phases to the power cabinet has been lost. A logic error card senses power to the stationary and movable coils. If voltage to both coils is zero at the same time, the urgent alarm actuates. This condition would result in a dropped control rod, since no gripper coils are energized. A multiplexing error will actuate the alarm when a lift or movable thyristor in the power cabinet(s) fails, causing a multiplexing erro The logic cabinet failures which result in the ROD CONTROL URGENT FAILURE alarm are as follows: oscillator failure, slave cycler failure, or printed card removed from normal positio Failure of the oscillator in the logic cabinet can result in improper sequencing of the CRDM coils, or a dropped control rod. Failure of the slave cycler indicates that logic signals between the master cycler and the slave cycler are not being coordinated properl Tuesday, November 05, 2002 03:19:18 PM
MCS Time:
RO Tier:
Key Word:
Source:
Test:
T1G2 ROD DR NEW C
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ACCCADACAA Scr SRO Tier:
TiGI OP Cog. Level:
C/A 3.8/ Exam:
NA02301 Misc:
RA/LSM/SC amble Range: A - D
Tuesday, November 05, 2002 03:19:18 PM
8. 003K3.02 001/T2GI/T2G1/RCS FLOW TAP/C/A 3.9/4.2/NEW/NA02301/C/RA/LM/SC REF:
OBJ: Topic 8.14a Terminal Knowledge Objective 12003 Distractor A Incorrect - RCS loop flow has no control function Distractor B Incorrect - Loss of the high side tap will indicated decreased flow and result in a reactor trip.
Distractor C Incorrect - The reactor is above the P8 setpoin D Correct MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DADADAADBC RO Tier:
T2G1 RCS FLOW TAP Source:
NEW C
Scramble Range: A - D SRO Tier:
T2G0 Cog. Level: C/A 3.9/4.2 Exam:
Misc:
NA02301 RA/LM/SC Tuesday, November 05, 2002 03:19:18 PM Key Word:
Test:
The following plant conditions exist:
All RCPs are runnin Reactor Power is 90% by Power Range Ni "C" Reactor Coolant Loop Flow Transmitter High Pressure Tap break Which one of the following describes the effect of this loss on the RPS (disregard any effects on containment)?
Loss of the flow tap in RCS loop "C" will:
A. only effect the RCS control function and not affect RPS or continued plant operatio B. provide a higher than normal flow signal and not affect RPS or continued plant operatio C. have no effect on reactor powe DW result in a reactor tri. 004G2.1.27 001/T2G1/T2GI/VCT LEVEL/C/A 3.2/3.3/BANK/NA02301/C/RA/LM/SC Given the following plant conditions:
- Unit 1 is at 100% power, with CVCS aligned for normal operatio One orifice is in servic VCT level is 32%.
- All controls are in automatic, 1-CH-LT-112, VCT level transmitter, fails hig Which one of the following describes the final actual VCT level? (Assume no operator action.)
A. Automatic VCT make-up capability is lost, and the VCT level decreases until charging pump suction automatically shifts to the RWS B. Continuous VCT automatic makeup occurs causing the VCT to overfill and the VCT relief valve lift C.0 1-CH-LCV-115A, VCT level control valve, will divert to the stripper, and VCT level will cycle due to automatic makeu D. 1-CH-LCV-1 15A, VCT level control valve, will receive an open demand, but will not open until the setpoint on 1-CH-LCV-112C, VCT level controller is exceede Normal VCT level will be maintained.
REF:Bank question 5546 OBJ: Chemical & Volume Control 237 Question Comment Level will cycle between 20% and 40% because makeup flow is greater than flow through LCV-1 1 Distractor A Incorrect - Level will initially decrease as LCV-1 15 diverts. Level will decrease until auto Makeup starts but will stop increasing when auto makeup stop Distractor B Incorrect - Level will not overfill because auto makeup will stop and with LCV-1 15 open level will begin decreasin C Correct Distractor D Incorrect - There is no 1-CH-LCV-1 12C interlock with 1-CH-LCV-1 15 MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CCCBADCCAC Scramble Range: A - D Tuesday, November 05, 2002 03:19:18 PM
RO Tier:
T2GI SRO Tier:
T2G1 Key Word:
VCT LEVEL Cog. Level:
C/A 3.2/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LM/SC Tuesday, November 05, 2002 03:19:18 PM
10. 004K5.01 00 1/T2Gl/T2G1/VCT/C/A 2.7/3.3/NEW/NA02301/C/RA/LSM/SC Which one of the following is the reason for maintaining a hydrogen cover gas in the CVCS VCT during normal at power operation?
A. To assure N-1 6 concentrations are ALAR B. To maintain hydrogen concentrations above the TRM lower limi C. To maintain conductivity below.017 Micro Mho Df To maintain oxygen concentration below the TRM upper limit.
REF: NCRODP-41-NA pages 13, 91-93; NAPS TRM B3.4.1 pages B3.4.1-1 - B3.4.1-3 OBJ: 343 (SOER-97-1)
Distractor A - Incorrect - the use of hydrogen is not dependent on ALARA considerations of N-16 activiatio Distractor B - Incorrect - hydrogen is not added to the VCT to prevent reaching an explosive mixtur Distractor C - Incorrect - radioactive gases in the VCT are collected by Primary Vents and Drains System from CVC D - Correct - hydrogen is absorbed in the VCT water and helps scavenge oxygen in the RCS. Maintaining oxygen concentration less than the TRM limits with Tavg greater than or equal to 250 F provides adequate corrosion protectio MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DBACDBDBDD Scramble Range: A - D RO Tier:
T2G1 SRO Tier:
T2GI Key Word:
VCT Cog. Level: C/A 2.7/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:18 PM
11 005AA2.03 001//TGI/MISALIGNED RODS/M 2.5/3.0/NEW/NA02301/S/RA/LSM Unit 1 was increasing power in accordance with 1-PCT-34.3, following the successfull performance of a valve freedom tes A fuse blows that prevents 4 control rods from movin Which one of the following describes the required actions?
A. Stop the power increase and request I&C to adjust the IRPI' B. Enter 1-E-Cf Stop the power increase and enter 1-AP-D. Stop the power increase and declare the computer inoperable and enter 1-AP-42.
1-AP-1.3 CONTROL ROD OUT OF ALIGNMENT provides instructions for recovering from the following misaligned rod events:
Any Single Control Rod is out of alignment by any number of steps, or Any Single Control Rod is out of alignment by any number of steps, or Any Single Control Rod is out of alignment by any number of steps, or Multiple Control Rods are out of alignment provided Misaligned Control Rods are all in the same group Multiple Control Rods are out of alignment provided All of the misaligned Control Rods are at the same position Multiple Control Rods are out of alignment provided All of the are less than 12 steps out of alignmen MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CCADBCBBAC RO Tier:
Key Word:
Source:
Test:
MISALIGNED RODS NEW S
SRO Tier:
Cog. Level:
Exam:
Misc:
misaligned Control Rods Scramble Range: A - D TIGI M 2.5/ NA02301 RA/LSM
Tuesday, November 05, 2002 03:19:19 PM
12. 005AKI.01 001/T1GI//STUCK ROD/C/A 3.1/3.8/BANK/NA02301/R/RA/GWL/SC-A Unit ramp to 100% is in progress on Unit At about 95% power annunciator A-H7, A. MONITOR, alarms. The RO determines that rod H-14 in control bank D appears to be stuck at 144 step Which one of the following describes the effect this event will have on core flux patterns?
There should be:
A. minimal effect on axial flux difference indicators the same elevatio B. minimal effect on axial flux difference indicators range detectors at the same elevation.
and on power range detectors at but a large variation on power C. a large variation on axial flux difference indicators but a minimal effect on power range detectors at the same elevatio DW a large variation on axial flux difference indicators and on power range detectors at the same elevatio North Anna Bank Question # 3761 modified for a stuck ro Associated objective: 1102 A. Incorrect, there will be a large effect on axial flux, and power range detector B. Incorrect, same as C. Incorrect, same as A.
D. Correct, a effect on MCS Time:
RO Tier:
TIc Key Word:
STi Source:
BA Test:
R Stuck rod will cause a large effect on axial flux difference, and a large power range detectors at the same elevatio I Points:
1.00 Version:
0 1 23456789 Answer: DDABACCADB Scramble Range: A - D
SRO Tier:
JCK ROD Cog. Level: C/A 3.1/ NK Exam:
NA02301 Misc:
RA/GWL/SC
Tuesday, November 05, 2002 03:19:19 PM C
L kt
13. 005K3.07 001/T2G3/T2G3/RHR/M 3.2*/3.6*/NEW/NA02301/C/RA/LSM/SC Unit one has cooled to slightly less than 100°F in preparation for refueling operation The Reactor Purification (RP) System is aligned so that the RP pumps take a suction on the reactor cavity and the RHR System downstream of the combined discharge lin Only the 1A pump is running. A RHR Heat Exchanger CC Flow transducer FT-132A has just failed lo Which one of the following will occur?
MCR alarm annunciation and indication and:
A. containment isolation trip valve 1-CC-TV-1 03A will clos B. the 1B RHR pump will auto star C. the IA RHR pump suction will autoswap to the RWS Dvf no Automatic actions.
This is for indication only, has no automatic features Module 40 Refueling operations. The plant cooldown continues to less than 140°F in preparation for refueling operations. During refueling the RHR System is maintained in service with the number of pumps and heat exchangers in operation as required by the decay heat load. During this period the RHR System can be used, in conjunction with the RP System, to purify the reactor cavity coolant. The RP System is aligned so that the RP pumps take a suction on the reactor cavity and the RHR System downstream of the combined discharge line. The flow rate from the RHR System to the RP System is controlled at 60 gpm, which does not affect the shutdown cooling ability of the RHR Syste Component Cooling Components The Component Cooling (CC) System (see Figure 40-2) supplies cooling water to the RHR heat exchangers and pump seal coolers. The cooling water is supplied to the RHR components from the same header that supplies the reactor coolant pump The supply flow is controlled by normally open, manually operated isolation valve The cooling water flow rate to heat exchanger 1A, as an example, is monitored by flow transducer FT-1 32A which provides MCR alarm annunciation and indication. The component cooling water flows through the shell of the heat exchanger at a design rate of 1.72 x 106 Ibm/hr and receives 30.5 x 106 Btu/hr of heat transferred from the RHR
Tuesday, November 05, 2002 03:19:19 PM
coolant. The outlet piping of the heat exchanger is protected from overpressurization by relief valve RV-128A which relieves at 150 psig to the containment drain trenc Flow through heat exchanger 1A is controlled by motor-operated valve 1-CC-MOV-1OOA, which is controlled from the vertical board in the MC The piping from heat exchanger 1A penetrates the Auxiliary Building where flow can be isolated by containment isolation trip valve 1-CC-TV-103A. The valve is operated from the safeguards panel train A but automatically shuts upon receipt of a containment isolation signal. The outlet temperature is monitored by a temperature element (TE-149A) which provides MCR indication before flow combines with the flow from the other heat exchanger and returns to the component cooling pump The supply line to each heat exchanger provides flow to another manifold which provides component cooling water (or makeup) to the following components: PDTT cooler, neutron shield tank cooler, neutron shield tank and surge tank (makeup), excess letdown heat exchanger, and RHR pump seal cooler The component cooling water is provided to seal cooler 1A, as an example, at 10 gpm through normally open, manual isolation valves. The cooling water cools the seal coolant to ensure adequate lubrication and cooling exists to maintain zero seal leakage. The component cooling flow rate through the cooler is monitored by a flow switch (FS-131A); the cooler outlet temperature is monitored by TE-150 Overpressure protection for the cooler component cooling piping is provided by relief valve RV-1 31 A which relieves to the drain trench at 150 psig. The combined seal cooler flow, along with the other components listed above, is returned to the piping downstream of 1-CC-MOV-1OOB. It is common to receive RCP low CC flow alarms intermittently when additional CC is "cut in" to the RHR heat exchangers (1-CC-MOV-1OOA and/or B throttled open).
Power Supplies The power supplies for the major components in the RHR System are listed in Table 40-5 as well as illustrated in Figures 40-3 through 40- Tuesday, November 05, 2002 03:19:19 PM
RO Tier:
T2G3 SRO Tier:
T2G3 Key Word:
RHR Cog. Level:
M 3.2*/3.6*
Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:19 PM
14. 006K4.13 001/T2G2/T2G2/SOLID STATE PROT/C/A 3.8/4.1/BANK/NA02301/C/RA/LSM/SC Unit one was operating at 100% powe An SI has occurre Which one of the following describes what INDICATIONS would be observed if one SI reset switch was operated [i.e. one train of SI was reset] instead of the SI initiate switch?
A. Since only one train was reset, an automatic SI would be reinitiated after 60 second B. The reset is transparent and no indications are available to the operators except by referral to the computer printou CU Several solid state protection system status lights will flas D. All the status and permissive windows will glow steadily and the first out indicator will glow steady red.
BANK 1992 NCRODP-93-10-LP-2, Revision MCS Time:
I Points:
1.00 RO Tier:
Key Word:
Source:
Test:
T2G2 SOLID STATE PROT BANK C
Tuesday, November 05, 2002 03:19:19 PM 3, Objective D.; LER 91-009 Version:
0 1 234567 89 Answer: CBDCDDABBD Scramble Range: A - D SRO Tier:
T2G2 Cog. Level: C/A 3.8/ Exam:
NA02301 Misc:
RA/LSM/SC
15. 007EA2.02 001/T1G2//E-0/M 4.3/4.6/NEW/NA02301/R/RA/LSM/GH The unit is at 100 % power Level transmitter 1-RC-LT-1459 failed on a previous shift and was placed in the TRI Vital bus 1-11 Inverter fails causing a loss of vital bus 1-1 Which one of the following statements is correct?
The reactor should:
A. have tripped, the crew should manually trip the reactor and enter 1-FR-BH have tripped, the crew should enter ITS 3. C. NOT have tripped, the crew should enter 1-AP-D. NOT have tripped, the crew should place the second channel in TRIP.
Replaced because question was similar to a common question Emergency Response Guideline Procedure Usage Resetting a Safety System If the system has not been reset once, then the RO shall reset the system when directed by procedure with concurrence from the cognizant SRO whether or not it has actuated. This action is not required if the procedure step includes the words "if required". Once the system has been reset, it is not necessary to reposition the reset switches every time a procedure directs a reset; simply verify that the applicable status lights indicate the reset condition. If it does not, then another reset is performed NCRODP-92-LP-1 Revision 8 MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BCACBCBBCD Scramble Range: A - D Tuesday, November 05, 2002 03:19:19 PM
RO Tier:
T1G2 SRO Tier:
Key Word:
E-0 Cog. Level:
M 4.3/ Source:
NEW Exam:
NA02301 Test:
R Misc:
RA/LSM/GH Tuesday, November 05, 2002 03:19:19 PM
1 1 flfhI{
nY) *nH ~/T-)CAIT)C/PRT/r/A '" I/q 4/lt1MAO23O1/CIRA/LSM/SC Modified SHNPP Exam bank Question B02-06 MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 Answer: CACBBBCC RO Tier:
T2G3 SRO Tier:
Key Word:
PRT Cog. Level:
Source:
M Exam:
Test:
C Misc:
Tuesday, November 05, 2002 03:19:19 PM
CC Scramble Range: A - D T2G3 C/A 3.1/ NA02301 RA/LSM/SC
Which one of the following outlines the appropriate operator actions for drawing a bubble in the Pressurizer once saturation conditions have been reached?
Ensure RCS Temperature is greater than 170 degrees F., and :
A. Increase PZR spray flow and place another CVCS letdown orifice into servic B. Decrease PZR spray flow and place excess letdown into servic Cf Increase CVCS letdown flow and maintain charging flow constan D. Decrease CVCS charging flow and maintain letdown flow constan. 008AKI.01 00I/TI G2/TG2/SAFETY VALVE/C/A 3.2/3.7/M/NA02301/C/RA/GWL/LSM/SC-Unit 1 is stable at 100% powe A pressurizer safety valve opens and fails to reseat and the unit trip Which one of the following indications would the operator expect to see as a result of this event?
A. Safety tailpipe temperature decreas B. Safety tailpipe temperature increas Cf Safety tailpipe temperature and then slowly decreas D. Safety tailpipe temperature and then slowly increase.
would increase to greater than 600 OF and then slowly would increase to greater than 600 OF and then slowly would increase to between than 200 OF and 300 OF would increase to between than 200 OF and 300 OF Bank Question From Farley 2000 NRC exa North Anna Lesson Plan NCRODP-74-NA objectives A and G. and pages 23 and 24 of the lesson pla A. Incorrect, This would be the correct temperature for pressure at 2240 psig. Since the pressure the steam is going to is 8 to 11 psig the temperature will be between 212-330 degrees per the steam table B. Incorrect, Same as above for temperatur C. (Correct) Incorrect, After the safety has relieved to the PRT the pressure will start increasing towards 100 psig. Per the steam tables, as the pressure rises towards 100 psig, the temperature will also rise until the rupture disc relieves, then the pressure will drop and stablize out. (PRT remains intact) - This answer is now correct based on NA comment D. (Incorrect) Correct, as the pressure rises towards 100 psig, the temperature will also rise.
MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CABBCCDDBA Scramble Range: A - D Tuesday, November 05, 2002 03:19:19 PM
RO Tier:
Key Word:
Source:
Test:
T102 SAFETY VALVE M
C SRO Tier:
Cog. Level:
Exam:
Mise:
TiG2 C/A 3.2/ NA02301 RA/GWL/LSM/SC Tuesday, November 05, 2002 03:19:20 PM
18. 008K3.03 00 I/T2G3//RCP/C/A 4.1/4.2/BANK/NA0230 I/R/RA/LSM Assume the following plant conditions:
Unit 1 is at 100% power Unit 2 is in mode 6 The unit-1 and unit-2 component cooling water systems are split Component cooling pump 1-CC-P-IA has just been tagged out for bearing replacement A ground on 1J emergency bus causes supply breaker 15J11 to trip 1J emergency diesel generator starts, but does not load Which one of the following statements is correct concerning subsequent operation of the reactor coolant pumps (RCPs)?
A. Component cooling water flow to the pump thermal barriers must be manually isolated to prevent thermal barrier damag B. The RCPs may be run indefinitely provided seal injection flow is maintained, and the seal leak-off valves remain ope Cf The RCPs must be tripped or the motor windings will be damage D. Component cooling water flow must be restored within 20 minutes or RCP seal damage will occur.
Tuesday, November 05, 2002 03:19:20 PM
Associated objective(s):
Bank ID: 5580 3656 List the following information associated with the component cooling water pump Power supply to each pump Interlocks associated with manually starting a pump Interlocks associated with automatically starting a pump Interlocks associated with automatically tripping a pump MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CDDDABCBDA Scramble Range: A - D RO Tier:
T2G3 SRO Tier:
Key Word:
RCP Cog. Level: C/A 4.1/ Source:
BANK Exam:
NA02301 Test:
R Mise:
RA/LSM Tuesday, November 05, 2002 03:19:20 PM
19. 009EK3.11 001/TI G2/T1G2/RCP TRIP/M 4.4/4.5/NEW/NA02301/C/RA/LSM/SC The Continuous Action for 1-E-1 provides the requirements for RCP Trip Criteri Under some conditions the RCPs are directed to be tripped. Which one of the following is the basis for this trip criteria?
A' To Minimize mass loss from a small break LOC B. To Protect the RCP Seal C. To Minimize RCS heatu D. To establish natural circulation.
ERG exe volume generic issues page 58 the only purpose is to minimize break flow MCS Time:
I Points:
1.00 Version:
Answer:
A RO Tier:
Key Word:
Source:
Test:
TIG2 RCP TRIP NEW C
Tuesday, November 05, 2002 03:19:20 PM for a small break LOCA 123456789 CACCDABCB Scramble Range: A - D SRO Tier:
T102 Cog. Level:
M 4.4/ Exam:
NA02301 Misc:
RA/LSM/SC
20 01(o920 1 001/T2G2/T2G2/UV/DV/M 3.0/.34/M/NA02301/C/RA/LSM/SC NCRODP-74-LP-1 OBJ. D BANK 1996/01/29 MCS Time:
I Points:
RO Tier:
Key Word:
Source:
Test:
T2G2 UV/DV M
C 1.00 Version:
0 1 23456789 Answer: ADCAACADBB Scr SRO Tier:
T2G2 Cog. Level: M 3.0/.34 Exam:
NA02301 Misc:
RA/LSM/SC
Tuesday, November 05, 2002 03:19:20 PM Which one of the following will NOT be automatically powered by its emergency bus, following a UV/DV event? (Assume each component was running/energized prior to the event.)
Af PZR back-up heate B. Instrument Air compresso C. 480V emergency bu D. Inside reciro. spray pump.
amble Range: A - D
21. 011 EK3.06 001/T 10G2/Tf 1/PHASE A/M 4.3*/4.3*/NEW/NA02301/C/RA/LSM/SC A Large Break LOCA has occurred. Which one of the following following is a result of a Phase A actuation?
A. Both Instrument Air 1-IA-TV-102A and RHR CC Return 1-CC-TV-103A clos B. Both Blowdown trip valve 1-BD-TV-10OF and Instrument Air 1-IA-TV-102A ope Cf Both Letdown trip valve 1-CH-TV-1204B and Blowdown trip valve 1-BD-TV-1OOF clos D. Blowdown trip valve I-BD-TV-10OF closes and Instrument Air 1-IA-TV-102A open Replaced a KA that did not apply to North Anna Question replaced to provide a question that matches Operator expected memory level knowledge.
MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CBADBBDDCD Scramble Range: A - D RO Tier:
T1G2 SRO Tier:
TIGI Key Word:
PHASE A Cog. Level: M4.3*/4.3*
Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC
Tuesday, November 05, 2002 03:19:20 PM
'VY
,n 1 11 nnh//,flCflITg/C/A )
Old n/NPWINAfl9aOh/SIRA/fSM/SC Unit 1 is 100 % power with the following conditions:
Normal letdown is isolated by the previous shift due to a lea Excess letdown flow was maximized, but pressurizer level is still increasin At 02:00, The power supply to group 4 pressurizer heaters failed, and repairs are estimated to required 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> At 04:00 Pressurizer level is 87% and is increasing at 1.5% per hou Assume pressurizer level continues to increase at this rate and that the group 4 heaters are returned to service at the precise time estimated by mechanical Maintenance. Which one of the following is correct:
Unit 1 must be:
A. in mode 3 no later than 08:00 and must be in Mode 4 no later than 14:0 B. in mode 3 no later than 09:00 and must be in Mode 4 no later than 15:0 Cf in mode 3 no later than 14:00 and must be in Mode 4 no later than 20:0 D. in mode 3 no later than 21:00 and repairs will be completed before a mode 4 entry is require..
,-
,
aant%.
.4.00 lkA30 I uesday, November U0, 2UU0 03: 19:.0 uiVl
93% is reached at 8:00 am + six hours is 2:00pm + 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is 8:00pm Reference:
North Anna Units 1 and 2 B 3.4.9-4 Rev 0 (Draft 3), 10/09/00 Pressurizer B 3.4.9 BASES ACTIONS A.1, A.2, A.3 and If the pressurizer water level is not within the limit, action must be taken to bring the unit to a MODE in which the LCO does not apply. To achieve this status, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> the unit must be brought to MODE 3, with all rods fully inserted and incapable of withdrawal. Additionally, the unit must be brought to MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This takes the unit out of the applicable MODE The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit system If one required group of pressurizer heaters is inoperable, restoration is required within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is reasonable considering the anticipation that a demand caused by loss of offsite power would be unlikely in this period. Pressure control may be maintained during this time using the remaining heater C.1 and If one group of pressurizer heaters are inoperable and cannot be restored in the allowed Completion Time of Required Action B.1, the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit system MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CCDBABADAA Scramble Range: A - D RO Tier:
SRO Tier:
T2G2 Key Word:
TS Cog. Level:
C/A 2.9/ Source:
NEW Exam:
NA02301 Test:
S Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:20 PM
23. 01 1K6.01 001/T2G2//ES-0.4/C/A 2.7/3. 1/NEW/NA02301/R/RA/LSM/SC Unit 1 was at 100% power when a loss of offsite power. The crew has transitioned to 1-ES-0.4, Natural Circulation Cooldown with Steam Void in Vessel (without RVLIS),
from 1-ES-0.2A, Natural Circulation Cooldown with CRDM Fan The following conditions currently exist:
-
RCS pressure is 1600 psi RCS temperature is 450 degrees The crew has just completed step 6, which requires them to maintain charging and seal injection flow equal to letdown and seal leakoff flo Which one of the following is the reason for equalizing charging and letdown flows during the subsequent depressurization?
A! Allows Pressurizer level to be used for monitoring void growt B. Assures RCS total mass does not drop below minimum conditions assumed in FSAR analysi C. Pressurizer level is not accurate during these conditions and flow matching assures the pressurizer will not go soli D. Assures the regenerative heat exchanger is not over stressed due to large fluctuations in charging and letdown.
Reference EOP Owners Group Guidelines MCS Time:
I Points:
1.00 RO Tier:
Key Word:
Source:
Test:
T2G2 ES-NEW R
Version:
0 1 23456789 Answer: AAAADBABBB SRO Tier:
Cog. Level:
C/A Exam:
NAC Misc:
RA/
Scramble Range: A - D 2.7/ )2301 LSM/SC Tuesday, November 05, 2002 03:19:20 PM
24. 012K5.02 00I/T2G2/T2G2/RPS/C/A 3.1/3.3/NEW/NA02301/C/RA/LSM Which one of the following is the purpose of the overpower delta T trip. The trip was designed to:
A. provide protection for a departure from nucleate boiling ONL BX act as backup to the high neutron flux trip and limits required range of OTDT protectio C. provide protection for departure from nucleate boiling and a act as a backup to the high neutron flux tri D. continuously calculate the RCS overpower delta T trip settings under varying load conditions and transients.
Delta T protection system. The overtemperature delta T trip is designed to protect the reactor core from departure from nucleate boiling (DNB) conditions by continuously calculating the RCS overtemperature delta T trip settings under varying load conditions and transients. The overpower delta T trip is designed to protect against a high fuel rod power density and subsequent fuel rod cladding failure and fuel meltdown. The overpower delta T reactor trip acts as a backup to the high neutron flux trip and limits required range of OTDT protectio MCS Time:
I Points:
1.00 Version:
0 1 2345 67 89 Answer: BACCACBCAA Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
RPS Cog. Level:
C/A 3.1/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM Tuesday, November 05, 2002 03:19:20 PM
25. 013A1.05 001/T2GI/T2GI/ESF/C/A 3.4/3.6/BANKiNA02301/C/RA/LM Given the following plant conditions:
1. The unit is currently at 480 degrees F 2. Normal cooldown is in progres A steam break occurs on the 40 inch main steam heade Which one of the following is the ESF response to this failure?
A. Neither a main steam line isolation or safety injection will occu B. Only a safety injection will occu Cf Only a main steam line isolation will occu D. Both a main steam line isolation and a safety injection occurs.
NA bank Time:
T2G1 rd:
ESF BANK C
question 3824 Points:
1.00 Version:
0 1 2 3 4 5 6 7 Answer: CCDDCAAD SRO Tier:
Cog. Level:
Exam:
Misc:
AC Scramble Range: A - D T2GI C/A 3.4/ NA02301 RA/LM Tuesday, November 05, 2002 03:19:21 PM REF:
Test:
26. 013K6.01 001/T2G1/T2GI/ESF/C/A 2.7/3.1/NEW/NA02301/C/RA/LSM/SC Given the following plant conditions:
- A reactor shutdown is in progress as required by ITS 3. Pressurizer pressure PT-455 failed downscal The channel has been placed in tri RCS pressure has decreased to 1750 psig during a plant cooldow Lo-Lo Pressurizer Pressure SI signals have been blocked as required by the shutdown procedur Subsequently, pressurizer pressure PT-456 fails hig Which one of the following correctly describes how the ESF system will respond to this failure?
A. Only a Phase A actuation will occu BY An SI and containment isolation phase A will occu C. No ESF actuation will occur, Lo-Lo Pressurizer Pressure SI signals have been blocke D. No SI will occur, but the reactor will tri REF: Process Instrumentation & Control sheets NA-DW-108D014 sheet 5; NA-DW-5655D 33 sheets 6 and 8; Lesson Plan for Safety Injection System (52);
Module NCRODP-52 Safety Injection System OBJ: 1.2 page 45 of 56 LP Distractor A - Incorrect - Pressurizer Pressure PT-455B in trip position and 456B failed upscale provide will result in more than an SI actuatio B - Correct - Pressurizer Pressure PT-455B in trip position and 456B failed upscale provide will result in both an SI and Phase A isolatio Distractor C - Incorrect - Lo-Lo Pressurizer Pressure SI signal auto unblock Distractor D - Incorrect - SI does occu MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBCDDCCBBD Scramble Range: A - D RO Tier:
T2G1 SRO Tier:
T2G1 Key Word:
ESF Cog. Level:
C/A 2.7/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC
Tuesday, November 05, 2002 03:19:21 PM
27. 014A2.04 001//T2GI/ROD CONTROL/M 3.4/3.9/BANK/NA02301/S/RA/LSM/SC The unit is at 100% power when control bank "B" rod D-1 0 drops with no reactor tri During the subsequent recovery of rod D-10, the operator mistakenly opens all lift coil disconnect switches in control bank "A," except for rod B-10. The reactor operator selects control bank "B" and begins outward rod motion. As a result of this operation the ROD CONTROL FAILURE annunciator will during rod motio Af URGENT; not alarm as expecte B. NON-URGENT; alar C. URGENT; alar D. NON-URGENT; not alarm as expecte bank 2157 MCS Time:
I RO Tier:
Key Word:
Source:
Test:
Points:
1.00 Version:
Answer:
ROD CONTROL BANK S
0123456789 AACDACDBCC SRO Tier:
T2GI Cog. Level:
Exam:
Misc:
Scramble Range: A - D M 3.4/ NA02301 RA/LSM/SC
Tuesday, November 05, 2002 03:19:21 PM
28. 014K4.06 001/T2G2//ROD CONTROL/C/A 3.4/3.7/NEW/NA02301/R/RA/LSM/SC While completing AP 1-3, Attachment 2, Realigning Control Rod - Rod Lo The ROD BANK LO/LO-LO LIMIT annunciator alarms. Which one of the following is the cause of this alarm?
A. More than one rod in the same group has been moved simultaneousl B. All of the affected bank's lift coils have been energize C. The local Manual/Automatic switch has been placed in MANUA Df The affected banks's pulse-to-analog convertor was pulsed to zero. D.
Does not alarm May cause urgent failure alarm Required action, but does not cause this alarm Correct Abnormal Procedure AP 1.3 Attachment 2 MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 Answer: DDBDBDCD RO Tier:
T2G2 SRO Tier:
Key Word:
ROD CONTROL Cog. Level:
Source:
NEW Exam:
Test:
R Misc:
Tuesday, November 05, 2002 03:19:21 PM
A D Scramble Range: A - D C/A 3.4/ NA02301 RA/LSM/SC
29. 015/17AA2.08 001//TI GI/3.4/3.5/M 3.4/3.5/NEW/NA02301/S/RA/LSM/SC Unit 1 is starting up after a refueling outage. At 25 % power the following RCP temperatures exist:
for the "A" RCP radial bearing 2050F pump bearing 200°F stator 2950F motor bearing 190°F for the "B" RCP:
radial bearing 210°F pump bearing 205'F stator 285°F motor bearing 185°F for the "C" RCP:
radial bearing 205°F pump bearing 195°F stator 2850F motor bearing 2050F Which one of the follow is the appropriate actions to direct the crew to perform?
A. There are no required actions at this power leve B. Secure RCP C. Secure RCP DW Secure RCP C.
Tuesday, November 05, 2002 03:19:21 PM
C RCP motor Radial Bearing temperature is above temperature limi NEW SRO ONLY Reference: BANK Question ID: 5435 Which ONE of the following temperatures would require securing a reactor coolant pump? RCP radial bearing 210°F RCP pump bearing 205°F RCP stator 2950F RCP motor bearing 205°F Answer:
D MCS Time:
RO Tier:
Key Word:
Source:
Test:
Points:
1.00 3.4/ NEW S
Version:
0 1 234567 Answer: DABCCDAD SRO Tier:
Cog. Level:
Exam:
Misc:
B B Scramble Range: A - D TIGI M 3.4/ NA02301 RA/LSM/SC Tuesday, November 05, 2002 03:19:21 PM
30. 015/17AA2.10 001/T1GO//RCP/C/A 3.7/3.7/NEW/NA02301/R/RA/GWL/SC
- Unit I is at 100% powe The P-250 computer has faile Annunciator 1-C-G6, RCP 1A-B-C Illuminates LABYTH Seal Low Flo Seal leakoff flows to the RCP's begin to lowe "C" RCP seal injection flow drops to zero, and seal leakoff indicates 1.0 gp "A" and "B" seal injection flows begin to dro AR C-G-6 Instructs you to Monitor "C" RCP radial bearing temperature, if bearing temperature approaches 225 degrees then trip the reactor and stop "C" RC Which one of the following describes the indications available for monitoring radial bearing temperature in accordance with 1-AP-42?
A. 1-RC-TR-144 B. There are no direct indications available. A test instrument must be installed in the rack roo Cf PC D. There are no direct indications available. A test instrument must be installed locall Annunciator Response procedure 1-AR-C-G Chemical and Volume Control Objective 9.1 A. Incorrect, This would be the correct action if there was two phase flow in the seal leakoff lin B. Incorrect, This would be the correct action if cooling to the thermal barrier also existed D. Incorrect, This would be a correct action if CC had been lost C. This is the action directed by the A MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CDDDDABBCB Scramble Range: A - D RO Tier:
TIG1 SRO Tier:
Key Word:
RCP Cog. Level: C/A 3.7/ Source:
NEW Exam:
NA02301 Test:
R Misc:
RA/GWL/SC Tuesday, November 05, 2002 03:19:21 PM
31. 015G2.1.32 001//T2GI/RCP/C/A 3.4/3.8/BANK/NA02301/S/RA/LSM BANK 1996 VISION OBJ. 11101 1996/01/29 MCS Time:
I Points:
1.00 RO Tier:
Key Word:
Source:
Test:
RCP BANK S
Version:
0 1 234567 89 Answer: ACDACBCAAB Scramble Range: A - D SRO Tier:
T2G1 Cog. Level: C/A 3.4/ Exam:
NA02301 Misc:
RA/LSM Tuesday, November 05, 2002 03:19:23 PM Given the following conditions:
-
Unit 1 is at 100 percent powe C-G2, "RCP 1B STANDPIPE HI LEVEL" has li "- "B" seal injection flow is 7.8 GP "- "B" seal leak-off flow is 0.2 GP Seal return temperature is 150 OF and rising steadil "- "B" RCP temperatures are as follows:
-
Motor stator - 241.8 0F
-
Motor upper bearing - steady at 114.5 OF
-
Motor lower bearing - steady at 128.5 OF
-
Pump radial bearing - rising slowly at 128.5 OF Based on the above indications, you should direct the operating crew to perform which one of the following?
Af trip the unit, secure "B" RCP and close its No. 1 seal leakoff valve after the pump stops.
B. trip the "B" RCP and close its No. 1 seal leakoff valve after the pump stop C. close the "B" RCP's No. 1 seal leakoff valve within 5 minutes and shutdown the unit within the next 30 minutes then secure the "B" RC D. trip the unit, secure "B" RCP and contact OMOC.
32. 015K3.06 001/T2G1//ROD CONTROL/C/A 2.9*/3.2*/BANK/NA02301/R!RA/LM The unit is at 75% power with "D" bank control rods at 150 steps in AUTOMATIC when power-range nuclear instrument N-44 fails LO Assuming NO OPERATOR ACTIO Which one of the following describes the effect this failure will have on Rod Control? D.
The control rods will insert automatically for that positio The control rods will insert automatically for the previous positio The control rods will withdraw automatically that positio The control rods will withdraw automatically the previous position.
several seconds and then remain in several seconds and then withdraw to for several seconds and then remain in for several seconds and then insert to REF: NA Bank question 2162; Lesson Plan Rod Control (065)
OBJ: 2.9.2, 2.9.6 MCS Time:
I Points:
RO Tier:
T2G I Key Word:
ROD CONTROL Source:
BANK Test:
R 1.00 Version:
0 1 2345 6789 Answer: DCDBCBACDA Scramble Range: A - D SRO Tier:
Cog. Level:
C/A 2.9*/3.2*
Exam:
NA02301 Misc:
RA/LM Tuesday, November 05, 2002 03:19:23 PM
33. 015K6.02 001/T2Gl//SOURCE RANGE/C/A 2.6/2.9/BANK!NA02301/R/RA/LM/SC Which one of the following describes how the pulse height discriminator failing low would affect the indication of the failed Source Range channel?
A. The output would decrease due to failure in removing the higher amplitude neutron generated pluse B. The output would increase due to electronic filtering which narrows the pulse height windo Cf The output would increase due to counting both the gamma and decay-alpha generated pulse D. The output would decrease due to decreased gamma interaction inside the detector.
REF: Braidwood 9/14/98 RO; Ex-core Nuclear Instrumentation System (62) objective Comment: The Pulse height discriminator is used to set window to detect those pulses with an energy level high enough to be from an event associated with neutron detection. Gamma and other interactions such as the alpha decay of fission product daughters are of lower height (energy) and the discriminator normally electronically removes them.
MCS Time:
Points:
T2GI SOURCERANGE BANK R
1.00 Version:
0 1 23456789 Answer: CCDADDCACC SRO Tier:
Cog. Level:
C/A Exam:
NA(
Misc:
RA/
Scramble Range: A - D 2.6/ LM/SC Tuesday, November 05, 2002 03:19:23 PM RO Tier:
Key Word:
Source:
Test:
34. 016A2.01 00 I/T2G2/T2G2/NNIS/C/A 3.0/3. I/NEW/NA02301/C/RA/LSM/SC Which one of the following describes the immediate effects and the long term effects if the main generator hydrogen cooler Air Release Valve Level Switch failed while the bearing cooling system is operating normally in the tower mode? (For the long term effect assume the problem is not corrected)
Af There is no immediate effect. On the subsequent system startup, the bearing cooling pump discharge MOVs will not open past the 25 percent system flow positio B. There is no immediate effect. On the subsequent system startup, the bearing cooling pump discharge MOVs must be opened manuall C. Initially the bearing cooling pump discharge valves will not open past the 35 percent system flow position. On the subsequent system startup, the pump discharge MOVs must be opened manuall D. Initially the bearing cooling pump discharge valves will not close past the 50 percent system flow position. On the subsequent system startup, the pump discharge MOVs must be de-energized to allow the valves to be open enough for the pump to start. The valve then must be positioned manuall NRCODP33 If the main generator hydrogen cooler Air Release Valve Level Switch failed while the system is operating normally in the tower mode, there is no immediate effect. If the problem is not corrected, on the subsequent system startup, the pump discharge MOVs will not open past the 25 percent system flow positio MCS Time:
I Points:
1.00 Version:
0 1 2345 67 89 Answer: ADCABADDAC Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
NNIS Cog. Level: C/A 3.0/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:23 PM
35. 017K3.01 00 I/T2G 1/T2G I/NATURAL CIRC/M 3.5*/3.7*/BANK/NA02301/C/RA/LM/LSM If all core exit thermocouples are inoperable during an event in which the RCPs were tripped, what other indication(s) may be used to verify that natural circulation cooling is occurring?
Af RCS hot leg temperature onl B. RCS cold leg temperature onl C. Both RCS cold leg and hot leg temperatur D. There are no direct indications availabl REF: NA Bank 3796 OBJ: 12484 MCS Time:
I RO Tier:
Key Word:
Source:
Test:
T2G I NATURM BANK C
Points:
1.00 Version:
0 1 2 3 4 5 6 Answer: ACCBDCB SRO Tier:
L CIRC Cog. Level:
Exam:
Misc:
B
A D Scra T2G 1 M 3.5*/3.7*
NA02301 RA/LM/LSM
.mble Range: A - D
Tuesday, November 05, 2002 03:19:23 PM
36. 017K4.01 001/T2GI//ICCM/M 3.4/3.7/BANK/NA02301/R/RA/LM Which one of the following is the primary purpose of the subcooled margin monitor subsystem associated with the Inadequate Core Cooling Monitor System?
The primary purpose is to provide a :
REF:NA Bank OBJ:
Distractor A:
Distractor B:
C:
Distractor D:
MCS Time:
RO Tier:
T2G Key Word:
ICC Source:
BAI Test:
R Tuesday, November 05, 20 S501 Incorrect - Subcooled margin monitor is based on a temperature margi Incorrect - Subcooled margin monitor utilizes core-exit thermocouple Correct Incorrect - combination of two incorrect statement I Points:
1.00 Version:
0 1 2345 6789 Answer: CCDCDADBAA Scramble Range: A - D i1 SRO Tier:
'M Cog. Level:
M 3.4/ NK Exam:
NA02301 Misc:
RA/LM 302 03:19:23 PM
A. pressure margin to saturation based on the wide-range Reactor Coolant System pressur B. temperature margin to saturation based on the wide-range Reactor Coolant Syst temperatur Cf temperature margin to saturation based on the core-exit thermocouple D. pressure margin to saturation based on the wide-range Reactor Coolant System temperature and pressure.
tem
37. 022AA2.03 001//T1G2/3.1/3.6/C/A 3.1/3.6/M/NA02301/S/RA/LSM/SC The plant is in Mode 4, RCS pressure is 300 psig, and RCS temperature is 250 O large break LOCA occurs and none of the charging pumps can be started due to various malfunctions.
Which one of the following methods is required per regain adequate core cooling?
1-AP-17, Shutdown LOCA, to A. Manually actuate Safety Injectio B. Establish RHR coolin C. Manually open accumulator isolation valve DO Establish low head SI flow.
reference Bank 1993/10/11 1-AP-17, Attachment 8, Rev. 3, page 3 MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 Answer: DCBABCBD RO Tier:
SRO Tier:
Key Word:
3.1/ Cog. Level:
Source:
M Exam:
Test:
S Misc:
A D Scramble Range: A - D TI02 C/A 3.1/ NA02301 RA/LSM/SC Tuesday, November 05, 2002 03:19:23 PM A
38. 022K2.02 001/T2G1//POWER SUPPLY/M 2.5/2.4/BANK/NA02301/R/RA/LSM Which one of the following pump?
is the power supply to the "A" outside recirculation spray A. 4160-volt AC bus 1 B/ 4160-volt AC bus 1 C. 480-volt AC bus 1J D. 480-volt AC bus 1 H1.
Bank-ID: 280 MCS Time:
I RO Tier:
Key Word:
Source:
Test:
T2GI POWER5 BANK R
Points:
1.00 Version:
0 1 23456789 Answer: BDDBBDBCAA SRO Tier:
SUPPLY Cog. Level:
M 2 Exam:
NA(
Misc:
RA/
Scramble Range: A - D
.5/ /LSM Tuesday, November 05, 2002 03:19:23 PM
39. 022K4.03 00l/T2GI/T2Gl/3.6*/4.0/C/A 3.6/4.0/NEW/NA02301/C/RA/LSM/SC There are two types of containment isolation signals: (a) phase A and (b) phase The phase A containment isolation signal is initiated either automatically by a safety injection actuation signal or manually by operator action. The phase A signal shuts all containment isolation valves for penetrations that are not essential for an orderly cooldown of the reactor with the reactor coolant pumps running. The phase B containment isolation signal is initiated automatically when containment total pressure exceeds 27.75 psia. There is no provision for direct manual initiation of only a phase B signal without also initiating a CDA. The phase B signal completes containment isolation by sending a close signal to containment isolation valves for component cooling water used by the reactor coolant pumps, which will be secured by the control room operator, the return from the containment recirculation air coolers, the steam generator blowdown isolation valves (which are also closed by phase A) and instrument air. Containment isolation must be reset before valves shut by either phase A or phase B can be reopened. The equipment that generates the containment isolation signals is more fully discussed in the Instrumentation and Controls section of this modul MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BABABAACDB Scramble Range: A - D RO Tier:
T2G0 SRO Tier:
T2GI Key Word:
3.6*/ Cog. Level: C/A 3.6/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:24 PM A small leak has developed in the component cooling water supply line to the reactor coolant pumps. An initial idea is to initiate a phase B containment isolation which will close the component cooling water supply trip valves to reactor coolant pump Subsequent review has found this is not practical because of which one of the following?
A. There is no provision for direct manual initiation of only a phase B signal without first initiating a phase A signa B. There is no provision for direct manual initiation of only a phase B signal without also initiating a containment depressurization signa C. The direct manual initiation of only a phase B signal will also cause a phase A signal which will shut all containment isolation valves for penetrations that are not essential for an orderly cooldown of the reactor with the reactor coolant pumps runnin D. The direct manual initiation of only a phase B signal will also cause containment depressurization signal.
40. 024AK3.01 001/T1G1//BORATION/M 4.1/4.4/M/NA02301/R!RA/GWL/LSM/SC
- Unit 1 is operating at 50% powe The crew is required to evacuate the control room due to noxious fume Which one of the following would require the crew to commence an emergency boration in accordance with 1-AP-20, "Operation from the Auxiliary Shutdown Panel"?
Af The crew was unable to verify IRPI status before leaving the control roo B. One Control Rod remains fully withdrawn, all other IRPIs indicate zer C. IRPIs indicated for three control rods indicated six steps; all other IRPIs indicate zer D. The control room remains uninhabitable 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> following the reactor tri North Anna Bank Question # 3779. Modifie Changed conditions in answers to allow for another answer to be correc Changed the time on D to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> instead of 1 Changed # of rods and rod heigh A. correct. recent procedure chang B. Incorrect, Shut down margin is calculated with the most reactive rod out of the core, the procedure directs the crew to emergency borate only if two or more rods are ou C. Incorrect - with three control rods indicated out greater than 10 steps out of the core the procedure calls for an emergency boration. This does not meet that criteria D. Incorrect, the previous procedure stated - the time is greater than 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> and requires emergency boratio MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ABDAABDDDC Scramble Range: A - D RO Tier:
TIGI SRO Tier:
Key Word:
BORATION Cog. Level:
M 4.1/ Source:
M Exam:
NA02301 Test:
R Misc:
RA/GWL/LSM/SC
Tuesday, November Ub, 2UUZ 03:19:24 nPM
41. 024G2.4.35 001//TiG1/BORATION/C/A 3.3/3.5/M/NA02301/S/RA/LSM/SC The control room has been evacuated due to an uninhabitable atmosphere. The 1-E-0 immediate actions were performed prior to evacuating the control room. The RO reported the all IRPI's indicated zero except; I 1 rod at 30 steps
- 1 rod at 20 steps
- 1 rod at 10 steps Which one of the following describes how long emergency boration is required?
A. 12 minute B. 25 minute CU 50 minute D. Until a SDM of less than or equal to 0.95 is reache Reference required 1993/10/11 Modified bank to match new criteria of 25 minutes per rod changed AP reference 1-AP-20, Rev. 18, page 8 MCS Time:
I Points:
BORATION M
S 1.00 Version:
0 1 23456 Answer: CCCDDCD SRO Tier:
Cog. Level:
Exam:
Misc:
789 D C Scre TIGI C/A 3.3/ NA02301 RA/LSM/SC amble Range: A - D
Tuesday, November 05, 2002 03:19:24 PM RO Tier:
Key Word:
Source:
Test:
A
42. 025AK3.03 001/TIG2/T1G2/REFUELING/C/A 3.9/4.1/BANK/NA02301/C/RA/LSM/SC Unit 1 is in Mode 5 for an un-scheduled maintenance outag The unit has been shutdown for 10 day RCS temperature is 130 O RCS Level is +11" above centerlin Residual heat removal (RHR) pump 1-RH-P-1B is in servic Both RHR heat exchangers are in servic The reactor operator observes the following RHR parameters:
- RHR flow - fluctuating 2800 gpm plus or minus 200 gp RHR motor amps - fluctuating 35 plus or minus 5 amp RCS Stand Pipe level - fluctuating at 11 plus or minus 1 inc Which one of the following describes the RHR flow? The RHR flow is....
(1 -AP-1 1 is available for reference)
Av above design flow and can be reduced to 2250 gp B. below design flow and can be raised to 2900 gp C. below design flow and can be left at 2800 gp D. above design flow and can be raised to 4000 gpm.
Tuesday, November 05, 2002 03:19:24 PM
Bank 3037 reference AP-1 1 _ Question replaced Original Question Stand pipe operation changed Unit 2 is refueling and is on RHR. There has been a degradation of RHRSW causing the running RHR pumps to cavitate. Unit 2 then enters 1-AP-1 1, LOSS OF RHR. The RCS level stand pipe initially has dropped then began to slowly rise. You get initial reports from the refueling floor that there is some boiling in the core. The caution in 1 -AP-1 I describes which one of the following effect on the RCS Level measurements?
Changes in RCS temperature due to boiling in the core can result in Reactor Vessel water level changes that may not show on RCS standpipe level indicator.
Changes in RCS pressure due to boiling in the core can result in Reactor level changes that may not show on RCS ultrasonic level indicator.
Vessel water Changes in RCS temperature due to boiling in the core can result in Reactor Vessel water level changes that may not show on RCS ultrasonic level indicato Changes in RCS pressure due to boiling in the core can result in Reactor Vessel water level changes that may not show on RCS standpipe level indicator.
Answer - D MCS Time:
I RO Tier:
Key Word:
Source:
Test:
TIG2 REFUEL BANK C
Points:
1.00 Version:
0 1 2 3 4 5 6 Answer: AABDCCB SRO Tier:
ING Cog. Level:
Exam:
Misc:
789 B B A Scramble Range: A - D TIG2 C/A 3.9/ NA02301 RA/LSM/SC Tuesday, November 05, 2002 03:19:24 PM
43. 026AK3.03 00I/TIGI/TI GI/DEGRADED COOLING/C/A 4.0/4.2/BANK/NA02301/C/RA/GWL/SC
- Unit 2 has entered 2-FR-C.2 "Response to Degraded Core Cooling"' due to indications of degraded core coolin "B" RCP is running, "A" and "C" have been secure Component Cooling water flow to the motor has just been los Which one of the following describes the actions that should be taken in accordance with 2-FR-C.2?
A. Secure the "B" RCP immediately; allowing it to run will cause core cooling to degrade furthe B. Continue to operate "B"RCP; this will allow better pressure control of the Rea4 Coolant Syste C. Secure the "B" RCP immediately; damage to the motor windings could occu Df Continue to operate "B" RCP until directed by the procedure; the pump may provide core cooling.
ctor North Anna Bank question # 254 A. Incorrect, allowing the B RCP to continue to run could cause reflux cooling to take place, this will not degrade core cooling furthe B. Incorrect, Pressurizer sprays come off the A and C RCPs, not the B RC C. Incorrect, The B RCP should remain running until directed by the procedur D. Correct, the B RCP should remain running the pump could provide some reflux coolin MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DCBAAADAAA Scramble Range: A - D RO Tier:
TIGI SRO Tier:
TIGI Key Word:
DEGRADED COOLING Cog. Level: C/A 4.0/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/GWL/SC
Tuesday, November 05, 2002 03:19:24 PM
44. 026K4.01 001/T2G2/T2GI/RECIRC SPRAY/C/A 4.2/4.3/BANK/NA02301/C/RA/LSM/SC Which one of the following describes how the Recirculation Spray System would be affected by a rupture outside containment in the Quench Spray Pump discharge piping?
A. The additional source of water for the Outside Recirculation Spray [ORS] pumps will be lost and ORS pump available NPSH will not be increased by reduced temperature of the water at the suction of the ORS pump B. The capacity of the Recirculation Spray System will be reduced by the loss of the ORS pumps when the Quench Spray System is isolate C.ý The additional source of water for the Inside Recirculation Spray [IRS] pumps will be lost and IRS pump available NPSH will be decreased by the increased temperature of the water at the suction of the IRS pump D. The capacity of the Recirculation Spray System will be reduced by the loss of the ORS pumps when the Quench Spray System is isolated; however, the IRS pump NPSH will be increased by the increase in containment pressure due to the early termination of quench spray.
NCRDOP-91.1-LP-3, Revision 4, Pages 12 & 13 1992 bank MCS Time:
I Points:
RO Tier:
Key Word:
Source:
Test:
T2G2 RECIRC SPRAY BANK C
1.00 Version:
0 1 23456 Answer: CCCABCB SRO Tier:
Cog. Level:
Exam:
Misc:
789 D B B Scramble Range: A - D T2GI C/A 4.2/ NA02301 RA/LSM/SC Tuesday, November 05, 2002 03:19:24 PM
45. 027AK3.04 001/TI I/T1G2/PZR/C/A 2.8/3.3/NEW/NA02301/C/RA/GWL/LSM/SC
- Unit 1 has had a Reactor Trip and Safety Injection due to a main steam line brea The steam break was isolated prior to the diagnostic steps in E-E-0 "Reactor Trip and/or Safety Injection", has been complete The crew is performing actions in ES-1.1 SI Terminatio Pressurizer level is 22% and slowly risin Pressurizer heaters have been energize Pressurizer pressure is 1900 psi The crew desires to raise Pressure to normal operating pressur Which one of the following describes how and why pressurizer pressure will respond when compared to normal steady state condition A. Pressure will rise more rapidly than normal due to charging flow being maximized, and the bubble being compresse B/ Pressure will rise more slowly than normal due to the liquid in the pressurizer being subcoole C. Pressure will rise more rapidly than normal due to letdown being placed in service, preheating the charging flo D. Pressure will rise more slowly than normal due to the pressurizer vapor space temperature being higher than norma A. Incorrect, Cooler water has entered the pressurizer, the actions of SI termination have the crew maintain charging flow to maintain pressurizer level but charging flow will not be maximized. (initial conditions pressurizer level 22% and slowly risin B. Correct, the water in the pressurizer is subcooled and will require time to heat, therfore pressure rise will be slower when compared to normal steady state condition C. Incorrect, placing letdown in service will tend to lower pressurizer pressure, so the pressure rise would be slowe D. Incorrect, pressurizer vapor space temperature will be lower than normal, based on Psat-Tsat condition MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBCBACBCCD Scramble Range: A - D RO Tier:
TIGI SRO Tier:
T1G2 Key Word:
PZR Cog. Level: C/A 2.8/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/GWL/LSM/SC Tuesday, November 05, 2002 03:19:24 PM
46. 028AA2.02 001//TIG3/IA LOSS/C/A 3.4/3.8/BANKINA02301/S/RA/LSM/SC Given the following conditions:
-
Unit 1 was operating at 100 percent powe A loss of station IA has occurre The unit has been tripped due to low IA pressur The procedure will eventually direct the closure of one of the charging line MOVs for which one of the following reasons?
A' a loss of PZR level contro B. the letdown divert valve failing to the strippe C. the letdown pressure control valve, 1-CH-PCV-1145, failing close D. a loss of VCT makeup capabilit *REFERENCE VISION OBJ. 11662, AP-28 (bank)
Bases for isolating charging BANK 1996/01/29 MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ABBBDABCCA Scramble Range: A - D RO Tier:
SRO Tier:
T1G3 Key Word:
IA LOSS Cog. Level:
C/A 3.4/ Source:
BANK Exam:
NA02301 Test:
S Misc:
RA/LSM/SC
.
.
.
......
aannn o,..~C'.fl flt57 I uesday, November uo, 2u00 03: i rlv
47. 028K5,04 O01/T2G3/T2G2/HYDROGEN/M 2.6/3.2*/BANK/NA02301/C/RA/LSM Which one of the following describes the design basis of the Hydrogen Recombiner System?
A./ Reduce hydrogen concentration from 4 percent to 0.5 percent at a flow rate of 50 SCF B. Maintain hydrogen concentration less than 6 percent following a LOCA with Zr-Water reactio C. Reduce hydrogen concentration from 15 percent to 4 percent in less than 10 days following a LOC D. Maintain Hydrogen concentration less than 6 % in less than 10 days following a LOC L.P. NCRODP-91.2-LP-1, Rev. 6, p. 29, Objective G 1992 bank MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ABABDCBACB Scramble Range: A - D RO Tier:
T2G3 SRO Tier:
T2G2 Key Word:
HYDROGEN Cog. Level:
M 2.6/3.2*
Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LSM
Tuesday, November 05, 2UUZ U0:iu:19 :2vM
48 029EA209 001 /T1G1/REACTOR TRIP/M 4.4/4.5/NEW/NA02301/S/RAILSM!SC both must be opened reference 1-FR-S.1 step 2.d RNO MCS Time:
I Points:
1.00 Version:
Answer:
RO Tier:
Key Word:
Source:
Test:
REACTOR TRIP NEW S
01234567 CAAACAAA SRO Tier:
Cog. Level:
Exam:
Misc:
B B Scramble Range: A - D TIGI M 4.4/ NA02301 RA/LSM/SC
Tuesday, November 05, 2002 03:19:25 PM Unit one has had a turbine trip, but the reactor did not trip and the generator out put breaker did not open. The RO verifies automatic rod insertion and verifies the turbine is tripped. Which one of the following describes the procedurally required actions if the generator output breaker cannot be verified open within 30 seconds?
A. Manually open G-12 ONL B. Manually open exciter field breaker ONL C0 Manually open both G-1 2 and the exciter field breake D. Manually open either G-12 or the exciter field breake. 029K4.03 001/T2G2/T2G2/PURGE/M 3.2/3.5/BANK/NA02301/C/RA/LM/SC Which one of the following conditions will automatically trip the containment purge supply fans?
A." Containment particulate radiation monitor hi-hi alar B. Safety Injectio C. Containment Depressurizatio D. Vent stack "B" radiation monitor hi-hi alar Bank supplied by Utility for this exa Changed K/A since orginal selected K/A did not apply to North Anna. There was no physical connection between the CTMT and the purge system blowers. The original question also required the operator to know from memory a caution in an OP. This was not considered information an operator should have memorize Which one of the following describes the precautions to be taken BEFORE operating a purge blower?
Containment pressure must be atmospheric, RCS temperature < 200 degrees Break containment vacuum using MOV-HV-1 OOB and ensure reactor shut dow Pressurize containment to atmospheric, verify RCS temperature < 250 degrees F, bypass filters unless particulate is hig Be in Mode 6, RCS temperature < 200 degrees F, containment pressure within 4 psi of atmospheri L.P. NCRODP-91.2-LP-1, Rev. 6, page 33, Objective G 1-OP-21.2 Containment Purge, Rev. 13, page 2 & 3 of 8 1992 bank MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ABACBAAADA Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
PURGE Cog. Level:
M 3.2/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LM/SC Tuesday, November 05, 2002 03:19:25 PM
50. 032AA2.04 001//i 1G2/SOURCE RANGE/M 2.3.1/3.5/BANK/NA02301/S/RA/LSM/SC Your shift is in the process of performing a reactor startup, and the reactor operator is withdrawing control rods to take the reactor critical. As reactor power increases, the reactor operator can manually block the source-range nuclear instruments after verifying which one of the following?
A. Both intermediate-range detectors are properly compensated by indicating within one-half decade of each othe B. The intermediate-range detectors have both increased at least one decade from the bottom of their scal C. Both intermediate-range detectors are indicating on-scal DW At least a one decade overlap between the source-range and intermediate-range detectors.
replaced question - KA was not applicable to NA MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 Answer: DDBBAACD RO Tier:
SRO Tier:
Key Word:
SOURCE RANGE Cog. Level:
Source:
BANK Exam:
Test:
S Misc:
Tuesday, November 05, 2002 03:19:25 PM
DC Scramble Range: A - D TIG2 M 2.3.1/ NA02301 RA/LSM/SC
51. 034K4.02 00 I/T2G3//HOIST/M 2.6/3.4/BANK/NA02301/R/RA/LSM Which one of the following describes the conditions which render the Manipulator Crane bridge AND trolley inoperative simultaneously?
A. The upender is in the vertical position in the fuel transfer cana B. The trolley bypass is engage CU The hoist is being operated or the gripper tube is dow D. The Dillon load cell indicates 1200 pounds or greate L.P. NCRODP-92.9-LP-3, Rev. 2, p. 37, Objective D 1992 bank MCS Time:
Points:
1.00 Version:
0 1 2 3456789 Answer: CCBDACDDDD Scramble Range: A - D RO Tier:
T2G3 SRO Tier:
Key Word:
HOIST Cog. Level:
M 2.6/ Source:
BANK Exam:
NA02301 Test:
R Misc:
RA/LSM
-
.
-
Ar~~no.t~.lffrWA62 Tuesday, November u0, LUUL 03: I9:2L riVI
52. 035K6.03 00I/T2G2/T2G2/S/G LEVEL/C/A 2.6/3.0/NEW/NA02301/C/RA/LSM/SC The crew has entered 1-AP-3, Loss of Vital Instrumentation, due to the failure of "B" Steam Generator Level Channel Ill. In accordance with 1-AP-3, which one of the following describes the actions that must be taken?
A. There are no required action B. Place the associated Main Feed Reg Valves in Manual ONL Cf Place BOTH the associated Main Feed Reg Valves and Main Feed Reg Bypass Valves in Manua D. Select Steam Generator Level Ch II as controlling channel.
1-AP-3 LOSS OF VITAL INSTRUMENTATION 2 of 15
[ 2] VERIFY STEAM GENERATOR LEVEL Do the following:
CONTROL PARAMETERS - NORMAL:
... Steam Flow-Feed Flow
- -.Steam Generator Level Ch Ill
.. Steam Pressure..
MCS Time:
I RO Tier:
Key Word:
Source:
Test:
Points:
1.00 Version:
Answer: C T2G2 S/G LEVEL NEW C
a) Place the associated valves in MANUAL Main Feed Reg Valves Main Feed Reg Bypass Valves b) Control Steam Generator level 123456789 CDBBABACA Scramble Range: A - D SRO Tier:
T2G2 Cog. Level:
C/A 2.6/ Exam:
NA02301 Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:25 PM
53. 036EA2.01 001//TlG3/3.4/4.1/M 3.4/4.1/BANK/NA02301/S/RA/LSM/SC During the refueling of Unit 2, a fuel assembly was placed in the wrong location. Per transient and accident analysis, this mistake could be found by which one of the following?
A. During the performance of the normal required calorimetri B. By observing the axial flux differentia Cf During the incore flux mappin D. At 100% power using the quadrant power tilt rati Replaced with Bank question-original not required knowledge and not the normally required SRO action Reference:
MODULE NCRODP-48 FUEL HANDLING SYSTEM Inadvertent loading of a fuel assembly into an improper position. This accident analysis assumes that a fuel assembly is placed in the wrong position in the core. An example is the inadvertent loading of a fuel assembly position requiring burnable poison rods with an assembly not having burnable poison rods. The power distortion due to any combination of misplaced fuel assemblies would significantly raise peaking factors and would be readily observable with in-core flux monitors. Core thermocouples would also indicate any abnormally high coolant enthalpy rise. In-core flux measurements are taken during the startup following the refueling operations. The results of this analysis concluded that fuel assembly loading errors are prevented by administrative procedures implemented during core loading. In the unlikely event that a loading error occurs, the power distribution effects either will be readily detected by the in-core movable detector system or will cause sufficiently small perturbation to be acceptable within the uncertainties allowed between nominal and design power shape MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CAAABBBBCD Scramble Range: A - D RO Tier:
SRO Tier:
T1G3 KeyWord:
3.4/ Cog. Level:
M 3.4/ Source:
BANK Exam:
NA02301 Test:
S Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:25 PM
54. 037AK1.02 001/T 1G2/T1G2/3.5/3.9/C/A 3.5/3.9/M/NA02301/C/RA/LSM Given the following conditions:
-
The unit was operating at 100% powe A major steam line rupture occurred on the "A" S An automatic SI was receive All systems responded as designe The operating crew is now in the later steps of 1-E-2, "FAULTED STEAM GENERATOR ISOLATION".
-
PRZR level has suddenly started decreasin PRZR pressure is 2100 PSIG and decreasin MS-RM-170 ("A" SG STEAMLINE RADIATION MONITOR) has a valid HI alar Based on the above information, the crew should do which one of the following?
A. upon completion of 1-E-2, transition to 1-ES-B. immediately enter 1-E-C. upon completion of 1-E-2, transition to 1-E-D' upon completion of 1-E-2, transition to 1-E-VISION OBJ. 13842 modified - bank 1996/01/29 MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DADAADAACC Scramble Range: A - D RO Tier:
TIG2 SRO Tier:
T1G2 Key Word:
3.5/ Cog. Level:
C/A 3.5/ Source:
M Exam:
NA02301 Test:
C Misc:
RA/LSM
Tuesday, November U0, ZUUZ u03:19:25 P
55. 038EA2.09 001//TIG2/4.2/4.2/C/A 4.2/4.2/NEW/NA02301/S/RA/LSM Which one of the following conditions support or indicate natural circulation flow in accordance with 1-E-3, Attachment 1, Natural Circulation Verification?
A. "
SG pressures - STABLE OR DECREASING RCS Hot Leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE RCS Cold Leg temperatures - STABLE OR DECREASING " SG pressures - STABLE OR DECREASING
.. * RCS Hot Leg temperatures - STABLE OR DECREASING RCS Cold Leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE SG temperature - AT SATURATION TEMPERATURE FOR SG PRESSURE RCS Hot Leg temperatures - STABLE OR DECREASING
- .
RCS Cold Leg temperatures - STABLE OR DECREASING Reference 1-E-3 Attachment 1 NATURAL CIRCULATION VERIFICATION NOTE: The following conditions support or indicate natural circulation flo. 1. 1. VERIFY NATURAL CIRCULATION FLOW
- .. Core Exit TCs - STABLE OR DECREASING RCS Cold Leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 RO Tier:
Key Word:
Source:
Test:
Answer: CACBDBDBAD Se SRO Tier:
T1G2 Cog. Level: C/A 4.2/ Exam:
NA02301 4.2/ NEW S
Misc:
ramble Range: A - D RA/LSM
Tuesday, November 05, 2002 03:19:26 PM
56. 038EK3.08 00I/TI G2//RCP TRIP/M 4.1/4.2/NEW/NAO2301/R/RA/GWL/LSM/SC-Unit 2 has had a steam generator tube ruptur The crew is performing 2-E-At the step for checking RCP trip and charging pump recirc. criteria the crew determines that the all RCPs must be trippe Which one of the following correctly describes the reason for tripping the RCPs during a SGTR event when the trip criteria is met?
A. This will ensure core cooling during a steam generator tube rupture even B.' To minimize the effects of a misdiagnosis of the fault or a multiple failure even C. To reduce RCS pressure, since this will slow the rate of inleakage into the steam generato D. To allow natural circulation cooling to develop, since this will expedite steam generator cooldown.
NCRODP-92-LP-5. North Anna Steam Generator Tube Rupture lesson plan page 1 WOG Background documen A. Incorrect, Tripping the RCP's during a tube rupture event is to minimize the effects of a
misdiagnosis. Core cooling would be better if the RCPs were left runnin B. Correct, lAW the WOG the tripping of the RCPs during a tube rupture event is so that the event will not be misdiagnosed if for some reason later the pumps were tripped/or lost at an inconvient time (a time that might mask the diagnosis).
C. Incorrect, stopping the RCPs will actually take away one of the methods for pressure reduction (sprays) securing the pumps will only slightly lower pressure and then is will be determined by heat input from the core and leak rat D. Incorrect, Stopping the pumps would not in themselves does not allow natural circulation to develop, the pumps must be stopped for natural circ cooling to occur but steam generator position and steam flow actually determine (delta T) natural circ flow. This would not expedite the cooldow MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBCCBCBBBC Scramble Range: A - D RO Tier:
TIG2 SRO Tier:
Key Word:
RCP TRIP Cog. Level:
M 4.1/ Source:
NEW Exam:
NA02301 Test:
R Misc:
RA/GWL/LSM/SC Tuesday, November 05, 2002 03:19:26 PM
57. 039K5.08 001/T2G2/T2G2/MSR/C/A 3.6/3.6/NEW/NA0230 1/C/LSM/LM!GH/SC Which one of the following would be the effects on reactor power and enthalpy of the HP Turbine Exhaust Steam entering the MSR if scaling of the heat exchanger reduces the MSR's efficiency by 50%? (Ignore any slight changes in ambient losses or gains)
A" Reactor power would increase and enthalpy would remain unchange B. Both reactor power and enthalpy would increas C. Both reactor power and enthalpy would decreas D. Reactor power would decrease and enthalpy would remain unchanged.
Solution: a Reactor power would increase because feedwater temperature would not be heated by the MSR. Enthalpy at the inlet of the MSR's would remain at the enthalpy of the outlet of the first stage of the turbine turbine which should essentially remain unchange NCRODP23 Assume that at full power operation 9,798,706 Ibm/hr of wet steam exits the HP turbine and enters the MSRs at an enthalpy (h) of 1115.5 Btu/Ibm and a pressure of 230 psi The quality (X) of the steam entering the MSRs is determined by solving the thermodynamic formula; h = hf + X hfg for X, and by finding the values for hf (368.3)
and hfg (831.8), corresponding to a saturation pressure of 230 psia, in the steam tables:
X = (h - hf)/hfg The quality of the inlet steam to the MSRs in this example is 89.8 percent. The MSRs remove approximately 10 percent (988,745 Ibm/hr) of this mass in the form of moisture (100 percent of the liquid). Thus, the steam entering the MSR tube bundle is dry, saturated steam (X=1 00 percent). The enthalpy of the steam entering the tube bundle is h = hf + X hfg, or h = 368.3 + 100(831.8), or h = 1200.1 Btu/Ib MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: AACBABDBBD Scramble Range: A - D Tuesday, November 05, 2002 03:19:26 PM
RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
MSR Cog. Level:
C/A 3.6/ Source:
NEW Exam:
NA02301 Test:
C Misc:
LSM/LM/GH/SC Tuesday, November 05, 2002 03:19:26 PM
58. 041K6.03 OOI/T2G3/T2G3/STEAM DUMPS/C/A 2.7/2.9/BANK/NA02301/C/LSM/LM/SC During operation of the Steam Dump System, which one of the following describes how the steam pressure arming signal is cleared?
A. By shifting the Steam Header Pressure Controller to MANUAL and decreasing signal demand to zer B." Must take the Steam Dump Mode Selector Switch to the Tavg Mod C. Must take the Steam Dump Interlock Switch to OFF/RESET and return the switch to the ON positio D. Must take the Steam Dump Interlock Switch to the BYPASS INTERLOCK positio bank-1992/03/16 Surry MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBBBACBABB Scramble Range: A - D RO Tier:
T2G3 SRO Tier:
T2G3 Key Word:
STEAM DUMPS Cog. Level:
C/A 2.7/ Source:
BANK Exam:
NA02301 Test:
C Misc:
LSM/LM/SC
-
..
.
~nsA70 Tuesday, November U0, LUUL U3: 9:2zo Hv
59. 045K4.34 001/T2G3/T2G3/ROD CONTROL/C/A 2.7/2.9/NEW/NA02301/C/RA/GWL
- Unit I has ramped to 12% Power due to maintenence concern PT-446 and PT-447 indicate approximately 12 % turbine loa Rod control has been left in automatic from the ramp dow Steam Dumps have been taken to the steam pressure mode in preparation for removing the turbin The RO inadvertently opens the steam dumps until reactor power indicates 17% on N-41 and N-42, and 16 % on N-43 and N-4 RCS temperature lowers to 543 degrees Which one of the following describes the effect this failure will have on the Rod Control System?
A. Control Rod will step out at 40 spin until Tave and Tref are within 1.5 degree B! Control Rods will not step out due to control interlock C-5 not being satisfie C. Control Rod will step out at 32 spm until Tave and Tref are within 1.5 degree D. Control Rods will not step out due to permissive P-10 not being satisfie NCRODP-77-NA Objective I, NCRODP-65, Objective A and A. Incorrect, Rods will not step out in auto due to turbine load being < 15%.
B. Correct, Rods will not step out due to turbine load being < 15% and C-5 not allowing auto rod motio C. Incorrect, Rods will not step out due to turbine loa D. Incorrect, Rods will not step out and P-10 does not effect auto-rod motio MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBCABCADAC Scramble Range: A - D RO Tier:
T2G3 SRO Tier:
T2G3 Key Word:
ROD CONTROL Cog. Level:
C/A 2.7/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/GWL Tuesday, November 05, 2002 03:19:26 PM
anO n~i A A9 n9) nfl/l/Tflhl/2 c/4 1/CIA t1/4.1/NFEW/NA02301/S/RA/LSMISC Unit 1 is at 100 percent powe.TeR reports that you have degrading Condenser vacuum and decreasing generator outpu You direct the crew to enter 1-AP-14, Low Condenser Vacuu Reactor power has been reduced to 60%, condenser pressure is now 5.6 inches of Hg absolut Which one of the following is the correct action?
A. Exit 1-AP-14 and go to 1-E-B! Go to 1-E-0 and complete 1-AP-1 C. Complete 1-AP-14 and then go to 1-E-0 D. Place Condenser Hogger Ejectors in Service per 1-OP-3 Reference - 1-AP-14, revision 17 a 1-E-0 does not contain sufficient guidance for this condition, must also remain in the AP b correct per step 4, RNO c Have reached reactor trip criteria for Condenser pressure, must enter 1-E-0 d only appropriate, if pressure had not degraded MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BCDBBBCDAD Scramble Range: A - D RO Tier:
SRO Tier:
TIGI Key Word:
3.9/ Cog. Level:
C/A 3.9/ Source:
NEW Exam:
NA02301 Test:
S Misc:
RA/LSM/SC L__
l_
ORA.....
t^lo.
if DNA
I uesday, INoVemIber U0, 20U0 u,:U
61. 055EK 1.02 001/TO1G/T lG 1/CSFST/C/A 3.3/3.7/BANK/NA02301/C/RA/LSM VISION OBJ. 13835 (LORP)
BANK 1996/01/29 MCS Time:
I Points:
1.00 RO Tier:
Key Word:
Source:
Test:
TIGI CSFST BANK C
Version:
0 1 234567 Answer: AABBBDDA SRO Tier:
Cog. Level:
Exam:
Misc:
C A Scramble Range: A - D TIGI C/A 3.3/ NA02301 RA/LSM Tuesday, November 05, 2002 03:19:26 PM When depressurizing SGs in 1-ECA-0.0, the operator is directed to check RCS Tcold temperatures > 315 OF during the depressurization to ensure that the evolution does not do which one of the following?
A" challenge the integrity critical safety functio B. disrupt natural circulatio C. create a void in the reactor vessel upper hea D. inject nitrogen from the SI accumulators into the RCS.
62.055K3.01 001/T2G2//CONDENSER/C/A 2.5/2.7/M/NA02301/R/RA/LSM/SC Unit 1 is 18% power during startu A malfunction causes all condenser waterbox vacuum breakers to ope Condenser pressure is 5.0 inches Hg absolute and increasin Which one of the following is the required immediate action?
A. Reduce turbine power and maintain turbine load until condenser vacuum is stabl B. Trip the turbine and go to 1-AP-2.1, Turbine Trip without Reactor Trip Require C. Trip the turbine and reduce the reactor to less than 5%.
DO Go to 1-E-0, Reactor Trip and Safety Injection.
1-AP-14, Rev. 9, page 2 1993 bank MCS Time:
I Points:
RO Tier:
T202 Key Word:
CONDENSER Source:
M Test:
R 1.00 Version:
0 1 234567 Answer: DBBCCAAB SRO Tier:
Cog. Level:
Exam:
Misc:
A B Scramble Range: A - D C/A 2.5/ NA02301 RA/LSM/SC
Tuesday, November 05, 2002 03:19:26 PM
63. 056A2.04 001/T2GI/T2GI/CONDENSATE/C/A 2.6/2.8/NEW/NA02301/C/RA/LM/LSM/SC REF: MODULE NCRODP-25 MAIN CONDENSATE SYSTEM pages 62-63 OBJ: 2.19 Distractor B - PS-CN-1 18A is the condensate pump discharge header pressur Header pressure will not decrease on a pump star Distractor C - A faulted speed switch will result in the associated pump tripping and auto-start of the third pum Distractor D - A drop in Feedwater suction pressure is not characteristic with starting a second condensate pum MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 RO Tier:
Key Word:
Source:
Test:
T2GI CONDENSATE NEW C
Answer: ADADBADDCC Scrambl SRO Tier:
T2G0 Cog. Level: C/A 2.6/ Exam:
NA02301 Misc:
RA/LMfLSM/SC e Range: A - D
Tuesday, November 05, 2002 03:19:27 PM
- Unit I is operating at 5% power
- 1B condensate pump is runnin IC condensate pumps is in AUT A condensate pump is manually starte Condensate pump 1 C auto starts Which ONE of the following is the most probable cause of both condensate pump 1C starting and what action should be taken?
Af Caused by the 1C handswitch being in the AUTO position when starting the 1A condensate pump. The 1C condensate pump should be shutdown per normal operating procedure B. Starting condensate pump 1A dropped pressure sensed by PS-CN-1 18A to below 440 psig, an auto-start for IC. The 1C condensate pump should be shutdown per normal operating procedure C. Caused by false low hotwell level generated because the 1B pump was running when starting the 1A condensate pump. The 1C condensate pump should be shutdown per normal operating procedure D. Caused by a drop in Feedwater suction pressure below 280 psig, characteristic of starting a second condensate pump at this power level. Notify the Shift Superviso. 056AK3.02 00I/TIG3//ECA-0.0/C/A 3.5/3.9/NEW/NA02301/R/RA/LSM/SC Unit 1 has lost off site power and the EDGs failed to start. The crew enters 1-ECA-Loss of all AC power. The crew was successful in starting the I H emergency diesel generator and has restored power to the 1 H 4160-volt emergency bus. An SI occurred during the recovery efforts. Which one of the following describes your required actions, and the reason for those actions?
A. The SI should not be reset to allow automatic loading of equipment on the 1 H bu B. The running SI pumps should be stopped, operators must manually load equipment on the 1H bus in a controlled fashion per 1-EC-0.0 to prevent overloading the ED C. The SI should be reset to allow manual loading of equipment on the 1 H bu D. The SI should not be reset, the running SI pumps should be stopped because of sequencing and loading concerns on the 1 H bu NEW Reference 1-ECA-0.0 Revision 18, Caution before step 9 page 6 of 18 distractor analysis - this is only done because of loading concerns, the SI is required to be reset to allow the manual loading of a recovered ED MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CABACDCBAC Scramble Range: A - D RO Tier:
TIG3 SRO Tier:
Key Word:
ECA-Cog. Level:
C/A 3.5/ Source:
NEW Exam:
NA02301
"Test:
R Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:27 PM
65. 057AA1.06 001/TIG1/T1GI/MANUAL CONTROL/C/A 3.5/3.5/BANK!NA02301/C/RA/LSM Given the following conditions:
-
Unit I is at 35 percent powe While hanging a tagout, an operator opened the wrong breaker and de-energized the power to 1-DA-TV-1OO The mispositioned breaker has been re-closed lAW procedure J-A6, "RX CONT SUMP HI LEVEL" has alarme In order to pump the containment sump, the operator will have to do which one of the following?
A. push the OPEN button for 1-DA-TV-1OO BY push the CLOSE button for 1-DA-TV-1OO C. cycle 1 -DA-P-1 B to OFF, then back to AUT D. reset train "B" of Phase "A" isolatio BANK 1996 VISION OBJ. 11550 MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BCACCCBDDC Scramble Range: A - D RO Tier:
TIGI SRO Tier:
T1GI Key Word:
MANUAL CONTROL Cog. Level: C/A 3.5/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LSM
Tuesday, November U0, zuuz U3:19:27 PrMv
66. 058AK3.02 001/T1G2/TIG2/LOSS OF DC POWER/C/A 4.0/4.2/M/NA02301/C/RA/LSM/SC Given the following:
-
Unit 1 was operating at 100 percent powe CH-P-1A was runnin A loss of DC control power to the 1J bus has occurre While stabilizing the unit, a spurious SI occurre As you enter E-0, which one of the following pump combinations will exist as a result of these failures?
A. 1-CH-P-1A NOT running, 1-CH-P-1B running, 1-CH-P-iC runnin B/ 1-CH-P-1A running, 1-CH-P-1B NOT running, 1-CH-P-1C NOT runnin C. 1-CH-P-1A running, 1-CH-P-1B running, 1-CH-P-1C NOT runnin D. 1-CH-P-1A running, 1-CH-P-1B NOT running, 1-CH-P-IC runnin Bank NCRODP-35-LP-1 OBJ. B, NCRODP-41-LP-1 OBJ. G MCS Time:
Points:
1.00 TIG2 LOSS OF DC POWER M
C RO Tier:
Key Word:
Source:
Test:
Version:
0 1 2345 6789 Answer: BCAACADACA SRO Tier:
TIG2 Cog. Level:
Exam:
Misc:
Scramble Range: A - D C/A 4.0/ NA02301 RA/LSM/SC
Tuesday, November 05, 2002 03:19:27 PM
67 059A3.02 0O/T2GI/T2GI/STEAM PRESSURE/C/A 2..9/3.1/BANK/NAO2301/C/RA/LM/GHILSM!SC REF: NCRODP26 Main Feedwater p77-81 OBJ:
SOURCE: Braidwood 4/1/96 Distractor A - Incorrect - feed flow would decreas Distractor B - Incorrect - swell in not caused by decreased feed flo Distractor D - Incorrect - feed flow would decreas Comment: The mass flow rate of steam is directly proportional to the density of steam, which is proportional to the square root of steam pressure. Loss of steam pressure transmitter appears to the Steam Generator Water Level Control system as a decrease in steam flow.
MCS Time:
I RO Tier:
T2G1 Key Word:
STEAM]
Source:
BANK Test:
C Points:
1.00 Version:
0 1 2 3456789 Answer: CCDBABBCDC Scramble R SRO Tier:
T2G I PRESSURE Cog. Level:
C/A 2..9/ Exam:
NA02301 Misc:
RA/LM/GH/LSM/SC ange: A - D Tuesday, November 05, 2002 03:19:27 PM The following plant conditions exist:
- Reactor Power is 100%
- Rod Control is in AUTO
- Steam Generator Level Control is in AUTO
- Steam Generator Level Control inputs (steam flow, feed flow, turbine first stage pressure) are selected to Channel III With NO OPERATOR ACTION, which one of the following conditions describes the effect on plant operation when channel Ill stem pressure in "A" Steam Generator fails low?
A. Increased feed flow results in Steam Generator shrink, Steam Generator level stablizes at a slightly higher leve B. Decreased feed flow results in Steam Generator swell, Steam Generator level stablizes at a slightly lower leve C. Decreased feed flow results in a reactor trip on LO-LO Steam Generator leve D. Increased feed flow results in a Hi-Hi Steam Generator level and a P-14 permissive.
68. 059AK3.03 001/T1G2/TIG1/RADWASTE/M 3.0/3.7/M/NA02301/C/RA/LSM Assume the following condition A Liquid radwaste release is in progres Unit 1 is operating at 15% powe Unit 2 is in a forced maintenance outage due to multiple condenser tube failure Unit-2 water boxes are tagged out and drained for the repair The liquid Effluent Radiation monitor has been declared inoperabl Health Physics has take a grab sample and the results indicate the release may continu Circulating water pump 1-CW-P-1C has just tripped, leaving the "A," "B," and "D" circulating water pumps running Which one of the following actions must be taken?
Secure all liquid waste release Trip the reactor and enter 1-E-Align liquid waste releases to unit-2 Trip the turbine and enter 1-AP-2.1.
discharge tunnel.
A. Not enough dilution water flow Modified bank ID: 3121 MCS Time:
Points:
1.00 Version:
Answer:
RO Tier:
T1G2 Key Word:
RADWASTE Source:
M Test:
C 01234567 AACBABAC SRO Tier:
Cog. Level:
Exam:
Misc:
CID Scramble Range: A - D TIGI M 3.0/ NA02301 RA/LSM Tuesday, November 05, 2002 03:19:27 PM AY D.
69. 059K4.16 001/T2GI//FEED PUMP TRIP/M 3.1*/3.2*/BANK/NA02301/R/RA/LSM/SC Which one of the following conditions will cause a main feedwater pump to trip?
A. "A" main feedwater pump will trip if its lube oil pressure is 7 psi B. "A" or "B" main feedwater pumps will trip on low condenser vacuu C. "B" main feedwater pump will trip if suction pressure is < 300 psig for 45 second Df Undervoltage on "A" 4160-volt station service bus will cause "A" main feedwater pump to tri REF: NA Bank 3365 OBJ:
Distractor A - Incorrect - lube oil pressure less than 5 psig causes tri Distractor B - Incorrect - there is no low condenser vacuum trip Distractor C - Incorrect - suction pressure less than 280 psig for 55 sec for B pump MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DCDCABCAAC Scramble Range: A - D RO Tier:
T2G1 SRO Tier:
Key Word:
FEED PUMP TRIP Cog. Level:
M 3.1*/3.2*
Source:
BANK Exam:
NA02301 Test:
R Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:27 PM
70 060G24.21 001//TI 2/3.7/4.3/M 3.7/4.3/BANKINAO2301/S/RA/LSM BANK ID: 2676 MCS Time:
I Points:
1.00 RO Tier:
Key Word:
Source:
Test:
3.7/ BANK S
Version:
0 1 234567 Answer: ADBCDCCD SRO Tier:
Cog. Level:
Exam:
Misc:
B D Scramble Range: A - D TIG2 M 3.7/ NA02301 RA/LSM Tuesday, November 05, 2002 03:19:27 PM While operating with primary-to-secondary leakage, steam release from the which one of the following does NOT require entry into O-AP-54, Accidental, Unplanned, or Uncontrolled Radioactive Gaseous Waste Release?
Af containment hogger discharg B. main condenser hogger discharg C. decay heat release valv D. steam generator power-operated relief valve.
71. 061K1.07 00 1/T2G I/T2G I/FIRE PROTECTION/C/A 3.4/3.7/BANK/NA02301/C/RA/LSM/LM With AFW in service to supply S/G feedwater, ECST level suddenly begins to decrease rapidly due to a rupture in the tan Which ONE of the following water sources should be aligned to supply AFW pump suction?
A. Standby 300,000-gallon condensate storage tan B. In-service 300,000-gallon condensate storage tan C. Fire Protection System using diesel-driven pump 1-FP-P-DY Fire Protection System using motor-driven pump 1-FP-P-REF: 1-AR-F-E8; 1-AP-22.5; 1-OP-3 OBJ: 5971 COMMENT: Answer correct: Fire protection using lake water is the preferred source; 1-FP-P-1 takes suction on the lak Distractors A & B: - candidate misconception concerning piping configuration for CST supply to AFW system. CST cannot be aligned to supply suction directly to the AFW pumps, only to makeup to the ECST; since the ECST is ruptured, this is not an optio Distractor C - fire protection system is the preferred alternate suction sourc Distractors wrong:
diesel-driven pump takes suction from the service water reservoi MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DAAABCCCAA Scramble Range: A - D RO Tier:
T2GI SRO Tier:
T2GI Key Word:
FIRE PROTECTION Cog. Level: C/A 3.4/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LSM/LM Tuesday, November 05, 2002 03:19:28 PM
72. 061K4.04 001/T2G1//AUX FEED WATERIM 3.1/3.4/NEW/NA02301/R/RA/LSM/GH/SC Which one of the following describes the design features that limit the maximum flow from each of the AFW pumps in the event of a piping rupture?
A! An orifice is installed on the discharge header of the turbine-driven pump. A PCV is installed on the discharge header of each motor-driven pump B. An orifice is installed on each pump's discharge heade C. A PCV is installed on each pump's discharge heade D. A PCV is installed on the discharge header of the turbine-driven pump. An orifice is installed on the discharge header of each motor-driven pump REF: NCRODP-26-NA Three auxiliary feedwater pumps are provided; two are motor-driven and the third is turbine-driven. This ensures that at least one pump is available during a complete loss of power. The discharge header of the turbine-driven pump has an orifice which limits the maximum flow from the pump in the event of a piping rupture downstream of the orifice. This flow-limiting action for the motor-driven pumps is accomplished by pressure control valves located on the pump discharge. One pump is normally dedicated to a particular steam generator, but any pump can feed any steam generator if required. A hand control valve (HCV) and a MOV header are provided on the auxiliary feedwater pumps discharge for each steam generator. These headers permit greater auxiliary feedwater diversity and reliability. Prior to joining the main feedwater headers, a check valve in the auxiliary feedwater line prevents backflow from the steam generators in the event of an auxiliary feedwater piping ruptur MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ACAACBDBDB Scramble Range: A - D RO Tier:
T2G0 SRO Tier:
Key Word:
AUX FEED WATER Cog. Level:
M 3.1/ Source:
NEW Exam:
NA02301 Test:
R Misc:
RA/LSM/GH/SC
Tuesday, November 0b, 2U00Z u0:iu:z1:
r8w
73. 062A2.09 001/T2G2//AC CURRENT/C/A 2.7/3.0/NEW/NA02301/R/LSM/LM/GH/SC Shutting the battery input breaker on a 120-volt AC Static Inverter without previously charging the capacitors results in which one of the following:
A. large voltage surges, breaker trip, and possible circuit damag B! large current surges, breaker trip, and possible circuit damag C. large surges in both voltage and current, breaker trip, and possible circuit damag D. normal breaker operations, the capacitors are charged after the battery input breaker is close Lesson Plan for VITAL AND EMERGENCY ELECTRICAL DISTRIBUTION SYSTEM (35) The static inverters provide a reliable source of AC electrical power to vital instrumentation and control. Pre-charging the inverter precharges the filtering capacitors to prevent large current surge.
Shutting the breaker without previously charging the capacitors results in large current surges, breaker over-current trip, and possible circuit damage MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBDADACCCA Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
Key Word:
AC CURRENT Cog. Level: C/A 2.7/ Source:
NEW Exam:
NA02301 Test:
R Misc:
LSM/LM!GH/SC Tuesday, November 05, 2002 03:19:28 PM
74 062AK3 0n 001/T 1GI/T G 1/SERVICE WATER/C/A 4.0/4.2/M/NA02301/C/RA/LSM Modified NA Bank ID: 3989 Original Question:
Unit 1 was operating at 100% power, with both unit l's service water pumps in operation, when a total loss of off-site power occurred. The following conditions exist:
All plant equipment responded as designed with the exception of the U-1 1H and 1J emergency diesel generators (EDG) which failed to star The operators have corrected the cause of the start failure and are preparing to start the 1H ED Following the successful start of the I H EDG, the unit I "A" service water pump will automatically start on loss of reserve station service low service water flow J4160V emergency bus UV "B" service water pump trip Answer:
A Tuesday, November 05, 2002 03:19:28 PM
Unit I was operating at 100% power, with both unit l's service water pumps in operation, when a total loss of off-site power occurred. The following conditions exist:
All plant equipment responded as designed with the exception of the 1H and 1J emergency diesel generators (EDG) which failed to star The operators have corrected the cause of the 1 H EDG and are preparing to start the ED Following the successful start of the 1 H EDG, Which one of the following is correct concerning the unit 1 "A" service water pump?
Af will automatically start on loss of reserve station servic B. will automatically start on low service water flo C. automatically start on 1J4160V emergency bus U D. must be manually restarte MCS Time:
Points:
1.00 RO Tier:
TIGI Key Word:
SERVICE WATER Source:
M Test:
C Tuesday, November 05, 2002 03:19:29 PM Version: 0 1 2345 6789 Answer: ABAADDDADB Scramble Range: A - D SRO Tier:
TIGI Cog. Level: C/A 4.0/ Exam:
NA02301 Misc:
RA/LSM
75. 062G2.1.12 001//T2G2/EDG/C/A 2..9/4.0/NEW/NA02301/S/LSM/LM/SC One qualified circuit between the offsite transmission network and the onsite Class I E AC Electrical Power Distribution System has been declared inoperable. You instruct the crew to perform 1-PT-80. The circuit that was declared inoperable fails SR 3.8. acceptance criteri Which one of the following are your next required actions?
Af Test the remaining circuit B. Enter TS Condition G Required Action G.1 and C. Enter TS Condition I Required Action I D. Enter TS 3.0.3.
A. Since the Required Action only specifies "perform," a failure of SR 3.8. acceptance criteria does not result in a Required Action not met. The remaining circuits must be teste B. Only correct if this constitutes a second required circuit failure. The second offsite circuit is inoperable, and Condition G, for two offsite circuits inoperable, is entere C. Only required if two EDG's are inoperable. The failure of the SR does not cause the EDG to be inoperabl D. Entry TS 3.0.3 is required if 3 or more sources are inoperabl Reference TS/ TS BASIS 3. AC Sources-Operating B 3.8.1 BASES (Draft 3), 07/17/01 LCO LCO 3.8.2, "AC Sources-Shutdown."
ACTIONS To ensure a highly reliable power source remains with one offsite circuit inoperable, it is necessary to verify the OPERABILITY of the remaining required offsite circuit(s) on a more frequent basis. Since the Required Action only specifies "perform," a failure of SR 3.8.1.1 acceptance criteria does not result in a Required Action not met. However, if a second required circuit fails SR 3.8.1.1, the second offsite circuit is inoperable, and Condition G, for two offsite circuits inoperable, is entere Required Action A.2, which only applies if the train cannot be powered from an offsite source, is intended to provide assurance that an event coincident with a single failure of Tuesday, November 05, 2002 03:19:29 PM
the associated EDG will not result in a complete loss of safety function of critical redundant required features. These features are powered from the redundant AC electrical power trains. The Completion Time for Required Action A.2 is intended to allow the operator time to evaluate and repair any discovered inoperabilities. This Completion Time also allows (continued)
3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:
a. Two qualified circuits between the offsite transmission network and the onsite Class 1 E AC Electrical Power Distribution System; b. Two emergency diesel generators (EDGs) capable of supplying the onsite Class 1 E power distribution subsystem(s);
c. One qualified circuit between the offsite transmission network and the onsite Class 1 E AC Electrical Power Distribution System and one EDG capable of supplying the onsite Class 1 E AC power distribution subsystem on the other unit for each required shared component; and d. Required sequencing timing relay A. One LCO 3.8.1.a offsite circuit inoperabl A.1 Perform SR 3.8.1.1 for required OPERABLE offsite circuit(s).
Tuesday, November 05, 2002 03:19:29 PM
'76 flCITV) ni nO I /'flfl9/T2g I/PlWPR SI JSPPLYVIM 2.9*/3.1*/M/NA02301/C/RA/GWL/LSMVSC Which one of the following is the power supply to the Unit 1 air side seal oil back up pump?
Af 125-volt DC bus 1-I B. "A" 480-volt AC Bu C. 120-volt AC Vital Bus 1-1 D. "H" 480-volt AC Bu North Anna Lesson NCRODP-32-NA objective G of detailed description Modified from questions # ID 183 and 11 A. Correct, this is the power supply for the Air side seal oil back-up pum B. Incorrect, this the emergency bus power supply for B train AC component C. Incorrect, this is the power supply various vital load D. Incorrect, this the emergency bus power supply for A train AC component MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ACBCCDBDBC Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
T2G1 Key Word:
POWER SUPPLY Cog. Level:
M 2.9*/3.1*
Source:
M Exam:
NA02301 Test:
C Misc:
RA/GWL/LSM/SC
I uesday, INvmbeIIIJrv Ut, tuut Ua. I:.C.-
77. 064A4.01 001/T202/T2G2/EDG/C/A 4.0/4.3/BANK/NA02301/C/RA/LSM/GH The 1J Emergency Diesel Generator (EDG) is supplying the 1J Bus. The Motor Operated Potentiometer (MOP) has failed. Speed is being controlled manuall If the 1J EDG trips due to an overspeed condition, which one of the following actions must be taken to restart the 1 J EDG? B.
Reset the shutdown relay in the control room and reset the fuel rack Reset the shutdown relay in the control room and return the MOP defeat switch to AUTO.
C. Reset the Tuel racks then return me iVMUO UeTat SWILAH LU,/-U I % D. Return the MOP defeat switch to AUTO then reset the fuel rack OP-6.2, Rev. 23, pages 3 and 4 1992 bank MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: AADACBCCDD Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
EDG Cog. Level:
C/A 4.0/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LSM/GH
Tuesday, November 05, 2002 03:19:29 PM
78. 065AK3.08 O01/TiIG3/TIG2/ES-O.2/C/A 3.0/3.2/MJNA02301/C/RA/LSM/SC Unit 1 was operating at 100% power when a loss of instrument air occurred. The crew tripped the reactor and performed I-E-0, "Reactor Trip or Safety Injection," and 1-ES-0.1, "Reactor Trip Response."
The following conditions exist:
All RCPs secured due to loss of component cooling wate Containment instrument air pressure is 0 psi CRDM fans 1-HV-F-37A, E, and F are runnin The Operations Manager has approved a natural circulation cooldow The crew should use which one of the following ?
A. 1-ES-0.2B, Natural Circulation Cooldown without CRDM Fan B. 1-OP-3.2, Unit Shutdown From Mode 3 to Mode C. 1-ES-0.2A, Natural Circulation Cooldown with CRDM Fans, then transition to 1-ES-0.2B, Natural Circulation Cooldown without CRDM Fans, when directe Df 1-ES-0.2A, "Natural Circulation Cooldown with CRDM Fans," and perform to completio Bank 84 modified format only ID: 4097 Associated objective(s):
12492 Plant Mod during the last two outages made "D" correct answe MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DDBCACDACD Scramble Range: A - D RO Tier:
T1G3 SRO Tier:
TIG2 Key Word:
ES-Cog. Level: C/A 3.0/ Source:
M Exam:
NA02301 Test:
C Misc:
RA/LSM/SC
Tuesday, November 0h, 2uuz u3:19:29 P'
'70 n0'G2 A 25 OOlfrIT/GlHFIRE PROTE.CTION/M 2.9/3.4/BANK/NA02301/R/RA/GWL/SC
- A fire is in progress in the Unit I emergency switchgear roo Halon has been discharged into the are No other manual actions have taken place in the emergency switchgear roo A Safety Injection signal has resulted in the dumping of the control room air bottles into the emergency switch gear roo Which one of the following correctly describes how the ventilation lineup will be affected?
A. The emergency switchgear room recirculation fans will tri B. 1-HV-F-41 fan starts and pressurizes the control roo C. All fans remain running and the control room pressurization is unaffecte Df The control room will not pressurize due to the closure of the fire damper North Anna Bank Question #678 Associated objective 578 A. Incorrect, Emergency switchgear room recirculation fans have not trippe B. Incorrect, with the fire dampers being closed the control room will not pressuriz C. Incorrect, the control room pressurization is affected, it will not pressurize because of the fire dampers being close D. Correct, with the fire dampers being closed the control room will not pressuriz MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DBABDBABBD Scramble Range: A - D RO Tier:
TIGI SRO Tier:
Key Word:
FIRE PROTECTION Cog. Level:
M 2.9/ Source:
BANK Exam:
NA02301 Test:
R Misc:
RA/GWL/SC
- L..... ~
noro4n On OK'A
T uesday, N*ovember*
05, 400Z
- O :**rv
80. 067G2.4.26 001//TI G1/EPIP/M 2.9/3.3/NEW/NA02301/S/RA/LSM/SC You are the Unit Supervisor. You are informed that there has been an accident involving a company truck colliding with a reserve station service transformer(RSFT).
A small fire was involved, but was quickly extinguished by the truck driver using a portable fire extinguisher located in the truck (six minutes). The RSFT has failed resulting in a partial loss of offsite power. The EDG and all the associated equipment responded normall Which one of the following describes your required response?
A. EPIP-1.01 must be initiated because Safety-related equipment was affected by the fir B. EPIP-1.01 must be initiated because the fire was extinguished with out assembling the fire brigad C. EPIP-1.01 is not initiated because although safety related equipment was effected, the fire duration was less than 10 minute D. The fire caused the activation of safety related equipment, EPIP-1.01 must be entere EPIP-1.01 must be initiated if either of the following conditions occur during a fire (0-FCA-0).
Safety-related equipment is affected by the fire Fire duration is greater than ten minutes MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 Answer: ABDCDCDD RO Tier:
SRO Tier:
Key Word:
EPIP Cog. Level:
Source:
NEW Exam:
Test:
S Misc:
Tuesday, November 05, 2002 03:19:29 PM
A A Scramble Range: A - D T1GI M 2.9/ NA02301 RA/LSM/SC
81. 068A3.02 00I/T2Gl/T2G1/RADWASTE/C/A 3.2/3.5/NEW/NA02301/C/RA/LSM Which one of the following describes how the liquid waste effluent control valve, PCV-LW-1 15, operates?
Af Fails shut on loss of air and fails shut on loss of electric powe B. Fails shut on loss of air and fails as-is on loss of electric powe C. Automatically closes on high effluent flow rate and fails shut on loss of ai D. Fails shut on high effluent flow rate.
NCRODP-92.3-LP.1, Revision 4, Page 22 MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 Answer: ADCDDBBD RO Tier:
T2G1 SRO Tier:
Key Word:
RADWASTE Cog. Level:
Source:
NEW Exam:
Test:
C Misc:
Tuesday, November 05, 2002 03:19:29 PM
C B Scramble Range: A - D T2G 1 C/A 3.2/ NA02301 RA/LSM
82 06RAK2.03 00I/T1 G I/TI GI/AUX SHUTDOWN/C/A 2.9/3.l/BANK/NA02301/C/RAILSM/SC Given the following plant conditions:
Unit 1 was at 100% power when noxious fumes forced evacuation of the control roo The immediate actions of 1-AP-20, Operation from the Auxiliary Shutdown Panel, were completed prior to evacuatio AFW flow was throttled to 150 GPM to each S/G prior to evacuatio Which one of the following describes the sequence of control manipulations required to transfer control of "C" S/G AFW flow?
Af Decrease the demand on 1-FW-HCV-1OOC controller, then place the LOCAL-REMOTE switch in LOCA B. Place the LOCAL-REMOTE switch in LOCAL, then decrease the demand on the controlle C. Place the LOCAL-REMOTE switch in LOCAL, then throttle 1-FW-MOV-100 D. Locally throttle 1-FW-MOV-1OOC, then place the LOCAL-REMOTE switch in LOCA Bank - Supplied by Utility for this examinatio Orginal Question - replaced. While this question was used on the 1992 exam, it's contents are no longer considered required operator knowledg LCV-1460 A and B, Letdown Isolation Valves, do not have "Local/Remote" switches at the auxiliary shutdown pane Which one of the following describes the reason?
HCV-1200 A, B, and C provide sufficient letdown isolation alon LCV-1460 A and B can be controlled from the Appendix R isolation pane LCV-1460 A and B cannot be operated without HCV-1200A, B and C being close There is no need to operate LCV-1460A and B after Control Room Evacuatio NCRODP-88.3-LP.1, Objective B 1993 bank MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: AABCACCACB Scramble Range: A - D RO Tier:
TIGI SRO Tier:
TIGI Key Word:
AUX SHUTDOWN Cog. Level:
C/A 2.9/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LSM/SC
.
.
..
... ~nr flflflF~fl o.4f.of f,,
iTuesday, November 05, 2002 03: 19:30 rl~
83. 071A4.24 00I/T2G01/T2G 1/WASTE GAS/M 2.9/3.4/NEW/NA02301/C/RA/LSM/SC Tuesday, November 05, 2002 03:19:30 PM The "A" waste gas decay tank (WGDT) has been sampled and release paperwork has been delivered to the control room by Health Physic Which one of the following correctly describes the personnel involvement in the control room prior to releasing the WGDT?
A. Any backboards-qualified operator can release the tank and a licensed senior reactor operator must be made aware of the releas B. Only a licensed reactor operator can release the tank and a licensed reactor operator must be made aware of the releas Cý A licensed reactor operator or license class trainee can release the tank and a licensed senior reactor operator must be made aware of the releas D. A licensed reactor operator can release the tank and an additional licensed reactor operator must be made aware of the release.
Source - new - written by licensee for this exam.
Question replaced - based on interpretation of K/A and task was normally performed by HP Which one of the following describes the controls used for Waste Gas Decay Tank releases?
The Waste Decay Tank is sampled:
and assessed independently to verify compliance with release limit and assessed independently for noble gases, radioiodines, particulates, and tritiu to ensure the 30 day dose commitment estimate is not exceed and to verify compliance with release limit to ensure the 30 day dose commitment estimate is not exceed and to verify compliance with IOCFR part 20 limit Reference:
Ncrodp-45 The actual source term through the Process Vent System is sampled routinely. Dose calculations are made to ensure that actual releases are within the limits established for this release pathway. Concurrently, dose projections are made to estimate the dose commitment for the next 30 day period. The dose projection provides a degree of assurance that continued operation will not exceed any release limit. In addition to these normal release considerations, specific releases such as a Waste Gas Decay Tank are sampled and assessed independently to verify compliance. The Process Vent System is routinely sampled for noble gases, radioiodines, particulates, and tritiu MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CBBCDBACCD Scramble Range: A - D RO Tier:
T2G1 SRO Tier:
T2G1 Key Word:
WASTE GAS Cog. Level:
M 2.9/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:30 PM
84. 072A1.01 001/T2G1/T2GI/RAD MONITOR!M 3.4/3.6/NEW/NA02301/C/RA/LSM Following a seismic event, which one of the following provide high range containment radiation monitors which are for indication/verification purposes only and do not affect the logic schemes of any safety-related plant systems?
A. Merlin-Gerin Radiation Monitoring Subsyste B. Kaman Radiation Monitoring Subsyste C4 Victoreen Radiation Monitoring Subsyste D. Nuclear Research Corporation Radiation Monitoring Subsyste Reference:
NCRODP-46 Victoreen Radiation Monitoring Subsystem. Each Containment is equipped with two Seismic class I (earthquake-proof) monitor units (see Table 46-4). Each unit consists of a high range detector (100 to 107 R/hour), a control room readout unit, a recorder, and interconnecting cable. The detectors are located approximately 155 degrees apart for Unit 1 and approximately 130o apart for Unit 2 on the inside of the containment polar crane wall to provide physical separation. Their location approximately 5 feet above the operating floor facilitates the periodic calibration of the detectors. The units are designed for intense radiation fields, such as might exist after an accident, and are powered from diverse vital buses. Their indicators and racks in the MCR also meet separation and seismic requirements. The high range containment radiation monitors are for indication/verification purposes only and do not affect the logic schemes of any safety-related plant system Nuclear Research Corporation (NRC) Radiation Monitoring Subsystem. The NRC high range monitors are located on potential effluent lines that were either not provided with Westinghouse monitors or lacked high range monitors. The NRC high range monitors (listed in Table 46-5) were installed prior to the Kaman monitors. (This is mentioned because there are some redundant monitors between the two subsystems.) These monitors measure the gaseous effluent release paths of the Process Vent Subsystem of the Gaseous Waste System, ventilation vent stacks "A" and "B", and potential effluent paths of contaminated steam (in the event of a primary-to-secondary leak in the steam generators.) The potential paths of contaminated steam monitored are the six main steam lines and the exhausts from the two turbine-driven auxiliary feed pump The high range effluent monitors consist of a detector and the control unit. The
-.
- ....
..
oo no ol99 Tuesday, November u0, ZUUZ 03::
.uiV
detector has an 9-decade range of 10-5 to 10+4 R/hr which is displayed on an 8 decade display of 10-4 to 10+4 and is comprised of two G-M tubes, an ion chamber, and an internal cesium check source. The components are enclosed in a box that protects them from expected operating environments. The detector is enclosed in a lead shield to reduce background radiatio Kaman Radiation Monitoring Subsystem. The high range monitors in this subsystem are supplemented by normal range monitors for verification purposes. The Kaman monitors are listed in Table 46-6. These monitors measure the gaseous effluent release paths of the process vent (a subsystem of the Gaseous Waste System), and ventilation vent stacks "A" and "B". These monitors operate in conjunction with the Westinghouse monitors for the same release paths. They have a greater sensitivity and range than the Westinghouse monitors for these release path They can monitor beta/gamma activity from 10-7 to 105 microcurie per cubic centimeter and iodine/particulate releases below 100 microcurie per cubic centimeter. They are redundant also with the NRC monitors. (The NRC monitors were originally intended to be a short term solution to NUREG 0578, but have been left in place as backup monitors.)
The normal range monitors consist of a cabinet assembly, a pumping system with automatic flow control, a gas sampler assembly with a beta detector and check source, two particulate-iodine collectors without detectors, and an associated microcomputer. The high range monitors consist of a cabinet assembly, a pumping system with automatic flow control, a gas sampler assembly with two G-M tubes and a check source, and three particulate-iodine collector assemblies with G-M tube detector The process vent normal range monitor from Table 46-6, GW-RM-1 78-1, has the same automatic functions as those mentioned previously for Westinghouse process vent monitors GW-RM-101 and -102. A high radiation level sensed by GW-RM-178-1 causes the flow control valve GW-FCV-101 from the waste gas decay tanks to shut, the containment vacuum pumps to trip, and the vacuum pumps' discharge valves to shu Merlin-Gerin Radiation Monitoring Subsystem. The Merlin-Gerin radiation monitoring subsystem consists of the eight N-16 radiation monitors (1-MS-RM-190, 191,192, and 193 and 2-MS-RM-290, 291, 292, and 293). These radiation monitors are used to monitor the main steam lines for indication of a Steam Generator tube leak or rupture. The monitors provide the operators with an indication in the Control Room of Steam Generator leaks as small as 1 gallon per day (GPD). The Merlin-Gerin subsystem also is installed in the discharge line of the High Capacity Steam Generator Blowdown System. These monitors, 1-SS-RM-125 and 2-SS-RM-225, monitors the blowdown effluent prior to discharge to the Circulating Water tunnel and subsequent discharge to the environment. Radiation monitor 1-SS-RM-125 is located in the Turbine Building basement adjacent to Blowdown Cooler 1-BD-E-2A/B. The monitor Tuesday, November 05, 2002 03:19:30 PM 100
has a local indicator and provides a signal to the Blowdown System control panel 1-EI-CP-10. A high radiation alarm will be annunciated in the Control Room by a Steam Generator Blowdown Trouble alarm. The Blowdown radiation monitor has a 1OE-07 to 1OE-03 pCi/cc range. The Merlin-Gerin radiation monitors are listed in Table 46-1 All Rad Monitor Alarm Setpoints are maintained in the "Rad Monitor Setpoint Records" book in the MC Tuesday, November 05, 2002 03:19:30 PM 101
85. 072K3.02 001/T2G1//3.1/3.5/M 3.1/3.5/BANK/NA02301/R/RALSM/SC Assume the following condition Unit I is in mode 6 Core off-load is in progress A fuel handling accident has occurred A high and a high-high alarm was received on Fuel Pit Bridge Radiation Monitor I-RM-RMS-15 This alarm will isolate main control room ventilation and which one of the following?
A. Dump bottled air, and start the unit-1 41 and 42 fans onl Bf Dump bottled air, and start both units' 41 and 42 fan C. Start all 41 and 42 fans, but will not dump bottled ai D. Dump bottled air, but will not start any 41 or 42 fa MODIFIED BANK 3088 Original Question:
Assume the following condition Unit 1 is in mode 6 Core off-load is in progress A fuel handling accident has occurred in the fuel building A high and a high-high alarm was received on 1-RM-RMS-1 5 This alarm will isolate main control room ventilation, dump bottled air, and start the unit -1 unit 41 and 42 fans only dump bottled air, and start both units' 41 and 42 fans and start all 41 and 42 fans, but will not dump bottled air and dump bottled air, but will not start any 41 or 42 fan Answer:
B 102 Tuesday, November Ub, ZUUL U0:i9:30 u IV
MCS Time:
I RO Tier:
T2G1 Key Word:
3.1/ Source:
BANK Test:
R Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BDADBDCBAB SRO Tier:
Tuesday, November 05, 2002 03:19:30 PM Scramble Range: A - D Cog. Level: M 3.1/ * Exam:
NA02301 Misc:
RA/LSM/SC 103
86. 073A1.01 O0I/T2G2/T2G2/RAD MONITOR/M 3.2/3.5/M/NA02301/C/LSM/LM/LSM/SC Which one of the following describe the result of a hi-hi alarm actuation on the Westinghouse clarifier outlet process monitor (RM-1 11)?
A. Only clarifier inlet valve PCV-LW-100 closes, which causes the steam generator blowdown pumps to trip. The clarifier outlet FCV-LW-1 15 does not clos BY The actuation causes clarifier outlet valve PCV-LW-1 15 to close and clarifier inlet FCV-LW-100 to close. The steam generator blowdown pumps trip when the inlet valve close C. The actuation causes clarifier inlet valve FCV-LW-100 to close and the steam generator blowdown pumps to trip. The clarifier outlet PCV-LW-1 15 does not clos D. Clarifier outlet valve PCV-LW-1 15 closes, which causes clarifier inlet valve FCV-LW-100 to close, which in turn causes the steam generator blowdown pumps to tri Bank 1091 MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BDBAACCBCD Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
RAD MONITOR Cog. Level:
M 3.2/ Source:
M Exam:
NA02301 Test:
C Misc:
LSM/LM/LSM/SC 104 Tuesday, November Ub, 0UUL u0:19:30U P
87. 075G2.1.27 001/T2G2/T2G2/CIRC WATERIM 2.8/2.9/M/NA02301/C/RA/LSM Which one of the following conditions will cause the unit-1 "A" Circulating Water System's screenwash pump (1-CW-P-2A) to start automatically when its control switch is in the AUTO position?
A. Rotation of any travelling water screen for any reaso B. Screenwash header pressure decreases below 65 psi C. Bearing Lube System PCV is fully close D'/ Bearing lube pressure < 25 psi Bank - ID: 854 Associated objective(s):
7447 List the following information associated with the circulating water screenwash pump Functions which can be performed by each pump Conditions which will start each screenwash pump manually Conditions which will start each screenwash pump automatically MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DADCCCADBC Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
CIRC WATER Cog. Level:
M 2.8/ Source:
M Exam:
NA02301 Test:
C Mise:
RA/LSM Tuesday, November 05, 2002 03:19:30 PM 105
88. 076AA1.04 00I/T 1G1/T1GI/RCS ACTIVITY/M 3.2/3.4/NEW/NA02301/C/RA/LSM/GH Unit 1 is operating at 100% powe The letdown radiation monitor is in HIGH alar You request Chemistry to confirm result Chemistry report the dose equivalent Iodine is 50 microcuries/gram Which one of the following should you do?
Af Consult with Health Physics and Chemistry to determine if a change in letdown flow is desire B. This indicates 1% failed fuel, trip the reactor and enter 1-E-C. This indicates 1% failed fuel, Isolate letdow D. Request chemistry to take a second sample, declare the monitor inoperabl Replaced question - based on expected operator knowledge MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ADBCBDBACD Scramble Range: A - D RO Tier:
TIGI SROTier:
TIGI Key Word:
RCS ACTIVITY Cog. Level: M 3.2/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/GH
.
.
.
.
.
.
o.4l.O-fA 106 I uesday, November u0, 2UU0 W:
u0 r1:1
89. 079K1.01 001/T202/T2G2/AIR SYSTEMS/M 3.9/3.1/NEW/NA02301/C/LSM/LM/SC Which one of the following describe the interconnection of the service air and instrument air systems?
A. the Service Air Receivers are the backup air supply for the Instrument Air Receiver BY the Service Air Receivers normally supply air to the Instrument Air Receiver C. the Instrument Air Receivers normally supply air to the Service Air Receiver D. the Instrument Air Receivers are the backup air supply for the Service Air Receivers.
Module NCRODP17 At one time, the Service Air Receivers served as the "backup" air supply for the Instrument Air Receivers. This was accomplished by utilizing cross connect piping between both Service Air Receivers and both Instrument Air Receivers. This cross connect piping has four installed Pressure Control Valves and four associated check valves. On decreasing Instrument Air Pressure, the Pressure Control Valves use to automatically open at a predetermined set point to allow the Service Air Receivers to makeup for pressure losses in the Instrument Air Receivers. The check valves associated with the Pressure Control Valves prevent flow reversals from the Instrument Air Receivers to the Service Air Receivers. Therefore, the Instrument Air Receivers will not depressurize if the Service Air Receivers lose pressure. In order to enhance the overall reliability of the Instrument Air Subsystem, the four Pressure Control Valves have been failed open by disconnecting their Instrument Air supply lines. As such, the Service Air Receivers have become the "normal" air supply for the Instrument Air Receivers as opposed to the "backup" air supply that was originally intende MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BDBAADDBDD Scramble Range: A - D RO Tier:
T2G2 SRO Tier:
T2G2 Key Word:
AIR SYSTEMS Cog. Level: M 3.9/ Source:
NEW Exam:
NA02301 Test:
C Misc:
LSM/LM/SC Tuesday, November 05, 2002 03:19:31 PM 107
90. 086A2.01 OO1/T2G2/T2G2/FIRE PROTECTION/M 2.9/3.1/NEW/NA02301/C/LSM/LM/SC Unit 1 receives the following alarm:
1 D-C6, MOTOR FIRE PP RUNNING A few moments later you receive a telephone call and are told that the pump was inadvertently started by an instrument technician during a surveillance. Which one of the following describes how you would secure the pump?
Af The pump can be secured from the intake structure ONL B. The pump can be secured from the service water pump house ONL C. The pump can be secured from the unit 1 benchboard ONL D. The pump can be secured from both the unit I benchboard or at the service water pump hous Lesson Plan - Fire Protection System - Fire Protection System-construction, Operation and Procedures The motor driven fire pump can be started at the unit one main control board or in the motor driven fire pump house at the intake structur The pump can only be stopped at the intake structur.
Indications available to the control room operator that a pump has started Control room annunciator 1D-C6, MOTOR FIRE PP RUNNIN.
The rated discharge flow of the motor driven fire pump is 2500 gp.
The relief valve setpoint for the motor driven fire pump is 164 psi E Diesel?driven fire pump I ?FP?P?2. [6633] The diesel driven fire pump 1-FP-P-2 takes a suction from unit one "A" service water ba.
Conditions that will cause the pump to start or trip automatically The diesel-driven pump starts in the AUTO mode if there is a loss of AC control power or main fire loop pressure drops to 52 psig as sensed by 108 Tuesday, November 0,5, 20UU2 u0:i9:31 Piv
PS-FP-1203 provided the local (AUTO-OFF-MANUAL A-MANUAL B-TEST) switch in the AUTO positio The diesel-driven fire pump automatically stops on overspeed (approx. 1900 rpm) or low oil pressure (12 psig). Manual start and stop The diesel-driven fire pump can be started from the main control room unit 1 benchboard by placing the (ON, AUTO) switch in the ON positio From the service water pump house the pump can be manually started using either of the following method (1)
By placing the local test control switch in either MANUAL A or MANUAL B and depressing the START pushbutto (2)
The pump can also be manually started by placing the local (AUTO-OFF-MANUAL A-MANUAL B-TEST) switch in the TEST positio The pump can be secured from the service water pump house ONL (1)
Depressing the local STOP pushbutton (normal method)
(2)
Placing the local (AUTO-OFF-MANUAL A-MANUAL B-TEST) switch in the OFF position Tuesday, November 05, 2002 03:19:31 PM 109
91. 103A2.04 001/T2G3//CONT. EXIT/M 3.5/3.6/NEW/NA02301/R/LSM/LM/SC Which one of the following describe the operation of the Personnel Air Lock Emergency Doors and equalizing valves?
A. Interlocked to each other and to the main door B. Interlocked to each other but not to the main door C. Not interlocked to each other but are interlocked to the main door D. Not interlocked to each other or to the main door VIRGINIA POWER 1-OP-1 NORTH ANNA POWER STATION REVISION 14 PAGE 22 OF 30 4.5 Operation Of The Personnel Air Lock Emergency Doors CAUTION: These doors and equalizing valves are not interlocked to each other or to the main door NOTE: These doors are to be used only for emergency entrance or exit from the airloc MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DBAABCCCCA Scramble Range: A - D RO Tier:
T2G3 SRO Tier:
Key Word:
CONT. EXIT Cog. Level:
M 3.5/ Source:
NEW Exam:
NA02301 Test:
R Misc:
LSM/LM/SC...
.
.................
110 Tuesday, November 05, 2002 03:19*:3 1 m-ivi
92. G2.1.1 001/T3/T3/STANDING ORDER/C/A 3.7/3.8/NEW/NAO2301/C/RA/LSM When pumping the Gas Stripper, it is permissible to pump to a lower than normal level in order to minimize the number of times that the Stripper must be pumped. Which one of the following allows this to occur?
Af Standing Order No. 215, Rev 3, Pumping of radioactive fluids to the Boron Recovery Tanks B. The NPDES release permi C. Engineering Transmittal SE-97-119, Rev. 0, but must be approved by the Operations Manager or designe D. Engineering Transmittal SE-97-119, Rev. 0, but must be approved by the Operations Manager may not be delegate Reference NEW North Anna Power Station Standing Order No. 215, Rev 3 TITLE:
Pumping of radioactive fluids to the Boron Recovery Tanks I BACKGROUND:
Deviation Report N-96-1770 was written on September 11, 1996 documenting the unplanned radioactive release while filling the "C" Boron Recovery Tank, 1-BR-TK-4 The fill rate was approximately 30 gallons per minute which exceeded the capacity of the Process Vent sweep. This produced flow through the BRT vent into the Waste Solids Building. The Waste Solids Building is not a monitored release path within the NAPS licens Task assignment MCT 96-0226 was initiated to coordinate a test of the BRT vent flow as created by the process vent system. Testing of the vent inlet flow was attempted using a differential pressure measurement across the roof vent of the boron recovery tanks. The differential pressure was too low to be measured on a manometer that has graduations of 0.1 inch (water). The calculated vent flow velocity of 1 foot/second is too low to be measured with a rotameter(REA 97-065 had been written to install throttle valves and rotometers in the vent lines from the three BRTs for utilization during filling operations). Other solutions are being sought for final resolution in accordance with MCT 96-022.
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111 Tuesday, November 05, 2u00 03: 193 i rivi
Engineering Transmittal SE-97-119, Rev. 0 summarized the measurement of sweep gas flow rate from the boron recovery tanks to the process vent. The ET provides guidance to Design Engineering for use in developing DCP 97-110 to add isolation valves as well as liquid and gas flow measuring devices to properly monitor BRT filling activities. Without the addition of these isolation valves to ensure that all sweep gas is drawn from the on-service BRT while filling, the maximum allowable fill rate for a BRT is 5 gpm. After the DCP is completed and installed, and the OP's are properly revised, the maximum allowable fill rate will increase to 30 gp Il INSTRUCTIONS:
A Miscellaneous Gas Release Permit must be completed prior to pumping from any Source to the Boron Recovery Tanks. When pumping the Gas Stripper, it is permisible To pump to a lower than normal level in order to minimize the number of times that the Stripper must be pumped.
Tuesday, November 05, 2002 03:19:31 PM Pfl T;r" T1 Answer: ADCCCBDCCA OW") 'rbý.-
TA Scramble Range: A - D 112
93. G2.1.10 001//T3/QPTR AFD/C/A 2.7/3.9/NEW/NA02301/S/RA/LSM/SC The Unit is being maintained within the boundaries of LCO 3.1.4, LCO 3.1.5,
"Shutdown Bank Insertion Limits," LCO 3.1.6, LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)," and LCO 3.2.4, "QUADRANT POWER TILT RATIO (QPTR),". Which one of the following is ensured?
A.' The core operates within the fuel design criteria.
B. There are no fuel cladding failures in the event of a LOCA, loss of flow, or other accident requiring termination by an RPS trip functio C. There are no fuel cladding failures in the event of a LOCA, loss of flow, or other accident requiring termination by an ECCS initiation.
ejected rod, ejected rod, D. There are no fuel cladding failures in the event of a LOCA, loss of flow, ejected rod, or other accident requiring termination by an RPS trip function or an ECCS initiation.
Tuesday, November 05, 2002 03:19:31 PM 113
B, C, and D are incorrect because this will not prevent cladding damage, it will ONLY minimize i Reference:
North Anna Units 1 and 2 B 3.1.6-2 Rev 4 (Draft 1), 06/19/01 Control Bank Insertion Limits B 3. The control banks are used for precise reactivity control of the reactor. The positions of the control banks are normally controlled automatically by the Rod Control System, but can also be manually controlled. They are capable of adding reactivity very quickly (compared to borating or diluting).
The power density at any point in the core must be limited, so that the fuel design criteria are maintained. Together, LCO 3.1.4, LCO 3.1.5, "Shutdown Bank Insertion Limits," LCO 3.1.6, LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)," and LCO 3.2.4,
"QUADRANT POWER TILT RATIO (QPTR)," provide limits on control component operation and on monitored process variables, which ensure that the core operates within the fuel design criteri The shutdown and control bank insertion and alignment limits, AFD, and QPTR are process variables that together characterize and control the three dimensional power distribution of the reactor core. Additionally, the control bank insertion limits control the reactivity that could be added in the event of a rod ejection accident, and the shutdown and control bank insertion limits ensure the required SDM is maintaine Operation within the subject LCO limits will limit fuel cladding failures that would breach the primary fission product barrier and release fission products to the reactor coolant to within acceptable limits in the event of a loss of coolant accident (LOCA), loss of flow, ejected rod, or other accident requiring termination by a Reactor Trip System (RTS) trip functio APPLICABLE SAFETY ANALYSES The shutdown and control bank insertion limits, AFD, and QPTR LCOs are required to maintain power distributions that limit fuel cladding failures to within acceptable limits in the event of a LOCA, loss of flow, ejected rod, or other accident requiring termination by an RTS trip functio MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ABBCABBACB Scramble Range: A - D RO Tier:
SRO Tier:
T3 Key Word:
QPTR AFD Cog. Level:
C/A 2.7/ Source:
NEW Exam:
NA02301 Test:
S Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:31 PM 114
94. G2.1.11 001//T3/TS/C/A 3.0/3.8/NEWINA02301/S/RA/LSM/SC Unit I is operating at is 97 %
At 03:00 you were informed that QPTR is 1.0 It is now 04:00 which one of the following is the highest power level the ITS will allow for this condition?
A. 97 %
B. 94%
C. 91%
D. 84%
A. This is not a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO, no power change is required for two hours.
B. Reflects 3% change (step change for each 1% RTP)
C. Reflects 6% change (half of change required at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
D. Reflects required change in two hour Reference:
(New SRO ONLY)
QPTR 3.2.4-1 Rev 4 (Draft 1), 06/19/01 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)
LCO 3.2.4 The QPTR shall be # 1.02.
MODE 1 with THERMAL POWER > 50% RT TS Required ACTIONS A. QPTR not within limi A.1 Reduce THERMAL POWER 3% from RTP for hours each 1% of QPTR > 1.00. Within 2 MCS Time:
Points:
1.00 Version:
0 1 23456789 Answer: ADCCADBCDB Scramble Range: A - D 115 Tuesday, November 05, 2002 03:19:32 PM
RO Tier:
Key Word:
TS Source:
NEW Test:
S Tuesday, November 05, 2002 03:19:32 PM SRO Tier:
T3 Cog. Level:
C/A 3.0/ Exam:
NA02301 Misc:
RA/LSM/SC 116
.d'.J. '..JL.L.AV VUI'
O
Cfl 1 10 AAhITVTtLfl Afl 1IlA lAfl </rAAN1CI1'JAfl730h/C/RA/LSM Assume the following condition Unit 1 is in mode 5 following a refueling outage Startup of secondary systems is in progress The annex supervisor assigns you to perform a valve lineup on the Main Feedwater System You are an operator who is currently working on step 3 of the development program You should do which one of the following?
A' inform the annex supervisor that you are not qualified to perform any tasks on the Main Feedwater Syste B. perform the valve lineup only if you have completed all job performance measures on the Main Feedwater Syste C. inform the annex supervisor that you are qualified to perform only those tasks in step 3 for which you have completed job performance measure D. perform the valve lineup, but notify the annex supervisor that it will have to be independently verifie Bank 39 ID: 3224 MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ADCCDCBDDD Scramble Range: A - D RO Tier:
T3 SRO Tier:
T3 Key Word:
3.4/ Cog. Level:
M 3.4/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LSM
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117 T uesday, November 05, 2004* va: 19:34,l
96. G2.1.7 001//T3/E-O/C/A 3.7/4.4/NEW/NA02301/S/RA/LSM/SC You are the U Unit I was at 100 percent powe A SGTR occurred,
-
The crew is responding to the SGTR in accordance with 1-E-3 You have just dispatch the Turbine Building Operators to Transfer Auxiliary Steam and Secure Powdex Syste Which one of the following describes the reasons that these actions must be taken at this point in this procedure?
Af To prevent contamination of the secondary systems B. To prevent the release of particulates from the powdex filter elements C. To ensure proper steam flow is available, because the auxiliary boiler is unreliabl D. To prevent lifting the relief valve on the auxiliary steam syste E-3 steps 1 through 6. NCRODP-92-LP-5 Procedure change MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: ADDBBDCADA Scramble Range: A - D RO Tier:
SRO Tier:
T3 Key Word:
E-0 Cog. Level:
C/A 3.7/ Source:
NEW Exam:
NA02301 Test:
S Misc:
RA/LSM/SC 118 Tuesday, November Ub, 20UUZ U3:19:32 IVI
97. G2.2.11 001/T3/T3/CONT. ENTRY/M 2.5/3.4/NEW/NA02301/C/RA/LSM/SC Unit I is at 100% power. A team of three people plan to enter containment to trouble shoot a failed letdown trip valv Which one of the following can an individual team member not waive prior to entry?
A! The use of SCBA for a short duration entr B. Two hours rest since last containment entr C. Working in containment twice during the previous 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. At least six hours of rest during the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a. correct - The use of SCBA is required if Containment pressure is greater than or equal to 9.0 psia and less than 12.0 psia. SCBA with 33 to 37 percent oxygen volume shall be use b, c, d these requirements are listed as those that can be waived in source - NEW VPAP-0106 1.6a. Objective Reference:
Topic 1.6: Subatmospheric Containment Entry (VPAP-0106) 13547 1.6a. Objective List the following information associated with subatmospheric containment entry (VPAP-0106).
Definition of subatmospheric containment Physical conditions limiting the authorization of individuals for entry into containment that may not be waived Conditions limiting the authorization of individuals for entry into containment that may be waived by the individual Minimum and maximum number of members of which the entry team shall consist Conditions that require the containment to be evacuated
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fA 119 I uesday, Novemoer u0, LUU2 03: 1.ot 9U V
1.6b. Content Definition of subatmospheric containment Air Pressure less than or equal to 12.0 psi.
Physical conditions limiting the authorization of individuals for entry into containment that may not be waived Containment Entry Team personnel shall not have: Obvious or known respiratory difficulties (e.g., could, flu, sinusitis) Respiratory or cardiovascular ailments or be under a physician's care for those ailments Conditions limiting the authorization of individuals for entry into containment that may be waived by the individua NOTE: The following items may be waived by the Containment Entry Team member. Worked at the Station for less than 10 continuous hours immediately before entry At least six hours of rest in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> More than two hours of light duties since the last exit from Containment Not worked twice in containment in the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Minimum and maximum number of members of which the entry team shall consist The smallest Containment Entry Team shall consist of two members, one of which shall be a HP Technicia. The largest Containment Entry Team shall consist of 15 members One member shall be the Containment Entry Team Leade.
Conditions that require the containment to be evacuated The Containment shall be evacuated if: The containment evacuation alarm, Station emergency alarm, or high flux at shutdown alarm sounds Containment evacuation is announced over the Gai-tronics system Tuesday, November 05, 2002 03:19:32 PM 120
98. G2.2.13 001/T3/T3/VALVE/M 3.6/.38/M/NA02301/C/RA/LSM/GH/SC Source: Bank ID: modified - 3222 distractor analysis:
A, B and C. This valve is part of maintenance and may be operated by Maintenance Department personne D. Correct answer per VPAP 1401 section 6.1.7 Associated objective(s):
13558 Explain the operating policy associated with the following activities (VPAP-1401).
Station component operation (SOER-94-2)
Station valve operation Tuesday, November 05, 2002 03:19:32 PM Assume the following condition Unit I is at 100% power Charging pump 1-CH-P-1C is tagged out Preventive maintenance was performed on "C" charging pump suction valve I-CH-MOV-1270A An electrician is prepared to obtain test data on the valve The valve must be returned to mid-position in accordance with the maintenance procedure. Which one of the following can perform this task?
A. Operations department personnel are the only personnel authorized to operate the valve. Any operator qualified for the task may operate this valv B. Only an operator with an active license may operate this valv C. Only an operator with an active license, or an operator in training under the direct supervision of an operator with an active license may operate this valv D. The electrician may manually operate the valve.
121
Control room notification Switchyard activities Availability of safety systems (SOER-98-1)
DOMINION VPAP-1401 REVISION 10 PAGE 13 OF 35 6.1.7 Station Valve Operations [Commitment 3.2.3]
a. Operations Department personnel shall be the only Station personnel authorized to manipulate valves except:
1. Instrument valves (e.g., local isolation valves, equalizing valves, and vents and drains) may be operated by qualified Instrument Technicians. Instrument valves are normally downstream of a root valve and are used to isolate an instrumen If an instrument has only one valve for isolation, that valve shall be used as an instrument valv. Sample valves may be operated by qualified Chemistry and Radiological Control Technician. Motor Operated Valves (MOVs) that require testing as part of a Maintenance Procedure may be operated by Maintenance Department personne. Valves that require testing as part of an Engineering Work Request (EWR) or Design Change Package (DCP) may be operated by Testing personne. Fire Protection valves may be operated by Safety and Loss Prevention personnel with the concurrence of the Operations Shift Superviso. Valves that are used to control a process (not related to plant operations) may be operated by individuals responsible for that process, as determined by Operations managemen b. Valve operation shall be in accordance with approved Station procedures, skill of the craft, or if action is required to protect Station equipment or personne c. A procedure or process that directs operation of a valve shall include sufficient Shift Supervisor notificatio d. Valves that have Danger Tags attached to them shall not be operated.
Tuesday, November 05, 2002 03:19:32 PM 122
99. G2.2.2 001/T3/T3/CONTROLS/C/A 4.0/3.5/NEW/NA02301/C/RAILSM/SC Unit 2 is at 74% reactor power. Severe thunderstorms are in the area and the unit trips for no apparent reason. The crew enters 2-E-The Reactor was verified trippe The Turbine Trip Push buttons were manually depresse Turbine stop valves FAILED to clos Which one of the following describes your next two Immediate action?
A. Put Both EHC pumps in pull to lock, then reset reheater B. Put Both EHC pumps in pull to lock, then verify Generator output breaker ope C. Manually run back turbine, then Put Both EHC pumps in pull to loc DW Put Both EHC pumps in pull to lock, then manually run back turbin reference - I -E-0 rev 27 page 2 of 22 a. Put Both EHC pumps in pull to lock, the turbine is not tripped so turbine must be run back b. generator output breakers are after first two steps c turbine is runback only if Put Both EHC pumps in pull to lock fails to close turbine stop valves. Stem states assume no other failures d. Correct answer MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DABAADBCBD Scramble Range: A - D RO Tier:
T3 SRO Tier:
T3 Key Word:
CONTROLS Cog. Level: C/A 4.0/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:32 PM 123
100. G2.2.26 001//T3/REFUELING/M 2.5/3.7/NEW/NA02301/S/RA/LSM Unit one is in refueling. 1-OP-4.1 is in effec While performing 1-OP-4.1, it becomes necessary to perform two steps out of sequence. Performing these steps requires a Completion Signature. According to 1_OP-4.1, which one of the following groups have been granted Completion Signature authority to authorize these steps to be completed out of sequence?
A. Refueling SRO, Superintendent of Operations, and Shift Superviso Bf Fueling Handling Supervisor and Supervisor Operations Suppor C. Refueling SRO, Unit SRO, and Fuel Handling Superviso D. Refueling SRO, Unit SRO, Fuel Handling Supervisor, Supervisor Operations Support, Superintendent of Operations, and Shift Supervisor.
VIRGINIA POWER 1-OP-NORTH ANNA POWER STATION REVISION 45-P2 PAGE 26 OF 143 4.22 Operations NOT requiring the completion of preceding steps may be done out of sequence. The Fueling Handling Supervisor or Supervisor Operations Support must initial and explain any steps done out of sequence on Attachment 5, Step Deviation Comment Sheet. (Steps done concurrently will NOT be considered out of sequence.)
Completion Signature authority is granted to the Fueling Handling Supervisor or Supervisor Operations Support only. Unless otherwise noted, other signature authority may be delegate MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BDBACBCBBB Scramble Range: A - D RO Tier:
SRO Tier:
T3 Key Word:
REFUELING Cog. Level:
M 2.5/ Source:
NEW Exam:
NA02301 Test:
S Misc:
RA/LSM Tuesday, November 05, 2002 03:19:33 PM 124
101. G2.3.1 001/T3/T3/2.6/3.0/C/A 2.6/3.0/BANK/NA02301/C/RA/LSM Given the following:
Committed Dose Equivalent (CDE) is 2525 mr Deep Dose Equivalent (DDE) is 2335 mr Lens Dose Equivalent (LDE) is 744 mr Committed Effected Dose Equivalent (CEDE) is 405 mr Total Organ Dose Equivalent (TODE) is 4865 mr Shallow Dose Equivalent (SDE) is 435 mr Maximum Extremity (ME) is 6565 mr Which one of the following is the Total Effective Dose Equivalent?
A. 5270 mr B. 15249 mr C. 6444 mr Dv 2740 m Source Bank - 62-ID: 3849 Associated objective(s):
13583 List the following information (VPAP-2101).
associated with the radiation protection program 10-CFR-20 dose limits Administrative dose limits MCS Time:
Points:
RO Tier:
Key Word:
Source:
Test:
T3 2.6/ BANK C
1.00 Version: 0123456 Answer: DAAADAC(
SRO Tier:
Cog. Level:
Exam:
Misc:
789 CAA Sc T3 C/A 2.6/ NA02301 RA/LSM ramble Range: A - D 125 Tuesday, November 05, 2002 03:19:33 PM
102. G2.3.2 001/T3/T3/ALARA/C/A 2.5/2.9/NEW/NA02301/C/RA/LSM/SC An accident an NAPS results in a radioactive plume passing over the switchyard. An operator stationed at the switchyard is exposed to 11 REM/hr whole body for a 2-hour perio Which one of the follow correctly describes the operator? This operator is in the:
A. low population zone and has exceeded 10 CFR100 Limit B. low population zone and has not exceeded 10 CFR100 Limit C. exclusion area and has exceeded 10 CFR100 Limit Df exclusion area and has not exceeded 10 CFR100 Limits.
Switch yard is within the exclusion area boundary and the 22 REM Dose is with-in the the 25 REM legal limi Question replaced at request of utility-New question more closely reflects information that is required operator knowledg When application of process or engineering controls to keep radioactive material in air below values that constitute an Airborne Radioactivity Area are not practicable, then VPAP-2102 directs other controls shall be:
implemented to maintain the total effective dose equivalent (TEDE) ALAR implemented to maintain the deep Dose Equivalent (DDE) ALAR Implemented through the use of a respiratory device with a higher protection factor (PF)
than the peak concentration may be selected to be consistent with TEDE ALARA Implemented through the use of a respiratory device with a higher protection factor (PF)
than the peak concentration may be selected to be consistent with DDE ALAR B & D incorrect because of DDE B&C incorrect because of higher PF Source - New VPAP-2102 REVISION 8 PAGE 16 OF 65 6.3.1 TEDE ALARA Evaluation a. Radiation exposure control measures should be designed, selected, implemented, and maintained to ensure that anticipated and actual doses are ALAR b. When application of process or engineering controls to keep radioactive material in air below values that constitute an Airborne Radioactivity Area are not practicable, then other controls shall be implemented to maintain the total effective dose equivalent (TEDE) ALARA. The use (or non-use) of a respiratory device with a lower protection Tuesday, November 05, 2002 03:19:33 PM 126
factor (PF) than the peak concentration may be selected to be consistent with TEDE ALARA. A Respiratory Hazards evaluation should be a component of a TEDE ALARA Evaluatio c. C-HP-1042.210, Respiratory Hazards Evaluation And Respiratory Protection Selection, provides several methods to evaluate respiratory hazards due to airborne radioactive material if historical conditions are not applicable or unavailable. If one of these methods is used in the TEDE ALARA Evaluation process, list methods used in part 2.1 of TEDE ALARA Evaluation (Attachment 2) and attach worksheet from C-HP-1042.210 to the completed TEDE ALARA Evaluatio d. A TEDE ALARA Evaluation shall be done if any of the following conditions are met. Documented evaluations for use (or non-use) of individual respiratory protection shall be performed on TEDE ALARA Evaluation (Attachment 2) when activity exposure projections meet one or more of the following:
- Ratio of dose rate, mrem/hr, to DAC fraction is greater than 50 and without respirator use, individual DAC-Hour exposure would exceed 10 DAC-Hours
- Requested by Station ALARA Coordinator e. HP Operations should initiate TEDE ALARA Evaluation (Attachment 2) based on the above criteria, unless deemed appropriate to do so by the Station ALARA Coordinato f. If initiated outside the Station ALARA Staff, forward TEDE Evaluation form to the Station ALARA Staff for completio Tuesday, November 05, 2002 03:19:33 PM 127
103. G2.4.1 001/T3/T3/IMMEDIATE ACTIONS/M 4.3/4.6/NEW/NA02301/C/RA/LSM/SC Solution. B A - Immediate Action Steps of FR-B - correct C - EOP immediate actions SHOULD The first four Immediate Action Steps must be performed sequentiall D - EOP immediate actions SHOULD The first four Immediate Action Steps must be performed sequentially shall be performed in sequence or sequentially not SHALL be of E-0 and the not SHALL be of E-0 and the performed from memory, and only Immediate Action Steps of FR-performed from memory, and only Immediate Action Steps of FR-S.1 Reference:
OPAP-0002 REVISION 7 PAGE 24 OF 41 e. Immediate Action Steps 1. EOP Immediate Action Steps should be performed from memory. Immediate Action Steps are designated by brackets around the individual step number in the applicable procedures (e.g., [1.J)
2. The first four Immediate Action Steps of E-0 and the Immediate Action Steps of FR-S.1 shall be performed in sequence or sequentially. All other Immediate Action steps do not have specific step sequence requirement. Immediate Action Steps that have been performed shall be verified when the EOP is entered.
MCS Time:
I Points:
1.00 Version: 0123456789 Answer: BCBBDDCCDC Scramble Range: A - D 128 Tuesday, November 05, 2002 03:19:33 PM Which one of the following are correct concerning EOP immediate actions?
A. EOP Immediate Action Steps SHOULD be performed from memor The Immediate Action Steps of E-0 SHALL be performed in sequence or sequentiall BY EOP Immediate Action Steps SHOULD be performed from memor The Immediate Action Steps of E-0 and FR-S.1 ONLY SHALL be performed in sequence or sequentiall C. EOP Immediate Action Steps SHALL be performed from memor The Immediate Action Steps E-O, FR-S.1, and ECA-0.0 ONLY SHALL be performed in sequence or sequentiall D. EOP Immediate Action Steps SHALL be performed from memory and SHALL be performed in sequence or sequentiall RO Tier:
Key Word:
Source:
Test:
T3 IMMEDIATE ACTIONS NEW C
Tuesday, November 05, 2002 03:19:33 PM SRO Tier:
Cog. Level:
Exam:
Misc:
T3 M 4.3/ NA02301 RA/LSMISC 129
104. G2.4.10 001/T3/T3/3.0/3.1/M 3.0/3.1/NEW/NA02301/C/RA/LSM/SC 1J EDG has just started. Following the start you receive a "Starting Air Pressure Low" alarm. Which one of the following is the most probable cause?
A" This is an expected alarm when the EDG start B. Air compressor control switch is in the off positio C. Failure of the 1-EG-PS-1JA to start air compresso D. Refrigerant air dryer line is froze a. This is an expected alarm for a normal start of the ED b. Would cause alarm, however the alarm would have come in before the EDG would have starte c. Would cause alarm, however the alarm would have come in before the EDG would have starte d. Would cause alarm, however the alarm would have come in before the EDG would have starte Source - NEWI-AR-21, revision 15, page 3 of 36 MCS Time:
Points:
1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: ACCCACDCAA Scramble Range: A - D RO Tier:
T3 SRO Tier:
T3 Key Word:
3.0/ Cog. Level: M 3.0/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC 130 Tuesday, November 05, 2U02 U03:19:33 PiM
105. G2.4.16 O0I/T3/T3/CSFST/M 3.0/4.0/M/NA02301/C/RA/LSM/SC Which one of the following correctly lists the CSF in DESCENDING order of priority?
A. Subcriticality, Core Cooling, Heat Sink, RCS Inventory, Containment, RCS Integrit B. Subcriticality, Containment, Heat Sink, RCS Integrity, Core Cooling, RCS Inventor CU Subcriticality, Core Cooling, Heat Sink, RCS Integrity, Containment, RCS Inventor D. Subcriticality, Containment, Heat Sink, RCS Inventory, Core Cooling, RCS Integrity.
Source BANK Modified 1990/11/26 V. C. Summer 1 MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: CACCBBABDA RO Tier:
T3 Key Word:
CSFST Source:
M C
SRO Tier:
T3 Cog. Level:
Exam:
Misc:
Scramble Range: A - D M 3.0/ NA02301 RA/LSM/SC 131 Tuesday, November 05, 2002 03:19:33 PM Test:
106. G2.4.23 001/T3/T3/RESET/M 2.8/3.8/NEW/NA02301/C/RA/LSM/SC Which one of the following is correct concerning Safety System Resets within EOPs?
A. If the system (e.g., Safety Injection, Containment Isolation) has NOT been reset once, then the Crew shall reset the system when directed by procedure if it has actuated. This action is not required if the procedure step includes the words "if necessary."
B. Once the system (e.g., Safety Injection, Containment Isolation) has been reset once, it is necessary to reposition the reset switches every time a procedure directs a reset. Verifying that the applicable status light still reflects the reset condition is not acceptable. If it does not, another reset shall be performe Cf If the system (e.g., Safety Injection, Containment Isolation) has NOT been reset once, then the Crew shall reset the system when directed by procedure whether it has actuated or not. This action is not required if the procedure step includes the words, "if necessary."
D. Once the system (e.g., Safety Injection, Containment Isolation) has been reset once, it is NOT necessary to reposition the reset switches every time a procedure directs a reset. Verify that the applicable status light still reflects the reset conditio If it does, another reset shall be performe Solution - c a. Does not have to have actuated b. It is not necessary to reset switches c. correct answer d. if it does not, another reset shall be performed NEW OPAP-0002 REVISION 7 PAGE 24 OF 41 d. Safety System Resets 1. If the system (e.g., Safety Injection, Containment Isolation) has not been reset once, then the Reactor Operator shall reset the system when directed by procedure with concurrence from the cognizant SRO whether it has actuated or not. This action is not required if the procedure step includes the words if necessar. Once the system has been reset once, it is not necessary to reposition the reset switches every time a procedure directs a reset. Verify that the applicable status light still reflects the reset condition. If it does not, another reset shall be performe Tuesday, November 05, 2002 03:19:33 PM 132
MCS Time:
RO Tier:
Key Word:
Source:
Test:
Points:
1.00 Version:
Answer:
T3 RESET NEW C
0123456789 CACAAABAAA SRO Tier:
T3 Cog. Level: M 2 Exam:
NA(
Misc:
RA/
Scramble Range: A - D
.8/ LSM/SC 133 Tuesday, November 05, 2002 03:19:34 PM
107. G2.4.32 001/T3/T3/EPIPS/M 3.3/3.5/BANK/NA02301/C/RA/LSM Which of the following station procedures must be initiated if the Hathaway annunciators, the Prodac-250 computer, the PCS computer, and the ERF computer systems are all inoperable during a unit transient?
A! Emergency Plan Implementing Procedures (EPIPs).
B. Annunciator Response Procedures (ARs).
C. Emergency Operating Procedures (EOPs).
D. Critical Status Function Trees Source - bank ID: 634 Associated objective(s):
7843 Identify the appropriate controlling station procedure to be used in response to a loss of the Hathaway annunciators, the Prodac-250 computer, and the ERF computer system during a unit transien MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: AABCCADDCC Scramble Range: A - D RO Tier:
T3 SRO Tier:
T3 Key Word:
EPIPS Cog. Level:
M 3.3/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LSM 134 Tuesday, November U0, ZUU2 u0j:19:4 rIVi
108. G2.4.6 00I/T3/T3/QUENCH SPRAY/C/A 3.1/4.0/BANK/NA02301/C/RA/LSM Given a spurious CDA, the operating crew uses E-1, Attachment #3, "Termination of Quench Spray," as a guide. Which of the following represents the correct sequence for securing Quench Spray?
Af Reset CDA; stop the QS pumps; close the QS pump discharge valves; then close the CAT discharge valve B. Reset CDA; stop the QS pumps; then close the CAT discharge valves; and then the QS pump discharge valves.
C. Stop the QS pumps; close the valves.
CAT discharge valves; then the QS pump discharge D. Stop the QS pumps; close the QS pump discharge valves; then reset CDA.
Source - Bank ID: 4074 Associated objective(s):
13593 Explain the guidelines for using the following types of procedures (OPAP-0002; SER-1999-2).
Operating procedures Emergency operating procedures Abnormal procedures Annunciator response procedures MCS Time:
I Points:
1.00 V
A RO Tier:
Key Word:
Source:
Test:
ersion:
0 1
.nswer: A B T3 QUENCH SPRAY BANK C
23456789 BDCBDBBB SRO Tier:
T3 Cog. Level: C/A 3.1/4 Exam:
NA02301 Misc:
RA/LSM Scramble Range: A - D Tuesday, November 05, 2002 03:19:34 PM 135
109. W/E03EK3.1 001/T2G2/T2G2/2.8/3.2/C/A 3.3/3.7/NEW/NA02301/C/RA/LSM/SC Unit 1 is recovering from a small break LOC ES-i.2, "Post-LOCA Cooldown and Depressurization", is in us All ECCS equipment is operating properl Depressurization of the RCS has commence Pressurizer level has just risen rapidly from off-scale low to 50%.
Which one of the following is the cause of the rapid increase in pressurizer level?
A. A pressurizer vapor space leak has develope B. Voiding is occurring in the reactor vessel hea C. SI flow is refilling the pressurize D. Temperature variations are affecting the reference leg of the pressurizer level instrument.
REFERENCE ES-1.2 - Post-LOCA Cooldown and Depressurization, Caution prior to Step 12.
MCS Time:
RO Tier:
Key Word:
Source:
Test:
Points:
1.00 Version:
Answer:
T2G2 2.8/ NEW C
0123456789 BABACBDAAB Scramble Range: A - D SRO Tier:
T2G2 Cog. Level:
C/A 3.3/ Exam:
NA02301 Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:34 PM 136
110. WEOIG2.4.4 00i/T1G2//SI TERMINATION/C/A 4.0/4.3/M/NA02301/R/RA/GWL/SC
- Unit 1 has had a Reactor Trip and Safety Injection due to a main steam line break in containmen "B" S/G has boiled dry and pressure is approximately 50 psi "A" S/G narrow range level is 20% and slowly risin "C" S/G narrow range level is 10% and slowly risin Total AFW Flow is 300 gp Pressurizer level is 19% and risin Containment pressure is 21 psia and slowly lowerin RCS subcooling is stable at 88 O RCS pressure is 1800 psig and slowly risin Which one of the following sets of conditions will allow the crew to transition from 1 -E-1 to 1-ES-1.1 "SI Termination"?
A. One intact steam generator increases to greater than 11 %, and Pressurizer level increases to 45%.
BY Pressurizer level increases to 45%, and AFW flow is raised to 345 gp C. One intact steam generator increases to 23%, and AFW flow is raised to 350 gp D. RCS Subcooling is raised to 100 OF, and Pressurizer level increases to 21%.
Modified from North Anna Bank question # 5019 Associated Objective 1368 (Adverse Numbers)
A. Incorrect, Steam generator level is required to be > 22%, or AFW flow > 340 gp B. Correct, Pressurizer level must be 40% or greater and AFW Flow > 340 gp C. Incorrect, SG level satisfies one condition, but pressurizer level is still not 40% or greate D. Incorrect, Pressurizer level must be 40% or greate MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBBABDAACB Scramble Range: A - D RO Tier:
TIG2 SRO Tier:
Key Word:
SI TERMINATION Cog. Level: C/A 4.0/ Source:
M Exam:
NA02301 Test:
R Misc:
RA/GWL/SC Tuesday, November 05, 2002 03:19:34 PM 137
111. WE02EA2.2 00t//TIGI/TS/C/A 3.5/4.0/NEW/NA02301/S/RA/LSM Unit one is in Post LOCA cooldown. The current temperature is 345 ' A mechanical failure of one train of SI has just occurred. The other train is availabl Which one of the following describe the TS LCO that apply to this condition:
A. LCO 3. B. LCO 3. C. LCO 3. Df No LCO's appl No LCOs apply only one train is required in mode 4 North Anna Units 1 and 2 B 3.5.3-2 Rev 0 (Draft 1), 06/05/00 ECCS-Shutdown B 3. BASES LCO During an event requiring ECCS actuation, a flow path is required to provide an abundant supply of water from the RWST to the RCS via the ECCS pumps and their respective supply headers to each of the three cold leg injection nozzles. In the long term, this flow path may be switched to take its supply from the containment sump and to deliver its flow to the RCS hot or cold leg APPLICABILITY In MODES 1, 2, and 3, the OPERABILITY requirements for ECCS are covered by LCO 3. In MODE 4 with RCS temperature below 350....F, one OPERABLE ECCS train is acceptable without single failure consideration, on the basis of the stable reactivity of the reactor and the limited core cooling requirement In MODES 5 and 6, unit conditions are such that the probability of an event requiring ECCS injection is extremely low. Core cooling requirements in MODE 5 are addressed by LCO 3.4.7, "RCS Loops-MODE 5, Loops Filled," and LCO 3.4.8, "RCS Loops-MODE 5, Loops Not Filled." MODE 6 core cooling requirements are addressed by LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation-High Water Level," and LCO 3.9.6, "Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level."
MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DBCBCCDAAB Scramble Range: A - D Tuesday, November 05, 2002 03:19:34 PM 138
RO Tier:
SRO Tier:
TIGI Key Word:
TS Cog. Level:
C/A 3.5/ Source:
NEW Exam:
NA02301 Test:
S Misc:
RA/LSM Tuesday, November 05, 2002 03:19:34 PM 139
112. WE03EA2.1 O01//T1G2/E-I/M 3.4/4.2/NEW/NA02301/S/RA/LSM Caution before step five reminds the operator that the PRZR heaters may not be covered at this point and that the heaters should not be energized until the heaters are covered.
NEW MCS Time:
I RO Tier:
Key Word:
E-I Source:
NEW Test:
S Points:
1.00 Version:
0 1 2 3 4 5 6 Answer: CBBBBDD SRO Tier:
Cog. Level:
Exam:
Misc:
789 CAC Scramble Range: A - D TIG2 M 3.4/ NA02301 RA/LSM Tuesday, November 05, 2002 03:19:34 PM Unit I has just transitioned from 1-E-1. Loss of Reactor or Secondary Coolant. The crew has entered 1-ES-1.2, Post LOCA Cooldown and depressurizatio At step 5 in the procedure you are directed to place the PRZR heaters in Pull to Lock. Which one of the following is the reason for this?
A. To Minimize heat load during the cooldow B. To prevent potential overload on any running ED CU To prevent damaging the heater D. To prevent pressure transients.
140
113. WE03EK3.1 001/TI G2/TIG2/ECA-2. 1/C/A 3.6/3.9/BANKiNA0230I/C/RA/LSM/SC Given the following conditions:
-
Unit I was operating at 100% powe An earthquake resulted in a rupture of the 40" main steam manifol The operating crew was unable to close the MSTVs or the MSNRVs and has transitioned to 1-ECA-2.1, "UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS".
-
A report comes in from the MSVH that "C" MSNVR has been close The RO observes "C" SG pressure increasing slowl Based on the above information, the operating crew should:
Af transition to 1-E-2, "FAULTED STEAM GENERATOR ISOLATION".
B. transition to 1-E-3, "STEAM GENERATOR TUBE RUPTUR C. remain in 1-ECA-2.1 until RHR is in servic D. remain in 1-ECA-2.1 until SI is terminated.
1996/01/29 MCS Time:
I RO Tier:
Key Word:
Source:
Test:
TiG2 ECA-BANK C
Points:
1.00 Version:
0 1 23456789 Answer: ACAAAADDBC Scramble Range: A - D SRO Tier:
TIG2 Cog. Level: C/A 3.6/ Exam:
NA02301 Misc:
RA/LSM/SC Tuesday, November 05, 2002 03:19:34 PM 141
114. WE04EA2.1 001//TIGI/STEAM BREAK/C/A 3.4/4.3/BANK/NA02301/S/RA/LSM Given the following conditions:
-
Unit 1 was operating at 100 percent powe You were in the MCR restroom when an event occurre seconds after hearing the annunciators, you are in the OATC area and observe the following annunciators lit on the "first-out panels": (NOTE: These are the ONLY annunciators lit on their respective panels.)
-
D-13, "PZR LO PRESS SI-RX TRIP" is yello D-Cl, "NIS PWR RGE HI -HI SP RX TRIP" is re D-E4, "NIS PWR RGE HI RATE RX TRIP" is whit D-F2, "HI STM LINE dP-SG 1 B LO SI-RX TRIP" is yello D-G1, "STM GEN 1A LO-LO LEVEL RX TRIP" is whit D-G2, "STM GEN 1 B LO-LO LEVEL RX TRIP" is whit D-G3, "STM GEN 1 C LO-LO LEVEL RX TRIP" is whit D-H2, "STM GEN 1 B LO LEV/STM FWF MISMTCH" is whit E-D1, "REACTOR TRIPPED TURB TRIP" is re E-D4, "AMSAC INITIATED" is whit E-C3, "TURB STOP VV LO TURB TRIP" is whit E-D3, "INTER-RH STOP VV LO TURB TRIP" is whit E-F2, "FEED WTR PP BKRS OPEN TURB TRIP" is whit Based on the above information, which one of the following has occured?
A. large steam break inside containmen B0 steam break outside containmen C. large break LOCA inside containmen D. LOCA outside containmen BANK 1996/01/29 VISION OBJ. 12025, SIMULATOR SETUP Reactor trip status panel MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBADDCCDCC Scramble Range: A - D RO Tier:
SRO Tier:
TIGI Key Word:
STEAM BREAK Cog. Level: C/A 3.4/ Source:
BANK Exam:
NA02301 Test:
S Misc:
RA/LSM Tuesday, November 05, 2002 03:19:34 PM 142
115. WE04EK2.1002/T11G2//E-3/C/A 3.6/4.0/NEW/NA02301/R/RA/LSM According to 1 -E-3, which one of the following is the reason that feed flow to any Ruptured SG that is faulted should remain isolated unless needed for cooldown?
A" To prevent excessive RCS cooldow B. To Prevent spread of contaminatio C. To prevent Dilution of the RC D. To prevent loss of feed flow inventory.
Note prior to step 4 1 -E-3, rev 19 MCS Time:
Points:
1.00 Version:
Answer:
RO Tier:
Key Word:
Source:
Test:
A TIG2 E-3 NEW R
123456789 ADADBADBB SRO Tier:
Cog. Level: C/A Exam:
NA(
Misc:
RAJ Scramble Range: A - D
.3.6/ LSM 143 Tuesday, November 05, 2002 03:19:35 PM
116 WE05EK 12 001/T1 G2/TiG2/3.9/4.5/M 3.9/4.5/NEW/NA02301/C/RA/LSM/SC NEW Reference 1-FR-H.1, Revision 13, page 2 of 15 Note prior to step one indicated that procedure cannot be that 340 because of operator action a. correct answer b. RCS only applies if greater than any NON-Faulted SG c. RCS only applies if greater than any NON-Faulted SG d. RCS only applies if greater than any NON-Faulted SG does not apply here MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: AADCCDACAC entered if AFW flow is less Pressure Pressure Pressure, RCP pump statu Scramble Range: A - D S
RO Tier:
Key Word:
Source:
Test:
TIG2 3.9/ NEW C
Tuesday, November 05, 2002 03:19:35 PM SRO Tier:
TIG2 Cog. Level: M 3.9/ Exam:
NA02301 Misc:
RA/LSM/SC 144 Operators are responding to three faulted steam generator The heat sink status tree has a red terminus. Which one of the following is the reason that the operators should not perform any steps in 1-FR-H.I?
Operator actions taken in ECA 2-1 have:
A. reduced total AFW flo B. reduced RCS pressur C. increased total AFW flo D. increased RCS pressur. WE06EK2.2 001/TIGI/TIGI/CORE COOLING/C/A 3.8/4.1I/BANK/NAO2301/C/RA/LSM While responding to Inadequate Core Cooling in accordance with 1-FR-C.1, which one of the following describes how core recovery by SI accumulator injection is initiated?
A. Dumping steam to the condenser and initiating forced two phase flow using the RCP B! Dumping steam to the condenser or using SG PORV C. Restarting the RCPs to sweep steam voids and nitrogen gas from the cor D. Increasing nitrogen pressure on the top of the SI accumulators to increase the injection rate into the RCS.
NCRODP-95.6, Revision 2, Page 3.9, Step 11, Objective bank MCS Time:
RO Tier:
Key Word:
Source:
Test:
TIGI CORE C BANK C
Points:
1.00 Version:
0 1 2345 6789 Answer: BDACCAADDA Sc SROTier:
TIGI OOLING Cog. Level: C/A 3.8/ Exam:
NA02301 Misc:
RA/LSM
- ramble Range: A - D Tuesday, November 05, 2002 03:19:35 PM 145
118. WE08EKI.2 001/T1Gl/TIGI/PTS/M 3.4/4.0/BANKINAO2301/C/RA/GWL/SC
- Unit 2 has experienced a Main Steam Line Break
- All systems operated as designe The crew responded in accordance with the emergency operating procedures, and is currently in 2-FR-P.1 "Response to Imminent Pressurized Thermal Shock".
- The crew has been directed by the procedure to perform a "SOAK".
Which one of the following evolutions can be performed during the soak?
A. Warm up the RHR System and place it in servic B! Un-isolate charging pump recirculatio C. Raise steam generator water levels to 50% and secure AFW pump D. Energize the pressurizer heater North Anna Exam bank questions #3109 and 358 A. Incorrect, warming up the RHR system could cooldown the RCS even more, and placing it in service would cooldown the RC B. Correct, unisolating the charging pump recirculation would tend to lower RCS pressure, and would not raise pressure or cause a cooldow C. Incorrect, raising steam generator water levels would cause an RCS cooldow D. Incorrect, Energizing the pressurizer heaters would raise RCS pressure resulting in increased thermal stresse MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BCCADADAAA Scramble Range: A - D RO Tier:
TiGI SROTier:
TIGI Key Word:
PTS Cog. Level: M 3.4/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/GWL/SC Tuesday, November 05,2002 03:19:35 PM 146
119. WE09EA1.2 00f I/Tl G/TiGI/NATURAL CIRC/M 3.6/3.9/BANK/NA02301/C/RA/GWL/SC
- A natural circulation cooldown is in progress on Unit Steam Generator feed flow rate is increase Assume all parameters are within limit Which one of the following describes how this will affect the natural circulation flow rate?
A. Natural circulation flow rate will decreas B. Natural circulation flow rate will not be affecte C. Natural circulation flow rate will be stopped, and will not recommenc D. Natural circulation flow rate will increas From Farley exam ban North Anna associated objective 12484 and 1343 A. Incorrect, slowly increasing steam flow from the steam generators will increase natural circulation flo B. Incorrect, Natural circulation flow will be affecte C. Incorrect, Natural circulation flow may be stopped momentarily if the steam demand was increased to much, but would re-establish it self, at a higher flow rat D. Correct, increasing the steaming rate on the S/G will increse the natural circulation flow rat MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: DACBADAABB Scramble Range: A - D RO Tier:
TIGI SRO Tier:
TIG1 Key Word:
NATURAL CIRC Cog. Level:
M 3.6/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/GWL/SC...
-.-....
,
n....
...... nA 147 T uesday, November U0, ZUUL 03: 19:35 avI
120. WE 11EK2.2 001/T 1G2/T 1G2/HEAT REMOVAL/C/A 3.9/4.3/BANK/NA02301/C/RA/LSM/SC Given the following conditions:
-
A LOCA has occurred
-
A CDA signal was received
-
The current containment pressure is 25 psia and decreasing
-
The RWST level is 24 percent
-
CETC's are 430 degrees F and decreasing Which ONE of the following describes the action to be taken by the operator?
A. Momentarily place the spray actuation Reset Train A and B Switches in RESET to reset the CDA signa B! Verify changeover from injection mode to recirculation mode or shift manually if not yet accomplished.
C. Reset the CDA signal and stop the Quench Spray pumps to let the pressure decay naturally and conserve resource D. Refill the RWST from the CVCS system and continue to spray down containment until pressure is 12 psi /02/24 L.P. NCRODP-91-1-LP-3, Rev. 4, page 13, Objective B MCS Time:
RO Tier:
TIG2 Key Word:
HEAT RI Source:
BANK Test:
C Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BDABDCBDDA Scn SRO Tier:
T1G2 EMOVAL Cog. Level: C/A 3.9/ Exam:
NA02301 Misc:
RA/LSM/SC 148 Tuesday, November 05, 2002 03:19:35 PM rmble Range: A - D
121. WE12EK3.3 001/TIGI//FEEDWATER/M 3.5/3.7/M/NA02301/R/RA/GWL/SC
- Assume the following plant conditions:
- All steam generators are depressurizing uncontrollabl Narrow range level in each steam generator is off scale lo Which one of the following correctly describes how feedwater flow to the steam generators should be controlled, and why this is necessary?
A. Maintain a minimum of 340 gpm total to all steam generators, this is the minimum flow required to ensure decay heat removal is sufficient to prevent fuel damag B! Maintain a minimum of 100 gpm to each steam generator, this will minimize thermal shock effects if feedwater flow is increase C. Maintain a minimum of 340 gpm to all steam generators not isolated, this will prevent overheating of the AFW pumps due to running at low flow conditions for long periods of tim D. Maintain a minimum of 100 gpm total to all steam generators, this is the minimum flow required to prevent the Reactor Coolant System from re-pressurizin Modified from North Anna Bank questions, # 3055,2885, and 376 Associated objectives 13842, and 1384 A. Incorrect, While in ECA-2.1 AFW flow is to be limited to 100 gpm for each generato gpm is the correct flow rate for other ERGs, and the reason is correct for those procedure B. Correct, 100 gpm should be delivered to each steam generator, and this is the correct reason listed in the WOG background document C. Incorrect, This is the incorrect amount, while this would prevent overheating of the AFW pumps, this is not the reason that flow is limited in ECA D. Incorrect, 100 gpm total to all generators is not correct(100 to each S/G is required), the RCS will re pressurize when cooldown (shrinkage of the RCS can be made up by the Safey Injection system MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BCCADADADC Scramble Range: A - D RO Tier:
TIGI SRO Tier:
Key Word:
FEEDWATER Cog. Level:
M 3.5/ Source:
M Exam:
NA02301 Test:
R Misc:
RA/GWL/SC
...
149 Tuesday, November 05, 20UZ U0:19:35 w;
122. WE12G2.4.22 001//TIGI/SG LEVEL/C/A 3.0/4.3/M/NA02301/S/RA/LSM E-1, Loss Of Reactor Or Secondary Coolant, Step 3, CHECK INTACT SG LEVELS, reads:
a) Narrow range level - GREATER THAN 11% [23%]
b) Control feed flow to maintain narrow range level between 23% and 50%
Which one of the following is the REASON or BASIS for these actions?
To maintain RCS Heat Sink and...
A. minimize pressurized thermal shoc B/ establish symmetric cooling of the RC C. maintain the SGs in a wet conditio D. to establish conditions to prevent core reflux boiling.
1-E-1 Rev 15, Owners Group Guideline!
NCRODP-95.4, Revision 4, Pages 5.11 MODIFIED BANK 1992 MCS Time:
I Points:
1.00 Version:
Answer:
RO Tier:
Key Word:
SG LEVEL Source:
M Test:
S
& 5.12, Objective BBBDCADDDB Scramble Range: A - D SRO Tier:
TIGI Cog. Level:
C/A 3.0/ Exam:
NA02301 Misc:
RA/LSM Tuesday, November 05, 2002 03:19:35 PM 150
123. WE14EAI.3 001/TIG1/TIGI/CONTAINMENT/C/A 3.3/3.8/M/NA02301/C/RA/GWL/SC
- A Reactor Trip and Safety Injection has occurred on Unit I
- CDA has not actuate All Steam Generator Pressures are stable at approximately 800 psi Containment pressure as indicated on recorder 1-LM-PR-I1OB is 29 psia and slowly decreasin E-0, "Reactor Trip or Safety Injection", is in effect the crew is at the "CHECK IF CDA IS REQUIRED" ste Which one of the following correctly describes the action that the crew should take?
A. Start the quench spray pumps and open pump discharge and chemical addition tank valve BY Manually Acuate CDA, and ensure CDA actions are complet C. Continue in 1-E-0, (no action is required)
D. Go to 1-FR-Z.1, "Response to High Containment Pressure".
Modified From North Anna Bank Question 3312,3320 and 3861. Associated objective s12460, and 1246 A. Incorrect, this would be the correct action that would be required if containment pressure exceeded 20 psia and a CDA was not require B. Correct, if containment pressure exceeded 28 psia a CDA should have occured and the crew should iniate a CD C. Incorrect, Actions must be taken to address this critical safety concer D. Incorrect, FR-Z.1 has steps that will address these conditions, but should not be used until E-0 is exite MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BBACCBDAAA Scramble Range: A - D RO Tier:
TIGI SRO Tier:
TIGI Key Word:
CONTAINMENT Cog. Level: C/A 3.3/ Source:
M Exam:
NA02301 Test:
C Misc:
RA/GWL/SC Tuesday, November 05, 2002 03:19:36 PM 151
124. WE15EKI.1 00I/TIG3/TIG3/FLOODING/C/A 2.8/3.0/NEW/NAO2301/C/RAILSMISC Unit 1 control room receives reports of flooding in the auxiliary building. The crew enters O-AP-39.2. Which one of the following systems could be damaged by this flooding?
Af Chargin B. Pressurizer Spra C. Containment Ventilatio D. Pressurizer level Contro New Per O-AP-39.2 Revision 6, Page 2. Auxiliary Building Flooding could cause a loss of chargin MCS Time:
Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: AAAADACABC Scramble Range: A - D RO Tier:
TIG3 SRO Tier:
TIG3 Key Word:
FLOODING Cog. Level:
C/A 2.8/ Source:
NEW Exam:
NA02301 Test:
C Misc:
RA/LSM/SC S...
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152 Tuesday, November 05, ZUUL U0:1 I;
-I
1 "*xvrlicniti'l -,nhIlfrlgrl9/TflWAgTp. GASg/AM O./ 3I3BANK/NA02301/C/RAILSM/SC Which one of the following statements is correct if a high-high alarm is initiated by radiation monitor 1 -RM-VG-1 01, "Process Vent Particulate Rad Monitor" during a waste gas decay tank release?
A. 1-GW-FCV-101 (decay tanks effluent flow control) will close automatically and must be reset locally before it can be reopene BY 1-GW-TV-102A (containment vacuum pump discharge) will close automatically, and will reopen when the alarm condition clears and the OPEN pushbutton is depresse C. 1-GW-TV-102A (containment vacuum pump discharge) will close automatically and must be reset locally before it can be reopene D. 1-GW-FCV-101 (decay tanks effluent flow control) will close automatically and will reopen automatically when the alarm condition clears and the CLOSE pushbutton is depresse Bank 16 ID: 3812 MCS Time:
I Points:
1.00 Version:
0 1 2 3 4 5 6 7 8 9 Answer: BAADADACAA Scramble Range: A - D RO Tier:
T1G2 SRO Tier:
TIG2 Key Word:
WASTE GAS Cog. Level: M 3.0/ Source:
BANK Exam:
NA02301 Test:
C Misc:
RA/LSM/SC
.
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..n..e f *,153 I uesaay, November 05, 20uuz 0o: 13 6O Fivi