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| number = ML17075A382
| number = ML17075A382
| issue date = 01/16/2017
| issue date = 01/16/2017
| title = Limerick Generating Station - Final Written Examination with Answer Key (401-5 Format) (Folder 3)
| title = Final Written Examination with Answer Key (401-5 Format) (Folder 3)
| author name =  
| author name =  
| author affiliation = Exelon Generation Co, LLC
| author affiliation = Exelon Generation Co, LLC
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:KEY LIMERICK 2017 SRO NRC \VRITTEN EXAM 1 A 27 B 52 A 78 c 2 B 28 c 53 B 79 A 3 D 29 D 54 c 80 c 4 c 30 A 55 A 81 B 5 -e-Ace-er+ Sol"" C 31 D 56 A 82 D 6 Ao 32 c 57 B 83 B c 7 D 33 B 58 D 84 A 8 A 34 B 59 c 85 A 9 D 35 B 60 A 86 c 10 D 36 B 61 c 87 A 11 A 37 A 62 c 88 B 12 D 38 D 63 B 89 c 13 B 39 c 64 c 90 A 14 D 40 D 65 A 91 D defe-U 92 15 B 41 A 66 B D M2":¢7 16 D 42 c 67 A 93 c 17 c 43 A 68 D 94 D 18 B 44 B 69 B 95 B 19 A 45 c 70 c 96 D 20 D 46 B 71 B 97 D 21 A 47 D 72 A 98 B 22 D 48 c 73 c 99 c 23 A 49 c 74 c 100 B 24 D 50 B 75 c 25 B 51 A 76 A 26 D 77 D Page 1of1 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 1 ID: 14553n Points: 1.00 A startup is in progress on unit 1 Which of the following describes when the IRM's will swap to a high frequency amplifier and the potential for a half SCRAM and I or a rod block? Ranging IBM from range Potential for a half SCRAM and I or rod block A. 6to 7 Half SCRAM and rod block B. 6to 7 Half SCRAM only c. 2 to 3 Half SCRAM and rod block D. 2 to 3 Half SCRAM only Answer: A Answer Explanation A Correct per GP-2 App 1; WHEN changing range from 6 to 7 on the IRMs, THEN the range change swaps from the low frequency amplifier to the high frequency amplifier AND could cause a half-scram.
{{#Wiki_filter:KEY LIMERICK 2017 SRO NRC \VRITTEN EXAM 1 A                   27   B               52   A           78 c 2   B                   28   c                 53   B           79 A 3 D                   29   D                 54   c           80 c 4 c                   30   A                 55   A           81 B 5 -e- Ace-er+ Sol"" C   31   D                 56   A           82 D Ao 2ft~1 6 c                    32   c                 57   B           83 B 7 D                   33   B                 58   D           84 A 8 A                   34   B                 59   c           85 A 9 D                   35   B                 60   A           86 c 10 D                   36   B                 61   c           87 A 11 A                   37   A                 62   c           88 B 12 D                   38   D                 63   B           89 c 13   B                   39   c                 64   c           90 A 14 D                   40   D                 65   A           91 D 15                                              66 defe-U B                   41   A                       B M2":¢7 92  D 16 D                   42   c                 67   A           93 c 17 c                   43   A                 68   D           94 D 18   B                   44   B               69   B           95 B 19 A                   45   c                 70   c           96 D 20 D                   46   B                 71   B           97 D 21 A                   47   D                 72   A           98 B 22 D                   48   c                 73   c           99 c 23 A                   49   c                 74   c           100 B 24 D                   50   B                 75   c 25 B                   51   A                 76   A 26 D                                           77   D Page 1of1
Although GP-2 does not reference a rod block the 1/2 scram is due to potential spiking of the IRM when ranging between 6 and 7. Any spiking that will cause a 1/2 scram will also cause a rod block B Incorrect a rod block will also be generated.
 
Plausible to examinee who does not recall that when ranging from 6 to 7 there is a potential for spiking of the IRM which could result in a rod block and half SCRAM C Incorrect; plausible to the examinee who recalls an IRM function (SAM down scale rod block is bypassed) when ranging from 2 to 3 D Incorrect; plausible to the examinee who confuses the SAM down scale bypass when ranged from 2 to 3 with when the amplifier swaps to high frequency and does not recall that a rod block will also be generated.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 1                                                 ID: 14553n                                   Points: 1.00 A startup is in progress on unit 1 Which of the following describes when the IRM's will swap to a high frequency amplifier and the potential for a half SCRAM and I or a rod block?
from spiking of the IRM. LMK 2017 IL T NRG JANUARY Page: 1 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO . Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
Ranging IBM from range                           Potential for a half SCRAM and I or rod block A.       6to 7                                         Half SCRAM and rod block B.       6to 7                                         Half SCRAM only
No Points: 1.00 Time to Complete:
: c.       2 to 3                                       Half SCRAM and rod block D.       2 to 3                                       Half SCRAM only Answer:           A Answer Explanation A     Correct per GP-2 App 1; WHEN changing range from 6 to 7 on the IRMs, THEN the range change swaps from the low frequency amplifier to the high frequency amplifier AND could cause a half-scram.
2 Difficulty:
Although GP-2 does not reference a rod block the 1/2 scram is due to potential spiking of the IRM when ranging between 6 and 7. Any spiking that will cause a 1/2 scram will also cause a rod block B     Incorrect a rod block will also be generated. Plausible to examinee who does not recall that when ranging from 6 to 7 there is a potential for spiking of the IRM which could result in a rod block and half SCRAM C     Incorrect; plausible to the examinee who recalls an IRM function (SAM down scale rod block is bypassed) when ranging from 2 to 3 D     Incorrect; plausible to the examinee who confuses the SAM down scale bypass when ranged from 2 to 3 with when the amplifier swaps to high frequency and does not recall that a rod block will also be generated. from spiking of the IRM.
2.50 System ID: 1455392 User-Defined ID: Q# 1 NEW Lesson Plan Objective:
LMK 2017 ILT NRG JANUARY                         Page: 1 of 374                                 17 January 2017
LGSOPS007 4.22A Topic: IRM ranqe RO: 2.6 SRO: 2.7 KA#: 215003 K5.01 LMK 2017 IL T NRC JANUARY Page: 2 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 IL T NRG JANUARY Page: 3 of 374 2 215003 K5.01 2.6/2.7 215003 Intermediate Range Monitor (IRM) System Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM : Detector o eration Hi h 41.5 GP-2 LGSOPS0074 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 2 10:1454410 Points: 1.00 Unit 1 plant conditions:  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO .
-107 REACTOR F-5, DIV 1 STEAM LEAK DET SYS HI TEMPfrROUBLE alarm is lit -107 REACTOR H-5, DIV 3 STEAM LEAK DET SYS HI TEMPfrROUBLE alarm is NOT lit -RCIC STEAM LINE HI FLOW alarm is NOT lit An Equipment Operator in the Aux. Equipment room reports the following
Question 1 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               2 Difficulty:                     2.50 System ID:                       1455392 User-Defined ID:                 Q# 1 NEW Lesson Plan Objective:           LGSOPS007 4.22A Topic:                           IRM ranqe RO:                             2.6 SRO:                             2.7 KA#:                             215003 K5.01 LMK 2017 ILT NRC JANUARY                     Page: 2 of 374           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 215003 K5.01 2.6/2.7 215003 Intermediate Range Monitor (IRM) System Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM : Detector o eration Hi h 41.5 GP-2 LGSOPS0074 LMK 2017 ILT NRG JANUARY              Page: 3 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 2                                                 10:1454410                                     Points: 1.00 Unit 1 plant conditions:
          - 107 REACTOR F-5, DIV 1 STEAM LEAK DET SYS HI TEMPfrROUBLE alarm is lit
          - 107 REACTOR H-5, DIV 3 STEAM LEAK DET SYS HI TEMPfrROUBLE alarm is NOT lit
            - RCIC STEAM LINE HI FLOW alarm is NOT lit An Equipment Operator in the Aux. Equipment room reports the following
* NUMAC TIS-25-101A RCIC equipment room is reading 195 degrees F
* NUMAC TIS-25-101A RCIC equipment room is reading 195 degrees F
* NU MAC TIS-25-101 C RCIC equipment room is reading 11 O degrees F Assuming no operator action which of the following identifies the status of the RCIC Isolation Valves one minute later? A. B. c. D. HV49-1 F007 BCIC Steam Line Inboard Isolation Open Open Closed Closed Answer: B !Answer Explanation HV49-1 FOOS BCIC Steam Line Outboard Isolation Open Closed Open Closed D incorrect If power is available either division activation will close all associated RCIC steam line The two divisions are for redundancy, with no high steam line flow (>300%) there is not a isolation is. Candidate must determine that div 1 is above both the alarm (>123 degrees) setpoint and above ltrip set point (> 180 degrees) plausible to the examinee who incorrectly believes that both DIV 1 and 3 temperatures are required for any valve to close. B Correct the DIV 1 hi temperature will close the outboard valve. C incorrect plausible to the examinee who incorrectly believes the DIV 1 isolation closes the inboard valve LMK 2017 IL T NRG JANUARY Page: 4 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 2 Info IQuestion Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
* NU MAC TIS-25-101 C RCIC equipment room is reading 11 O degrees F Assuming no operator action which of the following identifies the status of the RCIC Isolation Valves one minute later?
No Points: 1.00 Time to Complete:
HV49-1 F007 BCIC Steam Line Inboard           HV49-1 FOOS BCIC Steam Line Outboard Isolation                                       Isolation A.                            Open                                            Open B.                            Open                                           Closed
3 Difficulty:
: c.                          Closed                                          Open D.                          Closed                                         Closed Answer:            B
2.00 System ID: 1454410 User-Defined ID: Q# 2 MODIFIED Lesson Plan Obiective:
          !Answer Explanation D incorrect If power is available either division activation will close all associated RCIC steam line
LOT0380.06 RCIC Topic: Describe the status of RCIC Isolation valves with "DIV 1 STEAM LEAK DETECTION" RO: 3.1 SRO: 3.2 KA#: 217000 K1 .07 LMK 2017 ILT NRC JANUARY Page: 5 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
          ~alves. The two divisions are for redundancy, with no high steam line flow (>300%) there is not a
LMK 2017 ILT NRC JANUARY Page: 6 of 374 217000 K1.07 3.1/3.2 Reactor Core Isolation Cooling System (RCIC) Knowledge of the physical connections and/or cause effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the followin : Leak detection 2 41.5,41.7 bank 560597 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 3 10:1454509 Points: 1.00 Unit 1 plant conditions are as follows:
          ~ull isolation is.
* OPCON 4 * '1 B' RHR is in Shutdown Cooling The following sequence of events occurs
Candidate must determine that div 1 is above both the alarm (>123 degrees) setpoint and above ltrip set point (> 180 degrees)
* Annunciator 122-A 1 012 BUS OIFF/ OVERCURRENT LOCKOUT alarms
          ~incorrect    plausible to the examinee who incorrectly believes that both DIV 1 and 3 temperatures are required for any valve to close.
* After the annunciator is received reactor level lowers to -25 inches before being restored (no other operator actions have been taken) Which of the following describes the final position of the listed RHR valves due to the above conditions?
B Correct the DIV 1 hi temperature will close the outboard valve.
A. B. c. 0. HV51-1F009, RHR S/O Cooling Inboard PCIV Rj-IR injection Outboard PCIV J.. -fttr,P 1/'2-7/ 11 HV51-1 F009 HV51-1F0158 Open Open Closed Closed Open Closed Closed Open Answer: 0 Answer Explanation  
C incorrect plausible to the examinee who incorrectly believes the DIV 1 isolation closes the inboard valve LMK 2017 ILT NRG JANUARY                           Page: 4 of 374                                 17 January 2017
:J. v,(Jl 'i f'2j7 HV51-1 F009, 1 RHR S/O Cooling Inboard PCIV power supply is 011 HV51-1F0158, 1 B RHR S/O Cooling injection PCIV power supply is 012 A Incorrect plausible to the examinee who recalls that both the HV51-1 F015A&B are powered from the same source but believe it is 011 not 012 B Incorrect plausible to the examinee who does not recognize that a 012 bus differential over current will deenergize the bus, preventing the motor operated valves from closing C Incorrect plausible to the examinee who reverse inboard and outboard power supplies 0 Correct with 012 deenergized only the HV51-1 F009, RHR S/O Cooling Inboard PCIV will close LMK 2017 IL T NRC JANUARY Page: 7 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
 
No Points: 1.00 Time to Complete:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 2 Info IQuestion Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1454410 User-Defined ID:                 Q# 2 MODIFIED Lesson Plan Obiective:           LOT0380.06 RCIC Describe the status of RCIC Isolation valves with "DIV 1 STEAM Topic:
6 Difficulty:
LEAK DETECTION" RO:                             3.1 SRO:                             3.2 KA#:                             217000 K1 .07 LMK 2017 ILT NRC JANUARY                       Page: 5 of 374                                 17 January 2017
2.00 System ID: 1454509 User-Defined ID: Q#3 NEW Lesson Plan Objective:
 
LLOR0701 E.3 Topic: Loss of power to SDC valves RO: 2.5 SRO: 2.7 KA#: 205000 K2.02 LMK 2017 IL T NRG JANUARY Page: B of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRG JANUARY Page: 9 of 374 2 205000 K2.02 2.5/2.7 Shutdown Cooling System (RHR Shutdown Cooling Mode Knowledge of electrical power supplies to the following:
217000 K1.07 3.1/3.2 Reactor Core Isolation Cooling System (RCIC)
Motor operated valves low 4 41.7 S51.7.B ON-121 821-1090-E-01 2 Sh. 12, C61-1050-E-01 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 4 ID: 1454528 ' Points: 1.00 Unit 2 plant conditions:  
Knowledge of the physical connections and/or cause effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the followin : Leak detection 2
-HPCI is running in full flow test (CST to CST) at 5600 gpm A loss of Division 2 DC power occurs. Which of the following identifies the impact, if any, on continued HPCI operation?
41.5,41.7 bank 560597 LMK 2017 ILT NRC JANUARY              Page: 6 of 374                            17 January 2017
A. Continues to run at 5600 gpm B. Div 2 isolation occurs C. Turbine Governor Valve closes D. HPCI over speed trip occurs Answer: C Answer Explanation of DIV 2 power to HPCI will cause HPCI speed to run back to the low setting due to loss of control power to the flow controller which feeds the Turbine Governor.
 
DIV 2 provides power for control power, isolation circuits, all DIV 2 valves, initiation logic, aux oil pump control and turbine logic. HPCI is out of service and not available on loss of DIV 2. Plausible to candidate who does not remember loss of div 2 will close governor but recalls that isolation is energized to operate. B Plausible to candidate who believes that HPCI isolation logic is deenergize to operate C Correct A loss of DIV 2 power to HPCI will cause HPCI speed to run back to the low setting due loss of control power to the flow controller which feeds the Turbine Governor.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 3                                                     10:1454509                             Points: 1.00 Unit 1 plant conditions are as follows:
When turbine speed drops below approximately 1000 RPM the shaft driven oil pump will not have sufficient pressure to maintain the governor valve open. a loss of div II de will cause the aux. oil pump to lose power, so it will not be available to start on low pressure.
* OPCON 4
without the aux oil pump the governor will continue to close to the full closed position.
  *     '1 B' RHR is in Shutdown Cooling The following sequence of events occurs
D Plausible to candidate who believes the qovernor fails full open on a loss of power LMK 2017 ILT NRG JANUARY Page: 10 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
* Annunciator 122-A1 012 BUS OIFF/ OVERCURRENT LOCKOUT alarms
No Points: 1.00 Time to Complete:
* After the annunciator is received reactor level lowers to -25 inches before being restored (no other operator actions have been taken)
3 Difficulty:
Which of the following describes the final position of the listed RHR valves due to the above conditions?
2.00 System ID: 1454528 User-Defined ID: 0#4 BANK Lesson Plan Objective:
[:  ~~H~O HV51-1F009, RHR S/O Cooling Inboard PCIV HV51-1F015B~ Rj-IR ~/~ cooling injection Outboard PCIV 1
HPCI 14.A Topic: Predict Impact of Loss of Div 2 DC on HPCI Operation RO: 2.5 SRO: 2.7 KA#: 206000 K2.04 LMK 2017 IL T NRG JANUARY Page: 11 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
J.. -fttr,P 1/'2-7/ 11                                         :J. v,(Jl 'i
LMK 2017 IL T NRG JANUARY Page: 12 of 374 2 1 206000 K2.04 2.5/2.7 High Pressure Coolant Injection System Knowledge of electrical power supplies to the following:
                                                                                                ~ f'2j7 HV51-1 F009              HV51-1F0158 A.              Open                           Open B.              Closed                         Closed
Turbine control circuits:
: c.              Open                           Closed
BWR-2,3,4 lower 2 41.7 E41-1040-E-OO 4, sht. 001 E41-1040-E-OO 5, sht. 001 E41-1040-E-OO 6, sht. 001 ARC-MCR-117, A1 bank 560442 26 30 36 2 17 January 2017 5 Given: EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO ID: 1454611
: 0.              Closed                         Open Answer:         0 Answer Explanation HV51-1 F009, 1RHR S/O Cooling Inboard PCIV power supply is 011 HV51-1F0158, 1B RHR S/O Cooling injection PCIV power supply is 012 A     Incorrect plausible to the examinee who recalls that both the HV51-1 F015A&B are powered from the same source but believe it is 011 not 012 B     Incorrect plausible to the examinee who does not recognize that a 012 bus differential over current will deenergize the bus, preventing the motor operated valves from closing C     Incorrect plausible to the examinee who reverse inboard and outboard power supplies 0     Correct with 012 deenergized only the HV51-1 F009, RHR S/O Cooling Inboard PCIV will close LMK 2017 ILT NRC JANUARY                               Page: 7 of 374                         17 January 2017
* INSTRUMENT AIR HEADER A PRESSURE LO annunciator is in alarm *INSTRUMENT AIR HEADER B PRESSURE LO annunciator is in alarm
 
* Instrument Air header pressure is lowering Points: 1.00 The CRS has directed a power reduction per ON-119, Loss Of Instrument Air Which of the following describes the bases for the power reduction?
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 3 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?       No Points:                         1.00 Time to Complete:               6 Difficulty:                     2.00 System ID:                     1454509 User-Defined ID:               Q#3 NEW Lesson Plan Objective:         LLOR0701 E.3 Topic:                         Loss of power to SDC valves RO:                             2.5 SRO:                           2.7 KA#:                           205000 K2.02 LMK 2017 ILT NRG JANUARY                     Page: B of 374       17 January 2017
A. Reduce the probability of a turbine trip from lowering condenser vacuum. B. Reduce the transient if a SCRAM is required due to rods drifting in. C. Reduce the probability of inadequate feedwater should the condensate or feed pump min flow valves drift. D. Reduce the probability of power exceeding 100% should the feedwater heater dump valves fail open. Answer: Answer Explanation  
 
: 1. Both inst. air header low alarms coming in is an entry condition for ON-119. 2. The bases for reducing power to 44% is to reduce the probability of a loss of adequate feedwater should the Condensate or RFP Min Flow valve begin to drift open. 3. Low Instrument Air pressure could cause CAD HCU scram valves to drift open, resulting in the associated control rods to insert. This is the Bases for manually SCRAM ING the reactor if control rods start to drift in 4. Air ejector valves may fail due to loss of air causing vacuum to decrease, however ON-119 directs entry to OT-116 for loss of vacuum actions 5. Feed water dump valves may fail open on a loss of air causing a power increase, however ON-119 directs operators to OT-104 for a loss of feedwater heating Q..f'(_ B t.M.cL. C ltt correct for the above reasons and the distractors are plausible to the examinee who does not recall the basis for reducinq power to 44% LMK 2017 IL T NRC JANUARY Page: 13 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? No for practice?
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
No Points: 1.00 rnme to Complete:
2 205000 K2.02 2.5/2.7 Shutdown Cooling System (RHR Shutdown Cooling Mode Knowledge of electrical power supplies to the following: Motor operated valves low 4
3 Difficulty:
41.7 S51.7.B ON-121 821-1090-E-01 2 Sh. 12, C61-1050-E-01 LMK 2017 ILT NRG JANUARY              Page: 9 of 374                          17 January 2017
2.00 System ID: 1454611 User-Defined ID: 0#5 NEW Lesson Plan Objective:
 
LGSOPS1550.03 lfopic: actions for loss of air RO: 3.3 SRO: 3.4 KA#: 300000 K3.02 LMK 2017 IL T NRC JANUARY Page: 14 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 4                                                   ID: 1454528 '                                   Points: 1.00 Unit 2 plant conditions:
LMK 2017 IL T NRC JANUARY Page: 15 of 374 300000 K3.02 3.3/3.4 Instrument Air System (IAS) Knowledge of the effect that a loss or malfunction of the
        - HPCI is running in full flow test (CST to CST) at 5600 gpm A loss of Division 2 DC power occurs.
* INSTRUMENT AIR SYSTEM) will have on the following:
Which of the following identifies the impact, if any, on continued HPCI operation?
Systems having neumatic valves and controls 41.7 ON-119 P&ID M-0015 sht 4 28 40 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 6 ID: 1685687 Points: 1.00 Unit 1 is operating at 100% power when the following occurs: -The speed demand signal from DFWLC for the '1 A' RFP fails to 1 mA. RPS successfully actuates, but an ATWS occurs. One minute later, all of the logic to produce an ARCS Feedwater Runback is satisfied.
A.         Continues to run at 5600 gpm B.         Div 2 isolation occurs C.       Turbine Governor Valve closes D.         HPCI over speed trip occurs Answer:             C Answer Explanation
WHICH ONE of the following identifies the status of '1A' RFP two minutes after the runback logic is satisfied? (Assume Il.Q operator action.) A. Running at 2300 rpm; M/A Station in control B. Running at 2300 rpm; MSC in control C. Running at the same speed as before the runback signal; MSC in control D. Running at the same speed as before the runback signal; M/A Station in control Answer: C Answer Explanation The speed demand signal loss results in 1 A RFP swapping to MSC (an automatic swap to MSC when the DFWLC output fails to 1 mA) control and "locking up" at its present speed. Since its in "lockup" p.ri.Qr to the Runback, it will NOT respond to the Runback signal. 'C' is correct for the above reasons. 'A', 'B' are wrong. Plausible to the examines who forgets that the pre-existing lockup inhibits that RFP from responding to the runback. 'D' is wrong. Control will not swap back to or stav in M/A station control. LMK 2017 IL T NRG JANUARY Page: 16 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 6 Info K;luestion Type: Multiple Choice Status: Active !Always select on test? No !Authorized for practice?
        ~loss of DIV 2 power to HPCI will cause HPCI speed to run back to the low setting due to loss of control power to the flow controller which feeds the Turbine Governor. DIV 2 provides power for control power, isolation circuits, all DIV 2 valves, initiation logic, aux oil pump control and turbine
No Points: 1.00 tTime to Complete:
        ~rip logic. HPCI is out of service and not available on loss of DIV 2.
4 Difficulty:
        ~ Plausible to candidate who does not remember loss of div 2 will close governor but recalls that
2.50 System ID: 1685687 User-Defined ID: 0#6 Lesson Plan Obiective:
        ~he  isolation is energized to operate.
LOT-0550, OBJ4 lropic: RFP Speed Signal Loss -RFP Response to RRCS FW R/B Siona! RO: 3.7 SRO: 3.7 KA#: 259002 K3.02 LMK 2017 IL T NRG JANUARY Page: 17 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
B Plausible to candidate who believes that HPCI isolation logic is deenergize to operate C Correct A loss of DIV 2 power to HPCI will cause HPCI speed to run back to the low setting due
LMK 2017 IL T NRC JANUARY Page: 18 of 374 259002 K3.02 3.7/3.7 Reactor Water Level Control System Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following:
        ~o  loss of control power to the flow controller which feeds the Turbine Governor. When turbine speed drops below approximately 1000 RPM the shaft driven oil pump will not have sufficient pressure to maintain the governor valve open. a loss of div II de will cause the aux. oil pump to lose power, so it will not be available to start on low pressure. without the aux oil pump the governor will continue to close to the full closed position.
Reactor feedwater s stem 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 19 of 374 17 January 2017 7 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO ID: 1454748 Unit 2 plant conditions are as follows: -100% Reactor Power -Normal Electrical Lineup The following sequence of events occurs:
D Plausible to candidate who believes the qovernor fails full open on a loss of power LMK 2017 ILT NRG JANUARY                           Page: 10 of 374                                   17 January 2017
* t = 0 seconds
 
* t = 20 seconds RPV level drops below -129 inches 201 Safeguard Bus < 70% bus voltage Points: 1.00 Which of the following identifies the closed 023 Bus Source Breaker AND. the status of the "2C" AHR Pump Breaker at T =75 seconds? A. B. C. 0. CLOSEDD23BUSSOUBCE BREAKER 101-023 101-023 023 OG Output Breaker 023 OG Output Breaker Answer: 0 !Answer Explanation "2C" RHB PUMP BREAKER Open Closed Open Closed LMK 2017 IL T NRC JANUARY Page: 20 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 023 OG Output Breaker closed 023 DG started on the LOCA signal. Since it had been running for greater than 1 O seconds before the loss of power, the DG is ready to be loaded and the 0.5 second closing signal from the 023 Bus Under voltage logic will allow the 023 DG Output Breaker to close before the 1.0 second Dead Bus Transfer closing. Since the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will llow the breaker to reclose. open his answer is incorrect because the 023 DG Output Breaker will close (0.5 second time delayed closure) before the 101-023 Breaker (1.0 second time delayed closure), since the 023 DG was previously running and was in a "ready-to-load" status. Since the time frame between the initial tart signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker closes. The "2C" RHR Pump will not remain shutdown.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 4 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1454528 User-Defined ID:                 0#4 BANK Lesson Plan Objective:           HPCI 14.A Topic:                           Predict Impact of Loss of Div 2 DC on HPCI Operation RO:                             2.5 SRO:                             2.7 KA#:                             206000 K2.04 LMK 2017 ILT NRG JANUARY                       Page: 11 of 374                             17 January 2017
101-023 closed his answer is incorrect because the 023 DG Output Breaker will close (0.5 second time delayed losure) before the 101-023 Breaker (1.0 second time delayed closure), since the 023 DG was previously running and was in a "ready-to-load" status. Since the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker (not he 101-023 Breaker) closes. The "2C" RHR Pump will not remain shutdown.
 
023 OG Output Breaker open his answer is incorrect because the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully harge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker (not the 101-023 Breaker) closes. he "2C" RHR Pum will not remain shutdown.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 ILT NRG JANUARY Page: 21 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 7 Info Question Tvpe: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice?
2 1
No Points: 1.00 rl"ime to Complete:
206000 K2.04 2.5/2.7 High Pressure Coolant Injection System Knowledge of electrical power supplies to the following: Turbine control circuits: BWR-2,3,4 lower 2
3 Difficulty:
41.7 E41-1040-E-OO 4, sht. 001 26 E41-1040-E-OO 30 5, sht. 001 E41-1040-E-OO 36 2
2.00 System ID: 1454748 User-Defined ID: Q# 7 BANK Lesson Plan Objective:
6, sht. 001 ARC-MCR-117, A1 bank 560442 LMK 2017 ILT NRG JANUARY            Page: 12 of 374                            17 January 2017
LGSOPS0092.5A lropic: Unit 2 plant conditions are as follows: -100% Reactor Power -Normal Electrical Lineup The RO: 3.1 SRO: 3.4 KA#: 262001 K4.04 LMK 2017 IL T NRG JANUARY Page: 22 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 IL T NRG JANUARY Page: 23 of 374 262001 K4.04 2.8/3.1 A.C. Electrical Distribution Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the followin : Protective rela in Hi her 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 8 10:1454749 Points: 1.00 Unit 1 plant conditions:  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 5                                                      ID: 1454611                               Points: 1.00 Given:
-Reactor scrammed; all control rods fully inserted -RPV level is -7", steady -Drywell pressure is 6.5 psig, up slow -1 A AHR Pump is operating in Suppression Pool Spray -All other low pressure ECCS pumps are secured Wide range level instrument LIS-42-1 N691 A, which inputs to ADS, fails downscale.
* INSTRUMENT AIR HEADER A PRESSURE LO annunciator is in alarm
Assuming no operator action, which of the following identifies the impact on the ADS SRVs? A. Remain closed B. Open immediately  
        *INSTRUMENT AIR HEADER B PRESSURE LO annunciator is in alarm
: c. Open in 105 seconds D. Open in 525 seconds Answer: A Answer Explanation A E c G ow (1.68) X (or 420) X (or 420) X (or 420) X (or 420) Rx Level (-129) x x x x Cont Level x x (12.5) T.D. (105) x x 125# AHR A/C 0 0 145# A CS 0 145# c cs 0 125# B/D AHR 0 0 145# B CS 0 145# D CS 0 Enerqizes K6A K6E K6C K6G With RPV Level < 12.5" and Drywell Pressure > 1.68# and the "1 A" AHR pump running, the 105 sec time delay and -129" on both A and E channels is needed. The failed instrument in the stem (LIS-42-1 N691 A,C,E or G) provides the -129" input to one channel, but not to the other channel. Therefore, ADS does not initiate.
* Instrument Air header pressure is lowering The CRS has directed a power reduction per ON-119, Loss Of Instrument Air Which of the following describes the bases for the power reduction?
System design is such that -129 signals are required for 1 division to initiate to prevent inadvertent isolation LMK 2017 IL T NRG JANUARY Page: 24 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15*01January2017 NRC test SRO Question 8 Info Question Type: Multiple Choice Status:
A.           Reduce the probability of a turbine trip from lowering condenser vacuum.
Always select on test? No /\uthorized for practice?
B.           Reduce the transient if a SCRAM is required due to rods drifting in.
No Points: 1.00 !rime to Complete:
C.           Reduce the probability of inadequate feedwater should the condensate or feed pump min flow valves drift.
3 Difficulty:
D.         Reduce the probability of power exceeding 100% should the feedwater heater dump valves fail open.
2.00 System ID: 1454749 User-Defined ID: Q# 8 BANK Lesson Plan Objective:
Answer:
LGSOPS005.03F Topic: Impact of failed level instrument on ADS RO: 3.7 SRO: 3.9 KA#: 218000 K4.01 LMK 2017 IL T NRG JANUARY Page: 25 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Answer Explanation
LMK 2017 IL T NRG JANUARY Page: 26 of 374 2 218000 K4.01 3.7/3.9 Automatic Depressurization System Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature{s) and/or interlocks which provide for the following:
: 1.     Both inst. air header low alarms coming in is an entry condition for ON-119.
Prevent inadvertent initiation of ADS lo ic 3 41.7 see explanation bank 562181 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 9 10:1455668 Points: 1.00 Unit 1 is operating at full power when 113 BS CORE SPRAY LINE INTERNAL BREAK alarm actuates and will not clear. An equipment operator reports that Core Spray differential pressure transmitter PDT-052-1 N056 indicates  
: 2.     The bases for reducing power to 44% is to reduce the probability of a loss of adequate feedwater should the Condensate or RFP Min Flow valve begin to drift open.
+2.1 psid. Given the following from the annunciator response card OPERATOR ACTIONS: NOTE: Alarm designed to indicate failure of one of the core spray loop piping between the vessel penetration AND the core shroud penetration.
: 3.       Low Instrument Air pressure could cause CAD HCU scram valves to drift open, resulting in the associated control rods to insert. This is the Bases for manually SCRAM ING the reactor if control rods start to drift in
Normal rated power shroud/annulus dP is 7.5 psid. A valid value of greater than +1.3 or less than -3.B psid indicates a failure of the core spray piping outside the shroud. A value of greater than +7.5 psid or less than -10.0 psid indicates a failure of the core spray piping outside the vessel. A failure between the vessel AND containment would be measured by the containment leakage detection systems. This instrument loop is very noisy due to the condensation of steam inside the core spray piping AND also sensing pressures inside the shroud. Spurious alarms that immediately clear should NOT be considered valid. For a subsequent loss of high pressure injection; Which of the following lists the heat removal capabilities of the affected Core Spray system? A. Effective for BOTH core submergence AND spray cooling B. NOT effective for EITHER core submergence OR for spray cooling C. Effective for spray cooling but NOT tor core submergence D. Effective for core submergence but NOT for spray cooling Answer: D nswer Explanation RC-113-BS alarm indicates an A loop leak in the annulus is detected.This break prevents core spray flow from reaching the spray nozzles, located above the core. But since the line break is in he annulus, core spray flow will discharge through the break into the annulus, which can provide ater for core submergence.
: 4.     Air ejector valves may fail due to loss of air causing vacuum to decrease, however ON-119 directs entry to OT-116 for loss of vacuum actions
Answer D is correct and answer A, B, and C are incorrect but plausible to the examinee who miss understands the information provided, or does not understand the design features of the reactor vessel and internals.
: 5.     Feed water dump valves may fail open on a loss of air causing a power increase, however ON-119 directs operators to OT-104 for a loss of feedwater heating Q..f'(_
B t.M.cL. C ltt correct for the above reasons and the distractors are plausible to the examinee who does not recall the basis for reducinq power to 44%
LMK 2017 ILT NRC JANUARY                               Page: 13 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 5 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No
        ~uthorized for practice?         No Points:                         1.00 rnme to Complete:               3 Difficulty:                     2.00 System ID:                       1454611 User-Defined ID:                 0#5 NEW Lesson Plan Objective:           LGSOPS1550.03 lfopic:                         actions for loss of air RO:                             3.3 SRO:                             3.4 KA#:                             300000 K3.02 LMK 2017 ILT NRC JANUARY                       Page: 14 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
300000 K3.02 3.3/3.4 Instrument Air System (IAS)
Knowledge of the effect that a loss or malfunction of the
* INSTRUMENT AIR SYSTEM) will have on the following: Systems having neumatic valves and controls 41.7 ON-119 28 P&ID M-0015 40 sht 4 LMK 2017 ILT NRC JANUARY              Page: 15 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 6                                                   ID: 1685687                               Points: 1.00 Unit 1 is operating at 100% power when the following occurs:
        - The speed demand signal from DFWLC for the '1 A' RFP fails to 1 mA.
RPS successfully actuates, but an ATWS occurs.
One minute later, all of the logic to produce an ARCS Feedwater Runback is satisfied.
WHICH ONE of the following identifies the status of '1A' RFP two minutes after the runback logic is satisfied?
(Assume Il.Q operator action.)
A.       Running at 2300 rpm; M/A Station in control B.       Running at 2300 rpm; MSC in control C.       Running at the same speed as before the runback signal; MSC in control D.       Running at the same speed as before the runback signal; M/A Station in control Answer:             C Answer Explanation The speed demand signal loss results in 1A RFP swapping to MSC (an automatic swap to MSC when the DFWLC output fails to 1 mA) control and "locking up" at its present speed. Since its in "lockup" p.ri.Qr to the Runback, it will NOT respond to the Runback signal.
          'C' is correct for the above reasons.
          'A', 'B' are wrong. Plausible to the examines who forgets that the pre-existing lockup inhibits that RFP from responding to the runback.
          'D' is wrong. Control will not swap back to or stav in M/A station control.
LMK 2017 ILT NRG JANUARY                           Page: 16 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 6 Info K;luestion Type:                 Multiple Choice Status:                         Active
        !Always select on test?           No
        !Authorized for practice?         No Points:                         1.00 tTime to Complete:               4 Difficulty:                     2.50 System ID:                       1685687 User-Defined ID:                 0#6 Lesson Plan Obiective:           LOT-0550, OBJ4 RFP Speed Signal Loss - RFP Response to RRCS FW R/B lropic:
Siona!
RO:                             3.7 SRO:                             3.7 KA#:                             259002 K3.02 LMK 2017 ILT NRG JANUARY                       Page: 17 of 374                       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
259002 K3.02 3.7/3.7 Reactor Water Level Control System Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following: Reactor feedwater s stem LMK 2017 ILT NRC JANUARY            Page: 18 of 374                              17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 19 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO 7                                              ID: 1454748                               Points: 1.00 Unit 2 plant conditions are as follows:
        - 100% Reactor Power
        - Normal Electrical Lineup The following sequence of events occurs:
* t = 0 seconds               RPV level drops below -129 inches
* t = 20 seconds              201 Safeguard Bus < 70% bus voltage Which of the following identifies the closed 023 Bus Source Breaker AND. the status of the "2C" AHR Pump Breaker at T =75 seconds?
CLOSEDD23BUSSOUBCE                                "2C" RHB PUMP BREAKER                                    BREAKER A.                         101-023                                   Open B.                        101-023                                   Closed C.                023 OG Output Breaker                             Open
: 0.                023 OG Output Breaker                             Closed Answer:         0
        !Answer Explanation LMK 2017 ILT NRC JANUARY                         Page: 20 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 023 OG Output Breaker               closed 023 DG started on the LOCA signal. Since it had been running for greater than 1O seconds before the loss of power, the DG is ready to be loaded and the 0.5 second closing signal from the 023 Bus Under voltage logic will allow the 023 DG Output Breaker to close before the 1.0 second Dead Bus Transfer closing. Since the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will llow the breaker to reclose.
open his answer is incorrect because the 023 DG Output Breaker will close (0.5 second time delayed closure) before the 101-023 Breaker (1.0 second time delayed closure), since the 023 DG was previously running and was in a "ready-to-load" status. Since the time frame between the initial tart signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker closes. The "2C" RHR Pump will not remain shutdown.
101-023                             closed his answer is incorrect because the 023 DG Output Breaker will close (0.5 second time delayed losure) before the 101-023 Breaker (1.0 second time delayed closure), since the 023 DG was previously running and was in a "ready-to-load" status. Since the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker (not he 101-023 Breaker) closes. The "2C" RHR Pump will not remain shutdown.
023 OG Output Breaker               open his answer is incorrect because the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully harge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker (not the 101-023 Breaker) closes.
he "2C" RHR Pum will not remain shutdown.
LMK 2017 ILT NRG JANUARY                           Page: 21 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 7 Info Question Tvpe:                 Multiple Choice Status:                         Active Alwavs select on test?           No Authorized for practice?         No Points:                         1.00 rl"ime to Complete:             3 Difficulty:                     2.00 System ID:                       1454748 User-Defined ID:                 Q# 7 BANK Lesson Plan Objective:           LGSOPS0092.5A lropic:
Unit 2 plant conditions are as follows: - 100% Reactor Power -
Normal Electrical Lineup The RO:                             3.1 SRO:                             3.4 KA#:                             262001 K4.04 LMK 2017 ILT NRG JANUARY                       Page: 22 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
262001 K4.04 2.8/3.1 A.C. Electrical Distribution Knowledge of A.C.
ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the followin : Protective rela in Hi her LMK 2017 ILT NRG JANUARY              Page: 23 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 8                                                 10:1454749                                     Points: 1.00 Unit 1 plant conditions:
        - Reactor scrammed; all control rods fully inserted
        - RPV level is -7", steady
        - Drywell pressure is 6.5 psig, up slow
        - 1A AHR Pump is operating in Suppression Pool Spray
        - All other low pressure ECCS pumps are secured Wide range level instrument LIS-42-1 N691 A, which inputs to ADS, fails downscale.
Assuming no operator action, which of the following identifies the impact on the ADS SRVs?
A.       Remain closed B.     Open immediately
: c.     Open in 105 seconds D.     Open in 525 seconds Answer:         A Answer Explanation A             E       c             G ow   (1.68)       X (or 420) X (or 420) X (or 420) X (or 420)
Rx Level (-129)       x             x       x             x Cont Level             x                     x (12.5)
T.D. (105)             x                     x 125# AHR A/C           0           0 145# A CS             0 145# c cs                           0 125# B/D AHR                                 0             0 145# B CS                                   0 145# D CS                                                 0 Enerqizes             K6A         K6E     K6C         K6G With RPV Level < 12.5" and Drywell Pressure > 1.68# and the "1 A" AHR pump running, the 105 sec time delay and -129" on both A and E channels is needed. The failed instrument in the stem (LIS-42-1 N691 A,C,E or G) provides the -129" input to one channel, but not to the other channel.
Therefore, ADS does not initiate.
System design is such that -129 signals are required for 1 division to initiate to prevent inadvertent isolation LMK 2017 ILT NRG JANUARY                         Page: 24 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15*01January2017 NRC test SRO Question 8 Info Question Type:                   Multiple Choice Status:                         ~ctive Always select on test?           No
      /\uthorized for practice?       No Points:                         1.00
      !rime to Complete:               3 Difficulty:                     2.00 System ID:                     1454749 User-Defined ID:               Q# 8 BANK Lesson Plan Objective:         LGSOPS005.03F Topic:                         Impact of failed level instrument on ADS RO:                             3.7 SRO:                           3.9 KA#:                           218000 K4.01 LMK 2017 ILT NRG JANUARY                       Page: 25 of 374                   17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 218000 K4.01     3.7/3.9 Automatic Depressurization System Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature{s) and/or interlocks which provide for the following:
Prevent inadvertent initiation of ADS lo ic 3
41.7 see explanation bank 562181 LMK 2017 ILT NRG JANUARY            Page: 26 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 9                                                 10:1455668                                   Points: 1.00 Unit 1 is operating at full power when 113 BS CORE SPRAY LINE INTERNAL BREAK alarm actuates and will not clear. An equipment operator reports that Core Spray differential pressure transmitter PDT-052-1 N056 indicates +2.1 psid.
Given the following from the annunciator response card OPERATOR ACTIONS:
NOTE:     Alarm designed to indicate failure of one of the core spray loop piping between the vessel penetration AND the core shroud penetration. Normal rated power shroud/annulus dP is 7.5 psid.             A valid value of greater than +1.3 or less than -3.B psid indicates a failure of the core spray piping outside the shroud. A value of greater than +7.5 psid or less than -10.0 psid indicates a failure of the core spray piping outside the vessel. A failure between the vessel AND containment would be measured by the containment leakage detection systems. This instrument loop is very noisy due to the condensation of steam inside the core spray piping AND also sensing pressures inside the shroud. Spurious alarms that immediately clear should NOT be considered valid.
For a subsequent loss of high pressure injection; Which of the following lists the heat removal capabilities of the affected Core Spray system?
A.       Effective for BOTH core submergence AND spray cooling B.       NOT effective for EITHER core submergence OR for spray cooling C.       Effective for spray cooling but NOT tor core submergence D.       Effective for core submergence but NOT for spray cooling Answer:           D nswer Explanation RC-113-BS alarm indicates an A loop leak in the annulus is detected.This break prevents core spray flow from reaching the spray nozzles, located above the core. But since the line break is in he annulus, core spray flow will discharge through the break into the annulus, which can provide ater for core submergence. Answer D is correct and answer A, B, and C are incorrect but plausible to the examinee who miss understands the information provided, or does not understand the design features of the reactor vessel and internals.
Incorrect plausible to the examinee who miss interprets the information in the ARC and believe he value +2.1 is in the acceptable range B Incorrect plausible to the examinee who does not recognize the line break is in the annulus, ore spray flow will discharge through the break into the annulus, which can provide water for core submergence.
Incorrect plausible to the examinee who miss interprets the information in the ARC and believe he value +2.1 is in the acceptable range B Incorrect plausible to the examinee who does not recognize the line break is in the annulus, ore spray flow will discharge through the break into the annulus, which can provide water for core submergence.
C Incorrect lausible to the examinee who confuses s ra and submer ence coolin LMK 2017 IL T NRG JANUARY Page: 27 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
C Incorrect lausible to the examinee who confuses s ra and submer ence coolin LMK 2017 ILT NRG JANUARY                           Page: 27 of 374                             17 January 2017
No Points: 1.00 rnme to Complete:
 
4 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 9 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 rnme to Complete:               4 Difficulty:                     4.00 System ID:                       1455668 User-Defined ID:                 Q# 9 BANK Lesson Plan Objective:           LLOT035.1 OA lropic:                         Core spray cooling mode RO:                             2.8 SRO:                             2.9 KA#:                             209001 K5.04 LMK 2017 ILT NRG JANUARY                       Page: 28 of 374       17 January 2017
4.00 System ID: 1455668 User-Defined ID: Q# 9 BANK Lesson Plan Objective:
 
LLOT035.1 OA lropic: Core spray cooling mode RO: 2.8 SRO: 2.9 KA#: 209001 K5.04 LMK 2017 ILT NRG JANUARY Page: 28 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRC JANUARY Page: 29 of 374 209001 K5.04 2.8/2.9 Low Pressure Core Spray System Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY bank 510688 Oyster creek modified bank 510688 Oyster creek modified bank 51 0688 Oyster creek modified 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 10 ID: 1671166 Points: 1.00 Unit 1 is operating at 100% power. 1 UNIT DIV 1 SFGD BATTERY CHARGERS TROUBLE (120 G-1) alarms. An EO reports that the 480 VAC MCC supply breaker for the 1A1D103 Battery Charger has tripped. WHICH one of the following is supplying power for Div 1 DC loads? A. 1A1 Battery, ONLY B. 1A2D103 Battery Charger, ONLY C. 1A1 AND 1A2 Batteries D. 1A1 Battery AND 1A2D103 Battery Charger Answer: D Answer Explanation The Division I DC Distribution system has 2 batteries and each battery has a battery charger. The battery chargers are the normal source of power for the DC system. With a trip of one of the battery chargers, the associated battery will begin to discharge.
209001 K5.04 2.8/2.9 Low Pressure Core Spray System Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY bank 510688 Oyster creek modified bank 510688 Oyster creek modified bank 51 0688 Oyster creek modified LMK 2017 ILT NRC JANUARY              Page: 29 of 374                        17 January 2017
The second battery charger will continue to supply the DC bus. ARC-MCR-120 G-1, E-33 sh. 1, E-92 sh. 1 1A1 Battery only is plausible as a source but incomplete without the A2 side of the battery 1A2D103 Battery Charger only is plausible but incomplete answer without A 1 1A1 and 1 A2 Batteries is plausible but incorrect as the 1A2D103 charger is still functioning and suoolying the bus. LMK 2017 IL T NRC JANUARY Page: 30 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 1 O Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
 
No Points: 1.00 Time to Complete:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 10                                               ID: 1671166                                     Points: 1.00 Unit 1 is operating at 100% power.
4 Difficulty:
1 UNIT DIV 1 SFGD BATTERY CHARGERS TROUBLE (120 G-1) alarms.
1.00 System ID: 1671166 User-Defined ID: Q#10 BANK Lesson Plan Obiective:
An EO reports that the 480 VAC MCC supply breaker for the 1A1D103 Battery Charger has tripped.
LLOR0605D.01 Topic: Unit 1 is at 100% Reactor power. 1 UNIT DIV 1 SFGD BATTERY CHARGERS TROUBLE (120 G-1) alarms. An E RO: 3.2 SRO: 3.3 KA#: 263000 K1 .02 LMK 2017 IL T NRC JANUARY Page: 31 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
WHICH one of the following is supplying power for Div 1 DC loads?
LMK 2017 ILT NRC JANUARY Page: 32 of 374 D.C. Electrical Distribution Knowledge of the physical connections and/or causeeffect relationships between D.C. ELECTRICAL DISTRIBUTION and the following:
A.       1A1 Battery, ONLY B.     1A2D103 Battery Charger, ONLY C.       1A1 AND 1A2 Batteries D.     1A1 Battery AND 1A2D103 Battery Charger Answer:         D Answer Explanation The Division I DC Distribution system has 2 batteries and each battery has a battery charger. The battery chargers are the normal source of power for the DC system. With a trip of one of the battery chargers, the associated battery will begin to discharge. The second battery charger will continue to supply the DC bus.
Battery charger and batter E-0092 sht1 E-0033 sh. ARC-MCR-120 G-1 bank 562594 bank 562594 bank 562594 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 11 ID: 1454874 Points: 1.00 A LOCA occurs on Unit 2 which results in the following conditions:
ARC-MCR-120 G-1, E-33 sh. 1, E-92 sh. 1 1A1 Battery only is plausible as a source but incomplete without the A2 side of the battery 1A2D103 Battery Charger only is plausible but incomplete answer without A 1 1A1 and 1A2 Batteries is plausible but incorrect as the 1A2D103 charger is still functioning and suoolying the bus.
LMK 2017 ILT NRC JANUARY                         Page: 30 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 1O Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               4 Difficulty:                     1.00 System ID:                       1671166 User-Defined ID:                 Q#10 BANK Lesson Plan Obiective:           LLOR0605D.01 Unit 1 is at 100% Reactor power. 1 UNIT DIV 1 SFGD BATTERY Topic:
CHARGERS TROUBLE (120 G-1) alarms. An E RO:                             3.2 SRO:                             3.3 KA#:                             263000 K1 .02 LMK 2017 ILT NRC JANUARY                       Page: 31 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
D.C. Electrical Distribution Knowledge of the physical connections and/or causeeffect relationships between D.C. ELECTRICAL DISTRIBUTION and the following: Battery charger and batter E-0092 sht1 E-0033 sh.
ARC-MCR-120 G-1 bank 562594 bank 562594 bank 562594 LMK 2017 ILT NRC JANUARY            Page: 32 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 11                                               ID: 1454874                                 Points: 1.00 A LOCA occurs on Unit 2 which results in the following conditions:
RPV level drops to -140" before being restored to +20" with low pressure ECCS All Unit 2 diesels are running unloaded
RPV level drops to -140" before being restored to +20" with low pressure ECCS All Unit 2 diesels are running unloaded
* The PRO has been directed to synchronize D23 DIG with the 201 Safeguard Bus.
* The PRO has been directed to synchronize D23 DIG with the 201 Safeguard Bus.
* Before this can be performed, D23 D-G TROUBLE (221 B-1) alarms in the MCR.
* Before this can be performed, D23 D-G TROUBLE (221 B-1) alarms in the MCR.
* An EO dispatched to D23 reports that "J.W. TEMP HIGH" is in alarm at 2C-C514 panel and actual Jacket water temperature is 200&deg;F. WHICH ONE of the following describes the response of the D23 Diesel Generator if the "Diesel Generator Auto Start Signal Bypass" (BYPASSED) pushbutton PB/CG001 is depressed?
* An EO dispatched to D23 reports that "J.W. TEMP HIGH" is in alarm at 2C-C514 panel and actual Jacket water temperature is 200&deg;F.
A. Diesel will trip B. Diesel will continue to run in isochronous mode C. Diesel converts from droop to isochronous mode D. Diesel converts from isochronous to droop mode Answer: A Answer Explanation On a LOCA signal, the diesel will start in the isochronous mode. To synchronize the engine it must be converted to droop. To perform this, the operator must first depress the DG AUTO START BYPASS pushbutton to de-energize the LOCA start logic for the diesel and closes a permissive in the control switch logic to allow energization of the droop relay. Once this has been performed, the diesel control switch in the MCR must be placed to start. This will place the diesel in the droop mode of operation.
WHICH ONE of the following describes the response of the D23 Diesel Generator if the "Diesel Generator Auto Start Signal Bypass" (BYPASSED) pushbutton PB/CG001 is depressed?
However, if any trips that are normally bypassed are present when the DG AUTO ST ART pushbutton is depressed, the engine will trip due to the LOCA relay being de-energized by the pushbutton.
A.       Diesel will trip B.       Diesel will continue to run in isochronous mode C.       Diesel converts from droop to isochronous mode D.       Diesel converts from isochronous to droop mode Answer:           A Answer Explanation On a LOCA signal, the diesel will start in the isochronous mode. To synchronize the engine it must be converted to droop. To perform this, the operator must first depress the DG AUTO START BYPASS pushbutton to de-energize the LOCA start logic for the diesel and closes a permissive in the control switch logic to allow energization of the droop relay. Once this has been performed, the diesel control switch in the MCR must be placed to start. This will place the diesel in the droop mode of operation. However, if any trips that are normally bypassed are present when the DG AUTO ST ART pushbutton is depressed, the engine will trip due to the LOCA relay being de-energized by the pushbutton. Ref. caution in S92.7.N. the distractors are plausible to the examinee who does not recall that the TRIP bypass will go away when the LOCA is reset and C also requires the examinee to misinterpret droop and isochronous operation.
Ref. caution in S92.7.N. the distractors are plausible to the examinee who does not recall that the TRIP bypass will go away when the LOCA is reset and C also requires the examinee to misinterpret droop and isochronous operation.
Hi temp trip is bypassed on LOCA siqnal LMK 2017 ILT NRG JANUARY                           Page: 33 of 374                             17 January 2017
Hi temp trip is bypassed on LOCA siqnal LMK 2017 IL T NRG JANUARY Page: 33 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
 
No Points: 1.00 if ime to Complete:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 11 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 if ime to Complete:             3 Difficulty:                     2.80 System ID:                       1454874 User-Defined ID:                 Q# 11 BANK Lesson Plan Objective:           LGSOPS0092B.1 OF Effect on Diesel running on LOCA due to depressing AUTO ifopic:
3 Difficulty:
START BYPASS with Hiqh Lube Oil Temp present RO:                             3.8 SRO:                             3.9 KA#:                             264000 K6.07 LMK 2017 ILT NRG JANUARY                       Page: 34 of 374                             17 January 2017
2.80 System ID: 1454874 User-Defined ID: Q# 11 BANK Lesson Plan Objective:
 
LGSOPS0092B.1 OF ifopic: Effect on Diesel running on LOCA due to depressing AUTO START BYPASS with Hiqh Lube Oil Temp present RO: 3.8 SRO: 3.9 KA#: 264000 K6.07 LMK 2017 IL T NRG JANUARY Page: 34 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRG JANUARY Page: 35 of 374 2 1 264000 K6.07 3.8/3.9 Emergency Generators (Diesel/Jet)
2 1
Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET)  
264000 K6.07 3.8/3.9 Emergency Generators (Diesel/Jet) Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET) :Cooling bank 554174 modified to better match K.A LMK 2017 ILT NRG JANUARY              Page: 35 of 374                            17 January 2017
:Cooling bank 554174 modified to better match K.A 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 36 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 12 ID: 1600748 ... Points: 1.00 Unit 1 is at 100% power when a malfunction in the Reactor Enclosure Cooling Water system (RECW) causes the following:
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 36 of 374         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 12                                             ID: 1600748 ...                             Points: 1.00 Unit 1 is at 100% power when a malfunction in the Reactor Enclosure Cooling Water system (RECW) causes the following:
* A rising trend in RWCU Non-Regenerative Heat Exchanger outlet temperature.
* A rising trend in RWCU Non-Regenerative Heat Exchanger outlet temperature.
Current Non-Regenerative Heat Exchanger outlet temperature is 128 &deg; F Temperature is rising at constant rate of 2 &deg; F/min Which of the choices correctly completes the following statement?
Current Non-Regenerative Heat Exchanger outlet temperature is 128 &deg; F Temperature is rising at constant rate of 2 &deg; F/min Which of the choices correctly completes the following statement?
A RWCU isolation signal will actuate in (1) minutes, reactor coolant (2) will rise if the isolation fails to occur. A. (1) 3.5 (2) pH B. (1) 3.5 (2) conductivity  
A RWCU isolation signal will actuate in     (1) minutes, reactor coolant (2) will rise if the isolation fails to occur.
: c. (1) 6 (2) pH D. (1) 6 (2) conductivity Answer: D !Answer Explanation LMK 2017 IL T NRG JANUARY Page: 37 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO The RWCU system is operated using S44.0.A, "OPERATING RWCU TO MEET PLANT CONDITIONS" (among other procedures).
A.     (1) 3.5 (2) pH B.     (1) 3.5 (2) conductivity
Within this procedure one of the system Precautions is: 3.7 RWCU system will isolate at 140&deg;F at outlet of Non-regenerative Heat Exchanger.
: c.     (1) 6 (2) pH D.     (1) 6 (2) conductivity Answer:         D
080 3.2.5.1 Basis -Non-Regenerative Heat Exchanger Outlet Temperature The limit on the Non-Regen HX outlet temperature is required to protect the filtering and ion exchange medium (resin) used in the F/Ds. Excessive temperatures can cause the resin to disintegrate and dissolve in the reactor water, compounding contamination and radiation problems.
          !Answer Explanation LMK 2017 ILT NRG JANUARY                       Page: 37 of 374                             17 January 2017
The controlling value of 140F is established by the system specification  
 
{6.1.2.1}.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO The RWCU system is operated using S44.0.A, "OPERATING RWCU TO MEET PLANT CONDITIONS" (among other procedures). Within this procedure one of the system Precautions is:
ON-116 12.3 IF Reactor Water Conductivity is greater than 1.0 umho/cm with main steam line (MSL) radiation high AND Reactor Water pH low (Resin or other organic intrusion is suspected), !THEN PERFORM the following:
3.7 RWCU system will isolate at 140&deg;F at outlet of Non-regenerative Heat Exchanger.
12.3.1 IF MSL radiation rises to 1.5 x normal full power background, !THEN ENTER ON-102 EXECUTE concurrently.
080 3.2.5.1 Basis - Non-Regenerative Heat Exchanger Outlet Temperature The limit on the Non-Regen HX outlet temperature is required to protect the filtering and ion exchange medium (resin) used in the F/Ds. Excessive temperatures can cause the resin to disintegrate and dissolve in the reactor water, compounding contamination and radiation problems. The controlling
        ~arameter value of 140F is established by the system specification {6.1.2.1}.
ON-116 12.3 IF Reactor Water Conductivity is greater than 1.0 umho/cm with main steam line (MSL) radiation high AND Reactor Water pH low (Resin or other organic intrusion is suspected),
        !THEN PERFORM the following:
12.3.1 IF MSL radiation rises to 1.5 x normal full power background,
        !THEN ENTER ON-102
        ~ND EXECUTE concurrently.
12.3.2 DETERMINE RWCU Demin that could be passing resin by identifying demin with high effluent conductivity (suspect demin recently placed in service).
12.3.2 DETERMINE RWCU Demin that could be passing resin by identifying demin with high effluent conductivity (suspect demin recently placed in service).
A Wrong -Plausible to the student who either recalls the isolation set point incorrectly or performs the calculation incorrectly, also plausible to the student who incorrectly recalls (reverses) the Affect on conductivity and PH B Wrong -Plausible to the student who either recalls the isolation set point incorrectly or performs the calculation incorrectly.
A     Wrong - Plausible to the student who either recalls the isolation set point incorrectly or performs the calculation incorrectly, also plausible to the student who incorrectly recalls (reverses) the Affect on conductivity and PH B     Wrong - Plausible to the student who either recalls the isolation set point incorrectly or performs the calculation incorrectly.
C Wrong -plausible to the student who incorrectly recalls (reverses) the Affect on conductivity and PH D Correct for the above reasons -Isolation occurs at 140 F. At a rate of rise of 2 degrees/ minutes the isolation will occur after 6 minutes (rise of 12 degrees F). and conductivity rises and PH lowers LMK 2017 IL T NRC JANUARY Page: 38 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 12 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
C     Wrong - plausible to the student who incorrectly recalls (reverses) the Affect on conductivity and PH D     Correct for the above reasons - Isolation occurs at 140 F. At a rate of rise of 2 degrees/
No Points: 1.00 ifime to Complete:
minutes the isolation will occur after 6 minutes (rise of 12 degrees F). and conductivity rises and PH lowers LMK 2017 ILT NRC JANUARY                         Page: 38 of 374                                 17 January 2017
2 Difficulty:
 
3.00 System ID: 1600748 User-Defined ID: Q #12 NEW Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 12 Info Question Type:                   Multiple Choice Status:                         Active
LGSOPS0044.05 (RWCU) rrooic: RWCU -Expain and apply all system limits and precautions RO: 2.9 SRO: 3.3 KA#: 400000 LMK 2017 IL T NRC JANUARY Page: 39 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
        ~lways select on test?           No
LMK 2017 IL T NRC JANUARY Page: 40 of 374 RO 2 1 400000 K3.01 2.9/3.3 Component Cooling Water System (CCWS) Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: Loads cooled by ccws. *AW' LGSOPS0010 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 13 ID: 1454932 Points: 1.00. Unit 1 was operating at 100% power when a LOCA occurred.
        ~uthorized for practice?         No Points:                         1.00 ifime to Complete:               2 Difficulty:                     3.00 System ID:                       1600748 User-Defined ID:                 Q #12 NEW Lesson Plan Objective:           LGSOPS0044.05 (RWCU) rrooic:                         RWCU - Expain and apply all system limits and precautions RO:                             2.9 SRO:                             3.3 KA#:                             400000 LMK 2017 ILT NRC JANUARY                       Page: 39 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
RO 2
1 400000 K3.01 2.9/3.3 Component Cooling Water System (CCWS) Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: Loads cooled by ccws.
LGSOPS0010
                                                                                  *AW'
                                                                                    ~:',:;
LMK 2017 ILT NRC JANUARY            Page: 40 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 13                                               ID: 1454932                                   Points: 1.00.
Unit 1 was operating at 100% power when a LOCA occurred.
Plant conditions are as follows
Plant conditions are as follows
* Reactor level is -150 inches, being controlled with LPCI Which of the following describes (1) the source of water to the LPCI unit coolers and (2) where the cooling water is returningX  
* Reactor level is -150 inches, being controlled with LPCI Which of the following describes (1) the source of water to the LPCI unit coolers and (2) where the cooling water is returningX 2. 1>1i'n1.t+e.s o.f-fe.,r' re~ leve..L reo.c.ltie.s -15?> 1'nc.J,,~~ ? ,ei,o         !z.7}7 (Assume no operator action)
: 2. 1>1i'n1.t+e.s o.f-fe.,r' leve..L reo.c.ltie.s  
* A.         (1) Service Water (2) Cooling Tower B.       (1) Service Water (2) Spray Pond C.       (1) ESW (2) Cooling Tower D.       (1) ESW (2) Spray Pond Answer:             B Answer Explanation At -129 inches a loca signal will start the diesel generators and the ESW pumps. However, since
-15?>  
        ,here is no loss of off site power service water will still be running. The examinee must realize that service water is at a higher pressure than ESW and service water will keep the ESW supply check valve closed and continue to supply the unit coolers. On the return header the the air operated valves will realign on the ESW pump start causing the return path to realign from the cooling tower to the Spray Pond.
? ,ei,o !z.7}7 (Assume no operator action)
For the above reasons B is correct. The distractor are plausible to the examinee who does not recall that Service Water is at a higher pressure than ESW or incorrectly recalls the return flow path arrangement A     Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supply the loads. When the ESW pump starts the valve line up for ESW return path swaps from the cooling towers to the spray pond.
* A. (1) Service Water (2) Cooling Tower B. (1) Service Water (2) Spray Pond C. (1) ESW (2) Cooling Tower D. (1) ESW (2) Spray Pond Answer: B Answer Explanation At -129 inches a loca signal will start the diesel generators and the ESW pumps. However, since ,here is no loss of off site power service water will still be running. The examinee must realize that service water is at a higher pressure than ESW and service water will keep the ESW supply check valve closed and continue to supply the unit coolers. On the return header the the air operated valves will realign on the ESW pump start causing the return path to realign from the cooling tower to the Spray Pond. For the above reasons B is correct. The distractor are plausible to the examinee who does not recall that Service Water is at a higher pressure than ESW or incorrectly recalls the return flow path arrangement A Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supply the loads. When the ESW pump starts the valve line up for ESW return path swaps from the cooling towers to the spray pond. B Correct service water is at a higher pressure and suppling the loads and ESW return path is aligned to the spray pond C Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supply the loads. When the ESW pump starts the valve line up for ESW return path swaps from the cooling towers to the spray pond. D Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supplv the loads. LMK 2017 IL T NRC JANUARY Page: 41 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
B     Correct service water is at a higher pressure and suppling the loads and ESW return path is aligned to the spray pond C     Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supply the loads. When the ESW pump starts the valve line up for ESW return path swaps from the cooling towers to the spray pond.
No Points: 1.00 Time to Complete:
D     Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supplv the loads.
3 Difficulty:
LMK 2017 IL T NRC JANUARY                         Page: 41 of 374                               17 January 2017
3.00 Svstem ID: 1454932 User-Defined ID: Q# 13 NEW Lesson Plan Obiective:
 
LOT051.161 Topic: LPCI component coolinq water RO: 2.9 SRO: 2.9 KA#: 203000 A1 .09 LMK 2017 IL T NRG JANUARY Page: 42 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 13 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.00 Svstem ID:                       1454932 User-Defined ID:                 Q# 13 NEW Lesson Plan Obiective:           LOT051.161 Topic:                           LPCI component coolinq water RO:                             2.9 SRO:                             2.9 KA#:                             203000 A1 .09 LMK 2017 ILT NRG JANUARY                       Page: 42 of 374       17 January 2017
LMK 2017 IL T NRC JANUARY Page: 43 of 374 2 1 203000 A1 .09 2.9/2.9 RHR/LPCI:
 
Injection Mode (Plant Specific)
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:
2 1
203000 A1 .09 2.9/2.9 RHR/LPCI: Injection Mode (Plant Specific) Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:
INJECTION MODE (PLANT SPECIFIC) controls including:
INJECTION MODE (PLANT SPECIFIC) controls including:
Component cooling water 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 14 ID: 1455377 Points: 1.00 The SPDS MSIV Event Indicator is showing MSIVs SHUT, with a green border. Which of the following situations can cause this display? A. MSIVs have received an isolation command, but are still full open. B. MSIVs have received an isolation command, and are stroking closed. C. MSIVs are closed manually, with an isolation command present. D. MSIVs are closed manually, with NO isolation command present. Answer: D Answer Explanation COLOR CODING CONVENTION:  
Component cooling water LMK 2017 ILT NRC JANUARY            Page: 43 of 374                          17 January 2017
: a. MAGENTA= bad data, which means a signal is out of range, or there has been a system  
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 14                                               ID: 1455377                                     Points: 1.00 The SPDS MSIV Event Indicator is showing MSIVs SHUT, with a green border.
Which of the following situations can cause this display?
A.       MSIVs have received an isolation command, but are still full open.
B.       MSIVs have received an isolation command, and are stroking closed.
C.       MSIVs are closed manually, with an isolation command present.
D.       MSIVs are closed manually, with NO isolation command present.
Answer:           D Answer Explanation COLOR CODING CONVENTION:
: a. MAGENTA= bad data, which means a signal is out of range, or there has been a system
        ~ailure.
: b. RED = Alarm condition exists. One or more of the associated points have exceeded their setpoints.
: b. RED = Alarm condition exists. One or more of the associated points have exceeded their setpoints.
K:. YELLOW = Off-normal condition exists. One or more of the associated points are approaching operating limits (e.g. Rx water level approaching scram point); an important plant event is initiated (e.g. ADS timer initiated);
K:. YELLOW = Off-normal condition exists. One or more of the associated points are approaching
insufficient information available to validate a control parameter (or disagreement of data). k:L GREEN = Safe condition exists. Normal operating parameters present. e. CYAN = Sufficient data available to validate control parameters; indicates normal/satisfactory operation of systems/equipment. DARK BLUE= System/component is INACTIVE.  
        ~heir operating limits (e.g. Rx water level approaching scram point); an important plant event is initiated (e.g. ADS timer initiated); insufficient information available to validate a control parameter (or disagreement of data).
: g. WHITE = Active I permissive conditions exists. h. "BLINKING" = Used to ALERT the operator of a dynamic condition which requires acknowledgment.
k:L GREEN = Safe condition exists. Normal operating parameters present.
A Incorrect plausible to the examinee who believe the shut indication means that MSIV received an isolation command and that green indicates that they have not reposition B Incorrect plausible to examinee who believes green indication is activated when MSIV red light goes out (this will cause MSIV to indicate closed) but fails to recognize that green SPDS indication is normal operating parameters C Incorrect plausible to examinee who believe green is closed and does not apply red exceeding setpoint to the MSIV indication D Correct MSIV's where shut with no isolation signal (manually closed) LMK 2017 IL T NRG JANUARY Page: 44 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 14 Info Question Tvoe: Multiple Choice Status: Active select on test? No for practice?
: e. CYAN = Sufficient data available to validate control parameters; indicates normal/satisfactory operation of systems/equipment.
No Points: 1.00 rnme to Complete:
        ~. DARK BLUE= System/component is INACTIVE.
3 Difficulty:
: g. WHITE = Active I permissive conditions exists.
2.00 System ID: 1455377 User-Defined ID: Q# 14 BANK Lesson Plan Objective:
: h. "BLINKING" = Used to ALERT the operator of a dynamic condition which requires acknowledgment.
LGSOPS0038B.1 Topic: ERFDS Critical Plant Variables display, format 00 RO: 2.5 SRO: 2.8 KA#: 223002 A1 .03 LMK 2017 IL T NRC JANUARY Page: 45 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
A   Incorrect plausible to the examinee who believe the shut indication means that MSIV received an isolation command and that green indicates that they have not reposition B   Incorrect plausible to examinee who believes green indication is activated when MSIV red light goes out (this will cause MSIV to indicate closed) but fails to recognize that green SPDS indication is normal operating parameters C   Incorrect plausible to examinee who believe green is closed and does not apply red exceeding setpoint to the MSIV indication D   Correct MSIV's where shut with no isolation signal (manually closed)
LMK 2017 IL T NRG JANUARY Page: 46 of 374 223002 A 1.03 2.5/2.8 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including:
LMK 2017 ILT NRG JANUARY                         Page: 44 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 14 Info Question Tvoe:                 Multiple Choice Status:                         Active
        ~lways select on test?         No
        ~uthorized for practice?       No Points:                         1.00 rnme to Complete:               3 Difficulty:                     2.00 System ID:                     1455377 User-Defined ID:               Q# 14 BANK Lesson Plan Objective:         LGSOPS0038B.1 Topic:                         ERFDS Critical Plant Variables display, format 00 RO:                             2.5 SRO:                           2.8 KA#:                           223002 A1 .03 LMK 2017 ILT NRC JANUARY                       Page: 45 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
223002 A1.03 2.5/2.8 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including:
SPDS/ERIS/CRIDS/GDS:
SPDS/ERIS/CRIDS/GDS:
lower 5 41.5 LGSOPS00388 17 January 2017
lower 5
* EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 15 ID: 1455388 Points: 1.00 Unit 1 is operating at 100% power with the following conditions:
41.5 LGSOPS00388 LMK 2017 ILT NRG JANUARY            Page: 46 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 15                                                 ID: 1455388                                   Points: 1.00 Unit 1 is operating at 100% power with the following conditions:
* RT-6-041-490-1, Suppression Pool Gross Input Leak Rate Determination is being performed
* RT-6-041-490-1, Suppression Pool Gross Input Leak Rate Determination is being performed
* Per the above RT, the last RT-6-041-230-1 MSRV tailpipe temperature data monitoring information is retrieved and the data for the A SRV is shown below. ATTACHMENT 1 Page 1of1 DateJTime RX Power RX Press flh) %
* Per the above RT, the last RT-6-041-230-1 MSRV tailpipe temperature data monitoring information is retrieved and the data for the A SRV is shown below.
00 .:1...1 lt /Jf.. Ji.:J!. na % IQO % SRV /1>VY PSIG IO"l1 PSlG 1(')"1'1 PSIG Tailpipe Temp Pilot Temp l"f f A Which of the following combinations of pilot valve temperature and tailpipe temperature would indicate leakage past the pilot valve seat? Pilot valve temperature Tailpipe temperature A. 499 degrees F 140 degrees F B. 499 degrees F 150 degrees F c. 511 degrees F 140 degrees F D. 511 degrees F 150 degrees F Answer: B Answer Explanation Bis correct temperature is lower than base line temperature due to the cooling effect of the steam and the pressure drop of the steam. leakage past the seat will end up in the tailpipe causing tailpipe to rise
ATTACHMENT 1 Page 1of1 DateJTime         .!Ll~.l!!_.u_:~              -~--'.lliJ.Jz_~: 00       .:1...1 lt /Jf.. Ji.:J!.
* IA incorrect plausible to the examinee who recalls temperature will lower due to the cooling effect !Of the steam flow and the pressure drop of the steam. A pilot valve temperature decrease without a rise in tailpipe is indicative of srv external leakage into the drywell C incorrect plausible to the examinee who believes that the stagnant steam in the line would be replaced with 545 degree reactor steam but neglects the cooling effect of flow and pressure drop and does not know where pilot vale leakage goes D Incorrect but plausible for the reasons described above LMK 2017 IL T NRG JANUARY Page: 47 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 48 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 15 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
RX Power                          flh)    %                  na     %                     IQO   %
No Points: 1.00 rnme to Complete:
SRV         RX Press                  /1>VY     PSIG             IO"l1   PSlG                 1(')"1'1 PSIG Tailpipe Temp                                                                       l"f f A     Pilot Temp Which of the following combinations of pilot valve temperature and tailpipe temperature would indicate leakage past the pilot valve seat?
3 Difficulty:
Pilot valve temperature                         Tailpipe temperature A.       499 degrees F                                 140 degrees F B.       499 degrees F                                 150 degrees F
2.00 System ID: 1455388 User-Defined ID: Q# 15 NEW Lesson Plan Objective:
: c.       511 degrees F                                 140 degrees F D.       511 degrees F                                 150 degrees F Answer:           B
LGSOPS001 ffopic: Determine pilot leakage tailpipe temperature for leaking SRV RO: 3.1 SRO: 3.2 KA#: 239002 LMK 2017 IL T NRC JANUARY Page: 49 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
* Answer Explanation Bis correct temperature is lower than base line temperature due to the cooling effect of the steam
LMK 2017 IL T NRC JANUARY Page: 50 of 374 RO 2 239002 A2.02 3.1 /3.2 Relief/Safety Valves Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions SRV  
          ~low and the pressure drop of the steam. leakage past the seat will end up in the tailpipe causing tailpipe
; 2 5 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 51 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 16 ID; 1455407 A Reactor Startup is in progress with the following conditions:
          ~emperature    to rise
* IA incorrect plausible to the examinee who recalls temperature will lower due to the cooling effect
          !Of the steam flow and the pressure drop of the steam. A pilot valve temperature decrease without a rise in tailpipe
          ~emperature is indicative of srv external leakage into the drywell C incorrect plausible to the examinee who believes that the stagnant steam in the line would be replaced with 545 degree reactor steam but neglects the cooling effect of flow and pressure drop and does not know where pilot vale leakage goes D Incorrect but plausible for the reasons described above LMK 2017 ILT NRG JANUARY                           Page: 47 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 48 of 374         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 15 Info Question Type:                 Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 rnme to Complete:               3 Difficulty:                     2.00 System ID:                       1455388 User-Defined ID:                 Q# 15 NEW Lesson Plan Objective:           LGSOPS001 ffopic:                           Determine pilot leakage tailpipe temperature for leaking SRV RO:                             3.1 SRO:                             3.2 KA#:                             239002 LMK 2017 ILT NRC JANUARY                       Page: 49 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
RO 2
239002 A2.02 3.1 /3.2 Relief/Safety Valves Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES
                                                            ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions SRV
:1ift~~''.i ;
2 5
LMK 2017 ILT NRC JANUARY            Page: 50 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 51 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 16                                               ID; 1455407                       Points; 1.00 A Reactor Startup is in progress with the following conditions:
* Reactor is critical on a stable, positive period
* Reactor is critical on a stable, positive period
* Reactor power is on range 3 of the IRMs
* Reactor power is on range 3 of the IRMs
* The RO is withdrawing SRMs
* The RO is withdrawing SRMs
* The RO continues to up range the IRMs until all IRMs are on range 8 Then a malfunction in the '1A' SRM causes count rate to rise to 2X10 5 cps. Given the above, which one of the following is correct regarding, (1) Any alarms received AND (2) Any required actions directed by plant procedures that would allow the startup to continue?
* The RO continues to up range the IRMs until all IRMs are on range 8 Then a malfunction in the '1A' SRM causes count rate to rise to 2X105 cps.
A. (1) SRM rod block AND upscale alarm. (2) Bypass SRM "A". B. 1) SRM rod block AND upscale alarm. (2) Place SRM "A" in standby. C. (1) Upscale alarm but NOT SRM rod block. (2) Place SRM "A" in standby. D. 1) Upscale alarm but NOT SRM rod block. (2) Bypass SRM "A". Answer: D !Answer Explanation LMK 2017 IL T NRG JANUARY Page: 52 of 374 Points; 1.00 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Incorrect:
Given the above, which one of the following is correct regarding, (1) Any alarms received AND (2) Any required actions directed by plant procedures that would allow the startup to continue?
If any SAM channel detects > 1 X 105 cps, a rod block is activated.
A.       (1) SRM rod block AND upscale alarm.
This rod block is bypassed if: -The mode switch is in RUN -The associated IRM range switches are at range 8 or above Since the IRMs are on range 8, the rod block would not occur. IAW the ARC107 H4 the directed action is to bypass the SRM. B. Incorrect:
(2) Bypass SRM "A".
Taking the function switch out of operate will cause an !NOP/upscale alarm. Plausible if the candidate does not remember that taking the iunction switch out of Operate will cause an INOP trip. Additionally this action is not directed by any plant procedure.
B.       1) SRM rod block AND upscale alarm.
D. Correct: Upscale alarm The IRMs on range 8 or higher. ARC-MCR-107 H4 directs bypassing the SRM. C. Incorrect:
(2) Place SRM "A" in standby.
This action is not authorized by the ARC and will generate an INOP TRIP alarm LMK 2017 IL T NRG JANUARY Page: 53 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO SRM CHANNEL "A" CONTROL ROD BLOCK SIGNALS AND BYPASSES CLOSED IF IRM"A"IS ABOVE RANGE7 CLOSED IF IRM"C"IS ABOVE RANGE7 CLOSED IF IRM"E"IS ABOVE RANGE7 CLOSED IF IRM"G" IS ABOVE RANGE 7 SRM INOPERATIVE TRIP -Internal Module Unplugged CLOSED IF OPENSONSRM IRM"A"IS "A" UPSCALE BYPASSED ALARM CLOSED IF (1 X 10" CPS) SRM "A" IS BYPASSED CLOSED IF IRM"C"IS OPENSONSRM BYPASSED "A" INOPERATIVE TRIP CLOSED IF OPENS ON SRM "A" IRM"E" IS CLOSED IF DOWNSCALE TRIP BYPASSED IRMs "A", 11 C 11 , (3 CPS) 11 E 11 ,AND 11 G 11 ARE ABOVE RANGE2 CLOSED IF IRM"G"IS CLOSED ON BYPASSED RETRACT PERMIT (100 CPS) \ CLOSED IF REACTOR SRM"C" MODE SWITCH (IDENTICAL TO OPENS IFSRM ISIN "RUN" "A" ABOVE) DETECTOR "A" IS NOT FULLY INSERTED CONTROL ROD WITHDRAWAL BLOCK OCCURS WHEN ROD BLOCK RELAY DE-ENERGIZES ROD BLOCK RELAY all control rod withdrawal block functions are bypassed if:
C.       (1) Upscale alarm but NOT SRM rod block.
* The associated SRM channel is bypassed -Channel Mode Switch not in "OPERATE"
(2) Place SRM "A" in standby.
* All four IRM channels (in the same RPS trip system) are on Range 8 or above -Low detector voltage LMK 2017 IL T NRG JANUARY Page: 54 of 374
D.       1) Upscale alarm but NOT SRM rod block.
* The Reactor Mode Switch is in the "RUN' position 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 16 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
(2) Bypass SRM "A".
No Points: 1.00 Time to Complete:
Answer:           D
3 Difficulty:
        !Answer Explanation LMK 2017 ILT NRG JANUARY                         Page: 52 of 374                     17 January 2017
2.50 System ID: 1455407 User-Defined ID: Q# 16 MODIFIED Lesson Plan Objective:
 
LGSOPS0074.6 Topic: Predict Response to SRM Count rate dropping RO: 3.3 SRO: 3.5 KA#: 215004 A2.05 LMK 2017 IL T NRC JANUARY Page: 55 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO
LMK 2017 IL T NRC JANUARY Page: 56 of 374 Source Range Monitor (SRM) System Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
      ~. Incorrect: If any SAM channel detects > 1 X 105 cps, a rod block is activated. This rod block is bypassed if:
Faulty or erratic o eration of detectors/s stem hi her 41.5,41.6,41.7 ARC-107-G4 ARC-107-14 Modified NRC bank see revision histo Modified 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 57 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO 17 ID: 1455428 Points: 1.00 Unit 1 plant conditions are as follows:
        - The mode switch is in RUN
        -The associated IRM range switches are at range 8 or above Since the IRMs are on range 8, the rod block would not occur.
IAW the ARC107 H4 the directed action is to bypass the SRM.
B. Incorrect: Taking the function switch out of operate will cause an !NOP/upscale alarm.
Plausible if the candidate does not remember that taking the iunction switch out of Operate will cause an INOP trip. Additionally this action is not directed by any plant procedure.
D. Correct: Upscale alarm The IRMs on range 8 or higher. ARC-MCR-107 H4 directs bypassing the SRM.
C. Incorrect: This action is not authorized by the ARC and will generate an INOP TRIP alarm LMK 2017 ILT NRG JANUARY                         Page: 53 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO SRM CHANNEL "A" CONTROL ROD BLOCK SIGNALS AND BYPASSES CLOSED IF           CLOSED IF                                   OPENSONSRM IRM"A"IS             IRM"A"IS                                     "A" UPSCALE ABOVE                BYPASSED                                     ALARM RANGE7                                CLOSED IF                 (1 X 10" CPS)
SRM "A" IS BYPASSED CLOSED IF            CLOSED IF IRM"C"IS             IRM"C"IS                                    OPENSONSRM ABOVE                BYPASSED                                     "A" INOPERATIVE RANGE7                                                            TRIP CLOSED IF           CLOSED IF IRM"E" IS                                                OPENS ON SRM "A" IRM"E"IS                                     CLOSED IF                         DOWNSCALE TRIP ABOVE                BYPASSED               IRMs "A", 11 C 11 ,
(3 CPS)
RANGE7                                      11 E ,AND G 11       11  11 ARE ABOVE RANGE2 CLOSED IF            CLOSED IF IRM"G" IS           IRM"G"IS                        CLOSED ON ABOVE                BYPASSED                       RETRACT RANGE 7                                              PERMIT (100 CPS)
CLOSED IF REACTOR MODE SWITCH SRM"C" (IDENTICAL TO
                                                                                                                  \
OPENS IFSRM ISIN "RUN"                   "A" ABOVE)                           DETECTOR "A" IS NOT FULLY INSERTED CONTROL ROD WITHDRAWAL                     ROD BLOCK RELAY BLOCK OCCURS WHEN ROD BLOCK RELAY DE-ENERGIZES
                                                                                  ~:          all control rod withdrawal block functions are bypassed if:
SRM INOPERATIVE TRIP
* The associated SRM channel is bypassed
          - Internal Module Unplugged
* All four IRM channels (in the same RPS
          - Channel Mode Switch not in "OPERATE"                                          trip system) are on Range 8 or above
          - Low detector voltage
* The Reactor Mode Switch is in the "RUN' position LMK 2017 ILT NRG JANUARY                            Page: 54 of 374                                                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 16 Info Question Type:                   Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.50 System ID:                       1455407 User-Defined ID:                 Q# 16 MODIFIED Lesson Plan Objective:           LGSOPS0074.6 Topic:                           Predict Response to SRM Count rate dropping RO:                             3.3 SRO:                             3.5 KA#:                             215004 A2.05 LMK 2017 ILT NRC JANUARY                       Page: 55 of 374                       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Source Range Monitor (SRM) System Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM)
SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic o eration of detectors/s stem hi her 41.5,41.6,41.7 ARC-107-G4 ARC-107-14 Modified NRC bank see revision histo Modified LMK 2017 ILT NRC JANUARY            Page: 56 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 57 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO 17                                             ID: 1455428                                 Points: 1.00 Unit 1 plant conditions are as follows:
* Reactor STARTUP is in progress
* Reactor STARTUP is in progress
* Reactor power is 20%
* Reactor power is 20%
* 1 B RPS/UPS, "Inverter AC Feed Switch" is aligned to Primary Alternate Supply During the startup the following alarms on MCA PNL 122 annunciate:
* 1B RPS/UPS, "Inverter AC Feed Switch" is aligned to Primary Alternate Supply During the startup the following alarms on MCA PNL 122 annunciate:
* 18 RPS & UPS STATIC INVERTER TROUBLE
* 18 RPS & UPS STATIC INVERTER TROUBLE
* 1 DB-1 250 VDC MCC UNDERVOLTAGE
* 1DB-1 250 VDC MCC UNDERVOLTAGE
* 1 DB-2 250 VDC MCC UNDERVOL T AGE All RPS white status lights are lit. WHICH ONE of the following identifies the source currently providing power to "1 B" RPS? A. 480VAC Non-Safeguard NQI bypassing the RPS/UPS inverter B. 480VAC Non-Safeguard bypassing the RPS/UPS inverter C. TSC UPS Inverter NQI bypassing the RPS/UPS Inverter D. TSC UPS Inverter bypassing the RPS/UPS Inverter Answer: C /Answer Explanation LMK 2017 IL T NRC JANUARY Page: 58 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO DISTRACTOR 480VAC Non-Safeguard not bypassing the RPS/UPS Inverter -This is incorrect answer because the DC supply is the normal preferred source from 1 DB-1 250 VDC MCC. The primary alternate supply is from the TSC UPS Inverter (1440-C-F) and the Secondary Alternate supply is from Non Safeguard 480 VAC MCC 124A-G-F for the 1 B Inverter.
* 1DB-2 250 VDC MCC UNDERVOLT AGE All RPS white status lights are lit.
Per the conditions stated, The primary alternate is selected on the Inverter AC Feed Selector Switch and the RPS inverter static switch will auto swap to the selected supply which in this case is the primary alternate supply. In this stated condition the AC supply is not bypassing the RPS inverter, but is going through the inverter.
WHICH ONE of the following identifies the source currently providing power to "1 B" RPS?
ANSWER TSC UPS Inverter not bypassing the RPS/UPS Inverter-This answer is correct because the conditions do not state that the Inverter is bypassed.
A.       480VAC Non-Safeguard NQI bypassing the RPS/UPS inverter B.       480VAC Non-Safeguard bypassing the RPS/UPS inverter C.       TSC UPS Inverter NQI bypassing the RPS/UPS Inverter D.       TSC UPS Inverter bypassing the RPS/UPS Inverter Answer:         C
The conditions also state that the primary Alternate Supply is selected which is the TSC MCC supply. The inverter can be manually bypassed by procedure if the inverter fails to auto swap utilizing the maintenance BYPASS switch. DISTRACTOR TSC UPS Inverter bypassing the RPS/UPS Inverter-This answer is incorrect because the conditions do not state that the Inverter is bypassed.
        /Answer Explanation LMK 2017 ILT NRC JANUARY                       Page: 58 of 374                             17 January 2017
The conditions also state that the Secondary Alternate Supply is selected which is not the TSC MCC supply. The inverter can be manually bypassed by procedure if the inverter fails to auto swap utilizing the maintenance BYPASS switch. DISTRACT OR 480VAC Non-Safeguard bypassing the RPS/UPS Inverter -This answer is partially correct by identifying the correct Secondary Alternate AC supply but is incorrect because the inverter is not Manually bypassed using the maintenance BYPASS switch. LMK 2017 IL T NRG JANUARY Page: 59 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
 
No Points: 1.00 Time to Complete:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO DISTRACTOR       480VAC Non-Safeguard not bypassing the RPS/UPS Inverter - This is incorrect answer because the DC supply is the normal preferred source from 1DB-1 250 VDC MCC.
3 Difficulty:
The primary alternate supply is from the TSC UPS Inverter (1440-C-F) and the Secondary Alternate supply is from Non Safeguard 480 VAC MCC 124A-G-F for the 1B Inverter. Per the conditions stated, The primary alternate is selected on the Inverter AC Feed Selector Switch and the RPS inverter static switch will auto swap to the selected supply which in this case is the primary alternate supply. In this stated condition the AC supply is not bypassing the RPS inverter, but is going through the inverter.
3.00 System ID: 1455428 User-Defined ID: 0# 17 MODIFIED Lesson Plan Objective:
ANSWER           TSC UPS Inverter not bypassing the RPS/UPS Inverter-This answer is correct because the conditions do not state that the Inverter is bypassed. The conditions also state that the primary Alternate Supply is selected which is the TSC MCC supply. The inverter can be manually bypassed by procedure if the inverter fails to auto swap utilizing the maintenance BYPASS switch.
LGSOPS0071  
DISTRACTOR       TSC UPS Inverter bypassing the RPS/UPS Inverter-This answer is incorrect because the conditions do not state that the Inverter is bypassed. The conditions also state that the Secondary Alternate Supply is selected which is not the TSC MCC supply. The inverter can be manually bypassed by procedure if the inverter fails to auto swap utilizing the maintenance BYPASS switch.
.2A Topic: RPS/UPS static inverter RO: 2.8 SRO: 3.1 KA#: 262002 LMK 2017 IL T NRG JANUARY Page: 60 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
DISTRACTOR        480VAC Non-Safeguard bypassing the RPS/UPS Inverter - This answer is partially correct by identifying the correct Secondary Alternate AC supply but is incorrect because the inverter is not Manually bypassed using the maintenance BYPASS switch.
LMK 2017 IL T NRC JANUARY Page: 61 of 374 262002 A3.01 2.8/3.1 Uninterruptable Power Supply (A.C./D.C.)
LMK 2017 ILT NRG JANUARY                   Page: 59 of 374                                   17 January 2017
Ability to monitor automatic operations of the UNINTERRUPTABLE POWER SUPPLY (A.C.ID.C.)
 
including:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 17 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.00 System ID:                       1455428 User-Defined ID:                 0# 17 MODIFIED Lesson Plan Objective:           LGSOPS0071 .2A Topic:                           RPS/UPS static inverter RO:                             2.8 SRO:                             3.1 KA#:                             262002 LMK 2017 ILT NRG JANUARY                       Page: 60 of 374       17 January 2017
Transfer from preferred to alternate source lower 6 41.7 201 O lgs NRC exam 995089 bu cert modified 201 O lgs NRC exam 2010 lgs NRC exam 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO 18 10:1455088 Points: 1.00 Unit 2 is operating at 100% power when a loss of feedwater occurs. RPV water level drops to -43" before recovering to +35". RO Scram actions are complete and ALL automatic scram signals are either clear or bypassed.
 
The RO places the RPS RESET switch to 'GP 1/4' then to 'GP 2/3' positions:  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
-N.o. other operator actions are taken WHICH ONE of the following identifies the status of RPS .and. the SCRAM air header? A. Reset Pressurizing B. Reset NOT Pressurizing  
262002 A3.01 2.8/3.1 Uninterruptable Power Supply (A.C./D.C.) Ability to monitor automatic operations of the UNINTERRUPTABLE POWER SUPPLY (A.C.ID.C.) including:
: c. NOT reset Pressurizing D. NOT reset NOT Pressurizing Answer: B Answer Explanation Because RPV level dropped below -38", ARI also initiated.
Transfer from preferred to alternate source lower 6
Although the RO has successfully reset RPS, the "no other operator actions" statement means that the RO has not reset ARI. Thus, RPS is reset, but the HCU Scram Valves (Inlet/Outlet) are still open; i.e., until ARI is reset, ARI Valves remain open, blocking/venting the scram air header, with no air to the actuators needed to re-close the Scram Valves. A Incorrect plausible to examinee who does not recognize that ARI has not been reset so the scam air header will not pressurize B Correct RPS will reset but the scram air header will not pressurize C incorrect plausible to the examinee who believes placing the RPS reset switch to 'GP 1/4' and 'GP 2/3 positions will allow the air header to pressurize independent of RPS reset D Incorrect plausible to the examinee who believe ARI must be reset in order to reset RPS LMK 2017 ILT NRC JANUARY Page: 62 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
41.7 201 O lgs NRC exam 995089 bu cert modified 201 O lgs NRC exam 2010 lgs NRC exam LMK 2017 ILT NRC JANUARY              Page: 61 of 374                          17 January 2017
No Points: 1.00 Time to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO 18                                               10:1455088                                   Points: 1.00 Unit 2 is operating at 100% power when a loss of feedwater occurs.
2.00 System ID: 1455088 User-Defined ID: Q# 18 BANK Lesson Plan Objective:
RPV water level drops to -43" before recovering to +35".
LLOT0046.4G Topic:
RO Scram actions are complete and ALL automatic scram signals are either clear or bypassed.
Required to Reset a Scram that included RPV level dropping to -38" RO: 3.6 SRO: 3.6 KA#: 212000 A.07 LMK 2017 IL T NRC JANUARY Page: 63 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
The RO places the RPS RESET switch to 'GP 1/4' then to 'GP 2/3' positions:
LMK 2017 IL T NRC JANUARY Page: 64 of 374 RO 2 212000 A3.07 3.6/3.6 212000 Reactor Protection System Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including:
        - N.o. other operator actions are taken WHICH ONE of the following identifies the status of RPS .and. the SCRAM air header?
SCRAM air header bank1244449,553971 minor revision to match KA 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 19 ID: 1455570 Points: 1.00 Unit 2 is operating at 85% power with both Recirc Pumps in service. l&C discovers an error in the recently completed  
A.     Reset Pressurizing B.     Reset NOT Pressurizing
'B' Recirc Loop (Drive) Flow surveillance:  
: c.     NOT reset Pressurizing D.     NOT reset NOT Pressurizing Answer:         B Answer Explanation Because RPV level dropped below -38", ARI also initiated. Although the RO has successfully reset RPS, the "no other operator actions" statement means that the RO has not reset ARI.
-Indicated  
Thus, RPS is reset, but the HCU Scram Valves (Inlet/Outlet) are still open; i.e., until ARI is reset,
'B' Recirc Loop Flow is LOWER than aci.u.al.
        ~he ARI Valves remain open, blocking/venting the scram air header, with no air to the actuators needed to re-close the Scram Valves.
flow As a result of this discovery, which of the following APRM, Simulated Thermal Power (STP) trip setpoints are affected, (if any)? A. 1 ,2,3, and 4 B. 1 and 3 only C. 2 and 4 only D. No APRM STP trip setpoints are affected Answer: A lAnswer Explanation IA is correct the examinee must recall that A and B recirc loop flows are summed and used by all IAPRM STP and displayed on the ODA's B Incorrect plausible to the examinee who believes B recirc loop only provides input to 2 of 4 iAPRM STP indication on the ODA C incorrect plausible to the examinee who believes B recirc loop only provides input to 2 of 4 IAPRM STP indication on the ODA D Incorrect plausible to the examinee who does not recall how APRM STP is calculated LMK 2017 IL T NRC JANUARY Page: 65 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 19 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
A   Incorrect plausible to examinee who does not recognize that ARI has not been reset so the scam air header will not pressurize B   Correct RPS will reset but the scram air header will not pressurize C   incorrect plausible to the examinee who believes placing the RPS reset switch to 'GP 1/4' and 'GP 2/3 positions will allow the air header to pressurize independent of RPS reset D   Incorrect plausible to the examinee who believe ARI must be reset in order to reset RPS LMK 2017 ILT NRC JANUARY                         Page: 62 of 374                                 17 January 2017
No Points: 1.00 Time to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 18 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1455088 User-Defined ID:                 Q# 18 BANK Lesson Plan Objective:           LLOT0046.4G
2.00 System ID: 1455570 User-Defined ID: Q# 19 NEW Lesson Plan Objective:
                                        ~ctions  Required to Reset a Scram that included RPV level Topic:
LGSOPS007 48.138 Topic: ODA setpoint shange in core flow RO: 3.6 SRO: 3.8 KA#: 215005 A4.06 LMK 2017 IL T NRG JANUARY Page: 66 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
dropping to -38" RO:                             3.6 SRO:                             3.6 KA#:                             212000 A.07 LMK 2017 ILT NRC JANUARY                       Page: 63 of 374                             17 January 2017
LMK 2017 IL T NRC JANUARY Page: 67 of 374 2 1 215005 A4.06 3.6/3.8 Average Power Range Monitor/Local Power Range Monitor System Ability to manually operate and/or monitor in the control room: Verification of proper functionin o erabilit 4 0 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 20 ID: 1455452 Points: 1.00 Unit 1 is in OPCON 1 with the following conditions:
 
* 1 B SLC pump is deenergized and blocked for repair
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
RO 2
212000 A3.07 3.6/3.6 212000 Reactor Protection System Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including: SCRAM air header bank1244449,553971 minor revision to match KA LMK 2017 ILT NRC JANUARY              Page: 64 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 19                                               ID: 1455570                                   Points: 1.00 Unit 2 is operating at 85% power with both Recirc Pumps in service.
l&C discovers an error in the recently completed 'B' Recirc Loop (Drive) Flow surveillance:
        - Indicated 'B' Recirc Loop Flow is LOWER than aci.u.al. flow As a result of this discovery, which of the following APRM, Simulated Thermal Power (STP) trip setpoints are affected, (if any)?
A.       1,2,3, and 4 B.       1 and 3 only C.       2 and 4 only D.       No APRM STP trip setpoints are affected Answer:           A lAnswer Explanation IA is correct the examinee must recall that A and B recirc loop flows are summed and used by all IAPRM STP and displayed on the ODA's B Incorrect plausible to the examinee who believes B recirc loop only provides input to 2 of 4 iAPRM STP indication on the ODA C incorrect plausible to the examinee who believes B recirc loop only provides input to 2 of 4 IAPRM STP indication on the ODA D Incorrect plausible to the examinee who does not recall how APRM STP is calculated LMK 2017 ILT NRC JANUARY                         Page: 65 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 19 Info Question Type:                   Multiple Choice Status:                         Active
        ~lwavs select on test?           No
        ~uthorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1455570 User-Defined ID:                 Q# 19 NEW Lesson Plan Objective:           LGSOPS00748.138 Topic:                           ODA setpoint shange in core flow RO:                             3.6 SRO:                             3.8 KA#:                             215005 A4.06 LMK 2017 ILT NRG JANUARY                       Page: 66 of 374           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 1
215005 A4.06 3.6/3.8 Average Power Range Monitor/Local Power Range Monitor System Ability to manually operate and/or monitor in the control room:
Verification of proper functionin o erabilit 4
0 LMK 2017 ILT NRC JANUARY              Page: 67 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 20                                               ID: 1455452                                     Points: 1.00 Unit 1 is in OPCON 1 with the following conditions:
* 1B SLC pump is deenergized and blocked for repair
* Division II D.C. has experienced a fault and is deenergized
* Division II D.C. has experienced a fault and is deenergized
* A feedwater transient caused reactor water level to drop to +5 inches before being restored to + 35inches
* A feedwater transient caused reactor water level to drop to +5 inches before being restored to +
* All RO SCRAM actions have been completed per OT-200 attachment  
35inches
# 1
* All RO SCRAM actions have been completed per OT-200 attachment # 1
* Reactor power remains at 100% WHICH ONE of the following identifies the status of RWCU System isolation valves 3 minutes later? A. B. C. D. INBOARD ISOLATION VALVE HV-44-1 EOOl Open Closed Open Closed Answer: D !Answer Explanation OUTBOARD ISOLATION VALVE HV-44-1 F004 Open Closed Closed Open A Incorrect plausible to the examinee who recalls that without Div II DC that Div II ARCS is INOP but incorrectly believes that both divisions of ARCS are required to close either RWCU isolation valve. B Incorrect plausible to the examinee who who does not recall that Div I ARCS uses B SBLC pp logic to close the HV-44-1 F004 C Incorrect plausible to the examine who reverse Div I and Div II ARCS actions D Correct although DIV 1 ARCS normally closes both RWCU isol valves it does so through the SLC pump logic. with the B SLC pump deenergized the outboard valve will not close. The distractors are plausible to the examinee who does not properly recall how SLC in conjunction with ARCS work to isolate RWCU. LMK 2017 IL T NRC JANUARY Page: 68 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 20 Info Question T e: Status: lete: LMK 2017 IL T NRG JANUARY ILT 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 4 3.00 1455452 Q#20 NEW LGSOPS0048.08A SLC RWCU isolation 3.9 3.9 Page: 69 of 374 211000 A4.06 3.9/3.9 Standby Liquid Control System Ability to manually operate and/or monitor in the control room: RWCU *Rev;. #: 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 70 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 21 ID: 1455676 Points: 1.00 Plant conditions are as follows;
* Reactor power remains at 100%
WHICH ONE of the following identifies the status of RWCU System isolation valves 3 minutes later?
INBOARD ISOLATION VALVE                      OUTBOARD ISOLATION VALVE HV-44-1 EOOl                                 HV-44-1 F004 A.        Open                                        Open B.      Closed                                        Closed C.        Open                                         Closed D.      Closed                                        Open Answer:         D
        !Answer Explanation A   Incorrect plausible to the examinee who recalls that without Div II DC that Div II ARCS is INOP but incorrectly believes that both divisions of ARCS are required to close either RWCU isolation valve.
B   Incorrect plausible to the examinee who who does not recall that Div I ARCS uses B SBLC pp logic to close the HV-44-1 F004 C   Incorrect plausible to the examine who reverse Div I and Div II ARCS actions D   Correct although DIV 1 ARCS normally closes both RWCU isol valves it does so through the SLC pump logic. with the B SLC pump deenergized the outboard valve will not close.
The distractors are plausible to the examinee who does not properly recall how SLC in conjunction with ARCS work to isolate RWCU.
LMK 2017 ILT NRC JANUARY                         Page: 68 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 20 Info Question T e:              Multi le Choice Status:                    Active No No 1.00 lete:        4 3.00 1455452 Q#20 NEW LGSOPS0048.08A SLC RWCU isolation 3.9 3.9 211000 A4.06 3.9/3.9 Standby Liquid Control System Ability to manually operate and/or monitor in the control room: RWCU
                                                                                  *Rev;.
LMK 2017 ILT NRG JANUARY                  Page: 69 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 70 of 374         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 21                                                   ID: 1455676                                       Points: 1.00 Plant conditions are as follows;
* Unit 1 is at 50% power, shutting down due to a fuel failure.
* Unit 1 is at 50% power, shutting down due to a fuel failure.
* Unit 2 is in OPCON 5 with refueling activities in progress with secondary containment set on the refuel floor.
* Unit 2 is in OPCON 5 with refueling activities in progress with secondary containment set on the refuel floor.
* An unisolable steam leak develops in the UNIT 1 reactor enclosure.
* An unisolable steam leak develops in the UNIT 1 reactor enclosure.
* Unit 1 reactor enclosure radiation levels rise to 2.3 mR/hr Regarding the reactor enclosure and the refuel floor, which of the following describes the Zones SBGT will maintain at a negative pressure and the reason for the initiation of SBGT? Zones SBGT will maintain negative A. Unit 1 reactor enclosure ONLY B. Unit 1 reactor enclosure ONLY C. Unit 1 reactor enclosure and Refuel floor D. Unit 1 reactor enclosure and Refuel floor Answer: A Answer Explanation Reason for SBGT initiation Limit iodine and particulate concentration in gases, prior to discharge Limit particulate concentration in gases ONLY, prior to discharge Limit iodine and particulate concentration in gases, prior to discharge Limit particulate concentration in gases ONLY, prior to discharge A Correct Reactor HVAC isolates at 1.35 mr/h.although refuel floor containment is set, only when Zones are crosstied will a reactor HVAC isolation also isolate the refuel floor. The purpose of the SBGT filters per the Design basis document L-S-32 is The SGTS/RERS filters iodine and particulate concentrations in gases potentially present within the Secondary Containment prior to discharge to the environment via the North Stack. B Incorrect Limit particulate only is incorrect but plausible to the examinee who does not recall the purpose of the charcoal filters C incorrect plausible to the examinee who recognizes that the radiation levels are above the refuel floor setpoint, but either does not recall the crosstie logic or believe that hi reactor radiation will isolate the refuel floor as long as the zone is established D incorrect plausible to the examinee who recognizes that the radiation levels are above the refuel floor setpoint, but either does not recall the crosstie logic or believe that hi reactor radiation will isolate the refuel floor as long as the zone is established and does not recall the purpose of the charcoal filters LMK 2017 IL T NRC JANUARY Page: 71 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 21 Info Question T e: Multi le Choice Status: Active No No 1.00 3 3.00 1455676 Q#21NEW LOT0200.01 C SBGT initiation 3.9 4.0 261000 2.1.27 Comments:
* Unit 1 reactor enclosure radiation levels rise to 2.3 mR/hr Regarding the reactor enclosure and the refuel floor, which of the following describes the Zones SBGT will maintain at a negative pressure and the reason for the initiation of SBGT?
LMK 2017 ILT NRC JANUARY Page: 72 of 374 RO 2 261000 2.1.27 3.9/4.0 Standby Gas Treatment System Knowledge of system ur ose and/or function.
Zones SBGT will maintain negative                 Reason for SBGT initiation A.         Unit 1 reactor enclosure ONLY                   Limit iodine and particulate concentration in gases, prior to discharge B.        Unit 1 reactor enclosure ONLY                  Limit particulate concentration in gases ONLY, prior to discharge C.        Unit 1 reactor enclosure and Refuel floor      Limit iodine and particulate concentration in gases, prior to discharge D.        Unit 1 reactor enclosure and Refuel floor      Limit particulate concentration in gases ONLY, prior to discharge Answer:            A Answer Explanation A    Correct Reactor HVAC isolates at 1.35 mr/h.although refuel floor containment is set, only when Zones are crosstied will a reactor HVAC isolation also isolate the refuel floor. The purpose of the SBGT filters per the Design basis document L-S-32 is The SGTS/RERS filters iodine and particulate concentrations in gases potentially present within the Secondary Containment prior to discharge to the environment via the North Stack.
17 January 2017 EXAMINATION ANSWER KEY IL T 15*01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 73 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 22 10:1649592 Points: 1.00 Unit 1 is operating at 100% power when emergent maintenance on the SLC tank Main Control Room level indication is required.
B   Incorrect Limit particulate only is incorrect but plausible to the examinee who does not recall the purpose of the charcoal filters C   incorrect plausible to the examinee who recognizes that the radiation levels are above the refuel floor setpoint, but either does not recall the crosstie logic or believe that hi reactor radiation will isolate the refuel floor as long as the zone is established D   incorrect plausible to the examinee who recognizes that the radiation levels are above the refuel floor setpoint, but either does not recall the crosstie logic or believe that hi reactor radiation will isolate the refuel floor as long as the zone is established and does not recall the purpose of the charcoal filters LMK 2017 ILT NRC JANUARY                             Page: 71 of 374                                   17 January 2017
The level indication is taken out of service for maintenance by isolating and venting the air. WHICH ONE of the following describes the SLC alarm that will be received and the availability of the SLC pumps in the above configuration?
 
ALARM SLC Pump Availability A. High level available B. Low level NOT available  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 21 Info Question T   e:         Multi le Choice Status:                 Active No No 1.00 3
: c. High level NOT available D. Low level available Answer: D Answer Explanation  
3.00 1455676 Q#21NEW LOT0200.01 C SBGT initiation 3.9 4.0 261000 2.1.27 Comments:
!To answer the question the candidate must understand the operation of the SLC tank bubbler and how the bubbler will fail when air is removed. With air removed from the bubbler, level indication  
RO 2
/Will fail low. Also the candidate must know that the bubbler is for indication only and has no effect on the the operation of the SLC pumps and SLC system operability.
261000 2.1.27 3.9/4.0 Standby Gas Treatment System Knowledge of system ur ose and/or function.
Higher back pressure equals higher tank level. with air isolated to the bubbler tank level indication in the MCR will read O IA Incorrect level will indicate lower B incorrect the pumps trip on low tank level but not from the MCR indication that uses a bubbler air system for indication C Incorrect With air removed from the bubbler, level indication will fail low. the pumps trip on low tank level but not from the MCR indication that uses a bubbler air system for indication D Correct LMK 2017 IL T NRG JANUARY Page: 74 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 22 Info Question Type: Multiple Choice Status: Active select on test? No Authorized for practice?
LMK 2017 ILT NRC JANUARY              Page: 72 of 374                        17 January 2017
No Points: 1.00 Time to Complete:
 
6 Difficulty:
EXAMINATION ANSWER KEY ILT 15*01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 73 of 374       17 January 2017
2.00 System ID: 1649592 User-Defined ID: Q#22 NEW Lesson Plan Objective:
 
LLOR1102E Topic: SLC operability RO: 3.1 SRO: 4.2 KA#: 211000 2.2.36 LMK 2017 IL T NRG JANUARY Page: 75 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 22                                               10:1649592                                     Points: 1.00 Unit 1 is operating at 100% power when emergent maintenance on the SLC tank Main Control Room level indication is required.
LMK 2017 IL T NRC JANUARY Page: 76 of 374 2 1 211000 2.2.36 3.1/4.2 Standby Liquid Control System Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for o erations.
The level indication is taken out of service for maintenance by isolating and venting the air.
low 41.10 22 Bank 906982 modified 211000A1.10 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 23 ID: 1601488
WHICH ONE of the following describes the SLC alarm that will be received and the availability of the SLC pumps in the above configuration?
ALARM                                   SLC Pump Availability A.         High level                                 available B.         Low level                                   NOT available
: c.         High level                                 NOT available D.         Low level                                   available Answer:           D Answer Explanation
        !To answer the question the candidate must understand the operation of the SLC tank bubbler and how the bubbler will fail when air is removed. With air removed from the bubbler, level indication
        /Will fail low. Also the candidate must know that the bubbler is for indication only and has no effect on the the operation of the SLC pumps and SLC system operability.
Higher back pressure equals higher tank level. with air isolated to the bubbler tank level indication in the MCR will read O IA Incorrect level will indicate lower B incorrect the pumps trip on low tank level but not from the MCR indication that uses a bubbler air system for indication C Incorrect With air removed from the bubbler, level indication will fail low. the pumps trip on low tank level but not from the MCR indication that uses a bubbler air system for indication D Correct LMK 2017 ILT NRG JANUARY                         Page: 74 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 22 Info Question Type:                   Multiple Choice Status:                         Active
        ~lways select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               6 Difficulty:                     2.00 System ID:                       1649592 User-Defined ID:                 Q#22 NEW Lesson Plan Objective:           LLOR1102E Topic:                           SLC operability RO:                             3.1 SRO:                             4.2 KA#:                             211000 2.2.36 LMK 2017 ILT NRG JANUARY                       Page: 75 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 1
211000 2.2.36 3.1/4.2 Standby Liquid Control System Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for o erations.
low 41.10 22 Bank 906982 modified 211000A1.10 LMK 2017 ILT NRC JANUARY            Page: 76 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 23                                                 ID: 1601488
* Points: 1.00 Unit 1 is in OPCON 3 with the following
* Points: 1.00 Unit 1 is in OPCON 3 with the following
* Reactor pressure is 500 psi
* Reactor pressure is 500 psi
* Drywall purge is in progress with the OA Drywall Purge fan through the OA SBGT filter
* Drywall purge is in progress with the OA Drywall Purge fan through the OA SBGT filter
* Maintenance has entered the drywall Which of the following describes the maximum allowable suppression pool to drywall differential pressure and what is the basis for this requirement?
* Maintenance has entered the drywall Which of the following describes the maximum allowable suppression pool to drywall differential pressure and what is the basis for this requirement?
Differential pressure A. 0.5 PSID B. 0.5 PSID C. 5.0 PSID D. 5.0 PSID Answer: A !Answer Explanation Basis tor this limit To prevent suppression pool nitrogen from entering the drywall To prevent exceeding the maximum drywall floor differential design pressure To prevent suppression pool nitrogen from entering the drywall To prevent exceeding the maximum drywall floor differential design pressure A Correct per warning in S57.5.B The Primary Containment Vacuum Relief Valves are designed to lift at 0.5 psid to relieve Suppression Pool pressure to the Drywall. For personnel access to the Drywall, with the Suppression Pool inerted with N2, Suppression Pool/Drywell differential pressure must be maintained below 0.5 psid to prevent Suppression Pool inerted atmosphere from flooding the Drywell. B Incorrect 5.0 is the containment external to internal limit plausible to the examinee who contuses internal to external pressure with OW to supp pool. C Incorrect plausible to the examinee who confuses internal to external pressure with OW to supp pool. bases D Incorrect 5.0 is the containment external to internal limit LMK 2017 ILT NRC JANUARY Page: 77 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
Differential pressure                       Basis tor this limit A.       0.5 PSID                                       To prevent suppression pool nitrogen from entering the drywall B.        0.5 PSID                                        To prevent exceeding the maximum drywall floor differential design pressure C.        5.0 PSID                                        To prevent suppression pool nitrogen from entering the drywall D.        5.0 PSID                                        To prevent exceeding the maximum drywall floor differential design pressure Answer:          A
No Points: 1.00 Time to Complete:
        !Answer Explanation A   Correct per warning in S57.5.B The Primary Containment Vacuum Relief Valves are designed to lift at 0.5 psid to relieve Suppression Pool pressure to the Drywall. For personnel access to the Drywall, with the Suppression Pool inerted with N2, Suppression Pool/Drywell differential pressure must be maintained below 0.5 psid to prevent Suppression Pool inerted atmosphere from flooding the Drywell.
3 Difficulty:
B   Incorrect 5.0 is the containment external to internal limit plausible to the examinee who contuses internal to external pressure with OW to supp pool.
2.00 System ID: 1601488 User-Defined ID: Q#23 NEW Lesson Plan Objective:
C   Incorrect plausible to the examinee who confuses internal to external pressure with OW to supp pool. bases D   Incorrect 5.0 is the containment external to internal limit LMK 2017 ILT NRC JANUARY                           Page: 77 of 374                                   17 January 2017
LOT0060.4D Topic: ourge containment DP RO: 2.9 SRO: 3.2 KA#: 261000 A4.05 LMK 2017 IL T NRG JANUARY Page: 78 of 374 17 January 2017 EXAMINATION ANSWER KEY Comments:
 
LMK 2017 ILT NRC JANUARY ILT 15-01 January 2017 NRC test SRO 2 261000 A4.05 2.9/3.2 Standby Gas Treatment System Ability to manually operate and/or monitor in the control room: Drywell to suppression chamber/torus  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 23 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1601488 User-Defined ID:               Q#23 NEW Lesson Plan Objective:           LOT0060.4D Topic:                           ourge containment DP RO:                             2.9 SRO:                             3.2 KA#:                             261000 A4.05 LMK 2017 ILT NRG JANUARY                       Page: 78 of 374       17 January 2017
,,,,"'''''""'', 1 differential ressure: Mark-1,II Page: 79 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 80 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 24 ID: 1455288 Points: 1.00 Plant conditions are as follows;
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 261000 A4.05 2.9/3.2 Standby Gas Treatment System Ability to manually operate and/or monitor in the control room: Drywell to suppression chamber/torus
                                                        ,,,,"'''''""'',1 differential ressure: Mark-1,II LMK 2017 ILT NRC JANUARY              Page: 79 of 374                                       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 80 of 374         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 24                                             ID: 1455288                                 Points: 1.00 Plant conditions are as follows;
* Control enclosure HVAC is in service with the A Safeguard Battery room exhaust fan OAV124 in service
* Control enclosure HVAC is in service with the A Safeguard Battery room exhaust fan OAV124 in service
* Unit 1 Safeguard Battery room exhaust fan supply damper HD-78-90B has failed closed Which of the following describes the plant response and the reason for this response?
* Unit 1 Safeguard Battery room exhaust fan supply damper HD-78-90B has failed closed Which of the following describes the plant response and the reason for this response?
A. B. c. D. PLANT RESPONSE B Safeguard Battery room exhaust fan OBV124 Starts B Safeguard Battery room exhaust fan OBV124 Starts Connecting damper HD-78-092B Unit 1 battery room to Emergency Switchgear and Battery Room Supply Air will open Connecting damper HD-78-092B Unit 1 battery room to Emergency Switchgear and Battery Room Supply Air will open Answer: D !Allswer Explanation LMK 2017 ILT NRG JANUARY Page: 81 of 374 REASON FOR THIS RESPONSE Maintain battery room temperature Reduce Hydrogen buildup Maintain battery room temperature Reduce Hydrogen buildup 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Lesson plan LGSOPS0078
PLANT RESPONSE                              REASON FOR THIS RESPONSE A.       B Safeguard Battery room exhaust fan         Maintain battery room temperature OBV124 Starts B.      B Safeguard Battery room exhaust fan         Reduce Hydrogen buildup OBV124 Starts
* if both battery exhaust fans trip, or any of the battery exhaust fan inlet dampers are less than full open, dampers will open connecting the battery room exhaust duct to the emergency switchgear and battery room supply fan suction. This ensures hydrogen does not accumulate in the battery rooms. UFSAR 9.5-13 irhe exhaust ducts from the Class 1 E battery rooms are provided with safety-grade isolation dampers in both branches of duct-work leading to the battery room exhaust fans and to the emergency switchgear and battery room supply air fan cabinets.
: c.      Connecting damper HD-78-092B Unit 1         Maintain battery room temperature battery room to Emergency Switchgear and Battery Room Supply Air will open D.      Connecting damper HD-78-092B Unit 1         Reduce Hydrogen buildup battery room to Emergency Switchgear and Battery Room Supply Air will open Answer:           D
The dampers in the duct-work leading to the exhaust fans are provided with safety-related position switches which activate the dampers in the duct-work leading to the supply air fan cabinets.
        !Allswer Explanation LMK 2017 ILT NRG JANUARY                       Page: 81 of 374                               17 January 2017
In the event of closure of any of dampers leading to the exhaust fans, the dampers in the duct-work from the battery rooms of affected reactor unit and leading to the air supply fan cabinets will automatically open, thereby establishing recirculation air flow through the affected battery rooms. This re-establishment prevents accumulation of hydrogen above safe limits. IA is incorrect plausible to the examinee who does not recall that all battery rooms tie into a common header there by thinking an A/C damper closure would start the B tan. also the examinee does not recall the bases for reciculation.
 
B is incorrect plausible to the examinee who does not recall that all battery rooms tie into a common header there by thinking an A/C damper closure would start the B fan. C Incorrect plausible to the examinee who does not recall the bases for reciculation.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Lesson plan LGSOPS0078
D correct for the reasons stated above. LMK 2017 IL T NRC JANUARY Page: 82 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Question 24 Info k:luestion Tvpe: Multiple Choice Status: Active IAlwavs select on test? No Authorized for practice?
* if both battery exhaust fans trip, or any of the battery exhaust fan inlet dampers are less than full open, dampers will open connecting the battery room exhaust duct to the emergency switchgear and battery room supply fan suction. This ensures hydrogen does not accumulate in the battery rooms.
No Points: 1.00 Time to Complete:
UFSAR 9.5-13 irhe exhaust ducts from the Class 1E battery rooms are provided with safety-grade isolation dampers in both branches of duct-work leading to the battery room exhaust fans and to the emergency switchgear and battery room supply air fan cabinets. The dampers in the duct-work leading to the exhaust fans are provided with safety-related position switches which activate the dampers in the duct-work leading to the supply air fan cabinets. In the event of closure of any of
3 Difficulty:
        ~he dampers leading to the exhaust fans, the dampers in the duct-work from the battery rooms of
2.00 Svstem ID: 1455288 User-Defined ID: 0#24 NEW Lesson Plan Objective:
        ~he affected reactor unit and leading to the air supply fan cabinets will automatically open, thereby establishing recirculation air flow through the affected battery rooms. This re-establishment prevents accumulation of hydrogen above safe limits.
LGSOPS0078.1 C Topic: Battery H2 buildup RO: 2.6 SRO: 2.9 KA#: 263000 K5.01 LMK 2017 IL T NRC JANUARY Page: 83 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
IA is incorrect plausible to the examinee who does not recall that all battery rooms tie into a common header there by thinking an A/C damper closure would start the B tan. also the examinee does not recall the bases for reciculation.
LMK 2017 IL T NRG JANUARY Page: 84 of 374 2 263000 K5.01 2.6/2.9 D.C. Electrical Distribution Knowledge of the operational implications of the following concepts as they apply to D.C. ELECTRICAL DISTRIBUTION  
B is incorrect plausible to the examinee who does not recall that all battery rooms tie into a common header there by thinking an A/C damper closure would start the B fan.
: Hydrogen generation during batter char in lower 6 41.5 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 25 ID: 1455268'.
C Incorrect plausible to the examinee who does not recall the bases for reciculation.
Points: 1.00: Unit 1 plant conditions are as follows: HPCI is in service for RPV pressure control (CST to CST) FIC-055-1 R600 "HPCI FLOW CONTROL VALVE AUTO/MAN switch" is in AUTO HV-55-1 FOOS "HPCI, Test Loop Shutoff" is throttled to maintain pump discharge pressure 150 psig over Reactor pressure.
D correct for the reasons stated above.
The RO throttles HV-55-1 FOOS in the closed direction for one second WHICH ONE of the following describes HPCI turbine speed and flow rate five minutes later, as compared to conditions prior to throttling HV-55-1 FOOS? HPCI Turbine Speed Flow rate A. No change Higher B. Higher No change c. Lower No change D. No change Lower Answer: B Answer Explanation B Correct: Higher/ No change: With Flow Controller in AUTO, system flow is maintained constant.
LMK 2017 ILT NRC JANUARY                           Page: 82 of 374                               17 January 2017
IF FOOS is throttled closed HPCI speed will need to increase to maintain the same flow A Incorrect:
 
No change/Higher:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 24 Info k:luestion Tvpe:                 Multiple Choice Status:                         Active IAlwavs select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 Svstem ID:                       1455288 User-Defined ID:                 0#24 NEW Lesson Plan Objective:           LGSOPS0078.1 C Topic:                           Battery H2 buildup RO:                             2.6 SRO:                             2.9 KA#:                             263000 K5.01 LMK 2017 ILT NRC JANUARY                       Page: 83 of 374       17 January 2017
plausible to the examinee who believe speed is maintained constant and that flow will increase with a higher DP across the valve C Incorrect:
 
Lower/No change: plausible to the examinee who believe throttling the 1 FOOS will lower pump speed D Incorrect:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
No Change/Lower:
2 263000 K5.01     2.6/2.9 D.C. Electrical Distribution Knowledge of the operational implications of the following concepts as they apply to D.C. ELECTRICAL DISTRIBUTION :
Flow Controller is in Auto, maintaining system flow constant.
Hydrogen generation during batter char in lower 6
plausible to the examinee who believes AUTO maintains speed constant LMK 2017 IL T NRC JANUARY Page: 85 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 25 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
41.5 LMK 2017 ILT NRG JANUARY            Page: 84 of 374                          17 January 2017
No Points: 1.00 !Time to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 25                                             ID: 1455268'.                               Points: 1.00:
2.50 System ID: 1455268 User-Defined ID: Q# 25 BANK Lesson Plan Objective:
Unit 1 plant conditions are as follows:
LOT-340.12 HPCI !Topic: Unit 1 plant conditions are as follows: u HPCI is in service for RPV pressure control (CST to CST) L RO: 3.8 SRO: 3.7 KA#: 206000 A1 .06 LMK 2017 IL T NRC JANUARY Page: 86 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01January2017 NRC test SRO Comments:
HPCI is in service for RPV pressure control (CST to CST)
LMK 2017 IL T NRC JANUARY Page: 87 of 374 RO 2 1 206000A1.06 3.8/3.7 High Pressure Coolant Injection System Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including:
FIC-055-1 R600 "HPCI FLOW CONTROL VALVE AUTO/MAN switch" is in AUTO HV-55-1 FOOS "HPCI, Test Loop Shutoff" is throttled to maintain pump discharge pressure 150 psig over Reactor pressure.
S stem flow: BWR-2,3,4 S55.1.D, note Ste 4.4.3 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 26 ID: 1455689 Points: 1.00 Unit 2 is operating normally at 80% power when a LOCA occurs. -A LOCA signal is generated for all four divisions of ECCS WHICH ONE of the following describes the RHR pump starting sequence?
The RO throttles HV-55-1 FOOS in the closed direction for one second WHICH ONE of the following describes HPCI turbine speed and flow rate five minutes later, as compared to conditions prior to throttling HV-55-1 FOOS?
A. All Unit 2 RHR pumps will start immediately  
HPCI Turbine Speed             Flow rate A.     No change                         Higher B.     Higher                           No change
: 8. All Unit 2 RHR pumps will start after a 7 second time delay C. "2A" and "28" RHR pumps start immediately, "2C" and "20" RHR pumps start after a 5 second time delay 0. "2C" and "20" RHR pumps start immediately, "2A" and "28" RHR pumps start after a 5 second time delay Answer: 0 Answer Explanation The RHR pumps start on a LOCA signal a) With offsite power pumps C&O start immediately and A&8 start 5 seconds later. b) Without off-site power each pump starts when the associated diesel output breaker shuts. A Incorrect, plausible to the examinee who confuses sequence with RHR pump start on a loss of offsite power 8 Incorrect, plausible to the examinee who confuses sequence with Core Spray initiation on a loss of off site power C Incorrect plausible to the examinee who reverses the dedicated LPCI pp LMK 2017 IL T NRG JANUARY Page: 88 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 26 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
: c.     Lower                             No change D.     No change                         Lower Answer:           B Answer Explanation B Correct: Higher/ No change: With Flow Controller in AUTO, system flow is maintained constant. IF FOOS is throttled closed HPCI speed will need to increase to maintain the same flow A Incorrect: No change/Higher: plausible to the examinee who believe speed is maintained constant and that flow will increase with a higher DP across the valve C Incorrect: Lower/No change: plausible to the examinee who believe throttling the 1FOOS will lower pump speed D Incorrect: No Change/Lower: Flow Controller is in Auto, maintaining system flow constant.
No Points: 1.00 rnme to Complete:
plausible to the examinee who believes AUTO maintains speed constant LMK 2017 ILT NRC JANUARY                         Page: 85 of 374                               17 January 2017
5 Difficulty:
 
2.00 System ID: 1455689 User-Defined ID: Q# 26 BANK Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 25 Info Question Type:                   Multiple Choice Status:                         Active
LOT0051.07 rropic: offsite power is available  
        ~lwavs select on test?           No
-RPV pressure is 360 psig -drywell pressure reaches 1.68 psig describ RO: 4.0 SRO: 3.9 KA#: 203000 A3.02 LMK 2017 IL T NRC JANUARY Page: 89 of 374 17 January 2017 EXAMINATION ANSWER KEY Comments:
        ~uthorized for practice?         No Points:                         1.00
LMK 2017 IL T NRC JANUARY IL T 15-01 January 2017 NRC test SRO Lesson Plan: LOR-9305-B, Obj. 2 LLOR0101 C, Obj. 4 RO 2 203000 A3.02 4.0/3.9 RHR/LPCI:
        !Time to Complete:               3 Difficulty:                     2.50 System ID:                       1455268 User-Defined ID:                 Q# 25 BANK Lesson Plan Objective:           LOT-340.12 HPCI Unit 1 plant conditions are as follows: u HPCI is in service for
Injection Mode (Plant Specific)
        !Topic:
Ability to monitor automatic operations of the RHR/LPCI:
RPV pressure control (CST to CST) L RO:                             3.8 SRO:                             3.7 KA#:                             206000 A1 .06 LMK 2017 ILT NRC JANUARY                       Page: 86 of 374                                 17 January 2017
INJECTION MODE (PLANT SPECIFIC) including:
 
Pum start 2 41.7 E11-1040 bank 554543 bank 554543 bank 554543 KIA Catalog: 203000 K4.01 4.2/4.2 JT A 2030020101 Page: 90 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 27 ID: 1478356 Points: 1.QQ, Unit 1 is operating at 100% power with the following:
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:
* 1D01 TURBINE ENCLOSURE 250V DC MOTOR CONTROL CENTER (10-D125}
RO 2
has been deenergized for 2 hours A malfunction on the main turbine lube oil system results in the following:
1 206000A1.06 3.8/3.7 High Pressure Coolant Injection System Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including:
S stem flow: BWR-2,3,4 S55.1.D, note Ste 4.4.3 LMK 2017 ILT NRC JANUARY            Page: 87 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 26                                                 ID: 1455689                               Points: 1.00 Unit 2 is operating normally at 80% power when a LOCA occurs.
        - A LOCA signal is generated for all four divisions of ECCS WHICH ONE of the following describes the RHR pump starting sequence?
A.         All Unit 2 RHR pumps will start immediately
: 8.       All Unit 2 RHR pumps will start after a 7 second time delay C.         "2A" and "28" RHR pumps start immediately, "2C" and "20" RHR pumps start after a 5 second time delay
: 0.       "2C" and "20" RHR pumps start immediately, "2A" and "28" RHR pumps start after a 5 second time delay Answer:             0 Answer Explanation The RHR pumps start on a LOCA signal a) With offsite power pumps C&O start immediately and A&8 start 5 seconds later.
b) Without off-site power each pump starts when the associated diesel output breaker shuts.
A Incorrect, plausible to the examinee who confuses sequence with RHR pump start on a loss of offsite power 8 Incorrect, plausible to the examinee who confuses sequence with Core Spray initiation on a loss of off site power C Incorrect plausible to the examinee who reverses the dedicated LPCI pp LMK 2017 ILT NRG JANUARY                         Page: 88 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 26 Info Question Type:                 Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 rnme to Complete:               5 Difficulty:                     2.00 System ID:                       1455689 User-Defined ID:                 Q# 26 BANK Lesson Plan Objective:           LOT0051.07 offsite power is available - RPV pressure is 360 psig - drywell rropic:
pressure reaches 1.68 psig describ RO:                             4.0 SRO:                             3.9 KA#:                             203000 A3.02 LMK 2017 ILT NRC JANUARY                       Page: 89 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
RO 2
203000 A3.02 4.0/3.9 RHR/LPCI: Injection Mode (Plant Specific) Ability to monitor automatic operations of the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) including:
Pum start 2
41.7 E11-1040           J!:l~'
                                                                                      **~"'
bank 554543 bank 554543 bank 554543 Lesson Plan: LOR-9305-B, Obj. 2 LLOR0101 C, Obj. 4 KIA Catalog: 203000 K4.01 4.2/4.2 JT A 2030020101 LMK 2017 ILT NRC JANUARY              Page: 90 of 374                              17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 27                                             ID: 1478356                                 Points: 1.QQ, Unit 1 is operating at 100% power with the following:
* 1D01 TURBINE ENCLOSURE 250V DC MOTOR CONTROL CENTER (10-D125} has been deenergized for 2 hours A malfunction on the main turbine lube oil system results in the following:
* Main Shaft Oil Pump (MSOP) discharge pressure of 150 psig
* Main Shaft Oil Pump (MSOP) discharge pressure of 150 psig
* Turning gear oil pump (TGOP) discharge pressure of 10 psig WHICH ONE of the following identifies the status of the Turning Gear Oil Pump (TGOP) and Emergency Bearing Oil Pump (EBOP)? I.GQE A. Running B. Running c. Not Running D. Not Running Answer: B Answer Explanation EBOP is powered form non safeguard DC. ITGOP is powered from D114-G-D .EBQE Running Not Running Not Running Running TGOP Start on MSOP discharge pressure < 190 OR bearing header pressure <15 psig EBOP Start on MSOP discharge pressure < 180 AND TGOP discharge pressure < 12 psig A Incorrect plausible to examinee who belives EBOP is powered from safeguard DC B Correct TGOP has a start signal as does EBOP however EBOP power supply is lost C Incorrect plausible to the examinee who does not recall the TGOP start setpoints D Incorrect plausible to the examinee who reverses the power supplies for TGOP and EBOP LMK 2017 IL T NRG JANUARY Page: 91 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01January2017 NRC test SRO Question 27 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
* Turning gear oil pump (TGOP) discharge pressure of 10 psig WHICH ONE of the following identifies the status of the Turning Gear Oil Pump (TGOP) and Emergency Bearing Oil Pump (EBOP)?
No Points: 1.00 Time to Complete:
I.GQE                                         .EBQE A.       Running                                      Running B.       Running                                      Not Running
2 Difficultv:
: c.       Not Running                                  Not Running D.       Not Running                                  Running Answer:           B Answer Explanation EBOP is powered form non safeguard DC.
2.00 Svstem ID: 1478356 User-Defined ID: Q#27 NEW Lesson Plan Objective:
ITGOP is powered from D114-G-D TGOP Start on MSOP discharge pressure < 190 OR bearing header pressure <15 psig EBOP Start on MSOP discharge pressure < 180 AND TGOP discharge pressure < 12 psig A     Incorrect plausible to examinee who belives EBOP is powered from safeguard DC B   Correct TGOP has a start signal as does EBOP however EBOP power supply is lost C     Incorrect plausible to the examinee who does not recall the TGOP start setpoints D   Incorrect plausible to the examinee who reverses the power supplies for TGOP and EBOP LMK 2017 ILT NRG JANUARY                       Page: 91 of 374                             17 January 2017
LGSOPS0019.IL4 Topic: Main turb oil pp power RO: 2.7 SRO: 2.7 KA#: 245000 K1 .09 LMK 2017 IL T NRG JANUARY Page: 92 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 IL T NRG JANUARY Page: 93 of 374 2 2 245000 K1 .09 2.7/2.7 Main Turbine Generator and Auxiliary Systems Knowledge of the physical connections and/or causeeffect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the following:
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 27 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?       No Points:                         1.00 Time to Complete:               2 Difficultv:                     2.00 Svstem ID:                     1478356 User-Defined ID:               Q#27 NEW Lesson Plan Objective:         LGSOPS0019.IL4 Topic:                         Main turb oil pp power RO:                             2.7 SRO:                           2.7 KA#:                           245000 K1 .09 LMK 2017 ILT NRG JANUARY                     Page: 92 of 374     17 January 2017
D. C . electrical distribution 41.4 LGSOPS0019 2 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 28 . 10: 1455690 Points: 1.00 Unit 1 is in OPCON 1, with the following:  
 
-'1 A' Recirc Pump removed from service due to seal failure -'1 B' Recirc Pump operating at 980 rpm with the following failed/bypassed cells on '1 B' ASD: -Two (2) Phase 'A' cells -One (1) Phase 'B' cell WHICH ONE of the following combinations of additional cell failures would require operators to insert a manual scram? A Phase B Phase C Phase A. 0 0 3 B. 0 2 c. 2 1 0 D. Answer: c Answer Explanation See 843.1.F, Attachment 2, page 16 of 65, FRR # 2.1.2 ... the '1 B' ASD will trip if EITHER all 4 cells fail on a given Phase, OR a total of more than 6 cells fail. Therefore, the two additional Phase 'A' cell failures will trip the '1 B' ASD. With '1 A' Recirc Pump already secured, a trip of '1 B' iwill require a manual scram per OT-112, step 3.1. LMK 2017 IL T NRG JANUARY Page: 94 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 28 Info Question Tvpe: Multiple Choice Status: Active !Always select on test? No !Authorized for practice?
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
No Points: 1.00 rnme to Complete:
2 2
3 Difficulty:
245000 K1 .09 2.7/2.7 Main Turbine Generator and Auxiliary Systems Knowledge of the physical connections and/or causeeffect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the following: D. C . electrical distribution 41.4 LGSOPS0019                   2 LMK 2017 ILT NRG JANUARY            Page: 93 of 374                          17 January 2017
4.00 System ID: 1455690 User-Defined ID: Q# 28 BANK Lesson Plan Objective:
 
LGSOPS0043B.2C Topic: ASD Response to Cell Bypass RO: 3.2 SRO: 3.2 KA#: 202001 K2.01 LMK 2017 IL T NRC JANUARY Page: 95 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 28                                                 . 10: 1455690                                 Points: 1.00 Unit 1 is in OPCON 1, with the following:
LMK 2017 IL T NRG JANUARY Page: 96 of 374 202001 K2.01 3.2/3.2 Recirculation System Knowledge of electrical power supplies to the following:
        - '1 A' Recirc Pump removed from service due to seal failure
Recirculation um s: Plant-S ecific bank 966665 bank 966665 bank 966665 Rev 3 #t .. 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 IL T NRC JANUARY Page: 97 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 29 10: 1535797 Points: 1.00 Unit 1 initial plant conditions are as follows:
        - '1 B' Recirc Pump operating at 980 rpm with the following failed/bypassed cells on '1 B' ASD:
                  - Two (2) Phase 'A' cells
                  - One (1) Phase 'B' cell WHICH ONE of the following combinations of additional cell failures would require operators to insert a manual scram?
A Phase                           B Phase                     C Phase A.         0                                 0                           3 B.         0                                 2
: c.         2                                 1                           0 D.
Answer:           c Answer Explanation See 843.1.F, Attachment 2, page 16 of 65, FRR # 2.1.2 ... the '1 B' ASD will trip if EITHER all 4 cells fail on a given Phase, OR a total of more than 6 cells fail. Therefore, the two additional Phase 'A' cell failures will trip the '1 B' ASD. With '1 A' Recirc Pump already secured, a trip of '1 B' iwill require a manual scram per OT-112, step 3.1.
LMK 2017 ILT NRG JANUARY                             Page: 94 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 28 Info Question Tvpe:                   Multiple Choice Status:                         Active
        !Always select on test?           No
        !Authorized for practice?         No Points:                         1.00 rnme to Complete:                 3 Difficulty:                     4.00 System ID:                       1455690 User-Defined ID:                 Q# 28 BANK Lesson Plan Objective:           LGSOPS0043B.2C Topic:                           ASD Response to Cell Bypass RO:                             3.2 SRO:                             3.2 KA#:                             202001 K2.01 LMK 2017 ILT NRC JANUARY                       Page: 95 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
202001 K2.01 3.2/3.2 Recirculation System Knowledge of electrical power supplies to the following: Recirculation um s: Plant-S ecific Rev    3
                                                                                  #t ..
bank 966665 bank 966665 bank 966665 LMK 2017 ILT NRG JANUARY            Page: 96 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 ILT NRC JANUARY             Page: 97 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 29                                               10: 1535797                               Points: 1.00 Unit 1 initial plant conditions are as follows:
* SAMPS are being implemented
* SAMPS are being implemented
* Reactor Level is -290" down slow with no injection
* Reactor Level is -290" down slow with no injection
* Reactor Pressure is 1175 psig steady (no SRV pneumatics available)
* Reactor Pressure is 1175 psig steady (no SRV pneumatics available)
RPV pressure reduction has been ordered by performing section 4.7 of T-260, "RPV Venting Through HPCI Steam Line." During the depressurization, HPCI Pump Room pressure peaked at 3 psig. WHICH ONE of the following correctly identifies whether the release is (a) Scrubbed and/or Filtered and (b) the release path? Scrubbed and/or Filtered Release Path A. Yes Monitored Elevated B. Yes Unmonitored Ground Level C. No Monitored Elevated D. No Unmonitored Ground Level Answer: D !Answer Explanation LMK 2017 IL T NRG JANUARY Page: 98 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Section 4.7 of T-260, RPV Venting Through HPCI Steam Line contains the following Cautions: It is highly probable that the vent path in Section 4.7 will flood the Reactor Enclosure with nuclear steam AND reactor source term. 3. The flooding of the Reactor Enclosure with Nuclear Steam will cause severe Reactor Enclosure environmental conditions which could render ECCS !AND other equipment inoperable, along with the potential of losing Reactor Enclosure electrical power. rThis in addition to the Stem stating that the pump room peaking at 3 psig (well above the 5 inches of water column for the Steam Flooding Dampers and the 0.5 psig for the blowout panes) the candidate should determine that there is an unscrubbed, unfiltered ground level release. A is plausible if the candidate mistakenly believes that steam is scrubbed through the suppression pool water or the SBGTS filters and is released through the North Stack via SBGTS. B is plausible if the candidate mistakenly believes that the steam is scrubbed through the suppression pool prior to going out the blowout panel C is plausible if the candidate mistakenly believes that the steam exits the plant via Reactor Enclosure HVAC out the South Stack. D is correct The RO candidate is responsible to know that the pump room peaking at 3 psig (well above the 5 inches of water column for the Steam Flooding Dampers and the 0.5 psig for the blowout panes) the RO candidate should determine that there is an unscrubbed (venting HPCI steam line will not go through the suppression pool), unfiltered ground level release (pressurizing HPCI pump room will cause steam flooding dampers to close isolating the room from reactor HVAC as the room pressurizes blowout pannels will open causing an unfiltered/ground level release. LMK 2017 IL T NRG JANUARY Page: 99 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 29 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
RPV pressure reduction has been ordered by performing section 4.7 of T-260, "RPV Venting Through HPCI Steam Line."
No Points: 1.00 rrime to Complete:
During the depressurization, HPCI Pump Room pressure peaked at 3 psig.
3 Difficulty:
WHICH ONE of the following correctly identifies whether the release is (a) Scrubbed and/or Filtered and (b) the release path?
3.00 System ID: 1535797 User-Defined ID: Q# 29 BANK Lesson Plan Objective:
Scrubbed and/or Filtered                       Release Path A.                             Yes                             Monitored Elevated B.                           Yes                         Unmonitored Ground Level C.                             No                             Monitored Elevated D.                             No                         Unmonitored Ground Level Answer:           D
LGSOPS0076B.9 lropic: Given plant conditions and applicable T-260 section determine unmonitored release path RO: 4.0 SRO: 4.4 KA#: 290001 K3.01 LMK 2017 IL T NRC JANUARY Page: 100 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
        !Answer Explanation LMK 2017 ILT NRG JANUARY                         Page: 98 of 374                           17 January 2017
LMK 2017 IL T NRC JANUARY Page: 101 of 374 2 2 290001 K3.01 4.0/4.4 Secondary Containment Knowledge of the effect that a loss or malfunction of the SECONDARY CONTAINMENT will have on following:
 
tOff-site radioactive release rates 41.7 LGSOPS0076B.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Section 4.7 of T-260, RPV Venting Through HPCI Steam Line contains the following Cautions:
bank 1247968 bank 1247968 bank 1247968 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 30 ID: 1601388 Points: 1.00 Unit 1 plant conditions are as follows: Reactor power is 100% 30 scfm Offgas effluent flow Offgas dew point monitor is reading 40&deg;F The Charcoal Vault Refrigeration Compressors trip and cannot be restarted.
        ~- It is highly probable that the vent path in Section 4.7 will flood the Reactor Enclosure with nuclear steam AND reactor source term.
: 3. The flooding of the Reactor Enclosure with Nuclear Steam will cause severe Reactor Enclosure environmental conditions which could render ECCS
      !AND other equipment inoperable, along with the potential of losing Reactor Enclosure electrical power.
rThis in addition to the Stem stating that the pump room peaking at 3 psig (well above the 5 inches of water column for the Steam Flooding Dampers and the 0.5 psig for the blowout panes) the candidate should determine that there is an unscrubbed, unfiltered ground level release.
A is plausible if the candidate mistakenly believes that steam is scrubbed through the suppression pool water or the SBGTS filters and is released through the North Stack via SBGTS.
B is plausible if the candidate mistakenly believes that the steam is scrubbed through the suppression pool prior to going out the blowout panel C is plausible if the candidate mistakenly believes that the steam exits the plant via Reactor Enclosure HVAC out the South Stack.
D is correct The RO candidate is responsible to know that the pump room peaking at 3 psig (well above the 5 inches of water column for the Steam Flooding Dampers and the 0.5 psig for the blowout panes) the RO candidate should determine that there is an unscrubbed (venting HPCI steam line will not go through the suppression pool), unfiltered ground level release (pressurizing HPCI pump room will cause steam flooding dampers to close isolating the room from reactor HVAC as the room pressurizes blowout pannels will open causing an unfiltered/ground level release.
LMK 2017 ILT NRG JANUARY                         Page: 99 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 29 Info Question Type:                 Multiple Choice Status:                         Active
        ~lways select on test?         No
        ~uthorized for practice?       No Points:                         1.00 rrime to Complete:             3 Difficulty:                     3.00 System ID:                     1535797 User-Defined ID:               Q# 29 BANK Lesson Plan Objective:         LGSOPS0076B.9 Given plant conditions and applicable T-260 section determine lropic:
unmonitored release path RO:                             4.0 SRO:                           4.4 KA#:                           290001 K3.01 LMK 2017 ILT NRC JANUARY                     Page: 100 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 2
290001 K3.01 4.0/4.4 Secondary Containment Knowledge of the effect that a loss or malfunction of the SECONDARY CONTAINMENT will have on following: tOff-site radioactive release rates 41.7 LGSOPS0076B.
bank 1247968 bank 1247968 bank 1247968 LMK 2017 ILT NRC JANUARY            Page: 101 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 30                                                                     ID: 1601388                                     Points: 1.00 Unit 1 plant conditions are as follows:
Reactor power is 100%
30 scfm Offgas effluent flow Offgas dew point monitor is reading 40&deg;F The Charcoal Vault Refrigeration Compressors trip and cannot be restarted.
WHICH ONE of the following identifies the change in the activity of the Offgas effluent, if any and the monitoring location?
WHICH ONE of the following identifies the change in the activity of the Offgas effluent, if any and the monitoring location?
Change in Activity Monitoring Location A. Rises North Stack B. Rises South Stack c. Remains the same North Stack D. Remains the same South Stack Answer: A Answer Explanation he charcoal delays gaseous xenon, krypton, and their daughter products along with biologically significant isotopes Sr-89, Sr-90, Ba-140 and Cs-137 in the Offgas stream through adsorption.
Change in Activity                         Monitoring Location A.             Rises                                           North Stack B.             Rises                                           South Stack
his allows the radioactive isotopes to decay to levels acceptable for release to the atmosphere.  
: c.             Remains the same                               North Stack D.             Remains the same                               South Stack Answer:                       A Answer Explanation he charcoal delays gaseous xenon, krypton, and their daughter products along with biologically significant isotopes Sr-89, Sr-90, Ba-140 and Cs-137 in the Offgas stream through adsorption.
....... is incorrect.
his allows the radioactive isotopes to decay to levels acceptable for release to the atmosphere.
Release rates will be higher and the release will be through the South Stack. This distractor is plausible based on the misconceptions described in the first 2 distractors.
        ~.l!I.Si'J..2!'-"".......,....._."-'H....... is incorrect. Release rates will be higher and the release will be through the South Stack. This distractor is plausible based on the misconceptions described in the first 2 distractors.
LMK 2017 IL T NRC JANUARY Page: 102 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 30 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
LMK 2017 ILT NRC JANUARY                                              Page: 102 of 374                                17 January 2017
No Points: 1.00 Time to Complete:
 
0 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 30 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               0 Difficulty:                     2.50 System ID:                       1601388 User-Defined ID:                 0#30 BANK Lesson Plan Objective:           LOT0510.06 Given the following conditions: - Reactor power is 100% - 30 lfopic:
2.50 System ID: 1601388 User-Defined ID: 0#30 BANK Lesson Plan Objective:
scfm Offqas effluent flow - Offqas de RO:                             2.7 SRO:                             2.9 KA#:                             271000 LMK 2017 ILT NRC JANUARY                     Page: 103 of 374                               17 January 2017
LOT0510.06 lfopic: Given the following conditions:  
 
-Reactor power is 100% -30 scfm Offqas effluent flow -Offqas de RO: 2.7 SRO: 2.9 KA#: 271000 LMK 2017 IL T NRC JANUARY Page: 103 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRG JANUARY Page: 104 of 374 RO 2 2 271000 K4.06 Offgas System Knowledge of OFFGAS SYSTEM design feature(s) and/or interlocks which provide for the following:
RO 2
Decay of fission product gases to particulate dau hters bank 833329 bank 833329 bank 833329 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 31 10:1601440 Points: 1.00 Unit 1 is operating at 100% power when the following occurs: -HIGH-HIGH level condition in the '1A' Feedwater Heater (FWH) WHICH ONE of the following describes the response of APRMs and the resultant feedwater temperature at the inlet to the reactor feed pump ? (assume no operator action) APBM Beadings Reactor feed pump inlet temperature A. Lower Lower B. Lower Higher c. Higher Higher D. Higher Lower Answer: D Answer Explanation Upon a high high FWH isolation on the 1 A FWH, HV-005-*02 and HV-005-*01 close stopping all FW flow through the 1 A low pressure string. The flow through the 1 B and 1 C FW String combines and is equally distributed to the 1 A, 1 B, and 1 C Feed pumps. The FW temperature at the inlet of the BFPT is lower than normal resulting in a an overall temperature decrease at the BFP inlet reactor power will increase by approximately 1 .5% A Incorrect plausible to the examinee who does not recall that the effect of the loss of extraction steam has a greater effect than the increase in flow through the remaining heat exchangers B Incorrect plausible to the examine who believe a loss of the "A" low pressure heater string will cause flow to the A BFP to lower resulting in a recirc runback and at the effect of the loss of extraction steam has a greater effect than the increase in flow through the remaining heat exchangers C Incorrect plausible to the examine the loss of extraction steam will override the effect of increased flow through the remaining strings and reverses the reactivity effect D Correct feed water temp. entering the 6th feedwater heaters is lower so feed water to the vessel temp is lower causinq a power increase LMK 2017 IL T NRC JANUARY Page: 105 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 31 Info Question Type: Multiple Choice Status: Active Always select on test? No for practice?
2 271000 K4.06 Offgas System Knowledge of OFFGAS SYSTEM design feature(s) and/or interlocks which provide for the following: Decay of fission product gases to particulate dau hters bank 833329 bank 833329 bank 833329 LMK 2017 ILT NRG JANUARY            Page: 104 of 374                          17 January 2017
No Points: 1.00 lrime to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 31                                               10:1601440                                     Points: 1.00 Unit 1 is operating at 100% power when the following occurs:
2.00 System ID: 1601440 User-Defined ID: Q# 31 BANK Lesson Plan Obiective:
        - HIGH-HIGH level condition in the '1A' Feedwater Heater (FWH)
LOT-0530, OBJ. #3 lropic: A "High-High" level condition occurs in the "1 A" feedwater heater 'FWH) -Any automatic actions th RO: 2.7 SRO: 2.7 KA#: 256000 K5.08 LMK 2017 ILT NRC JANUARY Page: 106 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
WHICH ONE of the following describes the response of APRMs and the resultant feedwater temperature at the inlet to the reactor feed pump ? (assume no operator action)
LMK 2017 IL T NRC JANUARY Page: 107 of 374 2 2 256000 K5.08 2.7/2.7 Reactor Condensate System Knowledge of the operational implications of the following concepts as they apply to REACTOR CONDENSATE SYSTEM: Heat removal (transfer) mechanisms 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 32 10:1601405 Points: 1.00 Both units are operating at 100% power Which of the following describes if the power supply to the Motor Driven Fire Pump is safeguard power or Non-safeguard power, and if a Tech Requirements Manual (TRM) entry is required for a loss of power to the Motor Driven Fire Pump ? Safeguard or non-safeguard TAM entry BeQuired A. Safeguard No B. Safeguard Yes c. Non-safeguard Yes D. Non-safeguard No Answer: c Answer Explanation Motor driven fire pump MDFP A Incorrect plausible to examinee who belives fire protection pump are safeguard and belives loss of 1 of 3 pumps Motor diesel and backup diesel would not require TAM entry B Incorrect plausible to examinee who belivesfire protection pump are safeguard C Correct MDFP is powered for 214D (non-safeguard) and loss of 1 pump does require TAM entry (7day) D Incorrect plausible to examinee who belive loss of 1 of 3 pumps Motor diesel and backup diesel would not require TAM entry LMK 2017 IL T NRC JANUARY Page: 108 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 32 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
APBM Beadings                       Reactor feed pump inlet temperature A.                           Lower                                       Lower B.                           Lower                                       Higher
No Points: 1.00 Time to Complete:
: c.                           Higher                                     Higher D.                           Higher                                     Lower Answer:           D Answer Explanation Upon a high high FWH isolation on the 1A FWH, HV-005-*02 and HV-005-*01 close stopping all FW flow through the 1A low pressure string. The flow through the 1B and 1C FW String combines and is equally distributed to the 1A, 1B, and 1C Feed pumps. The FW temperature at the inlet of the BFPT is lower than normal resulting in a an overall temperature decrease at the BFP inlet reactor power will increase by approximately 1.5%
3 Difficulty:
A Incorrect plausible to the examinee who does not recall that the effect of the loss of extraction steam has a greater effect than the increase in flow through the remaining heat exchangers B Incorrect plausible to the examine who believe a loss of the "A" low pressure heater string will cause flow to the A BFP to lower resulting in a recirc runback and at the effect of the loss of extraction steam has a greater effect than the increase in flow through the remaining heat exchangers C Incorrect plausible to the examine the loss of extraction steam will override the effect of increased flow through the remaining strings and reverses the reactivity effect D Correct feed water temp. entering the 6th feedwater heaters is lower so feed water to the vessel temp is lower causinq a power increase LMK 2017 ILT NRC JANUARY                         Page: 105 of 374                               17 January 2017
2.00 System ID: 1601405 User-Defined ID: 0#32 NEW Lesson Plan Objective:
 
LGSOPS0022.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 31 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No
7H Topic: Loss of pwr to MDFP RO: 3.1 SRO: 3.1 KA#: 286000 K6.01 LMK 2017 IL T NRC JANUARY Page: 109 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
        ~uthorized for practice?         No Points:                         1.00 lrime to Complete:               3 Difficulty:                     2.00 System ID:                       1601440 User-Defined ID:                 Q# 31 BANK Lesson Plan Obiective:           LOT-0530, OBJ. #3 A "High-High" level condition occurs in the "1 A" feedwater heater lropic:
LMK 2017 IL T NRG JANUARY Page: 110 of 374 286000K6.01 3.1 /3.1 Fire Protection System Knowledge of the effect that a loss or malfunction of the following will have on the FIRE PROTECTION SYSTEM AC. electrical distribution:
                                        'FWH) - Any automatic actions th RO:                             2.7 SRO:                             2.7 KA#:                             256000 K5.08 LMK 2017 ILT NRC JANUARY                       Page: 106 of 374                               17 January 2017
Plant-S ecific lower 8 41.7 Rev .. 3 I:; 4 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 33 10:1455176 Points: 1.00. Unit 2 is operating at 100% power with the following conditions:  
 
-Suppression pool temperature is 93 degrees -"2B" AHR loop is operating in Suppression Pool Cooling -"OB" RHRSW pump is providing cooling water to the "2B" AHR heat exchanger A Division 2 LOCA signal is inadvertently generated.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
The PRO reopens HV-051-2F024B "SUPP POOL CLG B". No other operator actions are taken. WHICH ONE of the following describes the change in suppression pool heat removal (if any) over the next 5 minutes and the reason for the response?
2 2
A. Less heat removal due to OB RHRSW pump trip B. Less heat removal due to 2B AHR heat exchanger being bypassed C. Less heat removal due to 2B AHR pump trip D. Heat removal rate is unchanged, system remains in service Answer: B Answer Explanation IWith the Div 2 LOCA signal the F048 Heat Exchanger Bypass valve would get an open signal for lthree minutes along with the F024, test valve closing. Therefore, the heat exchanger is bypassed and Suppression Pool temperature will increase.
256000 K5.08 2.7/2.7 Reactor Condensate System Knowledge of the operational implications of the following concepts as they apply to REACTOR CONDENSATE SYSTEM:
A Incorrect.
Heat removal (transfer) mechanisms LMK 2017 ILT NRC JANUARY            Page: 107 of 374                          17 January 2017
Less heat removal, but the RHRSW pump will not trip. Plausible to the examinee who either does not recall the RHRSW rad monitors are powered from unit 1 and RHRSW will not trip on rad monitor down scale. or does not recall that B RHRSW pump is powered from 012 B Correct. less heat removal due to the HTX bypass valve opening C Incorrect.
 
Plausible to the examinee who does not recall that the running AHR pump will not trip on a LOCA signal as the Core Spray pumps do D Incorrect.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 32                                             10:1601405                                 Points: 1.00 Both units are operating at 100% power Which of the following describes if the power supply to the Motor Driven Fire Pump is safeguard power or Non-safeguard power, and if a Tech Requirements Manual (TRM) entry is required for a loss of power to the Motor Driven Fire Pump ?
Plausible to the examinee who does not recall that the heat exchanger bypass valve will automatically open on a LOCA siqnal LMK 2017 IL T NRG JANUARY Page: 111 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 33 Info Question Type: Multiple Choice Status: Active !Always select on test? No !Authorized for practice?
Safeguard or non-safeguard         TAM entry BeQuired A.         Safeguard                                   No B.         Safeguard                                   Yes
No Points: 1.00 Time to Complete:
: c.         Non-safeguard                               Yes D.         Non-safeguard                               No Answer:           c Answer Explanation Motor driven fire pump MDFP A Incorrect plausible to examinee who belives fire protection pump are safeguard and belives loss of 1 of 3 pumps Motor diesel and backup diesel would not require TAM entry B Incorrect plausible to examinee who belivesfire protection pump are safeguard C Correct MDFP is powered for 214D (non-safeguard) and loss of 1 pump does require TAM entry (7day)
3 Difficulty:
D Incorrect plausible to examinee who belive loss of 1 of 3 pumps Motor diesel and backup diesel would not require TAM entry LMK 2017 ILT NRC JANUARY                       Page: 108 of 374                             17 January 2017
3.50 System ID: 1455176 User-Defined ID: Q# 33 BANK Lesson Plan Objective:
 
LOT0051.08 Topic: pool temp RHR in pool cooling loca occurs RO: 4.0 SRO: 4.0 KA#: 219000 A 1.01 LMK 2017 IL T NRC JANUARY Page: 112 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 32 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1601405 User-Defined ID:                 0#32 NEW Lesson Plan Objective:           LGSOPS0022. 7H Topic:                           Loss of pwr to MDFP RO:                             3.1 SRO:                             3.1 KA#:                             286000 K6.01 LMK 2017 ILT NRC JANUARY                       Page: 109 of 374     17 January 2017
LMK 2017 IL T NRC JANUARY Page: 113of374 RO 2 2 219000A1.01 4.0/4.0 RHR/LPCI:
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
286000K6.01 3.1 /3.1 Fire Protection System Knowledge of the effect that a loss or malfunction of the following will have on the FIRE PROTECTION SYSTEM AC. electrical distribution: Plant-S ecific lower 8
41.7 Rev.. 3 I:;     4 LMK 2017 ILT NRG JANUARY            Page: 110 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 33                                               10:1455176                                 Points: 1.00.
Unit 2 is operating at 100% power with the following conditions:
        - Suppression pool temperature is 93 degrees
        - "2B" AHR loop is operating in Suppression Pool Cooling
        - "OB" RHRSW pump is providing cooling water to the "2B" AHR heat exchanger A Division 2 LOCA signal is inadvertently generated. The PRO reopens HV-051-2F024B "SUPP POOL CLG B". No other operator actions are taken.
WHICH ONE of the following describes the change in suppression pool heat removal (if any) over the next 5 minutes and the reason for the response?
A.     Less heat removal due to OB RHRSW pump trip B.       Less heat removal due to 2B AHR heat exchanger being bypassed C.       Less heat removal due to 2B AHR pump trip D.       Heat removal rate is unchanged, system remains in service Answer:           B Answer Explanation IWith the Div 2 LOCA signal the F048 Heat Exchanger Bypass valve would get an open signal for lthree minutes along with the F024, test valve closing. Therefore, the heat exchanger is bypassed and Suppression Pool temperature will increase.
A Incorrect. Less heat removal, but the RHRSW pump will not trip. Plausible to the examinee who either does not recall the RHRSW rad monitors are powered from unit 1 and RHRSW will not trip on rad monitor down scale. or does not recall that B RHRSW pump is powered from 012 B Correct. less heat removal due to the HTX bypass valve opening C Incorrect. Plausible to the examinee who does not recall that the running AHR pump will not trip on a LOCA signal as the Core Spray pumps do D Incorrect. Plausible to the examinee who does not recall that the heat exchanger bypass valve will automatically open on a LOCA siqnal LMK 2017 ILT NRG JANUARY                         Page: 111 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 33 Info Question Type:                   Multiple Choice Status:                         Active
        !Always select on test?           No
        !Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.50 System ID:                       1455176 User-Defined ID:               Q# 33 BANK Lesson Plan Objective:           LOT0051.08 Topic:                           pool temp RHR in pool cooling loca occurs RO:                             4.0 SRO:                           4.0 KA#:                           219000 A 1.01 LMK 2017 ILT NRC JANUARY                       Page: 112 of 374                    17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
RO 2
2 219000A1.01 4.0/4.0 RHR/LPCI:
Torus/Suppression Pool Cooling Mode Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:
Torus/Suppression Pool Cooling Mode Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE n/a 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 34 ID: 1649532 Points: 1.00 Unit 1 is operating at 100% power.
TORUS/SUPPRESSION POOL COOLING MODE n/a LMK 2017 ILT NRC JANUARY            Page: 113of374                          17 January 2017
* Control rod 30-31 SCRAMS Which of the following describes the indications on the four rod display, and the action required (if any) to run a P-1? Four rod display indication Action reciuired to run a P-1 A. Blank, Blank Wait for rod to settle .QNLY B. Blank, Blank Isolate rod and wait for it to settle C. 0,0 No action required D. .... , --Isolate rod and wait for it to settle Answer: B Explanation When a control rod SCRAMS it goes to the overtravel in position (beyond RPIS position switches a 00 position note in ON-104 page 8 states Until a control rod settles to a known position, i.e. other than inserted to beyond 00, a P-1 cannot be run. incorrect four rod position will indicate blank, blank but rod must be isolated to settle, plausible the examinee who thinks that it will respond as a full reactor scram does. when scram discharge volume fills the rods will settle to 00 without isolating.
 
B correct RPIS will show blank (no position on the four rod display) when it scrams (overtravel in) since only 1 rod scrammed the SDV will not fill and the rod will stay at over travel position.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 34                                               ID: 1649532                                       Points: 1.00 Unit 1 is operating at 100% power.
once rod is isolated and allowed to settle at 00 a P-1 can be run C incorrect plausible to the examine who does not recall the RPIS reed switch allocations at 00 and past 00. If examinee believes that position will show 00 than a P-1 would be able to be run D incorrect--,--(a dash in each window) of the four rod display for 30-31 is what is shown when rods are between notches while stroking.
* Control rod 30-31 SCRAMS Which of the following describes the indications on the four rod display, and the action required (if any) to run a P-1?
this is plausible to the examinee who believes that past 0,0 is equivalent to between notches LMK 2017 IL T NRG JANUARY Page: 114of374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 34 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
Four rod display indication                     Action reciuired to run a P-1 A.       Blank, Blank                                   Wait for rod to settle .QNLY B.       Blank, Blank                                   Isolate rod and wait for it to settle C.       0,0                                             No action required D.       .... , --                                       Isolate rod and wait for it to settle Answer:           B
No Points: 1.00 Time to Complete:
        ~nswer Explanation When a control rod SCRAMS it goes to the overtravel in position (beyond RPIS position switches
3 Difficulty:
        ~or a 00 position note in ON-104 page 8 states Until a control rod settles to a known position, i.e. other than inserted to beyond 00, a P-1 cannot be run.
3.00 System ID: 1649532 User-Defined ID: Q#34 NEW Lesson Plan Objective:
        ~ incorrect four rod position will indicate blank, blank but rod must be isolated to settle, plausible
LGSOPS0073A.2H ifooic: RPIS Overtravel RO: 3.6 SRO: 3.9 KA#: 214000 A2.03 LMK 2017 IL T NRG JANUARY Page: 115 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
        ~o the examinee who thinks that it will respond as a full reactor scram does. when scram discharge volume fills the rods will settle to 00 without isolating.
LMK 2017 IL T NRG JANUARY Page: 116 of 374 2 2 214000 A2.03 3.6/3.9 RPIS Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or o erations:
B correct RPIS will show blank (no position on the four rod display) when it scrams (overtravel in) since only 1 rod scrammed the SDV will not fill and the rod will stay at over travel position. once
Overtravel/in-out low 7 41.6 ON-104 LGSOPS00738 5 Rev:\&#xa5; s **1: ,J; 0 h' 2 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 117 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January2017 NRCtestSRO 35 10: 1601449 Points: 1.00 A chemical spill results in the following:  
        ~he rod is isolated and allowed to settle at 00 a P-1 can be run C incorrect plausible to the examine who does not recall the RPIS reed switch allocations at 00 and past 00. If examinee believes that position will show 00 than a P-1 would be able to be run D incorrect--,-- (a dash in each window) of the four rod display for 30-31 is what is shown when rods are between notches while stroking. this is plausible to the examinee who believes that past 0,0 is equivalent to between notches LMK 2017 ILT NRG JANUARY                         Page: 114of374                                     17 January 2017
-'A' and 'C' Toxic Gas detectors tripped -'A' and 'D' Control Enclosure Chlorine detectors UPSCALE WHICH ONE of the following identifies the status of the CREFAS Fans? A. Both are running B. Neither is running C. Only the 'A' fan is running D. Only the '8' fan is running Answer: 8 \Answer Explanation LMK 2017 IL T NRC JANUARY Page: 118 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO nswer: Remains in Standby, Neither CREFAS fan running he chlorine monitoring system will initiate an automatic isolation of the Control Room HVAC system if chlorine concentration exceeds 0.40 ppm in the Control Room HVAC intake plenum. here are four chlorine detectors, which provide input to four chlorine isolation channels, as allows: (If the A and D chlorine detectors sense high chlorine, but not the Band C = No isolation) he A and C or B and 0 detectors must sense high chlorine to cause an isolation signal. If the and C chlorine detectors sense greater than 0.40 ppm chlorine, then both the A and C chlorine isolation channels will trip. If the B and D chlorine detectors sense greater than 0.40 ppm chlorine, then both the B and D chlorine isolation channels will trip. If a chlorine isolation signal is generated on all four isolation channels, then a complete isolation will occur, which results in the following:The main Control Room air is recirculated using the normal supply and return fans, while the CREFAS fan draws some of the recirculating air through the CREFAS filter, then sends it back to the suction of the normal supply fans. (Since no outside air is drawn in, MCR C1P will decay to O psid.) chlorine isolation is accomplished as follows:The A or B CREFAS fan will start after a 30 second time delay. (Whichever fan is in AUTO will start.)The A CREFAS fan is started only by the C isolation channel, and the B CREFAS fan is started only by the D isolation channe (B & D detectors)!.
 
The toxic gas monitors provide indication and alarm in the event of toxic gas enters the Control Enclosure.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 34 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.00 System ID:                       1649532 User-Defined ID:                 Q#34 NEW Lesson Plan Objective:           LGSOPS0073A.2H ifooic:                         RPIS Overtravel RO:                             3.6 SRO:                             3.9 KA#:                             214000 A2.03 LMK 2017 ILT NRG JANUARY                       Page: 115 of 374     17 January 2017
Three analyzers located in the Control Enclosure are used to detect gases that are proven to be toxic, and initiate a MCR alarm once triggered.
 
There are no automatic functions r interlocks associated with the toxic gas monitors.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
utomatically initiates "A" CREFAS only, with the "A" CREFAS running -see explanation utomatically initiates "B" CREFAS only, with the "B" CREFAS running -see explanation utomatically initiates both "A" & "B" CREFAS, with both CREFAS fans running -see explanation LMK 2017 IL T NRC JANUARY Page: 119 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO * *isolation Valves Include: HV73..U21A,B HV73-052A,B HD7tUl53A, B HV73-057A,B HV78-071A,B AND Question written to MCA ventalation already have several questions on reactor HVAC/SBGT no isolations on turb hvac LMK 2017 ILT NRG JANUARY Page: 120 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 35 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
2 2
No Points: 1.00 rnme to Complete:
214000 A2.03 3.6/3.9 RPIS Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION SYSTEM ;
3 Difficulty:
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or o erations: Overtravel/in-out low 7
2.00 System ID: 1601449 User-Defined ID: Q# 35 BANK Lesson Plan Objective:
41.6 5
LGSOPS0078.3H Topic: Describe CREFAS operation with a A MCR Radiation Isolation auto initiatiation RO: 3.8 SRO: 3.8 KA#: 288000 A3.01 LMK 2017 IL T NRG JANUARY Page: 121 of 374 17 January 2017 EXAMINATION ANSWER KEY Comments:
ON-104                 Rev:\&#xa5; s LGSOPS00738          **1:
LMK 2017 IL T NRC JANUARY IL T 15-01 January 2017 NRC test SRO 2 2 288000 A3.01 3.8/3.8 Plant Ventilation Systems Ability to monitor automatic operations of the PLANT VENTILATION SYSTEMS including:
h'
Isolation/initiation si nals On a MCR Rad Isolation, the CREFAS Fan that is in AUTO will start (only 1 fan is in AUTO in a normal alignment) and the outside air dampers to the CREFAS Filters will open. Page: 122 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO LMK 2017 IL T NRC JANUARY Page: 123 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 36 ID: 1455868 Points: 1.00 Unit 1 was operating at 100% power when the following occurred.
                                                                                      ,J; 0 2
* The 1 M SRV spuriously opened several minutes ago.
LMK 2017 ILT NRG JANUARY            Page: 116 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 117 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January2017 NRCtestSRO 35                                               10: 1601449         Points: 1.00 A chemical spill results in the following:
        - 'A' and 'C' Toxic Gas detectors tripped
        - 'A' and 'D' Control Enclosure Chlorine detectors UPSCALE WHICH ONE of the following identifies the status of the CREFAS Fans?
A.       Both are running B.       Neither is running C.       Only the 'A' fan is running D.       Only the '8' fan is running Answer:           8
        \Answer Explanation LMK 2017 ILT NRC JANUARY                         Page: 118 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO nswer: Remains in Standby, Neither CREFAS fan running he chlorine monitoring system will initiate an automatic isolation of the Control Room HVAC system if chlorine concentration exceeds 0.40 ppm in the Control Room HVAC intake plenum.
here are four chlorine detectors, which provide input to four chlorine isolation channels, as allows: (If the A and D chlorine detectors sense high chlorine, but not the Band C = No isolation) he A and C or B and 0 detectors must sense high chlorine to cause an isolation signal. If the and C chlorine detectors sense greater than 0.40 ppm chlorine, then both the A and C chlorine isolation channels will trip. If the B and D chlorine detectors sense greater than 0.40 ppm chlorine, then both the B and D chlorine isolation channels will trip.
If a chlorine isolation signal is generated on all four isolation channels, then a complete isolation will occur, which results in the following:The main Control Room air is recirculated using the normal supply and return fans, while the CREFAS fan draws some of the recirculating air through the CREFAS filter, then sends it back to the suction of the normal supply fans.
(Since no outside air is drawn in, MCR C1P will decay to O psid.)
chlorine isolation is accomplished as follows:The A or B CREFAS fan will start after a 30 second time delay. (Whichever fan is in AUTO will start.)The A CREFAS fan is started only by the C isolation channel, and the B CREFAS fan is started only by the D isolation channe (B & D detectors)!.
The toxic gas monitors provide indication and alarm in the event of toxic gas enters the Control Enclosure. Three analyzers located in the Control Enclosure are used to detect gases that are proven to be toxic, and initiate a MCR alarm once triggered. There are no automatic functions r interlocks associated with the toxic gas monitors.
utomatically initiates "A" CREFAS only, with the "A" CREFAS running - see explanation utomatically initiates "B" CREFAS only, with the "B" CREFAS running - see explanation utomatically initiates both "A" & "B" CREFAS, with both CREFAS fans running - see explanation LMK 2017 ILT NRC JANUARY                           Page: 119 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO AND
                                  * *isolation Valves Include: HV73..U21A,B HV73-052A,B HD7tUl53A, B HV73-057A,B HV78-071A,B Question written to MCA ventalation already have several questions on reactor HVAC/SBGT no isolations on turb hvac LMK 2017 ILT NRG JANUARY                       Page: 120 of 374                         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 35 Info Question Type:                   Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 rnme to Complete:                 3 Difficulty:                     2.00 System ID:                       1601449 User-Defined ID:                 Q# 35 BANK Lesson Plan Objective:           LGSOPS0078.3H Describe CREFAS operation with a A MCR Radiation Isolation Topic:
auto initiatiation RO:                             3.8 SRO:                             3.8 KA#:                             288000 A3.01 LMK 2017 ILT NRG JANUARY                       Page: 121 of 374                         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 2
288000 A3.01 3.8/3.8 Plant Ventilation Systems Ability to monitor automatic operations of the PLANT VENTILATION SYSTEMS including: Isolation/initiation si nals On a MCR Rad Isolation, the CREFAS Fan that is in AUTO will start (only 1 fan is in AUTO in a normal alignment) and the outside air dampers to the CREFAS Filters will open.
LMK 2017 ILT NRC JANUARY              Page: 122 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 ILT NRC JANUARY             Page: 123 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 36                                             ID: 1455868                                     Points: 1.00 Unit 1 was operating at 100% power when the following occurred.
* The 1M SRV spuriously opened several minutes ago.
* The PRO observes the following indications and diagnoses a tailpipe leak.
* The PRO observes the following indications and diagnoses a tailpipe leak.
* Suppression pool level is 22.5 feet PSIG 6.5 ., PSIG 215.9 6.3 Which of the following describes where the 1 M SRV tailpipe leak is located and the allowed action that will mitigate the containment pressure rise? Location of tailpipe leak A. Suppression Pool B. Suppression Pool C. Drywell D. Drywell Answer: B !Answer Explanation LMK 2017 ILT NRG JANUARY Page: 124 of 374 Allowed action that will mitigate the condition Spray the Drywell Spray the Suppression Pool Spray the Suppression Pool Spray the Drywell 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Examinee must recognize I recall that TR-157-122 Drywell reading is on top, but on PR-57-101 Suppression Pool is on top. Given that pool pressure is > drywell the leak must be in the suppression pool air space. There are 2 ways to reach drywell spray in T-102, from containment pressure leg and from drywell temperature leg. Drywell temperature leg DWT-4 stop sign when DW temp cannot be maintained  
* Suppression pool level is 22.5 feet PSIG 6.5
<145 degrees continue.
                                          .,                                             PSIG 215.9                                                     6.3 Which of the following describes where the 1M SRV tailpipe leak is located and the allowed action that will mitigate the containment pressure rise?
From the containment pressure leg drywell spray is not authorized until pool pressure is> 7.5 psig A Incorrect spraying the DW is not allowed nor would it be the most efficient way to deal with the leak plausible to the examinee who believe that since the air volume of the DW is larger than that of the pool spraying the DW will be more effective and does not recall the limits for DW spray or thinks DW is at 215 degrees. B Correct pool pressure is> than DW pressure so the leak is in the pool and the downcomer vacuum breakers have opened causing DW pressure to rise. Spraying the pool is directed before pool pressure reaches 7.5 psig, pool spray is allowed and the most effective way to mitigate the pressure rise. C Incorrect leak is in the pool plausible to the examinee who does not recall which reading is dw and which is pool D Incorrect spraying the DW is not allowed nor would it be the most efficient way to deal with the leak plausible to the examinee who believe that since the air volume of the DW is larger than that of the pool spraying the DW will be more effective and does not recall the limits for DW spray or thinks DW is at 215 degrees. LMK 2017 IL T NRC JANUARY Page: 125 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 36 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
Location of tailpipe leak                     Allowed action that will mitigate the condition A.     Suppression Pool                             Spray the Drywell B.     Suppression Pool                              Spray the Suppression Pool C.     Drywell                                       Spray the Suppression Pool D.     Drywell                                      Spray the Drywell Answer:         B
No Points: 1.00 Time to Complete:
        !Answer Explanation LMK 2017 ILT NRG JANUARY                       Page: 124 of 374                                 17 January 2017
3 Difficulty:
 
4.00 System ID: 1455868 User-Defined ID: Q#36 NEW Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Examinee must recognize I recall that TR-157-122 Drywell reading is on top, but on PR-57-101 Suppression Pool is on top. Given that pool pressure is > drywell the leak must be in the suppression pool air space. There are 2 ways to reach drywell spray in T-102, from containment pressure leg and from drywell temperature leg. Drywell temperature leg DWT-4 stop sign when DW temp cannot be maintained <145 degrees continue. From the containment pressure leg drywell spray is not authorized until pool pressure is> 7.5 psig A     Incorrect spraying the DW is not allowed nor would it be the most efficient way to deal with the leak plausible to the examinee who believe that since the air volume of the DW is larger than that of the pool spraying the DW will be more effective and does not recall the limits for DW spray or thinks DW is at 215 degrees.
LGSOPS1560.05 Topic: pool spray RO: 4.0 SRO: 3.9 KA#: 230000 LMK 2017 IL T NRG JANUARY Page: 126 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
B     Correct pool pressure is> than DW pressure so the leak is in the pool and the downcomer vacuum breakers have opened causing DW pressure to rise. Spraying the pool is directed before pool pressure reaches 7.5 psig, pool spray is allowed and the most effective way to mitigate the pressure rise.
LMK 2017 IL T NRC JANUARY Page: 127 of 374 2 2 230000 A4.13 4.0/3.9 RHR/LPCI:
C     Incorrect leak is in the pool plausible to the examinee who does not recall which reading is dw and which is pool D     Incorrect spraying the DW is not allowed nor would it be the most efficient way to deal with the leak plausible to the examinee who believe that since the air volume of the DW is larger than that of the pool spraying the DW will be more effective and does not recall the limits for DW spray or thinks DW is at 215 degrees.
Torus/Suppression Pool Spray Mode Ability to manually operate and/or monitor in the ;:Rev 2 .. 5 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 128 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 37 ID: 1455770 Points: 1.00 Unit 1 is at 75% reactor power. Operators are preparing to continue raising power by control rod withdrawal Operators are performing S73.1.A NORMAL OPERATION OF THE REACTOR MANUAL CONTROL SYSTEM Given the following indications; OFUVE WATER Which of the following lists both the direction to manipulate the Drive Water Pressure Control Valve HV-46-1 F003 and the resulting pressure indication to be obtained, prior to withdrawing control rods? Direction to manipulate Drive Water Pressure Control Valve HV-46-1 F003 A. Close B. Open c. Close D. Open Answer: A !Answer Explanation LMK 2017 IL T NRC JANUARY Page: 129 of 374 Indication to obtain PDl-46-1 R602 between 255-265 PSI PDl-46-1 R602 between 255-265 PSI PDl-46-1 R603 between 25-35 PSI PDl-46-1 R603 between 25-35 PSI 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO A Correct per 846.1.a normal operating pressure for CRD drive water is 255-265 psi. closing pressure control valve will raise drive water pressure B Incorrect opening pressure comtrol valve will reduce pressure, plausible to the examinee who incorrectly recalls which side of the pressure regulating valve the indicator is on and does not take into account that the flow control valve wil auto open as the pressure control valve is closed C Incorrect cooling water DP is within its normal band of 10 to 25 psi. adjusting pressure control valve HV-46-1 F003 will have minimal affect on the down stream side of the valve because the flow control vave will is in auto and will open or close to maintain system flow. plausible to the examinee who does not recall normal value for PDl-46-1 R603 or how the flow controller in automatic will affect system pressure D Incorrect cooling water DP is within its normal band of 10 to 25 psi. adjusting pressure control valve HV-46-1 F003 will have minimal affect on the down stream side of the valve because the flow control vave will is in auto and will open or close to maintain system flow. plausible to the examinee who does not recall normal value for PDl-46-1 R603 or how the flow controller in automatic will affect system pressure LMK 2017 IL T NRC JANUARY Page: 130 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 37 Info Question Type: Multiple Choice Status: Active Always select on test? No for practice?
LMK 2017 ILT NRC JANUARY                         Page: 125 of 374                             17 January 2017
No Points: 1.00 rnme to Complete:
 
5 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 36 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     4.00 System ID:                       1455868 User-Defined ID:               Q#36 NEW Lesson Plan Objective:           LGSOPS1560.05 Topic:                           pool spray RO:                             4.0 SRO:                             3.9 KA#:                           230000 LMK 2017 ILT NRG JANUARY                     Page: 126 of 374       17 January 2017
3.50 System ID: 1455770 User-Defined ID: 0#37 NEW Lesson Plan Objective:
 
LGSOPS0046.2A Topic: drive water DP RO: 4.2 SRO: 4.4 KA#: 201001 2.2.44 LMK 2017 IL T NRC JANUARY Page: 131 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRC JANUARY Page: 132 of 374 2 2 201001 2.2.44 4.2/4.4 Control Rod Drive Hydraulic System Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and! directives affect plant and s stem conditions.
2 2
5 1 '#;{,'J,, 3 1 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 38 10: 1455177 Points: 1.00 WHICH ONE of the following identifies the required POST-LOCA Drywell ventilation fans and what the operation of these fans will ensure? EANS. Operation Ensures A. A,B,C,D A valid Drywell temperature indication B. A,B,G,H A valid Drywell temperature indication  
230000 A4.13 4.0/3.9 RHR/LPCI:
: c. A,B,C,D Prevent areas of high H2 and 02 concentrations in the DW D. A,B,G,H Prevent areas of high H2 and 02 concentrations in the DW Answer: D Answer Explanation lr.s 3.6.6.2 lists 1AV212,1BV212,1GV212,1 HV212 as the subset of drywell coolers that are the H2 mixing coolers. They discharge to the higher elevations to prevent localized accumulation of H2 and 02 from exceeding the lower flammability limits during LOCA conditions.
Torus/Suppression Pool Spray Mode Ability to manually operate and/or monitor in the
Incorrect answers either have incorrect fans or valid temperature.
                                                                              ;:Rev   2
selecting incorrect fans is plausible to if examinee fails to memorize correct fans. Valid temperature is plausible to examinee who believe he coolinq function of the hiqher elevations is the bases for requiring these fans LMK 2017 IL T NRG JANUARY Page: 133 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 38 Info Question Type: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice?
                                                                                ..     5 LMK 2017 ILT NRC JANUARY            Page: 127 of 374                        17 January 2017
No Points: 1.00 Time to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 128 of 374       17 January 2017
2.00 System ID: 1455177 User-Defined ID: 0#38 BANK Lesson Plan Objective:
 
LGSOPS0077.3 Topic: Post-LOCA DW Vent Fans And Design Function Of These Fans RO: 3.5 SRO: 3.8 KA#: 223001 LMK 2017 ILT NRC JANUARY Page: 134 of 37 4 17 January 2017 EXAMINATION ANSWER KEY Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 37                                               ID: 1455770                                 Points: 1.00 Unit 1 is at 75% reactor power.
LMK 2017 ILT NRG JANUARY IL T 15-01 January 2017 NRC test SRO  
Operators are preparing to continue raising power by control rod withdrawal Operators are performing S73.1.A NORMAL OPERATION OF THE REACTOR MANUAL CONTROL SYSTEM Given the following indications; OFUVE WATER Which of the following lists both the direction to manipulate the Drive Water Pressure Control Valve HV-46-1 F003 and the resulting pressure indication to be obtained, prior to withdrawing control rods?
Direction to manipulate Drive Water             Indication to obtain Pressure Control Valve HV-46-1 F003 A.     Close                                           PDl-46-1 R602 between 255-265 PSI B.     Open                                           PDl-46-1 R602 between 255-265 PSI
: c.      Close                                          PDl-46-1 R603 between 25-35 PSI D.      Open                                            PDl-46-1 R603 between 25-35 PSI Answer:        A
          !Answer Explanation LMK 2017 ILT NRC JANUARY                          Page: 129 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO A   Correct per 846.1.a normal operating pressure for CRD drive water is 255-265 psi. closing pressure control valve will raise drive water pressure B     Incorrect opening pressure comtrol valve will reduce pressure, plausible to the examinee who incorrectly recalls which side of the pressure regulating valve the indicator is on and does not take into account that the flow control valve wil auto open as the pressure control valve is closed C     Incorrect cooling water DP is within its normal band of 10 to 25 psi. adjusting pressure control valve HV-46-1 F003 will have minimal affect on the down stream side of the valve because the flow control vave will is in auto and will open or close to maintain system flow.
plausible to the examinee who does not recall normal value for PDl-46-1 R603 or how the flow controller in automatic will affect system pressure D     Incorrect cooling water DP is within its normal band of 10 to 25 psi. adjusting pressure control valve HV-46-1 F003 will have minimal affect on the down stream side of the valve because the flow control vave will is in auto and will open or close to maintain system flow.
plausible to the examinee who does not recall normal value for PDl-46-1 R603 or how the flow controller in automatic will affect system pressure LMK 2017 ILT NRC JANUARY                         Page: 130 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 37 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No
        ~uthorized for practice?         No Points:                         1.00 rnme to Complete:               5 Difficulty:                     3.50 System ID:                       1455770 User-Defined ID:                 0#37 NEW Lesson Plan Objective:           LGSOPS0046.2A Topic:                           drive water DP RO:                             4.2 SRO:                             4.4 KA#:                             201001 2.2.44 LMK 2017 ILT NRC JANUARY                       Page: 131 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 2
201001 2.2.44 4.2/4.4 Control Rod Drive Hydraulic System Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and!
directives affect plant and s stem conditions.
5
                                                                                  'Rft~; 1
                                                                                  '#;{,'J,, 3
                                                                                  ,,,~,;, \~ 1 LMK 2017 ILT NRC JANUARY            Page: 132 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 38                                             10: 1455177                                   Points: 1.00 WHICH ONE of the following identifies the required POST-LOCA Drywell ventilation fans and what the operation of these fans will ensure?
EANS.           Operation Ensures A.       A,B,C,D     A valid Drywell temperature indication B.       A,B,G,H     A valid Drywell temperature indication
: c.       A,B,C,D     Prevent areas of high H2 and 02 concentrations in the DW D.       A,B,G,H     Prevent areas of high H2 and 02 concentrations in the DW Answer:           D Answer Explanation lr.s 3.6.6.2 lists 1AV212,1BV212,1GV212,1 HV212 as the subset of drywell coolers that are the H2 mixing coolers. They discharge to the higher elevations to prevent localized accumulation of H2 and 02 from exceeding the lower flammability limits during LOCA conditions. Incorrect answers either have incorrect fans or valid temperature. selecting incorrect fans is plausible to if examinee fails to memorize correct fans. Valid temperature is plausible to examinee who believe he coolinq function of the hiqher elevations is the bases for requiring these fans LMK 2017 ILT NRG JANUARY                       Page: 133 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 38 Info Question Type:                   Multiple Choice Status:                         Active Alwavs select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1455177 User-Defined ID:                 0#38 BANK Lesson Plan Objective:           LGSOPS0077.3 Topic:                           Post-LOCA DW Vent Fans And Design Function Of These Fans RO:                             3.5 SRO:                             3.8 KA#:                             223001 LMK 2017 ILT NRC JANUARY                       Page: 134 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
3.5/3.8 Primary Containment System and Auxiliaries Knowledge of PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES design feature(s) and/or interlocks which provide for the following: Prevents hydrogen from reaching an explosive mixture lower 5
41.7 bank 557056 bank 557056 bank 557056


==Reference:==
==Reference:==
T.S. Bases  3/4.6.6          557056 KIA: 223001 K4.04, SG.07, K6.04 Used as SRO ONLY for ILT Proc Final - Good for RO Use LMK 2017 ILT NRG JANUARY              Page: 135 of 374                            17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 39                                              ID: 1454413                                  Points: 1.00 Unit 2 plant conditions:
    - OPCON 4
    - Preparations are being made to flood the main steam lines per GP-6.1, 'Shutdown Operations'
    -  RPV level is +90"
    - All appropriate steps in GP-6.1 have been performed HV-051-2F008 Shutdown Cooling outboard supply receives an inadvertent isolation signal and cannot be reopened WHICH of the following is the MINIMUM reactor level that will ensure adequate core circulation exists, per GP-6.1?
A.      Upset Range level indicates +61" B.      Shutdown Range level indicates +79" C.      Shutdown Range level indicates + 61" D.      Wide Range level indicates +61" Answer:        C Answer Explanation Shutdown Range level indicates +61 inches is correct: Per caution in GP-6.1, RPV level must be maintained greater than 60 inches on Shutdown Range or greater than 78 inches on Upset Range for sufficient natural circulation in the event of a loss of forced circulation.
Upset level indication at 61 inches is incorrect: Does not meet the minimum RPV level of 78 inches in GP-6.1.
Wide Range level indication at 61 inches is incorrect: Wide Range level is not referenced in GP-6.1.
Shutdown range +79 is incorrect not the minimum required level.
LMK 2017 ILT NRC JANUARY                        Page: 136 of 374                              17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 39 Info Question Type:                  Multiple Choice Status:                        Active Always select on test?          No Authorized for oractice?        No Points:                          1.00 rTime to Comolete:              4 Difficulty:                    2.00 System ID:                      1454413 User-Defined ID:                Q# 39 MODIFIED Lesson Plan Objective:          LOT0051.11 AHR fTooic:                          Natural Circ followina loss of SDC RO:                            3.5 SRO:                            3.6 KA#:                            295001.AK1 .01 LMK 2017 ILT NRC JANUARY                      Page: 137 of 374            17 January 2017
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:
295001 AK1 .01 3.5/3.6 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :Natural circulation lower 1&4 41.9&41.10 32 bank Modified LMK 2017 ILT NRG JANUARY            Page: 138 of 374                          17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY            Page: 139 of 374        17 January 2017


T.S. Bases 3/4.6.6 3.5/3.8 Primary Containment System and Auxiliaries Knowledge of PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES design feature(s) and/or interlocks which provide for the following:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 40                                                 10:1433148                                     Points: 1.00 Plant conditions are as follows:
Prevents hydrogen from reaching an explosive mixture lower 5 41.7 bank 557056 bank 557056 bank 557056 557056 KIA: 223001 K4.04, SG.07, K6.04 Used as SRO ONLY for IL T Proc Final -Good for RO Use Page: 135 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 39 ID: 1454413 Points: 1.00 Unit 2 plant conditions:
-OPCON 4 -Preparations are being made to flood the main steam lines per GP-6.1, 'Shutdown Operations'
-RPV level is +90" -All appropriate steps in GP-6.1 have been performed HV-051-2F008 Shutdown Cooling outboard supply receives an inadvertent isolation signal and cannot be reopened WHICH of the following is the MINIMUM reactor level that will ensure adequate core circulation exists, per GP-6.1? A. Upset Range level indicates
+61" B. Shutdown Range level indicates
+79" C. Shutdown Range level indicates
+ 61" D. Wide Range level indicates
+61" Answer: C Answer Explanation Shutdown Range level indicates
+61 inches is correct: Per caution in GP-6.1, RPV level must be maintained greater than 60 inches on Shutdown Range or greater than 78 inches on Upset Range for sufficient natural circulation in the event of a loss of forced circulation.
Upset level indication at 61 inches is incorrect: Does not meet the minimum RPV level of 78 inches in GP-6.1. Wide Range level indication at 61 inches is incorrect:
Wide Range level is not referenced in GP-6.1. Shutdown range +79 is incorrect not the minimum required level. LMK 2017 IL T NRC JANUARY Page: 136 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 39 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for oractice?
No Points: 1.00 rTime to Comolete:
4 Difficulty:
2.00 System ID: 1454413 User-Defined ID: Q# 39 MODIFIED Lesson Plan Objective:
LOT0051.11 AHR fTooic: Natural Circ followina loss of SDC RO: 3.5 SRO: 3.6 KA#: 295001.AK1
.01 LMK 2017 IL T NRC JANUARY Page: 137 of 37 4 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:
LMK 2017 IL T NRG JANUARY Page: 138 of 374 295001 AK1 .01 3.5/3.6 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION
:Natural circulation lower 1&4 41.9&41.10 bank Modified 32 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 139 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 40 10:1433148 Points: 1.00 Plant conditions are as follows:
* Suppression Pool temperature is 200&deg; F
* Suppression Pool temperature is 200&deg; F
* Drywall pressure is 8.0 psig
* Drywall pressure is 8.0 psig
* Suppression Pool pressure is 3.0 psig
* Suppression Pool pressure is 3.0 psig
* CST level is 1 foot Given the following graphs; Which of the following lists the system(s), and flow rates if any, that are able to inject without violating NPSH limits? CURVE * * &sect;: 100 U'l NPSH LEGENQ S1.u:um:uion E?Clot ere:uum: 1.ill!il 0 psi -4.99 psi 5 psi-9.99 psi 10 psi -14.99 psi 15 psi HPCI NPSH LIMIT 0 0 1,000 2,000 3,000 4,000 Pump Flow (gpm) LMK 2017 IL T NRC JANUARY Page: 140 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO RCIC NPSH LIMIT 0.. 100 0.. :::: tJj 50 0 0 100 200 300 400 500 600 Pump Flow (gpm) A. .B.Qili HPCI at 3500 GPM AND. RCIC at 500 GPM B. NEITHER HPCI at 3500 GPM QB RCIC at 500 GPM C. BCIC at 500 GPM but NQI HPCI at 3500 gpm D. HPCI at 3500 GPM but NQI BCIC at 500 gpm Answer: D Explanation A Incorrect plausible to the examinee who uses drywell pressure B Incorrect plausible to the examinee who cannot determine safe side of NPSH graph and who uses drywell pressure not pool pressure C Incorrect plausible to the examinee who uses drywell pressure tor the BCIC graph or cannot determine safe side of graph D Correct only HPCI at 3500 is on the safe side of graph LMK 2017 IL T NRC JANUARY Page: 141 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 40 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
* CST level is 1 foot Given the following graphs; Which of the following lists the system(s), and flow rates if any, that are able to inject without violating NPSH limits?
No Points: 1.00 ifime to Complete:
NPSH     CUB~Ji    LEGENQ CURVE              S1.u:um:uion E?Clot ere:uum:
4 Difficulty:
1.ill!il
3.00 System ID: 1433148 User-Defined ID: Q#40 NEW Lesson Plan Objective:
* 0 psi - 4.99 psi
LOT0340.14F ifopic: NPSH RO: 3.0 SRO: 3.4 KA#: 295026 EK1 .01 LMK 2017 IL T NRC JANUARY Page: 142 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
* 5 psi- 9.99 psi 10 psi - 14.99 psi
LMK 2017 IL T NRC JANUARY Page: 143 of 374 295026 EK1 .01 3.0/3.4 Suppression Pool High Water Temperature Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGHWATER TEMPERATURE  
                                      ~  15 psi HPCI NPSH LIMIT
:Pum NPSH y; 25 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 41 ID: 1650585 Points: 1.00 Unit 1 plant conditions are as follows: Unit has been shutdown due to major fuel damage An off-site release is in progress WHICH ONE of the following annunciators indicate that a release is in progress that will result in the exposure of a member of the public in an Unrestricted Area exceeding limits? A. 003 RAD E-1, NORTH STACK HI-HI RADIATION B. 107REACTOR1-1, MAIN STEAM LINE HIGH-HIGH RADIATION C. 003 RAD F-2, UNIT 1 & 2 SOUTH STACK HI RADIATION D. 109 RAD E-1, 1 REAC ENCL REFUEL FLR VENT EXHAUST RAD MON A/B HI-HI I DOWNSCALE Answer: A Answer Explanation HI-HI alarms indicate that the site is releasing in excess of ODCM limits and a member of the general public standing in an Unrestricted Area (at site boundary) would exceed legal limit (10CFR20) 003 RAD E-1 North Stack HI-HI Rad Hl-Setpoint 3.45e-5 uCi/cc for Noble Gas if his would correspond to a UE ie greater than 2.2E04 uCi/cc From the ODCM: 2.2 GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION K:ontrol 3.1.2 requires that an alarm setpoint be established for the noble gas monitoring channels (RY26-075A(B), RY26-185A(B), RY26-285A(B), and RY26-076) to ensure that the release rate of radioactive materials does not exceed the limits of Control 3.2.2.1.a, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrern/yr to the total body or 3000 mrern/yr to the skin A Correct B incorrect plausible to exarninee who belives MAIN STEAM LINE HI HI RAD alarm indicates a leak from the main steam line that will result in the exposure of a member of the public in an Unrestricted Area exceeding limits and that the HiHI willresult in escalation of E-plan C incorrect plausible to exarninee who belives Soth stack HI alarm will result in the exposure of a member of the public in an Unrestricted Area exceeding limits and that the HiHI willresult in escalation of E-plan D plausible tto the examinee who does not recall the reactor hvac radiation alarm setpoints A correct 003 RAD E-1 North Stack HI-HI Rad Hl-Setpoint 3.45e-5 uCi/cc for Noble Gas B incorrect LMK 2017 ILT NRC JANUARY Page: 144 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 IL T NRC JANUARY Page: 145 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 41 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
      &sect;:
No Points: 1.00 !Time to Complete:
U'l 100 0 +--~~--'~~~-i-~~~-i-~~~~~~-'-~--'
2 Difficulty:
0        1,000     2,000         3,000         4,000 Pump Flow (gpm)
2.20 System ID: 1650585 User-Defined ID: Q#41BANK Lesson Plan Objective:
LMK 2017 ILT NRC JANUARY                           Page: 140 of 374                               17 January 2017
LOT0720.03A rropic: Stack monitor RO: 3.9 SRO: 4.2 KA#: 295038 EK2.04 LMK 2017 ILT NRG JANUARY Page: 146 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 IL T NRG JANUARY Page: 147 of 374 1 295038 EK2.04 3.9/4.2 High Off-Site Release Rate Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE: .Rev:i ARC -MCR-003 'ff.* .. bank 562030 bank 562030 bank 562030 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 42 ID: 1454789 Points: 1.00 Unit 1 is operating at 100% power with the following:  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO RCIC NPSH LIMIT 0..     100 0..
-'1 B' Core Spray Pump is operating in Full Flow Test A reactor coolant leak occurs. -RPV water level reaches -133" -RPV pressure reaches 465 psig -Drywell pressure reaches 3.0 psig 12 seconds later, which of the following describes the status of: (1) '1 B' Core Spray Pump, .and (2) HV-052-1F015B, CORE SPRAY LOOP B TEST BYPASS PCIV? A. ( 1) Tripped and restarted (2) Closed and CANNOT be re-opened B. (1) Did not trip and is still running (2) Closed and CAN be re-opened C. (1) Tripped and is NOT running (2) Closed and CANNOT be re-opened D. ( 1) Did not trip and is still running (2) Open Answer: C Answer Explanation  
tJj 50 0
'C' is correct. The Core Spray initiation signal has been reached (high Drywell Pressure ( Low RPV level -129 inches). As such, the 1B CS Pump trips (LOCA shed) and will re-sequence back on, but not until t=15 seconds (with offsite power available).
0         100         200       300           400   500         600 Pump Flow (gpm)
Therefore, at t=12 seconds, the pump remains tripped. However, the Test Bypass valve auto-closed on the LOCA signal and will not re-open so long as the signal is present. 'A' is wrong. Plausible to the examinee who confuses the re-sequence time for the 'B'/'D' CS Pumps (i.e., t=15 sec, with offsite power available) with the re-sequence time for the 'A'/'C' CS Pumps (i.e., t=10 seconds, with offsite power available).  
A.     .B.Qili HPCI at 3500 GPM   AND. RCIC at 500 GPM B.     NEITHER HPCI at 3500 GPM QB RCIC at 500 GPM C.     BCIC at 500 GPM but NQI HPCI at 3500 gpm D. HPCI at 3500 GPM but NQI BCIC at 500 gpm Answer:         D
'B' is wrong. Plausible to the examinee who does not recognize that an initiation signal exists (thus, the pump did not LOCA shed), but who believes that the transient condition would result in closure of the Test Bypass valve. i'D' is wrong. Plausible to the examinee who does not recognize that an initiation signal exists; the pump is still running and the Test Bypass valve is still open. LMK 2017 IL T NRG JANUARY Page: 148 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 42 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
          ~nswer  Explanation A   Incorrect plausible to the examinee who uses drywell pressure B   Incorrect plausible to the examinee who cannot determine safe side of NPSH graph and who uses drywell pressure not pool pressure C   Incorrect plausible to the examinee who uses drywell pressure tor the BCIC graph or cannot determine safe side of graph D   Correct only HPCI at 3500 is on the safe side of graph LMK 2017 ILT NRC JANUARY                         Page: 141 of 374                             17 January 2017
No Points: 1.00 Time to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 40 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?         No Points:                         1.00 ifime to Complete:             4 Difficulty:                     3.00 System ID:                       1433148 User-Defined ID:               Q#40 NEW Lesson Plan Objective:           LOT0340.14F ifopic:                         NPSH RO:                             3.0 SRO:                             3.4 KA#:                           295026 EK1 .01 LMK 2017 ILT NRC JANUARY                       Page: 142 of 374     17 January 2017
2.00 Svstem ID: 1454789 User-Defined ID: Q# 42 BANK Lesson Plan Objective:
 
LGSOPS0052.07 Topic: Core Spray Response to Coolant Leak When operating in Full Flow Test RO: 4.2 SRO: 4.3 KA#: 295031 EK2.03 LMK 2017 IL T NRG JANUARY Page: 149 of 374 17 January 2017 EXAMINATION ANSWER KEY Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRG JANUARY ILT 15-01 January 2017 NRC test SRO Reactor Low Water Level WATER LEVEL Knowledge of the interrelations between REACTOR LOW WATER E21-1040 sht1 N/A bank 895494 bank N/A *R6V*' 5 th . 0 833342 lost n random selection coin toss Page: 150 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 43 ID: 1433212 Points: 1.00 Given the following:
295026 EK1 .01 3.0/3.4 Suppression Pool High Water Temperature Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGHWATER TEMPERATURE :Pum NPSH y;     25 LMK 2017 ILT NRC JANUARY            Page: 143 of 374                            17 January 2017
* The Fire Brigade is fighting a fire in the warehouse.
 
* The Motor Driven Fire Pump started and immediately tripped on spurious overcurrent.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 41                                                   ID: 1650585                                     Points: 1.00 Unit 1 plant conditions are as follows:
* The Diesel Driven Fire Pump is running and supplying the fire header with pressure at 97 psig.
Unit has been shutdown due to major fuel damage An off-site release is in progress WHICH ONE of the following annunciators indicate that a release is in progress that will result in the exposure of a member of the public in an Unrestricted Area exceeding limits?
* The overcurrent trip of the Motor Driven Fire Pump breaker is reset. Which of the following describes the Motor Driven and Diesel Driven fire pump response?
A.       003 RAD E-1, NORTH STACK HI-HI RADIATION B.       107REACTOR1-1, MAIN STEAM LINE HIGH-HIGH RADIATION C.       003 RAD F-2, UNIT 1 & 2 SOUTH STACK HI RADIATION D.       109 RAD E-1, 1 REAC ENCL REFUEL FLR VENT EXHAUST RAD MON A/B HI-HI I DOWNSCALE Answer:           A Answer Explanation HI-HI alarms indicate that the site is releasing in excess of ODCM limits and a member of the general public standing in an Unrestricted Area (at site boundary) would exceed legal limit (10CFR20) 003 RAD E-1 North Stack HI-HI Rad Hl-Setpoint 3.45e-5 uCi/cc for Noble Gas if his would correspond to a UE ie greater than 2.2E04 uCi/cc From the ODCM:
A. The Motor Driven Fire Pump starts and the Diesel Driven Fire Pump continues to run. B. The Motor Driven Fire Pump starts and the Diesel Driven Fire Pump stops immediately.
2.2 GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION K:ontrol 3.1.2 requires that an alarm setpoint be established for the noble gas
C. The Motor Driven Fire Pump remains in standby and the Diesel Driven Fire Pump continues to run. D. The Motor Driven Fire Pump starts and, assuming header pressure rises to and remains above 100 psig, the Diesel Driven Fire Pump stops 5 minute later. Answer: A Answer Explanation A Correct per ARC-MCR-005 A-1 Motor driven fire pump starts at 100 psig lowering there is no auto shutdown of the diesel driven fire pump B Incorrect Plausible to the examinee who believe there is a lead lag arrangement similar to the condensate transfer system C Incorrect Plausible to the examinee who does not recall the 100 psi start set point for the Motor Driven Fire Pump D Incorrect Plausible to the examinee who believe there is a lead lag arrangement similar to the condensate transfer system LMK 2017 ILT NRG JANUARY Page: 151 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 43 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
        ~ffluent monitoring channels (RY26-075A(B), RY26-185A(B), RY26-285A(B),
No Points: 1.00 Time to Complete:
and RY26-076) to ensure that the release rate of radioactive materials does not exceed the limits of Control 3.2.2.1.a, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrern/yr to the total body or 3000 mrern/yr to the skin A Correct B incorrect plausible to exarninee who belives MAIN STEAM LINE HI HI RAD alarm indicates a leak from the main steam line that will result in the exposure of a member of the public in an Unrestricted Area exceeding limits and that the HiHI willresult in escalation of E-plan C incorrect plausible to exarninee who belives Soth stack HI alarm will result in the exposure of a member of the public in an Unrestricted Area exceeding limits and that the HiHI willresult in escalation of E- plan D plausible tto the examinee who does not recall the reactor hvac radiation alarm setpoints A correct 003 RAD E-1 North Stack HI-HI Rad Hl-Setpoint 3.45e-5 uCi/cc for Noble Gas B incorrect LMK 2017 ILT NRC JANUARY                           Page: 144 of 374                                 17 January 2017
3 Difficulty:
 
2.00 System ID: 1433212 User-Defined ID: Q# 43 MODIFIED Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 ILT NRC JANUARY             Page: 145 of 374       17 January 2017
LGSOPS0022.5A Topic: Fire pp operation RO: 2.5 SRO: 2.6 KA#: 60000 AK2.04 LMK 2017 IL T NRG JANUARY Page: 152 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 ILT NRC JANUARY Page: 153 of 374 60000 AK2.04 2.5/2.6 Plant Fire On Site Knowledge of the interrelations between PLANT FIRE ON SITE and the following:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 41 Info Question Type:                   Multiple Choice Status:                         Active
Breakers I relays I and disconnects lower 8 41.7 ARC-MCR-005 A-1 ARC-MCR-005 B-2 modified South Texas ro*ect bank Modified South Tex as ro*ect bank 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 44 10: 145441.1 Points: 1.00 Unit 1 was operating at 100% power when an accident occurred.
        ~lwavs select on test?           No
Current plant conditions are as follows:
        ~uthorized for practice?         No Points:                         1.00
        !Time to Complete:             2 Difficulty:                     2.20 System ID:                       1650585 User-Defined ID:               Q#41BANK Lesson Plan Objective:           LOT0720.03A rropic:                         Stack monitor RO:                             3.9 SRO:                             4.2 KA#:                             295038 EK2.04 LMK 2017 ILT NRG JANUARY                       Page: 146 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
1 295038 EK2.04 3.9/4.2 High Off-Site Release Rate Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE:
                                                                                  .Rev:i ARC -MCR-003       'ff.*..
bank 562030 bank 562030 bank 562030 LMK 2017 ILT NRG JANUARY              Page: 147 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 42                                                   ID: 1454789                               Points: 1.00 Unit 1 is operating at 100% power with the following:
          - '1 B' Core Spray Pump is operating in Full Flow Test A reactor coolant leak occurs.
          - RPV water level reaches -133"
          - RPV pressure reaches 465 psig
          - Drywell pressure reaches 3.0 psig 12 seconds later, which of the following describes the status of:
(1) '1 B' Core Spray Pump, .and (2) HV-052-1F015B, CORE SPRAY LOOP B TEST BYPASS PCIV?
A.       (1) Tripped and restarted (2) Closed and CANNOT be re-opened B.       (1) Did not trip and is still running (2) Closed and CAN be re-opened C.       (1) Tripped and is NOT running (2) Closed and CANNOT be re-opened D.       ( 1) Did not trip and is still running (2) Open Answer:           C Answer Explanation
          'C' is correct. The Core Spray initiation signal has been reached (high Drywell Pressure ( Low RPV level -129 inches). As such, the 1B CS Pump trips (LOCA shed) and will re-sequence back on, but not until t=15 seconds (with offsite power available). Therefore, at t=12 seconds, the pump remains tripped. However, the Test Bypass valve auto-closed on the LOCA signal and will not re-open so long as the signal is present.
          'A' is wrong. Plausible to the examinee who confuses the re-sequence time for the 'B'/'D' CS Pumps (i.e., t=15 sec, with offsite power available) with the re-sequence time for the 'A'/'C' CS Pumps (i.e., t=10 seconds, with offsite power available).
          'B' is wrong. Plausible to the examinee who does not recognize that an initiation signal exists (thus, the pump did not LOCA shed), but who believes that the transient condition would result in closure of the Test Bypass valve.
i'D' is wrong. Plausible to the examinee who does not recognize that an initiation signal exists;
          ~herefore, the pump is still running and the Test Bypass valve is still open.
LMK 2017 ILT NRG JANUARY                               Page: 148 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 42 Info Question Type:                   Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 Svstem ID:                       1454789 User-Defined ID:                 Q# 42 BANK Lesson Plan Objective:           LGSOPS0052.07 Core Spray Response to Coolant Leak When operating in Full Topic:
Flow Test RO:                             4.2 SRO:                             4.3 KA#:                             295031 EK2.03 LMK 2017 ILT NRG JANUARY                       Page: 149 of 374                         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Reactor Low Water Level WATER LEVEL Knowledge of the interrelations between REACTOR LOW WATER E21-1040 sht1       *R6V*' 5 th . 0 N/A bank 895494 bank N/A 833342 lost n random selection coin toss LMK 2017 ILT NRG JANUARY            Page: 150 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 43                                                 ID: 1433212                                 Points: 1.00 Given the following:
* The   Fire Brigade is fighting a fire in the warehouse.
* The   Motor Driven Fire Pump started and immediately tripped on spurious overcurrent.
* The   Diesel Driven Fire Pump is running and supplying the fire header with pressure at 97 psig.
* The   overcurrent trip of the Motor Driven Fire Pump breaker is reset.
Which of the following describes the Motor Driven and Diesel Driven fire pump response?
A.       The Motor Driven Fire Pump starts and the Diesel Driven Fire Pump continues to run.
B.       The Motor Driven Fire Pump starts and the Diesel Driven Fire Pump stops immediately.
C.       The Motor Driven Fire Pump remains in standby and the Diesel Driven Fire Pump continues to run.
D.       The Motor Driven Fire Pump starts and, assuming header pressure rises to and remains above 100 psig, the Diesel Driven Fire Pump stops 5 minute later.
Answer:           A Answer Explanation A     Correct per ARC-MCR-005 A-1 Motor driven fire pump starts at 100 psig lowering there is no auto shutdown of the diesel driven fire pump B     Incorrect Plausible to the examinee who believe there is a lead lag arrangement similar to the condensate transfer system C     Incorrect Plausible to the examinee who does not recall the 100 psi start set point for the Motor Driven Fire Pump D     Incorrect Plausible to the examinee who believe there is a lead lag arrangement similar to the condensate transfer system LMK 2017 ILT NRG JANUARY                           Page: 151 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 43 Info Question Type:                 Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1433212 User-Defined ID:               Q# 43 MODIFIED Lesson Plan Objective:         LGSOPS0022.5A Topic:                           Fire pp operation RO:                             2.5 SRO:                           2.6 KA#:                           60000 AK2.04 LMK 2017 ILT NRG JANUARY                       Page: 152 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
60000 AK2.04 2.5/2.6 Plant Fire On Site Knowledge of the interrelations between PLANT FIRE ON SITE and the following:
Breakers I relays I and disconnects lower 8
41.7 ARC-MCR-005 A-1 ARC-MCR-005 B-2 modified South Texas ro*ect bank Modified South Tex as ro*ect bank LMK 2017 ILT NRC JANUARY            Page: 153 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 44                                               10: 145441.1                                   Points: 1.00 Unit 1 was operating at 100% power when an accident occurred. Current plant conditions are as follows:
* An ATWS is in progress
* An ATWS is in progress
* Reactor power is 13% * 'A' RPS status lights are lit * 'B' RPS status lights are out
* Reactor power is 13%
*   'A' RPS status lights are lit
*   'B' RPS status lights are out
* The second RPV level lowering has just been completed per T-117
* The second RPV level lowering has just been completed per T-117
* RPV level is being maintained between -186" and -161"
* RPV level is being maintained between -186" and -161"
* No floor actions for the second lowering have been taken Which one of the following will allow insertion of rods to terminate the ATWS A. Close the 46-1 F034 CRD Charging Water Header Supply AND reset RDCS B. Bypass the RWM AND reset RDCS C. Close the 46-1 F034 CRD Charging Water Header Supply AND bypass the RWM D. Bypass the RWM AND do NOT reset RDCS Answer: B Answer Explanation A Incorrect Close the 46-1 F034 CRD charging water header supply valve is not required for an electrical ATWS B Correct Bypassing the RWM is required since it is enforcing and rods will be inserted directly to position 00 and not to bank position.
* No floor actions for the second lowering have been taken Which one of the following will allow insertion of rods to terminate the ATWS A.       Close the 46-1 F034 CRD Charging Water Header Supply AND reset RDCS B.       Bypass the RWM AND reset RDCS C.       Close the 46-1 F034 CRD Charging Water Header Supply AND bypass the RWM D.       Bypass the RWM AND do NOT reset RDCS Answer:           B Answer Explanation A     Incorrect Close the 46-1 F034 CRD charging water header supply valve is not required for an electrical ATWS B   Correct Bypassing the RWM is required since it is enforcing and rods will be inserted directly to position 00 and not to bank position. since level is below -129 inches RDCS will lose power on the LOCA signal and need to be reset.
since level is below -129 inches RDCS will lose power on the LOCA signal and need to be reset. C Incorrect Close the 46-1 F034 CRD charging water header supply valve is not required for an electrical ATWS D Incorrect plausible to examinee who either does not recognize that a LOCA signal is present or that RDCS will need to be reset after the 4 KV bus is reset LMK 2017 ILT NRC JANUARY Page: 154 of 37 4 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 44 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
C     Incorrect Close the 46-1 F034 CRD charging water header supply valve is not required for an electrical ATWS D   Incorrect plausible to examinee who either does not recognize that a LOCA signal is present or that RDCS will need to be reset after the 4 KV bus is reset LMK 2017 ILT NRC JANUARY                         Page: 154 of 37 4                               17 January 2017
No Points: 1.00 !rime to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 44 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?       No Points:                         1.00
3.00 System ID: 1454411 User-Defined ID: 0#44 NEW Lesson Plan Objective:
        !rime to Complete:             3 Difficulty:                     3.00 System ID:                     1454411 User-Defined ID:               0#44 NEW Lesson Plan Objective:         LGSOPS2003.03 Tooic:                           ATWS RMCS RO:                             3.8 SRO:                           3.9 KA#:                           295037 EK2.11 LMK 2017 ILT NRC JANUARY                     Page: 155 of 374     17 January 2017
LGSOPS2003.03 Tooic: ATWS RMCS RO: 3.8 SRO: 3.9 KA#: 295037 EK2.11 LMK 2017 IL T NRC JANUARY Page: 155 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Comments:
 
LMK 2017 ILT NRC JANUARY Page: 156 of 374 Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVEAPRM DOWNSCALE OR UNKNOWN and the 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 45 ID: 1433350 Points: 1.00 Unit 1 is operating at 100% power when a Large drywell leak occurs.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Comments:
Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVEAPRM DOWNSCALE OR UNKNOWN and the LMK 2017 ILT NRC JANUARY            Page: 156 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 45                                             ID: 1433350                     Points: 1.00 Unit 1 is operating at 100% power when a Large drywell leak occurs.
* Suppression pool pressure is 20 psig up slow
* Suppression pool pressure is 20 psig up slow
* Suppression pool level is 15 feet steady 35 I 30 -C!) t:J) 25 a. -t:J) t:J) 20 w a:: a. ..J IS 0 _,,,,,,. / 0 a. a. 10 a. I / " :::::> t:J) 5 0 5 10 15 20 25 30 35 45 SUPP POOL WATER LEVEL (FT) LMK 2017 IL T NRC JANUARY Page: 157 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO WHICH of the following describes the action to be taken and the reason for performing this action? A. B. c. D. Action Rapidly depressurize per T-101 RPV Control Emergency blowdown per T-112 Emergency Slowdown Emergency blowdown per T-112 Emergency Slowdown Rapidly depressurize per T-101 RPV Control Answer: C Answer Explanation Reason Reduce Drywall pressure and temperature through the combined effects of evaporative and convective cooling Reduce Drywall pressure and temperature through the combined effects of evaporative and convective cooling Ensure that the pressure suppression function of the primary containment is maintained Ensure that the pressure suppression function of the primary containment is maintained Refer to T-102, specifically, the PC/P (Primary Containment Pressure) leg. Only when operators determine that the SAFE side of the Pressure Suppression Pressure (PSP) Curve, PC/P-3, cannot be maintained does Step PC/P-11 direct operators to perform a T-112 Emergency Slowdown.
* Suppression pool level is 15 feet steady 35 I
The T-102 Bases for Step PC/P-11 describes the PSP purpose as "to assure the pressure suppression function of primary containment is maintained." Rapidly depressurize per lf-101 is incorrect, plausible to the examines who plots the graph incorrectly and believes they are on the safe side of PC/P-3 but approaching the unsafe side. Reduce Drywall pressure and through the combined effects of evaporative and convective cooling is incorrect but plausible to the examines who confuses the drywall spray basis with the depressurization basis . . From the stem A LOCA is in progress causing Drywall pressure to rise, this will cause pool pressure to rise following drywall pressure at some at some slightly lower pressure based on pool level (Downcomer submergence)
C!)
A B c D Incorrect Rapidly depressurize per T-101 RPV Control Incorrect Emergency blowdown per T-112 Emergency Slowdown Correct Emergency blowdown per T-112 Emergency Slowdown Incorrect Rapidly depressurize per T-101 RPV Control LMK 2017 IL T NRG JANUARY Page: 158 of 374 Reduce Drywall pressure and temperature through the combined effects of evaporative and convective cooling Reduce Drywell pressure and temperature through the combined effects of evaporative and convective cooling Ensure that the pressure suppression function of the primary containment is maintained Ensure that the pressure suppression function of the primary containment is maintained 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 45 Info Question Tvpe: Multiple Choice Status: Active lA.lwavs select on test? No Authorized for practice?
t:J) 30
No Points: 1.00 Time to Complete:
: a. 25 t:J) t:J)                                                           _,,,,,,. ~
4 Difficulty:
                                                                              ~
2.50 System ID: 1433350 User-Defined ID: 0#45 NEW Lesson Plan Objective:
w 20                                                   ~*
LLOT1560.4 Topic: Recall reason for Emergency Slowdown based on PSP RO: 3.7 SRO: 4.1 KA#: 295024 EK3.04 LMK 2017 IL T NRG JANUARY Page: 159 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
a::
LMK 2017 IL T NRC JANUARY Page: 160 of 374 295024 EK3.04 3.7/4.1 295024 High Drywell Presure Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE:
a.
EK3.04 tEmergency de ressurization 41.5, 41.10 T-101 T-101 bases T-102 T-102 bases 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 46 ID: 1649449 Points: 1.00 Unit 2 is in OPCON 3 when a LOCA occurs. Suppression Pool pressure is 4 psig Shutdown cooling inboard suction valve HV-51-2F009 cannot be opened The CRS directs performance of S41.7.B Use Of SRV's and Suppression Pool Cooling As An Alternate Shutdown Cooling Method. Which of the following describes the minimum reactor pressure required to ensure sufficient flow rate and the suction source(s) allowed for injection (Suppression Pool and/or CST) after raising RPV level<! 150 inches? Minimum Reactor Pressure Suction Source(s)
..J 0      IS
Allowed For Injection A. 50 psig Suppression Pool ONLY B. 54 psig Suppression Pool ONLY c. 50 psig Suppression Pool AND CST D. 54 psig Suppression Pool AND CST Answer: B Answer Explanation A Incorrect plausible to examinee who recalls the 50 psi limit for SRV to open but does not recll that the limit is 50 psi above pool pressure B Correct reactor pressure must be 50 psig> than pool pressure and after level is raised injection with cond. transfer and CAD is secured. C Incorrect plausible to examinee who recalls the 50 psi limit for SRV to open but does not recll that the limit is 50 psi above pool pressure and or does not recognize that after level is raised injection with cond. transfer and CAD is secured D Incorrect after level is raised injection with cond. transfer and CRD is secured LMK 2017 IL T NRG JANUARY Page: 161 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 46 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
                                          ~
No Points: 1.00 Time to Complete:
                                              /
3 Difficulty:
0                     I a.
2.50 System ID: 1649449 User-Defined ID: 0#46 NEW Lesson Plan Objective:
: a. 10                     /
LOT1550.03 (ON-120) Topic: alt SOC RO: 3.6 SRO: 3.8 KA#: 295021 AK3.05 LMK 2017 IL T NRG JANUARY Page: 162 of 37 4 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
: a.                       "
LMK 2017 IL T NRC JANUARY Page: 163 of 37 4 295021 AK3.05 3.6/3.8 Loss of Shutdown Cooling Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING : Establishing alternate heat removal flow aths lower 4 41.5 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 164 of 374 17 January 2017 47 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 10:1649473 Points: 1.00 Unit 1 plant conditions are as follows: RPV level is being controlled from the Remote Shutdown Panel (RSP) per SE-1 RPV level is+ 50 inches up slow RCIC flow is zero gpm at 2400 rpm RPV pressure is 950 psig, down slow WHICH ONE of the following identifies a required action and the reason it is necessary?
t:J) 5 0
ACTION A. Trip HPCI immediately B. Trip HPCI if level exceeds +54 inches C. Trip HPCI immediately D. Trip HPCI if level exceeds +54 inches Answer: D [Answer Explanation BEASON Prevent excessive RPV cooldown due to uncontrolled steam usage Prevent excessive RPV cooldown due to uncontrolled steam usage Prevent reactor overfill due to fire induced spurious initiation Prevent reactor overfill due to fire induced spurious initiation LMK 2017 ILT NRC JANUARY Page: 165 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO NOTE 1. Reactor level rise without explanation may be caused by a spurious, fire caused HPCI initiation.
5         10         15         20         25             30 35     45 SUPP POOL WATER LEVEL (FT)
Step 4.3.2 is a PROMPT Action from the fire safe shutdown analysis, to be completed within 4 minutes, to stop HPCI injection AND prevent reactor overfill.  
LMK 2017 ILT NRC JANUARY                       Page: 157 of 374               17 January 2017
: 2. HPCI Emergency Shutdown Key (HPCI SHUTDOWN KEY H2191) is already installed in HS-56-*62 in Remote Shutdown Panel (ASP) *O-C201 SE-1 step 4.3.2 IF Reactor level is rising above +54 inches AND continues to rise after RCIC flow is reduced, THEN using HPCI Emergency Shutdown Key H2191 PLACE HS-56-*62, "HPCI EMERG S/D SWITCH," to "OFF" at *OC201, to trip HPCI. D correct per step 4.3.2 do not trip HPCI until level is > +54 rising with no injection.
 
HPCI would normally run to maintain level between -39 and +54 HPCI is tripped to prevent vessel overfill A Incorrect plausible to examinee who believe that HPCI must always be tripped at the RSP as a 4 minute immediate action and I or believe the basis is to limit cooldown.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO WHICH of the following describes the action to be taken and the reason for performing this action?
B Incorrect plausible to examinee who does not recall basis for tripping HPCI but remembers that injection through core spray will cause pressure reduction (will not exceed cooldown rate) C Incorrect for the reasons stated above KIA does not differentiate between main turb and HPCl/RCIC at LGS MSIVs are closed during MCR abandonment there is no procedural basis or UFSAR information on separating gen. from grid unable to write a question on main turb for this K/A LMK 2017 ILT NRC JANUARY Page: 166 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 47 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
Action                                                  Reason A.       Rapidly depressurize per T-101 RPV             Reduce Drywall pressure and temperature Control                                         through the combined effects of evaporative and convective cooling B.        Emergency blowdown per T-112                   Reduce Drywall pressure and temperature Emergency Slowdown                             through the combined effects of evaporative and convective cooling
No Points: 1.00 !Time to Complete:
: c.        Emergency blowdown per T-112                   Ensure that the pressure suppression Emergency Slowdown                             function of the primary containment is maintained D.        Rapidly depressurize per T-101 RPV             Ensure that the pressure suppression Control                                         function of the primary containment is maintained Answer:           C Answer Explanation Refer to T-102, specifically, the PC/P (Primary Containment Pressure) leg. Only when operators determine that the SAFE side of the Pressure Suppression Pressure (PSP) Curve, PC/P-3, cannot be maintained does Step PC/P-11 direct operators to perform a T-112 Emergency Slowdown. The T-102 Bases for Step PC/P-11 describes the PSP purpose as "to assure the pressure suppression function of primary containment is maintained." Rapidly depressurize per lf-101 is incorrect, plausible to the examines who plots the graph incorrectly and believes they are on the safe side of PC/P-3 but approaching the unsafe side. Reduce Drywall pressure and
2 Difficulty:
        ~emperature through the combined effects of evaporative and convective cooling is incorrect but plausible to the examines who confuses the drywall spray basis with the depressurization basis .
2.00 Svstem ID: 1649473 User-Defined ID: Q# 47 MODIFIED Lesson Plan Objective:
        .From the stem A LOCA is in progress causing Drywall pressure to rise, this will cause pool pressure to rise following drywall pressure at some at some slightly lower pressure based on pool level (Downcomer submergence)
SE-1 TRAINING Topic: SE-1 HPCI Shutdown Requirement RO: 3.7 SRO: 3.8 KA#: 295016 AK3.02 LMK 2017 IL T NRG JANUARY Page: 167 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
A     Incorrect Rapidly depressurize per T-101           Reduce Drywall pressure and temperature RPV Control                                       through the combined effects of evaporative and convective cooling B    Incorrect Emergency blowdown per T-112           Reduce Drywell pressure and temperature Emergency Slowdown                               through the combined effects of evaporative and convective cooling c    Correct Emergency blowdown per T-112             Ensure that the pressure suppression Emergency Slowdown                               function of the primary containment is maintained D    Incorrect Rapidly depressurize per T-101         Ensure that the pressure suppression RPV Control                                       function of the primary containment is maintained LMK 2017 ILT NRG JANUARY                         Page: 158 of 374                                 17 January 2017
LMK 2017 ILT NRG JANUARY Page: 168 of 374 295016 AK3.02 Control Room Abandonment Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT  
 
: 586875 modified 586875 modified 586875 modified 7 3 17 January 2017 48 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO ID: 1454791 Unit 2 plant conditions are as follows: Startup in progress with Reactor Pressure at 380 psig Normal Electrical lineup Points: 1.00 A small coolant leak results in Drywall pressure rising to 2 psig and all automatic actions occur as designed.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 45 Info Question Tvpe:                  Multiple Choice Status:                          Active lA.lwavs select on test?          No Authorized for practice?        No Points:                         1.00 Time to Complete:               4 Difficulty:                     2.50 System ID:                       1433350 User-Defined ID:                 0#45 NEW Lesson Plan Objective:           LLOT1560.4 Topic:                           Recall reason for Emergency Slowdown based on PSP RO:                             3.7 SRO:                             4.1 KA#:                             295024 EK3.04 LMK 2017 ILT NRG JANUARY                       Page: 159 of 374                         17 January 2017
WHICH ONE of the following identifies the source of power to Safeguard and Non-Safeguard DC loads one (1) minute later? (No operator action has been taken.) SAFEGUARD DC SOURCE NON-SAFEGUARD DC SOURCE A. Batteries Batteries B. Batteries Battery Chargers c. Battery Chargers Batteries D. Battery Chargers Battery Chargers Answer: C Answer Explanation is correct. All Battery Chargers are powered from Safeguard AC Power. With the provided conditions, a LOCA signal will occur. This will result in the tripping of all Non-Safeguard loads powered from Safeguard Buses. Two of the Non-Safeguard Battery Chargers will shunt trip (2BC01 and 2BC02) and one (2BC) is powered from D224-G-D MCC which will trip on a LOCA and must be manually reset in the MCR. All of the Divisional Battery Chargers will be re-energized automatically when he respective 480 VAC Load Center automatically re-closes 3 seconds following the LOCA signal.
 
is incorrect.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Th is wou Id be correct immediately following the LOCA as the 480 VAC Load Center will trip on the LOCA signal which will de-energize all of the battery chargers.
295024 EK3.04 3.7/4.1 295024 High Drywell Presure Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE:
However, 3 seconds later the Load Center Breaker will auto re-close and re-energize the Safeguard Battery Chargers.
EK3.04 tEmergency de ressurization 41.5, 41.10 T-101 T-101 bases T-102 T-102 bases LMK 2017 ILT NRC JANUARY            Page: 160 of 374                          17 January 2017
The Non-Safeguard Battery Chargers will shunt trip and must be manually reset. Until they are reset, Non-Safeguard DC loads will be supplied from batteries.
 
LMK 2017 IL T NRC JANUARY Page: 169 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 48 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 46                                                 ID: 1649449                                   Points: 1.00 Unit 2 is in OPCON 3 when a LOCA occurs.
No Points: 1.00 rnme to Complete:
Suppression Pool pressure is 4 psig Shutdown cooling inboard suction valve HV-51-2F009 cannot be opened The CRS directs performance of S41.7.B Use Of SRV's and Suppression Pool Cooling As An Alternate Shutdown Cooling Method.
5 Difficulty:
Which of the following describes the minimum reactor pressure required to ensure sufficient flow rate and the suction source(s) allowed for injection (Suppression Pool and/or CST) after raising RPV level<! 150 inches?
2.00 System ID: 1454791 User-Defined ID: Q # 48 BANK Lesson Plan Objective:
Minimum Reactor Pressure                         Suction Source(s) Allowed For Injection A.       50 psig                                         Suppression Pool ONLY B.       54 psig                                         Suppression Pool ONLY
LGSOPS0095
: c.       50 psig                                         Suppression Pool AND CST D.       54 psig                                         Suppression Pool AND CST Answer:           B Answer Explanation A   Incorrect plausible to examinee who recalls the 50 psi limit for SRV to open but does not recll that the limit is 50 psi above pool pressure B   Correct reactor pressure must be 50 psig> than pool pressure and after level is raised injection with cond. transfer and CAD is secured.
-7 rropic: Effect of LOCA signal on Battery Chargers RO: 3.6 SRO: 3.7 KA#: 295003 AA 1. 04 LMK 2017 IL T NRG JANUARY Page: 170 of 374 17 January 2017 EXAMINATION ANSWER KEY Comments:
C   Incorrect plausible to examinee who recalls the 50 psi limit for SRV to open but does not recll that the limit is 50 psi above pool pressure and or does not recognize that after level is raised injection with cond. transfer and CAD is secured D   Incorrect after level is raised injection with cond. transfer and CRD is secured LMK 2017 ILT NRG JANUARY                           Page: 161 of 374                               17 January 2017
LMK 2017 ILT NRC JANUARY ILT 15-01January2017 NRC test SRO 295003 AA 1.04 3.6/3. 7 Partial or Complete Loss of A.C. Power Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: D.C. electrical minor rev to match KA 45 6 K6. Knowledge of the effect that a loss or malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION: (CFR: 41.7 / 45.7) K6.0l A.C. electrical distribution  
 
............................. . . . . . . . . . . . . . . . . . . .
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 46 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?       No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.50 System ID:                     1649449 User-Defined ID:               0#46 NEW Lesson Plan Objective:         LOT1550.03 (ON-120)
3.2 3.5 Page: 171 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 49 10:1455250 Points: 1.00 Plant conditions are as follows:
Topic:                         alt SOC RO:                             3.6 SRO:                           3.8 KA#:                           295021 AK3.05 LMK 2017 ILT NRG JANUARY                     Page: 162 of 374    17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
295021 AK3.05 3.6/3.8 Loss of Shutdown Cooling Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING :
Establishing alternate heat removal flow aths lower 4
41.5 LMK 2017 ILT NRC JANUARY            Page: 163 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 164 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 47                                              10:1649473                                       Points: 1.00 Unit 1 plant conditions are as follows:
RPV level is being controlled from the Remote Shutdown Panel (RSP) per SE-1 RPV level is+ 50 inches up slow RCIC flow is zero gpm at 2400 rpm RPV pressure is 950 psig, down slow WHICH ONE of the following identifies a required action and the reason it is necessary?
ACTION                                           BEASON A.       Trip HPCI immediately                         Prevent excessive RPV cooldown due to uncontrolled steam usage B.       Trip HPCI if level exceeds +54 inches         Prevent excessive RPV cooldown due to uncontrolled steam usage C.       Trip HPCI immediately                         Prevent reactor overfill due to fire induced spurious initiation D.       Trip HPCI if level exceeds +54 inches         Prevent reactor overfill due to fire induced spurious initiation Answer:         D
[Answer Explanation LMK 2017 ILT NRC JANUARY                        Page: 165 of 374                                  17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO NOTE
: 1. Reactor level rise without explanation may be caused by a spurious, fire caused HPCI initiation. Step 4.3.2 is a PROMPT Action from the fire safe shutdown analysis, to be completed within 4 minutes, to stop HPCI injection AND prevent reactor overfill.
: 2. HPCI Emergency Shutdown Key (HPCI SHUTDOWN KEY H2191) is already installed in HS-56-*62 in Remote Shutdown Panel (ASP) *O-C201 SE-1 step 4.3.2 IF Reactor level is rising above +54 inches AND continues to rise after RCIC flow is reduced, THEN using HPCI Emergency Shutdown Key H2191 PLACE HS-56-*62, "HPCI EMERG S/D SWITCH," to "OFF" at *OC201, to trip HPCI.
D correct per step 4.3.2 do not trip HPCI until level is > +54 rising with no injection. HPCI would normally run to maintain level between -39 and +54 HPCI is tripped to prevent vessel overfill A Incorrect plausible to examinee who believe that HPCI must always be tripped at the RSP as a 4 minute immediate action and I or believe the basis is to limit cooldown.
B Incorrect plausible to examinee who does not recall basis for tripping HPCI but remembers that injection through core spray will cause pressure reduction (will not exceed cooldown rate)
C Incorrect for the reasons stated above KIA does not differentiate between main turb and HPCl/RCIC at LGS MSIVs are closed during MCR abandonment there is no procedural basis or UFSAR information on separating gen. from grid unable to write a question on main turb for this K/A LMK 2017 ILT NRC JANUARY                         Page: 166 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 47 Info Question Type:                   Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00
      !Time to Complete:               2 Difficulty:                     2.00 Svstem ID:                       1649473 User-Defined ID:                 Q# 47 MODIFIED Lesson Plan Objective:           SE-1 TRAINING Topic:                           SE-1 HPCI Shutdown Requirement RO:                             3.7 SRO:                             3.8 KA#:                             295016 AK3.02 LMK 2017 ILT NRG JANUARY                       Page: 167 of 374         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
295016 AK3.02 Control Room Abandonment Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT :
7 3
586875 modified 586875 modified 586875 modified LMK 2017 ILT NRG JANUARY            Page: 168 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 48                                                                ID: 1454791                                                       Points: 1.00 Unit 2 plant conditions are as follows:
Startup in progress with Reactor Pressure at 380 psig Normal Electrical lineup A small coolant leak results in Drywall pressure rising to 2 psig and all automatic actions occur as designed.
WHICH ONE of the following identifies the source of power to Safeguard and Non-Safeguard DC loads one (1) minute later?
(No operator action has been taken.)
SAFEGUARD DC SOURCE                                                       NON-SAFEGUARD DC SOURCE A.         Batteries                                                                   Batteries B.         Batteries                                                                   Battery Chargers
: c.         Battery Chargers                                                           Batteries D.         Battery Chargers                                                           Battery Chargers Answer:                 C Answer Explanation
        ~LLJ..-cLL~UY:na..a~~~~J.Ll!~L),j~..liiU~L.liil::uJii~:...u:!ooUJi.:.;z.oi::.~u.u:llll~~                                    is correct. All Battery Chargers are powered from Safeguard AC Power. With the provided conditions, a LOCA signal will occur. This will result in the tripping of all Non-Safeguard loads powered from Safeguard Buses. Two of the Non-Safeguard Battery Chargers will shunt trip (2BC01 and 2BC02) and one (2BC) is powered from D224-G-D MCC which will trip on a LOCA and must be manually reset in the MCR. All of the Divisional Battery Chargers will be re-energized automatically when he respective 480 VAC Load Center automatically re-closes 3 seconds following the LOCA signal.
        ~LLJ...Jiiliuo.sz...:::.-'Zl!:lc:J~JJ.l!iDJ.L),j~.JiiU~L.liil::uJii~:...u:!ootl.Jl::sl.~li&!olu.u:llllOl....lo~ is incorrect. Th is wou Id be correct immediately following the LOCA as the 480 VAC Load Center will trip on the LOCA signal which will de-energize all of the battery chargers. However, 3 seconds later the Load Center Breaker will auto re-close and re-energize the Safeguard Battery Chargers. The Non-Safeguard Battery Chargers will shunt trip and must be manually reset. Until they are reset, Non-Safeguard DC loads will be supplied from batteries.
LMK 2017 ILT NRC JANUARY                                          Page: 169 of 374                                                  17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 48 Info Question Type:                  Multiple Choice Status:                        Active
        ~lways select on test?          No
        ~uthorized for practice?        No Points:                          1.00 rnme to Complete:              5 Difficulty:                    2.00 System ID:                      1454791 User-Defined ID:                Q # 48 BANK Lesson Plan Objective:          LGSOPS0095 - 7 rropic:                          Effect of LOCA signal on Battery Chargers RO:                              3.6 SRO:                            3.7 KA#:                            295003 AA 1. 04 LMK 2017 ILT NRG JANUARY                      Page: 170 of 374                    17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:
295003 AA 1.04 3.6/3. 7 Partial or Complete Loss of A.C. Power Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.
POWER: D.C. electrical 45 6
minor rev to match KA K6. Knowledge of the effect that a loss or malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION:
(CFR: 41.7 / 45.7)
K6.0l A.C. electrical distribution ............................. .
                                . . . . . . . . . . . . . . . . . . 3.2 3.5 LMK 2017 ILT NRC JANUARY                Page: 171 of 374                                   17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 49                                                         10:1455250                                   Points: 1.00 Plant conditions are as follows:
* OA MCR Chiller in service
* OA MCR Chiller in service
* 1 A OW Chiller in service
* 1A OW Chiller in service
* 2B OW Chiller in service
* 2B OW Chiller in service
* 012 O/G running for its monthly surveillance test
* 012 O/G running for its monthly surveillance test
* OB ESW is running, an EO has just closed 11-1013 UNIT 1 SW TO LOOP B ESW and 11-2013 UNIT 2 SW TO LOOP B ESW per the 012 surveillance test. Shortly thereafter, OB ESW pump trips WHICH ONE of the following groups of equipment lose cooling water? A. 1A Orywell Chiller, Unit 1 HPCI, and Unit 1 RCIC B. 2A Orywell Chiller, Unit 2 HPCI, and Unit 1 RCIC C. Unit 2 HPCI, and Unit 2 RCIC 0. OA MCR Chiller, Unit 1 HPCI, and Unit 1 RCIC Answer: C Answer Explanation Reference SIM-12 drawing or P&IO 11 sheet 2 and 3 with no flow in B ESW loop and the 11-1013 closed flow is lost to the OB MCR chiller unit 2 HPCI and unit 2 RCIC. The lineup for sw to HPCI and RCIC is as followes 11-1010 unit 1 SW to unit 1 A ESW provides a flow path for SW to unit 1 HPCI and RCIC. 11-2013 unt 2 SW to unit 2 B ESW provides flow to unit 2 HPCI and RCIC ........ ..........  
* OB ESW is running, an EO has just closed 11-1013 UNIT 1 SW TO LOOP B ESW and 11-2013 UNIT 2 SW TO LOOP B ESW per the 012 surveillance test.
*.._..,plausible to the examinee who doesn't recall the chillers cooled by ESW or that unit HPCI sw is from the 11-2013.
Shortly thereafter, OB ESW pump trips WHICH ONE of the following groups of equipment lose cooling water?
* Plausible to the examinee who reverses the 11-1010 and 11-2013 loads . LMK 2017 IL T NRG JANUARY Page: 172 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 49 Info Question Tvoe: Multiple Choice Status: Active Always select on test? No Authorized for practice?
A.       1A Orywell Chiller, Unit 1 HPCI, and Unit 1 RCIC B.       2A Orywell Chiller, Unit 2 HPCI, and Unit 1 RCIC C.       Unit 2 HPCI, and Unit 2 RCIC
No Points: 1.00 Time to Complete:
: 0.       OA MCR Chiller, Unit 1 HPCI, and Unit 1 RCIC Answer:                   C Answer Explanation Reference SIM-12 drawing or P&IO 11 sheet 2 and 3 with no flow in B ESW loop and the 11-1013 closed flow is lost to the OB MCR chiller unit 2 HPCI and unit 2 RCIC. The lineup for sw to HPCI and RCIC is as followes 11-1010 unit 1 SW to unit 1 A ESW provides a flow path for SW to unit 1 HPCI and RCIC. 11-2013 unt 2 SW to unit 2 B ESW provides flow to unit 2 HPCI and RCIC
4 Difficulty:
        ........~~..........*.._..,plausible to the examinee who doesn't recall the chillers cooled by ESW or that unit HPCI sw is from the 11-2013.
2.50 Svstem ID: 1455250 User-Defined ID: Q# 49 MODIFIED Lesson Plan Objective:
* Plausible to the examinee who reverses the 11-1010 and 11-2013 loads .
LGSOPS0011.7A lfopic: Recoqnize Service Water/ESW shared loads lost RO: 3.3 SRO: 3.4 KA#: 295018 AA 1.02 LMK 2017 IL T NRC JANUARY Page: 173 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:
LMK 2017 ILT NRG JANUARY                                   Page: 172 of 374                               17 January 2017
LMK 2017 ILT NRC JANUARY Page: 174 of 374 1 295018 AA 1.02 3.3/3.4 Partial or Complete Loss of Component Cooling Water Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System loads 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 175 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 50 10:1455199 Points: 1.00 Plant conditions are as follows: -Both Units are in their normal/preferred electrical lineup A grid disturbance causes a trip of the 10 Station Aux Bus Supply Breaker (105). 20 seconds after the trip of the 105 breaker, the PRO reviews the 4KV breaker alignment and reports the following:  
 
-013 Bus is de-energized  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 49 Info Question Tvoe:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               4 Difficulty:                     2.50 Svstem ID:                       1455250 User-Defined ID:                 Q# 49 MODIFIED Lesson Plan Objective:           LGSOPS0011.7A lfopic:                         Recoqnize Service Water/ESW shared loads lost RO:                             3.3 SRO:                             3.4 KA#:                             295018 AA 1.02 LMK 2017 ILT NRC JANUARY                     Page: 173 of 374                         17 January 2017
-013 O/G is running unloaded -All other 4 KV buses are energized WHICH ONE of the following identifies the likely cause of the 013 Safeguard Bus remaining de-energized?
 
A. 013 O/G Lockout B. 013 Bus Lockout C. 20 Station Aux Bus Lockout 0. 101 Safeguard Transformer Lockout Answer: B !Answer Explanation LMK 2017 IL T NRC JANUARY Page: 176 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Initially, D13 is powered from the 101 Safeguard Transformer through the 101-D13 breaker. hen the 1 O Station Aux Bus Supply Breaker (105) trips, the 101 Safeguard Transformer is de-energized, causing the 101-D13 breaker to trip on 101 Transformer Undervoltage ( <70%). ne (1) second later, the 201-D13 breaker should auto-close to re-energize the D13 bus. Similarly, at 0.5 seconds after the dead-bus condition on D13, the D13 DIG will get an auto-start ignal. However, if the 201-D13 breaker did close, the D13 DG Output breaker will not attempt to auto-close when all of its other closing permissives are satisfied.
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:
The stem conditions indicating hat the D13 bus is still de-energized at T =20 seconds from the 105 breaker trip means that neither the 201-D13 breaker nor the D13 DIG Output breaker have closed in on the bus. 'B' is correct. A D13 Bus Lockout will prevent both the 201-D13 and D13 DIG Output breakers ram closing in on the bus (see ARC-MCR-121, A 1 ). D12 and D14 bus are supplied from 201 bus nd unaffected by the trip of the 105 breaker. D11 DG will start on the undervoltage on D11 bus hen 101 bus losses power and the D111101 breaker trips, but the DG will not close in on the bus because before the DG gets up to speed the 2011D11 breaker will close. 'A' is wrong because it suggests that a D13 DIG Lockout would not only prevent the D13 DIG utput breaker from closing (which it will), but also prevent the 201-D13 feeder breaker from losing (which it WON'T). Plausible to the examines who either mis-understands the breakers hat are affected by a lockout, or who fails to review the D13 DIG Lockout ARC (ARC-MCR-121, C1). 'C' is wrong. Although a 20 Station Aux Bus Lockout will prevent the 201-D13 breaker from closing (because the 201 Transformer voltage is < 70%), it will NOT prevent closure of the D13 DIG Output breaker. 'D' is wrong. See ARC-MCR-120, F1. Only the 101 Safeguard Transformer Supply Breaker (from the 1 O Station Aux Bus) receives a .d.imci. trip from this kind of lockout. This lockout will not prevent closure of the 201-D13 feeder breaker, or of the D13 DIG Output breaker. Plausible to he examines who either mis-understands the breakers that are affected by a lockout, or who fails o review the 101 Transformer Lockout ARC ARC-MCR-120, F1 . LMK 2017 ILT NRG JANUARY Page: 177 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 50 Info Question Tvpe: Multiple Choice Status: Active !Always select on test? No !Authorized for practice?
1 295018 AA 1.02 3.3/3.4 Partial or Complete Loss of Component Cooling Water Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System loads LMK 2017 ILT NRC JANUARY            Page: 174 of 374                        17 January 2017
No Points: 1.00 tTime to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 175 of 374       17 January 2017
2.00 System ID: 1455199 User-Defined ID: Q# 50 BANK Lesson Plan Objective:
 
LGSOPS0092A.4A tTooic: Determininq Cause of a De-energized 4 KV Safeguard Bus RO: 3.9 SRO: 4.0 KA#: 700000 LMK 2017 IL T NRG JANUARY Page: 178 of 37 4 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 50                                             10:1455199                               Points: 1.00 Plant conditions are as follows:
LMK 2017 IL T NRG JANUARY Page: 179 of 374 700000AA1.05 3.9/4.0 Generator Voltage and Electric Grid Disturbances Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:
        - Both Units are in their normal/preferred electrical lineup A grid disturbance causes a trip of the 10 Station Aux Bus Supply Breaker (105).
ARC-MCR-121 , Al ARC-MCR-121 , Cl ARC-MCR-008 , A3 ARC-MCR-120 , Fl 295003 AK2.03 features 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 51 10:1649810 Points: 1.00 Unit 1 plant conditions are as follows:
20 seconds after the trip of the 105 breaker, the PRO reviews the 4KV breaker alignment and reports the following:
* OPCON 5 with fuel handling in-progress per FH-105, Core Component Movement -Core Transfer
        - 013 Bus is de-energized
* The SRO on the refueling platform reports that a fuel bundle is being lowered into the core While the bundle is being lowered, the RO reports that SRM "1 B" count rate has risen from 230 cps to 475 cps. WHICH ONE of the following describes the ability to continue lowering the bundle, and whether entry into ON-120, "Fuel Handling Problems" is required?
        - 013 O/G is running unloaded
A. B. c. D. Ability to Continue Lowering the Bundle into the Core Bundle may NOT be lowered until count rate stabilizes Bundle may NOT be lowered until count rate stabilizes Continued lowering of the bundle IS permitted Continued lowering of the bundle IS permitted Answer: A Answer Explanation Entry into ON-120 "Fuel Handling Problems NOT Required Required NOT Required Required A Correct Since SAM count rate doubled once, per FH-105 step 3.7.4 lowering of the bundle must stop until count rate stabilizes at a value of less than 2 doublings, and no spiking or indication of SRM inoperability exists, then lowering the bundle may be continued.
        - All other 4 KV buses are energized WHICH ONE of the following identifies the likely cause of the 013 Safeguard Bus remaining de-energized?
B Incorrect ON-120 entry is only required if SAM count rate doubles twice (i.e. one doubling would be from 230 to 460, a second doubling would be from 460 to 920) plausible to examinee who confuses FH-105 action with ON-120 entry C Incorrect Plausible to examine who does not recall FH-105 requirements D Incorrect Plausible to examine who does not recall FH-105 requirements or the attachment 1 actions of ON-120 -Since SAM count rate doubled once, per FH-105 step 3.7.4 lowering of the bundle must stop until count rate stabilizes at a value of less than 2 doublings, and no spiking or indication of SAM inoperability exists, then lowering the bundle may be continued.
A.       013 O/G Lockout B.       013 Bus Lockout C.     20 Station Aux Bus Lockout
ON-120 entry is only required if SAM count rate doubles twice (i.e. one doubling would be from 230 to 460, a second doubling would be from 460 to 920) FH-105, ON-120 LMK 2017 IL T NRG JANUARY Page: 180 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 51 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
: 0.       101 Safeguard Transformer Lockout Answer:         B
No Points: 1.00 Time to Complete:
        !Answer Explanation LMK 2017 ILT NRC JANUARY                       Page: 176 of 374                           17 January 2017
0 Difficulty:
 
2.00 System ID: 1649810 User-Defined ID: Q# 51 BANK Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Initially, D13 is powered from the 101 Safeguard Transformer through the 101-D13 breaker.
LLOT0760.10 rl"opic: OPCON 5 with fuel handling in-progress per FH-105, Core Comoonen RO: 3.4 SRO: 4.1 KA#: 295023 AA2.04 LMK 2017 IL T NRC JANUARY Page: 181of374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
hen the 1O Station Aux Bus Supply Breaker (105) trips, the 101 Safeguard Transformer is de-energized, causing the 101-D13 breaker to trip on 101 Transformer Undervoltage (<70%).
LMK 2017 IL T NRC JANUARY Page: 182 of 374 295023 AA2.04 3.4/4.1 Refueling AccidentsAbility to determine and/or interpret the following as they apply to REFUELING ACCIDENTS  
ne (1) second later, the 201-D13 breaker should auto-close to re-energize the D13 bus.
: tOccurrence of fuel handling accident Lower 8 41.10 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 52 10:1455248 Points: 1.00 WHICH ONE of the following describes the basis for performing an Emergency Slowdown when Drywell temperature cannot be restored and maintained below 340&deg;F? A. Maintain ADS SRV availability B. Prevent RPV level instrument reference leg boiling C. Maintain downcomer vacuum breaker availability D. Drywell Spray using fire water will be unavailable Answer: A Answer Explanation T-102, Subsequent steps in the drywell temperature (OW!f) control flowpath direct actions to rapidly shutdown the reactor and to emergency depressurize the RPV. These actions are appropriate, however, only if it has been determined that drywell temperature cannot be maintained below 340"F (i.e., the maximum temperature at which ADS is qualified and drywell design temperature).
Similarly, at 0.5 seconds after the dead-bus condition on D13, the D13 DIG will get an auto-start ignal. However, if the 201-D13 breaker did close, the D13 DG Output breaker will not attempt to auto-close when all of its other closing permissives are satisfied. The stem conditions indicating hat the D13 bus is still de-energized at T =20 seconds from the 105 breaker trip means that neither the 201-D13 breaker nor the D13 DIG Output breaker have closed in on the bus.
Step DW!f-10 ensures this condition has been met before allowing emergency RPV depressurization.
        'B' is correct. A D13 Bus Lockout will prevent both the 201-D13 and D13 DIG Output breakers ram closing in on the bus (see ARC-MCR-121, A 1). D12 and D14 bus are supplied from 201 bus nd unaffected by the trip of the 105 breaker. D11 DG will start on the undervoltage on D11 bus hen 101 bus losses power and the D111101 breaker trips, but the DG will not close in on the bus because before the DG gets up to speed the 2011D11 breaker will close.
When it has been determined that drywell temperature cannot be maintained below 340"F, operators are directed to continue at Step OW !f-11. correct for the above reason B incorrect.
        'A' is wrong because it suggests that a D13 DIG Lockout would not only prevent the D13 DIG utput breaker from closing (which it will), but also prevent the 201-D13 feeder breaker from losing (which it WON'T). Plausible to the examines who either mis-understands the breakers hat are affected by a lockout, or who fails to review the D13 DIG Lockout ARC (ARC-MCR-121, C1).
Plausible to the examinee who realizes that hi temperature in the OW may effect level indication C Incorrect.
        'C' is wrong. Although a 20 Station Aux Bus Lockout will prevent the 201-D13 breaker from closing (because the 201 Transformer voltage is < 70%), it will NOT prevent closure of the D13 DIG Output breaker.
Plausible to the examinee who recalls the solenoid operation of these valves, but does not recall that solenoids are for testing only D incorrect.
        'D' is wrong. See ARC-MCR-120, F1. Only the 101 Safeguard Transformer Supply Breaker (from the 1O Station Aux Bus) receives a .d.imci. trip from this kind of lockout. This lockout will not prevent closure of the 201-D13 feeder breaker, or of the D13 DIG Output breaker. Plausible to he examines who either mis-understands the breakers that are affected by a lockout, or who fails o review the 101 Transformer Lockout ARC ARC-MCR-120, F1 .
Plausible to the examinee who uses steam tables assumes saturated conditions and calculates 340 degrees will be about 130 psig. a steam leak in the drywell would be an isenthalpic process so without reactor pressure this calculation can not be assumed. LMK 2017 IL T NRC JANUARY Page: 183 of 37 4 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 52 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
LMK 2017 ILT NRG JANUARY                         Page: 177 of 374                                 17 January 2017
No Points: 1.00 Time to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 50 Info Question Tvpe:                   Multiple Choice Status:                         Active
2.40 System ID: 1455248 User-Defined ID: Q# 52 BANK 2015 NRC Lesson Plan Objective:
        !Always select on test?           No
LGSOPS1560.05 if opic: Basis for an Emergency Slowdown when Drywell temperature reaches 340 deq RO: 4.0 SRO: 4.1 KA#: 295028 EA2.01 LMK 2017 IL T NRC JANUARY Page: 184 of 37 4 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
        !Authorized for practice?         No Points:                           1.00 tTime to Complete:               3 Difficulty:                     2.00 System ID:                       1455199 User-Defined ID:               Q# 50 BANK Lesson Plan Objective:           LGSOPS0092A.4A tTooic:                           Determininq Cause of a De-energized 4 KV Safeguard Bus RO:                             3.9 SRO:                             4.0 KA#:                             700000 LMK 2017 ILT NRG JANUARY                       Page: 178 of 374                          17 January 2017
560429 LMK 2017 IL T NRC JANUARY Page: 185 of 374 295028 EA2.01 4.0/4.1 High Drywell Temperature Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE  
 
: Dr well tern erature lower 5 41.10 T-102 bases 2
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
5 Bank 560429 2015 NRC 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 53' 10: 1601451 Points: 1.00 Unit 1 is in OPCON 1. DEHC is operating in "Speed Control Mode" with the main turbine at 1800 rpm ready to synchronize to the grid. Which of the following completes the statement below If (1) turbine speed sensors fail, the turbine will respond by __(2l A. (1)2outof3 (2) closing the CVs and IVs but NOT the Stop Valves or ISVs B. (1)2outof3 (2) tripping C. (1) 1 out of 2 twice (2) closing the CVs and IVs but NOT the Stop Valves or ISVs D. (1) 1 out of 2 twice (2) tripping Answer: B Answer Explanation B Correct turbine trip logic for over speed or loss of speed signal is 2 out of 3 logic. loss of speed siqnal will cause a turbine trip A Incorrect but plausible to examinee who recalls that in speed control mode
700000AA1.05 3.9/4.0 Generator Voltage and Electric Grid Disturbances Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:
* At > 100% rated speed, the CVs start to close, a) From 101 % to 103%, all the IVs close b) At > 103%, CVs and IVs are closed and believes that a loss of speed signal will act the same as over speed in speed control mode c incorrect plausible to examinee who believes overspeed trip logic is the same as high level trip loqic D incorrect plausible to examinee who believes overspeed trip logic is the same as high level trip logic and believes loss of speed signal will act the same as overspeed in speed control mode as described in "A" LMK 2017 IL T NRC JANUARY Page: 186 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 53 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
features ARC-MCR-121
No Points: 1.00 Time to Complete:
                                                            , Al ARC-MCR-121
3 Difficulty:
                                                            , Cl ARC-MCR-008
2.00 System ID: 1601451 User-Defined ID: Q#53 NEW Lesson Plan Objective:
                                                            , A3 ARC-MCR-120
LGSOPS0031 B.01 D Topic: overspeed trip logic RO: 3.1 SRO: 3.1 KA#: 1295005 AA2.03 LMK 2017 IL T NRG JANUARY Page: 187 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
                                                            , Fl 295003 AK2.03 LMK 2017 ILT NRG JANUARY            Page: 179 of 374                            17 January 2017
LMK 2017 IL T NRC JANUARY Page: 188 of 374 295005 AA2.03 3.1 /3.1 Main Turbine Generator Trip Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERA TOR TRIP: Turbine valve osition lower 3 41.5 LGSOPS0018 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 189 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 54 10:1649516 Points: 1.00 SRVs are automatically cycling due to high reactor pressure.
 
WHICH one of the following describes the reason SRVs are manually opened per T-101? A. Lower the rate of inventory loss B. Ensure SBLC can inject at its design flow C. Reduce the potential for a stuck safety/relief valve D. Minimize likelihood of a downcomer vacuum breaker failure Answer: C !Answer Explanation LMK 2017 IL T NRC JANUARY Page: 190 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LGS TRIP Step RC/P-7 is a decision diamond that has operators evaluate whether or not any of he SRVs are cycling. "SRV cycling" is defined as multiple, closely sequenced SRV actuations where the SRV opens as RPV pressure exceeds the respective safety lift setpoint and closes as RPV pressure drops belo'A the respective reset setpoint.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 51                                                 10:1649810                                   Points: 1.00 Unit 1 plant conditions are as follows:
SRV cycling is undesirable and warrants prompt manual action for the following reasons:
* OPCON 5 with fuel handling in-progress per FH-105, Core Component Movement - Core Transfer
* The SRO on the refueling platform reports that a fuel bundle is being lowered into the core While the bundle is being lowered, the RO reports that SRM "1 B" count rate has risen from 230 cps to 475 cps.
WHICH ONE of the following describes the ability to continue lowering the bundle, and whether entry into ON-120, "Fuel Handling Problems" is required?
Ability to Continue Lowering the                 Entry into ON-120 "Fuel Handling Problems Bundle into the Core A.        Bundle may NOT be lowered until                 NOT Required count rate stabilizes B.        Bundle may NOT be lowered until                 Required count rate stabilizes
: c.        Continued lowering of the bundle IS             NOT Required permitted D.        Continued lowering of the bundle IS             Required permitted Answer:           A Answer Explanation A   Correct Since SAM count rate doubled once, per FH-105 step 3.7.4 lowering of the bundle must stop until count rate stabilizes at a value of less than 2 doublings, and no spiking or indication of SRM inoperability exists, then lowering the bundle may be continued.
B   Incorrect ON-120 entry is only required if SAM count rate doubles twice (i.e. one doubling would be from 230 to 460, a second doubling would be from 460 to 920) plausible to examinee who confuses FH-105 action with ON-120 entry C   Incorrect Plausible to examine who does not recall FH-105 requirements D   Incorrect Plausible to examine who does not recall FH-105 requirements or the attachment 1 actions of ON-120
          - Since SAM count rate doubled once, per FH-105 step 3.7.4 lowering of the bundle must stop until count rate stabilizes at a value of less than 2 doublings, and no spiking or indication of SAM inoperability exists, then lowering the bundle may be continued. ON-120 entry is only required if SAM count rate doubles twice (i.e. one doubling would be from 230 to 460, a second doubling would be from 460 to 920)
FH-105, ON-120 LMK 2017 ILT NRG JANUARY                           Page: 180 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 51 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               0 Difficulty:                     2.00 System ID:                       1649810 User-Defined ID:                 Q# 51 BANK Lesson Plan Objective:           LLOT0760.10 OPCON 5 with fuel handling in-progress per FH-105, Core rl"opic:
Comoonen RO:                             3.4 SRO:                             4.1 KA#:                             295023 AA2.04 LMK 2017 ILT NRC JANUARY                     Page: 181of374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
295023 AA2.04 3.4/4.1 Refueling AccidentsAbility to determine and/or interpret the following as they apply to REFUELING ACCIDENTS :
tOccurrence of fuel handling accident Lower 8
41.10 LMK 2017 ILT NRC JANUARY            Page: 182 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 52                                               10:1455248                                 Points: 1.00 WHICH ONE of the following describes the basis for performing an Emergency Slowdown when Drywell temperature cannot be restored and maintained below 340&deg;F?
A.     Maintain ADS SRV availability B.     Prevent RPV level instrument reference leg boiling C.     Maintain downcomer vacuum breaker availability D.     Drywell Spray using fire water will be unavailable Answer:         A Answer Explanation T-102, Subsequent steps in the drywell temperature (OW!f) control flowpath direct actions to rapidly shutdown the reactor and to emergency depressurize the RPV. These actions are appropriate, however, only if it has been determined that drywell temperature cannot be maintained below 340"F (i.e., the maximum temperature at which ADS is qualified and drywell design temperature). Step DW!f-10 ensures this condition has been met before allowing emergency RPV depressurization.
When it has been determined that drywell temperature cannot be maintained below 340"F, operators are directed to continue at Step OW !f-11.
        ~ correct for the above reason B incorrect. Plausible to the examinee who realizes that hi temperature in the OW may effect level indication C Incorrect. Plausible to the examinee who recalls the solenoid operation of these valves, but does not recall that solenoids are for testing only D incorrect. Plausible to the examinee who uses steam tables assumes saturated conditions and calculates 340 degrees will be about 130 psig. a steam leak in the drywell would be an isenthalpic process so without reactor pressure this calculation can not be assumed.
LMK 2017 ILT NRC JANUARY                       Page: 183 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 52 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?       No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.40 System ID:                       1455248 User-Defined ID:               Q# 52 BANK 2015 NRC Lesson Plan Objective:         LGSOPS1560.05 Basis for an Emergency Slowdown when Drywell temperature if opic:                        reaches 340 deq RO:                             4.0 SRO:                           4.1 KA#:                           295028 EA2.01 LMK 2017 ILT NRC JANUARY                     Page: 184 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
295028 EA2.01 4.0/4.1 High Drywell Temperature Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE :
Dr well tern erature lower 5
41.10 T-102 bases         'R<<t~~~ 2
                                                                                  ':#:';~tff01'' 5 Bank 560429 2015 NRC 560429 LMK 2017 ILT NRC JANUARY            Page: 185 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 53'                                               10: 1601451                                     Points: 1.00 Unit 1 is in OPCON 1.
DEHC is operating in "Speed Control Mode" with the main turbine at 1800 rpm ready to synchronize to the grid.
Which of the following completes the statement below If   (1)   turbine speed sensors fail, the turbine will respond by __(2l A.       (1)2outof3 (2) closing the CVs and IVs but NOT the Stop Valves or ISVs B.       (1)2outof3 (2) tripping C.       (1) 1 out of 2 twice (2) closing the CVs and IVs but NOT the Stop Valves or ISVs D.       (1) 1 out of 2 twice (2) tripping Answer:             B Answer Explanation B     Correct turbine trip logic for over speed or loss of speed signal is 2 out of 3 logic. loss of speed siqnal will cause a turbine trip A     Incorrect but plausible to examinee who recalls that in speed control mode
* At > 100% rated speed, the CVs start to close, a) From 101 % to 103%, all the IVs close b) At > 103%, CVs and IVs are closed and believes that a loss of speed signal will act the same as over speed in speed control mode c     incorrect plausible to examinee who believes overspeed trip logic is the same as high level trip loqic D   incorrect plausible to examinee who believes overspeed trip logic is the same as high level trip logic and believes loss of speed signal will act the same as overspeed in speed control mode as described in "A" LMK 2017 ILT NRC JANUARY                           Page: 186 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 53 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                       1601451 User-Defined ID:                 Q#53 NEW Lesson Plan Objective:           LGSOPS0031 B.01 D Topic:                           overspeed trip logic RO:                             3.1 SRO:                             3.1 KA#:                           1295005 AA2.03 LMK 2017 ILT NRG JANUARY                       Page: 187 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
295005 AA2.03 3.1 /3.1 Main Turbine Generator Trip Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERA TOR TRIP:
Turbine valve osition lower 3
41.5 LGSOPS0018 LMK 2017 ILT NRC JANUARY            Page: 188 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 189 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 54                                               10:1649516                         Points: 1.00 SRVs are automatically cycling due to high reactor pressure.
WHICH one of the following describes the reason SRVs are manually opened per T-101?
A.       Lower the rate of inventory loss B.       Ensure SBLC can inject at its design flow C.       Reduce the potential for a stuck safety/relief valve D.       Minimize likelihood of a downcomer vacuum breaker failure Answer:         C
        !Answer Explanation LMK 2017 ILT NRC JANUARY                       Page: 190 of 374                   17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LGS TRIP Step RC/P-7 is a decision diamond that has operators evaluate whether or not any of he SRVs are cycling.
        "SRV cycling" is defined as multiple, closely sequenced SRV actuations where the SRV opens as RPV pressure exceeds the respective safety lift setpoint and closes as RPV pressure drops belo'A the respective reset setpoint. SRV cycling is undesirable and warrants prompt manual action for the following reasons:
* It exerts significant dynamic loads upon the RPV, the SRV tail pipes and supporting structures, and the primary containment.
* It exerts significant dynamic loads upon the RPV, the SRV tail pipes and supporting structures, and the primary containment.
* Shrink and swell associated with SRV actuations cause RPV level fluctuations that complicate RPV level control actions.
* Shrink and swell associated with SRV actuations cause RPV level fluctuations that complicate RPV level control actions.
Line 601: Line 1,166:
* The potential for a stuck open SRV is increased.
* The potential for a stuck open SRV is increased.
IThe frequency at which SRV actuations are judged to constitute "cycling" is dependent on the effect of the actuations upon reactor power, RPV level, and RPV pressure, the effectiveness of automatic control systems, the practicability of manual control, and the availability of personnel for performance of manual control functions.
IThe frequency at which SRV actuations are judged to constitute "cycling" is dependent on the effect of the actuations upon reactor power, RPV level, and RPV pressure, the effectiveness of automatic control systems, the practicability of manual control, and the availability of personnel for performance of manual control functions.
RC/P-8 Manually open SRVs until RPV press drops to 990 psig DISCUSSION LGS TRIP Step RC/P-8 is entered as the result of a "YES" response to Step RC/P-7, indicating hat one or more SRVs are cycling. SRV cycling can be terminated by reducing RPV pressure to below the lowest SRV safety lift setpoint.
RC/P-8 Manually open SRVs until RPV press drops to 990 psig DISCUSSION LGS TRIP Step RC/P-8 is entered as the result of a "YES" response to Step RC/P-7, indicating hat one or more SRVs are cycling. SRV cycling can be terminated by reducing RPV pressure to below the lowest SRV safety lift setpoint. Step RC/P-8 directs actions to reduce RPV pressure to the RPV pressure that corresponds to the point at which all main turbine bypass valves will be fully open (990 psig), a value much lower than the lowest SRV safety lift setpoint.
Step RC/P-8 directs actions to reduce RPV pressure to the RPV pressure that corresponds to the point at which all main turbine bypass valves will be fully open (990 psig), a value much lower than the lowest SRV safety lift setpoint.
A         Incorrect plausible to the examines who recalls that 990 psi will keep max amount of steam to           bypass valves, however this is the reason for not going below 990 not why pressure is reduced by manually opening SRV's B         Incorrect plausible to examines who does not recall SLC is a positive displacement pump and that           discharge pressure will not effect pump flow rate C         Correct D         Incorrect plausible to the examines who does not evaluate how long it will take for the steam in the       downcomer to condense to the point of opening the downcomer vacuum breaker. with the same 1           or 2 SRVs cycling on pressure there will not be enough time for steam to condense to the point of           causing vacuum breaks rapidly cycling for potential to
A Incorrect plausible to the examines who recalls that 990 psi will keep max amount of steam to bypass valves, however this is the reason for not going below 990 not why pressure is reduced by manually opening SRV's B Incorrect plausible to examines who does not recall SLC is a positive displacement pump and that discharge pressure will not effect pump flow rate C Correct D Incorrect plausible to the examines who does not evaluate how long it will take for the steam in the downcomer to condense to the point of opening the downcomer vacuum breaker. with the same 1 or 2 SRVs cycling on pressure there will not be enough time for steam to condense to the point of causing vacuum breaks rapidly cycling for potential to or break. LMK 2017 IL T NRG JANUARY Page: 191 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 54 Info Question T e: Status: Comments:
        ~tick or break.
LMK 2017 ILT NRG JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 3 2.00 1649516 0#54 BANK LGSOPS1560.5 Page: 192 of 374 RC/P-7 295025 2.4.18 3.3/4.0 High Reactor Pressure Knowledge of the specific bases for EOPs lower 3 41.10 560722 bank modified 560722 bank modified 560722 bank modified 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 55 ID: 1649556 Points: 1.00 Unit 1 is in OPCON 5 when the following occurs
LMK 2017 ILT NRG JANUARY                           Page: 191 of 374                             17 January 2017
* Alarm 115-G5 1 B-1 D RH R Pump Room Flood has alarmed
 
* An EO reports several inches of water on the floor in the 1 B-1 D RHR pump room
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 54 Info Question T e:            Multi le Choice Status:                Active No No 1.00 3
2.00 1649516 0#54 BANK LGSOPS1560.5 RC/P-7 Comments:
295025 2.4.18 3.3/4.0 High Reactor Pressure Knowledge of the specific bases for EOPs lower 3
41.10 560722 bank modified 560722 bank modified 560722 bank modified LMK 2017 ILT NRG JANUARY              Page: 192 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 55                                               ID: 1649556                                 Points: 1.00 Unit 1 is in OPCON 5 when the following occurs
* Alarm 115-G5 1B-1 D RH R Pump Room Flood has alarmed
* An EO reports several inches of water on the floor in the 1B-1 D RHR pump room
* The EO reports the leak is on the RHR suction pipe BETWEEN the AHR suction valve and the AHR pump.
* The EO reports the leak is on the RHR suction pipe BETWEEN the AHR suction valve and the AHR pump.
* Suppression pool level is 21 feet 1 O inches down slow Given the following procedures ON-11 O Loss of Primary Containment 2 T-102 Primary Containment Control 3 T-103 Secondary Containment Control Which of the procedures listed above must be entered at this time? A. 2 and 3 ONLY B. 1and3 ONLY C. 1and2 ONLY D. 1, 2 and 3 Answer: A Answer Explanation A Correct symptom for on-110 loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs. T-103 entry includes Room flooding alarm condition for areas in Table SCC-1 which include AHR pump rooms. T-102 entry is not required until suppression pool level drops below 22 feet B symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs. T-102 is require (<22" pool level) regardless of OPCON C Incorrect symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs.T-103 entry required due to AHR room flood alarm D Incorrect symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs. LMK 2017 IL T NRC JANUARY Page: 193 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 55 Info Question Type: Multiple Choice Status: Active lA.lwavs select on test? No lA.uthorized for practice?
* Suppression pool level is 21 feet 1O inches down slow Given the following procedures ON-11 O Loss of Primary Containment 2         T-102 Primary Containment Control 3         T-103 Secondary Containment Control Which of the procedures listed above must be entered at this time?
No Points: 1.00 rTime to Complete:
A.     2 and 3 ONLY B.     1and3 ONLY C.     1and2 ONLY D.     1, 2 and 3 Answer:         A Answer Explanation A   Correct symptom for on-110 loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs. T-103 entry includes Room flooding alarm condition for areas in Table SCC-1 which include AHR pump rooms. T-102 entry is not required until suppression pool level drops below 22 feet B   symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs. T-102 is require (<22" pool level) regardless of OPCON C   Incorrect symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs.T-103 entry required due to AHR room flood alarm D   Incorrect symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs.
3 Difficulty:
LMK 2017 ILT NRC JANUARY                       Page: 193 of 374                             17 January 2017
3.50 System ID: 1649556 User-Defined ID: 0#55 NEW Lesson Plan Objective:
 
LGSOPS1560.04 Topic: low pool leveL AOP/EOP entry RO: 4.5 SRO: 4.7 KA#: 295030 2.4.4 LMK 2017 IL T NRG JANUARY Page: 194 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 55 Info Question Type:                     Multiple Choice Status:                           Active lA.lwavs select on test?           No lA.uthorized for practice?         No Points:                           1.00 rTime to Complete:                 3 Difficulty:                     3.50 System ID:                       1649556 User-Defined ID:                 0#55 NEW Lesson Plan Objective:           LGSOPS1560.04 Topic:                           low pool leveL AOP/EOP entry RO:                             4.5 SRO:                             4.7 KA#:                             295030 2.4.4 LMK 2017 ILT NRG JANUARY                       Page: 194 of 374       17 January 2017
LMK 2017 IL T NRG JANUARY Page: 195 of 374 Low Suppression Pool Water Level Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal I o eratin rocedures.
 
17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 56 ID; 1671239 Points: 1.00 Unit 2 is operating at 50% power when a feedwater malfunction results in the following:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Low Suppression Pool Water Level Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal I o eratin rocedures.
LMK 2017 ILT NRG JANUARY            Page: 195 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 56                                               ID; 1671239                                     Points: 1.00 Unit 2 is operating at 50% power when a feedwater malfunction results in the following:
* Reactor level begins lowering
* Reactor level begins lowering
* 107-H1 REACTOR WATER LEVEL BELOW LEVEL 3 TRIP is alarmed
* 107-H1 REACTOR WATER LEVEL BELOW LEVEL 3 TRIP is alarmed
Line 620: Line 1,196:
* The feedwater system restores level to +35 inches
* The feedwater system restores level to +35 inches
* PMS indicates reactor level reached + 10.5 inches WHICH ONE of the following identifies the required action in accordance with OT-117 RPS Failures?
* PMS indicates reactor level reached + 10.5 inches WHICH ONE of the following identifies the required action in accordance with OT-117 RPS Failures?
A. Perform a GP-4 Shutdown B. Reset "A" RPS trip system half SCRAM AND insert a manual half SCRAM on RPS trip system "B" C. Maintain half SCRAM on RPS trip system "A" AND do NOT insert a manual half SRAM on RPS trip system "B" D. Immediately SCRAM Unit 2 Answer: A Answer Explanation With reactor level at 10.5 it is possible that one and only one of the Reactor level trip unit would actuate. Requires the candidate to understand that with Reactor lo level Trip in alarm and one systems of RPS energized that entry into OT-117 is required.
A.       Perform a GP-4 Shutdown B.       Reset "A" RPS trip system half SCRAM AND insert a manual half SCRAM on RPS trip system "B" C.       Maintain half SCRAM on RPS trip system "A" AND do NOT insert a manual half SRAM on RPS trip system "B" D.       Immediately SCRAM Unit 2 Answer:           A Answer Explanation With reactor level at 10.5 it is possible that one and only one of the Reactor level trip unit would actuate.
A is correct failure to SCRAM in retrospect requires a GP-4 shutdown B incorrect, plausible to the examinee who believe that since A side worked only a B side half SCRAM needs to be inserted ON-117 C incorrect but plausible to examinee who believe that with either A or B RPS INOP maintaining 1 channel in tripped condition will satisfy the LCO D incorrect, plausible to the examinee who confuses failure to SCRAM in retrospect with failure to SCRAM in proqress LMK 2017 ILT NRC JANUARY Page: 196 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 56 Info Question T e: Status: Comments:
Requires the candidate to understand that with Reactor lo level Trip in alarm and one systems of RPS energized that entry into OT-117 is required.
LMK 2017 IL T NRG JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 4 3.00 1671239 0#56 NEW LGSOPS1540.3 SCRAM Erner enc Procedures 4.2 4.2 295006 2.4.46 295006 2.4.46 4.2/4.2 SCRAM Emergency Procedures I Plan: Ability to verify that the alarms are consisten with the plant c/tc''''Yl:t.foLI Conditions.
A is correct failure to SCRAM in retrospect requires a GP-4 shutdown B incorrect, plausible to the examinee who believe that since A side worked only a B side half SCRAM needs to be inserted ON-117 C incorrect but plausible to examinee who believe that with either A or B RPS INOP maintaining 1 channel in tripped condition will satisfy the LCO D incorrect, plausible to the examinee who confuses failure to SCRAM in retrospect with failure to SCRAM in proqress LMK 2017 ILT NRC JANUARY                         Page: 196 of 374                                 17 January 2017
Page: 197 of 374 Hi h 41.10 OT-117 ARC-MCR-107 G1 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 198 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 57 ID: 1601473 Points: 1.00 Unit 1 plant conditions:  
 
-Div 4 DC is lost -Operators enter E-1 FD, 'Loss of Div 4 125 VDC Bus 1 FD' WHICH ONE of the following identifies the type of manual isolation of the MCR directed by E-1 FD, and the reason why? A. Radiation Isolation, to ensure outside air is isolated to the MCR B. Chlorine Isolation, to ensure outside air is isolated to the MCR C. Chlorine Isolation, to maintain positive MCR pressure D. Radiation Isolation, to maintain positive MCR pressure Answer: B Answer Explanation B is correct with a loss of power to the isolation logic for one of two in series outside isolation dampers there is no assurance that if some other loss of power incident were to happen that it will ensure that a full chlorine isolation will occur during an actual chlorine accident.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 56 Info Question T e:            Multi le Choice Status:                Active No No 1.00 4
Therefore, E-1 FD directs that, upon loss of a division of DC, a chlorine isolation be performed to ensure outside air is isolated to the MCR. A incorrect plausible to the examinee who does not recall which isolation is directed from E-1 FD and does not recall the difference between chlorine isolation and radiation isolation suction paths C incorrect plausible to the examinee who believes chlorine isolation keeps the MCR positive to keep Chlorine out D Incorrect plausible to the examinee who believes a radiation isolation is directed from E-1 FD LMK 2017 IL T NRC JANUARY Page: 199 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 57 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
3.00 1671239 0#56 NEW LGSOPS1540.3 SCRAM Erner enc Procedures 4.2 4.2 295006 2.4.46 Comments:
No Points: 1.00 rTime to Complete:
295006 2.4.46 4.2/4.2 SCRAM Emergency Procedures I Plan: Ability to verify that the alarms are consisten with the plant c/tc''''Yl:t.foLI Conditions.
3 Difficulty:
Hi h 41.10 OT-117 ARC-MCR-107 G1 LMK 2017 ILT NRG JANUARY              Page: 197 of 374                                      17 January 2017
2.00 System ID: 1601473 User-Defined ID: Q# 57 BANK Lesson Plan Objective:
 
LGSOPS0078.04 Topic: Recall Reason for MCR Manual Chloring Isolation on loss of Div 4DC RO: 4.6 SRO: 4.6 KA#: 295004 2.4.49 LMK 2017 IL T NRG JANUARY Page: 200 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 198 of 374       17 January 2017
560683 LMK 2017 IL T NRC JANUARY Page: 201 of 374 295004 2.4.49 4.6/4.4 Partial or Complete Loss of D.C. Power Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
 
lower LGSOPS0078 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 58 10:1455234 Points: 1.00 Unit 1 is operating at 100% power
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 57                                                 ID: 1601473                                   Points: 1.00 Unit 1 plant conditions:
* Service air is connected to the 1 A instrument air header
        - Div 4 DC is lost
        - Operators enter E-1 FD, 'Loss of Div 4 125 VDC Bus 1FD' WHICH ONE of the following identifies the type of manual isolation of the MCR directed by E-1 FD, and the reason why?
A.       Radiation Isolation, to ensure outside air is isolated to the MCR B.       Chlorine Isolation, to ensure outside air is isolated to the MCR C.       Chlorine Isolation, to maintain positive MCR pressure D.       Radiation Isolation, to maintain positive MCR pressure Answer:           B Answer Explanation B is correct with a loss of power to the isolation logic for one of two in series outside isolation dampers there is no assurance that if some other loss of power incident were to happen that it will ensure that a full chlorine isolation will occur during an actual chlorine accident. Therefore, E-1 FD directs that, upon loss of a division of DC, a chlorine isolation be performed to ensure outside air is isolated to the MCR.
A incorrect plausible to the examinee who does not recall which isolation is directed from     E-1 FD and does not recall the difference between chlorine isolation and radiation isolation suction paths C incorrect plausible to the examinee who believes chlorine isolation keeps the MCR positive to keep Chlorine out D Incorrect plausible to the examinee who believes a radiation isolation is directed from E-1 FD LMK 2017 ILT NRC JANUARY                           Page: 199 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 57 Info Question Type:                   Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 rTime to Complete:               3 Difficulty:                     2.00 System ID:                       1601473 User-Defined ID:                 Q# 57 BANK Lesson Plan Objective:           LGSOPS0078.04 Recall Reason for MCR Manual Chloring Isolation on loss of Div Topic:
4DC RO:                             4.6 SRO:                             4.6 KA#:                           295004 2.4.49 LMK 2017 ILT NRG JANUARY                       Page: 200 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
295004 2.4.49 4.6/4.4 Partial or Complete Loss of D.C. Power Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
lower LGSOPS0078 560683 LMK 2017 ILT NRC JANUARY            Page: 201 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 58                                               10:1455234                                   Points: 1.00 Unit 1 is operating at 100% power
* Service air is connected to the 1A instrument air header
* INSTRUMENT AIR HEADER A PRESSURE LO annunciator is in alarm
* INSTRUMENT AIR HEADER A PRESSURE LO annunciator is in alarm
* INSTRUMENT AIR HEADER B PRESSURE LO annunciator is in alarm
* INSTRUMENT AIR HEADER B PRESSURE LO annunciator is in alarm
* PV-015-167 Service Air Header Pressure Control Valve has isolated
* PV-015-167 Service Air Header Pressure Control Valve has isolated
* Service air header pressure has equalized with 1 A instrument air header Which of the following describes the A and Bair header pressures that caused PV-015-167 Service Air Header Pressure Control Valve to isolate and how the Service Air Compressor is loaded? 1 A and 1 B instrument air header pressures A. Both headers < 70 psig B. At least one header is < 70 psig c. At least one header is < 70 psig D. Both headers < 70 psig Answer: D Answer Explanation Both air headers low pressure alarm (85psig) PV-05-167 closes when both headers are < 70 psig. Service air com lead side load at 97 psig lag at 94 Service air compressor loading Only the Lead side loaded Lead and Lag sides loaded Only the Lead side loaded Lead and Lag sides loaded The instrument air headers at LGS are 2 separate headers with check valves to maintain separation, however a leak at a component or at a panel where several lines come together after the check valve will cause both headers to depressurize.
* Service air header pressure has equalized with 1A instrument air header Which of the following describes the A and Bair header pressures that caused PV-015-167 Service Air Header Pressure Control Valve to isolate and how the Service Air Compressor is loaded?
Also, these headers run in close proximity to each other so any mechanical accident that damages one may also damage the other. per the stem PV-015-167 Service Air Header Pressure Control Valve has isolated.
1A and 1B instrument air header pressures           Service air compressor loading A.       Both headers < 70 psig                       Only the Lead side loaded B.       At least one header is < 70 psig             Lead and Lag sides loaded
this requires both headers to be less than 70 psig. When PV-015-167 isolates it separates the service air compressor from the service air loads and allows the service air compressor to supply the instrument air header. The air compressors are able to compress on both the piston up and down stroke, normally the only compress on one side, if air header pressure drop below a setpoint (94psig for service air) than the compressor will load on both up and down stroke. A is incorrect plausible to the examinee who doe not recall the loading sequence of the service air compressor B is incorrect plausible to the examinee who does not recall the requirement for BOTH air headers to be <70 psig for the PV-05-167 to close C incorrect but plausible for the reasons stated above D correct LMK 2017 ILT NRG JANUARY Page: 202 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 58 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
: c.       At least one header is < 70 psig             Only the Lead side loaded D.       Both headers < 70 psig                       Lead and Lag sides loaded Answer:         D Answer Explanation Both air headers low pressure alarm (85psig)
No Points: 1.00 !Time to Complete:
PV-05-167 closes when both headers are < 70 psig.
4 Difficulty:
Service air com lead side load at 97 psig lag at 94 The instrument air headers at LGS are 2 separate headers with check valves to maintain separation, however a leak at a component or at a panel where several lines come together after the check valve will cause both headers to depressurize. Also, these headers run in close proximity to each other so any mechanical accident that damages one may also damage the other. per the stem PV-015-167 Service Air Header Pressure Control Valve has isolated. this requires both headers to be less than 70 psig. When PV-015-167 isolates it separates the service air compressor from the service air loads and allows the service air compressor to supply the instrument air header. The air compressors are able to compress on both the piston up and down stroke, normally the only compress on one side, if air header pressure drop below a setpoint (94psig for service air) than the compressor will load on both up and down stroke.
3.00 Svstem ID: 1455234 User-Defined ID: 0#58 NEW Lesson Plan Obiective:
A is incorrect plausible to the examinee who doe not recall the loading sequence of the service air compressor B is incorrect plausible to the examinee who does not recall the requirement for BOTH air headers to be <70 psig for the PV-05-167 to close C incorrect but plausible for the reasons stated above D correct LMK 2017 ILT NRG JANUARY                         Page: 202 of 374                               17 January 2017
LOT-1550 ON-119 OBJ 3 tropic: backup to ins airf air RO: 3.3 SRO: 3.4 KA#: 295019 LMK 2017 IL T NRC JANUARY Page: 203 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 IL T NRC JANUARY Page: 204 of 374 3.3/3.4 Partial or Complete Loss of Instrument Air Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 205 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 59 .* ID: 1455127 Points: 1.00 Plant conditions are as follows:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 58 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00
        !Time to Complete:               4 Difficulty:                     3.00 Svstem ID:                       1455234 User-Defined ID:                 0#58 NEW Lesson Plan Obiective:           LOT-1550 ON-119 OBJ 3 tropic:                           backup to ins airf air RO:                             3.3 SRO:                             3.4 KA#:                           295019 LMK 2017 ILT NRC JANUARY                       Page: 203 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
3.3/3.4 Partial or Complete Loss of Instrument Air Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
LMK 2017 ILT NRC JANUARY            Page: 204 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 205 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 59 .*                                               ID: 1455127                           Points: 1.00 Plant conditions are as follows:
* Reactor pressure is 450 psig
* Reactor pressure is 450 psig
* Drywell pressure is 8 psig
* Drywell pressure is 8 psig
* Drywell temperature is 275 degrees Given the following graph Which of the following identifies whether the Drywell conditions are Safe or Unsafe and what the safe side of the graph is protecting from? CURVE PC/P*2 CU RYE DW/T .. 3 DRYWELL SPRAY INITIATION LIMIT 500-+--+---il---t--t--+--+  
* Drywell temperature is 275 degrees Given the following graph Which of the following identifies whether the Drywell conditions are Safe or Unsafe and what the safe side of the graph is protecting from?
........ -+--+--1 450-t----lt---t'--t--+-+--P--+----+----+---+---+--
CURVE PC/P*2 CU RYE DW/T .. 3 DRYWELL SPRAY INITIATION LIMIT 500-+--+---il---t--t--+--+........-+--+--1 450-t----lt---t'--t--+-+--P--+----+----+---+---+--
400--t----,__t--1t--t::l'"'-1--I--;.-+-+-;..-;-
400--t----,__t--1t--t::l'"'-1--I--;.-+-+-;..-;-
____ i--1!--1--1--1---!"-!
350.,........_,.__,.__,._~.,_.,_ ____i--1!--1--1--1---!"-!
300***t-.,.._.,.._.,...,...
300***t-.,.._.,.._.,...,...______
____ __ 250+-+--"""""'--+-+--+--
250+-+--"""""'--+-+--+--
200-i--t...---o--j.---l----l--i-->-_,__....._.__._
200-i--t...---o--j.---l----l--i-->-_,__....._.__._____    ~
____ 150-+--A-+-.....-+--;,..._.--+-+-
150-+--A-+-.....-+--;,..._.--+-+-
100* ; J
100*                 ;       J
* I 3 4 5 6 7 8 91011:12131415161718 Safe I Unsafe A. Unsafe B. Unsafe c. Safe D. Safe Answer: C LMK 2017 ILT NRC JANUARY Remaining on safe side protects from Containment Failure Level instrument inaccuracy Containment failure Level instrument inaccuracy Page: 206 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Answer Explanation Examinee must calculate that Drywell temperature and Pressure combination given are below the safe/unsafe line on the graph. Then the candidate must determine that below line is safe. the examinee must then determine that the graph in question is the DW spray initiation limit and not reference leg saturation limit curve and what the reason for these curves are A Incorrect plausible to examinee who does not recall safe side of graph B Incorrect plausible to examinee who does not recall safe side of graph and confuses this graph with the ref leg saturation curve C Correct safe side of graph is below the line and remaining on safe side protects against containment failure D Incorrect plausible to examinee who confuses this graph with the ref leg saturation curve LMK 2017 ILT NRC JANUARY Page: 207 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 59 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
* I 3 4       5   6     7 8 91011:12131415161718 Safe I Unsafe                           Remaining on safe side protects from A.           Unsafe                             Containment Failure B.           Unsafe                             Level instrument inaccuracy
No Points: 1.00 rnme to Complete:
: c.           Safe                               Containment failure D.           Safe                               Level instrument inaccuracy Answer:               C LMK 2017 ILT NRC JANUARY                             Page: 206 of 374                       17 January 2017
4 Difficulty:
 
3.00 System ID: 1455127 User-Defined ID: Q# 59 NEW Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer Explanation Examinee must calculate that Drywell temperature and Pressure combination given are below the safe/unsafe line on the graph. Then the candidate must determine that below line is safe. the examinee must then determine that the graph in question is the DW spray initiation limit and not
LGSOPS1560.04 Topic: DW temp pressure effects RO: 3.3 SRO: 3.5 KA#: 295012 AK1 .01 LMK 2017 IL T NRC JANUARY Page: 208 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
      ~he reference leg saturation limit curve and what the reason for these curves are A     Incorrect plausible to examinee who does not recall safe side of graph B     Incorrect plausible to examinee who does not recall safe side of graph and confuses this graph with the ref leg saturation curve C     Correct safe side of graph is below the line and remaining on safe side protects against containment failure D     Incorrect plausible to examinee who confuses this graph with the ref leg saturation curve LMK 2017 ILT NRC JANUARY                       Page: 207 of 374                             17 January 2017
LMK 2017 IL T NRG JANUARY Page: 209 of 374 1 2 295012 AK1 .01 3.3/3.5 High Drywell Temperature Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE  
 
: Pressure/temperature relationshi 2 5 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 60 10:1588533 Points: 1.00 Unit 2 is operating at 50 percent power. A Reactor Recirc Pump trips. Which of the following is correct regarding the initial indicated reactor level response, and the major reason for the reactor power reduction from the pump trip? Indicated level response Reason for power reduction A. Rises Change in void content 8. Rises Change in moderator temperature  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 59 Info Question Type:                 Multiple Choice Status:                         Active
: c. Lowers Change in void content D. Lowers Change in moderator temperature Answer: A Answer Explanation A A correct indicated level will rise. Due to increased void production in the core flow from the downcomer to the core will reduce causing level in the downcomer to rise. the void coefficient will be the major factor in the power change B Incorrect plausible to the examinee who believes reduced recirc flow will cause feedwater temperature to rise C Incorrect plausible to the examinee who does not recall that indicated level is read in the down comer not inside the shroud D Incorrect plausible to the examinee who does not recall that indicated level is read in the down comer not inside the shroud and believes reduced recirc flow will cause feedwater temperature to rise LMK 2017 IL T NRG JANUARY Page: 210 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 60 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
        ~lways select on test?           No
No Points: 1.00 Time to Complete:
        ~uthorized for practice?         No Points:                         1.00 rnme to Complete:               4 Difficulty:                     3.00 System ID:                       1455127 User-Defined ID:                 Q# 59 NEW Lesson Plan Objective:           LGSOPS1560.04 Topic:                           DW temp pressure effects RO:                             3.3 SRO:                             3.5 KA#:                             295012 AK1 .01 LMK 2017 ILT NRC JANUARY                     Page: 208 of 374       17 January 2017
3 Difficulty:
 
3.00 System ID: 1588533 User-Defined ID: Q# 60 MODIFIED lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LGSOPSO 43A Topic: RR DD trip void effect RO: 3.2 SRO: 3.2 KA#: 295014 AK2.04 LMK 2017 IL T NRC JANUARY Page: 211 of 374 17 January 2017 EXAMINATION ANSWER KEY Comments:
1 2
LMK 2017 IL T NRG JANUARY IL T 15-01 January 2017 NRC test SRO Page: 212 of 374 Inadvertent Reactivity Addition Knowledge of the interrelations between INADVERTENT REACTIVITY ADDITION and the seusquehanna Q 46 2013 exam modified seusquehanna Q 46 2013 exam modified seusquehanna Q 46 2013 exam modified 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 61 ID: 1601489. Points: 1.00 Unit 1 has experienced a core damage event with elevated Off-site release rates. For the CREFAS system, which correctly completes the statement below? CREFAS will automatically isolate if the outside air intake measures greater than (1) to ensure control room personnel do NOT receive more than (2) for the duration of the accident. ( 1) (2) A. 0.5 mR/hr 5 REM TEDE B. 0.5 mR/hr 25 REM CDE Thyroid c. 1 X 1 0-5 &#xb5;Ci/cc 5 REM TEDE D. 1 X 10-5 &#xb5;Ci/cc 25 REM CDE Thyroid Answer: c Answer Explanation iThe isolation set point for Main Control Room Normal Fresh Air Supply Radiation Monitor is 1X10-5 micro curies/cc (Tech Spec Table 3.3.7.1-1) iThe purpose of the CREFAS Radiation isolation is to limit the Control Room radiation exposure to personnel to 5 REM TEDE or less. Tech Spec Bases page 83/4 7-1a. A Wrong -Plausible to the student that mistakenly recalls the CREFAS CL2 isolation setpoint of 0.5 PPM in place of the Radiation isolation set point B Wrong -Plausible to the student that mistakenly recalls the CREFAS CL2 isolation setpoint of 0.5 PPM in place of the Radiation isolation set point and plausible to the student that remembers that all Radioligical Effluent Thyroid limits are 5X above the TEDE limits found in the EALs and selects the Thyroid Limit that would be 5X larger than the correct 5 REM TEDE limit C Correct for the above reasons D Wrong -Plausible to the student that remembers that all Radioligical Effluent Thyroid limits are 5X above the TEDE limits found in the EALs and selects the Thyroid Limit that would be 5X larger than the correct 5 REM TEDE limit LMK 2017 IL T NRC JANUARY Page: 213 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 61 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
295012 AK1 .01 3.3/3.5 High Drywell Temperature Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE :
No Points: 1.00 rnme to Complete:
Pressure/temperature relationshi 2
3 Difficulty:
5 LMK 2017 ILT NRG JANUARY            Page: 209 of 374                          17 January 2017
2.00 System ID: 1601489 User-Defined ID: Q#61NEW Lesson Plan Objective:
 
LGSOPS0078.11 rropic: Off-site Release Rate -Response of plant ventilation RO: 3.3 SRO: 3.5 KA#: APE 295017 AK3.02 LMK 2017 IL T NRC JANUARY Page: 214 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 60                                               10:1588533                                     Points: 1.00 Unit 2 is operating at 50 percent power.
LMK 2017 IL T NRG JANUARY Page: 215 of 374 2 295017 AK3.02 RO 3.3 SRO 3.5 APE: 295017 High Off-Site Release Rate AK3. Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: AK3.02 Plant ventilation.
A Reactor Recirc Pump trips.
Low 9 Radioactivit Release 41.5 EP-AA-1008 Addendum 3 Unit 1 Tech Specs Table 3.3.7.1-1 N/A 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 62 ID: 1588469 Points: 1.00 Unit 1 is operating at 40% power, with the following:  
Which of the following is correct regarding the initial indicated reactor level response, and the major reason for the reactor power reduction from the pump trip?
-The '1A' RPV Narrow Range (NR) Level Transmitter that inputs to the 'A' NR level indicator on 1 OC603 is failed upscale Five minutes later, the following occurs: -The '1 B' RPV Narrow Range (NR) Level Transmitter that inputs to the 'B' NR level indicator on 1 OC603 fails upscale WHICH ONE of the following describes the plant response (assume no operator action)? A. Reactor scrams due to a loss of Feedwater B. Reactor scrams due to a Main Turbine trip; RFPs ARE available after the scram C. Reactor remains operating D. Reactor scrams due to a Main Turbine trip; RFPs are NOT available after the scram Answer: C Answer Explanation The 4 RPV L Ts that input to DFWLC for the high level turbine trip logic are setup different than RPS trip logic. The DFWLC trip logic is A or B and C or D. RPS trip logic is A or C and B or D. With A and B level transmitters for DFWLC failing upscale, the main turbine and RFPT will not trip on high level. additionally these transmitters are different than the RPS level transmitters  
Indicated level response                         Reason for power reduction A.       Rises                                           Change in void content
'C' is correct for the above reasons. Reactor remains operating  
: 8.       Rises                                           Change in moderator temperature
'A' is wrong. Reactor scrams due to a loss of Feedwater Plausible to the examinee who does not recall the LT coincidence needed to produce the turbine trip function.  
: c.       Lowers                                           Change in void content D.       Lowers                                           Change in moderator temperature Answer:         A Answer Explanation A   A correct indicated level will rise. Due to increased void production in the core flow from the downcomer to the core will reduce causing level in the downcomer to rise. the void coefficient will be the major factor in the power change B   Incorrect plausible to the examinee who believes reduced recirc flow will cause feedwater temperature to rise C   Incorrect plausible to the examinee who does not recall that indicated level is read in the down comer not inside the shroud D   Incorrect plausible to the examinee who does not recall that indicated level is read in the down comer not inside the shroud and believes reduced recirc flow will cause feedwater temperature to rise LMK 2017 ILT NRG JANUARY                           Page: 210 of 374                               17 January 2017
'B' is wrong. Reactor scrams due to a Main Turbine trip; RFPs are available after the scram Plausible to the examinee who not only incorrectly concludes several points: 1) that these two L Ts work together to produce the needed turbine trip logic; and 2) that the RFPTs are available, post-scram (i.e., that the RFPTs will not have tripped on the LT failures).  
 
'D' is wrong. Reactor scrams due to a Main Turbine trip; RFPs are nD.t available after the scram Plausible for reasons similar to choices 'B' and 'C'. LMK 2017 IL T NRG JANUARY Page: 216 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Question 62 Info :)uestion Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 60 Info Question Type:                   Multiple Choice Status:                         Active
No Points: 1.00 Time to Complete:
        ~lwavs select on test?           No
3 Difficulty:
        ~uthorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.00 System ID:                       1588533 User-Defined ID:                 Q# 60 MODIFIED lesson Plan Objective:           LGSOPSO 43A Topic:                           RR DD trip void effect RO:                             3.2 SRO:                             3.2 KA#:                             295014 AK2.04 LMK 2017 ILT NRC JANUARY                       Page: 211 of 374     17 January 2017
2.50 System ID: 1588469 User-Defined ID: 0#62 BANK Lesson Plan Objective:
 
LLOT0540.14D Topic: Plant Response to RPV LT Upscale Failures RO: 3.5 SRO: 3.5 KA#: 295008 AA 1.08 LMK 2017 IL T NRC JANUARY Page: 217 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRC JANUARY Page: 218 of 374 295008 AA 1.08 3.5/3.5 High Reactor Water Level Ability to operate and/or monitor the following as they apply to HIGH REACTOR WATER LEVEL : Feedwater bank 908160 bank 908160 bank 908160 3 4 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 219 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 63 ID: 1601450 Points; 1.00 Unit 2 plant conditions are as follows: -Reactor power is 37% -Both CRD pumps are tripped and cannot be started 15 minutes later, 23 HCU Accumulator Trouble annunciators are alarming A GP-4 Shutdown is performed WHICH ONE of the following describes the plant response?
Inadvertent Reactivity Addition Knowledge of the interrelations between INADVERTENT REACTIVITY ADDITION and the seusquehanna Q 46 2013 exam modified seusquehanna Q 46 2013 exam modified seusquehanna Q 46 2013 exam modified LMK 2017 ILT NRG JANUARY            Page: 212 of 374                            17 January 2017
A. 23 rods will not insert B. All rods will insert with normal scram times C. All rods will insert with scram times greater than the Tech Spec allowable scram times for all rods D. All rods will insert with scram times greater than the Tech Spec allowable scram times for 23 rods Answer: B !Answer Explanation LMK 2017 IL T NRG JANUARY Page: 220 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO nswer: All rods will insert with normal scram times Per ON-107, During a reactor scram, the charging header provides the initial motive force to insert the rod. Then the scram accumulator pressure accelerates the drive and reactor pressure is used in the rod insertion process but is not required.
 
For example, a rod scrammed at 900 psig reactor pressure and zero accumulator nitrogen pressure would result in an insignificant increase in scram time. Twenty minutes is allowed to restore a tripped CRD pump if more than 1 scram accumulator is inoperable and reactor pressure is equal to or greater than 900 psig since reactor pressure is adequate to insert all control rods with or without inoperative scram accumulators.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 61                                               ID: 1601489.                                   Points: 1.00 Unit 1 has experienced a core damage event with elevated Off-site release rates. For the CREFAS system, which correctly completes the statement below?
hen this condition occurs below 900 psig reactor pressure, the mode switch is to be placed in shutdown as required by Technical Specifications.
CREFAS will automatically isolate if the outside air intake measures greater than       (1) to ensure control room personnel do NOT receive more than           (2) for the duration of the accident.
The insertion and disarming of control rods hen more than one accumulator is inoperable is performed to comply with Technical Specifications.
( 1)                                         (2)
3 rods will not insert -all rods will insert II rods will insert with significant longer scram times -all rods will insert, scram times will not ignificantly increase II rods will insert, however, 23 rods will have significant longer scram times -see explanation Examinee must recognize at 37% power reactor is at rated pressure A Wrong -Plausible if the student mis-applies the extremely reduced reactor pressure impact on the control rod scram ability to the 23 Control Rods with reduced Scram Accumulator Pressures (i.e. -at extremely reduced RPV pressure CRD differential puressure is insufficient to insert the control rod.) B Correct -as described above C Wrong -Plausible if the student mis-applies the reduced reactor pressure impact on the control rod scram ability to all core Control Rods (i.e. -at reduced RPV pressure rod scram times will be lengthened commencerate with the reduction in RPV pressure)
A.                         0.5 mR/hr                                 5 REM TEDE B.                         0.5 mR/hr                             25 REM CDE Thyroid
D Wrong -Plausible if the student mis-applies the reduced reactor pressure impact on the control rod scram ability to the 23 Control Rods with reduced Scram Accumulator Pressures (i.e. -at reduced RPV pressure rod scram times will be lengthened commencerate with the reduction in RPV pressure)
: c.                       1 X 10-5 &#xb5;Ci/cc                               5 REM TEDE D.                       1 X 10-5 &#xb5;Ci/cc                           25 REM CDE Thyroid Answer:           c Answer Explanation iThe isolation set point for Main Control Room Normal Fresh Air Supply Radiation Monitor is 1X10-5 micro curies/cc (Tech Spec Table 3.3.7.1-1) iThe purpose of the CREFAS Radiation isolation is to limit the Control Room radiation exposure to personnel to 5 REM TEDE or less. Tech Spec Bases page 83/4 7-1a.
LMK 2017 IL T NRC JANUARY Page: 221 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 63 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
A   Wrong - Plausible to the student that mistakenly recalls the CREFAS CL2 isolation setpoint of 0.5 PPM in place of the Radiation isolation set point B   Wrong - Plausible to the student that mistakenly recalls the CREFAS CL2 isolation setpoint of 0.5 PPM in place of the Radiation isolation set point and plausible to the student that remembers that all Radioligical Effluent Thyroid limits are 5X above the TEDE limits found in the EALs and selects the Thyroid Limit that would be 5X larger than the correct 5 REM TEDE limit C   Correct for the above reasons D   Wrong - Plausible to the student that remembers that all Radioligical Effluent Thyroid limits are 5X above the TEDE limits found in the EALs and selects the Thyroid Limit that would be 5X larger than the correct 5 REM TEDE limit LMK 2017 ILT NRC JANUARY                         Page: 213 of 374                               17 January 2017
No Points: 1.00 Time to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 61 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 rnme to Complete:               3 Difficulty:                     2.00 System ID:                       1601489 User-Defined ID:               Q#61NEW Lesson Plan Objective:           LGSOPS0078.11 rropic:                         Off-site Release Rate - Response of plant ventilation RO:                             3.3 SRO:                             3.5 KA#:                             APE 295017 AK3.02 LMK 2017 ILT NRC JANUARY                       Page: 214 of 374                             17 January 2017
3.50 System ID: 1601450 User-Defined ID: Q #63-BANK Lesson Plan Objective:
 
LG SOPS 1550.2 Topic: ON-107, Both CAD pumps are tripped and cannot be started and 23 HCU Accumulators RO: 3.3 SRO: 3.4 KA#: 295022 AA2.02 LMK 2017 IL T NRC JANUARY Page: 222 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRG JANUARY Page: 223 of 374 2 295022 AA2.02 RO 3.3 SRO 3.4 APE: 295022 Loss of CRD Pumps AA2. Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS : AA2.02 CRD s stem status Low 1 -Reactivit Control 41.10 ON-107 ReV:'' 1 #!';A\ 8 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 64 ID: 1442869 Points: 1.00 Unit 1 is operating at 100% power with the following conditions; SJAE DISCH TO RECOMBINER LO FLOW annunciator alarms Which of the following identifies where this parameter can be monitored and what is an expected Steam Jet Air Ejector (SJAE) response if actual flow is 9100 Lbm/hr? Location to monitor parameter A. 1 OC-652 Condenser panel B. 1 OC-652 Condenser panel C. 1 OC-673 OFF GAS panel D. 1 OC-673 OFF GAS panel Answer: C Answer Explanation SJAE response First Stage Air Ejector "AIR" valves will close Second Stage Air Ejector "STEAM" valve will close First Stage Air Ejector "AIR" valves will close Second Stage Air Ejector "STEAM" valve will close A Incorrect plausible to examinee who recalls that SJAE valves control stations and SJAE 2nd stage suction and discharge pressure indication are on 1 OC-652 and incorrectly believes that SJAE steam flow is also here B Incorrect plausible to examinee who recalls that SJAE valves control stations and SJAE 2nd stage suction and discharge pressure indication are on 1 OC-652 and incorrectly believes that SJAE steam flow is also here and incorrectly recalls which valve closes on low flow C Correct SJAE air and steam flow recorder FR-69-115 is located on 1 OC-673 and 1st stage air valves will close causing a loss of condenser vacuum D incorrect plausible to examinee who does not recall which SJAE valves close on low flow LMK 2017 IL T NRC JANUARY Page: 224 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 64 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
2 295017 AK3.02 RO 3.3 SRO 3.5 APE: 295017 High Off-Site Release Rate AK3. Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE:
No Points: 1.00 Time to Complete:
AK3.02 Plant ventilation.
3 Difficulty:
Low 9 Radioactivit Release 41.5 EP-AA-1008 Addendum 3 Unit 1 Tech Specs Table 3.3.7.1-1 N/A LMK 2017 ILT NRG JANUARY            Page: 215 of 374                          17 January 2017
3.00 System ID: 1442869 User-Defined ID: 0#64 NEW Lesson Plan Objective:
 
LGSOPS0069.7A iopic: Low vac RO: 4.6 SRO: 4.3 KA#: 295002 2.1.31 LMK 2017 IL T NRG JANUARY Page: 225 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 62                                                 ID: 1588469                                   Points: 1.00 Unit 1 is operating at 40% power, with the following:
LMK 2017 ILT NRC JANUARY Page: 226 of 374 4.6/4.3 Loss of Main Condenser Vacuum 2.1.31 Ability to locate control room switches, controls, and indications, and tol determine that they correctly reflect the desired lant lineu . 17 January 2017 65 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO 10:1588470 Points: 1.00 Initial Unit 2 plant conditions are as follows: -Reactor power is 100% -A group VlllA isolation occurred due to a blown fuse -The fuse has been replaced -Instrument Air is backing up Instrument Gas through SV-059-2288  
        - The '1A' RPV Narrow Range (NR) Level Transmitter that inputs to the 'A' NR level indicator on 1OC603 is failed upscale Five minutes later, the following occurs:
-Drywell pressure is 1.0 psig DOWN SLOW -Drywell venting is in progress through HV-057-211 and HV-057-217  
        - The '1 B' RPV Narrow Range (NR) Level Transmitter that inputs to the 'B' NR level indicator on 1OC603 fails upscale WHICH ONE of the following describes the plant response (assume no operator action)?
-Primary Containment Oxygen concentration is 3.5% UP SLOW No other Operator actions are taken and Drywell pressure stabilizes at 0.8 psig and then begins to rise slowly. The Containment Leak Detector is reading 88 cpm and steady. WHICH ONE of the following describes the required actions for these conditions?
A.       Reactor scrams due to a loss of Feedwater B.       Reactor scrams due to a Main Turbine trip; RFPs ARE available after the scram C.       Reactor remains operating D.       Reactor scrams due to a Main Turbine trip; RFPs are NOT available after the scram Answer:           C Answer Explanation The 4 RPV LTs that input to DFWLC for the high level turbine trip logic are setup different than RPS trip logic. The DFWLC trip logic is A or B and C or D. RPS trip logic is A or C and B or D.
A. Isolate instrument air to instrument gas and restart instrument gas B. Secure venting the Drywell per OT-101, High Drywell Pressure C. Raise rate of venting per OT-101, High Drywell Pressure D. Begin inerting the Drywell per T-228, lnerting/Purging Primary Containment Answer: A Answer Explanation A Correct, rising DW pressure with rising DW 02 and instrument air backing up instrument gas is indicative of a leak in the instrument gas system. Isolating instrument air to gas is directed by OT-101 since the VII IA isolation can be reset instrument gas should be restarted per OT-101 B Incorrect, secure venting is required if DW rad level is rising along with DW pressure plausible to C Incorrect raising vent rate cannot be done since both valves are fully open. plausible to examinee who confuses venting with purging. D Incorrect inertinq is directed from T-102 no entry for T-102 exists LMK 2017 IL T NRC JANUARY Page: 227 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 65 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
With A and B level transmitters for DFWLC failing upscale, the main turbine and RFPT will not trip on high level. additionally these transmitters are different than the RPS level transmitters
No Points: 1.00 Time to Complete:
          'C' is correct for the above reasons. Reactor remains operating
3 Difficulty:
          'A' is wrong. Reactor scrams due to a loss of Feedwater Plausible to the examinee who does not recall the LT coincidence needed to produce the turbine trip function.
2.00 System ID: 1588470 User-Defined ID: Q# 65 MODIFIED Lesson Plan Objective:
          'B' is wrong. Reactor scrams due to a Main Turbine trip; RFPs are available after the scram Plausible to the examinee who not only incorrectly concludes several points: 1) that these two LTs work together to produce the needed turbine trip logic; and 2) that the RFPTs are available, post-scram (i.e., that the RFPTs will not have tripped on the LT failures).
LLOT2006.1 Topic: OT-101, Drywall venting is in progress due to high drywall 1pressure RO: 3.8 SRO: 3.9 KA#: 295010 AA2.02 LMK 2017 IL T NRC JANUARY Page: 228 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
          'D' is wrong. Reactor scrams due to a Main Turbine trip; RFPs are nD.t available after the scram Plausible for reasons similar to choices 'B' and 'C'.
LMK 2017 IL T NRC JANUARY Page: 229 of 374 3.8/3.9 High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE : 562341 modified 562341 modified 562341 modified Rev 3 *#:'."i'.'i'.'f' 7 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 66 ID: 1682357 Points: 1.00 Consider the requirements of: -OP-AA-108-103, locked Equipment Program The PRO is directing the restoration of a locked, manual throttle valve to a position of "5 turns OPEN". WHICH ONE of the following describes the minimum verification(s) required for restoring this valve? A. Requires a Peer Check, ONLY B. Requires Concurrent Verification, ONLY C. Requires an Independent Verification, ONLY D. Requires a Peer Check AND an Independent Verification Answer: B Answer Explanation B is correct Per OP-AA-108-103, section 4.2.2 ... Concurrent Verification is required.
LMK 2017 ILT NRG JANUARY                         Page: 216 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 62 Info
:)uestion Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.50 System ID:                       1588469 User-Defined ID:                 0#62 BANK Lesson Plan Objective:           LLOT0540.14D Topic:                           Plant Response to RPV LT Upscale Failures RO:                             3.5 SRO:                             3.5 KA#:                             295008 AA 1.08 LMK 2017 ILT NRC JANUARY                       Page: 217 of 374                   17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
295008 AA 1.08 3.5/3.5 High Reactor Water Level Ability to operate and/or monitor the following as they apply to HIGH REACTOR WATER LEVEL : Feedwater 3
4 bank 908160 bank 908160 bank 908160 LMK 2017 ILT NRC JANUARY            Page: 218 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 219 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 63                                                 ID: 1601450                                 Points; 1.00 Unit 2 plant conditions are as follows:
        - Reactor power is 37%
        - Both CRD pumps are tripped and cannot be started 15 minutes later, 23 HCU Accumulator Trouble annunciators are alarming A GP-4 Shutdown is performed WHICH ONE of the following describes the plant response?
A.     23 rods will not insert B.     All rods will insert with normal scram times C.     All rods will insert with scram times greater than the Tech Spec allowable scram times for all rods D.     All rods will insert with scram times greater than the Tech Spec allowable scram times for 23 rods Answer:           B
        !Answer Explanation LMK 2017 ILT NRG JANUARY                         Page: 220 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO nswer: All rods will insert with normal scram times Per ON-107, During a reactor scram, the charging header provides the initial motive force to insert the rod. Then the scram accumulator pressure accelerates the drive and reactor pressure is used in the rod insertion process but is not required. For example, a rod scrammed at 900 psig reactor pressure and zero accumulator nitrogen pressure would result in an insignificant increase in scram time. Twenty minutes is allowed to restore a tripped CRD pump if more than 1 scram accumulator is inoperable and reactor pressure is equal to or greater than 900 psig since reactor pressure is adequate to insert all control rods with or without inoperative scram accumulators.
hen this condition occurs below 900 psig reactor pressure, the mode switch is to be placed in shutdown as required by Technical Specifications. The insertion and disarming of control rods hen more than one accumulator is inoperable is performed to comply with Technical Specifications.
3 rods will not insert - all rods will insert II rods will insert with significant longer scram times - all rods will insert, scram times will not ignificantly increase II rods will insert, however, 23 rods will have significant longer scram times - see explanation Examinee must recognize at 37% power reactor is at rated pressure A       Wrong - Plausible if the student mis-applies the extremely reduced reactor pressure impact on the control rod scram ability to the 23 Control Rods with reduced Scram Accumulator Pressures (i.e. - at extremely reduced RPV pressure CRD differential puressure is insufficient to insert the control rod.)
B       Correct - as described above C       Wrong - Plausible if the student mis-applies the reduced reactor pressure impact on the control rod scram ability to all core Control Rods (i.e. - at reduced RPV pressure rod scram times will be lengthened commencerate with the reduction in RPV pressure)
D     Wrong - Plausible if the student mis-applies the reduced reactor pressure impact on the control rod scram ability to the 23 Control Rods with reduced Scram Accumulator Pressures (i.e. - at reduced RPV pressure rod scram times will be lengthened commencerate with the reduction in RPV pressure)
LMK 2017 ILT NRC JANUARY                             Page: 221 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 63 Info Question Type:                   Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.50 System ID:                       1601450 User-Defined ID:                 Q #63- BANK Lesson Plan Objective:           LG SOPS 1550.2 ON-107, Both CAD pumps are tripped and cannot be started and Topic:
23 HCU Accumulators RO:                             3.3 SRO:                             3.4 KA#:                             295022 AA2.02 LMK 2017 ILT NRC JANUARY                       Page: 222 of 374                         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 295022 AA2.02 RO 3.3 SRO 3.4 APE: 295022 Loss of CRD Pumps AA2. Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS :
AA2.02 CRD s stem status Low 1 - Reactivit Control 41.10 ON-107 ReV:'' 1
                                                                                  #!';A\ 8 LMK 2017 ILT NRG JANUARY            Page: 223 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 64                                               ID: 1442869                                     Points: 1.00 Unit 1 is operating at 100% power with the following conditions; SJAE DISCH TO RECOMBINER LO FLOW annunciator alarms Which of the following identifies where this parameter can be monitored and what is an expected Steam Jet Air Ejector (SJAE) response if actual flow is 9100 Lbm/hr?
Location to monitor parameter                 SJAE response A.       1OC-652 Condenser panel                       First Stage Air Ejector "AIR" valves will close B.      1OC-652 Condenser panel                       Second Stage Air Ejector "STEAM" valve will close C.       1OC-673 OFF GAS panel                         First Stage Air Ejector "AIR" valves will close D.      1OC-673 OFF GAS panel                          Second Stage Air Ejector "STEAM" valve will close Answer:          C Answer Explanation A   Incorrect plausible to examinee who recalls that SJAE valves control stations and SJAE 2nd stage suction and discharge pressure indication are on 1OC-652 and incorrectly believes that SJAE steam flow is also here B   Incorrect plausible to examinee who recalls that SJAE valves control stations and SJAE 2nd stage suction and discharge pressure indication are on 1OC-652 and incorrectly believes that SJAE steam flow is also here and incorrectly recalls which valve closes on low flow C   Correct SJAE air and steam flow recorder FR-69-115 is located on 1OC-673 and 1st stage air valves will close causing a loss of condenser vacuum D   incorrect plausible to examinee who does not recall which SJAE valves close on low flow LMK 2017 ILT NRC JANUARY                         Page: 224 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 64 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.00 System ID:                       1442869 User-Defined ID:                 0#64 NEW Lesson Plan Objective:           LGSOPS0069.7A iopic:                           Low vac RO:                             4.6 SRO:                             4.3 KA#:                             295002 2.1.31 LMK 2017 ILT NRG JANUARY                       Page: 225 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
4.6/4.3 Loss of Main Condenser Vacuum 2.1.31 Ability to locate control room switches, controls, and indications, and tol determine that they correctly reflect the desired lant lineu .
LMK 2017 ILT NRC JANUARY            Page: 226 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO 65                                                  10:1588470                                   Points: 1.00 Initial Unit 2 plant conditions are as follows:
        -   Reactor power is 100%
        -   A group VlllA isolation occurred due to a blown fuse
        -   The fuse has been replaced
        -   Instrument Air is backing up Instrument Gas through SV-059-2288
        -   Drywell pressure is 1.0 psig DOWN SLOW
        -   Drywell venting is in progress through HV-057-211 and HV-057-217
        -   Primary Containment Oxygen concentration is 3.5% UP SLOW No other Operator actions are taken and Drywell pressure stabilizes at 0.8 psig and then begins to rise slowly.
The Containment Leak Detector is reading 88 cpm and steady.
WHICH ONE of the following describes the required actions for these conditions?
A.         Isolate instrument air to instrument gas and restart instrument gas B.       Secure venting the Drywell per OT-101, High Drywell Pressure C.       Raise rate of venting per OT-101, High Drywell Pressure D.       Begin inerting the Drywell per T-228, lnerting/Purging Primary Containment Answer:           A Answer Explanation A         Correct, rising DW pressure with rising DW 02 and instrument air backing up instrument gas is indicative of a leak in the instrument gas system. Isolating instrument air to gas is directed by         OT-101 since the VII IA isolation can be reset instrument gas should be restarted per OT-101 B         Incorrect, secure venting is required if DW rad level is rising along with DW pressure plausible to C         Incorrect raising vent rate cannot be done since both valves are fully open. plausible to examinee           who confuses venting with purging.
D         Incorrect inertinq is directed from T-102 no entry for T-102 exists LMK 2017 ILT NRC JANUARY                           Page: 227 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 65 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     2.00 System ID:                     1588470 User-Defined ID:               Q# 65 MODIFIED Lesson Plan Objective:         LLOT2006.1 OT-101, Drywall venting is in progress due to high drywall Topic:
1pressure RO:                             3.8 SRO:                           3.9 KA#:                           295010 AA2.02 LMK 2017 ILT NRC JANUARY                     Page: 228 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
3.8/3.9 High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE :
Rev 3
                                                                                  *#:'."i'.'i'.'f' 7 562341 modified 562341 modified 562341 modified LMK 2017 ILT NRC JANUARY            Page: 229 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 66                                               ID: 1682357                                   Points: 1.00 Consider the requirements of:
        - OP-AA-108-103, locked Equipment Program The PRO is directing the restoration of a locked, manual throttle valve to a position of "5 turns OPEN".
WHICH ONE of the following describes the minimum verification(s) required for restoring this valve?
A.       Requires a Peer Check, ONLY B.       Requires Concurrent Verification, ONLY C.       Requires an Independent Verification, ONLY D.       Requires a Peer Check AND an Independent Verification Answer:         B Answer Explanation B is correct Per OP-AA-108-103, section 4.2.2 ... Concurrent Verification is required.
A incorrect peer check is not used in the Locked Equipment Program C incorrect plausible to the examinee who recalls that general independent verification is a more stringent, but neglects the fact that the IV would have to unlock and reposition the valve, thus defeating the second verification.
A incorrect peer check is not used in the Locked Equipment Program C incorrect plausible to the examinee who recalls that general independent verification is a more stringent, but neglects the fact that the IV would have to unlock and reposition the valve, thus defeating the second verification.
D incorrect for the reasons stated above LMK 2017 IL T NRC JANUARY Page: 230 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 66 Info KA#: Comments:
D incorrect for the reasons stated above LMK 2017 ILT NRC JANUARY                         Page: 230 of 374                               17 January 2017
LMK 2017 IL T NRC JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 3 2.00 1682357 Q# 66 BANK LGSOPS2005A.2 Recall Controls for Restorin a Locked Manual Throttle Valve 3.9 4.3 2.2.14 Page: 231 of 374 3 N/A 2.1.8 RO 3.4 SRO 4.1 2.1.8 Ability to coordinate personnel activities outside the control room. Low N/A 41.10 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 232 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 67 ID: 1682350 Points: 1.00 The 1 A RHR Pump had been operating for 40 minutes in the full-flow test mode when it was manually secured. As soon as it was secured, it was realized that the 1 A RHR Pump needed to be restarted for testing. Which of the following describes the minimum wait time before restarting the 1 A RHR Pump? A. No wait time is required.
 
B. Must wait 15 minutes prior to restarting the pump. C. Must wait 30 minutes prior to restarting the pump. D. Must wait 60 minutes prior to restarting the pump. Answer: A Answer Explanation
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 66 Info Multi le Choice Active No No 1.00 3
* A is correct -per S51.8K 3.1 O For normal operations:
2.00 1682357 Q# 66 BANK LGSOPS2005A.2 Recall Controls for Restorin a Locked Manual Throttle Valve 3.9 4.3 KA#:                    2.2.14 Comments:
Pumps may only be started once an hour at rated temperature OR twice an hour at ambient temperature.
3 N/A 2.1.8 RO 3.4 SRO 4.1 2.1.8 Ability to coordinate personnel activities outside the control room.
Subsequent starts require a 30 minute run time at full speed OR 60 minute idle time. Since the motor has been running for 40 minutes, it can be started and brought up to operating speed one time with no waiting time required. correct B is incorrect but plausible if the examinee believes there is a 15 minute wait period requirement before restarting the Pump. C is incorrect but plausible if the examinee believes there is a 30 minute wait period requirement before restarting the Pump. D is incorrect but plausible if the examinee believes there is a 60 minute wait period requirement before restarting the Pump. lrhe precaution above aoolies to all larqe motors > 2.3 Kv and is not system specific LMK 2017 IL T NRC JANUARY Page: 233 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 67 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
Low N/A 41.10 LMK 2017 ILT NRC JANUARY              Page: 231 of 374                              17 January 2017
No Points: 1.00 rnme to Complete:
 
0 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 232 of 374       17 January 2017
0.00 System ID: 1682350 User-Defined ID: Q 67 BANK Lesson Plan Objective:
 
Topic: The1 A AHR Pump had been operating for 40 minutes in the full-flow test m RO: 3.8 SRO: KA#: 2.1.32 LMK 2017 IL T NRG JANUARY Page: 234 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 67                                               ID: 1682350                                   Points: 1.00 The 1A RHR Pump had been operating for 40 minutes in the full-flow test mode when it was manually secured. As soon as it was secured, it was realized that the 1A RHR Pump needed to be restarted for testing.
LMK 2017 IL T NRC JANUARY Page: 235 of 374 3 N/A 2.1.32 RO 3.8 Ability to explain and apply system limits and recautions.
Which of the following describes the minimum wait time before restarting the 1A RHR Pump?
41.10 'Rw'.;, 2 #:; 5 bank CL-ILT-635420 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 68 ID: 1588537 Points: 1.00 An operator must perform stroke time testing of a valve required by Technical Specifications for post-maintenance testing to restore operability.
A.       No wait time is required.
The valve is motor operated with seal-in control logic and a spring return to center control switch. To time the valve open, the operator must turn the control switch to the desired position (1) and must start the stopwatch when the (2) . A. (1) momentarily (2) red position indication light FIRST illuminates B. (1) momentarily (2) control Switch is placed to OPEN C. (1) for a count of three {3) (2) red position indication light FIRST illuminates D. (1) for a count of three (3) (2) control Switch is placed to OPEN Answer: D Answer Explanation From ST-6-107-200-0 IST VALVE STROKE SURVEILLANCE LOG step 3.3: 3.3 Stroke time is defined as the time from the initiation of the actuation signal until full closed indication OR full open indication is observed.
B.       Must wait 15 minutes prior to restarting the pump.
And OP-AA-103-105, LIMITORQUE MOTOR-OPERATED AND CHAINWHEEL OPERATED VALVE OPERATIONS step 4.2.2.3: 3. When remotely operating a MOV with seal-in control logic and a spring return o center control switch, the control switch must be turned to the desired position and held for a count of three (3) to ensure there is adequate time for he seal-in contacts to make-up. A Wrong -plausible to the student who fails to recall that the control swich must be held for a count of 3 to ensure adequate time for the seal-in contacts to make-up and to the student who mistakenly believes that the stopwatch is started when the red (open) position indication light first illuminates.
C.       Must wait 30 minutes prior to restarting the pump.
B Wrong -plausible to the student who fails to recall that the control swich must be held for a count of 3 to ensure adequate time for the seal-in contacts to make-up C Wrong -plausible to the student who mistakenly believes that the stopwatch is started when the red (open) position indication light first illuminates.
D.       Must wait 60 minutes prior to restarting the pump.
D Correct for the above reasons LMK 2017 IL T NRG JANUARY Page: 236 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 68 Info Question T e: Status: lwa s select on test? uthorized for ractice? lete: Comments:
Answer:           A Answer Explanation
LMK 2017 IL T NRG JANUARY ILT 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 3 3.00 1588537 Q# 68 -MODIFIED LGSOPS2010 27.C-CONDUCT OF OPS Valve Stroke -Post Maintenance Testin 2.9 2.2.21 Page: 237 of 374 OP-AA-103-105 OP-LG-108-101-1004 Modified from Clinton IL T 14-1 Exam #69. (Vision ID 1097944 Modified from Clinton IL T 14-1 Exam #69. (Vision ID 1097944 Created new first half of question to replace when to stop the stopwatch 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 238 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO LMK 2017 IL T NRG JANUARY Page: 239 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 69 ID: 1574760 Points: 1.00 Both Units are operating at 100% power. Maintenance has been performed on several air lock door seals. The following Post Maintenance Testing was performed with the resultant established SGTS flow rates at -.25 inches of water. Iest ST-6-076-310-1 SGTS REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY TEST ST-6-076-310-0 SGTS REFUEL AREA SECONDARY CONTAINMENT INTEGRITY TEST SGJS flow rate 2,250 CFM 820 CFM Which of the following identifies the status of the Unit 1 Reactor Enclosure and Refueling Area Secondary Containment for the above conditions?
* A is correct - per S51.8K 3.1 O For normal operations:
Unit 1 Reactor Enclosure Secondary Containment A. OPERABLE B. OPERABLE C. INOPERABLE D. INOPERABLE Answer: B !Answer Explanation LMK 2017 IL T NRG JANUARY Refueling Area Secondary Containment OPERABLE INOPERABLE OPERABLE INOPERABLE Page: 240 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO rThe Maintenance of Secondary Containment door seals impacts the operability of the Secondary Containment.
Pumps may only be started once an hour at rated temperature OR twice an hour at ambient temperature. Subsequent starts require a 30 minute run time at full speed OR 60 minute idle time.
From the Stem the student identifies that a "Drawdown test" was performed on the Refuel Floor and the Unit 1 Secondary Containment.
Since the motor has been running for 40 minutes, it can be started and brought up to operating speed one time with no waiting time required.
For the Reactor Enclosure the resultant flow of 2,250 CFM is within the surveillance requirement of 4.6.5.1.1.c.2 (less than or equal to 2,500 CFM). For the Refueling Area Secondary Containment the resultant flow of 820 CFM is NOT within the surveillance requirement of 4.6.5.1.2.( Less than or equal to 764 CFM). Based on the above information the Unit 1 Reactor Enclosure Secondary Containment is OPERABLE and the Refueling Floor Secondary Containment is INOPERABLE.
        ~is correct B is incorrect but plausible if the examinee believes there is a 15 minute wait period requirement before restarting the Pump.
These secondary containment SBGT flow rates are ON-111 symptoms for a loss of secondary containment and as such RO must know knowledge A Wrong -Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Refueling Area Secondary Containment B Correct as described above C Wrong -Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Refueling Area Secondary Containment and the Reactor Enclosure Secondary Containment D Wrong -Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Reactor Enclosure Secondary Containment LMK 2017 IL T NRC JANUARY Page: 241 of 37 4 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 69 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
C is incorrect but plausible if the examinee believes there is a 30 minute wait period requirement before restarting the Pump.
No Points: 1.00 Time to Complete:
D is incorrect but plausible if the examinee believes there is a 60 minute wait period requirement before restarting the Pump.
4 Difficulty:
lrhe precaution above aoolies to all larqe motors > 2.3 Kv and is not system specific LMK 2017 ILT NRC JANUARY                         Page: 233 of 374                               17 January 2017
2.00 Svstem ID: 1574760 User-Defined ID: Q#69 NEW Lesson Plan Objective:
 
LGSOPS0076B.9 Topic: Secondarv Containment Qperabilitv RO: 3.2 SRO: 3.8 KA#: G2.2.36 LMK 2017 ILT NRC JANUARY Page: 242 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 67 Info Question Type:                 Multiple Choice Status:                         Active
LMK 2017 IL T NRG JANUARY Page: 243 of 374 3 N/A 2.2.36 RO 3.1 SRO 4.2 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for o erations.
        ~lways select on test?           No
low N./A Tech Spec 3.6.5.2.1 Tech Spec 3.6.5.2.2 ST-6-076-310-0 ST-6-076-310-1 2 3 1 7 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 70 10:1455760 Points: 1.00 You have been authorized and briefed to do work in the RCA, the work area has no physical barrier (e.g., door); instead, its entrance has a barricade and flashing red light. Per RP-AA-460:
        ~uthorized for practice?         No Points:                         1.00 rnme to Complete:               0 Difficulty:                     0.00 System ID:                       1682350 User-Defined ID:                 Q 67 BANK Lesson Plan Objective:
WHICH one of the following identifies the posted radiation dose rate in this area? A. Greater than 30 mR/hr at 30 cm B. Greater than or equal to 100 mR/hr at 1 meter C. Greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter D. Greater than or equal to 500 mR/hr at 30 cm; less than 800 Rad/hr at 1 meter Answer: C Answer Explanation Per RP-AA-460, section 4.4.2.1.b.2 NOTE. .. a barricade and flashing red light can be used (in lieu of a physical barrier) only for a LHRA. Per section 4.4, the posted radiation dose rate (considering the more-conservative Exelon admin limit) for an LHRA is "greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter." A Incorrect Plausible to the exminee who recalls 80 Mr insted of 800 B incorect Plausible to the exminee who does not recall the 1 meter limit C correct the posted radiation dose rate (considering the more-conservative Exelon admin limit) for an LHRA is "greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter." D incorrect plausible to the examinee who reverses the 1 meter rad requirement LMK 2017 IL T NRC JANUARY Page: 244 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 70 Info Question Type: Multiple Choice Status: Active lAlways select on test? No lAuthorized for practice?
The1 A AHR Pump had been operating for 40 minutes in the Topic:
No Points: 1.00 rnme to Complete:
full-flow test m RO:                             3.8 SRO:
3 Difficulty:
KA#:                             2.1.32 LMK 2017 ILT NRG JANUARY                         Page: 234 of 374                       17 January 2017
2.00 System ID: 1455760 User-Defined ID: 0#70 BANK Lesson Plan Objective:
 
LLOT1760.10 Topic: Identity activities requiring drywell upper elevation access controls RO: 3.4 SRO: 3.8 KA#: 2.3.13 LMK 2017 IL T NRG JANUARY Page: 245 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRG JANUARY Page: 246 of 374 2.3.13 3.4/3.8 Knowledge of radiological safety procedures pertaining to licensed!
3 N/A 2.1.32 RO 3.8 Ability to explain and apply system limits and recautions.
operator duties, such as response to radiation monitor alarms,! containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, ali nin filters, etc. 986547 bank 986547 bank 986547 bank 'Rev:t, 2 9 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 71 ID: 1455767 Points: 1.00 An EO is required to enter an area in the Main Condenser Bay: -General area radiation level is 3 Rem/hr The EO's radiation history: -1760 mRem cumulative exposure for the current year (TEDE) -19 Rem lifetime exposure to this date (TEDE) -NRC Form 4 completed and on file -N.o dose extensions have been obtained The work activity will take 45 minutes to complete.
41.10
Regarding the following radiation exposure limits, which one of the answer choices identifies the limit(s), if any, that will be exceeded?  
                                                                                'Rw'.;, 2
: 1. Administrative Dose Control Level 2. NRC Exposure Limit 3. Emergency Exposure Limit A. None B. Limit #1 ONLY C. Limits #1 and #2 ONLY D. Limits #1, #2 AND #3 Answer: B Answer Explanation Calculating the EO's expected dose for this 45-minute activity:
                                                                                #:;     5 bank CL-ILT-635420 LMK 2017 ILT NRC JANUARY            Page: 235 of 374                        17 January 2017
3 Rem = 3000 mRem 3000 mRem X .75 = 2250 mRem to his current dose: 2250 mRem + 1760 mRem = 401 O mRem TEDE 4010 mRem exceeds the 2000 mRem TEDE Admin Dose Control Level of RP-AA-203, section 4.1.2. 4010 mRem does NQI exceed the 5000 mRem NRC Exposure Limit of section 4.1.1, Table 1. N.oLdoes the 4010 mRem (4.01 Rem) exceed the 10,000 mRem (10 rem) ... for protecting station property ... Emergency Exposure Limit of section 4.5.3, Table 2. ANSWER: Admin Dose Control Level onlv LMK 2017 IL T NRC JANUARY Page: 247 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 71 Info Question T e: Status: Comments:
 
LMK 2017 IL T NRC JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 4 2.50 1455767 Q#71BANK LLOT1760.5 Determine if an Dose Limits will be exceeded 3.2 3.7 2.3.4 Page: 248 of 374 Knowledge of radiation exposure limits under normal conditions.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 68                                                   ID: 1588537                                 Points: 1.00 An operator must perform stroke time testing of a valve required by Technical Specifications for post-maintenance testing to restore operability. The valve is motor operated with seal-in control logic and a spring return to center control switch.
bank 591143 bank 591143 bank 591143 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 249 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 72 10:1649570 Points: 1.00 Plant conditions:  
To time the valve open, the operator must turn the control switch to the desired position     (1)     and must start the stopwatch when the           (2) .
-Unit 1 is in OPCON 1 -Unit 2 is in OPCON 2 with GP-2, STARTUP in progress A yafui OBE EXCEEDED alarm is received and is confirmed by the U.S. Geological Survey. WHICH ONE of the following is a required operator action? A. Manually scram both reactors 8. Perform GP-4 Rapid Plant Shutdown on Unit 1 Manually scram Unit 2 reactor C. Perform GP-4 Rapid Plant Shutdown on both Units D. Perform GP-3 Normal Plant Shutdown on both Units Answer: A Answer Explanation Per SE-5 (Earthquake), Steps 4.2 and 4.5. The "valid" comment in the stem translates to "evidence of the seismic event" (mentioned in Step 4.5). Though Step 4.5 is not an "Immediate perator Action" initial license candidates are expected to recall manual scram/GP-4 Rapid Shutdown actions, no matter where they exist in procedure.
A.         (1) momentarily (2) red position indication light FIRST illuminates B.         (1) momentarily (2) control Switch is placed to OPEN C.         (1) for a count of three {3)
plausible to the examinee who considers that, whenever practical, LGS procedures direct us to perform a GP-4 Rapid Plant Shutdown (i.e., running Recirc Pumps to minimum speed and ransferring house loads to the startup buses before scramming the reactor) in order to minimize he plant transient.
(2) red position indication light FIRST illuminates D.         (1) for a count of three (3)
The fact that Unit 2 is only in OPCON 2 during a startup, the idea of simply scramming the reactor (i.e., without concern for the severity of a plant transient) makes this answer choice all the more distracting.
(2) control Switch is placed to OPEN Answer:             D Answer Explanation From ST-6-107-200-0 IST VALVE STROKE SURVEILLANCE LOG step 3.3:
Plausible to the exam i nee who does not recognize the significance of an OBE earthquake and/or confuses it with an SSE earthquake.
3.3 Stroke time is defined as the time from the initiation of the actuation signal until full closed indication OR full open indication is observed.
As such, the examinee is compelled to believe that an orderly plant shutdown of both Units is sufficient to miti ate the effects of the OBE. LMK 2017 IL T NRC JANUARY Page: 250 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 72 Info Question T e: Multi le Choice Status: Active No uthorized for ractice? No 1.00 lete: 3 2.00 1649570 Q# 72 BANK 2015 NRG LGSOPS2000.2 SE-5 -Recall Re uirements for Manual Scram 4.0 4.2 2.4.11 4.0/4.2 Bank 558648 2015 NRG LMK 2017 IL T NRC JANUARY Page: 251 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 252 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 73 ID: 1455732 The CRS has directed performance of T-260 REACTOR PRESSURE VESSEL DEPRESSURIZATIONNENTING on UNIT 2.
And OP-AA-103-105, LIMITORQUE MOTOR-OPERATED AND CHAINWHEEL OPERATED VALVE OPERATIONS step 4.2.2.3:
: 3. When remotely operating a MOV with seal-in control logic and a spring return o center control switch, the control switch must be turned to the desired position and held for a count of three (3) to ensure there is adequate time for he seal-in contacts to make-up.
A     Wrong - plausible to the student who fails to recall that the control swich must be held for a count of 3 to ensure adequate time for the seal-in contacts to make-up and to the student who mistakenly believes that the stopwatch is started when the red (open) position indication light first illuminates.
B     Wrong - plausible to the student who fails to recall that the control swich must be held for a count of 3 to ensure adequate time for the seal-in contacts to make-up C     Wrong - plausible to the student who mistakenly believes that the stopwatch is started when the red (open) position indication light first illuminates.
D     Correct for the above reasons LMK 2017 ILT NRG JANUARY                             Page: 236 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 68 Info Question T e:                   Multi le Choice Status:                         Active lwa s select on test?         No uthorized for ractice?         No 1.00 lete:            3 3.00 1588537 Q# 68 - MODIFIED LGSOPS2010 27.C-CONDUCT OF OPS Valve Stroke - Post Maintenance Testin 2.9 2.2.21 Comments:
OP-AA-103-105 OP-LG-108-101-1004 Modified from Clinton ILT 14-1 Exam #69. (Vision ID 1097944 Modified from Clinton ILT 14-1 Exam #69. (Vision ID 1097944 Created new first half of question to replace when to stop the stopwatch LMK 2017 ILT NRG JANUARY                      Page: 237 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 238 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 ILT NRG JANUARY             Page: 239 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 69                                               ID: 1574760                                 Points: 1.00 Both Units are operating at 100% power.
Maintenance has been performed on several air lock door seals.
The following Post Maintenance Testing was performed with the resultant established SGTS flow rates at
-.25 inches of water.
Iest                                           SGJS flow rate ST-6-076-310-1 SGTS REACTOR ENCLOSURE SECONDARY CONTAINMENT                                       2,250 CFM INTEGRITY TEST ST-6-076-310-0 SGTS REFUEL AREA SECONDARY CONTAINMENT INTEGRITY                                       820 CFM TEST Which of the following identifies the status of the Unit 1 Reactor Enclosure and Refueling Area Secondary Containment for the above conditions?
Unit 1 Reactor Enclosure Secondary                Refueling Area Secondary Containment Containment A.       OPERABLE                                        OPERABLE B.       OPERABLE                                       INOPERABLE C.       INOPERABLE                                     OPERABLE D.       INOPERABLE                                      INOPERABLE Answer:         B
        !Answer Explanation LMK 2017 ILT NRG JANUARY                         Page: 240 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO rThe Maintenance of Secondary Containment door seals impacts the operability of the Secondary Containment. From the Stem the student identifies that a "Drawdown test" was performed on the Refuel Floor and the Unit 1 Secondary Containment. For the Reactor Enclosure the resultant flow of 2,250 CFM is within the surveillance requirement of 4.6.5.1.1.c.2 (less than or equal to 2,500 CFM). For the Refueling Area Secondary Containment the resultant flow of 820 CFM is NOT within the surveillance requirement of 4.6.5.1.2.( Less than or equal to 764 CFM). Based on the above information the Unit 1 Reactor Enclosure Secondary Containment is OPERABLE and the Refueling Floor Secondary Containment is INOPERABLE.
These secondary containment SBGT flow rates are ON-111 symptoms for a loss of secondary containment and as such RO must know knowledge A   Wrong - Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Refueling Area Secondary Containment B     Correct as described above C     Wrong - Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Refueling Area Secondary Containment and the Reactor Enclosure Secondary Containment D     Wrong - Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Reactor Enclosure Secondary Containment LMK 2017 ILT NRC JANUARY                       Page: 241 of 37 4                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 69 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               4 Difficulty:                     2.00 Svstem ID:                       1574760 User-Defined ID:                 Q#69 NEW Lesson Plan Objective:           LGSOPS0076B.9 Topic:                           Secondarv Containment Qperabilitv RO:                             3.2 SRO:                             3.8 KA#:                             G2.2.36 LMK 2017 ILT NRC JANUARY                       Page: 242 of 374           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
3 N/A 2.2.36 RO 3.1 SRO 4.2 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for o erations.
low N./A Tech Spec 3.6.5.2.1 Tech Spec                   2 3.6.5.2.2                   3 ST-6-076-310-0             1 ST-6-076-310-1             7 LMK 2017 ILT NRG JANUARY            Page: 243 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 70                                             10:1455760                                   Points: 1.00 You have been authorized and briefed to do work in the RCA, the work area has no physical barrier (e.g.,
door); instead, its entrance has a barricade and flashing red light.
Per RP-AA-460:
WHICH one of the following identifies the posted radiation dose rate in this area?
A.       Greater than 30 mR/hr at 30 cm B.       Greater than or equal to 100 mR/hr at 1 meter C.       Greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter D.       Greater than or equal to 500 mR/hr at 30 cm; less than 800 Rad/hr at 1 meter Answer:         C Answer Explanation Per RP-AA-460, section 4.4.2.1.b.2 NOTE. .. a barricade and flashing red light can be used (in lieu of a physical barrier) only for a LHRA. Per section 4.4, the posted radiation dose rate (considering the more-conservative Exelon admin limit) for an LHRA is "greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter."
A Incorrect Plausible to the exminee who recalls 80 Mr insted of 800 B incorect Plausible to the exminee who does not recall the 1 meter limit C correct the posted radiation dose rate (considering the more-conservative Exelon admin limit) for an LHRA is "greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter."
D incorrect plausible to the examinee who reverses the 1 meter rad requirement LMK 2017 ILT NRC JANUARY                       Page: 244 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 70 Info Question Type:                   Multiple Choice Status:                         Active lAlways select on test?           No lAuthorized for practice?         No Points:                         1.00 rnme to Complete:                 3 Difficulty:                     2.00 System ID:                       1455760 User-Defined ID:                 0#70 BANK Lesson Plan Objective:           LLOT1760.10 Identity activities requiring drywell upper elevation access Topic:
controls RO:                             3.4 SRO:                             3.8 KA#:                             2.3.13 LMK 2017 ILT NRG JANUARY                       Page: 245 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2.3.13 3.4/3.8 Knowledge of radiological safety procedures pertaining to licensed!
operator duties, such as response to radiation monitor alarms,!
containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, ali nin filters, etc.
                                                                                  'Rev:t, 2 fhtt):Bl~: 9 986547 bank 986547 bank 986547 bank LMK 2017 ILT NRG JANUARY            Page: 246 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 71                                             ID: 1455767                                   Points: 1.00 An EO is required to enter an area in the Main Condenser Bay:
        - General area radiation level is 3 Rem/hr The EO's radiation history:
        - 1760 mRem cumulative exposure for the current year (TEDE)
        - 19 Rem lifetime exposure to this date (TEDE)
        - NRC Form 4 completed and on file
        - N.o dose extensions have been obtained The work activity will take 45 minutes to complete.
Regarding the following radiation exposure limits, which one of the answer choices identifies the limit(s), if any, that will be exceeded?
: 1. Administrative Dose Control Level
: 2. NRC Exposure Limit
: 3. Emergency Exposure Limit A.       None B.       Limit #1 ONLY C.       Limits #1 and #2 ONLY D.       Limits #1, #2 AND #3 Answer:           B Answer Explanation Calculating the EO's expected dose for this 45-minute activity:
3 Rem = 3000 mRem 3000 mRem X .75 = 2250 mRem
        ~dded to his current dose:
2250 mRem + 1760 mRem       = 401 O mRem TEDE 4010 mRem exceeds the 2000 mRem TEDE Admin Dose Control Level of RP-AA-203, section 4.1.2.
4010 mRem does NQI exceed the 5000 mRem NRC Exposure Limit of section 4.1.1, Table 1.
N.oLdoes the 4010 mRem (4.01 Rem) exceed the 10,000 mRem (10 rem) ... for protecting station property ... Emergency Exposure Limit of section 4.5.3, Table 2.
ANSWER: Admin Dose Control Level onlv LMK 2017 ILT NRC JANUARY                       Page: 247 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 71 Info Question T  e:          Multi le Choice Status:                  Active No No 1.00 4
2.50 1455767 Q#71BANK LLOT1760.5 Determine if an Dose Limits will be exceeded 3.2 3.7
 
====2.3.4 Comments====
Knowledge of radiation exposure limits under normal conditions.
bank 591143 bank 591143 bank 591143 LMK 2017 ILT NRC JANUARY              Page: 248 of 374                              17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 249 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 72                                                           10:1649570                                                 Points: 1.00 Plant conditions:
        - Unit 1 is in OPCON 1
        - Unit 2 is in OPCON 2 with GP-2, STARTUP in progress A yafui OBE EXCEEDED alarm is received and is confirmed by the U.S. Geological Survey.
WHICH ONE of the following is a required operator action?
A.         Manually scram both reactors
: 8.         Perform GP-4 Rapid Plant Shutdown on Unit 1 Manually scram Unit 2 reactor C.         Perform GP-4 Rapid Plant Shutdown on both Units D.         Perform GP-3 Normal Plant Shutdown on both Units Answer:               A Answer Explanation Per SE-5 (Earthquake), Steps 4.2 and 4.5. The "valid" comment in the stem translates to "evidence of the seismic event" (mentioned in Step 4.5). Though Step 4.5 is not an "Immediate perator Action" initial license candidates are expected to recall manual scram/GP-4 Rapid Shutdown actions, no matter where they exist in procedure.
1:.t:L~lJ'.Q.[ig.:Jt::e!lQITil...!.;;~L.l::iiap,u:LJ::jaillJill.lilll!OWILQr:LU.!]JlJL;.NLaillJ.aU;~dfilD.J.!illL~!.aCJ:o.r...Very plausible to the examinee who considers that, whenever practical, LGS procedures direct us to perform a GP-4 Rapid Plant Shutdown (i.e., running Recirc Pumps to minimum speed and ransferring house loads to the startup buses before scramming the reactor) in order to minimize he plant transient. The fact that Unit 2 is only in OPCON 2 during a startup, the idea of simply scramming the reactor (i.e., without concern for the severity of a plant transient) makes this answer choice all the more distracting.
r.u:.J.S...:wa~~'..e.r:t.orrll:i.1:.:::a.JiQim;~1artt..:::tnuta.c!Wr:LQILDJ:llll_u.rllls.. Plausible to the exam inee who does not recognize the significance of an OBE earthquake and/or confuses it with an SSE earthquake. As such, the examinee is compelled to believe that an orderly plant shutdown of both Units is sufficient to miti ate the effects of the OBE.
LMK 2017 ILT NRC JANUARY                                     Page: 250 of 374                                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 72 Info Question T e:                   Multi le Choice Status:                         Active No uthorized for ractice?         No 1.00 lete:             3 2.00 1649570 Q# 72 BANK 2015 NRG LGSOPS2000.2 SE Recall Re uirements for Manual Scram 4.0 4.2 2.4.11 4.0/4.2 Bank 558648 2015 NRG LMK 2017 ILT NRC JANUARY                       Page: 251 of 374                         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 252 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 73                                               ID: 1455732                                   Points: 1.00 The CRS has directed performance of T-260 REACTOR PRESSURE VESSEL DEPRESSURIZATIONNENTING on UNIT 2.
* The MSIV's are currently closed but are pneumatically functional
* The MSIV's are currently closed but are pneumatically functional
* The Main condenser is available
* The Main condenser is available
* Reactor pressure is 990 psig
* Reactor pressure is 990 psig
* Main Steam Line pressure is 400 psig down slow Points: 1.00 Step 4.1 RPV DEPRESSURIZATIONNENTING USING MAIN STEAM LINES is being performed Given the following valves. 1 . Bypass Leakage Barrier Block valves HV-41-242 and HV-41-243  
* Main Steam Line pressure is 400 psig down slow Step 4.1 RPV DEPRESSURIZATIONNENTING USING MAIN STEAM LINES is being performed Given the following valves.
: 2. Bypass Leakage Barrier Vent valves HV-41-240 and HV-41-241 From the above list, which valves, if required to be operated, will be operated by an equipment operator and where will the reactor steam be vented to? Actions pertormed by an Equipment Operator Reactor Steam will be directed to A. 20NLY Main Condenser B. 1 ONLY Reactor Enclosure  
: 1. Bypass Leakage Barrier Block valves HV-41-242 and HV-41-243
: c. 1 AND2 Main Condenser D. 1 AND2 Reactor Enclosure Answer: C Answer Explanation valves are operated locally reactor enclosure or AER room there are position indicating lights in the MCR. Section 4.2 using steam line drain vents to reactor enclosure A Incorrect both 1 and 2 are remote actions B Incorrect both 1 and 2 are remote actions and steam is directed to the main condenser C Correct both actions are performed locally and steam is directed to the main condenser D Incorrect steam is directed to the main condenser LMK 2017 ILT NRC JANUARY Page: 253 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 73 Info Question T e: Status: lwa s select on test? uthorized for ractice? lete: Comments:
: 2. Bypass Leakage Barrier Vent valves HV-41-240 and HV-41-241 From the above list, which valves, if required to be operated, will be operated by an equipment operator and where will the reactor steam be vented to?
LMK 2017 ILT NRC JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 3 2.00 1455732 Q# 73 NEW LGSOPS2003.3 EO actions 3.8 4.0 2.4.35 Page: 254 of 374 2.4.35 3.8/4.0 Knowledge of local auxiliary operator tasks during an emergency and the resultant o erational effects. low 9 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 255 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 74 ID: 1455708 Points: 1.00 WHICH ONE of the following requires a Unit 2 Tech Spec LCO Action that is 1-hour or less? A. RWCU inboard PCIV HV-44-2F001 breaker trips and cannot be reset. B. Operating at 100% power when 28 Recirc Pump trips C. Operating at 20% power when one control rod is determined to be stuck and is declared inoperable D. OPCON 1 when 022 DG fails its monthly surveillance and is declared inoperable Answer: C Answer Explanation U/2 TS 3.1.3.1.a.1 (for a stuck rod) is a "within 1 hour" action. U/2 TS 3.6.3.a is a 4 hour" action. U/2 TS 3.4.1.1.a (one recirc loop not in service) is a "within 4 hours" action. U/2 TS 3.8.1.1.a (one DG inoperable) is a "within 24 hours" action for demonstrating operability of lthe remaining AC sources (SR 4.8.1.1.1.a).
Actions pertormed by an Equipment             Reactor Steam will be directed to Operator A.       20NLY                                         Main Condenser B.         1 ONLY                                       Reactor Enclosure
However, Action 'e' also applies ... requiring the same SR 4.8.1.1.1.a to be performed "within 2 hours". LMK 2017 IL T NRG JANUARY Page: 256 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 74 Info Question T e: Status: lwa s select on test? uthorized for ractice? lete: Comments:
: c.         1 AND2                                       Main Condenser D.         1 AND2                                       Reactor Enclosure Answer:           C Answer Explanation
LMK 2017 IL T NRC JANUARY IL T 15-01 January 2017 NRG test SRO Multi le Choice Active No No 1.00 3 2.50 1455708 Q# 74 BANK LGSOPS00418.9 Tech S 3.9 4.5 .2.39 Page: 257 of 374 nize condition re 1-hour TS Action 2.2.39 3.9/4.5 Knowledge of less than or equal to one hour Technical Specification  
        ~lthough    valves are operated locally reactor enclosure or AER room there are position indicating lights in the MCR.
!action statements for s stems. Lower Tech Specs bank 989362 bank 989362 bank 989362 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 258 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 259 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 75 ID: 1455175 Points: 1.00 An earthquake has occurred resulting in the breach of a wall in the Unit 1 Spent Fuel Pool (SFP). Unit 1 SFP level is lowering, with the following:
Section 4.2 using steam line drain vents to reactor enclosure A     Incorrect both 1 and 2 are remote actions B   Incorrect both 1 and 2 are remote actions and steam is directed to the main condenser C     Correct both actions are performed locally and steam is directed to the main condenser D   Incorrect steam is directed to the main condenser LMK 2017 ILT NRC JANUARY                         Page: 253 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 73 Info Question T e:                   Multi le Choice Status:                         Active lwa s select on test?         No uthorized for ractice?       No 1.00 lete:            3 2.00 1455732 Q# 73 NEW LGSOPS2003.3 EO actions 3.8 4.0 2.4.35 Comments:
2.4.35 3.8/4.0 Knowledge of local auxiliary operator tasks during an emergency and the resultant o erational effects.
low 9
LMK 2017 ILT NRC JANUARY                      Page: 254 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 255 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 74                                               ID: 1455708                                   Points: 1.00 WHICH ONE of the following requires a Unit 2 Tech Spec LCO Action that is 1-hour or less?
A.     RWCU inboard PCIV HV-44-2F001 breaker trips and cannot be reset.
B.     Operating at 100% power when 28 Recirc Pump trips C.     Operating at 20% power when one control rod is determined to be stuck and is declared inoperable D.     OPCON 1 when 022 DG fails its monthly surveillance and is declared inoperable Answer:         C Answer Explanation U/2 TS 3.1.3.1.a.1 (for a stuck rod) is a "within 1 hour" action.
U/2 TS 3.6.3.a is a 4 hour" action.
U/2 TS 3.4.1.1.a (one recirc loop not in service) is a "within 4 hours" action.
U/2 TS 3.8.1.1.a (one DG inoperable) is a "within 24 hours" action for demonstrating operability of lthe remaining AC sources (SR 4.8.1.1.1.a). However, Action 'e' also applies ... requiring the same SR 4.8.1.1.1.a to be performed "within 2 hours".
LMK 2017 ILT NRG JANUARY                         Page: 256 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 74 Info Question T e:                   Multi le Choice Status:                         Active lwa s select on test?         No uthorized for ractice?       No 1.00 lete:            3 2.50 1455708 Q# 74 BANK LGSOPS00418.9 Tech S                 nize condition re        1-hour TS Action 3.9 4.5
                                          .2.39 Comments:
2.2.39 3.9/4.5 Knowledge of less than or equal to one hour Technical Specification !action statements for s stems.
Lower Tech Specs bank 989362 bank 989362 bank 989362 LMK 2017 ILT NRC JANUARY                      Page: 257 of 374                                  17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 258 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 259 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 75                                               ID: 1455175                             Points: 1.00 An earthquake has occurred resulting in the breach of a wall in the Unit 1 Spent Fuel Pool (SFP).
Unit 1 SFP level is lowering, with the following:
* Operators are NQI able to mitigate the SFP level problem using S53.0 normal makeup I response to low level in fuel storage pool or reactor well
* Operators are NQI able to mitigate the SFP level problem using S53.0 normal makeup I response to low level in fuel storage pool or reactor well
* An Equipment Operator on 352 elevation estimates the leakage rate is 800 gpm Operators enter TSG-4.1, 'Operational Contingency Guidelines.'
* An Equipment Operator on 352 elevation estimates the leakage rate is 800 gpm Operators enter TSG-4.1, 'Operational Contingency Guidelines.'
WHICH ONE of the following:  
WHICH ONE of the following:
(1) identifies which method for cooling the SFP should be used FIRST ("Makeup" or "Spray"), .and. (2) identifies if "Locally" or "External" source for 1ba1 method? A. (1) Makeup (2) Locally B. (1) Makeup (2) External c. (1) Spray (2) Locally D. (1) Spray (2) External Answer: c !Answer Explanation LMK 2017 IL T NRG JANUARY Page: 260 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO his question tests the examinee's ability to use the Alternate (B.5.b) Strategies of TSG-4.1. Key points in the stem are: an estimated SFP leakage rate of 800 gpm, and the fact that the refuel loor is still accessible.
(1) identifies which method for cooling the SFP should be used FIRST ("Makeup" or "Spray"), .and.
he examinee need only review Section I (SFP Cooling & Makeup), specifically, including its lowchart ("Generalized Decision Process for SFP Makeup versus Spray"). Following the decision points on this flowchart  
(2) identifies if "Locally" or "External" source for 1ba1 method?
... i.e., SFP Area Accessible? (YES); SFP Leakage Excessive (YES; see Note 3 at the bottom of the page ... anything greater than 500 gpm is excessive).
A.         (1) Makeup (2) Locally B.         (1) Makeup (2) External
As such, the FIRST method to be used is ... "Deploy Spray Locally" 'C' is correct for the above reasons. (1) Spray (2) Locally 'A' is wrong. (1) Makeup (2) Locally In the case of the Makeup method, "locally" is actually referred to as "Internal" in the TSG. Plausible to the examinee who cannot effectively use the lowchart.  
: c.         (1) Spray (2) Locally D.         (1) Spray (2) External Answer:             c
'B' is wrong. (1) Makeup (2) External Plausible for the same reason as choice 'A'. 'D' is wron . 2 External Plausible for the same reason as choices 'A' and 'B'. LMK 2017 IL T NRC JANUARY Page: 261 of 374 17 January 2017 EXAMINATION ANSWER KEY Comments:
        !Answer Explanation LMK 2017 ILT NRG JANUARY                           Page: 260 of 374                         17 January 2017
LMK 2017 IL T NRC JANUARY ILT 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 6 2.50 1455175 Q# 75 BANK LGSOPS2004.01 Selectin 8.5.b Strate er TSG-4.1 3.9 4.2 G2.1.25 Page: 262 of 374 2.1.25 3.9/4.2 Ability to interpret reference materials, such as graphs, curves, tables, etc. TSG-4.1 page 6 bank 895221 bank 895221 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 263 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 76 ID: 1650711 Points: 1.00 SRO 118 15 UNIT 1 ISO PHASE BUS COOLER TROUBLE alarm actuates.
 
An EO reports both ISO PHASE fans are tripped and cannot be started. The crew enters ON-101 , Loss of Isolated Phase Bus Cooling. Conditions at T =2 minutes: -Generator amps: 27,500 -MVARs: 285 -ISO PHASE temperature:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO his question tests the examinee's ability to use the Alternate (B.5.b) Strategies of TSG-4.1. Key points in the stem are: an estimated SFP leakage rate of 800 gpm, and the fact that the refuel loor is still accessible.
102 degrees C, up slow Conditions at T =13 minutes: -Generator amps: 19,500 -MVARs: 45 -ISO PHASE temperature:
he examinee need only review Section I (SFP Cooling & Makeup), specifically, including its lowchart ("Generalized Decision Process for SFP Makeup versus Spray").
104 degrees C, up slow Per ON-101, which of the following actions is required?
Following the decision points on this flowchart ... i.e., SFP Area Accessible? (YES); SFP Leakage Excessive (YES; see Note 3 at the bottom of the page ... anything greater than 500 gpm is excessive). As such, the FIRST method to be used is ... "Deploy Spray Locally"
A. Reduce MVARs to 0, if temperature rises above105 degrees C then perform a GP-4 Rapid Plant Shutdown.
        'C' is correct for the above reasons. (1) Spray (2) Locally
B. Continue to monitor temperatures and if temperature rises above 105 degrees C then continue reducing power in accordance with GP-5, Appendix 2. C. Reduce MVARs to 0, if temperature rises above 105 degrees C then perform load reduction to less than 7,469 generator amps. D. Immediately lower load to less than 7,469 generator amps. Answer: A Answer Explanation Justification:
        'A' is wrong. (1) Makeup (2) Locally In the case of the Makeup method, "locally" is actually referred to as "Internal" in the TSG. Plausible to the examinee who cannot effectively use the lowchart.
A. Correct Answer A: Reduction of MVARs to zero is directed in ON-101, Step 2.3 prior to steps to reduce power. Step 2.4 directs power reduction to less than 20,000 amps. Step 2.7 directs a GP-4 shutdown if power is above 25% and temperatures cannot be maintained less than 105 degrees C. 19,500 amps is approximately 62% power B. B is NOT correct because if maximum temperature is 105 and continuing to rise. A rapid plant shutdown is required.
        'B' is wrong. (1) Makeup (2) External Plausible for the same reason as choice 'A'.
Plausible to examinee who knows the limit of 105 degrees C but either does not recall a GP-4shutdown would is required or does not recall that 105 is max limit and machine must be immediately removed and belives power reduction is appropriate.
        'D' is wron .               2 External   Plausible for the same reason as choices 'A' and 'B'.
C. C is NOT correct. ON-101 does not contain guidance to lower load to 7,469. Plausible because a loss of stator cooling will result in an EHC load set runback if stator cooling is lost with stator current> 7,469 amps. I D. Choice Dis NOT correct. ON-101 does not direct this action. Plausible for reasons given for Choice C. LMK 2017 IL T NRG JANUARY Page: 264 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 76 Info Question T e: Status: lwa s select on test? uthorized for ractice? lete: RO: SRO: KA#: Comments:
LMK 2017 ILT NRC JANUARY                       Page: 261 of 374                                 17 January 2017
LMK 2017 IL T NRG JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 3 3.00 1650711 Q#76 NEW LOT0180.6P loss of iso hase 3.3 3.4 Page: 265 of 374 295018 AA2.01 3.3/3.4 Partial or Complete Loss of Component Cooling Water. Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Component n/a new 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 266 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 77 SRO Unit 2 is operating at 100% power HPCI testing is in progress ID; 1453889 A loss of EHC caused reactor pressure to spike to 1100 psig. 5 minutes after the pressure spike, Unit 2 plant conditions are as follows:
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 6
2.50 1455175 Q# 75 BANK LGSOPS2004.01 Selectin 8.5.b Strate er TSG-4.1 3.9 4.2 G2.1.25 Comments:
2.1.25 3.9/4.2 Ability to interpret reference materials, such as graphs, curves, tables, etc.
TSG-4.1 page 6 bank 895221 bank 895221 LMK 2017 ILT NRC JANUARY              Page: 262 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 263 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 76                                               ID: 1650711                                     Points: 1.00 SRO 118 15 UNIT 1 ISO PHASE BUS COOLER TROUBLE alarm actuates. An EO reports both ISO PHASE fans are tripped and cannot be started. The crew enters ON-101 , Loss of Isolated Phase Bus Cooling.
Conditions at T =2 minutes:
- Generator amps: 27,500
- MVARs: 285
- ISO PHASE temperature: 102 degrees C, up slow Conditions at T=13 minutes:
- Generator amps: 19,500
- MVARs: 45
- ISO PHASE temperature: 104 degrees C, up slow Per ON-101, which of the following actions is required?
A.       Reduce MVARs to 0, if temperature rises above105 degrees C then perform a GP-4 Rapid Plant Shutdown.
B.       Continue to monitor temperatures and if temperature rises above 105 degrees C then continue reducing power in accordance with GP-5, Appendix 2.
C.       Reduce MVARs to 0, if temperature rises above 105 degrees C then perform load reduction to less than 7,469 generator amps.
D.       Immediately lower load to less than 7,469 generator amps.
Answer:           A Answer Explanation Justification:
A.     Correct Answer A: Reduction of MVARs to zero is directed in ON-101, Step 2.3 prior to steps to reduce power. Step 2.4 directs power reduction to less than 20,000 amps.
Step 2.7 directs a GP-4 shutdown if power is above 25% and temperatures cannot be maintained less than 105 degrees C. 19,500 amps is approximately 62% power B.     B is NOT correct because if maximum temperature is 105 and continuing to rise. A rapid plant shutdown is required. Plausible to examinee who knows the limit of 105 degrees C but either does not recall a GP-4shutdown would is required or does not recall that 105 is max limit and machine must be immediately removed and belives power reduction is appropriate.
C.     C is NOT correct. ON-101 does not contain guidance to lower load to 7,469. Plausible because a loss of stator cooling will result in an EHC load set runback if stator cooling is lost with stator current> 7,469 amps.
I   D. Choice Dis NOT correct. ON-101 does not direct this action. Plausible for reasons given for Choice C.
LMK 2017 ILT NRG JANUARY                         Page: 264 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 76 Info Question T e:                   Multi le Choice Status:                         Active lwa s select on test?         No uthorized for ractice?         No 1.00 lete:            3 3.00 1650711 Q#76 NEW LOT0180.6P loss of iso hase RO:                              3.3 SRO:                            3.4 KA#:
Comments:
295018 AA2.01 3.3/3.4 Partial or Complete Loss of Component Cooling Water. Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Component n/a new LMK 2017 ILT NRG JANUARY                      Page: 265 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 266 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 77                                               ID; 1453889                                    Points: 1.00 SRO Unit 2 is operating at 100% power HPCI testing is in progress A loss of EHC caused reactor pressure to spike to 1100 psig.
5 minutes after the pressure spike, Unit 2 plant conditions are as follows:
* All SCRAM actions are complete
* All SCRAM actions are complete
* All APRMs are reading between 3.4 and 3.8 percent power
* All APRMs are reading between 3.4 and 3.8 percent power
Line 787: Line 1,602:
* Suppression Pool temperature is 105 degrees F and rising 1 degree every 4 minutes 20 minutes after the pressure spike
* Suppression Pool temperature is 105 degrees F and rising 1 degree every 4 minutes 20 minutes after the pressure spike
* All APRMs are still reading between 3.4 and 3.8 percent power Given
* All APRMs are still reading between 3.4 and 3.8 percent power Given
* T-213 INDIVIDUAL CONTROL ROD SCRAM/SOLENOID DE-ENERGIZATION
* T-213   INDIVIDUAL CONTROL ROD SCRAM/SOLENOID DE-ENERGIZATION
* T-215 DE-ENERGIZATION OF SCRAM SOLENOIDS
* T-215   DE-ENERGIZATION OF SCRAM SOLENOIDS
* T-216 MANUAL ISOLATION AND VENT OF SCRAM AIR HEADER Points: 1.00
* T-216   MANUAL ISOLATION AND VENT OF SCRAM AIR HEADER
* T-217 RPS/ARI RESET AND BACKUP METHOD OF DRAINING SCRAM DISCHARGE VOLUME
* T-217   RPS/ARI RESET AND BACKUP METHOD OF DRAINING SCRAM DISCHARGE VOLUME
* T-218 CONTROL ROD INSERTION BY WITHDRAW LINE VENTING
* T-218   CONTROL ROD INSERTION BY WITHDRAW LINE VENTING
* T-219 MAXIMIZING CAD COOLING WATER HEADER FLOW DURING ATWS CONDITIONS Which of the following lists the procedure to be used to insert rods, and if SBLC injection is required Procedures to insert rods SBLC injection required A. T-213, T-215, T-216, and T-219 Yes B. T-213, T-215, T-216, and T-219 No c. T-217 and T-218 No D. T-217 and T-218 Yes Answer: D !Answer Explanation LMK 2017 IL T NRC JANUARY Page: 267 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO << Incorrect examinee must determine that a SCRAM setpoint was exceeded and based on A power level either RPS or ARI inserted most rods as such the SCRAM air headed is depressurized air header depressurized per T-101 RC/Q13 T-217 and T-218 are directed plausible to the examinee who does not interpret the stem as a hydraulic ATWS and either does not recall the values for note 16 reactor shutdown (IRM below range 6) or miss applies step RC/Q4 B Incorrect examinee must determine that a SCRAM setpoint was exceeded and either RPS or ARI inserted most rods as such the SCRAM air headed is depressurized air header depressurized per T-101 RC/Q13 T-217 and T-218 are directed plausible to the examinee who does not interpret the stem as a hydraulic ATWS and or does not recall requirement to inject SLC prior to 11 O degrees in the suppression pool C Incorrect plausible to examinee who either does not recall the values for note 16 reactor shutdown (IRM below range 6) or miss applies step RC/Q4 and or does not recall requirement to inject SLC prior to 11 O degrees in the suppression pool D Correct examinee must determine that a SCRAM setpoint was exceeded and based on power level either RPS or ARI inserted most rods, (but must determine/
* T-219   MAXIMIZING CAD COOLING WATER HEADER FLOW DURING ATWS CONDITIONS Which of the following lists the procedure to be used to insert rods, and if SBLC injection is required Procedures to insert rods                               SBLC injection required A.       T-213, T-215, T-216, and T-219             Yes B.       T-213, T-215, T-216, and T-219             No
interpret that all rods did not insert to the NON-ATWS position of beyond 02), as such the SCRAM air headed is depressurized.
: c.       T-217 and T-218                             No D.       T-217 and T-218                             Yes Answer:           D
It the air header is depressurized per T-101 RC/Q13 T-217 and T-218 are directed and pool temperature is rising indicating a steam input to pool as such the SRO candidate must recognize (without reference) that TRIPS require him to order SLC injection prior to pool exceeding 110 degrees per T-101-RC/Q-16  
          !Answer Explanation LMK 2017 ILT NRC JANUARY                         Page: 267 of 374                               17 January 2017
-101 .,. Insert control rods using one OR more of the following:
 
Scram valves Scram valves Open Closed *Vent/drain  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO
*Scram solenoids scram discharge (T-215) volume (T-217) *Air header (T-216) *Withdraw line *Maximize CRD cooling vent (T-218) water flow (T-219)
        <<   Incorrect examinee must determine that a SCRAM setpoint was exceeded and based on A     power level either RPS or ARI inserted most rods as such the SCRAM air headed is depressurized air header depressurized per T-101 RC/Q13 T-217 and T-218 are directed plausible to the examinee who does not interpret the stem as a hydraulic ATWS and either does not recall the values for note 16 reactor shutdown (IRM below range 6) or miss applies step RC/Q4 B     Incorrect examinee must determine that a SCRAM setpoint was exceeded and either RPS or ARI inserted most rods as such the SCRAM air headed is depressurized air header depressurized per T-101 RC/Q13 T-217 and T-218 are directed plausible to the examinee who does not interpret the stem as a hydraulic ATWS and or does not recall requirement to inject SLC prior to 11 O degrees in the suppression pool C     Incorrect plausible to examinee who either does not recall the values for note 16 reactor shutdown (IRM below range 6) or miss applies step RC/Q4 and or does not recall requirement to inject SLC prior to 11 O degrees in the suppression pool D     Correct examinee must determine that a SCRAM setpoint was exceeded and based on power level either RPS or ARI inserted most rods, (but must determine/ interpret that all rods did not insert to the NON-ATWS position of beyond 02), as such the SCRAM air headed is depressurized. It the air header is depressurized per T-101 RC/Q13 T-217 and T-218 are directed and pool temperature is rising indicating a steam input to pool as such the SRO candidate must recognize (without reference) that TRIPS require him to order SLC injection prior to pool exceeding 110 degrees per T-101-RC/Q-16
          -101                                 .,.
Insert control rods using one OR more of the following:
Scram valves                             Scram valves Open                                     Closed
            *Vent/drain                       *Scram solenoids scram discharge                       (T-215) volume (T-217)                   *Air header (T-216)
            *Withdraw line                     *Maximize CRD cooling vent (T-218)                         water flow (T-219)
* Individual rod scrams (T-213)
* Individual rod scrams (T-213)
* RCJQ-13 I -101 LMK 2017 IL T NRC JANUARY Page: 268 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO --------I I BEFORE Supp Pool temp reaches 110&deg;F, L_ RC/Q-16 THEN inject SLC (848.1.B.
RCJQ-13                           *I
App. 1) -----------
          -101 LMK 2017 ILT NRC JANUARY                           Page: 268 of 374                           17 January 2017
LMK 2017 IL T NRC JANUARY Page: 269 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Question 77 Info Question Type: Multiple Choice Status: Active select on test? No [Authorized for practice?
 
No Points: 1.00 Time to Complete:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO I       BEFORE Supp Pool temp reaches 110&deg;F, I      THEN         inject SLC (848.1.B. App. 1)
2 Difficulty:
L_  ~-
3.00 System ID: 1453889 User-Defined ID: 0#77 NEW Lesson Plan Objective:
RC/Q-16  - ----------
LGSOPS1560.06 Topic: SRO Pool temperature RO: 4.0 SRO: 4.1 KA#: 295037 EA2.04 LMK 2017 IL T NRG JANUARY Page: 270 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
LMK 2017 ILT NRC JANUARY               Page: 269 of 374       17 January 2017
LMK 2017 IL T NRC JANUARY Page: 271 of 374 Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 78 10:1433288 Points: 1.00 SRO Unit 1 is operating at 100% power At 13:02 the following annunciator was received in the MCR: 006-1-2-L CONT EL 254 PB WEST.
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 77 Info Question Type:                   Multiple Choice Status:                         Active
        ~lwavs select on test?           No
[Authorized for practice?         No Points:                           1.00 Time to Complete:               2 Difficulty:                     3.00 System ID:                       1453889 User-Defined ID:                 0#77 NEW Lesson Plan Objective:           LGSOPS1560.06 Topic:                           SRO Pool temperature RO:                             4.0 SRO:                             4.1 KA#:                             295037 EA2.04 LMK 2017 ILT NRG JANUARY                       Page: 270 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR LMK 2017 ILT NRC JANUARY            Page: 271 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 78                                                 10:1433288                                     Points: 1.00 SRO Unit 1 is operating at 100% power At 13:02 the following annunciator was received in the MCR: 006-1-2-L CONT EL 254 PB WEST.
* The fire is in the static inverter room in the MCR annunciator fuse panel
* The fire is in the static inverter room in the MCR annunciator fuse panel
* At 13:12 the fire brigade leader reports the fire is extinguished
* At 13:12 the fire brigade leader reports the fire is extinguished
* As a result of the fire MCR annunciator panel 107 REACTOR AND 003 RAD have lost power
* As a result of the fire MCR annunciator panel 107 REACTOR AND 003 RAD have lost power
* The CRS entered ON-122 for the loss of annunciators Which of the following identifies an additional procedure the CRS is required to enter and the EAL declaration, if any? Additional Procedure entered EAL declaration reQuired A. T-104 None B. T-104 Unusual Event C. T-103 None D. T-103 Unusual Event Answer: C Explanation A Incorrect ON-122 provides direction for the TRIP procedure to enter if annunciator panels which contain entry conditions to T-103 OR T-104 are lost. ON-122 step 4.4 directs T-103 entry plausible to the examinee who incorrectly recalls which Trip procedure to enter. The second part is correct the fire is extinguished in less than 15 minutes so no HU3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 MCR indication no longer applies B Incorrect Incorrect ON-122 provides direction for the TRIP procedure to enter if annunciator panels which contain entry conditions to T-103 OR T-104 are lost. ON-122 step 4.4 directs T-103 entry plausible to the examinee who incorrectly recalls which Trip procedure to enter. The second part is incorrect the fire is extinguished in less than 15 minutes so no H U3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 no longer applies C Correct since the annunciator panel that lost power has T-103 entry condition (DIV 1-4 steam leak detection)
* The CRS entered ON-122 for the loss of annunciators Which of the following identifies an additional procedure the CRS is required to enter and the EAL declaration, if any?
ON-122 will direct entry to T-103 for performance of T-290 The second part is correct the fire is extinguished in less than 15 minutes so no HU3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 no longer applies D Incorrect plausible to the examinee who recalls T-103 entry is required but incorrectly believes either MU4 or HU3 should be ceclared.
Additional Procedure entered                     EAL declaration reQuired A.       T-104                                           None B.       T-104                                           Unusual Event C.       T-103                                           None D.       T-103                                           Unusual Event Answer:           C
LMK 2017 IL T NRG JANUARY Page: 272 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 78 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
          ~nswer Explanation A     Incorrect ON-122 provides direction for the TRIP procedure to enter if annunciator panels which contain entry conditions to T-103 OR T-104 are lost. ON-122 step 4.4 directs T-103 entry plausible to the examinee who incorrectly recalls which Trip procedure to enter. The second part is correct the fire is extinguished in less than 15 minutes so no HU3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 MCR indication no longer applies B     Incorrect Incorrect ON-122 provides direction for the TRIP procedure to enter if annunciator panels which contain entry conditions to T-103 OR T-104 are lost. ON-122 step 4.4 directs T-103 entry plausible to the examinee who incorrectly recalls which Trip procedure to enter. The second part is incorrect the fire is extinguished in less than 15 minutes so no H U3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 no longer applies C     Correct since the annunciator panel that lost power has T-103 entry condition (DIV 1-4 steam leak detection) ON-122 will direct entry to T-103 for performance of T-290 The second part is correct the fire is extinguished in less than 15 minutes so no HU3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 no longer applies D     Incorrect plausible to the examinee who recalls T-103 entry is required but incorrectly believes either MU4 or HU3 should be ceclared.
No Points: 1.00 Time to Complete:
LMK 2017 ILT NRG JANUARY                           Page: 272 of 374                               17 January 2017
4 Difficulty:
 
4.00 System ID: 1433288 User-Defined ID: Q# 78 NEW Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 78 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               4 Difficulty:                     4.00 System ID:                       1433288 User-Defined ID:                 Q# 78 NEW Lesson Plan Objective:           LOT1550.03 Topic:                           SRO Fire protection RO:                             3.1 SRO:                             3.6 KA#:                             600000 AA2.17 LMK 2017 ILT NRC JANUARY                       Page: 273 of 374     17 January 2017
LOT1550.03 Topic: SRO Fire protection RO: 3.1 SRO: 3.6 KA#: 600000 AA2.17 LMK 2017 IL T NRC JANUARY Page: 273 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 IL T NRG JANUARY Page: 274 of 374 RO 600000 AA2.17 301 /3.6 Plant Fire on site Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: AA2.17 Systems that may be affected b the fire 2 3  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
<<L,'.: 2 0 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 275 of 374 17 January 2017 79 SRO EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO ID: 1454790 Points: 1.00 Unit 1 is in OPCON 1
RO 600000 AA2.17 301 /3.6 Plant Fire on site Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:
AA2.17 Systems that may be affected b the fire 2
                                                                                  .Rev1~      3 2
                                                                                  ,<:.~;, ;'~'
                                                                                  <<L,'.:     0 LMK 2017 ILT NRG JANUARY            Page: 274 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 275 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 79                                                  ID: 1454790                                             Points: 1.00 SRO Unit 1 is in OPCON 1
* The pressure regulator for HV-076-196 SGTS (Standby Gas Treatment System) unit 1 exh isolation valve, air supply valve has a small air leak
* The pressure regulator for HV-076-196 SGTS (Standby Gas Treatment System) unit 1 exh isolation valve, air supply valve has a small air leak
* While the FIN team is investigating the pressure regulator becomes detached from the air line.
* While the FIN team is investigating the pressure regulator becomes detached from the air line.
* The Fin team closes HV-076-196 (AS) to stop the leak.
* The Fin team closes HV-076-196 (AS) to stop the leak.
* After the air isolation valve is closed the FIN team reports the status to the MCR.
* After the air isolation valve is closed the FIN team reports the status to the MCR.
* The RO reports that neither SBGT fan is running OVERRrDE FROM ZS-76-IOOA  
* The RO reports that neither SBGT fan is running OVERRrDE FROM ZS-76-IOOA ! G.4 l   S--- -       -     -
! G.4 l S------ISO TRIP r-*--------------
ISO TRIP r-*--------------                                                                               REACToR ENCLOsuRE ISOLATION SIGNAL FROM NOTE I CHANNEi. A 1
REACToR ENCLOsuRE ISOLATION SIGNAL FROM NOTE I CHANNEi. A 1 r---I 1 a.313'*0' FPD-206-1<1 1 I I I C881 '*1*1 C881
r---             ~~
-----<SH.2 G..5l M-26 FROM ZS-76-IOOB SOVERRIDE
C881
* { G,4 J l.. /:'. ISO TRIP REACTOR ENCLOSURE  
                                                                                              ~                                  mi~
!SOI.A TION 1 R r --SIGNAL FROM NOTE I y *-.f ISO .TRI!" CHANNR S 1occ101 11 css1 . --------1 ZS .
I                                                                    1 1                                                                    I I~~ ~
lSOlS! 197-T HS I I HO ---=i c--=---=---=---=---=---=--=-
                                                                                                          '*1*1 I L~:AI-~  C881
l
                                                  ~ a.313'*0' FPD-206-1<1 I   FROM ZS-76-IOOB SOVERRIDE
* I ' Which of the choices below correctly identifies the INOPERABLE SGTS Subsystem(s)
                                                                                                        <SH.2 G..5l   M-26
AND a required TS action? INOP subsystem(s)
                                                                            * { G,4 J l..
TS action A. ONLY A Restore subsystem within 7 days B. Both AAND B Begin a shutdown within 1 hour c. ONLY A Restore subsystem within 14 days D. Both A and B Restore subsystem within 2 hours Answer: A LMK 2017 IL T NRC JANUARY Page: 276 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer Explanation A Correct Loss of air will cause HV-076-0196 to fail open this should start A SBGT only. failure to start makes A SBGT INOP this is a 7 day LCO B Incorrect plausible to the examinee who does not recall or cannot determine from information provided that one valve opening does not start both trains of SBGT. T.S action would be correct if both trains were INOP C Incorrect A train only is correct however the T.S action is incorrect plausible to examinee who confuses SBGT T.S with CREFAS T.S D Incorrect only A is INOP and T.S is for one train INOP LMK 2017 IL T NRC JANUARY Page: 277 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 79 Info Question Type: Multiple Choice Status: Active select on test? No for practice?
1~
No Points: 1.00 [Time to Complete:
                                                                                /:'.
4 Difficulty:
y *-.f R  r- -    ISO TRIP
3.00 System ID: 1454790 User-Defined ID: Q# 79 NEW Lesson Plan Objective:
                                                                                        ~ ISO .TRI!"
LOT0200.13 rropic: SRO SBGT RO: 3.1 SRO: 4.2 KA#: 295019 2.2.36 LMK 2017 IL T NRC JANUARY Page: 278 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
REACTOR ENCLOSURE !SOI.A TION SIGNAL FROM NOTE I CHANNR S 1occ101   11                 css1         ~c R~~~~  .   - -------
LMK 2017 IL T NRC JANUARY Page: 279 of 374 3.1/4.2 Partial or Complete Loss of Instrument Air Ability to analyze the effect of maintenance activities, such as degraded I power sources, on the status of limiting conditions for o erations.
1197-ZS     ~
17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 80 10:1454228 Points; 1.00 SRO Plant conditions are as follows;
                                                                                      ~I              ~
T      .       ~~-t lSOlS!
                                                                                                                      ~-                     HS Ir-~ I ~*~                                            I         HO 1ll1~:el ~ ---=i
* c--=---=---=---=---=---=--=- l                         I           '
Which of the choices below correctly identifies the INOPERABLE SGTS Subsystem(s) AND a required TS action?
INOP subsystem(s)                               TS action A.         ONLY A                                       Restore subsystem within 7 days B.         Both AAND B                                   Begin a shutdown within 1 hour
: c.         ONLY A                                       Restore subsystem within 14 days D.         Both A and B                                 Restore subsystem within 2 hours Answer:           A LMK 2017 ILT NRC JANUARY                           Page: 276 of 374                                       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer Explanation A   Correct Loss of air will cause HV-076-0196 to fail open this should start A SBGT only.
failure to start makes A SBGT INOP this is a 7 day LCO B   Incorrect plausible to the examinee who does not recall or cannot determine from information provided that one valve opening does not start both trains of SBGT. T.S action would be correct if both trains were INOP C   Incorrect A train only is correct however the T.S action is incorrect plausible to examinee who confuses SBGT T.S with CREFAS T.S D   Incorrect only A is INOP and T.S is for one train INOP LMK 2017 ILT NRC JANUARY                         Page: 277 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 79 Info Question Type:                   Multiple Choice Status:                         Active
        ~lwavs select on test?           No
        ~uthorized for practice?         No Points:                         1.00
[Time to Complete:             4 Difficulty:                     3.00 System ID:                       1454790 User-Defined ID:                 Q# 79 NEW Lesson Plan Objective:           LOT0200.13 rropic:                         SRO SBGT RO:                             3.1 SRO:                             4.2 KA#:                           295019 2.2.36 LMK 2017 ILT NRC JANUARY                       Page: 278 of 374     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
3.1/4.2 Partial or Complete Loss of Instrument Air Ability to analyze the effect of maintenance activities, such as degraded I power sources, on the status of limiting conditions for o erations.
LMK 2017 ILT NRC JANUARY            Page: 279 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 80                                               10:1454228                                       Points; 1.00 SRO Plant conditions are as follows;
* Reactor power is 30% down slow
* Reactor power is 30% down slow
* The RO is inserting control rods
* The RO is inserting control rods
Line 847: Line 1,703:
* The main turbine was tripped due to HI vibration
* The main turbine was tripped due to HI vibration
* The main condenser vacuum breakers were opened With regard to the procedures listed below, which of the choices identifies the system(s) utilized in the EOP mitigation strategy for level control after the turbine trip until the ATWS is terminated?
* The main condenser vacuum breakers were opened With regard to the procedures listed below, which of the choices identifies the system(s) utilized in the EOP mitigation strategy for level control after the turbine trip until the ATWS is terminated?
T-251, Establish A HPCI Flow path Via Feedwater Only T-270, Terminate and Prevent Injection Into The RPV S06.1.D, Post SCRAM Level Control A. HPCI per T-251 but NOT RCIC per T-270 B. RCIC per T-270 but NOT HPCI per T-251 C. HPCI per T-251 AND RCIC per T-270 D. Condensate Pumps per S06.1.D Answer: C Answer Explanation A Incorrect plausible to the examinee who does not recall that T-270, terminate and prevent injection to the RPV allows RCIC to inject during an ATWS. B Incorrect although RCIC will be injecting it is not suficient to maintain level also HPCI can be used for after T-270 is complate and the SRO moves to stepLQ-119 which will allow HPCI through feedwater only per T-251 C Correct post turbine trip vacuum breakers are opened condensate is not available due to ATWS and pressure being maintained 990-1096 HPCI is available for level control through feedwater per T-251 and RCIC is allowed to inject per T-270 D Incorrect although cond. pps are available with an ATWS in progress reactor pressure will not be lowered per stop sign in T-101 RCP-18 LMK 2017 IL T NRC JANUARY Page: 280 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 80 Info Multi le Choice Active No No 1.00 3 3.00 1454228 Q# 80 NEW LGSOPS1560.06 SRO ATWS turb tri 3.7 4.7 295005 2.4.6 Comments:
T-251, Establish A HPCI Flow path Via Feedwater Only T-270, Terminate and Prevent Injection Into The RPV S06.1.D, Post SCRAM Level Control A.       HPCI per T-251 but NOT RCIC per T-270 B.       RCIC per T-270 but NOT HPCI per T-251 C.       HPCI per T-251 AND RCIC per T-270 D.       Condensate Pumps per S06.1.D Answer:           C Answer Explanation A     Incorrect plausible to the examinee who does not recall that T-270, terminate and prevent injection to the RPV allows RCIC to inject during an ATWS.
LMK 2017 ILT NRG JANUARY Page: 281 of 374 295005 2.4.6 3.7/4.7 Main Turbine Generator Trip Emergency Procedures I Plan Knowledge of EOP miti ation strate ies. 43.5 T-101 Rev< 2 ft;s:;{\ 2 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 282 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 283 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 81 SRO A LOCA occurred on unit 1 Plant conditions are as follows:
B     Incorrect although RCIC will be injecting it is not suficient to maintain level also HPCI can be used for after T-270 is complate and the SRO moves to stepLQ-119 which will allow HPCI through feedwater only per T-251 C     Correct post turbine trip vacuum breakers are opened condensate is not available due to ATWS and pressure being maintained 990-1096 HPCI is available for level control through feedwater per T-251 and RCIC is allowed to inject per T-270 D     Incorrect although cond. pps are available with an ATWS in progress reactor pressure will not be lowered per stop sign in T-101 RCP-18 LMK 2017 ILT NRC JANUARY                         Page: 280 of 374                                 17 January 2017
* All control rods fully inserted 10:1433008
 
* Reactor water level is -10 inches steady
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 80 Info Multi le Choice Active No No 1.00 3
3.00 1454228 Q# 80 NEW LGSOPS1560.06 SRO ATWS turb tri 3.7 4.7 295005 2.4.6 Comments:
295005 2.4.6 3.7/4.7 Main Turbine Generator Trip Emergency Procedures I Plan Knowledge of EOP miti ation strate ies.
43.5 T-101               Rev< 2 ft;s:;{\ 2 LMK 2017 ILT NRG JANUARY              Page: 281 of 374                      17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 282 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 283 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 81                                               10:1433008                          Points: 1.00 SRO A LOCA occurred on unit 1 Plant conditions are as follows:
* All control rods fully inserted
* Reactor water level is - 10 inches steady
* Reactor pressure is 960 psig steady
* Reactor pressure is 960 psig steady
* Suppression pool water level is 15 feet steady Points: 1.00
* Suppression pool water level is 15 feet steady
* Suppression pool water temperature on SPOTMOS Tl-41-101 A & B is 135&deg; F up slow
* Suppression pool water temperature on SPOTMOS Tl-41-101 A & B is 135&deg; F up slow
* B RHR is in suppression pool cooling
* B RHR is in suppression pool cooling
* B RHR suction temperature is 149&deg; F LMK 2017 IL T NRC JANUARY Page: 284 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Given the following information:
* B RHR suction temperature is 149&deg; F LMK 2017 ILT NRC JANUARY                         Page: 284 of 374                     17 January 2017
CURVE SP/T-1 LEGEND RPV PRESS --0 -55 psig 56 -300 prig 301 -500 psig 501 -700 prig -701 -900 psig -001 -1170 prig L CURVE SP/T-1 _J HEAT CAPACITY TEMP. LIMIT 25(} 230 21() CL L-19() ! :I e 170 !. E i! 15(} 8 0.. BO c:. 0 .ill ! lll} Q. Q. ::I 9() en 70 50 j(} 12 Suppression Pool Water Level (ft) Which of the following (1) is required to be directed by the CRS and (2) The reason for this action? A. (1) Depressurize the reactor to <900 psig per T-102 (2) Suppression pool temperature is approaching HCTL Limit S. (1) Emergency Slowdown IAW T-112 (2) HCTL is being exceeded C. (1) Depressurize the reactor to 750 psig per T-102 (2) HCTL is being exceeded D. (1) Emergency Slowdown IAW T-112 (2) Suppression pool temperature is approaching HCTL Limit LMK 2017 IL T NRC JANUARY Page: 285 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Answer: B Answer Explanation A Incorrect (1) Depressurize the reactor to <900 psig per T-102 (2) Suppression pool temperature is approaching HCTL Limit HTCL is being exceeded, a blowdown is required per SPfr-7 of T-102 This action and reason are plausible to the examinee who does not recall T-102 note 2 which makes the Tl-41-101 A&B not usable B Correct HTCL is being exceeded so a blowdown is required per T-112 from step SPfr-8 of T-102 C Incorrect ( 1) Depressurize the reactor to <900 psig per T-102 (2) HCTL is being exceeded Plausible to the examinee who confuses step SPfr-7 (cannot be maintained) with steps like SP/L-15 (cannot be Restored and Maintained D Incorrect (1) Emergency Slowdown IAW T-112 (2) Suppression pool temperature is approaching HCTL Limit Plausible to the Examinee who does not recognize that HCTL has already been exceeded and believe a blowdown is warranted prior to exceeding HCTL WHEN WHEN safe side of safe side of Curve Curve SP/L-t SPIT-1 ' CANNOT CANNOT '"'-.. be restored be maintained, AND maintained, contim.1e I.t:ifl1 continue SP!T-7 I
 
* L SPlL-15 " I #2 SPOTMOS probes located at Supp Pool level of 17. 8 ft. RHR suction temp it h RHR operating below 17. 8 ft is alid Supp Pool temp. LMK 2017 ILT NRG JANUARY Page: 286 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 81 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Given the following information:
No Points: 1.00 Time to Complete:
CURVE SP/T-1 LEGEND
3 Difficulty:
                          ~                    RPV PRESS 0 - 55 psig 56 - 300 prig
3.00 System ID: 1433008 User-Defined ID: Q#81NEW Lesson Plan Objective:
                            ~                  301 - 500 psig
LGSOPS1506.6 Topic: SRO Pool temp RO: 4.2 SRO: 4.2 KA#: :295026 2.4.47 LMK 2017 IL T NRC JANUARY Page: 287 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Comments:
                            --L 501 - 700 prig 701 - 900 psig 001 - 1170 prig CURVE SP/T-1
LMK 2017 IL T NRC JANUARY Page: 288 of 374 295026 2.4.47 4.2/4.2 Suppression Pool High Water Temperature 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
_J HEAT CAPACITY TEMP. LIMIT 25(}
17 January 2017 82 SRO EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 10:1454368 Points: 1.00 Unit 2 is operating at 100% power, with a normal electrical lineup.
230 21()
CL L- 19()
:I e 170 E
i! 15(}
80.. BO c:.
0
        .ill lll}
        !Q.
Q.
::I en    9()
70 50 j(}
12 Suppression Pool Water Level (ft)
Which of the following (1) is required to be directed by the CRS and (2) The reason for this action?
A.       (1) Depressurize the reactor to <900 psig per T-102 (2) Suppression pool temperature is approaching HCTL Limit S.       (1) Emergency Slowdown IAW T-112 (2) HCTL is being exceeded C.       (1) Depressurize the reactor to 750 psig per T-102 (2) HCTL is being exceeded D.       (1) Emergency Slowdown IAW T-112 (2) Suppression pool temperature is approaching HCTL Limit LMK 2017 ILT NRC JANUARY                                 Page: 285 of 374                     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer:             B Answer Explanation A     Incorrect (1) Depressurize the reactor to <900 psig per T-102 (2) Suppression pool temperature is approaching HCTL Limit HTCL is being exceeded, a blowdown is required per SPfr-7 of T-102 This action and reason are plausible to the examinee who does not recall T-102 note 2 which makes the Tl-41-101 A&B not usable B     Correct HTCL is being exceeded so a blowdown is required per T-112 from step SPfr-8 of T-102 C     Incorrect (1) Depressurize the reactor to <900 psig per T-102 (2) HCTL is being exceeded Plausible to the examinee who confuses step SPfr-7 (cannot be maintained) with steps like SP/L-15 (cannot be Restored and Maintained D     Incorrect (1) Emergency Slowdown IAW T-112 (2) Suppression pool temperature is approaching HCTL Limit Plausible to the Examinee who does not recognize that HCTL has already been exceeded and believe a blowdown is warranted prior to exceeding HCTL WHEN                                     WHEN safe side of                             safe side of Curve                               Curve SP/L-t SPIT-1                                 CANNOT CANNOT               ' '"'-..
be restored be maintained,                                 AND
                        ~                                    maintained, contim.1e                                 I.t:ifl1 continue SP!T-7           I
* L   SPlL-15
        #2 I
SPOTMOS probes located at Supp Pool level of 17. 8 ft. RHR suction temp it h RHR operating below 17. 8 ft is alid Supp Pool temp.
LMK 2017 ILT NRG JANUARY                               Page: 286 of 374                     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 81 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.00 System ID:                       1433008 User-Defined ID:               Q#81NEW Lesson Plan Objective:           LGSOPS1506.6 Topic:                           SRO Pool temp RO:                             4.2 SRO:                             4.2 KA#:                           :295026 2.4.47 LMK 2017 ILT NRC JANUARY                     Page: 287 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Comments:
295026 2.4.47 4.2/4.2 Suppression Pool High Water Temperature 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
LMK 2017 ILT NRC JANUARY            Page: 288 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 82                                                  10:1454368                                   Points: 1.00 SRO Unit 2 is operating at 100% power, with a normal electrical lineup.
* A grid disturbance results in 500 KV grid voltage lowering to 497 KV Which of the choices identifies the adverse generator condition that is prevented by adjusting VARs as directed by E-5, Grid Emergency and if Technical Specification 3.8.1.1., Sources Operating entry is required?
* A grid disturbance results in 500 KV grid voltage lowering to 497 KV Which of the choices identifies the adverse generator condition that is prevented by adjusting VARs as directed by E-5, Grid Emergency and if Technical Specification 3.8.1.1., Sources Operating entry is required?
Adverse condition TS 3 8 1 1 Entry Required A. Under Excitation Yes B. Under Excitation No c. Overheating No D. Overheating Yes Answer: D Answer Explanation rrhe examinee must understand that lowering grid voltage will cause VARS to rise. Excessive vars twill lead to machine overheating.
Adverse condition               TS 3 8 1 1 Entry Required A.         Under Excitation                             Yes B.         Under Excitation                             No
While lowering power will reduce vars it will not both comply with LD request for max MWE and stabilize the plant. A Incorrect Over heating the stator windings is correct. Plausible to candidate who does not recall basis for VAR limits and machine heating B Incorrect will not maintain max MWe and under excitation would be correct if voltage was rising resulting in lowering VARS on the main generator (i.e., move down on the Generator Capability Curve). T.S entry is requireddue to bus voltage <498 D correct reducing vars will reduce heat from the stator The given conditions (lowering grid voltage) will cause the generator automatic voltage regulator to attempt to raise grid voltage, causing the generator to pick up additional VARS (i.e., move up on the Generator Capability Curve). Without operator action, this would result in exceedingthe generator capability curve T.S Entry is required due to bus voltage <498 C This would be true if grid voltage was rising, resulting in lowering VARS on the main generator (i.e., move down on the Generator Capability Curve). I>entry is required LMK 2017 IL T NRG JANUARY Page: 289 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 82 Info Question Tvoe: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice?
: c.         Overheating                                   No D.         Overheating                                   Yes Answer:           D Answer Explanation rrhe examinee must understand that lowering grid voltage will cause VARS to rise. Excessive vars twill lead to machine overheating. While lowering power will reduce vars it will not both comply with
No Points: 1.00 rfime to Complete:
        ~he LD request for max MWE and stabilize the plant.
3 Difficulty:
A     Incorrect Over heating the stator windings is correct. Plausible to candidate who does not recall basis for VAR limits and machine heating B     Incorrect will not maintain max MWe and under excitation would be correct if voltage was rising resulting in lowering VARS on the main generator (i.e., move down on the Generator Capability Curve). T.S entry is requireddue to bus voltage <498 D     correct reducing vars will reduce heat from the stator The given conditions (lowering grid voltage) will cause the generator automatic voltage regulator to attempt to raise grid voltage, causing the generator to pick up additional VARS (i.e., move up on the Generator Capability Curve). Without operator action, this would result in exceedingthe generator capability curve T.S Entry is required due to bus voltage <498 C     This would be true if grid voltage was rising, resulting in lowering VARS on the main generator (i.e., move down on the Generator Capability Curve). I>entry is required LMK 2017 ILT NRG JANUARY                           Page: 289 of 374                               17 January 2017
3.00 Svstem ID: 1454368 User-Defined ID: Q#82 NEW Lesson Plan Objective:
 
LGSOPS0032.10 rropic: SRO RO: 3.6 SRO: 3.8 KA#: 70000 A2.10 LMK 2017 IL T NRC JANUARY Page: 290 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 82 Info Question Tvoe:                   Multiple Choice Status:                         Active Alwavs select on test?           No Authorized for practice?         No Points:                         1.00 rfime to Complete:               3 Difficulty:                     3.00 Svstem ID:                       1454368 User-Defined ID:                 Q#82 NEW Lesson Plan Objective:           LGSOPS0032.10 rropic:                         SRO RO:                             3.6 SRO:                             3.8 KA#:                             70000 A2.10 LMK 2017 ILT NRC JANUARY                       Page: 290 of 374     17 January 2017
LMK 2017 IL T NRC JANUARY Page: 291 of 374 APE: 700000 A2.10 3.6/3.8 Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:AA2.10 Generator overheating and the re uired actions 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 292 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 83 10:1455099 Points: 1.00 SRO Unit 1 was operating at 100% power when the following occurred
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Comments:
APE: 700000 A2.10 3.6/3.8 Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:AA2.10 Generator overheating and the re uired actions LMK 2017 ILT NRC JANUARY            Page: 291 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 292 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 83                                               10:1455099                                 Points: 1.00 SRO Unit 1 was operating at 100% power when the following occurred
* Reactor SCRAM on HI Drywall pressure
* Reactor SCRAM on HI Drywall pressure
* Drywall pressure is currently at 12 psig
* Drywall pressure is currently at 12 psig
* Drywall radiation monitors are reading 200 R/hr up slow
* Drywall radiation monitors are reading 200 R/hr up slow
* RPV Level is unknown T-116 step RF-3 directs assessing core damage Which of the following describes if core damage is occurring and the required action to take based on the conditions given above? Core Damage Required Action A. Is occurring Continue in T-102 and T-116 B. Is occurring EnterSAMPS  
* RPV Level is unknown T-116 step RF-3 directs assessing core damage Which of the following describes if core damage is occurring and the required action to take based on the conditions given above?
: c. Is NOT occurring Continue in T-102 and T-116 D. Is NOT occurring EnterSAMPS Answer: B \Answer Explanation LMK 2017 IL T NRC JANUARY Page: 293 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE : Drywell radiation levels The candidate must determine that a steam leak into primary containment exists causing the DW pressure ise and that there is indication of core damage from the given radiation levels in containment and as such SAMPS should be entered and TRIPS exited. TRIPS NOTE 19 8 "Core damage is occuring" refers to ongoing fuel degradation caused by loss of Adequate Core Cooling (TSG-3.8).
Core Damage                             Required Action A.                     Is occurring                     Continue in T-102 and T-116 B.                     Is occurring                             EnterSAMPS
Indications include: -Rising Pri Cnt radiation levels -Rising Pri Cnt H 2 levels -Rising MSL, SJAE, offgas OR Rx bldg radiation levels RPV Jevelfpressure history prior to loss of RPV level indication From TSG-3.8
: c.                 Is NOT occurring                     Continue in T-102 and T-116 D.                 Is NOT occurring                           EnterSAMPS Answer:           B
* Drywell radiation levels above the primary containment radiation rate corresponding to a loss of the fuel clad barrier per NEI 99-01 EAL s< heme. (-300 &#xb5;Ci/gm coolant activity dispersed in the drywell) From EP-AA-1008 Addendum 3 LMK 2017 ILT NRG JANUARY Page: 294 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Initiating Condition:
        \Answer Explanation LMK 2017 ILT NRC JANUARY                       Page: 293 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE : Drywell radiation levels The candidate must determine that a steam leak into primary containment exists causing the DW pressure ise and that there is indication of core damage from the given radiation levels in containment and as such SAMPS should be entered and TRIPS exited.
TRIPS NOTE 19 8         "Core damage is occuring" refers to ongoing fuel degradation caused by loss of Adequate Core Cooling (TSG-3.8). Indications include:
                      - Rising Pri Cnt radiation levels
                      - Rising Pri Cnt H 2 levels
                      - Rising MSL, SJAE, offgas OR Rx bldg radiation levels
                      ~ RPV Jevelfpressure history prior to loss of RPV level indication From TSG-3.8
* Drywell radiation levels above the primary containment radiation rate corresponding to a loss of the fuel clad barrier per NEI 99-01 EAL s< heme.
(-300 &#xb5;Ci/gm coolant activity dispersed in the drywell)
From EP-AA-1008 Addendum 3 LMK 2017 ILT NRG JANUARY                           Page: 294 of 374                                 17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO FC Initiating Condition:
Primary Containment Radiation Operating Mode Applicability:
Primary Containment Radiation Operating Mode Applicability:
1, 2, 3 Fission Product Barrier (FPB) Threshold:
1, 2, 3 Fission Product Barrier (FPB) Threshold:
LOSS Drywell radiation monitor reading> 1.90 E+02 Rfhr (190 Rfhr). Basis: FC The radiation monitor reading corresponds to an instantaneous release of all rea coolant mass into the primary containment, assuming that reactor coolant act* equals 300 &#xb5;Ci/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate ra e of 2% to 5% fuel dad damage. Since this condition indicates that a significant amou t of fuel dad damage has occurred, it represents a loss of the Fuel Clad Barrier. The radiation monitor reading in this threshold is higher than that specified for R S Barrier RC5 Loss Threshold since it indicates a loss of both the Fuel Clad Barner a d the RCS Barrier_ Note that a combination of the two monitor readings appropriat ty escalates the emergency classification level to a Site Area Emergency.
LOSS Drywell radiation monitor reading> 1.90 E+02 Rfhr (190 Rfhr).
Basis:
The radiation monitor reading corresponds to an instantaneous release of all rea coolant mass into the primary containment, assuming that reactor coolant act*
equals 300 &#xb5;Ci/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate ra e of 2% to 5% fuel dad damage. Since this condition indicates that a significant amou t of fuel dad damage has occurred, it represents a loss of the Fuel Clad Barrier.
The radiation monitor reading in this threshold is higher than that specified for R S Barrier RC5 Loss Threshold since it indicates a loss of both the Fuel Clad Barner a d the RCS Barrier_ Note that a combination of the two monitor readings appropriat ty escalates the emergency classification level to a Site Area Emergency.
There is no Fuel Clad Barner Potential loss threshold associated with Prima Containment Radiation.
There is no Fuel Clad Barner Potential loss threshold associated with Prima Containment Radiation.
Basis Reference(s):  
Basis Reference(s):
: 1. NEI 99--01Rev6, Table 9-F-2 A Incorrect Samps are required to be entered if core damage is occurring.
: 1.       NEI 99--01Rev6, Table 9-F-2 A     Incorrect Samps are required to be entered if core damage is occurring. TRIP note 19 reminds the SRO of indications of core damage. one of these indications is rising containment radiation. Plausible to the candidate that believes even with core damage under the current circumstances SAM PS are not required to be entered.
TRIP note 19 reminds the SRO of indications of core damage. one of these indications is rising containment radiation.
B     Correct: TRIP note 19 reminds the SRO of indications of core damage. one of these indications is rising containment radiation. SAMPS are entered if core damage exists per note 19 core damage does exist C     Incorrect: Core Damage is occurring. Plausable to the candidate that incorrectly determines that Radiation levels need to be higher than 200 R/hr to indicate core damage.
Plausible to the candidate that believes even with core damage under the current circumstances SAM PS are not required to be entered. B Correct: TRIP note 19 reminds the SRO of indications of core damage. one of these indications is rising containment radiation.
D     Incorrect: Core Damage is occurring. Plausable to the candidate that incorrectly determines that Radiation levels need to be higher than 200 R/hr to indicate core damage.
SAMPS are entered if core damage exists per note 19 core damage does exist C Incorrect:
LMK 2017 ILT NRC JANUARY                         Page: 295 of 374                             17 January 2017
Core Damage is occurring.
 
Plausable to the candidate that incorrectly determines that Radiation levels need to be higher than 200 R/hr to indicate core damage. D Incorrect:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 83 Info Question T e:           Multi le Choice Status:                 Active No No 1.00 3
Core Damage is occurring.
2.00 1455099 Q# 83 NEW LGSOPS1560.6 SRO DW ress and rad monitorin 3.3 3.6 295010 AA2.03 Comments:
Plausable to the candidate that incorrectly determines that Radiation levels need to be higher than 200 R/hr to indicate core damage. LMK 2017 IL T NRC JANUARY Page: 295 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 83 Info Question T e: Multi le Choice Status: Active No No 1.00 3 2.00 1455099 Q# 83 NEW LGSOPS1560.6 SRO DW ress and rad monitorin 3.3  
SRO 2
295010 AA2.03 3.3/3.6 High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE :
Dr well radiation levels lower 5
43.5 LMK 2017 ILT NRC JANUARY              Page: 296 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY            Page: 297 of 374        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY            Page: 298 of 374        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 84                                              10:1455896                                  Points: 1.00 SRO Unit 1 was at 100% power when a condenser vacuum leak developed.
Power has been reduced to 70% with condenser vacuum continuing to lower.
Off gas flow has risen from 20 SCFM to 75 SCFM Current condenser vacuum is 21.2 "Hg down slow.
Current offgas recombiner outlet temperature is 440 &deg;F Based on the given plant conditions WHICH ONE of the following identifies the action(s) required and follow up procedure to be directed per OT-116 "Loss of Condenser Vacuum"?
Action(s) reQuired                    Follow up procedure to direct A.        Manually TRIP Main Turbine WITHOUT            MA-AA-716-050-1000, Condenser Air performing a GP-4 shutdown              In-leakage Testing Guide And Limits B.        Manually TRIP Main Turbine WITHOUT                ON-103, Control Of Sustained performing a GP-4 shutdown              Combustion In The Off Gas System
: c.          Manually TRIP Main Turbine AFTER            MA-AA-716-050-1000, Condenser Air performing a GP-4 shutdown              In-leakage Testing Guide And Limits D.          Manually TRIP Main Turbine AFTER                ON-103, Control Of Sustained performing a GP-4 shutdown              Combustion In The Off Gas System Answer:          A
        !Answer Explanation LMK 2017 ILT NRG JANUARY                        Page: 299 of 374                            17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO From the stem of the question the student identifies that 21.2" Hg condenser vacuum. Based on
        ~his information the Main Turbine should have tripped on Low Vacuum (set point of 21.5 " Hg)
OT-116 Attachment 1 step 1:
: 1. IF condenser vacuum reaches 21.5" Hg Vac. as confirmed by Control Room instrumentation, rTHEN manually TRIP Main Turbine.
        ~dditionally,  the Bases of OT-116 states 6.1 If Condenser vacuum drops to the Main Turbine trip setpoint, the operator is directed to manually trip the turbine. This action is specified to ensure Main Turbine operation is suspended for Condenser vacuum conditions less than the automatic trip setpoint value. This will minimize
        ~he potential for Condenser/Turbine exhaust hood over pressurization and resultant rupture of the diaphragms on each Condenser shell. It should be noted that a Main Turbine trip at Reactor powers above the Turbine Trip Scram bypass setpoint (nominal 29.5% rated thermal power) will result in a Reactor scram. This protective action is expected and should not limit the operator's actions in ripping the Main Turbine.
This acknowledges that the priority is to trip the turbine and that a reactor scram should be expected if power is above 29.5%.
Additional information provided in the stem of Recombiner outlet temperature of 440 &deg;F was included to make ON-103 distractor more plausible. Value of 440 &deg;F was derived based on normal full power recombiner performance results in an outlet temperature of 480 &deg;F. For additional reference the setpoint for ARC-MCR-127 81, 1 Unit Recombiner Outlet Hi Temp does not occur until 840 &deg;F.
A    Correct as described above MA-AA-716-050-1000 is directed from OT-116 as a follow up action B    Wrong - Plausible if the student confuses the bases for breaking condenser vacuum on loss of sealing steam with the bases for tripping the Main Turbine on low condenser vacuum. From the stem off gas flow increases from 20 to 75 SCFM, symptoms for ON-103 Control of sustained combustion in the off gas system include a sudden change in off gas system flows, although this is one symptom and ON-103 is directed from OT-116 if indications of combustion exist in the off gas system the SRO must determine that the increase in flow is the result of a leak and not combustion supported by offgas recombiner outlet temperature in the normal range.
C    Wrong - Plausible if the student does not recognize that condenser vacuum is below the Turbine trip setpoint (21.5 " Hg) and applies normal step OT-116 step 3.4 actions to perform a GP-4 shutdown.
D    Wrong - Plausible if the student does not recognize that condenser vacuum is below the Turbine trip setpoint (21.5 " Hg) and applies normal step OT-116 step 3.4 actions to perform a GP-4 shutdown and if the student confuses the bases for breaking condenser vacuum on loss of sealing steam with the bases for tripping the Main Turbine on low condenser vacuum.From the stem off gas flow increases from 20 to 75 SCFM, symptoms for ON-103 Control of sustained combustion in the off gas system include a sudden change in off gas system flows, although this is one symptom and ON-103 is directed from OT-116 if indications of combustion exist in the off gas system the SRO must determine that the increase in flow is the result of a leak and not combustion supported by offgas recombiner outlet temperature in the normal range.
LMK 2017 ILT NRC JANUARY                          Page: 300 of 374                              17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 84 Info Question Type:                  Multiple Choice Status:                        Active
        ~lways select on test?          No Authorized for practice?        No Points:                          1.00 Time to Complete:                3 Difficulty:                      4.00 System ID:                      1455896 User-Defined ID:                0#84 NEW Lesson Plan Objective:          LGSOPS1540.5 (OT-116)
Topic:                          SRO- Loss of Condenser VAC RO:
SRO:                            4.4 KA#:                            295002 2.4.49 LMK 2017 ILT NRC JANUARY                      Page: 301 of 374      17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 295002 2.4.49 SRO 4.4 APE: 295002 Loss of Main Condenser Vacuum 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system com onents and controls.
Hi h 3 - Reactor Pressure Control 43.5 Rev;+' 3
                                                                                #~;:1tt 8 LMK 2017 ILT NRG JANUARY            Page: 302 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY            Page: 303 of 374        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 85                                              ID: 1455121                                    Points: 1.00 SRO An emergency has been declared due to a steam leak in the Unit 2 Reactor Enclosure. The following alarms are in:
SOUTH ST ACK HI RAD SOUTH STACK HI HI RAD Unit 2 reactor enclosure HVAC rad monitors read as follows
- Unit 2 RE Exhaust Rad                                RRSH-26-2R605A =1.5 mR/hr RRSH-26-2R605B = 1.4 mR/hr RRSH-26-2R605C = 1.3 mR/hr RRSH-26-2R605D = 1.5 mR/hr All available methods to isolate the leak have been attempted without success.
The following MCA radiological effluents indications exist:
-  WIDE RANGE MONITOR                                  RE26076-4 = 2.224E+02 &#xb5;Ci/Sec
-  WIDE RANGE MONITOR                                  RE26076-2 = 1.136E-06 &#xb5;Ci/cc
-  NORTH ST ACK VENT                                    RE26075A-1 = 2.992E-10 &#xb5;Ci/cc
-  NORTH ST ACK VENT                                    RE26075B-1 = 2.927E-10 &#xb5;Ci/cc
-  SOUTH ST ACK VENT                                    RE26285A-3 = 4.584E-04 &#xb5;Ci/cc
-  SOUTH ST ACK VENT                                    RE26285B-3 = 4.182E-04 &#xb5;Ci/cc Table R1 - Effluent Monitor Thresholds General Emergency          Site Area Emergency                  Alert            Unusual Event 1.92 E+08 &#xb5;Ci/sec        1.92 E+07 &#xb5;Ci/sec              1.92 E+06 &#xb5;Ci/sec      2.20 E+04 &#xb5;Ci/sec North Stack (WR Monitor: RIX-26-076-4) 2.71 E-01 uCi/cc            2.71 E-02 uCi/cc            2.71 E-03 uCi/cc        3.09 E-05 uCi/cc South (Unit 1: RY26-185A-3 / RY26-185B-3 or Unit 2 RY26-285A-3 / RY26-285B-3)
Stack WHICH ONE of the following identifies the CURRENT source of the offsite release and the required procedure action?
A.      North Stack Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination B.      North Stack Enter and execute T-104 Radiological Release C.      South Stack Enter and execute T-104 Radiological Release D.      South Stack Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination LMK 2017 ILT NRG JANUARY                        Page: 304 of 374                              17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer:        A Answer Explanation ANSWER            North Stack, Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination: Correct. With Reactor Enclosure Exhaust Rad greater than 1.35 mR/hr, a Secondary Containment Isolation will occur and the release will continue through Standby Gas which discharges through the North Stack.
With SOUTH STACK HI HI RAD in alarm, the ARC directs performance of ST-6-104-880-0. The Unit 2 South Stack Noble Gas channel is below the ALERT threshold of table R-1, therefore meeting T-104 entry is not required.
DISTRACTOR        North Stack, Enter and execute T-104 Radiological Release:
Incorrect, Release point correct but the ALERT limit has not been exceeded for entry into T-104.
Plausible to the examines who does not recall the T-104 entry (alert rad level)
DISTRACTOR        South Stack, Enter and execute T-104 Radiological Release:
Incorrect, the release rates are below any of the EAL thresholds and T-104 entry is not required since no ALERT thresholds have been met for release rates. Also, the South Stack release will stop following a Secondary Containment isolation signal.
Plausible to the examines who does not recognize that the unit 2 reactor hvac has isolated and does not recall the T-104 entry (alert rad level)
DISTRACTOR        South Stack, Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination: Incorrect, the South Stack release will stop following a Secondary Containment isolation signal.
Plausible to the examines who does not recognize that the unit 2 reactor hvac has isolated LMK 2017 ILT NRC JANUARY                  Page: 305 of 374                                17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 85 Info Question Type:                  Multiple Choice Status:                        Active Always select on test?          No Authorized for practice?        No Points:                          1.00
        !Time to Complete:              4 Difficulty:                    2.50 System ID:                      1455121 User-Defined ID:                Q# 85 BANK Lesson Plan Objective:          LLOT1790.4 (SRO) Assess Rad Effleunt EAL Table to determine release Topic:
point and required action RO:                              3.6 SRO:                            4.3 KA#:                            295017 AA2.04 LMK 2017 ILT NRG JANUARY                      Page: 306 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
295017 AA2.04 3.6/4.3 High Off-Site Release Rate Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: tSource of 43.5 T-104 13 EP-AA-1008 2
addendu 3 2012 Cert Exam 1006662 2010 NRC exam 2012 Cert Exam 1006662 2010 NRG exam 2012 Cert Exam 1006662 2010 NRG exam also 295038EA2.04 4.1 /4.5 LMK 2017 ILT NRC JANUARY            Page: 307 of 374                            17 January 2017


===3.6 295010===
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 308 of 374       17 January 2017
AA2.03 Comments:
 
LMK 2017 IL T NRC JANUARY Page: 296 of 374 SRO 2 295010 AA2.03 3.3/3.6 High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE : Dr well radiation levels lower 5 43.5 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 297 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 298 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 84 SRO 10:1455896 Points: 1.00 Unit 1 was at 100% power when a condenser vacuum leak developed.
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO 86                                               ID: 1659209',
Power has been reduced to 70% with condenser vacuum continuing to lower. Off gas flow has risen from 20 SCFM to 75 SCFM Current condenser vacuum is 21.2 "Hg down slow. Current offgas recombiner outlet temperature is 440 &deg;F Based on the given plant conditions WHICH ONE of the following identifies the action(s) required and follow up procedure to be directed per OT-116 "Loss of Condenser Vacuum"? A. B. c. D. Action(s) reQuired Manually TRIP Main Turbine WITHOUT performing a GP-4 shutdown Manually TRIP Main Turbine WITHOUT performing a GP-4 shutdown Manually TRIP Main Turbine AFTER performing a GP-4 shutdown Manually TRIP Main Turbine AFTER performing a GP-4 shutdown Answer: A !Answer Explanation LMK 2017 IL T NRG JANUARY Page: 299 of 374 Follow up procedure to direct MA-AA-716-050-1000, Condenser Air In-leakage Testing Guide And Limits ON-103, Control Of Sustained Combustion In The Off Gas System MA-AA-716-050-1000, Condenser Air In-leakage Testing Guide And Limits ON-103, Control Of Sustained Combustion In The Off Gas System 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO From the stem of the question the student identifies that 21.2" Hg condenser vacuum. Based on information the Main Turbine should have tripped on Low Vacuum (set point of 21.5 " Hg) OT-116 Attachment 1 step 1: 1. IF condenser vacuum reaches 21.5" Hg Vac. as confirmed by Control Room instrumentation, rTHEN manually TRIP Main Turbine.
the Bases of OT-116 states 6.1 If Condenser vacuum drops to the Main Turbine trip setpoint, the operator is directed to manually trip the turbine. This action is specified to ensure Main Turbine operation is suspended for Condenser vacuum conditions less than the automatic trip setpoint value. This will minimize potential for Condenser/Turbine exhaust hood over pressurization and resultant rupture of the diaphragms on each Condenser shell. It should be noted that a Main Turbine trip at Reactor powers above the Turbine Trip Scram bypass setpoint (nominal 29.5% rated thermal power) will result in a Reactor scram. This protective action is expected and should not limit the operator's actions in ripping the Main Turbine. This acknowledges that the priority is to trip the turbine and that a reactor scram should be expected if power is above 29.5%. Additional information provided in the stem of Recombiner outlet temperature of 440 &deg;F was included to make ON-103 distractor more plausible.
Value of 440 &deg;F was derived based on normal full power recombiner performance results in an outlet temperature of 480 &deg;F. For additional reference the setpoint for ARC-MCR-127 81, 1 Unit Recombiner Outlet Hi Temp does not occur until 840 &deg;F. A Correct as described above MA-AA-716-050-1000 is directed from OT-116 as a follow up action B Wrong -Plausible if the student confuses the bases for breaking condenser vacuum on loss of sealing steam with the bases for tripping the Main Turbine on low condenser vacuum. From the stem off gas flow increases from 20 to 75 SCFM, symptoms for ON-103 Control of sustained combustion in the off gas system include a sudden change in off gas system flows, although this is one symptom and ON-103 is directed from OT-116 if indications of combustion exist in the off gas system the SRO must determine that the increase in flow is the result of a leak and not combustion supported by off gas recombiner outlet temperature in the normal range. C Wrong -Plausible if the student does not recognize that condenser vacuum is below the Turbine trip setpoint (21.5 " Hg) and applies normal step OT-116 step 3.4 actions to perform a GP-4 shutdown.
D Wrong -Plausible if the student does not recognize that condenser vacuum is below the Turbine trip setpoint (21.5 " Hg) and applies normal step OT-116 step 3.4 actions to perform a GP-4 shutdown and if the student confuses the bases for breaking condenser vacuum on loss of sealing steam with the bases for tripping the Main Turbine on low condenser vacuum.From the stem off gas flow increases from 20 to 75 SCFM, symptoms for ON-103 Control of sustained combustion in the off gas system include a sudden change in off gas system flows, although this is one symptom and ON-103 is directed from OT-116 if indications of combustion exist in the off gas system the SRO must determine that the increase in flow is the result of a leak and not combustion supported by offgas recombiner outlet temperature in the normal range. LMK 2017 ILT NRC JANUARY Page: 300 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 84 Info Question Type: Multiple Choice Status: Active select on test? No Authorized for practice?
No Points: 1.00 Time to Complete:
3 Difficulty:
4.00 System ID: 1455896 User-Defined ID: 0#84 NEW Lesson Plan Objective:
LGSOPS1540.5 (OT-116) Topic: SRO-Loss of Condenser VAC RO: SRO: 4.4 KA#: 295002 2.4.49 LMK 2017 ILT NRC JANUARY Page: 301 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRG JANUARY Page: 302 of 374 2 295002 2.4.49 SRO 4.4 APE: 295002 Loss of Main Condenser Vacuum 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system com onents and controls.
Hi h 3 -Reactor Pressure Control 43.5 Rev;+' 3 8 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 303 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 85 ID: 1455121 Points: 1.00 SRO An emergency has been declared due to a steam leak in the Unit 2 Reactor Enclosure.
The following alarms are in: SOUTH ST ACK HI RAD SOUTH STACK HI HI RAD Unit 2 reactor enclosure HVAC rad monitors read as follows -Unit 2 RE Exhaust Rad RRSH-26-2R605A
= 1.5 mR/hr RRSH-26-2R605B
= 1.4 mR/hr RRSH-26-2R605C
= 1.3 mR/hr RRSH-26-2R605D
= 1.5 mR/hr All available methods to isolate the leak have been attempted without success. The following MCA radiological effluents indications exist: -WIDE RANGE MONITOR -WIDE RANGE MONITOR -NORTH ST ACK VENT -NORTH ST ACK VENT -SOUTH ST ACK VENT -SOUTH ST ACK VENT General Emergency North 1.92 E+08 &#xb5;Ci/sec Stack 2.71 E-01 uCi/cc RE26076-4
= 2.224E+02
&#xb5;Ci/Sec RE26076-2
= 1.136E-06
&#xb5;Ci/cc RE26075A-1
= 2.992E-10
&#xb5;Ci/cc RE26075B-1
= 2.927E-10
&#xb5;Ci/cc RE26285A-3
= 4.584E-04
&#xb5;Ci/cc RE26285B-3
= 4.182E-04
&#xb5;Ci/cc Table R1 -Effluent Monitor Thresholds Site Area Emergency Alert 1.92 E+07 &#xb5;Ci/sec 1.92 E+06 &#xb5;Ci/sec (WR Monitor: RIX-26-076-4) 2.71 E-02 uCi/cc 2.71 E-03 uCi/cc Unusual Event 2.20 E+04 &#xb5;Ci/sec 3.09 E-05 uCi/cc South Stack (Unit 1: RY26-185A-3
/ RY26-185B-3 or Unit 2 RY26-285A-3
/ RY26-285B-3)
WHICH ONE of the following identifies the CURRENT source of the offsite release and the required procedure action? A. North Stack Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination B. North Stack Enter and execute T-104 Radiological Release C. South Stack Enter and execute T-104 Radiological Release D. South Stack Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination LMK 2017 ILT NRG JANUARY Page: 304 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Answer: A Answer Explanation ANSWER North Stack, Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination:
Correct. With Reactor Enclosure Exhaust Rad greater than 1.35 mR/hr, a Secondary Containment Isolation will occur and the release will continue through Standby Gas which discharges through the North Stack. With SOUTH STACK HI HI RAD in alarm, the ARC directs performance of ST-6-104-880-0.
The Unit 2 South Stack Noble Gas channel is below the ALERT threshold of table R-1, therefore meeting T-104 entry is not required.
DISTRACTOR North Stack, Enter and execute T-104 Radiological Release: Incorrect, Release point correct but the ALERT limit has not been exceeded for entry into T-104. Plausible to the examines who does not recall the T-104 entry (alert rad level) DISTRACTOR South Stack, Enter and execute T-104 Radiological Release: Incorrect, the release rates are below any of the EAL thresholds and T-104 entry is not required since no ALERT thresholds have been met for release rates. Also, the South Stack release will stop following a Secondary Containment isolation signal. Plausible to the examines who does not recognize that the unit 2 reactor hvac has isolated and does not recall the T-104 entry (alert rad level) DISTRACTOR South Stack, Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination:
Incorrect, the South Stack release will stop following a Secondary Containment isolation signal. Plausible to the examines who does not recognize that the unit 2 reactor hvac has isolated LMK 2017 IL T NRC JANUARY Page: 305 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 85 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
No Points: 1.00 !Time to Complete:
4 Difficulty:
2.50 System ID: 1455121 User-Defined ID: Q# 85 BANK Lesson Plan Objective:
LLOT1790.4 Topic: (SRO) Assess Rad Effleunt EAL Table to determine release point and required action RO: 3.6 SRO: 4.3 KA#: 295017 AA2.04 LMK 2017 IL T NRG JANUARY Page: 306 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
LMK 2017 IL T NRC JANUARY Page: 307 of 374 295017 AA2.04 3.6/4.3 High Off-Site Release Rate Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: tSource of 43.5 T-104 EP-AA-1008 addendu 3 13 2 2012 Cert Exam 1006662 2010 NRC exam 2012 Cert Exam 1006662 2010 NRG exam 2012 Cert Exam 1006662 2010 NRG exam also 295038EA2.04 4.1 /4.5 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 308 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO 86 ID: 1659209',
* Points: 1.00 SRO Unit 1 is operating at 100% power when the following occurs; T=10:00
* Points: 1.00 SRO Unit 1 is operating at 100% power when the following occurs; T=10:00
* The following alarms come in o 109-A1, 1 SERVICE WATER HI RADIATION o 109-A2, 1 SERVICE WATER RAD MONITOR HI Hl/INOP DNSCL o 109-81, 1 REAC ENCL COOLING WATER HI RADIATION T= 10:15
* The following alarms come in o   109-A1, 1 SERVICE WATER HI RADIATION o   109-A2, 1 SERVICE WATER RAD MONITOR HI Hl/INOP DNSCL o   109-81, 1 REAC ENCL COOLING WATER HI RADIATION T= 10:15
* Chemistry reports the service water alarms are valid with the following readings o 6 times normal full power background (NFPB) T= 11:17
* Chemistry reports the service water alarms are valid with the following readings o   6 times normal full power background (NFPB)
* Chemistry reports the following service water rad monitor readings o 6.2 times normal full power background (NFPB)
T= 11:17
* Chemistry reports that an analysis of the effluent shows a dose of 3 mRem TEDE for 60 minutes of exposure Which of the following describes the component to isolate per S10.0.A, Service Water High Radiation, to reduce the radioactive input to service water, and the required EAL declaration if any? Component to isolate EAL declaration A. The in-service RWCU NON-regen UNUSUAL EVENT heat exchanger B. The in-service RWCU NON-regen NONE heat exchanger C. The in-service RECW heat exchanger UNUSUAL EVENT D. The in-service RECW heat exchanger NONE Answer: c !Answer Explanation LMK 2017 ILT NRG JANUARY Page: 309 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO The SRO candidate must determine that the SW rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3, even though service water does not directly discharge to he river A incorrect although RWCU is a cause for RECW hi rad, there are other possibilities (RWCU pp, recirc seal) as such the S10 procedure will direct removal of the in service RECW heat exchanger.
* Chemistry reports the following service water rad monitor readings o   6.2 times normal full power background (NFPB)
B incorrect although RWCU is a cause for RECW hi rad, there are other possibilities (RWCU pp, recirc seal) as such the S1 O procedure will direct removal of the in service RECW heat exchanger.
* Chemistry reports that an analysis of the effluent shows a dose of 3 mRem TEDE for 60 minutes of exposure Which of the following describes the component to isolate per S10.0.A, Service Water High Radiation, to reduce the radioactive input to service water, and the required EAL declaration if any?
No EAL is plausible if the candidate does not recall that the service water rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3 C correct candidate determine SW hi hi rad is a result of the RECW hi rad and correctly recalls 810.0.A step 4.7 isolate RECW heat exchanger.and correctly determines UE for effluent monitor >2 times alarm value and hat the service water rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3 D incorrect plausible to examinee who miss uses EAL and or does not recognize that the service water rad monitor is a discharqe permit specified monitor per OP-LG-1008 addendum 3 LMK 2017 ILT NRC JANUARY Page: 310 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 86 Info Question Type: Multiple Choice Status: Active lA.lways select on test? No lA.uthorized for practice?
Component to isolate                 EAL declaration A.       The in-service RWCU NON-regen                 UNUSUAL EVENT heat exchanger B.       The in-service RWCU NON-regen                 NONE heat exchanger C.       The in-service RECW heat exchanger             UNUSUAL EVENT D.       The in-service RECW heat exchanger             NONE Answer:         c
No Points: 1.00 lrime to Complete:
        !Answer Explanation LMK 2017 ILT NRG JANUARY                       Page: 309 of 374                           17 January 2017
2 Difficulty:
 
3.00 System ID: 1659209 User-Defined ID: Q# 86 NEW Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO The SRO candidate must determine that the SW rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3, even though service water does not directly discharge to he river A incorrect although RWCU is a cause for RECW hi rad, there are other possibilities (RWCU pp, recirc seal) as such the S10 procedure will direct removal of the in service RECW heat exchanger.
LOT1710.08 lropic: SW rad RO: 2.9 SRO: 3.0 KA#: 400000 A2.04 LMK 2017 ILT NRC JANUARY Page: 311 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
B incorrect although RWCU is a cause for RECW hi rad, there are other possibilities (RWCU pp, recirc seal) as such the S1 O procedure will direct removal of the in service RECW heat exchanger. No EAL is plausible if the candidate does not recall that the service water rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3 C correct candidate determine SW hi hi rad is a result of the RECW hi rad and correctly recalls 810.0.A step 4.7 isolate RECW heat exchanger.and correctly determines UE for effluent monitor
LMK 2017 ILT NRG JANUARY Page: 312 of 374 2 400000 A2.04 2.9/3.0 Component cooling water system (CCWS) Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
        >2 times alarm value and hat the service water rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3 D incorrect plausible to examinee who miss uses EAL and or does not recognize that the service water rad monitor is a discharqe permit specified monitor per OP-LG-1008 addendum 3 LMK 2017 ILT NRC JANUARY                       Page: 310 of 374                               17 January 2017
Radiation monitorin s stem alarm 43.4,5 S13.0.B 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 313 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 87 ID: 1455692 Points: 1.00 SRO Unit 2 is operating at 100% power when the following alarms are received simultaneously:
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 86 Info Question Type:                   Multiple Choice Status:                           Active lA.lways select on test?           No lA.uthorized for practice?         No Points:                           1.00 lrime to Complete:               2 Difficulty:                     3.00 System ID:                       1659209 User-Defined ID:                 Q# 86 NEW Lesson Plan Objective:           LOT1710.08 lropic:                           SW rad RO:                             2.9 SRO:                             3.0 KA#:                             400000 A2.04 LMK 2017 ILT NRC JANUARY                       Page: 311 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2 400000 A2.04 2.9/3.0 Component cooling water system (CCWS) Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Radiation monitorin s stem alarm 43.4,5 S13.0.B LMK 2017 ILT NRG JANUARY            Page: 312 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 313 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 87                                           ID: 1455692                               Points: 1.00 SRO Unit 2 is operating at 100% power when the following alarms are received simultaneously:
* ARC-MCR-207-B2, SRV ACOUSTIC MONITOR POWER LOSS OR CABLE FAULT
* ARC-MCR-207-B2, SRV ACOUSTIC MONITOR POWER LOSS OR CABLE FAULT
* ARC-MCR-208-AS, OPRM/APRM TROUBLE
* ARC-MCR-208-AS, OPRM/APRM TROUBLE
Line 954: Line 1,913:
* ARC-MCR-221-FS, 2A APRM UPS INVERTER TROUBLE
* ARC-MCR-221-FS, 2A APRM UPS INVERTER TROUBLE
* No other alarms were received on alarm panel 208 Given the above annunciators, which of the following is required?
* No other alarms were received on alarm panel 208 Given the above annunciators, which of the following is required?
A. Insert an "A" RPS half SCRAM per OT-117, RPS Failure B. Isolate RWCU and enter Tech Spec. 3.6.3 C. Enter OT-114, Inadvertent Opening Of A Relief Valve D. Enter ON-113, Loss Of RECW Answer: A !Answer Explanation LMK 2017 IL T NRC JANUARY Page: 314 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO !The listed annunciators in the stem are expected for a loss of 2A-Y185 2A APRM UPS Power. Upon a loss of 2A-Y185 the appropriate Event procedure to enter is E-2AY185.
A.     Insert an "A" RPS half SCRAM per OT-117, RPS Failure B.     Isolate RWCU and enter Tech Spec. 3.6.3 C.     Enter OT-114, Inadvertent Opening Of A Relief Valve D.     Enter ON-113, Loss Of RECW Answer:         A
Loss of power to 12AY185 will cause a loss of power to APRM voter units 1 and 3 causing a half scram !The Note prior to step 2.3 of E-2AY185 states:
          !Answer Explanation LMK 2017 ILT NRC JANUARY                     Page: 314 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO
      !The listed annunciators in the stem are expected for a loss of 2A-Y185 2A APRM UPS Power.
Upon a loss of 2A-Y185 the appropriate Event procedure to enter is E-2AY185. Loss of power to 12AY185 will cause a loss of power to APRM voter units 1 and 3 causing a half scram
      !The Note prior to step 2.3 of E-2AY185 states:
* ARC-MCR-208, A1, "NEUTRON MONITORING SYSTEM TRIP"
* ARC-MCR-208, A1, "NEUTRON MONITORING SYSTEM TRIP"
* ARC-MCR-208, 81, "AUTO SCRAM CHANNEL A 1"
* ARC-MCR-208, 81, "AUTO SCRAM CHANNEL A 1"
* ARC-MCR-208, 82, "AUTO SCRAM CHANNEL A2" Stem conditions state no other alarms were received on alarm panel 208, candidate must recognize an RPS failure occurred Initial Action in step 2.3 states: 2.3 IF "A" RPS fails to actuate a HALF SCRAM condition THEN ENTER OT-117 "RPS Failures" AND EXECUTE concurrently.
* ARC-MCR-208, 82, "AUTO SCRAM CHANNEL A2" Stem conditions state no other alarms were received on alarm panel 208, candidate must recognize an RPS failure occurred Initial Action in step 2.3 states:
Within OT-117, if there is a failure to half scam, step 3.2.1 directs inserting a manual half scram on the affected RPS side Candidate is required to demonstrate an understanding of the difference between a loss of 12AY185 2A APRM UPS power and 2AY160 RPS UPS power. Candidate must also recall actions required by E-2A Y185/E-2A Y160 and apply those actions to given conditions.
2.3 IF "A" RPS fails to actuate a HALF SCRAM condition THEN ENTER OT-117 "RPS Failures" AND EXECUTE concurrently.
An RPS half SCRAM occurs on loss of either power supply where as a RWCU isolation only occurs on a loss of 2A-Y160. A Correct for the above reasons 8 Wrong -Plausible if the candidate confuses the expected plant response on the loss of 2A-Y185 and believes that a RWCU NSSSS Isolation should have occurred and did not and directs the RWCU system be isolated to comply with Tech Spec 3.6.3 C Wrong -Plausible if the candidate recalls procedure E-2AY185 directs entering OT-114 (step 2.4) but does not recall that this step only applies if an SRV is confirmed to be open. D Wrong -Plausible if the candidate mis-diagnosis the event as a loss of 2AY-160 and recalls the first action step of E-2A Y160 is to enter ON-113 LMK 2017 ILT NRG JANUARY Page: 315 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 87 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
Within OT-117, if there is a failure to half scam, step 3.2.1 directs inserting a manual half scram on the affected RPS side Candidate is required to demonstrate an understanding of the difference between a loss of 12AY185 2A APRM UPS power and 2AY160 RPS UPS power.
No Points: 1.00 Time to Complete:
Candidate must also recall actions required by E-2AY185/E-2A Y160 and apply those actions to
3 Difficulty:
        ~he  given conditions. An RPS half SCRAM occurs on loss of either power supply where as a RWCU isolation only occurs on a loss of 2A-Y160.
3.00 System ID: 1455692 User-Defined ID: Q #87 NEW Lesson Plan Objective:
A     Correct for the above reasons 8     Wrong - Plausible if the candidate confuses the expected plant response on the loss of 2A-Y185 and believes that a RWCU NSSSS Isolation should have occurred and did not and directs the RWCU system be isolated to comply with Tech Spec 3.6.3 C     Wrong - Plausible if the candidate recalls procedure E-2AY185 directs entering OT-114 (step 2.4) but does not recall that this step only applies if an SRV is confirmed to be open.
LGSOPS007 4A.11 rropic: SRO -Impact of Power suppy dearaded in APRM/LPRM System RO: 2.7 SRO: 3.1 KA#: 1215005 A2.01 LMK 2017 IL T NRG JANUARY Page: 316 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
D     Wrong - Plausible if the candidate mis-diagnosis the event as a loss of 2AY-160 and recalls the first action step of E-2A Y160 is to enter ON-113 LMK 2017 ILT NRG JANUARY                         Page: 315 of 374                                 17 January 2017
LMK 2017 IL T NRG JANUARY Page: 317 of 374 RO 2 215005 A2.01 RO 2.7 SRO 3.1 215005 Average Power Range Monitor/Local Power Range Monitor A2. Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 318 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 319 of 374 17 January 2017 88 SRO EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO ID: 1455679 Unit 1 is in OPCON 4 with the following battery conditions:
 
Battery 1A10101 1A20101 1810101 1820101 1C0101 100101 Float Current 2.6 2.1 0.8 1.6 1.1 1.2 WHICH ONE of the following:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 87 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               3 Difficulty:                     3.00 System ID:                       1455692 User-Defined ID:                 Q #87 NEW Lesson Plan Objective:           LGSOPS007 4A.11 rropic:                         SRO - Impact of Power suppy dearaded in APRM/LPRM System RO:                             2.7 SRO:                             3.1 KA#:                           1215005 A2.01 LMK 2017 ILT NRG JANUARY                     Page: 316 of 374                         17 January 2017
Points: 1.00 (1) Identifies the battery, that if restored to Operable, would allow exiting Tech Spec LCO 3.8.2.2? And (2) Correctly completes the following about the design of the Class 1 E batteries:
 
Each Class 1 E battery bank is sized to have sufficient capacity without its charger to independently supply the large break LOOP/LOCA load profile tor (2) A. (1) 1A10101 (2) 1 hour B. (1) 1 C0101 (2) 4 hours c. (1) 1A10101 (2) 4 hours 0. (1) 1C0101 (2) 1 hour Answer: B !Answer Explanation LMK 2017 IL T NRG JANUARY Page: 320 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Provide  
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
RO 2
215005 A2.01 RO 2.7 SRO 3.1 215005 Average Power Range Monitor/Local Power Range Monitor A2. Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or LMK 2017 ILT NRG JANUARY              Page: 317 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 318 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 319 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 88                                                ID: 1455679                                 Points: 1.00 SRO Unit 1 is in OPCON 4 with the following battery conditions:
Battery           Float Current 1A10101                  2.6 1A20101                  2.1 1810101                  0.8 1820101                  1.6 1C0101                  1.1 100101                  1.2 WHICH ONE of the following:
(1) Identifies the battery, that if restored to Operable, would allow exiting Tech Spec LCO 3.8.2.2?
And (2) Correctly completes the following about the design of the Class 1E batteries:
Each Class 1E battery bank is sized to have sufficient capacity without its charger to independently supply the large break LOOP/LOCA load profile tor             (2)
A.       (1) 1A10101 (2) 1 hour B.       (1) 1C0101 (2) 4 hours
: c.       (1) 1A10101 (2) 4 hours
: 0.       (1) 1C0101 (2) 1 hour Answer:           B
        !Answer Explanation LMK 2017 ILT NRG JANUARY                           Page: 320 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Provide  


==References:==
==References:==
U1 Tech Spec 3.8.2.2 Candidate will assess the float current table and determine that there are 4 batteries INOP due to heir float currents. 1A1D101 and 1A2D101 are both INOP due to exceeding 2 amps, 1CD101 and 1DD101 are both INOP due to exceeding 1 amp.
rTech Spec 3.8.2.2 LCO requires a minimum of two divisions to be Operable. This is not the case due to Div 1, 3, and 4 all being INOP due to associated battery float current limits being exceeded. Action b.2 applies to all 4 batteries and is the source of part 1 of the answer. If action b2 is successful for 1CD101, Unit 1 will now have two Operable divisions (Division 2 and Division
: 3) and LCO 3.8.2.2 may be exited. However, if action b2 is successful for 1A1D101, three divisions will remain INOP due to Div 1 remaining INOP due to battery 1A2D101 remaining INOP.
From LGS UFSAR section 8.3.2.1.1.2 Class 1E Batteries Each Class 1E battery bank is sized to have sufficient capacity without its charger to independently supply the large break LOOP/LOCA load profile for A hours.
A    Wrong - Plausible to the candidate that mistakenly believes that restoring 1A1 D101 to Operable status would result in Division 1 being restored to Operable and the candidate that applies the 1 hour duration associated with establishing an alternate AC Source described in SE-1 "Loss of all AC Power (Station Blackout)" Bases coping time from the Station Blackout Analysis.
B    Correct for the reasons stated above C    Wrong - Plausible to the candidate that mistakenly believes that restoring 1A1D101 to Operable status would result in Division 1 being restored to Operable D    Wrong - Plausible to the candidate that mistakenly applies the 1 hour duration associated with establishing an alternate AC Source described in SE-1 "Loss of all AC Power (Station Blackout)" Bases coping time from the Station Blackout Analysis.
LMK 2017 ILT NRG JANUARY                        Page: 321 of 374                                17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 88 Info Question Tvoe:                    Multiole Choice Status:                          Active IAlwavs select on test?          No
        !Authorized for practice?        No Points:                          1.00 rnme to Complete:                5 Difficulty:                      2.00 Svstem ID:                      1455679 User-Defined ID:                Q# 88 NEW Lesson Plan Obiective:          LGSOPS0095.9A Topic:                            'SRO ONLY) - Tech Spec - Shutdown with 3 DC Divisions INOP RO:                              3.9 SRO:                            4.0 KA#:                            263000 G2.1.27 LMK 2017 ILT NRC JANUARY                        Page: 322 of 374                        17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
SRO 3
N/A 263000 G2.1.27 R0-3.9 SRO - 4.0 263000 D.C. Electrical Distribution 2.1.27 Knowledge of system ur ose and/or function 55.43 (2) Facility operating limitations in the technical s ecification and their bases Tech Spec 3.8.2.2 UFSAR 8.3.2.1.1.2 1248501 LMK 2017 ILT NRC JANUARY            Page: 323 of 374                          17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY            Page: 324 of 374        17 January 2017


U1 Tech Spec 3.8.2.2 Candidate will assess the float current table and determine that there are 4 batteries INOP due to heir float currents.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 89                                             10:1455217                               Points: 1.00 SRO Unit 1 is in OPCON 2 with reactor startup in progress.
1A1D101 and 1A2D101 are both INOP due to exceeding 2 amps, 1CD101 and 1DD101 are both INOP due to exceeding 1 amp. rTech Spec 3.8.2.2 LCO requires a minimum of two divisions to be Operable.
All IRM's are on Range 6 and reading as follows:
This is not the case due to Div 1, 3, and 4 all being INOP due to associated battery float current limits being exceeded.
                  "A"   22I125 "B"   24I125 "C"   31 I 125 "D"   24 I 125 "E"   55I125 "F" 54I125 "G"   33 I 125 "H"   31 I 125
Action b.2 applies to all 4 batteries and is the source of part 1 of the answer. If action b2 is successful for 1CD101, Unit 1 will now have two Operable divisions (Division 2 and Division 3) and LCO 3.8.2.2 may be exited. However, if action b2 is successful for 1A1D101, three divisions will remain INOP due to Div 1 remaining INOP due to battery 1A2D101 remaining INOP. From LGS UFSAR section 8.3.2.1.1.2 Class 1 E Batteries Each Class 1 E battery bank is sized to have sufficient capacity without its charger to independently supply the large break LOOP/LOCA load profile for A hours. A Wrong -Plausible to the candidate that mistakenly believes that restoring 1A1 D101 to Operable status would result in Division 1 being restored to Operable and the candidate that applies the 1 hour duration associated with establishing an alternate AC Source described in SE-1 "Loss of all AC Power (Station Blackout)" Bases coping time from the Station Blackout Analysis.
B Correct for the reasons stated above C Wrong -Plausible to the candidate that mistakenly believes that restoring 1A1D101 to Operable status would result in Division 1 being restored to Operable D Wrong -Plausible to the candidate that mistakenly applies the 1 hour duration associated with establishing an alternate AC Source described in SE-1 "Loss of all AC Power (Station Blackout)" Bases coping time from the Station Blackout Analysis.
LMK 2017 ILT NRG JANUARY Page: 321 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 88 Info Question Tvoe: Multiole Choice Status: Active IAlwavs select on test? No !Authorized for practice?
No Points: 1.00 rnme to Complete:
5 Difficulty:
2.00 Svstem ID: 1455679 User-Defined ID: Q# 88 NEW Lesson Plan Obiective:
LGSOPS0095.9A Topic: 'SRO ONLY) -Tech Spec -Shutdown with 3 DC Divisions INOP RO: 3.9 SRO: 4.0 KA#: 263000 G2.1.27 LMK 2017 IL T NRC JANUARY Page: 322 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
1248501 LMK 2017 ILT NRC JANUARY Page: 323 of 374 SRO 3 N/A 263000 G2.1.27 R0-3.9 SRO -4.0 263000 D.C. Electrical Distribution 2.1.27 Knowledge of system ur ose and/or function 55.43 (2) Facility operating limitations in the technical s ecification and their bases Tech Spec 3.8.2.2 UFSAR 8.3.2.1.1.2 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 324 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 89 10:1455217 Points: 1.00 SRO Unit 1 is in OPCON 2 with reactor startup in progress.
All IRM's are on Range 6 and reading as follows: "A" 22I125 "B" 24I125 "C" 31 I 125 "D" 24 I 125 "E" 55I125 "F" 54I125 "G" 33 I 125 "H" 31 I 125
* The RO ranges up IRMs B,C,G, and H to range 7 and
* The RO ranges up IRMs B,C,G, and H to range 7 and
* The A,D,E and F IRMs are inadvertently ranged up to range 8 and the RO continues to pull control rods. WHICH of the following identifies (1) all of the INOP IRMs AND (2) the required Tech Spec actions? A. (1) A AND D (2) Place an A side Half SCRAM in within 12 hours B. (1) A, D, E, AND F (2) Place a ROD BLOCK in within 12 hours C. (1) AAND D (2) Startup may continue D. (1) A, D, E, AND F (2) Place a ROD BLOCK in within 8 hour Answer: C !Answer Explanation LMK 2017 IL T NRC JANUARY Page: 325 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO A and D IRM are INOP for rod block instrumentation TS 3.3.6. G and H are only up ranged 1 time so no downscale rod block exist on them. Stem indicates the RO continues to pull rods after A and D IRM are< 3 /125 of scale rod block shound be generated Ranging from 6 to 7 will divide all readings by 3.16. A,D,E,F are ranged to 8 which will divide the reading by 3.16 again which will result in A and D I RM reading less than 3/125ths of scale which will result in a rod block. operators continue to pull control rods rod block must have not come in. Since only 6 IRMs are required for both RPS and Rod Block 1 IRM may be bypassed on each side. A and D IRM may be bypassed and startup may continue.
* The A,D,E and F IRMs are inadvertently ranged up to range 8 and the RO continues to pull control rods.
A incorrect plausible to candidate who belives an IRM downscale will generate a 1/2 scram B incorrect plausible to the examinee who correctly inedtifies that a ROD block should have been generated but does not recall the required number of IRM required per TS C Correct A and D IRM INOP for Rod Block function but 6 IRMs remain operable, starup may continue D incorrect plausible to he examinee who correctly inedtifies that a ROD block should have been generated but does not recall the required number of IRM required per TS and incorrectly belives B IRM is INOP LMK 2017 IL T NRG JANUARY Page: 326 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 89 Info Question T e: Status: RO: SRO: KA#: Comments:
WHICH of the following identifies (1) all of the INOP IRMs AND (2) the required Tech Spec actions?
LMK 2017 IL T NRC JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 3 3.00 1455217 Q# 89 NEW LGSOPS007 4.24A SRO Unit 1 is in OPCON 2 with reactor startup in progress.
A.       (1) A AND D (2) Place an A side Half SCRAM in within 12 hours B.     (1) A, D, E, AND F (2) Place a ROD BLOCK in within 12 hours C.     (1) AAND D (2) Startup may continue D.     (1) A, D, E, AND F (2) Place a ROD BLOCK in within 8 hour Answer:         C
All I RMs are on Ran e 6 and read in 3.4 4.7 215003 2.2.40 Page: 327 of 374 2 215003 2.2.40 3.4/4. 7 Ability to apply Technical S ecifications for a s stem. hi her 43.2 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 328 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 329 of 374 17 January 2017 90 SRO EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO ID; 1454750 Points: 1.00 A turbine trip with failure of bypass valves to open occurred on unit 1. After the event the plant is being prepared for startup. Engineering reports the SRV's lifted at the following pressures during the transient.
        !Answer Explanation LMK 2017 ILT NRC JANUARY                       Page: 325 of 374                         17 January 2017
SRV Lift Lifted SRV Lift Lifted f'.d SRV Lift Lifted set at r''l,,i set at '1?:j set at point point point H 1170 1175 D 1180 1180 A 1190 1190 '**''' J 1170 1160 rt 110' E 1180 1218 l(11;; B 1190 1188 ;;;> *;: L 1170 1159 > K 1180 1181 !*.*; c 1190 1190  
 
,.> N 1170 1133 M 1180 1183 '"':"' F 1190 1153 s 1180 1190 G u/ 1190 1230 Maintenance reports there are 3 spare SRV's with a lift set point of 1170 available on site Procurement reports that it will take 2 weeks to secure 1 additional SRV, AND 3 weeks to secure a second additional SRV. LMK 2017 IL T NRG JANUARY Page: 330 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO REACTOR COOLANT SYSTEM 314.4 2 SAFETY/RF!
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO A and D IRM are INOP for rod block instrumentation TS 3.3.6. G and H are only up ranged 1 time so no downscale rod block exist on them. Stem indicates the RO continues to pull rods after A and D IRM are< 3 /125 of scale rod block shound be generated Ranging from 6 to 7 will divide all readings by 3.16. A,D,E,F are ranged to 8 which will divide the reading by 3.16 again which will result in A and D IRM reading less than 3/125ths of scale which will result in a rod block. operators continue to pull control rods rod block must have not come in.
IEE VA! YF'i LIMITING CONQHHJN FOR OPERATION 3.4.2 The safety valve function of at least 12 of the following reactor coolant system safety/relief valves sha11 be OPERABLE with the specified code safety va1ve function lift settings:*#
Since only 6 IRMs are required for both RPS and Rod Block 1 IRM may be bypassed on each side. A and D IRM may be bypassed and startup may continue.
4 safety/relief valves a 1170 psig +/-31 5 safety/relief valves a 1180 psig +/-31 5 safety/relief valves a 1190 pstg +/-31 APPUCAB I lITY: OPERATIONAL CONDITIONS 1, 2, and 3. ACT10N: J. b. With the safety valve function of one or more of the above required safety/relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours. DELETED DELETED SlJRVE It! ANCE Rrntl!RFMENIS 4.4.2.1 DELETED 4.4.2.2 At least 112 of the safety relief valves shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations in accordance with the Surveillance Frequency Control Program, and they shall be rotated such that all 14 safety relief va1ves are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations in accordance with the Surveil la nee Frequency Contra l Program. A 11 safety valves will be recertification tested to meet a +/-1% tolerance prior to returning the valves to service. * # The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
A incorrect plausible to candidate who belives an IRM downscale will generate a 1/2 scram B incorrect plausible to the examinee who correctly inedtifies that a ROD block should have been generated but does not recall the required number of IRM required per TS C Correct A and D IRM INOP for Rod Block function but 6 IRMs remain operable, starup may continue D incorrect plausible to he examinee who correctly inedtifies that a ROD block should have been generated but does not recall the required number of IRM required per TS and incorrectly belives B IRM is INOP LMK 2017 ILT NRG JANUARY                         Page: 326 of 374                               17 January 2017
Up to 2 inoperable valves may be replaced with spare OPERABLE valves with lower setpolnts until the next refueling.
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 89 Info Question T e:          Multi le Choice Status:                Active No No 1.00 3
3.00 1455217 Q# 89 NEW LGSOPS007 4.24A SRO Unit 1 is in OPCON 2 with reactor startup in progress. All IRMs are on Ran e 6 and read in RO:                      3.4 SRO:                    4.7 KA#:                    215003 2.2.40 Comments:
2 215003 2.2.40 3.4/4. 7 Ability to apply Technical S ecifications for a s stem.
hi her 43.2 LMK 2017 ILT NRC JANUARY              Page: 327 of 374                              17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 328 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 329 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 90                                                  ID; 1454750                                 Points: 1.00 SRO A turbine trip with failure of bypass valves to open occurred on unit 1. After the event the plant is being prepared for startup.
Engineering reports the SRV's lifted at the following pressures during the transient.
f'.d SRV     Lift     Lifted           SRV   Lift     Lifted           SRV Lift Lifted set       at       r''l,,i       set     at       '1?:j       set   at point
                            ~~0~~\        point
                                                              ~~>~,
point H       1170     1175     ~j,! D         1180     1180     ~)'.:'. A   1190 1190 J       1170     1160     rt110' E     1180     1218     l(11;;
B   1190 1188 L       1170     1159     >     K     1180     1181     !*.*;
c   1190 1190
                            ~fu1>>                                ,.>
N       1170     1133             M     1180     1183       '"':"' F   1190 1153
                              '~4                              ''%~
                            ~i s     1180     1190             G   1190  1230 u/
Maintenance reports there are 3 spare SRV's with a lift set point of 1170 available on site Procurement reports that it will take 2 weeks to secure 1 additional SRV, AND 3 weeks to secure a second additional SRV.
LMK 2017 ILT NRG JANUARY                           Page: 330 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO REACTOR COOLANT SYSTEM 314.4 2     SAFETY/RF! IEE VA! YF'i LIMITING CONQHHJN FOR OPERATION 3.4.2 The safety valve function of at least 12 of the following reactor coolant system safety/relief valves sha11 be OPERABLE with the specified code safety va1ve function lift settings:*#
4     safety/relief valves   a 1170 psig +/-31 5     safety/relief valves   a 1180 psig +/-31 5     safety/relief valves   a 1190 pstg +/-31 APPUCAB I lITY:       OPERATIONAL CONDITIONS 1, 2, and 3.
ACT10N:
J. With the safety valve function of one or more of the above required safety/relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours.
: b. DELETED
            *~. DELETED SlJRVE It! ANCE Rrntl!RFMENIS 4.4.2.1         DELETED 4.4.2.2         At least 112 of the safety relief valves shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations in accordance with the Surveillance Frequency Control Program, and they shall be rotated such that all 14 safety relief va1ves are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations in accordance with the Surveil la nee Frequency Contra l Program. A11 safety valves will be recertification tested to meet a +/-1% tolerance prior to returning the valves to service.
* The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
      #      Up to 2 inoperable valves may be replaced with spare OPERABLE valves with lower setpolnts until the next refueling.
Of the choices below which one of the following will allow the mode switch to be placed in startup the earliest?
Of the choices below which one of the following will allow the mode switch to be placed in startup the earliest?
A. After SRV replacement with onsite spare SRV's, a risk assessment IS NOT required B. After SRV replacement with onsite spare SRV's, a risk assessment
A.       After SRV replacement with onsite spare SRV's, a risk assessment IS NOT required B.       After SRV replacement with onsite spare SRV's, a risk assessment _lS_required C.       After procurement of an additional SRV with a lift set point of 1180 D.       After procurement of 2 additional SRV's with a lift set point of 1190 LMK 2017 ILT NRC JANUARY                       Page: 331 of 374                             17 January 2017
_lS_required C. After procurement of an additional SRV with a lift set point of 1180 D. After procurement of 2 additional SRV's with a lift set point of 1190 LMK 2017 IL T NRC JANUARY Page: 331 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Answer: A Answer Explanation Per T.S 3.4.2 SRV set point acceptable tolerance is+/-3% examinee must determine that N,E,F,& Gare outside of 3% and inoperable Per T .S 3.4.2 only 12 of 14 are required Per the # note up to 2 SRV's may be replaced with lower set point SRV until the next refuel outage SRO must recall TS 3.0.4.b requirements tor when a risk assessment is required without reference A Correct replacing the N SRV and any 2 other SRV's will meet the requirements of T.S 3.4.2 using # note up to 2 SRV's may be replaced with lower set point SRV until the next refuel outage B Incorrect plausible to the examinee who does not recognize the # note and believe that using lower setpoint SRV could be used with a risk assessment C Incorrect plausible to the examinee who does not apply note# but does recognize that only 12 SRV's are needed D Incorrect plausible to the examinee who does apply the note # but does recognize that only 12 SRV's are required LMK 2017 IL T NRG JANUARY Page: 332 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 90 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
 
No Points: 1.00 Time to Complete:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer:           A Answer Explanation Per T.S 3.4.2 SRV set point acceptable tolerance is+/- 3% examinee must determine that N,E,F,& Gare outside of 3% and inoperable Per T .S 3.4.2 only 12 of 14 are required Per the # note up to 2 SRV's may be replaced with lower set point SRV until the next refuel outage SRO must recall TS 3.0.4.b requirements tor when a risk assessment is required without reference A     Correct replacing the N SRV and any 2 other SRV's will meet the requirements of T.S 3.4.2 using # note up to 2 SRV's may be replaced with lower set point SRV until the next refuel outage B     Incorrect plausible to the examinee who does not recognize the # note and believe that using lower setpoint SRV could be used with a risk assessment C     Incorrect plausible to the examinee who does not apply note# but does recognize that only 12 SRV's are needed D     Incorrect plausible to the examinee who does apply the note # but does recognize that only 12 SRV's are required LMK 2017 ILT NRG JANUARY                       Page: 332 of 374                             17 January 2017
4 Difficulty:
 
4.00 System ID: 1454750 User-Defined ID: Q# 90 NEW Lesson Plan Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 90 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 Time to Complete:               4 Difficulty:                     4.00 System ID:                       1454750 User-Defined ID:                 Q# 90 NEW Lesson Plan Objective:           LGSOPS1800.58 rropic:                         SRO SRV hi rector pressure RO:                             4.1 SRO:                             4.3 KA#:                             239002 A2.06 LMK 2017 ILT NRC JANUARY                     Page: 333 of 374       17 January 2017
LGSOPS1800.58 rropic: SRO SRV hi rector pressure RO: 4.1 SRO: 4.3 KA#: 239002 A2.06 LMK 2017 ILT NRC JANUARY Page: 333 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 IL T NRG JANUARY Page: 334 of 374 SRO 2 1 239002 A2.06 4.1 /4.3 Relief/Safety Valves Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Reactor high 186 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 335 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 91 ID: 1453648 Points: 1.00 SRO ONLY Unit 2 is operating at 100% power. Multiple cell failures on the 'A' ASD results in the following Recirc indications:  
SRO 2
'A' Becirc 'B' Becirc Loop Flow 28 Mlbm/hr 45 Mlbm/hr WHICH ONE of the following is the maximum allowable  
1 239002 A2.06 4.1 /4.3 Relief/Safety Valves Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES
'B' Recirc loop flow that will satisfy Tech Specs 3.4.1.3, and the Basis for the Tech Spec Becirc flow mismatch limitations? (Assume 'A' flow remains constant)
                                                            ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Reactor high 186 LMK 2017 ILT NRG JANUARY            Page: 334 of 374                          17 January 2017
HIGHEST 'B' Becirc flow value that will satisfy Tech Specs A. 33 Mlbm/hr B. 38 Mlbm/hr c. 33 Mlbm/hr D. 38 Mlbm/hr Answer: D !Answer Explanation LMK 2017 ILT NRG JANUARY Page: 336 of 374 Basis for Tech Spec Becirc flow mismatch limitations Prevents undue stress on the vessel nozzles and bottom head region Prevents undue stress on the vessel nozzles and bottom head region Ensure an adequate core flow coastdown from either recirc loop following a LOCA Ensure an adequate core flow coastdown from either recirc loop following a LOCA 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO is correct. Refer to Tech Spec 3.4.1.3 action a which states "Recirculation loop flow mismatch shall be maintained:
 
: a. Within 5% of each other with core flow greater than or equal to 0% of rated core flow, orb. within 10% of each other with core flow less than 70% of rated core low. From the daily ST, ST-6-107-590-2, Note 1 on page 85, (Rev. 134) states "If core flow< 70%, THEN VERIFY DIFFERENCE s 10 Mlbm/hr OR IF;?: 70%, THEN VERIFY DIFFERENCE s 5Mlbm/hr.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 335 of 374       17 January 2017
Therefore, when 'B' Recirc flow is reduced to 38 Mlbm/hr, total core flow will be less han 70% and the 10 Mlbm/hr flow mismatch requirement will be met.
 
incorrect.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 91                                               ID: 1453648                                       Points: 1.00 SRO ONLY Unit 2 is operating at 100% power.
This reduction is sufficient to meet the required 10% flow mismatch (actual value is 5% not the highest allowable value) The basis of the flow mismatch Tech Spec is wrong but plausible due to it actually being the basis for recirc loop temperature difference prior to a start of an idle recirc pump.
Multiple cell failures on the 'A' ASD results in the following Recirc indications:
incorrect.
                  'A' Becirc                       'B' Becirc Loop Flow         28 Mlbm/hr                       45 Mlbm/hr WHICH ONE of the following is the maximum allowable 'B' Recirc loop flow that will satisfy Tech Specs 3.4.1.3, and the Basis for the Tech Spec Becirc flow mismatch limitations? (Assume 'A' flow remains constant)
This reduction is sufficient to meet the required 10% flow mismatch (actual alue is 5% not the hi hest allowable value LMK 2017 IL T NRG JANUARY Page: 337 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 91 Info Puestion Type: Multiple Choice Status: Active select on test? No for practice?
HIGHEST 'B' Becirc flow value that will       Basis for Tech Spec Becirc flow mismatch satisfy Tech Specs                                 limitations A.                         33 Mlbm/hr Prevents undue stress on the vessel nozzles and bottom head region B.                                                          Prevents undue stress on the vessel 38 Mlbm/hr nozzles and bottom head region
No Points: 1.00 rfime to Complete:
: c.                        33 Mlbm/hr Ensure an adequate core flow coastdown from either recirc loop following a LOCA D.                        38 Mlbm/hr Ensure an adequate core flow coastdown from either recirc loop following a LOCA Answer:            D
4 Difficulty:
        !Answer Explanation LMK 2017 ILT NRG JANUARY                          Page: 336 of 374                                  17 January 2017
3.00 System ID: 1453648 User-Defined ID: Q#91BANK Lesson Plan Objective:
 
LGSOPS1800.58 rTopic: (SRO) Recall Tech Spec 3.4.1.3 SR requirements for Recirc Flow mismatch RO: 3.0 SRO: 3.2 KA#: 202002 A2.04 LMK 2017 ILT NRC JANUARY Page: 338 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Ill'"-"""""-'~  is correct. Refer to Tech Spec 3.4.1.3 action a which states "Recirculation loop flow mismatch shall be maintained: a. Within 5% of each other with core flow greater than or equal to 0% of rated core flow, orb. within 10% of each other with core flow less than 70% of rated core low. From the daily ST, ST-6-107-590-2, Note 1 on page 85, (Rev. 134) states "If core flow<
LMK 2017 IL T NRC JANUARY Page: 339 of 374 Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or modified after 2015 cert Also 295001 2.2.12 3.7/4.1 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO 92 ID: 1454490 SRO Unit 1 is operating at 100% power when a LOCA occurs Plant conditions are as follows;
70%, THEN VERIFY DIFFERENCE s 10 Mlbm/hr OR IF;?: 70%, THEN VERIFY DIFFERENCE s 5Mlbm/hr. Therefore, when 'B' Recirc flow is reduced to 38 Mlbm/hr, total core flow will be less han 70% and the 10 Mlbm/hr flow mismatch requirement will be met.
ia;_~...MIJ21IllD.lr..J:'..CBJilJllllS....UO.QU.e....&lm:S.S...J2D..lb.e.Jl:e&!se.l..DJl~lils...ania.J:2.QIIQJJn..bie&.!a..LlltgJQl]_iS incorrect. This reduction is sufficient to meet the required 10% flow mismatch (actual value is 5%
not the highest allowable value) The basis of the flow mismatch Tech Spec is wrong but plausible due to it actually being the basis for recirc loop temperature difference prior to a start of an idle recirc pump.
        ~..,,...,:i..is  incorrect. This reduction is sufficient to meet the required 10% flow mismatch (actual alue is 5% not the hi hest allowable value LMK 2017 ILT NRG JANUARY                                       Page: 337 of 374                                                   17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 91 Info Puestion Type:                   Multiple Choice Status:                         Active
        ~lways select on test?           No
        ~uthorized for practice?         No Points:                         1.00 rfime to Complete:               4 Difficulty:                     3.00 System ID:                       1453648 User-Defined ID:                 Q#91BANK Lesson Plan Objective:           LGSOPS1800.58 (SRO) Recall Tech Spec 3.4.1.3 SR requirements for Recirc rTopic:
Flow mismatch RO:                             3.0 SRO:                             3.2 KA#:                             202002 A2.04 LMK 2017 ILT NRC JANUARY                     Page: 338 of 374                           17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or modified after 2015 cert Also 295001 2.2.12 3.7/4.1 LMK 2017 ILT NRC JANUARY            Page: 339 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO 92                                                 ID: 1454490 SRO Unit 1 is operating at 100% power when a LOCA occurs Plant conditions are as follows;
* Drywell pressure is 14 psig
* Drywell pressure is 14 psig
* Drywell temperature is 248 degrees
* Drywell temperature is 248 degrees
Line 1,022: Line 2,056:
* Suppression pool level is 42 feet
* Suppression pool level is 42 feet
* D12 bus lockout occurs
* D12 bus lockout occurs
* D13 load center breaker trips and cannot be reclosed Which of the following describes (1) the T-225 action to be taken by the RS and (2) whether local manual operation, outside the MCA, of RHRSW Heat Exchanger lnle nd/or Outlet Valve(s) is required to complete the action? A. (1) Spray the Drywall (2) No B. (1) Spray the Suppression Pool (2) No C. (1) Spray the Drywell (2) Yes D. (1) Spray the Suppression P (2) Yes Answer: D Answer Explanation A Incorrect pla 1ble to examinee who does not diagnose >37.4 feet suppression pool level, and that d ell spray is prohibited per PC/P-10 of T-102. plausible to the examinee who does not call that Div 3 power supplies the A AHR htx outlet valve. B lncorre plausible to the examinee who does not recall that Div 3 power supplies the A RHR x outlet valve. C Inc rect plausible to examinee who does not diagnose >37.4 feet suppression pool level, a that drywell spray is prohibited per PC/P-10 of T-102. D orrect examinee recognizes sate to spray but realizes suppression pool level is too high to spray the Drywell and directs pool spray. With a loss of D13 load center the A RHRSW outlet valve to the RHR HTX has no power and must be opened manually.
* D13 load center breaker trips and cannot be reclosed Which of the following describes (1) the T-225 action to be taken by the RS and (2) whether local manual operation, outside the MCA, of RHRSW Heat Exchanger lnle nd/or Outlet Valve(s) is required to complete the action?
812.1.A which is directed from T-225 includes direction tor manual operation of RHRSW valves it required.
A.     (1) Spray the Drywall (2) No B.     (1) Spray the Suppression Pool (2) No C.     (1) Spray the Drywell (2) Yes D.     (1) Spray the Suppression P (2) Yes Answer:         D Answer Explanation A   Incorrect pla 1ble to examinee who does not diagnose >37.4 feet suppression pool level, and that d     ell spray is prohibited per PC/P-10 of T-102. plausible to the examinee who does not call that Div 3 power supplies the A AHR htx outlet valve.
LMK 2017 ILT NRG JANUARY Page: 340 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 92 Info Question T e: Status: lwa s select on test? uthorized for ractice? lete: SRO: KA#: Comments:
B   lncorre plausible to the examinee who does not recall that Div 3 power supplies the A RHR x outlet valve.
LMK 2017 IL T NRG JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 3 3.00 1454490 Q# 92 NEW LGSOPS1560.06 SRO FLA action cont. SPRAY 3.8 4.0 226001 2.4.35 Page: 341 of 374 2.4.35 3.8/4.0 RHR/LPCI:
C   Inc rect plausible to examinee who does not diagnose >37.4 feet suppression pool level, a that drywell spray is prohibited per PC/P-10 of T-102.
Containment Spray System Mode Knowledge of local auxiliary operator tasks during an emergency and the resultant o erational effects. Hi her ,ffev, ,#t'.';/;'
D     orrect examinee recognizes sate to spray but realizes suppression pool level is too high to spray the Drywell and directs pool spray. With a loss of D13 load center the A RHRSW outlet valve to the RHR HTX has no power and must be opened manually. 812.1.A which is directed from T-225 includes direction tor manual operation of RHRSW valves it required.
17 January 2017 EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 342 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 343 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 93 10:1454412 Points: 1.00 SRO Plant conditions are as follows: Unit 1 * * * *
LMK 2017 ILT NRG JANUARY                           Page: 340 of 374                             17 January 2017
* Reactor power is 100% RWCU resin spill has occurred in the Reactor Enclosure (RE) RE HVAC Exhaust radiation level is 11 mR/hr RWCU 'A' Pump Room radiation level is 120 mR/hr RWCU Regen Heat Exchanger Room radiation level is 122 mR/hr Access to Unit 1 Reactor Enclosure is required.
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 92 Info Question T e:                   Multi le Choice Status:                         Active lwa s select on test?         No uthorized for ractice?         No 1.00 lete:            3 3.00 1454490 Q# 92 NEW LGSOPS1560.06 SRO FLA action cont. SPRAY 3.8 SRO:                            4.0 KA#:                            226001 2.4.35 Comments:
2.4.35 3.8/4.0 RHR/LPCI: Containment Spray System Mode Knowledge of local auxiliary operator tasks during an emergency and the resultant o erational effects.
Hi her
                                                                                        ,ffev,
                                                                                        ,#t'.';/;'
LMK 2017 ILT NRG JANUARY                      Page: 341 of 374                      17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO LMK 2017 ILT NRC JANUARY           Page: 342 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 343 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 93                                             10:1454412                               Points: 1.00 SRO Plant conditions are as follows:
Unit 1
* Reactor power is 100%
* RWCU resin spill has occurred in the Reactor Enclosure (RE)
* RE HVAC Exhaust radiation level is 11 mR/hr
* RWCU 'A' Pump Room radiation level is 120 mR/hr
* RWCU Regen Heat Exchanger Room radiation level is 122 mR/hr Access to Unit 1 Reactor Enclosure is required.
Unit 2
Unit 2
* OPCON 5 Drywell purge in progress WHICH ONE of the following identifies (1) the T-103 action required for Unit 1? (2) the status of Unit 2 drywell purge? A. (1) Restore Reactor Enclosure HVAC per T-103 Secondary Containment Control, Step SCC/T-3 (2) Isolated B. (1) Restore Reactor Enclosure HVAC per T-103 Secondary Containment Control, Step SCC/T-3 (2) In service C. (1) Ensure Reactor HVAC isolation and SGTS initiation perT-103 Secondary Containment Control, Step SCC-4 (2) Isolated D. (1) Ensure Reactor HVAC isolation and SGTS initiation per T-103 Secondary Containment Control, Step SCC-4 (2) In service Answer: C \Answer Explanation LMK 2017 ILT NRG JANUARY Page: 344 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO A Incorrect The SRO candidate must demonstrate TRIP step knowledge by understanding SCCff-3 only applies if reactor enclosure rad is< 1.35 mR/H plausible if the examines does not recall requirement for rad to be below 1.35 or confuses this with T-104 RR-3 which allows start of REFUEL HVAC regardless for rad if entry is required B Incorrect At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge. The SRO candidate must demonstrate TRIP step knowledge by understanding SCCff-3 only applies if reactor enclosure rad is< 1.35 mR/H plausible if the examines does not recall requirement for rad to be below 1.35 or confuses this with T-104 RR-3 which allows start of REFUEL HVAC regardless for rad if entry is required C Correct At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge. Ensure Reactor HVAC isolation and SGTS initiation per T-103 Secondary Containment Control, Step SCC-4 D Incorrect At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge .. rr-104 RR-3 LMK 2017 ILT NRC JANUARY Page: 345 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 93 Info Question Tvoe: Multiple Choice Status: Active Always select on test? No Authorized for practice?
* OPCON 5 Drywell purge in progress WHICH ONE of the following identifies (1) the T-103 action required for Unit 1?
No Points: 1.00 iTime to Complete:
(2) the status of Unit 2 drywell purge?
3 Difficulty:
A.       (1) Restore Reactor Enclosure HVAC per T-103 Secondary Containment Control, Step SCC/T-3 (2) Isolated B.       (1) Restore Reactor Enclosure HVAC per T-103 Secondary Containment Control, Step SCC/T-3 (2) In service C.       (1) Ensure Reactor HVAC isolation and SGTS initiation perT-103 Secondary Containment Control, Step SCC-4 (2) Isolated D.       (1) Ensure Reactor HVAC isolation and SGTS initiation per T-103 Secondary Containment Control, Step SCC-4 (2) In service Answer:           C
3.00 System ID: 1454412 User-Defined ID: 0#93 NEW Lesson Plan Objective:
        \Answer Explanation LMK 2017 ILT NRG JANUARY                       Page: 344 of 374                           17 January 2017
LGSOPS1560.06 Topic: SRO Reactor encl hi rad RO: 3.4 SRO: 3.6 KA#: 290001 A2.03 LMK 2017 IL T NRG JANUARY Page: 346 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
 
LMK 2017 IL T NRG JANUARY Page: 347 of 374 Secondary Containment Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditionsor operations:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO A   Incorrect The SRO candidate must demonstrate TRIP step knowledge by understanding SCCff-3 only applies if reactor enclosure rad is< 1.35 mR/H plausible if the examines does not recall requirement for rad to be below 1.35 or confuses this with T-104 RR-3 which allows start of REFUEL HVAC regardless for rad if entry is required B   Incorrect At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge. The SRO candidate must demonstrate TRIP step knowledge by understanding SCCff-3 only applies if reactor enclosure rad is< 1.35 mR/H plausible if the examines does not recall requirement for rad to be below 1.35 or confuses this with T-104 RR-3 which allows start of REFUEL HVAC regardless for rad if entry is required C   Correct At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge. Ensure Reactor HVAC isolation and SGTS initiation per T-103 Secondary Containment Control, Step SCC-4 D   Incorrect At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge ..
High area radiation 43.4 & 43.5 ReV'< 2 3 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 94 ID: 1455644 Points: 1.00 SRO A large fire is burning at the 2C Main Power Transformer.
rr-104 RR-3 LMK 2017 ILT NRC JANUARY                         Page: 345 of 374                             17 January 2017
What are the SE-8 "Fire" requirements for controlling access of an offsite fire department?
 
The offsite fire department is to be escorted by ___ _ A. Radiation Protection B. any Fire Brigade Member qualified Equipment Operator C. a Fire Brigade Leader qualified Equipment Operator D. Plant Security Answer: D Explanation Limerick most Equipment operators are fire brigade qualified and any Equipment operator with more than 6 months in position is leader qualified as such there is an abundance of fire brigade I leader qualified people on site to support choices B and C A Wrong -Plausible to the examinee who recalls that RadPro responds to Fires within the Protected Area Boundary and translates this into they would be responsible to escort the responding fire department.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 93 Info Question Tvoe:                 Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?       No Points:                         1.00 iTime to Complete:             3 Difficulty:                     3.00 System ID:                       1454412 User-Defined ID:               0#93 NEW Lesson Plan Objective:         LGSOPS1560.06 Topic:                         SRO Reactor encl hi rad RO:                             3.4 SRO:                           3.6 KA#:                           290001 A2.03 LMK 2017 ILT NRG JANUARY                     Page: 346 of 374       17 January 2017
For fires within the Protected Area Boundary that do not contain a radiological concern (as is the case for this fire at the Main Power Transformer), the RP response (SE-8 section 4.12) parallels that of a EMT for the Fire Brigade Members. B Wrong -Plausible if the examinee assumes that the Offsite Fire Department should be escorted by an individual knowledgable in the equipment locations in the plant and fire fighting techniques.
 
C Wrong -Plausible if the examinee assumes that the Offsite Fire Department should be escorted by an individual in charge of fire fighting activities D Correct -SE-8 "Fire" Shift Supervisor Response section step 4.8.5.6 has the SRO request plant security to escort offsite Fire Departments to SROs and NOT General Employee Knowledge due to Licensed Operators having sole responsibility to direct actions from procedure SE-8 "Fire" LMK 2017 IL T NRG JANUARY Page: 348 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 94 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
No Points: 1.00 rnme to Complete:
Secondary Containment Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditionsor operations: High area radiation 43.4 & 43.5 ReV'< 2
3 Difficulty:
                                                                                  #:'h'~ 3 LMK 2017 ILT NRG JANUARY            Page: 347 of 374                          17 January 2017
2.00 System ID: 1455644 User-Defined ID: 0#94 NEW Lesson Plan Objective:
 
LLOT1563.04 (E/SE PROCEDURES) lropic: SRO -requirements for controlling vital/ controlled access RO: SRO: 3.2 KA#: 2.1.13 LMK 2017 IL T NRG JANUARY Page: 349 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 94                                                 ID: 1455644                                   Points: 1.00 SRO A large fire is burning at the 2C Main Power Transformer. What are the SE-8 "Fire" requirements for controlling access of an offsite fire department?
LMK 2017 ILT NRG JANUARY Page: 350 of 374 2.1.13 SRO Importance SRO 3.2 Knowledge of facility requirements for controlling vital/controlled access. Ff ev s #: 4 Applicable to SROs and NOT General Employee Knowledge due to Licensed Operators having sole responsibility to direct actions from procedure SE-8 "Fire" 17 January 2017 95 SRO EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO ID: 1455601 Points: 1.00 Given the following:
The offsite fire department is to be escorted by _ _ __
A.       Radiation Protection B.       any Fire Brigade Member qualified Equipment Operator C.       a Fire Brigade Leader qualified Equipment Operator D.       Plant Security Answer:           D
        ~nswer Explanation
        ~t  Limerick most Equipment operators are fire brigade qualified and any Equipment operator with more than 6 months in position is leader qualified as such there is an abundance of fire brigade I leader qualified people on site to support choices B and C A     Wrong - Plausible to the examinee who recalls that RadPro responds to Fires within the Protected Area Boundary and translates this into they would be responsible to escort the responding fire department. For fires within the Protected Area Boundary that do not contain a radiological concern (as is the case for this fire at the Main Power Transformer),
the RP response (SE-8 section 4.12) parallels that of a EMT for the Fire Brigade Members.
B     Wrong - Plausible if the examinee assumes that the Offsite Fire Department should be escorted by an individual knowledgable in the equipment locations in the plant and fire fighting techniques.
C     Wrong - Plausible if the examinee assumes that the Offsite Fire Department should be escorted by an individual in charge of fire fighting activities D     Correct - SE-8 "Fire" Shift Supervisor Response section step 4.8.5.6 has the SRO request plant security to escort offsite Fire Departments
        ~pplicable to SROs and NOT General Employee Knowledge due to Licensed Operators having sole responsibility to direct actions from procedure SE-8 "Fire" LMK 2017 ILT NRG JANUARY                             Page: 348 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 94 Info Question Type:                   Multiple Choice Status:                         Active Always select on test?           No Authorized for practice?         No Points:                         1.00 rnme to Complete:               3 Difficulty:                     2.00 System ID:                       1455644 User-Defined ID:                 0#94 NEW Lesson Plan Objective:           LLOT1563.04 (E/SE PROCEDURES) lropic:                         SRO - requirements for controlling vital/ controlled access RO:
SRO:                             3.2 KA#:                             2.1.13 LMK 2017 ILT NRG JANUARY                       Page: 349 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
2.1.13 SRO Importance SRO 3.2 Knowledge of facility requirements for controlling vital/controlled access.
Ffev  s
                                                                                  #:     4 Applicable to SROs and NOT General Employee Knowledge due to Licensed Operators having sole responsibility to direct actions from procedure SE-8 "Fire" LMK 2017 ILT NRG JANUARY            Page: 350 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 95                                              ID: 1455601                                   Points: 1.00 SRO Given the following:
* Unit 2 is operating at 85% power
* Unit 2 is operating at 85% power
* The 28 Reactor Feed Pump (RFP) has been experiencing fluctuating speed changes
* The 28 Reactor Feed Pump (RFP) has been experiencing fluctuating speed changes
* To support trouble shooting, l&C is requesting to connect a strip chart recorder to monitor the signal to the Woodward Governor for the 28 RFP
* To support trouble shooting, l&C is requesting to connect a strip chart recorder to monitor the signal to the Woodward Governor for the 28 RFP
* The strip chart recorder will be attached to existing test points in the system Refer to Attachment 4 "Risk and Rigor Determination Matrix" of MA-AA-716-004 "Conduct of Troubleshooting" to classify this activity This is a __ (1 } __ Risk troubleshooting activity, and requires Operations Department approval by the_(2)_.
* The strip chart recorder will be attached to existing test points in the system Refer to Attachment 4 "Risk and Rigor Determination Matrix" of MA-AA-716-004 "Conduct of Troubleshooting" to classify this activity This is a __ (1 }__ Risk troubleshooting activity, and requires Operations Department approval by the_(2)_.
A. (1) High (2) Shift Manager 8. (1) High (2) Work Control Supervisor C. (1) Medium (2) Shift Manager D. (1) Medium (2) Work Control Supervisor Answer: 8 Answer Explanation A Wrong -plausible if the student confuse the risk category of With test points (C) with that of without test points (A) Shift manager required approval 8 Correct -This is High Risk Troubleshooting per MA-AA-716-004 Attachment 4 due to DFLCS and the Woodward Governor being control systems that directly involve power generation support (1.2) and being Logic systems that can directly or indirectly cause a reactor scram (1.3). The risk category is C due to hooking up the recorder using existing test points. This requires the WCS approval C Wrong -plausible if the student confuse the risk level classification as Medium due to mis applying 2.3 as Level control changes in the reactor and confuses the risk category of With test points (C) with that of without test points (A) (shift manager required approval D Wrong -plausible if the student confuse the risk level classification as Medium due to mis applying 2.3 as Level control changes in the reactor. LMK 2017 IL T NRC JANUARY Page: 351 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 95 Info Question T e: Status: uthorized for ractice? lete: Comments:
A.     (1) High (2) Shift Manager
LMK 2017 IL T NRC JANUARY ILT 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 3 2.50 1455601 Q #95 MODIFIED LGSOPS2005A  
: 8.     (1) High (2) Work Control Supervisor C.     (1) Medium (2) Shift Manager D.     (1) Medium (2) Work Control Supervisor Answer:           8 Answer Explanation A   Wrong - plausible if the student confuse the risk category of With test points (C) with that of without test points (A) Shift manager required approval 8   Correct - This is High Risk Troubleshooting per MA-AA-716-004 Attachment 4 due to DFLCS and the Woodward Governor being control systems that directly involve power generation support (1.2) and being Logic systems that can directly or indirectly cause a reactor scram (1.3). The risk category is C due to hooking up the recorder using existing test points. This requires the WCS approval C   Wrong - plausible if the student confuse the risk level classification as Medium due to mis applying 2.3 as Level control changes in the reactor and confuses the risk category of With test points (C) with that of without test points (A) (shift manager required approval D   Wrong - plausible if the student confuse the risk level classification as Medium due to mis applying 2.3 as Level control changes in the reactor.
LMK 2017 ILT NRC JANUARY                         Page: 351 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 95 Info Question T e:                    Multi le Choice Status:                        Active No uthorized for ractice?        No 1.00 lete:            3 2.50 1455601 Q #95 MODIFIED LGSOPS2005A 6.8 ADMIN PROCED SRO 3.8 2.2.20 Comments:
Modified PBAPS 2008 ILT NRC SRO #21 Modified PBAPS 2008 ILT NRC SRO #21 N/A LMK 2017 ILT NRC JANUARY                      Page: 352 of 37 4                  17 January 2017


===6.8 ADMIN===
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY             Page: 353 of 374       17 January 2017
PROCED SRO 3.8 2.2.20 Page: 352 of 37 4 Modified PBAPS 2008 IL T NRC SRO #21 Modified PBAPS 2008 IL T NRC SRO #21 N/A 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 353 of 374 17 January 2017 96 SRO EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 10: 1685046 Given the following:
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 96                                              10: 1685046                                     Points: 1.00 SRO Given the following:
* A loss of coolant accident has occurred
* A loss of coolant accident has occurred
* T-101, RPV Control, and T-102, Primary Containment Control, have been entered
* T-101, RPV Control, and T-102, Primary Containment Control, have been entered
* SE-10, LOCA, has been entered
* SE-10, LOCA, has been entered
* 3 hours have elapsed since the LOCA signal
* 3 hours have elapsed since the LOCA signal
* Plant operators have arrived at the following SE-10 step: 4.25 WHEN greater than three hours have elapsed following the LOCA signal, Points: 1.00 Il:lEN. INJECT SLC per S48.1.B, Standby Liquid Control System Manual Initiation. (CM-4) WHICH ONE of the following describes the basis for performance of this step? A. Provides an additional source of injection to the reactor to help recover RPV water level B. Ensures sufficient negative reactivity is present to ensure reactor remains shutdown due to changes in core geometry C. Ensures Hot Shutdown Boron Weight is injected before suppression pool temperature exceeds the Heat Capacity Temperature Limit D. Minimizes radioactive release by adding sodium pentaborate to the suppression pool to satisfy the methodology for Alternate Source Term Answer: D !Answer Explanation LMK 2017 IL T NRG JANUARY Page: 354 of 374 17 January 2017 EXAMINATION ANSWER KEY K&A Rating: K&A Statement:
* Plant operators have arrived at the following SE-10 step:
Justification:
4.25 WHEN greater than three hours have elapsed following the LOCA signal, Il:lEN. INJECT SLC per S48.1.B, Standby Liquid Control System Manual Initiation. (CM-4)
IL T 15-01 January 2017 NRC test SRO G2.3.14 (3.8) Knowledge of radiation or contamination hazards that may arise during normal, abnormal or emergency conditions or activities A. Incorrect but plausible:
WHICH ONE of the following describes the basis for performance of this step?
Establishing SLC injection in 4.25 is not as a means for level control but as a means to control radiological dose following a loss of coolant accident involving core damage. Since SLC is identified as an Alternate Injection System it would likely be started to augment RPV injection in an earlier step of the Level branch, before RPV water level reaches the top of the active fuel. This is a plausible distracter for those candidates that do not recognize the radiological impact from SLC injection once T AF has been reached and also plausible for level control as injection requirements 3 hours after shutdown are much lower and closer to the capacity of the SLC pumps B. Incorrect but plausible:
A.       Provides an additional source of injection to the reactor to help recover RPV water level B.       Ensures sufficient negative reactivity is present to ensure reactor remains shutdown due to changes in core geometry C.       Ensures Hot Shutdown Boron Weight is injected before suppression pool temperature exceeds the Heat Capacity Temperature Limit D.       Minimizes radioactive release by adding sodium pentaborate to the suppression pool to satisfy the methodology for Alternate Source Term Answer:             D
Boration of the reactor coolant is performed to reduce power levels in the core by neutron moderation.
        !Answer Explanation LMK 2017 ILT NRG JANUARY                         Page: 354 of 374                               17 January 2017
This is plausible distracter for those candidates who believe that dose mitigation is achieved with boration of the coolant in the vessel versus the Suppression Pool volume C. Incorrect but plausible:
 
to the examinee who mistakes the basis for this injection with the basis for injecting SLC prior to Suppression Pool Temperature exceeded 110 degrees F from T-101 Step RC/Q-16 D. Correct: Design basis analyses credit SLC injection for limiting the radiological dose following loss of coolant accidents involving core damage. Radiation induced reactions are predicted to convert large fractions of dissolved ionic iodine into elemental iodine and organic iodides which can escape into the containment atmosphere.
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO K&A Rating:                            G2.3.14 (3.8)
The rate of these reactions is strongly dependent on suppression pool pH. If the bulk Suppression Pool pH is maintained greater than 7, very little of the dissolved iodine will be converted to volatile forms and most of the iodine fission products will be retained in the suppression pool, thereby preventing iodine re-evolution.
K&A Statement:                        Knowledge of radiation or contamination hazards that may arise during normal, abnormal or emergency conditions or activities Justification:
Over time, the pH in the Suppression Pool will tend to lower due to the addition of acidic chemicals.
A.       Incorrect but plausible: Establishing SLC injection in 4.25 is not as a means for level control but as a means to control radiological dose following a loss of coolant accident involving core damage. Since SLC is identified as an Alternate Injection System it would likely be started to augment RPV injection in an earlier step of the Level branch, before RPV water level reaches the top of the active fuel. This is a plausible distracter for those candidates that do not recognize the radiological impact from SLC injection once T AF has been reached and also plausible for level control as injection requirements 3 hours after shutdown are much lower and closer to the capacity of the SLC pumps B.       Incorrect but plausible: Boration of the reactor coolant is performed to reduce power levels in the core by neutron moderation. This is plausible distracter for those candidates who believe that dose mitigation is achieved with boration of the coolant in the vessel versus the Suppression Pool volume C.       Incorrect but plausible: to the examinee who mistakes the basis for this injection with the basis for injecting SLC prior to Suppression Pool Temperature exceeded 110 degrees F from T-101 Step RC/Q-16 D.         Correct: Design basis analyses credit SLC injection for limiting the radiological dose following loss of coolant accidents involving core damage. Radiation induced reactions are predicted to convert large fractions of dissolved ionic iodine into elemental iodine and organic iodides which can escape into the containment atmosphere. The rate of these reactions is strongly dependent on suppression pool pH. If the bulk Suppression Pool pH is maintained greater than 7, very little of the dissolved iodine will be converted to volatile forms and most of the iodine fission products will be retained in the suppression pool, thereby preventing iodine re-evolution. Over time, the pH in the Suppression Pool will tend to lower due to the addition of acidic chemicals. The sodium pentaborate solution used in the SLC system is derived from a strong base and therefore raises suppression pool pH
The sodium pentaborate solution used in the SLC system is derived from a strong base and therefore raises suppression pool pH  


==References:==
==References:==
SE-10, Rev. 56                            Applicant Ref: None UFSAR Section 9.3.5, Rev. 15 S48.1.B, Rev. 13 LLOT0048, Rev. 0 TS Bases 3/4.1.5, amendment 186 Learning Objective:          LLOT0048: IL 1, IL 10 LLOT1563: 03 Question source:            Bank NMP 8/2009 Question History:            Not used on 2008 or 2010 LGS initial exams Cognitive level:            Memory/Fundamental knowledge:                    x Comprehensive/Analysis:
LMK 2017 ILT NRG JANUARY                          Page: 355 of 374                                17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 10CFR Part 55:          43{b)(4), 43(b)(1)
Comments: This question is SRO only as it requires knowledge of administrative procedures that specify implementation and coordination of plant emergency procedures regarding radiation hazards that may arise during abnormal plant conditions and knowledge of conditions and limitations in the facility license.
LMK 2017 ILT NRC JANUARY                      Page: 356 of 374                            17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 96 Info Question T e:          Multi le Choice Status:                Active No No 1.00 2
3.00 1685046 Q# 96 BANK POOL PH 3.8 2.3.14 Comments:
Knowledge of radiation or contamination hazards that may arise during normal, abnormal or emergency conditions or activities lower n/a LMK 2017 ILT NRC JANUARY              Page: 357 of 374                      17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY            Page: 358 of 374        17 January 2017
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 97                                                      ID: 1685033                                Points: 1.00 SRO LGS has declared a GENERAL EMERGENCY.
Command & Control has been transferred to the TSC.
Consider the following ERO personnel:
: 1. Shift Manager I Shift Emergency Director
: 2. Radiation Protection Manager
: 3. Station Emergency Director WHICH ONE of the following identifies (from the above list) ALL of those who can APPROVE an "Authorization for Emergency Exposure" form for a worker to receive exposure greater than 25 Rem TEDE?
A.            1, 3 B.            2,3
: c.            2 D.            3 Answer:                    D nswer Explanation Refer to EP-AA-113-F-02 (Authorization for Emergency Exposure). The Shift Manager I Shift Emergency Director may approve ,ori.Qr to transferring Command and Control to the Station Emergency Director. After the transfer of command and control, only the Station Emergency Director can approve the emergency exposure.
        &#xb5;.<.-...LW-r..u..>.~._._._ Plausible to the examinee who recognizes that the Station Emergency Director has overall command and control of the ERO, but who believes that the expertise that only the RPM assesses is necessa to ultimate! a rove the ex osure re uest.
LMK 2017 ILT NRC JANUARY                                Page: 359 of 374                            17 January 2017


SE-10, Rev. 56 UFSAR Section 9.3.5, Rev. 15 S48.1.B, Rev. 13 LLOT0048, Rev. 0 TS Bases 3/4.1.5, amendment 186 Learning Objective:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 97 Info Question T e:                   Multi le Choice Status:                         Active lwa s select on test?         No uthorized for ractice?         No 1.00 lete:            3 2.00 1685033 Q# 97 BANK 2015 NRG EAL OBJECTIVES SRO Recall who can A RO:                              2.4 SRO:                            4.4 KA#:                            2.4.38 Comments:
LLOT0048:
2.4/4.4 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if re uired.
IL 1, IL 10 LLOT1563:
bank 1150031 2015 NRG LMK 2017 ILT NRC JANUARY                      Page: 360 of 374                            17 January 2017
03 Question source: Question History: Cognitive level: LMK 2017 IL T NRG JANUARY Bank NMP 8/2009 Not used on 2008 or 2010 LGS initial exams Memory/Fundamental knowledge:
 
Comprehensive/
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 361 of 374       17 January 2017
Analysis:
 
Page: 355 of 374 Applicant Ref: None x 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 1 OCFR Part 55: 43{b)(4), 43(b)(1) Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 98                                              10:1454851                             Points: 1.00 SRO Given the following:
This question is SRO only as it requires knowledge of administrative procedures that specify implementation and coordination of plant emergency procedures regarding radiation hazards that may arise during abnormal plant conditions and knowledge of conditions and limitations in the facility license. LMK 2017 ILT NRC JANUARY Page: 356 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 96 Info Question T e: Status: Comments:
Unit 2 is operating at 100% power
LMK 2017 IL T NRC JANUARY IL T 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 2 3.00 1685046 Q# 96 BANK POOL PH 3.8 2.3.14 Page: 357 of 374 Knowledge of radiation or contamination hazards that may arise during normal, abnormal or emergency conditions or activities lower n/a 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 358 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 97 ID: 1685033 Points: 1.00 SRO LGS has declared a GENERAL EMERGENCY.
* l&C is performing ST-2-072-104-1 "DIV IV NSSSS LSF/SAA"
Command & Control has been transferred to the TSC. Consider the following ERO personnel:
: 1. Shift Manager I Shift Emergency Director 2. Radiation Protection Manager 3. Station Emergency Director WHICH ONE of the following identifies (from the above list) ALL of those who can APPROVE an "Authorization for Emergency Exposure" form for a worker to receive exposure greater than 25 Rem TEDE? A. 1, 3 B. 2,3 c. 2 D. 3 Answer: D nswer Explanation Refer to EP-AA-113-F-02 (Authorization for Emergency Exposure).
The Shift Manager I Shift Emergency Director may approve ,ori.Qr to transferring Command and Control to the Station Emergency Director.
After the transfer of command and control, only the Station Emergency Director can approve the emergency exposure.
Plausible to the examinee who recognizes that the Station Emergency Director has overall command and control of the ERO, but who believes that the expertise that only the RPM assesses is necessa to ultimate!
a rove the ex osure re uest. LMK 2017 IL T NRC JANUARY Page: 359 of 374 17 January 2017 EXAMINATION ANSWER KEY Question 97 Info Question T e: Status: lwa s select on test? uthorized for ractice? lete: RO: SRO: KA#: Comments:
LMK 2017 IL T NRC JANUARY ILT 15-01 January 2017 NRG test SRO Multi le Choice Active No No 1.00 3 2.00 1685033 Q# 97 BANK 2015 NRG EAL OBJECTIVES SRO Recall who can A 2.4 4.4 2.4.38 Page: 360 of 374 2.4/4.4 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if re uired. bank 1150031 2015 NRG 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 361 of 374 17 January 2017 EXAMINATION ANSWER KEY 98 SRO Given the following:
IL T 15-01 January 2017 NRC test SRO 10:1454851 Unit 2 is operating at 100% power
* l&C is performing ST-2-072-104-1 "DIV IV NSSSS LSF/SAA" Points: 1.00
* 111 RECIRC-ES NSSSS Isolation Sys Out Of SERVICE (Outboard), has repeatedly alarmed due to the surveillance test
* 111 RECIRC-ES NSSSS Isolation Sys Out Of SERVICE (Outboard), has repeatedly alarmed due to the surveillance test
* The CRS determined the alarm to be a nuisance and authorized placing the annunciator mode switch in MANUAL
* The CRS determined the alarm to be a nuisance and authorized placing the annunciator mode switch in MANUAL
* The ST did NOT provide steps for changing the annunciator mode switch position Which one of the following describes the action required by OP-AA-103-102 "Watch-Standing Practices" AND OP-LG-103-102-1001 "Alarms And Indications" for these conditions?
* The ST did NOT provide steps for changing the annunciator mode switch position Which one of the following describes the action required by OP-AA-103-102 "Watch-Standing Practices" AND OP-LG-103-102-1001 "Alarms And Indications" for these conditions?
An __ (1 ) __ must be used if the annunciator mode switch is in manual greater than __ (2) __ . A. (1) Equipment Status Tag (EST) (2) 1 hour B. (1) Equipment Status Tag (EST) (2) 1 shift C. (1) Equipment Deficiency Tag (EDT} (2) 1 hour D. (1) Equipment Deficiency Tag (EDT) (2) 1 shift Answer: B Answer Explanation Correct: B For nuisance alarms, OP-AA-103-102 requires use of an EST if the annunciator mode switch will be in manual for greater than 1 shift. If the test procedure gives direction for controlling the annunciator mode switch, an EST is not required.
An __ (1 )__ must be used if the annunciator mode switch is in manual greater than __ (2) __ .
Distractors: Correct tag; wrong time. C Incorrect tag; incorrect time. Plausible because an EDT is used in cases where an annunciator alarms (and an alarm condition does NOT exist) due Ito an equipment/instrumentation failure. The applicant may confuse the specific cases involving annunciators when an EST is used versus an EDT. D Incorrect tag; correct time. Plausible because an EDT is used in cases where an annunciator alarms (and an alarm condition does NOT exist) due Ito an equipment/instrumentation failure. The applicant may confuse the specific cases involvinq annunciators when an EST is used versus an EDT. LMK 2017 IL T NRC JANUARY Page: 362 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 98 Info Question T e: Multi le Choice Status: Active No No 1.00 4 3.00 1454851 Q# 98 NEW LOT1572 COND. OF OPS SRO INOP annun 3.0 3.3 2.2.43 Comments:
A.       (1) Equipment Status Tag (EST) (2) 1 hour B.       (1) Equipment Status Tag (EST) (2) 1 shift C.       (1) Equipment Deficiency Tag (EDT} (2) 1 hour D.     (1) Equipment Deficiency Tag (EDT) (2) 1 shift Answer:           B Answer Explanation Correct: B For nuisance alarms, OP-AA-103-102 requires use of an EST if the annunciator mode switch will be in manual for greater than 1 shift. If the test procedure gives direction for controlling the annunciator mode switch, an EST is not required.
LMK 2017 ILT NRC JANUARY Page: 363 of 374 3.0/3.3 Knowledge of the process used to track inoperable alarms. lower n/a 43.5 OP-LG-103-102-1001 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 IL T NRC JANUARY Page: 364 of 374 17 January 2017 EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 99 SRO 10:1454568 Points: 1.00 Fuel is being loaded into the core on Unit 1, with the following:
Distractors:
-'1 A' SAM count rate is 3.5 cps and has a signal-to-noise ratio of 2.5 -'1 B' SAM count rate is 1.1 cps and has a signal-to-noise ratio of 7.0 -'1 C' SAM count rate is 2.0 cps and has a signal-to-noise ratio of 1.5 -'1 D' SAM count rate is 2.5 cps and has a signal-to-noise ratio of 2.3 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least two source range monitor (SRM) channels*
        ~ Correct tag; wrong time.
shall be OPERABLE and inserted to the normal operating level with: a. Continuous visual indication in the control room, b. At least one with audible alarm in the control room, c. One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and d. Unless adequate shutdown margin has been demonstrated, the shorting links shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn.**
C Incorrect tag; incorrect time. Plausible because an EDT is used in cases where an annunciator alarms (and an alarm condition does NOT exist) due Ito an equipment/instrumentation failure. The applicant may confuse the specific cases involving annunciators when an EST is used versus an EDT.
APPLICABILITY:
D Incorrect tag; correct time. Plausible because an EDT is used in cases where an annunciator alarms (and an alarm condition does NOT exist) due Ito an equipment/instrumentation failure. The applicant may confuse the specific cases involvinq annunciators when an EST is used versus an EDT.
OPERATIONAL CONDITION
LMK 2017 ILT NRC JANUARY                         Page: 362 of 374                       17 January 2017
: 5. With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS and insert all insertable control rods. LMK 2017 IL T NRC JANUARY Page: 365 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO '"&deg;I 1-1 I I I I I I I I I I I I 2.1 -I I I I I J I r l I I I I I I I I I I I I I J I ) 111 t I JI t I J 1 I 1 %.6 2.4 2.2 :
* o I\ I I I I I I I I I I I I I I I'\ J I I I I I I 1 I I I I &sect; ::: I \I I I I I I I I I I I I I ! 1 ** I l I I I I I I I I I I I I I .. 1.2 I I '! I I I I I I I I I I I I 1.a I I I 'i-1 I I I I I I I I I I o.. I I I&deg; *-1 ! ! ! I I I 111111t111' 0
* J ' I I I I I I I a
* I t I 2 ' 10 14 11 u 0 21 JO SIGNAL TO NOISE RATIO SRM COUNT RATE VERSUS SIGNAL TO NOISE RATIO FIGURE 3.3.6-1 WHICH ONE of the following describes the limitations, if any, regarding loading fuel into the core? A. Fuel may be loaded into any quadrant.
B. All fuel loading must be suspended immediately.
C. Fuel may be loaded into "A" or "D" core quadrants ONLY. D. Fuel may be loaded into "A", "C" or "D" core quadrants ONLY. LMK 2017 IL T NRC JANUARY Page: 366 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Answer: C Answer Explanation "A" SRM is operable even though 3.5 CPS is above the graph. The signal to noise ratio is used twhen counts are low and background noise may override the SRM signal. as seen on the graph once count rate exceeds approximately 2.3 any signal to noise ratio> approximately 2 will result in an operable SRM SRM Band C are below the line for signal to noise ratio and therefore INOP Correct: C '18" and "1C" SRMs are INOPERABLE
{"1C" due to inadequate Signal-To-Noise Ratio per Technical Specification Figure 3.3.6-1).
Therefore, fuel movement is only permitted in quadrants "A" and "D" per Technical Specification 3.9.2 {detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal")
Limerick Core quadrants are laid out as follows: AB DC Incorrect:
A With "1 B" and "1 C" SRMs INOPERABLE, fuel movement is permitted in quadrants "A" and "D" per Technical Specification 3.9.2 only (detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal").
Plausible to the candidate that mistakenly determines no SRMs are INOP due to assessing Signal to noise ratio incorrectly.
Incorrect:
B With "1 B" and "1 C" SRMs INOPERABLE, fuel movement is still permitted, but only in quadrants "A" and "D" per Technical Specification 3.9.2 {detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal").
Plausible to the candidate that mistakenly determines one or more additional inoperable SRMs due to assessing Signal to noise ration incorrectly.
Incorrect:
D Fuel cannot be loaded into quadrant "C" because the "1 C" SRM detector is INOPERABLE, and Technical Specification


====3.9.2 requires====
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 98 Info Question T    e:          Multi le Choice Status:                  Active No No 1.00 4
a detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant (adjacent being defined as "NOT diagonal").
3.00 1454851 Q# 98 NEW LOT1572 COND. OF OPS SRO INOP annun 3.0 3.3 2.2.43 Comments:
Plausible to the candidate that mistakenly determines no additional SRMs are INOP due to assessinq Signal to noise ratio incorrectlv.
3.0/3.3 Knowledge of the process used to track inoperable alarms.
LMK 2017 IL T NRC JANUARY Page: 367 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 99 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice?
lower n/a 43.5 OP-LG-103-102-1001 LMK 2017 ILT NRC JANUARY              Page: 363 of 374                      17 January 2017
No Points: 1.00 Jime to Complete:
 
3 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY            Page: 364 of 374        17 January 2017
2.00 System ID: 1454568 User-Defined ID: 0#99 BANK Lesson Plan Objective:
 
LGSOPS1800.68 iTopic: (SRO ONLY) -Tech Spec -SRM Operability During Fuel Loading RO: 3.0 SRO: 4.1 KA#: 2.1.36 LMK 2017 IL T NRC JANUARY Page: 368 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Comments:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 99                                              10:1454568                        Points: 1.00 SRO Fuel is being loaded into the core on Unit 1, with the following:
LMK 2017 IL T NRG JANUARY Page: 369 of 374 3 N/A 2.1.36 IMPORTANCE RO 3.0 SRO 4.1 Knowledge of procedures and limitations involved in core alterations.
        -  '1 A' SAM count rate is 3.5 cps and has a signal-to-noise ratio of 2.5
41.10; 43.6 Technical Specification 3.9.2 and Technical Specification Fi ure 3.3.6-1 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO LMK 2017 IL T NRG JANUARY Page: 370 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO 100 SRO Unit 1 is operating at 100% power. 10:1454415 Points: 1.00.
        -  '1 B' SAM count rate is 1.1 cps and has a signal-to-noise ratio of 7.0
* The Main Steam Line (MSL) Rad Monitors at 1 OC600 read as follows: A-2141 mR/hr up slow B -2170 mR/hr up slow C -2156 mR/hr up slow D -2196 mR/hr up slow
        -  '1 C' SAM count rate is 2.0 cps and has a signal-to-noise ratio of 1.5
        -  '1 D' SAM count rate is 2.5 cps and has a signal-to-noise ratio of 2.3 3/4.9.2       INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least two source range monitor (SRM) channels* shall be OPERABLE and inserted to the normal operating level with:
: a.      Continuous visual indication in the control room,
: b.      At least one with audible alarm in the control room,
: c.      One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and
: d.      Unless adequate shutdown margin has been demonstrated, the shorting links shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn.**
APPLICABILITY:        OPERATIONAL CONDITION 5.
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS and insert all insertable control rods.
LMK 2017 ILT NRC JANUARY                        Page: 365 of 374                  17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO
            '"&deg;I 1-1 I I I I I I I I I I I I 2.1
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  ! Il I I 1 **                              I    I      I I I        II    I II I
    ..      1.2  I I'! I I I I I I                                        IIIIII 1.a  I I I'i-1 I I I I                                        IIIII I o..            I I I&deg; *-1 !                                    !!            I I          I 0
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I    t      I 2              '            10          14            11  u          21          JO SIGNAL TO NOISE RATIO SRM COUNT RATE VERSUS SIGNAL TO NOISE RATIO FIGURE 3.3.6-1 WHICH ONE of the following describes the limitations, if any, regarding loading fuel into the core?
A.        Fuel may be loaded into any quadrant.
B.        All fuel loading must be suspended immediately.
C.        Fuel may be loaded into "A" or "D" core quadrants ONLY.
D.        Fuel may be loaded into "A", "C" or "D" core quadrants ONLY.
LMK 2017 ILT NRC JANUARY                              Page: 366 of 374                          17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer:          C Answer Explanation "A" SRM is operable even though 3.5 CPS is above the graph. The signal to noise ratio is used twhen counts are low and background noise may override the SRM signal. as seen on the graph once count rate exceeds approximately 2.3 any signal to noise ratio> approximately 2 will result in an operable SRM SRM Band C are below the line for signal to noise ratio and therefore INOP Correct: C
        '18" and "1C" SRMs are INOPERABLE {"1C" due to inadequate Signal-To-Noise Ratio per Technical Specification Figure 3.3.6-1). Therefore, fuel movement is only permitted in quadrants "A" and "D" per Technical Specification 3.9.2 {detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal")
Limerick Core quadrants are laid out as follows:
AB DC Incorrect: A With "1 B" and "1 C" SRMs INOPERABLE, fuel movement is permitted in quadrants "A" and "D" per Technical Specification 3.9.2 only (detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal"). Plausible to the candidate that mistakenly determines no SRMs are INOP due to assessing Signal to noise ratio incorrectly.
Incorrect: B With "1 B" and "1 C" SRMs INOPERABLE, fuel movement is still permitted, but only in quadrants "A" and "D" per Technical Specification 3.9.2 {detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal"). Plausible to the candidate that mistakenly determines one or more additional inoperable SRMs due to assessing Signal to noise ration incorrectly.
Incorrect: D Fuel cannot be loaded into quadrant "C" because the "1 C" SRM detector is INOPERABLE, and Technical Specification 3.9.2 requires a detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant (adjacent being defined as "NOT diagonal"). Plausible to the candidate that mistakenly determines no additional SRMs are INOP due to assessinq Signal to noise ratio incorrectlv.
LMK 2017 ILT NRC JANUARY                       Page: 367 of 374                             17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 99 Info Question Type:                 Multiple Choice Status:                         Active Always select on test?         No Authorized for practice?       No Points:                         1.00 Jime to Complete:               3 Difficulty:                     2.00 System ID:                       1454568 User-Defined ID:               0#99 BANK Lesson Plan Objective:         LGSOPS1800.68 (SRO ONLY) - Tech Spec - SRM Operability During Fuel iTopic:
Loading RO:                             3.0 SRO:                           4.1 KA#:                           2.1.36 LMK 2017 ILT NRC JANUARY                     Page: 368 of 374                         17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:
3 N/A 2.1.36 IMPORTANCE RO 3.0 SRO 4.1 Knowledge of procedures and limitations involved in core alterations.
41.10; 43.6 Technical Specification 3.9.2 and Technical Specification Fi ure 3.3.6-1 LMK 2017 ILT NRG JANUARY            Page: 369 of 374                        17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY             Page: 370 of 374       17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 100                                           10:1454415                                    Points: 1.00.
SRO Unit 1 is operating at 100% power.
* The Main Steam Line (MSL) Rad Monitors at 1OC600 read as follows:
A-2141 mR/hr up slow B - 2170 mR/hr up slow C - 2156 mR/hr up slow D - 2196 mR/hr up slow
* The HWC system is functioning correctly
* The HWC system is functioning correctly
* The following annunciators have been received:  
* The following annunciators have been received:
: 1. 109 RAD-F1, 1 MAIN STEAM LINE DIVISION 1 RAD MONITOR HI/DOWNSCALE  
: 1. 109 RAD-F1, 1 MAIN STEAM LINE DIVISION 1 RAD MONITOR HI/DOWNSCALE
: 2. 109 RAD-F2, 1 MAIN STEAM LINE RAD MON CID HI/DOWNSCALE WHICH ONE of the following identifies the procedure(s) requiring entry and an action(s) required as a result of the above conditions?
: 2. 109 RAD-F2, 1 MAIN STEAM LINE RAD MON CID HI/DOWNSCALE WHICH ONE of the following identifies the procedure(s) requiring entry and an action(s) required as a result of the above conditions?
ON-102, Air Ejector Discharge or Main Steam Line High Radiation T-101, RPV Control T-103, Secondary Containment Control Procedure(s) requiring entry A. ON-102 but NOT T-103 8. ON-102 AND T-103 c. ON-102 but NOT T-103 D. ON-102 AND T-103 Answer: B !Answer Explanation LMK 2017 IL T NRC JANUARY Page: 371 of 374 Actjon(s) required Reduce reactor power to lower MSL Rad levels below 1.5X NFPB Reduce reactor power to lower MSL Rad levels below 1.5X NFPB Shutdown the reactor and close the MSIVs Shutdown the reactor and close the MSIVs 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO From the stem the SRO candidate identifies that Main Steam Line (MSL) radiation is elevated and above 1.5 X Normal Full Power Background (NFPB) (the alarm set points are 1.5 X NFPB) for 109-F1 and 2 . Also from the stem the students determine that MSL Rad is below 3 X NFPB (based on the absence of ARC-MCR-107 11, Main steam line high-high radiation).
ON-102, Air Ejector Discharge or Main Steam Line High Radiation T-101, RPV Control T-103, Secondary Containment Control Procedure(s) requiring entry                     Actjon(s) required A.               ON-102 but NOT T-103                 Reduce reactor power to lower MSL Rad levels below 1.5X NFPB
Based in this information the appropriate procedures are both ON-102 and T-103. The appropriate action for conditions is found in ON-102 step 2.2: IF power reduction is required to maintain air ejector discharge radiation level below HiHi Alarm setpoint (ARC-MCR-*09 G1) OR main steam line radiation level below 1.5x normal full power background, lrHEN REDUCE reactor power in accordance with GP-5 Appendix 2, Section 3.1, Reducing Rx Power, AND Reactor Maneuvering Shutdown Instructions to maintain air ejector discharge radiation level below Hi Hi Alarm setpoint (ARC-MCR-*09 G1) AND Main Steam Line radiation level below 1.5 x normal full power background. (CM-1 T03582) A Wrong -Does not identify T-103 entry. Plausible to the student that believes T-103 entry is not required until 3X NFPB B Correct -See discussion above C Wrong -Does not identify T-103 entry and identifies that wrong actions for the given conditions.
: 8.                 ON-102 AND T-103                   Reduce reactor power to lower MSL Rad levels below 1.5X NFPB
Plausible to the student that believes T-103 entry is not required until 3X NFPB and believes that closure of the MSIVs is required at 1.5 X NFPB. This is requred above 3 x N FPB D Wrong -Identifies that wrong actions for the given conditions.
: c.               ON-102 but NOT T-103               Shutdown the reactor and close the MSIVs D.                 ON-102 AND T-103                   Shutdown the reactor and close the MSIVs Answer:         B
Plausible to the student that believes that closure of the MS IVs is required at 1.5 X NFPB. This is requred above 3 x NFPB LMK 2017 IL T NRC JANUARY Page: 372 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRC test SRO Question 100 Info Question Tvpe: Multiple Choice Status: Active select on test? No for practice?
          !Answer Explanation LMK 2017 ILT NRC JANUARY                       Page: 371 of 374                               17 January 2017
No Points: 1.00 rT'ime to Complete:
 
5 Difficulty:
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO From the stem the SRO candidate identifies that Main Steam Line (MSL) radiation is elevated and above 1.5 X Normal Full Power Background (NFPB) (the alarm set points are 1.5 X NFPB) for 109-F1 and 2 . Also from the stem the students determine that MSL Rad is below 3 X NFPB (based on the absence of ARC-MCR-107 11, Main steam line high-high radiation). Based in this information the appropriate procedures are both ON-102 and T-103. The appropriate action for
2.00 Svstem ID: 1454415 User-Defined ID: 0#100 NEW Lesson Plan Objective:
        ~hese conditions is found in ON-102 step 2.2:
LGSOPS0026A.
        ~.2  IF power reduction is required to maintain air ejector discharge radiation level below HiHi Alarm setpoint (ARC-MCR-*09 G1)
IL 12 Topic: SRO -Interpreting MSL Rad Monitor Readings RO: 2.9 SRO: 2.9 KA#: 272000 G2.3.5 LMK 2017 IL T NRG JANUARY Page: 373 of 374 17 January 2017 EXAMINATION ANSWER KEY IL T 15-01 January 2017 NRG test SRO Comments:
OR main steam line radiation level below 1.5x normal full power background, lrHEN REDUCE reactor power in accordance with GP-5 Appendix 2, Section 3.1, Reducing Rx Power, AND Reactor Maneuvering Shutdown Instructions to maintain air ejector discharge radiation level below Hi Hi Alarm setpoint (ARC-MCR-*09 G1)
LMK 2017 IL T NRG JANUARY Page: 374 of 374 3 N/A 2.3.5 IMPORTANCE RO 2.9 SRO 2.9 0 1 29 23 17 January 2017}}
AND Main Steam Line radiation level below 1.5 x normal full power background. (CM-1 T03582)
A       Wrong - Does not identify T-103 entry. Plausible to the student that believes T-103 entry is not required until 3X NFPB B       Correct - See discussion above C       Wrong - Does not identify T-103 entry and identifies that wrong actions for the given conditions. Plausible to the student that believes T-103 entry is not required until 3X NFPB and believes that closure of the MSIVs is required at 1.5 X NFPB. This is requred above 3 x N FPB D       Wrong - Identifies that wrong actions for the given conditions. Plausible to the student that believes that closure of the MS IVs is required at 1.5 X NFPB. This is requred above 3 x NFPB LMK 2017 ILT NRC JANUARY                         Page: 372 of 374                               17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 100 Info Question Tvpe:                   Multiple Choice Status:                         Active
      ~lwavs select on test?           No
      ~uthorized for practice?         No Points:                         1.00 rT'ime to Complete:             5 Difficulty:                     2.00 Svstem ID:                     1454415 User-Defined ID:               0#100 NEW Lesson Plan Objective:         LGSOPS0026A. IL 12 Topic:                         SRO - Interpreting MSL Rad Monitor Readings RO:                             2.9 SRO:                           2.9 KA#:                           272000 G2.3.5 LMK 2017 ILT NRG JANUARY                     Page: 373 of 374                     17 January 2017
 
EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Comments:
3 N/A 2.3.5 IMPORTANCE RO 2.9 SRO 2.9 0
1 29 23 LMK 2017 ILT NRG JANUARY            Page: 374 of 374                      17 January 2017}}

Latest revision as of 14:19, 24 February 2020

Final Written Examination with Answer Key (401-5 Format) (Folder 3)
ML17075A382
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 01/16/2017
From:
Exelon Generation Co
To:
NRC Region 1
Shared Package
ML16076A445 List:
References
U01940
Download: ML17075A382 (376)
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Text

KEY LIMERICK 2017 SRO NRC \VRITTEN EXAM 1 A 27 B 52 A 78 c 2 B 28 c 53 B 79 A 3 D 29 D 54 c 80 c 4 c 30 A 55 A 81 B 5 -e- Ace-er+ Sol"" C 31 D 56 A 82 D Ao 2ft~1 6 c 32 c 57 B 83 B 7 D 33 B 58 D 84 A 8 A 34 B 59 c 85 A 9 D 35 B 60 A 86 c 10 D 36 B 61 c 87 A 11 A 37 A 62 c 88 B 12 D 38 D 63 B 89 c 13 B 39 c 64 c 90 A 14 D 40 D 65 A 91 D 15 66 defe-U B 41 A B M2":¢7 92 D 16 D 42 c 67 A 93 c 17 c 43 A 68 D 94 D 18 B 44 B 69 B 95 B 19 A 45 c 70 c 96 D 20 D 46 B 71 B 97 D 21 A 47 D 72 A 98 B 22 D 48 c 73 c 99 c 23 A 49 c 74 c 100 B 24 D 50 B 75 c 25 B 51 A 76 A 26 D 77 D Page 1of1

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 1 ID: 14553n Points: 1.00 A startup is in progress on unit 1 Which of the following describes when the IRM's will swap to a high frequency amplifier and the potential for a half SCRAM and I or a rod block?

Ranging IBM from range Potential for a half SCRAM and I or rod block A. 6to 7 Half SCRAM and rod block B. 6to 7 Half SCRAM only

c. 2 to 3 Half SCRAM and rod block D. 2 to 3 Half SCRAM only Answer: A Answer Explanation A Correct per GP-2 App 1; WHEN changing range from 6 to 7 on the IRMs, THEN the range change swaps from the low frequency amplifier to the high frequency amplifier AND could cause a half-scram.

Although GP-2 does not reference a rod block the 1/2 scram is due to potential spiking of the IRM when ranging between 6 and 7. Any spiking that will cause a 1/2 scram will also cause a rod block B Incorrect a rod block will also be generated. Plausible to examinee who does not recall that when ranging from 6 to 7 there is a potential for spiking of the IRM which could result in a rod block and half SCRAM C Incorrect; plausible to the examinee who recalls an IRM function (SAM down scale rod block is bypassed) when ranging from 2 to 3 D Incorrect; plausible to the examinee who confuses the SAM down scale bypass when ranged from 2 to 3 with when the amplifier swaps to high frequency and does not recall that a rod block will also be generated. from spiking of the IRM.

LMK 2017 ILT NRG JANUARY Page: 1 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO .

Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 2.50 System ID: 1455392 User-Defined ID: Q# 1 NEW Lesson Plan Objective: LGSOPS007 4.22A Topic: IRM ranqe RO: 2.6 SRO: 2.7 KA#: 215003 K5.01 LMK 2017 ILT NRC JANUARY Page: 2 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 215003 K5.01 2.6/2.7 215003 Intermediate Range Monitor (IRM) System Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM : Detector o eration Hi h 41.5 GP-2 LGSOPS0074 LMK 2017 ILT NRG JANUARY Page: 3 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 2 10:1454410 Points: 1.00 Unit 1 plant conditions:

- 107 REACTOR F-5, DIV 1 STEAM LEAK DET SYS HI TEMPfrROUBLE alarm is lit

- 107 REACTOR H-5, DIV 3 STEAM LEAK DET SYS HI TEMPfrROUBLE alarm is NOT lit

- RCIC STEAM LINE HI FLOW alarm is NOT lit An Equipment Operator in the Aux. Equipment room reports the following

  • NUMAC TIS-25-101A RCIC equipment room is reading 195 degrees F
  • NU MAC TIS-25-101 C RCIC equipment room is reading 11 O degrees F Assuming no operator action which of the following identifies the status of the RCIC Isolation Valves one minute later?

HV49-1 F007 BCIC Steam Line Inboard HV49-1 FOOS BCIC Steam Line Outboard Isolation Isolation A. Open Open B. Open Closed

c. Closed Open D. Closed Closed Answer: B

!Answer Explanation D incorrect If power is available either division activation will close all associated RCIC steam line

~alves. The two divisions are for redundancy, with no high steam line flow (>300%) there is not a

~ull isolation is.

Candidate must determine that div 1 is above both the alarm (>123 degrees) setpoint and above ltrip set point (> 180 degrees)

~incorrect plausible to the examinee who incorrectly believes that both DIV 1 and 3 temperatures are required for any valve to close.

B Correct the DIV 1 hi temperature will close the outboard valve.

C incorrect plausible to the examinee who incorrectly believes the DIV 1 isolation closes the inboard valve LMK 2017 ILT NRG JANUARY Page: 4 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 2 Info IQuestion Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1454410 User-Defined ID: Q# 2 MODIFIED Lesson Plan Obiective: LOT0380.06 RCIC Describe the status of RCIC Isolation valves with "DIV 1 STEAM Topic:

LEAK DETECTION" RO: 3.1 SRO: 3.2 KA#: 217000 K1 .07 LMK 2017 ILT NRC JANUARY Page: 5 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

217000 K1.07 3.1/3.2 Reactor Core Isolation Cooling System (RCIC)

Knowledge of the physical connections and/or cause effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the followin : Leak detection 2

41.5,41.7 bank 560597 LMK 2017 ILT NRC JANUARY Page: 6 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 3 10:1454509 Points: 1.00 Unit 1 plant conditions are as follows:

  • OPCON 4
  • Annunciator 122-A1 012 BUS OIFF/ OVERCURRENT LOCKOUT alarms
  • After the annunciator is received reactor level lowers to -25 inches before being restored (no other operator actions have been taken)

Which of the following describes the final position of the listed RHR valves due to the above conditions?

[: ~~H~O HV51-1F009, RHR S/O Cooling Inboard PCIV HV51-1F015B~ Rj-IR ~/~ cooling injection Outboard PCIV 1

J.. -fttr,P 1/'2-7/ 11 :J. v,(Jl 'i

~ f'2j7 HV51-1 F009 HV51-1F0158 A. Open Open B. Closed Closed

c. Open Closed
0. Closed Open Answer: 0 Answer Explanation HV51-1 F009, 1RHR S/O Cooling Inboard PCIV power supply is 011 HV51-1F0158, 1B RHR S/O Cooling injection PCIV power supply is 012 A Incorrect plausible to the examinee who recalls that both the HV51-1 F015A&B are powered from the same source but believe it is 011 not 012 B Incorrect plausible to the examinee who does not recognize that a 012 bus differential over current will deenergize the bus, preventing the motor operated valves from closing C Incorrect plausible to the examinee who reverse inboard and outboard power supplies 0 Correct with 012 deenergized only the HV51-1 F009, RHR S/O Cooling Inboard PCIV will close LMK 2017 ILT NRC JANUARY Page: 7 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 6 Difficulty: 2.00 System ID: 1454509 User-Defined ID: Q#3 NEW Lesson Plan Objective: LLOR0701 E.3 Topic: Loss of power to SDC valves RO: 2.5 SRO: 2.7 KA#: 205000 K2.02 LMK 2017 ILT NRG JANUARY Page: B of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 205000 K2.02 2.5/2.7 Shutdown Cooling System (RHR Shutdown Cooling Mode Knowledge of electrical power supplies to the following: Motor operated valves low 4

41.7 S51.7.B ON-121 821-1090-E-01 2 Sh. 12, C61-1050-E-01 LMK 2017 ILT NRG JANUARY Page: 9 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 4 ID: 1454528 ' Points: 1.00 Unit 2 plant conditions:

- HPCI is running in full flow test (CST to CST) at 5600 gpm A loss of Division 2 DC power occurs.

Which of the following identifies the impact, if any, on continued HPCI operation?

A. Continues to run at 5600 gpm B. Div 2 isolation occurs C. Turbine Governor Valve closes D. HPCI over speed trip occurs Answer: C Answer Explanation

~loss of DIV 2 power to HPCI will cause HPCI speed to run back to the low setting due to loss of control power to the flow controller which feeds the Turbine Governor. DIV 2 provides power for control power, isolation circuits, all DIV 2 valves, initiation logic, aux oil pump control and turbine

~rip logic. HPCI is out of service and not available on loss of DIV 2.

~ Plausible to candidate who does not remember loss of div 2 will close governor but recalls that

~he isolation is energized to operate.

B Plausible to candidate who believes that HPCI isolation logic is deenergize to operate C Correct A loss of DIV 2 power to HPCI will cause HPCI speed to run back to the low setting due

~o loss of control power to the flow controller which feeds the Turbine Governor. When turbine speed drops below approximately 1000 RPM the shaft driven oil pump will not have sufficient pressure to maintain the governor valve open. a loss of div II de will cause the aux. oil pump to lose power, so it will not be available to start on low pressure. without the aux oil pump the governor will continue to close to the full closed position.

D Plausible to candidate who believes the qovernor fails full open on a loss of power LMK 2017 ILT NRG JANUARY Page: 10 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1454528 User-Defined ID: 0#4 BANK Lesson Plan Objective: HPCI 14.A Topic: Predict Impact of Loss of Div 2 DC on HPCI Operation RO: 2.5 SRO: 2.7 KA#: 206000 K2.04 LMK 2017 ILT NRG JANUARY Page: 11 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 1

206000 K2.04 2.5/2.7 High Pressure Coolant Injection System Knowledge of electrical power supplies to the following: Turbine control circuits: BWR-2,3,4 lower 2

41.7 E41-1040-E-OO 4, sht. 001 26 E41-1040-E-OO 30 5, sht. 001 E41-1040-E-OO 36 2

6, sht. 001 ARC-MCR-117, A1 bank 560442 LMK 2017 ILT NRG JANUARY Page: 12 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 5 ID: 1454611 Points: 1.00 Given:

  • Instrument Air header pressure is lowering The CRS has directed a power reduction per ON-119, Loss Of Instrument Air Which of the following describes the bases for the power reduction?

A. Reduce the probability of a turbine trip from lowering condenser vacuum.

B. Reduce the transient if a SCRAM is required due to rods drifting in.

C. Reduce the probability of inadequate feedwater should the condensate or feed pump min flow valves drift.

D. Reduce the probability of power exceeding 100% should the feedwater heater dump valves fail open.

Answer:

Answer Explanation

1. Both inst. air header low alarms coming in is an entry condition for ON-119.
2. The bases for reducing power to 44% is to reduce the probability of a loss of adequate feedwater should the Condensate or RFP Min Flow valve begin to drift open.
3. Low Instrument Air pressure could cause CAD HCU scram valves to drift open, resulting in the associated control rods to insert. This is the Bases for manually SCRAM ING the reactor if control rods start to drift in
4. Air ejector valves may fail due to loss of air causing vacuum to decrease, however ON-119 directs entry to OT-116 for loss of vacuum actions
5. Feed water dump valves may fail open on a loss of air causing a power increase, however ON-119 directs operators to OT-104 for a loss of feedwater heating Q..f'(_

B t.M.cL. C ltt correct for the above reasons and the distractors are plausible to the examinee who does not recall the basis for reducinq power to 44%

LMK 2017 ILT NRC JANUARY Page: 13 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 3 Difficulty: 2.00 System ID: 1454611 User-Defined ID: 0#5 NEW Lesson Plan Objective: LGSOPS1550.03 lfopic: actions for loss of air RO: 3.3 SRO: 3.4 KA#: 300000 K3.02 LMK 2017 ILT NRC JANUARY Page: 14 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

300000 K3.02 3.3/3.4 Instrument Air System (IAS)

Knowledge of the effect that a loss or malfunction of the

  • INSTRUMENT AIR SYSTEM) will have on the following: Systems having neumatic valves and controls 41.7 ON-119 28 P&ID M-0015 40 sht 4 LMK 2017 ILT NRC JANUARY Page: 15 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 6 ID: 1685687 Points: 1.00 Unit 1 is operating at 100% power when the following occurs:

- The speed demand signal from DFWLC for the '1 A' RFP fails to 1 mA.

RPS successfully actuates, but an ATWS occurs.

One minute later, all of the logic to produce an ARCS Feedwater Runback is satisfied.

WHICH ONE of the following identifies the status of '1A' RFP two minutes after the runback logic is satisfied?

(Assume Il.Q operator action.)

A. Running at 2300 rpm; M/A Station in control B. Running at 2300 rpm; MSC in control C. Running at the same speed as before the runback signal; MSC in control D. Running at the same speed as before the runback signal; M/A Station in control Answer: C Answer Explanation The speed demand signal loss results in 1A RFP swapping to MSC (an automatic swap to MSC when the DFWLC output fails to 1 mA) control and "locking up" at its present speed. Since its in "lockup" p.ri.Qr to the Runback, it will NOT respond to the Runback signal.

'C' is correct for the above reasons.

'A', 'B' are wrong. Plausible to the examines who forgets that the pre-existing lockup inhibits that RFP from responding to the runback.

'D' is wrong. Control will not swap back to or stav in M/A station control.

LMK 2017 ILT NRG JANUARY Page: 16 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 6 Info K;luestion Type: Multiple Choice Status: Active

!Always select on test? No

!Authorized for practice? No Points: 1.00 tTime to Complete: 4 Difficulty: 2.50 System ID: 1685687 User-Defined ID: 0#6 Lesson Plan Obiective: LOT-0550, OBJ4 RFP Speed Signal Loss - RFP Response to RRCS FW R/B lropic:

Siona!

RO: 3.7 SRO: 3.7 KA#: 259002 K3.02 LMK 2017 ILT NRG JANUARY Page: 17 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

259002 K3.02 3.7/3.7 Reactor Water Level Control System Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following: Reactor feedwater s stem LMK 2017 ILT NRC JANUARY Page: 18 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 19 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO 7 ID: 1454748 Points: 1.00 Unit 2 plant conditions are as follows:

- 100% Reactor Power

- Normal Electrical Lineup The following sequence of events occurs:

  • t = 0 seconds RPV level drops below -129 inches
  • t = 20 seconds 201 Safeguard Bus < 70% bus voltage Which of the following identifies the closed 023 Bus Source Breaker AND. the status of the "2C" AHR Pump Breaker at T =75 seconds?

CLOSEDD23BUSSOUBCE "2C" RHB PUMP BREAKER BREAKER A. 101-023 Open B. 101-023 Closed C. 023 OG Output Breaker Open

0. 023 OG Output Breaker Closed Answer: 0

!Answer Explanation LMK 2017 ILT NRC JANUARY Page: 20 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 023 OG Output Breaker closed 023 DG started on the LOCA signal. Since it had been running for greater than 1O seconds before the loss of power, the DG is ready to be loaded and the 0.5 second closing signal from the 023 Bus Under voltage logic will allow the 023 DG Output Breaker to close before the 1.0 second Dead Bus Transfer closing. Since the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will llow the breaker to reclose.

open his answer is incorrect because the 023 DG Output Breaker will close (0.5 second time delayed closure) before the 101-023 Breaker (1.0 second time delayed closure), since the 023 DG was previously running and was in a "ready-to-load" status. Since the time frame between the initial tart signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker closes. The "2C" RHR Pump will not remain shutdown.

101-023 closed his answer is incorrect because the 023 DG Output Breaker will close (0.5 second time delayed losure) before the 101-023 Breaker (1.0 second time delayed closure), since the 023 DG was previously running and was in a "ready-to-load" status. Since the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully charge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker (not he 101-023 Breaker) closes. The "2C" RHR Pump will not remain shutdown.

023 OG Output Breaker open his answer is incorrect because the time frame between the initial start signal for the "2C" RHR Pump (LOCA signal) and the subsequent restart signal after the 023 Bus is re-energized by the 023 DG is greater than 2.0 seconds, the charging motor on the "2C" RHR Pump breaker will fully harge the closing springs on the breaker, and the anti-pumping relay will not seal-in, which will allow the breaker to reclose after the 023 DG Output Breaker (not the 101-023 Breaker) closes.

he "2C" RHR Pum will not remain shutdown.

LMK 2017 ILT NRG JANUARY Page: 21 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 7 Info Question Tvpe: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice? No Points: 1.00 rl"ime to Complete: 3 Difficulty: 2.00 System ID: 1454748 User-Defined ID: Q# 7 BANK Lesson Plan Objective: LGSOPS0092.5A lropic:

Unit 2 plant conditions are as follows: - 100% Reactor Power -

Normal Electrical Lineup The RO: 3.1 SRO: 3.4 KA#: 262001 K4.04 LMK 2017 ILT NRG JANUARY Page: 22 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

262001 K4.04 2.8/3.1 A.C. Electrical Distribution Knowledge of A.C.

ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the followin : Protective rela in Hi her LMK 2017 ILT NRG JANUARY Page: 23 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 8 10:1454749 Points: 1.00 Unit 1 plant conditions:

- Reactor scrammed; all control rods fully inserted

- RPV level is -7", steady

- Drywell pressure is 6.5 psig, up slow

- 1A AHR Pump is operating in Suppression Pool Spray

- All other low pressure ECCS pumps are secured Wide range level instrument LIS-42-1 N691 A, which inputs to ADS, fails downscale.

Assuming no operator action, which of the following identifies the impact on the ADS SRVs?

A. Remain closed B. Open immediately

c. Open in 105 seconds D. Open in 525 seconds Answer: A Answer Explanation A E c G ow (1.68) X (or 420) X (or 420) X (or 420) X (or 420)

Rx Level (-129) x x x x Cont Level x x (12.5)

T.D. (105) x x 125# AHR A/C 0 0 145# A CS 0 145# c cs 0 125# B/D AHR 0 0 145# B CS 0 145# D CS 0 Enerqizes K6A K6E K6C K6G With RPV Level < 12.5" and Drywell Pressure > 1.68# and the "1 A" AHR pump running, the 105 sec time delay and -129" on both A and E channels is needed. The failed instrument in the stem (LIS-42-1 N691 A,C,E or G) provides the -129" input to one channel, but not to the other channel.

Therefore, ADS does not initiate.

System design is such that -129 signals are required for 1 division to initiate to prevent inadvertent isolation LMK 2017 ILT NRG JANUARY Page: 24 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15*01January2017 NRC test SRO Question 8 Info Question Type: Multiple Choice Status: ~ctive Always select on test? No

/\uthorized for practice? No Points: 1.00

!rime to Complete: 3 Difficulty: 2.00 System ID: 1454749 User-Defined ID: Q# 8 BANK Lesson Plan Objective: LGSOPS005.03F Topic: Impact of failed level instrument on ADS RO: 3.7 SRO: 3.9 KA#: 218000 K4.01 LMK 2017 ILT NRG JANUARY Page: 25 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 218000 K4.01 3.7/3.9 Automatic Depressurization System Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature{s) and/or interlocks which provide for the following:

Prevent inadvertent initiation of ADS lo ic 3

41.7 see explanation bank 562181 LMK 2017 ILT NRG JANUARY Page: 26 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 9 10:1455668 Points: 1.00 Unit 1 is operating at full power when 113 BS CORE SPRAY LINE INTERNAL BREAK alarm actuates and will not clear. An equipment operator reports that Core Spray differential pressure transmitter PDT-052-1 N056 indicates +2.1 psid.

Given the following from the annunciator response card OPERATOR ACTIONS:

NOTE: Alarm designed to indicate failure of one of the core spray loop piping between the vessel penetration AND the core shroud penetration. Normal rated power shroud/annulus dP is 7.5 psid. A valid value of greater than +1.3 or less than -3.B psid indicates a failure of the core spray piping outside the shroud. A value of greater than +7.5 psid or less than -10.0 psid indicates a failure of the core spray piping outside the vessel. A failure between the vessel AND containment would be measured by the containment leakage detection systems. This instrument loop is very noisy due to the condensation of steam inside the core spray piping AND also sensing pressures inside the shroud. Spurious alarms that immediately clear should NOT be considered valid.

For a subsequent loss of high pressure injection; Which of the following lists the heat removal capabilities of the affected Core Spray system?

A. Effective for BOTH core submergence AND spray cooling B. NOT effective for EITHER core submergence OR for spray cooling C. Effective for spray cooling but NOT tor core submergence D. Effective for core submergence but NOT for spray cooling Answer: D nswer Explanation RC-113-BS alarm indicates an A loop leak in the annulus is detected.This break prevents core spray flow from reaching the spray nozzles, located above the core. But since the line break is in he annulus, core spray flow will discharge through the break into the annulus, which can provide ater for core submergence. Answer D is correct and answer A, B, and C are incorrect but plausible to the examinee who miss understands the information provided, or does not understand the design features of the reactor vessel and internals.

Incorrect plausible to the examinee who miss interprets the information in the ARC and believe he value +2.1 is in the acceptable range B Incorrect plausible to the examinee who does not recognize the line break is in the annulus, ore spray flow will discharge through the break into the annulus, which can provide water for core submergence.

C Incorrect lausible to the examinee who confuses s ra and submer ence coolin LMK 2017 ILT NRG JANUARY Page: 27 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 rnme to Complete: 4 Difficulty: 4.00 System ID: 1455668 User-Defined ID: Q# 9 BANK Lesson Plan Objective: LLOT035.1 OA lropic: Core spray cooling mode RO: 2.8 SRO: 2.9 KA#: 209001 K5.04 LMK 2017 ILT NRG JANUARY Page: 28 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

209001 K5.04 2.8/2.9 Low Pressure Core Spray System Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY bank 510688 Oyster creek modified bank 510688 Oyster creek modified bank 51 0688 Oyster creek modified LMK 2017 ILT NRC JANUARY Page: 29 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 10 ID: 1671166 Points: 1.00 Unit 1 is operating at 100% power.

1 UNIT DIV 1 SFGD BATTERY CHARGERS TROUBLE (120 G-1) alarms.

An EO reports that the 480 VAC MCC supply breaker for the 1A1D103 Battery Charger has tripped.

WHICH one of the following is supplying power for Div 1 DC loads?

A. 1A1 Battery, ONLY B. 1A2D103 Battery Charger, ONLY C. 1A1 AND 1A2 Batteries D. 1A1 Battery AND 1A2D103 Battery Charger Answer: D Answer Explanation The Division I DC Distribution system has 2 batteries and each battery has a battery charger. The battery chargers are the normal source of power for the DC system. With a trip of one of the battery chargers, the associated battery will begin to discharge. The second battery charger will continue to supply the DC bus.

ARC-MCR-120 G-1, E-33 sh. 1, E-92 sh. 1 1A1 Battery only is plausible as a source but incomplete without the A2 side of the battery 1A2D103 Battery Charger only is plausible but incomplete answer without A 1 1A1 and 1A2 Batteries is plausible but incorrect as the 1A2D103 charger is still functioning and suoolying the bus.

LMK 2017 ILT NRC JANUARY Page: 30 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 1O Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 1.00 System ID: 1671166 User-Defined ID: Q#10 BANK Lesson Plan Obiective: LLOR0605D.01 Unit 1 is at 100% Reactor power. 1 UNIT DIV 1 SFGD BATTERY Topic:

CHARGERS TROUBLE (120 G-1) alarms. An E RO: 3.2 SRO: 3.3 KA#: 263000 K1 .02 LMK 2017 ILT NRC JANUARY Page: 31 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

D.C. Electrical Distribution Knowledge of the physical connections and/or causeeffect relationships between D.C. ELECTRICAL DISTRIBUTION and the following: Battery charger and batter E-0092 sht1 E-0033 sh.

ARC-MCR-120 G-1 bank 562594 bank 562594 bank 562594 LMK 2017 ILT NRC JANUARY Page: 32 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 11 ID: 1454874 Points: 1.00 A LOCA occurs on Unit 2 which results in the following conditions:

RPV level drops to -140" before being restored to +20" with low pressure ECCS All Unit 2 diesels are running unloaded

  • The PRO has been directed to synchronize D23 DIG with the 201 Safeguard Bus.
  • Before this can be performed, D23 D-G TROUBLE (221 B-1) alarms in the MCR.
  • An EO dispatched to D23 reports that "J.W. TEMP HIGH" is in alarm at 2C-C514 panel and actual Jacket water temperature is 200°F.

WHICH ONE of the following describes the response of the D23 Diesel Generator if the "Diesel Generator Auto Start Signal Bypass" (BYPASSED) pushbutton PB/CG001 is depressed?

A. Diesel will trip B. Diesel will continue to run in isochronous mode C. Diesel converts from droop to isochronous mode D. Diesel converts from isochronous to droop mode Answer: A Answer Explanation On a LOCA signal, the diesel will start in the isochronous mode. To synchronize the engine it must be converted to droop. To perform this, the operator must first depress the DG AUTO START BYPASS pushbutton to de-energize the LOCA start logic for the diesel and closes a permissive in the control switch logic to allow energization of the droop relay. Once this has been performed, the diesel control switch in the MCR must be placed to start. This will place the diesel in the droop mode of operation. However, if any trips that are normally bypassed are present when the DG AUTO ST ART pushbutton is depressed, the engine will trip due to the LOCA relay being de-energized by the pushbutton. Ref. caution in S92.7.N. the distractors are plausible to the examinee who does not recall that the TRIP bypass will go away when the LOCA is reset and C also requires the examinee to misinterpret droop and isochronous operation.

Hi temp trip is bypassed on LOCA siqnal LMK 2017 ILT NRG JANUARY Page: 33 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 if ime to Complete: 3 Difficulty: 2.80 System ID: 1454874 User-Defined ID: Q# 11 BANK Lesson Plan Objective: LGSOPS0092B.1 OF Effect on Diesel running on LOCA due to depressing AUTO ifopic:

START BYPASS with Hiqh Lube Oil Temp present RO: 3.8 SRO: 3.9 KA#: 264000 K6.07 LMK 2017 ILT NRG JANUARY Page: 34 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 1

264000 K6.07 3.8/3.9 Emergency Generators (Diesel/Jet) Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET) :Cooling bank 554174 modified to better match K.A LMK 2017 ILT NRG JANUARY Page: 35 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 36 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 12 ID: 1600748 ... Points: 1.00 Unit 1 is at 100% power when a malfunction in the Reactor Enclosure Cooling Water system (RECW) causes the following:

  • A rising trend in RWCU Non-Regenerative Heat Exchanger outlet temperature.

Current Non-Regenerative Heat Exchanger outlet temperature is 128 ° F Temperature is rising at constant rate of 2 ° F/min Which of the choices correctly completes the following statement?

A RWCU isolation signal will actuate in (1) minutes, reactor coolant (2) will rise if the isolation fails to occur.

A. (1) 3.5 (2) pH B. (1) 3.5 (2) conductivity

c. (1) 6 (2) pH D. (1) 6 (2) conductivity Answer: D

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 37 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO The RWCU system is operated using S44.0.A, "OPERATING RWCU TO MEET PLANT CONDITIONS" (among other procedures). Within this procedure one of the system Precautions is:

3.7 RWCU system will isolate at 140°F at outlet of Non-regenerative Heat Exchanger.

080 3.2.5.1 Basis - Non-Regenerative Heat Exchanger Outlet Temperature The limit on the Non-Regen HX outlet temperature is required to protect the filtering and ion exchange medium (resin) used in the F/Ds. Excessive temperatures can cause the resin to disintegrate and dissolve in the reactor water, compounding contamination and radiation problems. The controlling

~arameter value of 140F is established by the system specification {6.1.2.1}.

ON-116 12.3 IF Reactor Water Conductivity is greater than 1.0 umho/cm with main steam line (MSL) radiation high AND Reactor Water pH low (Resin or other organic intrusion is suspected),

!THEN PERFORM the following:

12.3.1 IF MSL radiation rises to 1.5 x normal full power background,

!THEN ENTER ON-102

~ND EXECUTE concurrently.

12.3.2 DETERMINE RWCU Demin that could be passing resin by identifying demin with high effluent conductivity (suspect demin recently placed in service).

A Wrong - Plausible to the student who either recalls the isolation set point incorrectly or performs the calculation incorrectly, also plausible to the student who incorrectly recalls (reverses) the Affect on conductivity and PH B Wrong - Plausible to the student who either recalls the isolation set point incorrectly or performs the calculation incorrectly.

C Wrong - plausible to the student who incorrectly recalls (reverses) the Affect on conductivity and PH D Correct for the above reasons - Isolation occurs at 140 F. At a rate of rise of 2 degrees/

minutes the isolation will occur after 6 minutes (rise of 12 degrees F). and conductivity rises and PH lowers LMK 2017 ILT NRC JANUARY Page: 38 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 12 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 ifime to Complete: 2 Difficulty: 3.00 System ID: 1600748 User-Defined ID: Q #12 NEW Lesson Plan Objective: LGSOPS0044.05 (RWCU) rrooic: RWCU - Expain and apply all system limits and precautions RO: 2.9 SRO: 3.3 KA#: 400000 LMK 2017 ILT NRC JANUARY Page: 39 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

RO 2

1 400000 K3.01 2.9/3.3 Component Cooling Water System (CCWS) Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: Loads cooled by ccws.

LGSOPS0010

  • AW'

~:',:;

LMK 2017 ILT NRC JANUARY Page: 40 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 13 ID: 1454932 Points: 1.00.

Unit 1 was operating at 100% power when a LOCA occurred.

Plant conditions are as follows

  • Reactor level is -150 inches, being controlled with LPCI Which of the following describes (1) the source of water to the LPCI unit coolers and (2) where the cooling water is returningX 2. 1>1i'n1.t+e.s o.f-fe.,r' re~ leve..L reo.c.ltie.s -15?> 1'nc.J,,~~ ? ,ei,o !z.7}7 (Assume no operator action)

,here is no loss of off site power service water will still be running. The examinee must realize that service water is at a higher pressure than ESW and service water will keep the ESW supply check valve closed and continue to supply the unit coolers. On the return header the the air operated valves will realign on the ESW pump start causing the return path to realign from the cooling tower to the Spray Pond.

For the above reasons B is correct. The distractor are plausible to the examinee who does not recall that Service Water is at a higher pressure than ESW or incorrectly recalls the return flow path arrangement A Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supply the loads. When the ESW pump starts the valve line up for ESW return path swaps from the cooling towers to the spray pond.

B Correct service water is at a higher pressure and suppling the loads and ESW return path is aligned to the spray pond C Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supply the loads. When the ESW pump starts the valve line up for ESW return path swaps from the cooling towers to the spray pond.

D Incorrect plausible to the examinee who does not recall that at -129 inches LOCA signal will start the Diesel generators which will cause the ESW pumps to start. however service water is at a higher pressure so it will supplv the loads.

LMK 2017 IL T NRC JANUARY Page: 41 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 Svstem ID: 1454932 User-Defined ID: Q# 13 NEW Lesson Plan Obiective: LOT051.161 Topic: LPCI component coolinq water RO: 2.9 SRO: 2.9 KA#: 203000 A1 .09 LMK 2017 ILT NRG JANUARY Page: 42 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 1

203000 A1 .09 2.9/2.9 RHR/LPCI: Injection Mode (Plant Specific) Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) controls including:

Component cooling water LMK 2017 ILT NRC JANUARY Page: 43 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 14 ID: 1455377 Points: 1.00 The SPDS MSIV Event Indicator is showing MSIVs SHUT, with a green border.

Which of the following situations can cause this display?

A. MSIVs have received an isolation command, but are still full open.

B. MSIVs have received an isolation command, and are stroking closed.

C. MSIVs are closed manually, with an isolation command present.

D. MSIVs are closed manually, with NO isolation command present.

Answer: D Answer Explanation COLOR CODING CONVENTION:

a. MAGENTA= bad data, which means a signal is out of range, or there has been a system

~ailure.

b. RED = Alarm condition exists. One or more of the associated points have exceeded their setpoints.

K:. YELLOW = Off-normal condition exists. One or more of the associated points are approaching

~heir operating limits (e.g. Rx water level approaching scram point); an important plant event is initiated (e.g. ADS timer initiated); insufficient information available to validate a control parameter (or disagreement of data).

k:L GREEN = Safe condition exists. Normal operating parameters present.

e. CYAN = Sufficient data available to validate control parameters; indicates normal/satisfactory operation of systems/equipment.

~. DARK BLUE= System/component is INACTIVE.

g. WHITE = Active I permissive conditions exists.
h. "BLINKING" = Used to ALERT the operator of a dynamic condition which requires acknowledgment.

A Incorrect plausible to the examinee who believe the shut indication means that MSIV received an isolation command and that green indicates that they have not reposition B Incorrect plausible to examinee who believes green indication is activated when MSIV red light goes out (this will cause MSIV to indicate closed) but fails to recognize that green SPDS indication is normal operating parameters C Incorrect plausible to examinee who believe green is closed and does not apply red exceeding setpoint to the MSIV indication D Correct MSIV's where shut with no isolation signal (manually closed)

LMK 2017 ILT NRG JANUARY Page: 44 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 14 Info Question Tvoe: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 3 Difficulty: 2.00 System ID: 1455377 User-Defined ID: Q# 14 BANK Lesson Plan Objective: LGSOPS0038B.1 Topic: ERFDS Critical Plant Variables display, format 00 RO: 2.5 SRO: 2.8 KA#: 223002 A1 .03 LMK 2017 ILT NRC JANUARY Page: 45 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

223002 A1.03 2.5/2.8 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including:

SPDS/ERIS/CRIDS/GDS:

lower 5

41.5 LGSOPS00388 LMK 2017 ILT NRG JANUARY Page: 46 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 15 ID: 1455388 Points: 1.00 Unit 1 is operating at 100% power with the following conditions:

  • RT-6-041-490-1, Suppression Pool Gross Input Leak Rate Determination is being performed
  • Per the above RT, the last RT-6-041-230-1 MSRV tailpipe temperature data monitoring information is retrieved and the data for the A SRV is shown below.

ATTACHMENT 1 Page 1of1 DateJTime .!Ll~.l!!_.u_:~ -~--'.lliJ.Jz_~: 00 .:1...1 lt /Jf.. Ji.:J!.

RX Power flh)  % na  % IQO  %

SRV RX Press /1>VY PSIG IO"l1 PSlG 1(')"1'1 PSIG Tailpipe Temp l"f f A Pilot Temp Which of the following combinations of pilot valve temperature and tailpipe temperature would indicate leakage past the pilot valve seat?

Pilot valve temperature Tailpipe temperature A. 499 degrees F 140 degrees F B. 499 degrees F 150 degrees F

c. 511 degrees F 140 degrees F D. 511 degrees F 150 degrees F Answer: B
  • Answer Explanation Bis correct temperature is lower than base line temperature due to the cooling effect of the steam

~low and the pressure drop of the steam. leakage past the seat will end up in the tailpipe causing tailpipe

~emperature to rise

  • IA incorrect plausible to the examinee who recalls temperature will lower due to the cooling effect

!Of the steam flow and the pressure drop of the steam. A pilot valve temperature decrease without a rise in tailpipe

~emperature is indicative of srv external leakage into the drywell C incorrect plausible to the examinee who believes that the stagnant steam in the line would be replaced with 545 degree reactor steam but neglects the cooling effect of flow and pressure drop and does not know where pilot vale leakage goes D Incorrect but plausible for the reasons described above LMK 2017 ILT NRG JANUARY Page: 47 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 48 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 15 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 3 Difficulty: 2.00 System ID: 1455388 User-Defined ID: Q# 15 NEW Lesson Plan Objective: LGSOPS001 ffopic: Determine pilot leakage tailpipe temperature for leaking SRV RO: 3.1 SRO: 3.2 KA#: 239002 LMK 2017 ILT NRC JANUARY Page: 49 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

RO 2

239002 A2.02 3.1 /3.2 Relief/Safety Valves Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions SRV
1ift~~.i ;

2 5

LMK 2017 ILT NRC JANUARY Page: 50 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 51 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 16 ID; 1455407 Points; 1.00 A Reactor Startup is in progress with the following conditions:

  • Reactor is critical on a stable, positive period
  • Reactor power is on range 3 of the IRMs
  • The RO continues to up range the IRMs until all IRMs are on range 8 Then a malfunction in the '1A' SRM causes count rate to rise to 2X105 cps.

Given the above, which one of the following is correct regarding, (1) Any alarms received AND (2) Any required actions directed by plant procedures that would allow the startup to continue?

A. (1) SRM rod block AND upscale alarm.

(2) Bypass SRM "A".

B. 1) SRM rod block AND upscale alarm.

(2) Place SRM "A" in standby.

C. (1) Upscale alarm but NOT SRM rod block.

(2) Place SRM "A" in standby.

D. 1) Upscale alarm but NOT SRM rod block.

(2) Bypass SRM "A".

Answer: D

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 52 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO

~. Incorrect: If any SAM channel detects > 1 X 105 cps, a rod block is activated. This rod block is bypassed if:

- The mode switch is in RUN

-The associated IRM range switches are at range 8 or above Since the IRMs are on range 8, the rod block would not occur.

IAW the ARC107 H4 the directed action is to bypass the SRM.

B. Incorrect: Taking the function switch out of operate will cause an !NOP/upscale alarm.

Plausible if the candidate does not remember that taking the iunction switch out of Operate will cause an INOP trip. Additionally this action is not directed by any plant procedure.

D. Correct: Upscale alarm The IRMs on range 8 or higher. ARC-MCR-107 H4 directs bypassing the SRM.

C. Incorrect: This action is not authorized by the ARC and will generate an INOP TRIP alarm LMK 2017 ILT NRG JANUARY Page: 53 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO SRM CHANNEL "A" CONTROL ROD BLOCK SIGNALS AND BYPASSES CLOSED IF CLOSED IF OPENSONSRM IRM"A"IS IRM"A"IS "A" UPSCALE ABOVE BYPASSED ALARM RANGE7 CLOSED IF (1 X 10" CPS)

SRM "A" IS BYPASSED CLOSED IF CLOSED IF IRM"C"IS IRM"C"IS OPENSONSRM ABOVE BYPASSED "A" INOPERATIVE RANGE7 TRIP CLOSED IF CLOSED IF IRM"E" IS OPENS ON SRM "A" IRM"E"IS CLOSED IF DOWNSCALE TRIP ABOVE BYPASSED IRMs "A", 11 C 11 ,

(3 CPS)

RANGE7 11 E ,AND G 11 11 11 ARE ABOVE RANGE2 CLOSED IF CLOSED IF IRM"G" IS IRM"G"IS CLOSED ON ABOVE BYPASSED RETRACT RANGE 7 PERMIT (100 CPS)

CLOSED IF REACTOR MODE SWITCH SRM"C" (IDENTICAL TO

\

OPENS IFSRM ISIN "RUN" "A" ABOVE) DETECTOR "A" IS NOT FULLY INSERTED CONTROL ROD WITHDRAWAL ROD BLOCK RELAY BLOCK OCCURS WHEN ROD BLOCK RELAY DE-ENERGIZES

~: all control rod withdrawal block functions are bypassed if:

SRM INOPERATIVE TRIP

  • The associated SRM channel is bypassed

- Internal Module Unplugged

  • All four IRM channels (in the same RPS

- Channel Mode Switch not in "OPERATE" trip system) are on Range 8 or above

- Low detector voltage

  • The Reactor Mode Switch is in the "RUN' position LMK 2017 ILT NRG JANUARY Page: 54 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 16 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.50 System ID: 1455407 User-Defined ID: Q# 16 MODIFIED Lesson Plan Objective: LGSOPS0074.6 Topic: Predict Response to SRM Count rate dropping RO: 3.3 SRO: 3.5 KA#: 215004 A2.05 LMK 2017 ILT NRC JANUARY Page: 55 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

Source Range Monitor (SRM) System Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM)

SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic o eration of detectors/s stem hi her 41.5,41.6,41.7 ARC-107-G4 ARC-107-14 Modified NRC bank see revision histo Modified LMK 2017 ILT NRC JANUARY Page: 56 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 57 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO 17 ID: 1455428 Points: 1.00 Unit 1 plant conditions are as follows:

  • Reactor STARTUP is in progress
  • Reactor power is 20%
  • 1B RPS/UPS, "Inverter AC Feed Switch" is aligned to Primary Alternate Supply During the startup the following alarms on MCA PNL 122 annunciate:
  • 18 RPS & UPS STATIC INVERTER TROUBLE
  • 1DB-2 250 VDC MCC UNDERVOLT AGE All RPS white status lights are lit.

WHICH ONE of the following identifies the source currently providing power to "1 B" RPS?

A. 480VAC Non-Safeguard NQI bypassing the RPS/UPS inverter B. 480VAC Non-Safeguard bypassing the RPS/UPS inverter C. TSC UPS Inverter NQI bypassing the RPS/UPS Inverter D. TSC UPS Inverter bypassing the RPS/UPS Inverter Answer: C

/Answer Explanation LMK 2017 ILT NRC JANUARY Page: 58 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO DISTRACTOR 480VAC Non-Safeguard not bypassing the RPS/UPS Inverter - This is incorrect answer because the DC supply is the normal preferred source from 1DB-1 250 VDC MCC.

The primary alternate supply is from the TSC UPS Inverter (1440-C-F) and the Secondary Alternate supply is from Non Safeguard 480 VAC MCC 124A-G-F for the 1B Inverter. Per the conditions stated, The primary alternate is selected on the Inverter AC Feed Selector Switch and the RPS inverter static switch will auto swap to the selected supply which in this case is the primary alternate supply. In this stated condition the AC supply is not bypassing the RPS inverter, but is going through the inverter.

ANSWER TSC UPS Inverter not bypassing the RPS/UPS Inverter-This answer is correct because the conditions do not state that the Inverter is bypassed. The conditions also state that the primary Alternate Supply is selected which is the TSC MCC supply. The inverter can be manually bypassed by procedure if the inverter fails to auto swap utilizing the maintenance BYPASS switch.

DISTRACTOR TSC UPS Inverter bypassing the RPS/UPS Inverter-This answer is incorrect because the conditions do not state that the Inverter is bypassed. The conditions also state that the Secondary Alternate Supply is selected which is not the TSC MCC supply. The inverter can be manually bypassed by procedure if the inverter fails to auto swap utilizing the maintenance BYPASS switch.

DISTRACTOR 480VAC Non-Safeguard bypassing the RPS/UPS Inverter - This answer is partially correct by identifying the correct Secondary Alternate AC supply but is incorrect because the inverter is not Manually bypassed using the maintenance BYPASS switch.

LMK 2017 ILT NRG JANUARY Page: 59 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 1455428 User-Defined ID: 0# 17 MODIFIED Lesson Plan Objective: LGSOPS0071 .2A Topic: RPS/UPS static inverter RO: 2.8 SRO: 3.1 KA#: 262002 LMK 2017 ILT NRG JANUARY Page: 60 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

262002 A3.01 2.8/3.1 Uninterruptable Power Supply (A.C./D.C.) Ability to monitor automatic operations of the UNINTERRUPTABLE POWER SUPPLY (A.C.ID.C.) including:

Transfer from preferred to alternate source lower 6

41.7 201 O lgs NRC exam 995089 bu cert modified 201 O lgs NRC exam 2010 lgs NRC exam LMK 2017 ILT NRC JANUARY Page: 61 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO 18 10:1455088 Points: 1.00 Unit 2 is operating at 100% power when a loss of feedwater occurs.

RPV water level drops to -43" before recovering to +35".

RO Scram actions are complete and ALL automatic scram signals are either clear or bypassed.

The RO places the RPS RESET switch to 'GP 1/4' then to 'GP 2/3' positions:

- N.o. other operator actions are taken WHICH ONE of the following identifies the status of RPS .and. the SCRAM air header?

A. Reset Pressurizing B. Reset NOT Pressurizing

c. NOT reset Pressurizing D. NOT reset NOT Pressurizing Answer: B Answer Explanation Because RPV level dropped below -38", ARI also initiated. Although the RO has successfully reset RPS, the "no other operator actions" statement means that the RO has not reset ARI.

Thus, RPS is reset, but the HCU Scram Valves (Inlet/Outlet) are still open; i.e., until ARI is reset,

~he ARI Valves remain open, blocking/venting the scram air header, with no air to the actuators needed to re-close the Scram Valves.

A Incorrect plausible to examinee who does not recognize that ARI has not been reset so the scam air header will not pressurize B Correct RPS will reset but the scram air header will not pressurize C incorrect plausible to the examinee who believes placing the RPS reset switch to 'GP 1/4' and 'GP 2/3 positions will allow the air header to pressurize independent of RPS reset D Incorrect plausible to the examinee who believe ARI must be reset in order to reset RPS LMK 2017 ILT NRC JANUARY Page: 62 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1455088 User-Defined ID: Q# 18 BANK Lesson Plan Objective: LLOT0046.4G

~ctions Required to Reset a Scram that included RPV level Topic:

dropping to -38" RO: 3.6 SRO: 3.6 KA#: 212000 A.07 LMK 2017 ILT NRC JANUARY Page: 63 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

RO 2

212000 A3.07 3.6/3.6 212000 Reactor Protection System Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including: SCRAM air header bank1244449,553971 minor revision to match KA LMK 2017 ILT NRC JANUARY Page: 64 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 19 ID: 1455570 Points: 1.00 Unit 2 is operating at 85% power with both Recirc Pumps in service.

l&C discovers an error in the recently completed 'B' Recirc Loop (Drive) Flow surveillance:

- Indicated 'B' Recirc Loop Flow is LOWER than aci.u.al. flow As a result of this discovery, which of the following APRM, Simulated Thermal Power (STP) trip setpoints are affected, (if any)?

A. 1,2,3, and 4 B. 1 and 3 only C. 2 and 4 only D. No APRM STP trip setpoints are affected Answer: A lAnswer Explanation IA is correct the examinee must recall that A and B recirc loop flows are summed and used by all IAPRM STP and displayed on the ODA's B Incorrect plausible to the examinee who believes B recirc loop only provides input to 2 of 4 iAPRM STP indication on the ODA C incorrect plausible to the examinee who believes B recirc loop only provides input to 2 of 4 IAPRM STP indication on the ODA D Incorrect plausible to the examinee who does not recall how APRM STP is calculated LMK 2017 ILT NRC JANUARY Page: 65 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 19 Info Question Type: Multiple Choice Status: Active

~lwavs select on test? No

~uthorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1455570 User-Defined ID: Q# 19 NEW Lesson Plan Objective: LGSOPS00748.138 Topic: ODA setpoint shange in core flow RO: 3.6 SRO: 3.8 KA#: 215005 A4.06 LMK 2017 ILT NRG JANUARY Page: 66 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 1

215005 A4.06 3.6/3.8 Average Power Range Monitor/Local Power Range Monitor System Ability to manually operate and/or monitor in the control room:

Verification of proper functionin o erabilit 4

0 LMK 2017 ILT NRC JANUARY Page: 67 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 20 ID: 1455452 Points: 1.00 Unit 1 is in OPCON 1 with the following conditions:

  • 1B SLC pump is deenergized and blocked for repair
  • Division II D.C. has experienced a fault and is deenergized
  • A feedwater transient caused reactor water level to drop to +5 inches before being restored to +

35inches

  • All RO SCRAM actions have been completed per OT-200 attachment # 1
  • Reactor power remains at 100%

WHICH ONE of the following identifies the status of RWCU System isolation valves 3 minutes later?

INBOARD ISOLATION VALVE OUTBOARD ISOLATION VALVE HV-44-1 EOOl HV-44-1 F004 A. Open Open B. Closed Closed C. Open Closed D. Closed Open Answer: D

!Answer Explanation A Incorrect plausible to the examinee who recalls that without Div II DC that Div II ARCS is INOP but incorrectly believes that both divisions of ARCS are required to close either RWCU isolation valve.

B Incorrect plausible to the examinee who who does not recall that Div I ARCS uses B SBLC pp logic to close the HV-44-1 F004 C Incorrect plausible to the examine who reverse Div I and Div II ARCS actions D Correct although DIV 1 ARCS normally closes both RWCU isol valves it does so through the SLC pump logic. with the B SLC pump deenergized the outboard valve will not close.

The distractors are plausible to the examinee who does not properly recall how SLC in conjunction with ARCS work to isolate RWCU.

LMK 2017 ILT NRC JANUARY Page: 68 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 20 Info Question T e: Multi le Choice Status: Active No No 1.00 lete: 4 3.00 1455452 Q#20 NEW LGSOPS0048.08A SLC RWCU isolation 3.9 3.9 211000 A4.06 3.9/3.9 Standby Liquid Control System Ability to manually operate and/or monitor in the control room: RWCU

  • Rev;.

LMK 2017 ILT NRG JANUARY Page: 69 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 70 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 21 ID: 1455676 Points: 1.00 Plant conditions are as follows;

  • Unit 1 is at 50% power, shutting down due to a fuel failure.
  • Unit 2 is in OPCON 5 with refueling activities in progress with secondary containment set on the refuel floor.
  • An unisolable steam leak develops in the UNIT 1 reactor enclosure.
  • Unit 1 reactor enclosure radiation levels rise to 2.3 mR/hr Regarding the reactor enclosure and the refuel floor, which of the following describes the Zones SBGT will maintain at a negative pressure and the reason for the initiation of SBGT?

Zones SBGT will maintain negative Reason for SBGT initiation A. Unit 1 reactor enclosure ONLY Limit iodine and particulate concentration in gases, prior to discharge B. Unit 1 reactor enclosure ONLY Limit particulate concentration in gases ONLY, prior to discharge C. Unit 1 reactor enclosure and Refuel floor Limit iodine and particulate concentration in gases, prior to discharge D. Unit 1 reactor enclosure and Refuel floor Limit particulate concentration in gases ONLY, prior to discharge Answer: A Answer Explanation A Correct Reactor HVAC isolates at 1.35 mr/h.although refuel floor containment is set, only when Zones are crosstied will a reactor HVAC isolation also isolate the refuel floor. The purpose of the SBGT filters per the Design basis document L-S-32 is The SGTS/RERS filters iodine and particulate concentrations in gases potentially present within the Secondary Containment prior to discharge to the environment via the North Stack.

B Incorrect Limit particulate only is incorrect but plausible to the examinee who does not recall the purpose of the charcoal filters C incorrect plausible to the examinee who recognizes that the radiation levels are above the refuel floor setpoint, but either does not recall the crosstie logic or believe that hi reactor radiation will isolate the refuel floor as long as the zone is established D incorrect plausible to the examinee who recognizes that the radiation levels are above the refuel floor setpoint, but either does not recall the crosstie logic or believe that hi reactor radiation will isolate the refuel floor as long as the zone is established and does not recall the purpose of the charcoal filters LMK 2017 ILT NRC JANUARY Page: 71 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 21 Info Question T e: Multi le Choice Status: Active No No 1.00 3

3.00 1455676 Q#21NEW LOT0200.01 C SBGT initiation 3.9 4.0 261000 2.1.27 Comments:

RO 2

261000 2.1.27 3.9/4.0 Standby Gas Treatment System Knowledge of system ur ose and/or function.

LMK 2017 ILT NRC JANUARY Page: 72 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15*01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 73 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 22 10:1649592 Points: 1.00 Unit 1 is operating at 100% power when emergent maintenance on the SLC tank Main Control Room level indication is required.

The level indication is taken out of service for maintenance by isolating and venting the air.

WHICH ONE of the following describes the SLC alarm that will be received and the availability of the SLC pumps in the above configuration?

ALARM SLC Pump Availability A. High level available B. Low level NOT available

c. High level NOT available D. Low level available Answer: D Answer Explanation

!To answer the question the candidate must understand the operation of the SLC tank bubbler and how the bubbler will fail when air is removed. With air removed from the bubbler, level indication

/Will fail low. Also the candidate must know that the bubbler is for indication only and has no effect on the the operation of the SLC pumps and SLC system operability.

Higher back pressure equals higher tank level. with air isolated to the bubbler tank level indication in the MCR will read O IA Incorrect level will indicate lower B incorrect the pumps trip on low tank level but not from the MCR indication that uses a bubbler air system for indication C Incorrect With air removed from the bubbler, level indication will fail low. the pumps trip on low tank level but not from the MCR indication that uses a bubbler air system for indication D Correct LMK 2017 ILT NRG JANUARY Page: 74 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 22 Info Question Type: Multiple Choice Status: Active

~lways select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 6 Difficulty: 2.00 System ID: 1649592 User-Defined ID: Q#22 NEW Lesson Plan Objective: LLOR1102E Topic: SLC operability RO: 3.1 SRO: 4.2 KA#: 211000 2.2.36 LMK 2017 ILT NRG JANUARY Page: 75 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 1

211000 2.2.36 3.1/4.2 Standby Liquid Control System Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for o erations.

low 41.10 22 Bank 906982 modified 211000A1.10 LMK 2017 ILT NRC JANUARY Page: 76 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 23 ID: 1601488

  • Points: 1.00 Unit 1 is in OPCON 3 with the following
  • Reactor pressure is 500 psi
  • Drywall purge is in progress with the OA Drywall Purge fan through the OA SBGT filter
  • Maintenance has entered the drywall Which of the following describes the maximum allowable suppression pool to drywall differential pressure and what is the basis for this requirement?

Differential pressure Basis tor this limit A. 0.5 PSID To prevent suppression pool nitrogen from entering the drywall B. 0.5 PSID To prevent exceeding the maximum drywall floor differential design pressure C. 5.0 PSID To prevent suppression pool nitrogen from entering the drywall D. 5.0 PSID To prevent exceeding the maximum drywall floor differential design pressure Answer: A

!Answer Explanation A Correct per warning in S57.5.B The Primary Containment Vacuum Relief Valves are designed to lift at 0.5 psid to relieve Suppression Pool pressure to the Drywall. For personnel access to the Drywall, with the Suppression Pool inerted with N2, Suppression Pool/Drywell differential pressure must be maintained below 0.5 psid to prevent Suppression Pool inerted atmosphere from flooding the Drywell.

B Incorrect 5.0 is the containment external to internal limit plausible to the examinee who contuses internal to external pressure with OW to supp pool.

C Incorrect plausible to the examinee who confuses internal to external pressure with OW to supp pool. bases D Incorrect 5.0 is the containment external to internal limit LMK 2017 ILT NRC JANUARY Page: 77 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1601488 User-Defined ID: Q#23 NEW Lesson Plan Objective: LOT0060.4D Topic: ourge containment DP RO: 2.9 SRO: 3.2 KA#: 261000 A4.05 LMK 2017 ILT NRG JANUARY Page: 78 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 261000 A4.05 2.9/3.2 Standby Gas Treatment System Ability to manually operate and/or monitor in the control room: Drywell to suppression chamber/torus

,,,,""",1 differential ressure: Mark-1,II LMK 2017 ILT NRC JANUARY Page: 79 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 80 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 24 ID: 1455288 Points: 1.00 Plant conditions are as follows;

  • Control enclosure HVAC is in service with the A Safeguard Battery room exhaust fan OAV124 in service
  • Unit 1 Safeguard Battery room exhaust fan supply damper HD-78-90B has failed closed Which of the following describes the plant response and the reason for this response?

PLANT RESPONSE REASON FOR THIS RESPONSE A. B Safeguard Battery room exhaust fan Maintain battery room temperature OBV124 Starts B. B Safeguard Battery room exhaust fan Reduce Hydrogen buildup OBV124 Starts

c. Connecting damper HD-78-092B Unit 1 Maintain battery room temperature battery room to Emergency Switchgear and Battery Room Supply Air will open D. Connecting damper HD-78-092B Unit 1 Reduce Hydrogen buildup battery room to Emergency Switchgear and Battery Room Supply Air will open Answer: D

!Allswer Explanation LMK 2017 ILT NRG JANUARY Page: 81 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Lesson plan LGSOPS0078

  • if both battery exhaust fans trip, or any of the battery exhaust fan inlet dampers are less than full open, dampers will open connecting the battery room exhaust duct to the emergency switchgear and battery room supply fan suction. This ensures hydrogen does not accumulate in the battery rooms.

UFSAR 9.5-13 irhe exhaust ducts from the Class 1E battery rooms are provided with safety-grade isolation dampers in both branches of duct-work leading to the battery room exhaust fans and to the emergency switchgear and battery room supply air fan cabinets. The dampers in the duct-work leading to the exhaust fans are provided with safety-related position switches which activate the dampers in the duct-work leading to the supply air fan cabinets. In the event of closure of any of

~he dampers leading to the exhaust fans, the dampers in the duct-work from the battery rooms of

~he affected reactor unit and leading to the air supply fan cabinets will automatically open, thereby establishing recirculation air flow through the affected battery rooms. This re-establishment prevents accumulation of hydrogen above safe limits.

IA is incorrect plausible to the examinee who does not recall that all battery rooms tie into a common header there by thinking an A/C damper closure would start the B tan. also the examinee does not recall the bases for reciculation.

B is incorrect plausible to the examinee who does not recall that all battery rooms tie into a common header there by thinking an A/C damper closure would start the B fan.

C Incorrect plausible to the examinee who does not recall the bases for reciculation.

D correct for the reasons stated above.

LMK 2017 ILT NRC JANUARY Page: 82 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 24 Info k:luestion Tvpe: Multiple Choice Status: Active IAlwavs select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 Svstem ID: 1455288 User-Defined ID: 0#24 NEW Lesson Plan Objective: LGSOPS0078.1 C Topic: Battery H2 buildup RO: 2.6 SRO: 2.9 KA#: 263000 K5.01 LMK 2017 ILT NRC JANUARY Page: 83 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 263000 K5.01 2.6/2.9 D.C. Electrical Distribution Knowledge of the operational implications of the following concepts as they apply to D.C. ELECTRICAL DISTRIBUTION :

Hydrogen generation during batter char in lower 6

41.5 LMK 2017 ILT NRG JANUARY Page: 84 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 25 ID: 1455268'. Points: 1.00:

Unit 1 plant conditions are as follows:

HPCI is in service for RPV pressure control (CST to CST)

FIC-055-1 R600 "HPCI FLOW CONTROL VALVE AUTO/MAN switch" is in AUTO HV-55-1 FOOS "HPCI, Test Loop Shutoff" is throttled to maintain pump discharge pressure 150 psig over Reactor pressure.

The RO throttles HV-55-1 FOOS in the closed direction for one second WHICH ONE of the following describes HPCI turbine speed and flow rate five minutes later, as compared to conditions prior to throttling HV-55-1 FOOS?

HPCI Turbine Speed Flow rate A. No change Higher B. Higher No change

c. Lower No change D. No change Lower Answer: B Answer Explanation B Correct: Higher/ No change: With Flow Controller in AUTO, system flow is maintained constant. IF FOOS is throttled closed HPCI speed will need to increase to maintain the same flow A Incorrect: No change/Higher: plausible to the examinee who believe speed is maintained constant and that flow will increase with a higher DP across the valve C Incorrect: Lower/No change: plausible to the examinee who believe throttling the 1FOOS will lower pump speed D Incorrect: No Change/Lower: Flow Controller is in Auto, maintaining system flow constant.

plausible to the examinee who believes AUTO maintains speed constant LMK 2017 ILT NRC JANUARY Page: 85 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 25 Info Question Type: Multiple Choice Status: Active

~lwavs select on test? No

~uthorized for practice? No Points: 1.00

!Time to Complete: 3 Difficulty: 2.50 System ID: 1455268 User-Defined ID: Q# 25 BANK Lesson Plan Objective: LOT-340.12 HPCI Unit 1 plant conditions are as follows: u HPCI is in service for

!Topic:

RPV pressure control (CST to CST) L RO: 3.8 SRO: 3.7 KA#: 206000 A1 .06 LMK 2017 ILT NRC JANUARY Page: 86 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:

RO 2

1 206000A1.06 3.8/3.7 High Pressure Coolant Injection System Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including:

S stem flow: BWR-2,3,4 S55.1.D, note Ste 4.4.3 LMK 2017 ILT NRC JANUARY Page: 87 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 26 ID: 1455689 Points: 1.00 Unit 2 is operating normally at 80% power when a LOCA occurs.

- A LOCA signal is generated for all four divisions of ECCS WHICH ONE of the following describes the RHR pump starting sequence?

A. All Unit 2 RHR pumps will start immediately

8. All Unit 2 RHR pumps will start after a 7 second time delay C. "2A" and "28" RHR pumps start immediately, "2C" and "20" RHR pumps start after a 5 second time delay
0. "2C" and "20" RHR pumps start immediately, "2A" and "28" RHR pumps start after a 5 second time delay Answer: 0 Answer Explanation The RHR pumps start on a LOCA signal a) With offsite power pumps C&O start immediately and A&8 start 5 seconds later.

b) Without off-site power each pump starts when the associated diesel output breaker shuts.

A Incorrect, plausible to the examinee who confuses sequence with RHR pump start on a loss of offsite power 8 Incorrect, plausible to the examinee who confuses sequence with Core Spray initiation on a loss of off site power C Incorrect plausible to the examinee who reverses the dedicated LPCI pp LMK 2017 ILT NRG JANUARY Page: 88 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 26 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 5 Difficulty: 2.00 System ID: 1455689 User-Defined ID: Q# 26 BANK Lesson Plan Objective: LOT0051.07 offsite power is available - RPV pressure is 360 psig - drywell rropic:

pressure reaches 1.68 psig describ RO: 4.0 SRO: 3.9 KA#: 203000 A3.02 LMK 2017 ILT NRC JANUARY Page: 89 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

RO 2

203000 A3.02 4.0/3.9 RHR/LPCI: Injection Mode (Plant Specific) Ability to monitor automatic operations of the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) including:

Pum start 2

41.7 E11-1040 J!:l~'

    • ~"'

bank 554543 bank 554543 bank 554543 Lesson Plan: LOR-9305-B, Obj. 2 LLOR0101 C, Obj. 4 KIA Catalog: 203000 K4.01 4.2/4.2 JT A 2030020101 LMK 2017 ILT NRC JANUARY Page: 90 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 27 ID: 1478356 Points: 1.QQ, Unit 1 is operating at 100% power with the following:

  • 1D01 TURBINE ENCLOSURE 250V DC MOTOR CONTROL CENTER (10-D125} has been deenergized for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> A malfunction on the main turbine lube oil system results in the following:
  • Main Shaft Oil Pump (MSOP) discharge pressure of 150 psig
  • Turning gear oil pump (TGOP) discharge pressure of 10 psig WHICH ONE of the following identifies the status of the Turning Gear Oil Pump (TGOP) and Emergency Bearing Oil Pump (EBOP)?

I.GQE .EBQE A. Running Running B. Running Not Running

c. Not Running Not Running D. Not Running Running Answer: B Answer Explanation EBOP is powered form non safeguard DC.

ITGOP is powered from D114-G-D TGOP Start on MSOP discharge pressure < 190 OR bearing header pressure <15 psig EBOP Start on MSOP discharge pressure < 180 AND TGOP discharge pressure < 12 psig A Incorrect plausible to examinee who belives EBOP is powered from safeguard DC B Correct TGOP has a start signal as does EBOP however EBOP power supply is lost C Incorrect plausible to the examinee who does not recall the TGOP start setpoints D Incorrect plausible to the examinee who reverses the power supplies for TGOP and EBOP LMK 2017 ILT NRG JANUARY Page: 91 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 27 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficultv: 2.00 Svstem ID: 1478356 User-Defined ID: Q#27 NEW Lesson Plan Objective: LGSOPS0019.IL4 Topic: Main turb oil pp power RO: 2.7 SRO: 2.7 KA#: 245000 K1 .09 LMK 2017 ILT NRG JANUARY Page: 92 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 2

245000 K1 .09 2.7/2.7 Main Turbine Generator and Auxiliary Systems Knowledge of the physical connections and/or causeeffect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the following: D. C . electrical distribution 41.4 LGSOPS0019 2 LMK 2017 ILT NRG JANUARY Page: 93 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 28 . 10: 1455690 Points: 1.00 Unit 1 is in OPCON 1, with the following:

- '1 A' Recirc Pump removed from service due to seal failure

- '1 B' Recirc Pump operating at 980 rpm with the following failed/bypassed cells on '1 B' ASD:

- Two (2) Phase 'A' cells

- One (1) Phase 'B' cell WHICH ONE of the following combinations of additional cell failures would require operators to insert a manual scram?

A Phase B Phase C Phase A. 0 0 3 B. 0 2

c. 2 1 0 D.

Answer: c Answer Explanation See 843.1.F, Attachment 2, page 16 of 65, FRR # 2.1.2 ... the '1 B' ASD will trip if EITHER all 4 cells fail on a given Phase, OR a total of more than 6 cells fail. Therefore, the two additional Phase 'A' cell failures will trip the '1 B' ASD. With '1 A' Recirc Pump already secured, a trip of '1 B' iwill require a manual scram per OT-112, step 3.1.

LMK 2017 ILT NRG JANUARY Page: 94 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 28 Info Question Tvpe: Multiple Choice Status: Active

!Always select on test? No

!Authorized for practice? No Points: 1.00 rnme to Complete: 3 Difficulty: 4.00 System ID: 1455690 User-Defined ID: Q# 28 BANK Lesson Plan Objective: LGSOPS0043B.2C Topic: ASD Response to Cell Bypass RO: 3.2 SRO: 3.2 KA#: 202001 K2.01 LMK 2017 ILT NRC JANUARY Page: 95 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

202001 K2.01 3.2/3.2 Recirculation System Knowledge of electrical power supplies to the following: Recirculation um s: Plant-S ecific Rev 3

  1. t ..

bank 966665 bank 966665 bank 966665 LMK 2017 ILT NRG JANUARY Page: 96 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 ILT NRC JANUARY Page: 97 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 29 10: 1535797 Points: 1.00 Unit 1 initial plant conditions are as follows:

  • SAMPS are being implemented
  • Reactor Level is -290" down slow with no injection
  • Reactor Pressure is 1175 psig steady (no SRV pneumatics available)

RPV pressure reduction has been ordered by performing section 4.7 of T-260, "RPV Venting Through HPCI Steam Line."

During the depressurization, HPCI Pump Room pressure peaked at 3 psig.

WHICH ONE of the following correctly identifies whether the release is (a) Scrubbed and/or Filtered and (b) the release path?

Scrubbed and/or Filtered Release Path A. Yes Monitored Elevated B. Yes Unmonitored Ground Level C. No Monitored Elevated D. No Unmonitored Ground Level Answer: D

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 98 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Section 4.7 of T-260, RPV Venting Through HPCI Steam Line contains the following Cautions:

~- It is highly probable that the vent path in Section 4.7 will flood the Reactor Enclosure with nuclear steam AND reactor source term.

3. The flooding of the Reactor Enclosure with Nuclear Steam will cause severe Reactor Enclosure environmental conditions which could render ECCS

!AND other equipment inoperable, along with the potential of losing Reactor Enclosure electrical power.

rThis in addition to the Stem stating that the pump room peaking at 3 psig (well above the 5 inches of water column for the Steam Flooding Dampers and the 0.5 psig for the blowout panes) the candidate should determine that there is an unscrubbed, unfiltered ground level release.

A is plausible if the candidate mistakenly believes that steam is scrubbed through the suppression pool water or the SBGTS filters and is released through the North Stack via SBGTS.

B is plausible if the candidate mistakenly believes that the steam is scrubbed through the suppression pool prior to going out the blowout panel C is plausible if the candidate mistakenly believes that the steam exits the plant via Reactor Enclosure HVAC out the South Stack.

D is correct The RO candidate is responsible to know that the pump room peaking at 3 psig (well above the 5 inches of water column for the Steam Flooding Dampers and the 0.5 psig for the blowout panes) the RO candidate should determine that there is an unscrubbed (venting HPCI steam line will not go through the suppression pool), unfiltered ground level release (pressurizing HPCI pump room will cause steam flooding dampers to close isolating the room from reactor HVAC as the room pressurizes blowout pannels will open causing an unfiltered/ground level release.

LMK 2017 ILT NRG JANUARY Page: 99 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 29 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rrime to Complete: 3 Difficulty: 3.00 System ID: 1535797 User-Defined ID: Q# 29 BANK Lesson Plan Objective: LGSOPS0076B.9 Given plant conditions and applicable T-260 section determine lropic:

unmonitored release path RO: 4.0 SRO: 4.4 KA#: 290001 K3.01 LMK 2017 ILT NRC JANUARY Page: 100 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 2

290001 K3.01 4.0/4.4 Secondary Containment Knowledge of the effect that a loss or malfunction of the SECONDARY CONTAINMENT will have on following: tOff-site radioactive release rates 41.7 LGSOPS0076B.

bank 1247968 bank 1247968 bank 1247968 LMK 2017 ILT NRC JANUARY Page: 101 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 30 ID: 1601388 Points: 1.00 Unit 1 plant conditions are as follows:

Reactor power is 100%

30 scfm Offgas effluent flow Offgas dew point monitor is reading 40°F The Charcoal Vault Refrigeration Compressors trip and cannot be restarted.

WHICH ONE of the following identifies the change in the activity of the Offgas effluent, if any and the monitoring location?

Change in Activity Monitoring Location A. Rises North Stack B. Rises South Stack

c. Remains the same North Stack D. Remains the same South Stack Answer: A Answer Explanation he charcoal delays gaseous xenon, krypton, and their daughter products along with biologically significant isotopes Sr-89, Sr-90, Ba-140 and Cs-137 in the Offgas stream through adsorption.

his allows the radioactive isotopes to decay to levels acceptable for release to the atmosphere.

~.l!I.Si'J..2!'-"".......,....._."-'H....... is incorrect. Release rates will be higher and the release will be through the South Stack. This distractor is plausible based on the misconceptions described in the first 2 distractors.

LMK 2017 ILT NRC JANUARY Page: 102 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 30 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 2.50 System ID: 1601388 User-Defined ID: 0#30 BANK Lesson Plan Objective: LOT0510.06 Given the following conditions: - Reactor power is 100% - 30 lfopic:

scfm Offqas effluent flow - Offqas de RO: 2.7 SRO: 2.9 KA#: 271000 LMK 2017 ILT NRC JANUARY Page: 103 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

RO 2

2 271000 K4.06 Offgas System Knowledge of OFFGAS SYSTEM design feature(s) and/or interlocks which provide for the following: Decay of fission product gases to particulate dau hters bank 833329 bank 833329 bank 833329 LMK 2017 ILT NRG JANUARY Page: 104 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 31 10:1601440 Points: 1.00 Unit 1 is operating at 100% power when the following occurs:

- HIGH-HIGH level condition in the '1A' Feedwater Heater (FWH)

WHICH ONE of the following describes the response of APRMs and the resultant feedwater temperature at the inlet to the reactor feed pump ? (assume no operator action)

APBM Beadings Reactor feed pump inlet temperature A. Lower Lower B. Lower Higher

c. Higher Higher D. Higher Lower Answer: D Answer Explanation Upon a high high FWH isolation on the 1A FWH, HV-005-*02 and HV-005-*01 close stopping all FW flow through the 1A low pressure string. The flow through the 1B and 1C FW String combines and is equally distributed to the 1A, 1B, and 1C Feed pumps. The FW temperature at the inlet of the BFPT is lower than normal resulting in a an overall temperature decrease at the BFP inlet reactor power will increase by approximately 1.5%

A Incorrect plausible to the examinee who does not recall that the effect of the loss of extraction steam has a greater effect than the increase in flow through the remaining heat exchangers B Incorrect plausible to the examine who believe a loss of the "A" low pressure heater string will cause flow to the A BFP to lower resulting in a recirc runback and at the effect of the loss of extraction steam has a greater effect than the increase in flow through the remaining heat exchangers C Incorrect plausible to the examine the loss of extraction steam will override the effect of increased flow through the remaining strings and reverses the reactivity effect D Correct feed water temp. entering the 6th feedwater heaters is lower so feed water to the vessel temp is lower causinq a power increase LMK 2017 ILT NRC JANUARY Page: 105 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 31 Info Question Type: Multiple Choice Status: Active Always select on test? No

~uthorized for practice? No Points: 1.00 lrime to Complete: 3 Difficulty: 2.00 System ID: 1601440 User-Defined ID: Q# 31 BANK Lesson Plan Obiective: LOT-0530, OBJ. #3 A "High-High" level condition occurs in the "1 A" feedwater heater lropic:

'FWH) - Any automatic actions th RO: 2.7 SRO: 2.7 KA#: 256000 K5.08 LMK 2017 ILT NRC JANUARY Page: 106 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 2

256000 K5.08 2.7/2.7 Reactor Condensate System Knowledge of the operational implications of the following concepts as they apply to REACTOR CONDENSATE SYSTEM:

Heat removal (transfer) mechanisms LMK 2017 ILT NRC JANUARY Page: 107 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 32 10:1601405 Points: 1.00 Both units are operating at 100% power Which of the following describes if the power supply to the Motor Driven Fire Pump is safeguard power or Non-safeguard power, and if a Tech Requirements Manual (TRM) entry is required for a loss of power to the Motor Driven Fire Pump ?

Safeguard or non-safeguard TAM entry BeQuired A. Safeguard No B. Safeguard Yes

c. Non-safeguard Yes D. Non-safeguard No Answer: c Answer Explanation Motor driven fire pump MDFP A Incorrect plausible to examinee who belives fire protection pump are safeguard and belives loss of 1 of 3 pumps Motor diesel and backup diesel would not require TAM entry B Incorrect plausible to examinee who belivesfire protection pump are safeguard C Correct MDFP is powered for 214D (non-safeguard) and loss of 1 pump does require TAM entry (7day)

D Incorrect plausible to examinee who belive loss of 1 of 3 pumps Motor diesel and backup diesel would not require TAM entry LMK 2017 ILT NRC JANUARY Page: 108 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 32 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1601405 User-Defined ID: 0#32 NEW Lesson Plan Objective: LGSOPS0022. 7H Topic: Loss of pwr to MDFP RO: 3.1 SRO: 3.1 KA#: 286000 K6.01 LMK 2017 ILT NRC JANUARY Page: 109 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

286000K6.01 3.1 /3.1 Fire Protection System Knowledge of the effect that a loss or malfunction of the following will have on the FIRE PROTECTION SYSTEM AC. electrical distribution: Plant-S ecific lower 8

41.7 Rev.. 3 I:; 4 LMK 2017 ILT NRG JANUARY Page: 110 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 33 10:1455176 Points: 1.00.

Unit 2 is operating at 100% power with the following conditions:

- Suppression pool temperature is 93 degrees

- "2B" AHR loop is operating in Suppression Pool Cooling

- "OB" RHRSW pump is providing cooling water to the "2B" AHR heat exchanger A Division 2 LOCA signal is inadvertently generated. The PRO reopens HV-051-2F024B "SUPP POOL CLG B". No other operator actions are taken.

WHICH ONE of the following describes the change in suppression pool heat removal (if any) over the next 5 minutes and the reason for the response?

A. Less heat removal due to OB RHRSW pump trip B. Less heat removal due to 2B AHR heat exchanger being bypassed C. Less heat removal due to 2B AHR pump trip D. Heat removal rate is unchanged, system remains in service Answer: B Answer Explanation IWith the Div 2 LOCA signal the F048 Heat Exchanger Bypass valve would get an open signal for lthree minutes along with the F024, test valve closing. Therefore, the heat exchanger is bypassed and Suppression Pool temperature will increase.

A Incorrect. Less heat removal, but the RHRSW pump will not trip. Plausible to the examinee who either does not recall the RHRSW rad monitors are powered from unit 1 and RHRSW will not trip on rad monitor down scale. or does not recall that B RHRSW pump is powered from 012 B Correct. less heat removal due to the HTX bypass valve opening C Incorrect. Plausible to the examinee who does not recall that the running AHR pump will not trip on a LOCA signal as the Core Spray pumps do D Incorrect. Plausible to the examinee who does not recall that the heat exchanger bypass valve will automatically open on a LOCA siqnal LMK 2017 ILT NRG JANUARY Page: 111 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 33 Info Question Type: Multiple Choice Status: Active

!Always select on test? No

!Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.50 System ID: 1455176 User-Defined ID: Q# 33 BANK Lesson Plan Objective: LOT0051.08 Topic: pool temp RHR in pool cooling loca occurs RO: 4.0 SRO: 4.0 KA#: 219000 A 1.01 LMK 2017 ILT NRC JANUARY Page: 112 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

RO 2

2 219000A1.01 4.0/4.0 RHR/LPCI:

Torus/Suppression Pool Cooling Mode Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE n/a LMK 2017 ILT NRC JANUARY Page: 113of374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 34 ID: 1649532 Points: 1.00 Unit 1 is operating at 100% power.

  • Control rod 30-31 SCRAMS Which of the following describes the indications on the four rod display, and the action required (if any) to run a P-1?

Four rod display indication Action reciuired to run a P-1 A. Blank, Blank Wait for rod to settle .QNLY B. Blank, Blank Isolate rod and wait for it to settle C. 0,0 No action required D. .... , -- Isolate rod and wait for it to settle Answer: B

~nswer Explanation When a control rod SCRAMS it goes to the overtravel in position (beyond RPIS position switches

~or a 00 position note in ON-104 page 8 states Until a control rod settles to a known position, i.e. other than inserted to beyond 00, a P-1 cannot be run.

~ incorrect four rod position will indicate blank, blank but rod must be isolated to settle, plausible

~o the examinee who thinks that it will respond as a full reactor scram does. when scram discharge volume fills the rods will settle to 00 without isolating.

B correct RPIS will show blank (no position on the four rod display) when it scrams (overtravel in) since only 1 rod scrammed the SDV will not fill and the rod will stay at over travel position. once

~he rod is isolated and allowed to settle at 00 a P-1 can be run C incorrect plausible to the examine who does not recall the RPIS reed switch allocations at 00 and past 00. If examinee believes that position will show 00 than a P-1 would be able to be run D incorrect--,-- (a dash in each window) of the four rod display for 30-31 is what is shown when rods are between notches while stroking. this is plausible to the examinee who believes that past 0,0 is equivalent to between notches LMK 2017 ILT NRG JANUARY Page: 114of374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 34 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 1649532 User-Defined ID: Q#34 NEW Lesson Plan Objective: LGSOPS0073A.2H ifooic: RPIS Overtravel RO: 3.6 SRO: 3.9 KA#: 214000 A2.03 LMK 2017 ILT NRG JANUARY Page: 115 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 2

214000 A2.03 3.6/3.9 RPIS Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION SYSTEM ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or o erations: Overtravel/in-out low 7

41.6 5

ON-104 Rev:\¥ s LGSOPS00738 **1:

h'

,J; 0 2

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 117 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January2017 NRCtestSRO 35 10: 1601449 Points: 1.00 A chemical spill results in the following:

- 'A' and 'C' Toxic Gas detectors tripped

- 'A' and 'D' Control Enclosure Chlorine detectors UPSCALE WHICH ONE of the following identifies the status of the CREFAS Fans?

A. Both are running B. Neither is running C. Only the 'A' fan is running D. Only the '8' fan is running Answer: 8

\Answer Explanation LMK 2017 ILT NRC JANUARY Page: 118 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO nswer: Remains in Standby, Neither CREFAS fan running he chlorine monitoring system will initiate an automatic isolation of the Control Room HVAC system if chlorine concentration exceeds 0.40 ppm in the Control Room HVAC intake plenum.

here are four chlorine detectors, which provide input to four chlorine isolation channels, as allows: (If the A and D chlorine detectors sense high chlorine, but not the Band C = No isolation) he A and C or B and 0 detectors must sense high chlorine to cause an isolation signal. If the and C chlorine detectors sense greater than 0.40 ppm chlorine, then both the A and C chlorine isolation channels will trip. If the B and D chlorine detectors sense greater than 0.40 ppm chlorine, then both the B and D chlorine isolation channels will trip.

If a chlorine isolation signal is generated on all four isolation channels, then a complete isolation will occur, which results in the following:The main Control Room air is recirculated using the normal supply and return fans, while the CREFAS fan draws some of the recirculating air through the CREFAS filter, then sends it back to the suction of the normal supply fans.

(Since no outside air is drawn in, MCR C1P will decay to O psid.)

chlorine isolation is accomplished as follows:The A or B CREFAS fan will start after a 30 second time delay. (Whichever fan is in AUTO will start.)The A CREFAS fan is started only by the C isolation channel, and the B CREFAS fan is started only by the D isolation channe (B & D detectors)!.

The toxic gas monitors provide indication and alarm in the event of toxic gas enters the Control Enclosure. Three analyzers located in the Control Enclosure are used to detect gases that are proven to be toxic, and initiate a MCR alarm once triggered. There are no automatic functions r interlocks associated with the toxic gas monitors.

utomatically initiates "A" CREFAS only, with the "A" CREFAS running - see explanation utomatically initiates "B" CREFAS only, with the "B" CREFAS running - see explanation utomatically initiates both "A" & "B" CREFAS, with both CREFAS fans running - see explanation LMK 2017 ILT NRC JANUARY Page: 119 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO AND

  • *isolation Valves Include: HV73..U21A,B HV73-052A,B HD7tUl53A, B HV73-057A,B HV78-071A,B Question written to MCA ventalation already have several questions on reactor HVAC/SBGT no isolations on turb hvac LMK 2017 ILT NRG JANUARY Page: 120 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 35 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 3 Difficulty: 2.00 System ID: 1601449 User-Defined ID: Q# 35 BANK Lesson Plan Objective: LGSOPS0078.3H Describe CREFAS operation with a A MCR Radiation Isolation Topic:

auto initiatiation RO: 3.8 SRO: 3.8 KA#: 288000 A3.01 LMK 2017 ILT NRG JANUARY Page: 121 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 2

288000 A3.01 3.8/3.8 Plant Ventilation Systems Ability to monitor automatic operations of the PLANT VENTILATION SYSTEMS including: Isolation/initiation si nals On a MCR Rad Isolation, the CREFAS Fan that is in AUTO will start (only 1 fan is in AUTO in a normal alignment) and the outside air dampers to the CREFAS Filters will open.

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 ILT NRC JANUARY Page: 123 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 36 ID: 1455868 Points: 1.00 Unit 1 was operating at 100% power when the following occurred.

  • The 1M SRV spuriously opened several minutes ago.
  • The PRO observes the following indications and diagnoses a tailpipe leak.
  • Suppression pool level is 22.5 feet PSIG 6.5

., PSIG 215.9 6.3 Which of the following describes where the 1M SRV tailpipe leak is located and the allowed action that will mitigate the containment pressure rise?

Location of tailpipe leak Allowed action that will mitigate the condition A. Suppression Pool Spray the Drywell B. Suppression Pool Spray the Suppression Pool C. Drywell Spray the Suppression Pool D. Drywell Spray the Drywell Answer: B

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 124 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Examinee must recognize I recall that TR-157-122 Drywell reading is on top, but on PR-57-101 Suppression Pool is on top. Given that pool pressure is > drywell the leak must be in the suppression pool air space. There are 2 ways to reach drywell spray in T-102, from containment pressure leg and from drywell temperature leg. Drywell temperature leg DWT-4 stop sign when DW temp cannot be maintained <145 degrees continue. From the containment pressure leg drywell spray is not authorized until pool pressure is> 7.5 psig A Incorrect spraying the DW is not allowed nor would it be the most efficient way to deal with the leak plausible to the examinee who believe that since the air volume of the DW is larger than that of the pool spraying the DW will be more effective and does not recall the limits for DW spray or thinks DW is at 215 degrees.

B Correct pool pressure is> than DW pressure so the leak is in the pool and the downcomer vacuum breakers have opened causing DW pressure to rise. Spraying the pool is directed before pool pressure reaches 7.5 psig, pool spray is allowed and the most effective way to mitigate the pressure rise.

C Incorrect leak is in the pool plausible to the examinee who does not recall which reading is dw and which is pool D Incorrect spraying the DW is not allowed nor would it be the most efficient way to deal with the leak plausible to the examinee who believe that since the air volume of the DW is larger than that of the pool spraying the DW will be more effective and does not recall the limits for DW spray or thinks DW is at 215 degrees.

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 36 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 4.00 System ID: 1455868 User-Defined ID: Q#36 NEW Lesson Plan Objective: LGSOPS1560.05 Topic: pool spray RO: 4.0 SRO: 3.9 KA#: 230000 LMK 2017 ILT NRG JANUARY Page: 126 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 2

230000 A4.13 4.0/3.9 RHR/LPCI:

Torus/Suppression Pool Spray Mode Ability to manually operate and/or monitor in the

Rev 2

.. 5 LMK 2017 ILT NRC JANUARY Page: 127 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 128 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 37 ID: 1455770 Points: 1.00 Unit 1 is at 75% reactor power.

Operators are preparing to continue raising power by control rod withdrawal Operators are performing S73.1.A NORMAL OPERATION OF THE REACTOR MANUAL CONTROL SYSTEM Given the following indications; OFUVE WATER Which of the following lists both the direction to manipulate the Drive Water Pressure Control Valve HV-46-1 F003 and the resulting pressure indication to be obtained, prior to withdrawing control rods?

Direction to manipulate Drive Water Indication to obtain Pressure Control Valve HV-46-1 F003 A. Close PDl-46-1 R602 between 255-265 PSI B. Open PDl-46-1 R602 between 255-265 PSI

c. Close PDl-46-1 R603 between 25-35 PSI D. Open PDl-46-1 R603 between 25-35 PSI Answer: A

!Answer Explanation LMK 2017 ILT NRC JANUARY Page: 129 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO A Correct per 846.1.a normal operating pressure for CRD drive water is 255-265 psi. closing pressure control valve will raise drive water pressure B Incorrect opening pressure comtrol valve will reduce pressure, plausible to the examinee who incorrectly recalls which side of the pressure regulating valve the indicator is on and does not take into account that the flow control valve wil auto open as the pressure control valve is closed C Incorrect cooling water DP is within its normal band of 10 to 25 psi. adjusting pressure control valve HV-46-1 F003 will have minimal affect on the down stream side of the valve because the flow control vave will is in auto and will open or close to maintain system flow.

plausible to the examinee who does not recall normal value for PDl-46-1 R603 or how the flow controller in automatic will affect system pressure D Incorrect cooling water DP is within its normal band of 10 to 25 psi. adjusting pressure control valve HV-46-1 F003 will have minimal affect on the down stream side of the valve because the flow control vave will is in auto and will open or close to maintain system flow.

plausible to the examinee who does not recall normal value for PDl-46-1 R603 or how the flow controller in automatic will affect system pressure LMK 2017 ILT NRC JANUARY Page: 130 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 37 Info Question Type: Multiple Choice Status: Active Always select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 5 Difficulty: 3.50 System ID: 1455770 User-Defined ID: 0#37 NEW Lesson Plan Objective: LGSOPS0046.2A Topic: drive water DP RO: 4.2 SRO: 4.4 KA#: 201001 2.2.44 LMK 2017 ILT NRC JANUARY Page: 131 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 2

201001 2.2.44 4.2/4.4 Control Rod Drive Hydraulic System Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and!

directives affect plant and s stem conditions.

5

'Rft~; 1

'#;{,'J,, 3

,,,~,;, \~ 1 LMK 2017 ILT NRC JANUARY Page: 132 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 38 10: 1455177 Points: 1.00 WHICH ONE of the following identifies the required POST-LOCA Drywell ventilation fans and what the operation of these fans will ensure?

EANS. Operation Ensures A. A,B,C,D A valid Drywell temperature indication B. A,B,G,H A valid Drywell temperature indication

c. A,B,C,D Prevent areas of high H2 and 02 concentrations in the DW D. A,B,G,H Prevent areas of high H2 and 02 concentrations in the DW Answer: D Answer Explanation lr.s 3.6.6.2 lists 1AV212,1BV212,1GV212,1 HV212 as the subset of drywell coolers that are the H2 mixing coolers. They discharge to the higher elevations to prevent localized accumulation of H2 and 02 from exceeding the lower flammability limits during LOCA conditions. Incorrect answers either have incorrect fans or valid temperature. selecting incorrect fans is plausible to if examinee fails to memorize correct fans. Valid temperature is plausible to examinee who believe he coolinq function of the hiqher elevations is the bases for requiring these fans LMK 2017 ILT NRG JANUARY Page: 133 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 38 Info Question Type: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1455177 User-Defined ID: 0#38 BANK Lesson Plan Objective: LGSOPS0077.3 Topic: Post-LOCA DW Vent Fans And Design Function Of These Fans RO: 3.5 SRO: 3.8 KA#: 223001 LMK 2017 ILT NRC JANUARY Page: 134 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

3.5/3.8 Primary Containment System and Auxiliaries Knowledge of PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES design feature(s) and/or interlocks which provide for the following: Prevents hydrogen from reaching an explosive mixture lower 5

41.7 bank 557056 bank 557056 bank 557056

Reference:

T.S. Bases 3/4.6.6 557056 KIA: 223001 K4.04, SG.07, K6.04 Used as SRO ONLY for ILT Proc Final - Good for RO Use LMK 2017 ILT NRG JANUARY Page: 135 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 39 ID: 1454413 Points: 1.00 Unit 2 plant conditions:

- OPCON 4

- Preparations are being made to flood the main steam lines per GP-6.1, 'Shutdown Operations'

- RPV level is +90"

- All appropriate steps in GP-6.1 have been performed HV-051-2F008 Shutdown Cooling outboard supply receives an inadvertent isolation signal and cannot be reopened WHICH of the following is the MINIMUM reactor level that will ensure adequate core circulation exists, per GP-6.1?

A. Upset Range level indicates +61" B. Shutdown Range level indicates +79" C. Shutdown Range level indicates + 61" D. Wide Range level indicates +61" Answer: C Answer Explanation Shutdown Range level indicates +61 inches is correct: Per caution in GP-6.1, RPV level must be maintained greater than 60 inches on Shutdown Range or greater than 78 inches on Upset Range for sufficient natural circulation in the event of a loss of forced circulation.

Upset level indication at 61 inches is incorrect: Does not meet the minimum RPV level of 78 inches in GP-6.1.

Wide Range level indication at 61 inches is incorrect: Wide Range level is not referenced in GP-6.1.

Shutdown range +79 is incorrect not the minimum required level.

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 39 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for oractice? No Points: 1.00 rTime to Comolete: 4 Difficulty: 2.00 System ID: 1454413 User-Defined ID: Q# 39 MODIFIED Lesson Plan Objective: LOT0051.11 AHR fTooic: Natural Circ followina loss of SDC RO: 3.5 SRO: 3.6 KA#: 295001.AK1 .01 LMK 2017 ILT NRC JANUARY Page: 137 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:

295001 AK1 .01 3.5/3.6 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :Natural circulation lower 1&4 41.9&41.10 32 bank Modified LMK 2017 ILT NRG JANUARY Page: 138 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 139 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 40 10:1433148 Points: 1.00 Plant conditions are as follows:

  • Suppression Pool temperature is 200° F
  • Drywall pressure is 8.0 psig
  • Suppression Pool pressure is 3.0 psig
  • CST level is 1 foot Given the following graphs; Which of the following lists the system(s), and flow rates if any, that are able to inject without violating NPSH limits?

NPSH CUB~Ji LEGENQ CURVE S1.u:um:uion E?Clot ere:uum:

1.ill!il

  • 0 psi - 4.99 psi
  • 5 psi- 9.99 psi 10 psi - 14.99 psi

~ 15 psi HPCI NPSH LIMIT

§:

U'l 100 0 +--~~--'~~~-i-~~~-i-~~~~~~-'-~--'

0 1,000 2,000 3,000 4,000 Pump Flow (gpm)

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO RCIC NPSH LIMIT 0.. 100 0..

tJj 50 0

0 100 200 300 400 500 600 Pump Flow (gpm)

A. .B.Qili HPCI at 3500 GPM AND. RCIC at 500 GPM B. NEITHER HPCI at 3500 GPM QB RCIC at 500 GPM C. BCIC at 500 GPM but NQI HPCI at 3500 gpm D. HPCI at 3500 GPM but NQI BCIC at 500 gpm Answer: D

~nswer Explanation A Incorrect plausible to the examinee who uses drywell pressure B Incorrect plausible to the examinee who cannot determine safe side of NPSH graph and who uses drywell pressure not pool pressure C Incorrect plausible to the examinee who uses drywell pressure tor the BCIC graph or cannot determine safe side of graph D Correct only HPCI at 3500 is on the safe side of graph LMK 2017 ILT NRC JANUARY Page: 141 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 40 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 ifime to Complete: 4 Difficulty: 3.00 System ID: 1433148 User-Defined ID: Q#40 NEW Lesson Plan Objective: LOT0340.14F ifopic: NPSH RO: 3.0 SRO: 3.4 KA#: 295026 EK1 .01 LMK 2017 ILT NRC JANUARY Page: 142 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295026 EK1 .01 3.0/3.4 Suppression Pool High Water Temperature Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGHWATER TEMPERATURE :Pum NPSH y; 25 LMK 2017 ILT NRC JANUARY Page: 143 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 41 ID: 1650585 Points: 1.00 Unit 1 plant conditions are as follows:

Unit has been shutdown due to major fuel damage An off-site release is in progress WHICH ONE of the following annunciators indicate that a release is in progress that will result in the exposure of a member of the public in an Unrestricted Area exceeding limits?

A. 003 RAD E-1, NORTH STACK HI-HI RADIATION B. 107REACTOR1-1, MAIN STEAM LINE HIGH-HIGH RADIATION C. 003 RAD F-2, UNIT 1 & 2 SOUTH STACK HI RADIATION D. 109 RAD E-1, 1 REAC ENCL REFUEL FLR VENT EXHAUST RAD MON A/B HI-HI I DOWNSCALE Answer: A Answer Explanation HI-HI alarms indicate that the site is releasing in excess of ODCM limits and a member of the general public standing in an Unrestricted Area (at site boundary) would exceed legal limit (10CFR20) 003 RAD E-1 North Stack HI-HI Rad Hl-Setpoint 3.45e-5 uCi/cc for Noble Gas if his would correspond to a UE ie greater than 2.2E04 uCi/cc From the ODCM:

2.2 GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION K:ontrol 3.1.2 requires that an alarm setpoint be established for the noble gas

~ffluent monitoring channels (RY26-075A(B), RY26-185A(B), RY26-285A(B),

and RY26-076) to ensure that the release rate of radioactive materials does not exceed the limits of Control 3.2.2.1.a, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrern/yr to the total body or 3000 mrern/yr to the skin A Correct B incorrect plausible to exarninee who belives MAIN STEAM LINE HI HI RAD alarm indicates a leak from the main steam line that will result in the exposure of a member of the public in an Unrestricted Area exceeding limits and that the HiHI willresult in escalation of E-plan C incorrect plausible to exarninee who belives Soth stack HI alarm will result in the exposure of a member of the public in an Unrestricted Area exceeding limits and that the HiHI willresult in escalation of E- plan D plausible tto the examinee who does not recall the reactor hvac radiation alarm setpoints A correct 003 RAD E-1 North Stack HI-HI Rad Hl-Setpoint 3.45e-5 uCi/cc for Noble Gas B incorrect LMK 2017 ILT NRC JANUARY Page: 144 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 ILT NRC JANUARY Page: 145 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 41 Info Question Type: Multiple Choice Status: Active

~lwavs select on test? No

~uthorized for practice? No Points: 1.00

!Time to Complete: 2 Difficulty: 2.20 System ID: 1650585 User-Defined ID: Q#41BANK Lesson Plan Objective: LOT0720.03A rropic: Stack monitor RO: 3.9 SRO: 4.2 KA#: 295038 EK2.04 LMK 2017 ILT NRG JANUARY Page: 146 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

1 295038 EK2.04 3.9/4.2 High Off-Site Release Rate Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE:

.Rev:i ARC -MCR-003 'ff.*..

bank 562030 bank 562030 bank 562030 LMK 2017 ILT NRG JANUARY Page: 147 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 42 ID: 1454789 Points: 1.00 Unit 1 is operating at 100% power with the following:

- '1 B' Core Spray Pump is operating in Full Flow Test A reactor coolant leak occurs.

- RPV water level reaches -133"

- RPV pressure reaches 465 psig

- Drywell pressure reaches 3.0 psig 12 seconds later, which of the following describes the status of:

(1) '1 B' Core Spray Pump, .and (2) HV-052-1F015B, CORE SPRAY LOOP B TEST BYPASS PCIV?

A. (1) Tripped and restarted (2) Closed and CANNOT be re-opened B. (1) Did not trip and is still running (2) Closed and CAN be re-opened C. (1) Tripped and is NOT running (2) Closed and CANNOT be re-opened D. ( 1) Did not trip and is still running (2) Open Answer: C Answer Explanation

'C' is correct. The Core Spray initiation signal has been reached (high Drywell Pressure ( Low RPV level -129 inches). As such, the 1B CS Pump trips (LOCA shed) and will re-sequence back on, but not until t=15 seconds (with offsite power available). Therefore, at t=12 seconds, the pump remains tripped. However, the Test Bypass valve auto-closed on the LOCA signal and will not re-open so long as the signal is present.

'A' is wrong. Plausible to the examinee who confuses the re-sequence time for the 'B'/'D' CS Pumps (i.e., t=15 sec, with offsite power available) with the re-sequence time for the 'A'/'C' CS Pumps (i.e., t=10 seconds, with offsite power available).

'B' is wrong. Plausible to the examinee who does not recognize that an initiation signal exists (thus, the pump did not LOCA shed), but who believes that the transient condition would result in closure of the Test Bypass valve.

i'D' is wrong. Plausible to the examinee who does not recognize that an initiation signal exists;

~herefore, the pump is still running and the Test Bypass valve is still open.

LMK 2017 ILT NRG JANUARY Page: 148 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 42 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 Svstem ID: 1454789 User-Defined ID: Q# 42 BANK Lesson Plan Objective: LGSOPS0052.07 Core Spray Response to Coolant Leak When operating in Full Topic:

Flow Test RO: 4.2 SRO: 4.3 KA#: 295031 EK2.03 LMK 2017 ILT NRG JANUARY Page: 149 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

Reactor Low Water Level WATER LEVEL Knowledge of the interrelations between REACTOR LOW WATER E21-1040 sht1 *R6V*' 5 th . 0 N/A bank 895494 bank N/A 833342 lost n random selection coin toss LMK 2017 ILT NRG JANUARY Page: 150 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 43 ID: 1433212 Points: 1.00 Given the following:

  • The Fire Brigade is fighting a fire in the warehouse.
  • The Motor Driven Fire Pump started and immediately tripped on spurious overcurrent.
  • The Diesel Driven Fire Pump is running and supplying the fire header with pressure at 97 psig.
  • The overcurrent trip of the Motor Driven Fire Pump breaker is reset.

Which of the following describes the Motor Driven and Diesel Driven fire pump response?

A. The Motor Driven Fire Pump starts and the Diesel Driven Fire Pump continues to run.

B. The Motor Driven Fire Pump starts and the Diesel Driven Fire Pump stops immediately.

C. The Motor Driven Fire Pump remains in standby and the Diesel Driven Fire Pump continues to run.

D. The Motor Driven Fire Pump starts and, assuming header pressure rises to and remains above 100 psig, the Diesel Driven Fire Pump stops 5 minute later.

Answer: A Answer Explanation A Correct per ARC-MCR-005 A-1 Motor driven fire pump starts at 100 psig lowering there is no auto shutdown of the diesel driven fire pump B Incorrect Plausible to the examinee who believe there is a lead lag arrangement similar to the condensate transfer system C Incorrect Plausible to the examinee who does not recall the 100 psi start set point for the Motor Driven Fire Pump D Incorrect Plausible to the examinee who believe there is a lead lag arrangement similar to the condensate transfer system LMK 2017 ILT NRG JANUARY Page: 151 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 43 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1433212 User-Defined ID: Q# 43 MODIFIED Lesson Plan Objective: LGSOPS0022.5A Topic: Fire pp operation RO: 2.5 SRO: 2.6 KA#: 60000 AK2.04 LMK 2017 ILT NRG JANUARY Page: 152 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

60000 AK2.04 2.5/2.6 Plant Fire On Site Knowledge of the interrelations between PLANT FIRE ON SITE and the following:

Breakers I relays I and disconnects lower 8

41.7 ARC-MCR-005 A-1 ARC-MCR-005 B-2 modified South Texas ro*ect bank Modified South Tex as ro*ect bank LMK 2017 ILT NRC JANUARY Page: 153 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 44 10: 145441.1 Points: 1.00 Unit 1 was operating at 100% power when an accident occurred. Current plant conditions are as follows:

  • An ATWS is in progress
  • Reactor power is 13%
  • 'A' RPS status lights are lit
  • 'B' RPS status lights are out
  • The second RPV level lowering has just been completed per T-117
  • RPV level is being maintained between -186" and -161"
  • No floor actions for the second lowering have been taken Which one of the following will allow insertion of rods to terminate the ATWS A. Close the 46-1 F034 CRD Charging Water Header Supply AND reset RDCS B. Bypass the RWM AND reset RDCS C. Close the 46-1 F034 CRD Charging Water Header Supply AND bypass the RWM D. Bypass the RWM AND do NOT reset RDCS Answer: B Answer Explanation A Incorrect Close the 46-1 F034 CRD charging water header supply valve is not required for an electrical ATWS B Correct Bypassing the RWM is required since it is enforcing and rods will be inserted directly to position 00 and not to bank position. since level is below -129 inches RDCS will lose power on the LOCA signal and need to be reset.

C Incorrect Close the 46-1 F034 CRD charging water header supply valve is not required for an electrical ATWS D Incorrect plausible to examinee who either does not recognize that a LOCA signal is present or that RDCS will need to be reset after the 4 KV bus is reset LMK 2017 ILT NRC JANUARY Page: 154 of 37 4 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 44 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00

!rime to Complete: 3 Difficulty: 3.00 System ID: 1454411 User-Defined ID: 0#44 NEW Lesson Plan Objective: LGSOPS2003.03 Tooic: ATWS RMCS RO: 3.8 SRO: 3.9 KA#: 295037 EK2.11 LMK 2017 ILT NRC JANUARY Page: 155 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Comments:

Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVEAPRM DOWNSCALE OR UNKNOWN and the LMK 2017 ILT NRC JANUARY Page: 156 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 45 ID: 1433350 Points: 1.00 Unit 1 is operating at 100% power when a Large drywell leak occurs.

  • Suppression pool pressure is 20 psig up slow
  • Suppression pool level is 15 feet steady 35 I

C!)

t:J) 30

a. 25 t:J) t:J) _,,,,,,. ~

~

w 20 ~*

a::

a.

..J 0 IS

~

/

0 I a.

a. 10 /
a. "

t:J) 5 0

5 10 15 20 25 30 35 45 SUPP POOL WATER LEVEL (FT)

LMK 2017 ILT NRC JANUARY Page: 157 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO WHICH of the following describes the action to be taken and the reason for performing this action?

Action Reason A. Rapidly depressurize per T-101 RPV Reduce Drywall pressure and temperature Control through the combined effects of evaporative and convective cooling B. Emergency blowdown per T-112 Reduce Drywall pressure and temperature Emergency Slowdown through the combined effects of evaporative and convective cooling

c. Emergency blowdown per T-112 Ensure that the pressure suppression Emergency Slowdown function of the primary containment is maintained D. Rapidly depressurize per T-101 RPV Ensure that the pressure suppression Control function of the primary containment is maintained Answer: C Answer Explanation Refer to T-102, specifically, the PC/P (Primary Containment Pressure) leg. Only when operators determine that the SAFE side of the Pressure Suppression Pressure (PSP) Curve, PC/P-3, cannot be maintained does Step PC/P-11 direct operators to perform a T-112 Emergency Slowdown. The T-102 Bases for Step PC/P-11 describes the PSP purpose as "to assure the pressure suppression function of primary containment is maintained." Rapidly depressurize per lf-101 is incorrect, plausible to the examines who plots the graph incorrectly and believes they are on the safe side of PC/P-3 but approaching the unsafe side. Reduce Drywall pressure and

~emperature through the combined effects of evaporative and convective cooling is incorrect but plausible to the examines who confuses the drywall spray basis with the depressurization basis .

.From the stem A LOCA is in progress causing Drywall pressure to rise, this will cause pool pressure to rise following drywall pressure at some at some slightly lower pressure based on pool level (Downcomer submergence)

A Incorrect Rapidly depressurize per T-101 Reduce Drywall pressure and temperature RPV Control through the combined effects of evaporative and convective cooling B Incorrect Emergency blowdown per T-112 Reduce Drywell pressure and temperature Emergency Slowdown through the combined effects of evaporative and convective cooling c Correct Emergency blowdown per T-112 Ensure that the pressure suppression Emergency Slowdown function of the primary containment is maintained D Incorrect Rapidly depressurize per T-101 Ensure that the pressure suppression RPV Control function of the primary containment is maintained LMK 2017 ILT NRG JANUARY Page: 158 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 45 Info Question Tvpe: Multiple Choice Status: Active lA.lwavs select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 2.50 System ID: 1433350 User-Defined ID: 0#45 NEW Lesson Plan Objective: LLOT1560.4 Topic: Recall reason for Emergency Slowdown based on PSP RO: 3.7 SRO: 4.1 KA#: 295024 EK3.04 LMK 2017 ILT NRG JANUARY Page: 159 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295024 EK3.04 3.7/4.1 295024 High Drywell Presure Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE:

EK3.04 tEmergency de ressurization 41.5, 41.10 T-101 T-101 bases T-102 T-102 bases LMK 2017 ILT NRC JANUARY Page: 160 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 46 ID: 1649449 Points: 1.00 Unit 2 is in OPCON 3 when a LOCA occurs.

Suppression Pool pressure is 4 psig Shutdown cooling inboard suction valve HV-51-2F009 cannot be opened The CRS directs performance of S41.7.B Use Of SRV's and Suppression Pool Cooling As An Alternate Shutdown Cooling Method.

Which of the following describes the minimum reactor pressure required to ensure sufficient flow rate and the suction source(s) allowed for injection (Suppression Pool and/or CST) after raising RPV level<! 150 inches?

Minimum Reactor Pressure Suction Source(s) Allowed For Injection A. 50 psig Suppression Pool ONLY B. 54 psig Suppression Pool ONLY

c. 50 psig Suppression Pool AND CST D. 54 psig Suppression Pool AND CST Answer: B Answer Explanation A Incorrect plausible to examinee who recalls the 50 psi limit for SRV to open but does not recll that the limit is 50 psi above pool pressure B Correct reactor pressure must be 50 psig> than pool pressure and after level is raised injection with cond. transfer and CAD is secured.

C Incorrect plausible to examinee who recalls the 50 psi limit for SRV to open but does not recll that the limit is 50 psi above pool pressure and or does not recognize that after level is raised injection with cond. transfer and CAD is secured D Incorrect after level is raised injection with cond. transfer and CRD is secured LMK 2017 ILT NRG JANUARY Page: 161 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Question 46 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.50 System ID: 1649449 User-Defined ID: 0#46 NEW Lesson Plan Objective: LOT1550.03 (ON-120)

Topic: alt SOC RO: 3.6 SRO: 3.8 KA#: 295021 AK3.05 LMK 2017 ILT NRG JANUARY Page: 162 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295021 AK3.05 3.6/3.8 Loss of Shutdown Cooling Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING :

Establishing alternate heat removal flow aths lower 4

41.5 LMK 2017 ILT NRC JANUARY Page: 163 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 164 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 47 10:1649473 Points: 1.00 Unit 1 plant conditions are as follows:

RPV level is being controlled from the Remote Shutdown Panel (RSP) per SE-1 RPV level is+ 50 inches up slow RCIC flow is zero gpm at 2400 rpm RPV pressure is 950 psig, down slow WHICH ONE of the following identifies a required action and the reason it is necessary?

ACTION BEASON A. Trip HPCI immediately Prevent excessive RPV cooldown due to uncontrolled steam usage B. Trip HPCI if level exceeds +54 inches Prevent excessive RPV cooldown due to uncontrolled steam usage C. Trip HPCI immediately Prevent reactor overfill due to fire induced spurious initiation D. Trip HPCI if level exceeds +54 inches Prevent reactor overfill due to fire induced spurious initiation Answer: D

[Answer Explanation LMK 2017 ILT NRC JANUARY Page: 165 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO NOTE

1. Reactor level rise without explanation may be caused by a spurious, fire caused HPCI initiation. Step 4.3.2 is a PROMPT Action from the fire safe shutdown analysis, to be completed within 4 minutes, to stop HPCI injection AND prevent reactor overfill.
2. HPCI Emergency Shutdown Key (HPCI SHUTDOWN KEY H2191) is already installed in HS-56-*62 in Remote Shutdown Panel (ASP) *O-C201 SE-1 step 4.3.2 IF Reactor level is rising above +54 inches AND continues to rise after RCIC flow is reduced, THEN using HPCI Emergency Shutdown Key H2191 PLACE HS-56-*62, "HPCI EMERG S/D SWITCH," to "OFF" at *OC201, to trip HPCI.

D correct per step 4.3.2 do not trip HPCI until level is > +54 rising with no injection. HPCI would normally run to maintain level between -39 and +54 HPCI is tripped to prevent vessel overfill A Incorrect plausible to examinee who believe that HPCI must always be tripped at the RSP as a 4 minute immediate action and I or believe the basis is to limit cooldown.

B Incorrect plausible to examinee who does not recall basis for tripping HPCI but remembers that injection through core spray will cause pressure reduction (will not exceed cooldown rate)

C Incorrect for the reasons stated above KIA does not differentiate between main turb and HPCl/RCIC at LGS MSIVs are closed during MCR abandonment there is no procedural basis or UFSAR information on separating gen. from grid unable to write a question on main turb for this K/A LMK 2017 ILT NRC JANUARY Page: 166 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 47 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00

!Time to Complete: 2 Difficulty: 2.00 Svstem ID: 1649473 User-Defined ID: Q# 47 MODIFIED Lesson Plan Objective: SE-1 TRAINING Topic: SE-1 HPCI Shutdown Requirement RO: 3.7 SRO: 3.8 KA#: 295016 AK3.02 LMK 2017 ILT NRG JANUARY Page: 167 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295016 AK3.02 Control Room Abandonment Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT :

7 3

586875 modified 586875 modified 586875 modified LMK 2017 ILT NRG JANUARY Page: 168 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 48 ID: 1454791 Points: 1.00 Unit 2 plant conditions are as follows:

Startup in progress with Reactor Pressure at 380 psig Normal Electrical lineup A small coolant leak results in Drywall pressure rising to 2 psig and all automatic actions occur as designed.

WHICH ONE of the following identifies the source of power to Safeguard and Non-Safeguard DC loads one (1) minute later?

(No operator action has been taken.)

SAFEGUARD DC SOURCE NON-SAFEGUARD DC SOURCE A. Batteries Batteries B. Batteries Battery Chargers

c. Battery Chargers Batteries D. Battery Chargers Battery Chargers Answer: C Answer Explanation

~LLJ..-cLL~UY:na..a~~~~J.Ll!~L),j~..liiU~L.liil::uJii~:...u:!ooUJi.:.;z.oi::.~u.u:llll~~ is correct. All Battery Chargers are powered from Safeguard AC Power. With the provided conditions, a LOCA signal will occur. This will result in the tripping of all Non-Safeguard loads powered from Safeguard Buses. Two of the Non-Safeguard Battery Chargers will shunt trip (2BC01 and 2BC02) and one (2BC) is powered from D224-G-D MCC which will trip on a LOCA and must be manually reset in the MCR. All of the Divisional Battery Chargers will be re-energized automatically when he respective 480 VAC Load Center automatically re-closes 3 seconds following the LOCA signal.

~LLJ...Jiiliuo.sz...:::.-'Zl!:lc:J~JJ.l!iDJ.L),j~.JiiU~L.liil::uJii~:...u:!ootl.Jl::sl.~li&!olu.u:llllOl....lo~ is incorrect. Th is wou Id be correct immediately following the LOCA as the 480 VAC Load Center will trip on the LOCA signal which will de-energize all of the battery chargers. However, 3 seconds later the Load Center Breaker will auto re-close and re-energize the Safeguard Battery Chargers. The Non-Safeguard Battery Chargers will shunt trip and must be manually reset. Until they are reset, Non-Safeguard DC loads will be supplied from batteries.

LMK 2017 ILT NRC JANUARY Page: 169 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 48 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 5 Difficulty: 2.00 System ID: 1454791 User-Defined ID: Q # 48 BANK Lesson Plan Objective: LGSOPS0095 - 7 rropic: Effect of LOCA signal on Battery Chargers RO: 3.6 SRO: 3.7 KA#: 295003 AA 1. 04 LMK 2017 ILT NRG JANUARY Page: 170 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:

295003 AA 1.04 3.6/3. 7 Partial or Complete Loss of A.C. Power Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

POWER: D.C. electrical 45 6

minor rev to match KA K6. Knowledge of the effect that a loss or malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION:

(CFR: 41.7 / 45.7)

K6.0l A.C. electrical distribution ............................. .

. . . . . . . . . . . . . . . . . . 3.2 3.5 LMK 2017 ILT NRC JANUARY Page: 171 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 49 10:1455250 Points: 1.00 Plant conditions are as follows:

  • OA MCR Chiller in service
  • 1A OW Chiller in service
  • 2B OW Chiller in service
  • 012 O/G running for its monthly surveillance test
  • OB ESW is running, an EO has just closed 11-1013 UNIT 1 SW TO LOOP B ESW and 11-2013 UNIT 2 SW TO LOOP B ESW per the 012 surveillance test.

Shortly thereafter, OB ESW pump trips WHICH ONE of the following groups of equipment lose cooling water?

A. 1A Orywell Chiller, Unit 1 HPCI, and Unit 1 RCIC B. 2A Orywell Chiller, Unit 2 HPCI, and Unit 1 RCIC C. Unit 2 HPCI, and Unit 2 RCIC

0. OA MCR Chiller, Unit 1 HPCI, and Unit 1 RCIC Answer: C Answer Explanation Reference SIM-12 drawing or P&IO 11 sheet 2 and 3 with no flow in B ESW loop and the 11-1013 closed flow is lost to the OB MCR chiller unit 2 HPCI and unit 2 RCIC. The lineup for sw to HPCI and RCIC is as followes 11-1010 unit 1 SW to unit 1 A ESW provides a flow path for SW to unit 1 HPCI and RCIC. 11-2013 unt 2 SW to unit 2 B ESW provides flow to unit 2 HPCI and RCIC

........~~..........*.._..,plausible to the examinee who doesn't recall the chillers cooled by ESW or that unit HPCI sw is from the 11-2013.

  • Plausible to the examinee who reverses the 11-1010 and 11-2013 loads .

LMK 2017 ILT NRG JANUARY Page: 172 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 49 Info Question Tvoe: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 2.50 Svstem ID: 1455250 User-Defined ID: Q# 49 MODIFIED Lesson Plan Objective: LGSOPS0011.7A lfopic: Recoqnize Service Water/ESW shared loads lost RO: 3.3 SRO: 3.4 KA#: 295018 AA 1.02 LMK 2017 ILT NRC JANUARY Page: 173 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO Comments:

1 295018 AA 1.02 3.3/3.4 Partial or Complete Loss of Component Cooling Water Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System loads LMK 2017 ILT NRC JANUARY Page: 174 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 175 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 50 10:1455199 Points: 1.00 Plant conditions are as follows:

- Both Units are in their normal/preferred electrical lineup A grid disturbance causes a trip of the 10 Station Aux Bus Supply Breaker (105).

20 seconds after the trip of the 105 breaker, the PRO reviews the 4KV breaker alignment and reports the following:

- 013 Bus is de-energized

- 013 O/G is running unloaded

- All other 4 KV buses are energized WHICH ONE of the following identifies the likely cause of the 013 Safeguard Bus remaining de-energized?

A. 013 O/G Lockout B. 013 Bus Lockout C. 20 Station Aux Bus Lockout

0. 101 Safeguard Transformer Lockout Answer: B

!Answer Explanation LMK 2017 ILT NRC JANUARY Page: 176 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Initially, D13 is powered from the 101 Safeguard Transformer through the 101-D13 breaker.

hen the 1O Station Aux Bus Supply Breaker (105) trips, the 101 Safeguard Transformer is de-energized, causing the 101-D13 breaker to trip on 101 Transformer Undervoltage (<70%).

ne (1) second later, the 201-D13 breaker should auto-close to re-energize the D13 bus.

Similarly, at 0.5 seconds after the dead-bus condition on D13, the D13 DIG will get an auto-start ignal. However, if the 201-D13 breaker did close, the D13 DG Output breaker will not attempt to auto-close when all of its other closing permissives are satisfied. The stem conditions indicating hat the D13 bus is still de-energized at T =20 seconds from the 105 breaker trip means that neither the 201-D13 breaker nor the D13 DIG Output breaker have closed in on the bus.

'B' is correct. A D13 Bus Lockout will prevent both the 201-D13 and D13 DIG Output breakers ram closing in on the bus (see ARC-MCR-121, A 1). D12 and D14 bus are supplied from 201 bus nd unaffected by the trip of the 105 breaker. D11 DG will start on the undervoltage on D11 bus hen 101 bus losses power and the D111101 breaker trips, but the DG will not close in on the bus because before the DG gets up to speed the 2011D11 breaker will close.

'A' is wrong because it suggests that a D13 DIG Lockout would not only prevent the D13 DIG utput breaker from closing (which it will), but also prevent the 201-D13 feeder breaker from losing (which it WON'T). Plausible to the examines who either mis-understands the breakers hat are affected by a lockout, or who fails to review the D13 DIG Lockout ARC (ARC-MCR-121, C1).

'C' is wrong. Although a 20 Station Aux Bus Lockout will prevent the 201-D13 breaker from closing (because the 201 Transformer voltage is < 70%), it will NOT prevent closure of the D13 DIG Output breaker.

'D' is wrong. See ARC-MCR-120, F1. Only the 101 Safeguard Transformer Supply Breaker (from the 1O Station Aux Bus) receives a .d.imci. trip from this kind of lockout. This lockout will not prevent closure of the 201-D13 feeder breaker, or of the D13 DIG Output breaker. Plausible to he examines who either mis-understands the breakers that are affected by a lockout, or who fails o review the 101 Transformer Lockout ARC ARC-MCR-120, F1 .

LMK 2017 ILT NRG JANUARY Page: 177 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 50 Info Question Tvpe: Multiple Choice Status: Active

!Always select on test? No

!Authorized for practice? No Points: 1.00 tTime to Complete: 3 Difficulty: 2.00 System ID: 1455199 User-Defined ID: Q# 50 BANK Lesson Plan Objective: LGSOPS0092A.4A tTooic: Determininq Cause of a De-energized 4 KV Safeguard Bus RO: 3.9 SRO: 4.0 KA#: 700000 LMK 2017 ILT NRG JANUARY Page: 178 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

700000AA1.05 3.9/4.0 Generator Voltage and Electric Grid Disturbances Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:

features ARC-MCR-121

, Al ARC-MCR-121

, Cl ARC-MCR-008

, A3 ARC-MCR-120

, Fl 295003 AK2.03 LMK 2017 ILT NRG JANUARY Page: 179 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 51 10:1649810 Points: 1.00 Unit 1 plant conditions are as follows:

  • OPCON 5 with fuel handling in-progress per FH-105, Core Component Movement - Core Transfer
  • The SRO on the refueling platform reports that a fuel bundle is being lowered into the core While the bundle is being lowered, the RO reports that SRM "1 B" count rate has risen from 230 cps to 475 cps.

WHICH ONE of the following describes the ability to continue lowering the bundle, and whether entry into ON-120, "Fuel Handling Problems" is required?

Ability to Continue Lowering the Entry into ON-120 "Fuel Handling Problems Bundle into the Core A. Bundle may NOT be lowered until NOT Required count rate stabilizes B. Bundle may NOT be lowered until Required count rate stabilizes

c. Continued lowering of the bundle IS NOT Required permitted D. Continued lowering of the bundle IS Required permitted Answer: A Answer Explanation A Correct Since SAM count rate doubled once, per FH-105 step 3.7.4 lowering of the bundle must stop until count rate stabilizes at a value of less than 2 doublings, and no spiking or indication of SRM inoperability exists, then lowering the bundle may be continued.

B Incorrect ON-120 entry is only required if SAM count rate doubles twice (i.e. one doubling would be from 230 to 460, a second doubling would be from 460 to 920) plausible to examinee who confuses FH-105 action with ON-120 entry C Incorrect Plausible to examine who does not recall FH-105 requirements D Incorrect Plausible to examine who does not recall FH-105 requirements or the attachment 1 actions of ON-120

- Since SAM count rate doubled once, per FH-105 step 3.7.4 lowering of the bundle must stop until count rate stabilizes at a value of less than 2 doublings, and no spiking or indication of SAM inoperability exists, then lowering the bundle may be continued. ON-120 entry is only required if SAM count rate doubles twice (i.e. one doubling would be from 230 to 460, a second doubling would be from 460 to 920)

FH-105, ON-120 LMK 2017 ILT NRG JANUARY Page: 180 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 51 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 2.00 System ID: 1649810 User-Defined ID: Q# 51 BANK Lesson Plan Objective: LLOT0760.10 OPCON 5 with fuel handling in-progress per FH-105, Core rl"opic:

Comoonen RO: 3.4 SRO: 4.1 KA#: 295023 AA2.04 LMK 2017 ILT NRC JANUARY Page: 181of374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295023 AA2.04 3.4/4.1 Refueling AccidentsAbility to determine and/or interpret the following as they apply to REFUELING ACCIDENTS :

tOccurrence of fuel handling accident Lower 8

41.10 LMK 2017 ILT NRC JANUARY Page: 182 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 52 10:1455248 Points: 1.00 WHICH ONE of the following describes the basis for performing an Emergency Slowdown when Drywell temperature cannot be restored and maintained below 340°F?

A. Maintain ADS SRV availability B. Prevent RPV level instrument reference leg boiling C. Maintain downcomer vacuum breaker availability D. Drywell Spray using fire water will be unavailable Answer: A Answer Explanation T-102, Subsequent steps in the drywell temperature (OW!f) control flowpath direct actions to rapidly shutdown the reactor and to emergency depressurize the RPV. These actions are appropriate, however, only if it has been determined that drywell temperature cannot be maintained below 340"F (i.e., the maximum temperature at which ADS is qualified and drywell design temperature). Step DW!f-10 ensures this condition has been met before allowing emergency RPV depressurization.

When it has been determined that drywell temperature cannot be maintained below 340"F, operators are directed to continue at Step OW !f-11.

~ correct for the above reason B incorrect. Plausible to the examinee who realizes that hi temperature in the OW may effect level indication C Incorrect. Plausible to the examinee who recalls the solenoid operation of these valves, but does not recall that solenoids are for testing only D incorrect. Plausible to the examinee who uses steam tables assumes saturated conditions and calculates 340 degrees will be about 130 psig. a steam leak in the drywell would be an isenthalpic process so without reactor pressure this calculation can not be assumed.

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 52 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.40 System ID: 1455248 User-Defined ID: Q# 52 BANK 2015 NRC Lesson Plan Objective: LGSOPS1560.05 Basis for an Emergency Slowdown when Drywell temperature if opic: reaches 340 deq RO: 4.0 SRO: 4.1 KA#: 295028 EA2.01 LMK 2017 ILT NRC JANUARY Page: 184 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295028 EA2.01 4.0/4.1 High Drywell Temperature Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE :

Dr well tern erature lower 5

41.10 T-102 bases 'R<<t~~~ 2

':#:';~tff01 5 Bank 560429 2015 NRC 560429 LMK 2017 ILT NRC JANUARY Page: 185 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 53' 10: 1601451 Points: 1.00 Unit 1 is in OPCON 1.

DEHC is operating in "Speed Control Mode" with the main turbine at 1800 rpm ready to synchronize to the grid.

Which of the following completes the statement below If (1) turbine speed sensors fail, the turbine will respond by __(2l A. (1)2outof3 (2) closing the CVs and IVs but NOT the Stop Valves or ISVs B. (1)2outof3 (2) tripping C. (1) 1 out of 2 twice (2) closing the CVs and IVs but NOT the Stop Valves or ISVs D. (1) 1 out of 2 twice (2) tripping Answer: B Answer Explanation B Correct turbine trip logic for over speed or loss of speed signal is 2 out of 3 logic. loss of speed siqnal will cause a turbine trip A Incorrect but plausible to examinee who recalls that in speed control mode

  • At > 100% rated speed, the CVs start to close, a) From 101 % to 103%, all the IVs close b) At > 103%, CVs and IVs are closed and believes that a loss of speed signal will act the same as over speed in speed control mode c incorrect plausible to examinee who believes overspeed trip logic is the same as high level trip loqic D incorrect plausible to examinee who believes overspeed trip logic is the same as high level trip logic and believes loss of speed signal will act the same as overspeed in speed control mode as described in "A" LMK 2017 ILT NRC JANUARY Page: 186 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 53 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1601451 User-Defined ID: Q#53 NEW Lesson Plan Objective: LGSOPS0031 B.01 D Topic: overspeed trip logic RO: 3.1 SRO: 3.1 KA#: 1295005 AA2.03 LMK 2017 ILT NRG JANUARY Page: 187 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295005 AA2.03 3.1 /3.1 Main Turbine Generator Trip Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERA TOR TRIP:

Turbine valve osition lower 3

41.5 LGSOPS0018 LMK 2017 ILT NRC JANUARY Page: 188 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 189 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 54 10:1649516 Points: 1.00 SRVs are automatically cycling due to high reactor pressure.

WHICH one of the following describes the reason SRVs are manually opened per T-101?

A. Lower the rate of inventory loss B. Ensure SBLC can inject at its design flow C. Reduce the potential for a stuck safety/relief valve D. Minimize likelihood of a downcomer vacuum breaker failure Answer: C

!Answer Explanation LMK 2017 ILT NRC JANUARY Page: 190 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LGS TRIP Step RC/P-7 is a decision diamond that has operators evaluate whether or not any of he SRVs are cycling.

"SRV cycling" is defined as multiple, closely sequenced SRV actuations where the SRV opens as RPV pressure exceeds the respective safety lift setpoint and closes as RPV pressure drops belo'A the respective reset setpoint. SRV cycling is undesirable and warrants prompt manual action for the following reasons:

  • Shrink and swell associated with SRV actuations cause RPV level fluctuations that complicate RPV level control actions.
  • Under failure-to-scram conditions, the consequent RPV level and RPV pressure oscillations can result in significant reactor power transients.
  • The potential for a stuck open SRV is increased.

IThe frequency at which SRV actuations are judged to constitute "cycling" is dependent on the effect of the actuations upon reactor power, RPV level, and RPV pressure, the effectiveness of automatic control systems, the practicability of manual control, and the availability of personnel for performance of manual control functions.

RC/P-8 Manually open SRVs until RPV press drops to 990 psig DISCUSSION LGS TRIP Step RC/P-8 is entered as the result of a "YES" response to Step RC/P-7, indicating hat one or more SRVs are cycling. SRV cycling can be terminated by reducing RPV pressure to below the lowest SRV safety lift setpoint. Step RC/P-8 directs actions to reduce RPV pressure to the RPV pressure that corresponds to the point at which all main turbine bypass valves will be fully open (990 psig), a value much lower than the lowest SRV safety lift setpoint.

A Incorrect plausible to the examines who recalls that 990 psi will keep max amount of steam to bypass valves, however this is the reason for not going below 990 not why pressure is reduced by manually opening SRV's B Incorrect plausible to examines who does not recall SLC is a positive displacement pump and that discharge pressure will not effect pump flow rate C Correct D Incorrect plausible to the examines who does not evaluate how long it will take for the steam in the downcomer to condense to the point of opening the downcomer vacuum breaker. with the same 1 or 2 SRVs cycling on pressure there will not be enough time for steam to condense to the point of causing vacuum breaks rapidly cycling for potential to

~tick or break.

LMK 2017 ILT NRG JANUARY Page: 191 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 54 Info Question T e: Multi le Choice Status: Active No No 1.00 3

2.00 1649516 0#54 BANK LGSOPS1560.5 RC/P-7 Comments:

295025 2.4.18 3.3/4.0 High Reactor Pressure Knowledge of the specific bases for EOPs lower 3

41.10 560722 bank modified 560722 bank modified 560722 bank modified LMK 2017 ILT NRG JANUARY Page: 192 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 55 ID: 1649556 Points: 1.00 Unit 1 is in OPCON 5 when the following occurs

  • Alarm 115-G5 1B-1 D RH R Pump Room Flood has alarmed
  • An EO reports several inches of water on the floor in the 1B-1 D RHR pump room
  • The EO reports the leak is on the RHR suction pipe BETWEEN the AHR suction valve and the AHR pump.

A. 2 and 3 ONLY B. 1and3 ONLY C. 1and2 ONLY D. 1, 2 and 3 Answer: A Answer Explanation A Correct symptom for on-110 loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs. T-103 entry includes Room flooding alarm condition for areas in Table SCC-1 which include AHR pump rooms. T-102 entry is not required until suppression pool level drops below 22 feet B symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs. T-102 is require (<22" pool level) regardless of OPCON C Incorrect symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs.T-103 entry required due to AHR room flood alarm D Incorrect symptom for on-11 O loss of primary containment include observation of a primary containment breach and are only required when primary containment is required per Tech Specs.

LMK 2017 ILT NRC JANUARY Page: 193 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 55 Info Question Type: Multiple Choice Status: Active lA.lwavs select on test? No lA.uthorized for practice? No Points: 1.00 rTime to Complete: 3 Difficulty: 3.50 System ID: 1649556 User-Defined ID: 0#55 NEW Lesson Plan Objective: LGSOPS1560.04 Topic: low pool leveL AOP/EOP entry RO: 4.5 SRO: 4.7 KA#: 295030 2.4.4 LMK 2017 ILT NRG JANUARY Page: 194 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

Low Suppression Pool Water Level Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal I o eratin rocedures.

LMK 2017 ILT NRG JANUARY Page: 195 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 56 ID; 1671239 Points: 1.00 Unit 2 is operating at 50% power when a feedwater malfunction results in the following:

  • Reactor level begins lowering
  • 107-H1 REACTOR WATER LEVEL BELOW LEVEL 3 TRIP is alarmed
  • The "A" RPS trip system is deenergized
  • The feedwater system restores level to +35 inches
  • PMS indicates reactor level reached + 10.5 inches WHICH ONE of the following identifies the required action in accordance with OT-117 RPS Failures?

A. Perform a GP-4 Shutdown B. Reset "A" RPS trip system half SCRAM AND insert a manual half SCRAM on RPS trip system "B" C. Maintain half SCRAM on RPS trip system "A" AND do NOT insert a manual half SRAM on RPS trip system "B" D. Immediately SCRAM Unit 2 Answer: A Answer Explanation With reactor level at 10.5 it is possible that one and only one of the Reactor level trip unit would actuate.

Requires the candidate to understand that with Reactor lo level Trip in alarm and one systems of RPS energized that entry into OT-117 is required.

A is correct failure to SCRAM in retrospect requires a GP-4 shutdown B incorrect, plausible to the examinee who believe that since A side worked only a B side half SCRAM needs to be inserted ON-117 C incorrect but plausible to examinee who believe that with either A or B RPS INOP maintaining 1 channel in tripped condition will satisfy the LCO D incorrect, plausible to the examinee who confuses failure to SCRAM in retrospect with failure to SCRAM in proqress LMK 2017 ILT NRC JANUARY Page: 196 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 56 Info Question T e: Multi le Choice Status: Active No No 1.00 4

3.00 1671239 0#56 NEW LGSOPS1540.3 SCRAM Erner enc Procedures 4.2 4.2 295006 2.4.46 Comments:

295006 2.4.46 4.2/4.2 SCRAM Emergency Procedures I Plan: Ability to verify that the alarms are consisten with the plant c/tc'Yl:t.foLI Conditions.

Hi h 41.10 OT-117 ARC-MCR-107 G1 LMK 2017 ILT NRG JANUARY Page: 197 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 198 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 57 ID: 1601473 Points: 1.00 Unit 1 plant conditions:

- Div 4 DC is lost

- Operators enter E-1 FD, 'Loss of Div 4 125 VDC Bus 1FD' WHICH ONE of the following identifies the type of manual isolation of the MCR directed by E-1 FD, and the reason why?

A. Radiation Isolation, to ensure outside air is isolated to the MCR B. Chlorine Isolation, to ensure outside air is isolated to the MCR C. Chlorine Isolation, to maintain positive MCR pressure D. Radiation Isolation, to maintain positive MCR pressure Answer: B Answer Explanation B is correct with a loss of power to the isolation logic for one of two in series outside isolation dampers there is no assurance that if some other loss of power incident were to happen that it will ensure that a full chlorine isolation will occur during an actual chlorine accident. Therefore, E-1 FD directs that, upon loss of a division of DC, a chlorine isolation be performed to ensure outside air is isolated to the MCR.

A incorrect plausible to the examinee who does not recall which isolation is directed from E-1 FD and does not recall the difference between chlorine isolation and radiation isolation suction paths C incorrect plausible to the examinee who believes chlorine isolation keeps the MCR positive to keep Chlorine out D Incorrect plausible to the examinee who believes a radiation isolation is directed from E-1 FD LMK 2017 ILT NRC JANUARY Page: 199 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 57 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rTime to Complete: 3 Difficulty: 2.00 System ID: 1601473 User-Defined ID: Q# 57 BANK Lesson Plan Objective: LGSOPS0078.04 Recall Reason for MCR Manual Chloring Isolation on loss of Div Topic:

4DC RO: 4.6 SRO: 4.6 KA#: 295004 2.4.49 LMK 2017 ILT NRG JANUARY Page: 200 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295004 2.4.49 4.6/4.4 Partial or Complete Loss of D.C. Power Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

lower LGSOPS0078 560683 LMK 2017 ILT NRC JANUARY Page: 201 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 58 10:1455234 Points: 1.00 Unit 1 is operating at 100% power

  • Service air is connected to the 1A instrument air header
  • PV-015-167 Service Air Header Pressure Control Valve has isolated
  • Service air header pressure has equalized with 1A instrument air header Which of the following describes the A and Bair header pressures that caused PV-015-167 Service Air Header Pressure Control Valve to isolate and how the Service Air Compressor is loaded?

1A and 1B instrument air header pressures Service air compressor loading A. Both headers < 70 psig Only the Lead side loaded B. At least one header is < 70 psig Lead and Lag sides loaded

c. At least one header is < 70 psig Only the Lead side loaded D. Both headers < 70 psig Lead and Lag sides loaded Answer: D Answer Explanation Both air headers low pressure alarm (85psig)

PV-05-167 closes when both headers are < 70 psig.

Service air com lead side load at 97 psig lag at 94 The instrument air headers at LGS are 2 separate headers with check valves to maintain separation, however a leak at a component or at a panel where several lines come together after the check valve will cause both headers to depressurize. Also, these headers run in close proximity to each other so any mechanical accident that damages one may also damage the other. per the stem PV-015-167 Service Air Header Pressure Control Valve has isolated. this requires both headers to be less than 70 psig. When PV-015-167 isolates it separates the service air compressor from the service air loads and allows the service air compressor to supply the instrument air header. The air compressors are able to compress on both the piston up and down stroke, normally the only compress on one side, if air header pressure drop below a setpoint (94psig for service air) than the compressor will load on both up and down stroke.

A is incorrect plausible to the examinee who doe not recall the loading sequence of the service air compressor B is incorrect plausible to the examinee who does not recall the requirement for BOTH air headers to be <70 psig for the PV-05-167 to close C incorrect but plausible for the reasons stated above D correct LMK 2017 ILT NRG JANUARY Page: 202 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 58 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00

!Time to Complete: 4 Difficulty: 3.00 Svstem ID: 1455234 User-Defined ID: 0#58 NEW Lesson Plan Obiective: LOT-1550 ON-119 OBJ 3 tropic: backup to ins airf air RO: 3.3 SRO: 3.4 KA#: 295019 LMK 2017 ILT NRC JANUARY Page: 203 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

3.3/3.4 Partial or Complete Loss of Instrument Air Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 205 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 59 .* ID: 1455127 Points: 1.00 Plant conditions are as follows:

  • Reactor pressure is 450 psig
  • Drywell pressure is 8 psig
  • Drywell temperature is 275 degrees Given the following graph Which of the following identifies whether the Drywell conditions are Safe or Unsafe and what the safe side of the graph is protecting from?

CURVE PC/P*2 CU RYE DW/T .. 3 DRYWELL SPRAY INITIATION LIMIT 500-+--+---il---t--t--+--+........-+--+--1 450-t----lt---t'--t--+-+--P--+----+----+---+---+--

400--t----,__t--1t--t::l'"'-1--I--;.-+-+-;..-;-

350.,........_,.__,.__,._~.,_.,_ ____i--1!--1--1--1---!"-!

300***t-.,.._.,.._.,...,...______

250+-+--"""""'--+-+--+--

200-i--t...---o--j.---l----l--i-->-_,__....._.__._____ ~

150-+--A-+-.....-+--;,..._.--+-+-

100*  ; J

  • I 3 4 5 6 7 8 91011:12131415161718 Safe I Unsafe Remaining on safe side protects from A. Unsafe Containment Failure B. Unsafe Level instrument inaccuracy
c. Safe Containment failure D. Safe Level instrument inaccuracy Answer: C LMK 2017 ILT NRC JANUARY Page: 206 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer Explanation Examinee must calculate that Drywell temperature and Pressure combination given are below the safe/unsafe line on the graph. Then the candidate must determine that below line is safe. the examinee must then determine that the graph in question is the DW spray initiation limit and not

~he reference leg saturation limit curve and what the reason for these curves are A Incorrect plausible to examinee who does not recall safe side of graph B Incorrect plausible to examinee who does not recall safe side of graph and confuses this graph with the ref leg saturation curve C Correct safe side of graph is below the line and remaining on safe side protects against containment failure D Incorrect plausible to examinee who confuses this graph with the ref leg saturation curve LMK 2017 ILT NRC JANUARY Page: 207 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 59 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 4 Difficulty: 3.00 System ID: 1455127 User-Defined ID: Q# 59 NEW Lesson Plan Objective: LGSOPS1560.04 Topic: DW temp pressure effects RO: 3.3 SRO: 3.5 KA#: 295012 AK1 .01 LMK 2017 ILT NRC JANUARY Page: 208 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

1 2

295012 AK1 .01 3.3/3.5 High Drywell Temperature Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE :

Pressure/temperature relationshi 2

5 LMK 2017 ILT NRG JANUARY Page: 209 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 60 10:1588533 Points: 1.00 Unit 2 is operating at 50 percent power.

A Reactor Recirc Pump trips.

Which of the following is correct regarding the initial indicated reactor level response, and the major reason for the reactor power reduction from the pump trip?

Indicated level response Reason for power reduction A. Rises Change in void content

8. Rises Change in moderator temperature
c. Lowers Change in void content D. Lowers Change in moderator temperature Answer: A Answer Explanation A A correct indicated level will rise. Due to increased void production in the core flow from the downcomer to the core will reduce causing level in the downcomer to rise. the void coefficient will be the major factor in the power change B Incorrect plausible to the examinee who believes reduced recirc flow will cause feedwater temperature to rise C Incorrect plausible to the examinee who does not recall that indicated level is read in the down comer not inside the shroud D Incorrect plausible to the examinee who does not recall that indicated level is read in the down comer not inside the shroud and believes reduced recirc flow will cause feedwater temperature to rise LMK 2017 ILT NRG JANUARY Page: 210 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 60 Info Question Type: Multiple Choice Status: Active

~lwavs select on test? No

~uthorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 1588533 User-Defined ID: Q# 60 MODIFIED lesson Plan Objective: LGSOPSO 43A Topic: RR DD trip void effect RO: 3.2 SRO: 3.2 KA#: 295014 AK2.04 LMK 2017 ILT NRC JANUARY Page: 211 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

Inadvertent Reactivity Addition Knowledge of the interrelations between INADVERTENT REACTIVITY ADDITION and the seusquehanna Q 46 2013 exam modified seusquehanna Q 46 2013 exam modified seusquehanna Q 46 2013 exam modified LMK 2017 ILT NRG JANUARY Page: 212 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 61 ID: 1601489. Points: 1.00 Unit 1 has experienced a core damage event with elevated Off-site release rates. For the CREFAS system, which correctly completes the statement below?

CREFAS will automatically isolate if the outside air intake measures greater than (1) to ensure control room personnel do NOT receive more than (2) for the duration of the accident.

( 1) (2)

A. 0.5 mR/hr 5 REM TEDE B. 0.5 mR/hr 25 REM CDE Thyroid

c. 1 X 10-5 µCi/cc 5 REM TEDE D. 1 X 10-5 µCi/cc 25 REM CDE Thyroid Answer: c Answer Explanation iThe isolation set point for Main Control Room Normal Fresh Air Supply Radiation Monitor is 1X10-5 micro curies/cc (Tech Spec Table 3.3.7.1-1) iThe purpose of the CREFAS Radiation isolation is to limit the Control Room radiation exposure to personnel to 5 REM TEDE or less. Tech Spec Bases page 83/4 7-1a.

A Wrong - Plausible to the student that mistakenly recalls the CREFAS CL2 isolation setpoint of 0.5 PPM in place of the Radiation isolation set point B Wrong - Plausible to the student that mistakenly recalls the CREFAS CL2 isolation setpoint of 0.5 PPM in place of the Radiation isolation set point and plausible to the student that remembers that all Radioligical Effluent Thyroid limits are 5X above the TEDE limits found in the EALs and selects the Thyroid Limit that would be 5X larger than the correct 5 REM TEDE limit C Correct for the above reasons D Wrong - Plausible to the student that remembers that all Radioligical Effluent Thyroid limits are 5X above the TEDE limits found in the EALs and selects the Thyroid Limit that would be 5X larger than the correct 5 REM TEDE limit LMK 2017 ILT NRC JANUARY Page: 213 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 61 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 rnme to Complete: 3 Difficulty: 2.00 System ID: 1601489 User-Defined ID: Q#61NEW Lesson Plan Objective: LGSOPS0078.11 rropic: Off-site Release Rate - Response of plant ventilation RO: 3.3 SRO: 3.5 KA#: APE 295017 AK3.02 LMK 2017 ILT NRC JANUARY Page: 214 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 295017 AK3.02 RO 3.3 SRO 3.5 APE: 295017 High Off-Site Release Rate AK3. Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE:

AK3.02 Plant ventilation.

Low 9 Radioactivit Release 41.5 EP-AA-1008 Addendum 3 Unit 1 Tech Specs Table 3.3.7.1-1 N/A LMK 2017 ILT NRG JANUARY Page: 215 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 62 ID: 1588469 Points: 1.00 Unit 1 is operating at 40% power, with the following:

- The '1A' RPV Narrow Range (NR) Level Transmitter that inputs to the 'A' NR level indicator on 1OC603 is failed upscale Five minutes later, the following occurs:

- The '1 B' RPV Narrow Range (NR) Level Transmitter that inputs to the 'B' NR level indicator on 1OC603 fails upscale WHICH ONE of the following describes the plant response (assume no operator action)?

A. Reactor scrams due to a loss of Feedwater B. Reactor scrams due to a Main Turbine trip; RFPs ARE available after the scram C. Reactor remains operating D. Reactor scrams due to a Main Turbine trip; RFPs are NOT available after the scram Answer: C Answer Explanation The 4 RPV LTs that input to DFWLC for the high level turbine trip logic are setup different than RPS trip logic. The DFWLC trip logic is A or B and C or D. RPS trip logic is A or C and B or D.

With A and B level transmitters for DFWLC failing upscale, the main turbine and RFPT will not trip on high level. additionally these transmitters are different than the RPS level transmitters

'C' is correct for the above reasons. Reactor remains operating

'A' is wrong. Reactor scrams due to a loss of Feedwater Plausible to the examinee who does not recall the LT coincidence needed to produce the turbine trip function.

'B' is wrong. Reactor scrams due to a Main Turbine trip; RFPs are available after the scram Plausible to the examinee who not only incorrectly concludes several points: 1) that these two LTs work together to produce the needed turbine trip logic; and 2) that the RFPTs are available, post-scram (i.e., that the RFPTs will not have tripped on the LT failures).

'D' is wrong. Reactor scrams due to a Main Turbine trip; RFPs are nD.t available after the scram Plausible for reasons similar to choices 'B' and 'C'.

LMK 2017 ILT NRG JANUARY Page: 216 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 62 Info

)uestion Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.50 System ID: 1588469 User-Defined ID: 0#62 BANK Lesson Plan Objective: LLOT0540.14D Topic: Plant Response to RPV LT Upscale Failures RO: 3.5 SRO: 3.5 KA#: 295008 AA 1.08 LMK 2017 ILT NRC JANUARY Page: 217 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295008 AA 1.08 3.5/3.5 High Reactor Water Level Ability to operate and/or monitor the following as they apply to HIGH REACTOR WATER LEVEL : Feedwater 3

4 bank 908160 bank 908160 bank 908160 LMK 2017 ILT NRC JANUARY Page: 218 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 219 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 63 ID: 1601450 Points; 1.00 Unit 2 plant conditions are as follows:

- Reactor power is 37%

- Both CRD pumps are tripped and cannot be started 15 minutes later, 23 HCU Accumulator Trouble annunciators are alarming A GP-4 Shutdown is performed WHICH ONE of the following describes the plant response?

A. 23 rods will not insert B. All rods will insert with normal scram times C. All rods will insert with scram times greater than the Tech Spec allowable scram times for all rods D. All rods will insert with scram times greater than the Tech Spec allowable scram times for 23 rods Answer: B

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 220 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO nswer: All rods will insert with normal scram times Per ON-107, During a reactor scram, the charging header provides the initial motive force to insert the rod. Then the scram accumulator pressure accelerates the drive and reactor pressure is used in the rod insertion process but is not required. For example, a rod scrammed at 900 psig reactor pressure and zero accumulator nitrogen pressure would result in an insignificant increase in scram time. Twenty minutes is allowed to restore a tripped CRD pump if more than 1 scram accumulator is inoperable and reactor pressure is equal to or greater than 900 psig since reactor pressure is adequate to insert all control rods with or without inoperative scram accumulators.

hen this condition occurs below 900 psig reactor pressure, the mode switch is to be placed in shutdown as required by Technical Specifications. The insertion and disarming of control rods hen more than one accumulator is inoperable is performed to comply with Technical Specifications.

3 rods will not insert - all rods will insert II rods will insert with significant longer scram times - all rods will insert, scram times will not ignificantly increase II rods will insert, however, 23 rods will have significant longer scram times - see explanation Examinee must recognize at 37% power reactor is at rated pressure A Wrong - Plausible if the student mis-applies the extremely reduced reactor pressure impact on the control rod scram ability to the 23 Control Rods with reduced Scram Accumulator Pressures (i.e. - at extremely reduced RPV pressure CRD differential puressure is insufficient to insert the control rod.)

B Correct - as described above C Wrong - Plausible if the student mis-applies the reduced reactor pressure impact on the control rod scram ability to all core Control Rods (i.e. - at reduced RPV pressure rod scram times will be lengthened commencerate with the reduction in RPV pressure)

D Wrong - Plausible if the student mis-applies the reduced reactor pressure impact on the control rod scram ability to the 23 Control Rods with reduced Scram Accumulator Pressures (i.e. - at reduced RPV pressure rod scram times will be lengthened commencerate with the reduction in RPV pressure)

LMK 2017 ILT NRC JANUARY Page: 221 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 63 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.50 System ID: 1601450 User-Defined ID: Q #63- BANK Lesson Plan Objective: LG SOPS 1550.2 ON-107, Both CAD pumps are tripped and cannot be started and Topic:

23 HCU Accumulators RO: 3.3 SRO: 3.4 KA#: 295022 AA2.02 LMK 2017 ILT NRC JANUARY Page: 222 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 295022 AA2.02 RO 3.3 SRO 3.4 APE: 295022 Loss of CRD Pumps AA2. Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS :

AA2.02 CRD s stem status Low 1 - Reactivit Control 41.10 ON-107 ReV: 1

  1. !';A\ 8 LMK 2017 ILT NRG JANUARY Page: 223 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 64 ID: 1442869 Points: 1.00 Unit 1 is operating at 100% power with the following conditions; SJAE DISCH TO RECOMBINER LO FLOW annunciator alarms Which of the following identifies where this parameter can be monitored and what is an expected Steam Jet Air Ejector (SJAE) response if actual flow is 9100 Lbm/hr?

Location to monitor parameter SJAE response A. 1OC-652 Condenser panel First Stage Air Ejector "AIR" valves will close B. 1OC-652 Condenser panel Second Stage Air Ejector "STEAM" valve will close C. 1OC-673 OFF GAS panel First Stage Air Ejector "AIR" valves will close D. 1OC-673 OFF GAS panel Second Stage Air Ejector "STEAM" valve will close Answer: C Answer Explanation A Incorrect plausible to examinee who recalls that SJAE valves control stations and SJAE 2nd stage suction and discharge pressure indication are on 1OC-652 and incorrectly believes that SJAE steam flow is also here B Incorrect plausible to examinee who recalls that SJAE valves control stations and SJAE 2nd stage suction and discharge pressure indication are on 1OC-652 and incorrectly believes that SJAE steam flow is also here and incorrectly recalls which valve closes on low flow C Correct SJAE air and steam flow recorder FR-69-115 is located on 1OC-673 and 1st stage air valves will close causing a loss of condenser vacuum D incorrect plausible to examinee who does not recall which SJAE valves close on low flow LMK 2017 ILT NRC JANUARY Page: 224 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 64 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 1442869 User-Defined ID: 0#64 NEW Lesson Plan Objective: LGSOPS0069.7A iopic: Low vac RO: 4.6 SRO: 4.3 KA#: 295002 2.1.31 LMK 2017 ILT NRG JANUARY Page: 225 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

4.6/4.3 Loss of Main Condenser Vacuum 2.1.31 Ability to locate control room switches, controls, and indications, and tol determine that they correctly reflect the desired lant lineu .

LMK 2017 ILT NRC JANUARY Page: 226 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO 65 10:1588470 Points: 1.00 Initial Unit 2 plant conditions are as follows:

- Reactor power is 100%

- A group VlllA isolation occurred due to a blown fuse

- The fuse has been replaced

- Instrument Air is backing up Instrument Gas through SV-059-2288

- Drywell pressure is 1.0 psig DOWN SLOW

- Drywell venting is in progress through HV-057-211 and HV-057-217

- Primary Containment Oxygen concentration is 3.5% UP SLOW No other Operator actions are taken and Drywell pressure stabilizes at 0.8 psig and then begins to rise slowly.

The Containment Leak Detector is reading 88 cpm and steady.

WHICH ONE of the following describes the required actions for these conditions?

A. Isolate instrument air to instrument gas and restart instrument gas B. Secure venting the Drywell per OT-101, High Drywell Pressure C. Raise rate of venting per OT-101, High Drywell Pressure D. Begin inerting the Drywell per T-228, lnerting/Purging Primary Containment Answer: A Answer Explanation A Correct, rising DW pressure with rising DW 02 and instrument air backing up instrument gas is indicative of a leak in the instrument gas system. Isolating instrument air to gas is directed by OT-101 since the VII IA isolation can be reset instrument gas should be restarted per OT-101 B Incorrect, secure venting is required if DW rad level is rising along with DW pressure plausible to C Incorrect raising vent rate cannot be done since both valves are fully open. plausible to examinee who confuses venting with purging.

D Incorrect inertinq is directed from T-102 no entry for T-102 exists LMK 2017 ILT NRC JANUARY Page: 227 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 65 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 2.00 System ID: 1588470 User-Defined ID: Q# 65 MODIFIED Lesson Plan Objective: LLOT2006.1 OT-101, Drywall venting is in progress due to high drywall Topic:

1pressure RO: 3.8 SRO: 3.9 KA#: 295010 AA2.02 LMK 2017 ILT NRC JANUARY Page: 228 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

3.8/3.9 High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE :

Rev 3

    1. '."i'.'i'.'f' 7 562341 modified 562341 modified 562341 modified LMK 2017 ILT NRC JANUARY Page: 229 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 66 ID: 1682357 Points: 1.00 Consider the requirements of:

- OP-AA-108-103, locked Equipment Program The PRO is directing the restoration of a locked, manual throttle valve to a position of "5 turns OPEN".

WHICH ONE of the following describes the minimum verification(s) required for restoring this valve?

A. Requires a Peer Check, ONLY B. Requires Concurrent Verification, ONLY C. Requires an Independent Verification, ONLY D. Requires a Peer Check AND an Independent Verification Answer: B Answer Explanation B is correct Per OP-AA-108-103, section 4.2.2 ... Concurrent Verification is required.

A incorrect peer check is not used in the Locked Equipment Program C incorrect plausible to the examinee who recalls that general independent verification is a more stringent, but neglects the fact that the IV would have to unlock and reposition the valve, thus defeating the second verification.

D incorrect for the reasons stated above LMK 2017 ILT NRC JANUARY Page: 230 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 66 Info Multi le Choice Active No No 1.00 3

2.00 1682357 Q# 66 BANK LGSOPS2005A.2 Recall Controls for Restorin a Locked Manual Throttle Valve 3.9 4.3 KA#: 2.2.14 Comments:

3 N/A 2.1.8 RO 3.4 SRO 4.1 2.1.8 Ability to coordinate personnel activities outside the control room.

Low N/A 41.10 LMK 2017 ILT NRC JANUARY Page: 231 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 232 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 67 ID: 1682350 Points: 1.00 The 1A RHR Pump had been operating for 40 minutes in the full-flow test mode when it was manually secured. As soon as it was secured, it was realized that the 1A RHR Pump needed to be restarted for testing.

Which of the following describes the minimum wait time before restarting the 1A RHR Pump?

A. No wait time is required.

B. Must wait 15 minutes prior to restarting the pump.

C. Must wait 30 minutes prior to restarting the pump.

D. Must wait 60 minutes prior to restarting the pump.

Answer: A Answer Explanation

  • A is correct - per S51.8K 3.1 O For normal operations:

Pumps may only be started once an hour at rated temperature OR twice an hour at ambient temperature. Subsequent starts require a 30 minute run time at full speed OR 60 minute idle time.

Since the motor has been running for 40 minutes, it can be started and brought up to operating speed one time with no waiting time required.

~is correct B is incorrect but plausible if the examinee believes there is a 15 minute wait period requirement before restarting the Pump.

C is incorrect but plausible if the examinee believes there is a 30 minute wait period requirement before restarting the Pump.

D is incorrect but plausible if the examinee believes there is a 60 minute wait period requirement before restarting the Pump.

lrhe precaution above aoolies to all larqe motors > 2.3 Kv and is not system specific LMK 2017 ILT NRC JANUARY Page: 233 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 67 Info Question Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rnme to Complete: 0 Difficulty: 0.00 System ID: 1682350 User-Defined ID: Q 67 BANK Lesson Plan Objective:

The1 A AHR Pump had been operating for 40 minutes in the Topic:

full-flow test m RO: 3.8 SRO:

KA#: 2.1.32 LMK 2017 ILT NRG JANUARY Page: 234 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

3 N/A 2.1.32 RO 3.8 Ability to explain and apply system limits and recautions.

41.10

'Rw'.;, 2

  1. 5 bank CL-ILT-635420 LMK 2017 ILT NRC JANUARY Page
    235 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 68 ID: 1588537 Points: 1.00 An operator must perform stroke time testing of a valve required by Technical Specifications for post-maintenance testing to restore operability. The valve is motor operated with seal-in control logic and a spring return to center control switch.

To time the valve open, the operator must turn the control switch to the desired position (1) and must start the stopwatch when the (2) .

A. (1) momentarily (2) red position indication light FIRST illuminates B. (1) momentarily (2) control Switch is placed to OPEN C. (1) for a count of three {3)

(2) red position indication light FIRST illuminates D. (1) for a count of three (3)

(2) control Switch is placed to OPEN Answer: D Answer Explanation From ST-6-107-200-0 IST VALVE STROKE SURVEILLANCE LOG step 3.3:

3.3 Stroke time is defined as the time from the initiation of the actuation signal until full closed indication OR full open indication is observed.

And OP-AA-103-105, LIMITORQUE MOTOR-OPERATED AND CHAINWHEEL OPERATED VALVE OPERATIONS step 4.2.2.3:

3. When remotely operating a MOV with seal-in control logic and a spring return o center control switch, the control switch must be turned to the desired position and held for a count of three (3) to ensure there is adequate time for he seal-in contacts to make-up.

A Wrong - plausible to the student who fails to recall that the control swich must be held for a count of 3 to ensure adequate time for the seal-in contacts to make-up and to the student who mistakenly believes that the stopwatch is started when the red (open) position indication light first illuminates.

B Wrong - plausible to the student who fails to recall that the control swich must be held for a count of 3 to ensure adequate time for the seal-in contacts to make-up C Wrong - plausible to the student who mistakenly believes that the stopwatch is started when the red (open) position indication light first illuminates.

D Correct for the above reasons LMK 2017 ILT NRG JANUARY Page: 236 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 68 Info Question T e: Multi le Choice Status: Active lwa s select on test? No uthorized for ractice? No 1.00 lete: 3 3.00 1588537 Q# 68 - MODIFIED LGSOPS2010 27.C-CONDUCT OF OPS Valve Stroke - Post Maintenance Testin 2.9 2.2.21 Comments:

OP-AA-103-105 OP-LG-108-101-1004 Modified from Clinton ILT 14-1 Exam #69. (Vision ID 1097944 Modified from Clinton ILT 14-1 Exam #69. (Vision ID 1097944 Created new first half of question to replace when to stop the stopwatch LMK 2017 ILT NRG JANUARY Page: 237 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 238 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO LMK 2017 ILT NRG JANUARY Page: 239 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 69 ID: 1574760 Points: 1.00 Both Units are operating at 100% power.

Maintenance has been performed on several air lock door seals.

The following Post Maintenance Testing was performed with the resultant established SGTS flow rates at

-.25 inches of water.

Iest SGJS flow rate ST-6-076-310-1 SGTS REACTOR ENCLOSURE SECONDARY CONTAINMENT 2,250 CFM INTEGRITY TEST ST-6-076-310-0 SGTS REFUEL AREA SECONDARY CONTAINMENT INTEGRITY 820 CFM TEST Which of the following identifies the status of the Unit 1 Reactor Enclosure and Refueling Area Secondary Containment for the above conditions?

Unit 1 Reactor Enclosure Secondary Refueling Area Secondary Containment Containment A. OPERABLE OPERABLE B. OPERABLE INOPERABLE C. INOPERABLE OPERABLE D. INOPERABLE INOPERABLE Answer: B

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 240 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO rThe Maintenance of Secondary Containment door seals impacts the operability of the Secondary Containment. From the Stem the student identifies that a "Drawdown test" was performed on the Refuel Floor and the Unit 1 Secondary Containment. For the Reactor Enclosure the resultant flow of 2,250 CFM is within the surveillance requirement of 4.6.5.1.1.c.2 (less than or equal to 2,500 CFM). For the Refueling Area Secondary Containment the resultant flow of 820 CFM is NOT within the surveillance requirement of 4.6.5.1.2.( Less than or equal to 764 CFM). Based on the above information the Unit 1 Reactor Enclosure Secondary Containment is OPERABLE and the Refueling Floor Secondary Containment is INOPERABLE.

These secondary containment SBGT flow rates are ON-111 symptoms for a loss of secondary containment and as such RO must know knowledge A Wrong - Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Refueling Area Secondary Containment B Correct as described above C Wrong - Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Refueling Area Secondary Containment and the Reactor Enclosure Secondary Containment D Wrong - Plausible if the student recalls the incorrect Surveillance acceptance criteria for the Reactor Enclosure Secondary Containment LMK 2017 ILT NRC JANUARY Page: 241 of 37 4 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 69 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 2.00 Svstem ID: 1574760 User-Defined ID: Q#69 NEW Lesson Plan Objective: LGSOPS0076B.9 Topic: Secondarv Containment Qperabilitv RO: 3.2 SRO: 3.8 KA#: G2.2.36 LMK 2017 ILT NRC JANUARY Page: 242 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

3 N/A 2.2.36 RO 3.1 SRO 4.2 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for o erations.

low N./A Tech Spec 3.6.5.2.1 Tech Spec 2 3.6.5.2.2 3 ST-6-076-310-0 1 ST-6-076-310-1 7 LMK 2017 ILT NRG JANUARY Page: 243 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 70 10:1455760 Points: 1.00 You have been authorized and briefed to do work in the RCA, the work area has no physical barrier (e.g.,

door); instead, its entrance has a barricade and flashing red light.

Per RP-AA-460:

WHICH one of the following identifies the posted radiation dose rate in this area?

A. Greater than 30 mR/hr at 30 cm B. Greater than or equal to 100 mR/hr at 1 meter C. Greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter D. Greater than or equal to 500 mR/hr at 30 cm; less than 800 Rad/hr at 1 meter Answer: C Answer Explanation Per RP-AA-460, section 4.4.2.1.b.2 NOTE. .. a barricade and flashing red light can be used (in lieu of a physical barrier) only for a LHRA. Per section 4.4, the posted radiation dose rate (considering the more-conservative Exelon admin limit) for an LHRA is "greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter."

A Incorrect Plausible to the exminee who recalls 80 Mr insted of 800 B incorect Plausible to the exminee who does not recall the 1 meter limit C correct the posted radiation dose rate (considering the more-conservative Exelon admin limit) for an LHRA is "greater than or equal to 800 mR/hr at 30 cm; less than 500 Rad/hr at 1 meter."

D incorrect plausible to the examinee who reverses the 1 meter rad requirement LMK 2017 ILT NRC JANUARY Page: 244 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 70 Info Question Type: Multiple Choice Status: Active lAlways select on test? No lAuthorized for practice? No Points: 1.00 rnme to Complete: 3 Difficulty: 2.00 System ID: 1455760 User-Defined ID: 0#70 BANK Lesson Plan Objective: LLOT1760.10 Identity activities requiring drywell upper elevation access Topic:

controls RO: 3.4 SRO: 3.8 KA#: 2.3.13 LMK 2017 ILT NRG JANUARY Page: 245 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2.3.13 3.4/3.8 Knowledge of radiological safety procedures pertaining to licensed!

operator duties, such as response to radiation monitor alarms,!

containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, ali nin filters, etc.

'Rev:t, 2 fhtt):Bl~: 9 986547 bank 986547 bank 986547 bank LMK 2017 ILT NRG JANUARY Page: 246 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 71 ID: 1455767 Points: 1.00 An EO is required to enter an area in the Main Condenser Bay:

- General area radiation level is 3 Rem/hr The EO's radiation history:

- 1760 mRem cumulative exposure for the current year (TEDE)

- 19 Rem lifetime exposure to this date (TEDE)

- NRC Form 4 completed and on file

- N.o dose extensions have been obtained The work activity will take 45 minutes to complete.

Regarding the following radiation exposure limits, which one of the answer choices identifies the limit(s), if any, that will be exceeded?

1. Administrative Dose Control Level
2. NRC Exposure Limit
3. Emergency Exposure Limit A. None B. Limit #1 ONLY C. Limits #1 and #2 ONLY D. Limits #1, #2 AND #3 Answer: B Answer Explanation Calculating the EO's expected dose for this 45-minute activity:

3 Rem = 3000 mRem 3000 mRem X .75 = 2250 mRem

~dded to his current dose:

2250 mRem + 1760 mRem = 401 O mRem TEDE 4010 mRem exceeds the 2000 mRem TEDE Admin Dose Control Level of RP-AA-203, section 4.1.2.

4010 mRem does NQI exceed the 5000 mRem NRC Exposure Limit of section 4.1.1, Table 1.

N.oLdoes the 4010 mRem (4.01 Rem) exceed the 10,000 mRem (10 rem) ... for protecting station property ... Emergency Exposure Limit of section 4.5.3, Table 2.

ANSWER: Admin Dose Control Level onlv LMK 2017 ILT NRC JANUARY Page: 247 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 71 Info Question T e: Multi le Choice Status: Active No No 1.00 4

2.50 1455767 Q#71BANK LLOT1760.5 Determine if an Dose Limits will be exceeded 3.2 3.7

2.3.4 Comments

Knowledge of radiation exposure limits under normal conditions.

bank 591143 bank 591143 bank 591143 LMK 2017 ILT NRC JANUARY Page: 248 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 249 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 72 10:1649570 Points: 1.00 Plant conditions:

- Unit 1 is in OPCON 1

- Unit 2 is in OPCON 2 with GP-2, STARTUP in progress A yafui OBE EXCEEDED alarm is received and is confirmed by the U.S. Geological Survey.

WHICH ONE of the following is a required operator action?

A. Manually scram both reactors

8. Perform GP-4 Rapid Plant Shutdown on Unit 1 Manually scram Unit 2 reactor C. Perform GP-4 Rapid Plant Shutdown on both Units D. Perform GP-3 Normal Plant Shutdown on both Units Answer: A Answer Explanation Per SE-5 (Earthquake), Steps 4.2 and 4.5. The "valid" comment in the stem translates to "evidence of the seismic event" (mentioned in Step 4.5). Though Step 4.5 is not an "Immediate perator Action" initial license candidates are expected to recall manual scram/GP-4 Rapid Shutdown actions, no matter where they exist in procedure.

1:.t:L~lJ'.Q.[ig.:Jt::e!lQITil...!.;;~L.l::iiap,u:LJ::jaillJill.lilll!OWILQr:LU.!]JlJL;.NLaillJ.aU;~dfilD.J.!illL~!.aCJ:o.r...Very plausible to the examinee who considers that, whenever practical, LGS procedures direct us to perform a GP-4 Rapid Plant Shutdown (i.e., running Recirc Pumps to minimum speed and ransferring house loads to the startup buses before scramming the reactor) in order to minimize he plant transient. The fact that Unit 2 is only in OPCON 2 during a startup, the idea of simply scramming the reactor (i.e., without concern for the severity of a plant transient) makes this answer choice all the more distracting.

r.u:.J.S...:wa~~'..e.r:t.orrll:i.1:.:::a.JiQim;~1artt..:::tnuta.c!Wr:LQILDJ:llll_u.rllls.. Plausible to the exam inee who does not recognize the significance of an OBE earthquake and/or confuses it with an SSE earthquake. As such, the examinee is compelled to believe that an orderly plant shutdown of both Units is sufficient to miti ate the effects of the OBE.

LMK 2017 ILT NRC JANUARY Page: 250 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 72 Info Question T e: Multi le Choice Status: Active No uthorized for ractice? No 1.00 lete: 3 2.00 1649570 Q# 72 BANK 2015 NRG LGSOPS2000.2 SE Recall Re uirements for Manual Scram 4.0 4.2 2.4.11 4.0/4.2 Bank 558648 2015 NRG LMK 2017 ILT NRC JANUARY Page: 251 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 252 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 73 ID: 1455732 Points: 1.00 The CRS has directed performance of T-260 REACTOR PRESSURE VESSEL DEPRESSURIZATIONNENTING on UNIT 2.

  • The MSIV's are currently closed but are pneumatically functional
  • Reactor pressure is 990 psig
1. Bypass Leakage Barrier Block valves HV-41-242 and HV-41-243
2. Bypass Leakage Barrier Vent valves HV-41-240 and HV-41-241 From the above list, which valves, if required to be operated, will be operated by an equipment operator and where will the reactor steam be vented to?

Actions pertormed by an Equipment Reactor Steam will be directed to Operator A. 20NLY Main Condenser B. 1 ONLY Reactor Enclosure

c. 1 AND2 Main Condenser D. 1 AND2 Reactor Enclosure Answer: C Answer Explanation

~lthough valves are operated locally reactor enclosure or AER room there are position indicating lights in the MCR.

Section 4.2 using steam line drain vents to reactor enclosure A Incorrect both 1 and 2 are remote actions B Incorrect both 1 and 2 are remote actions and steam is directed to the main condenser C Correct both actions are performed locally and steam is directed to the main condenser D Incorrect steam is directed to the main condenser LMK 2017 ILT NRC JANUARY Page: 253 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 73 Info Question T e: Multi le Choice Status: Active lwa s select on test? No uthorized for ractice? No 1.00 lete: 3 2.00 1455732 Q# 73 NEW LGSOPS2003.3 EO actions 3.8 4.0 2.4.35 Comments:

2.4.35 3.8/4.0 Knowledge of local auxiliary operator tasks during an emergency and the resultant o erational effects.

low 9

LMK 2017 ILT NRC JANUARY Page: 254 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 255 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 74 ID: 1455708 Points: 1.00 WHICH ONE of the following requires a Unit 2 Tech Spec LCO Action that is 1-hour or less?

A. RWCU inboard PCIV HV-44-2F001 breaker trips and cannot be reset.

B. Operating at 100% power when 28 Recirc Pump trips C. Operating at 20% power when one control rod is determined to be stuck and is declared inoperable D. OPCON 1 when 022 DG fails its monthly surveillance and is declared inoperable Answer: C Answer Explanation U/2 TS 3.1.3.1.a.1 (for a stuck rod) is a "within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />" action.

U/2 TS 3.6.3.a is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />" action.

U/2 TS 3.4.1.1.a (one recirc loop not in service) is a "within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />" action.

U/2 TS 3.8.1.1.a (one DG inoperable) is a "within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />" action for demonstrating operability of lthe remaining AC sources (SR 4.8.1.1.1.a). However, Action 'e' also applies ... requiring the same SR 4.8.1.1.1.a to be performed "within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />".

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 74 Info Question T e: Multi le Choice Status: Active lwa s select on test? No uthorized for ractice? No 1.00 lete: 3 2.50 1455708 Q# 74 BANK LGSOPS00418.9 Tech S nize condition re 1-hour TS Action 3.9 4.5

.2.39 Comments:

2.2.39 3.9/4.5 Knowledge of less than or equal to one hour Technical Specification !action statements for s stems.

Lower Tech Specs bank 989362 bank 989362 bank 989362 LMK 2017 ILT NRC JANUARY Page: 257 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 258 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 259 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 75 ID: 1455175 Points: 1.00 An earthquake has occurred resulting in the breach of a wall in the Unit 1 Spent Fuel Pool (SFP).

Unit 1 SFP level is lowering, with the following:

  • Operators are NQI able to mitigate the SFP level problem using S53.0 normal makeup I response to low level in fuel storage pool or reactor well
  • An Equipment Operator on 352 elevation estimates the leakage rate is 800 gpm Operators enter TSG-4.1, 'Operational Contingency Guidelines.'

WHICH ONE of the following:

(1) identifies which method for cooling the SFP should be used FIRST ("Makeup" or "Spray"), .and.

(2) identifies if "Locally" or "External" source for 1ba1 method?

A. (1) Makeup (2) Locally B. (1) Makeup (2) External

c. (1) Spray (2) Locally D. (1) Spray (2) External Answer: c

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 260 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO his question tests the examinee's ability to use the Alternate (B.5.b) Strategies of TSG-4.1. Key points in the stem are: an estimated SFP leakage rate of 800 gpm, and the fact that the refuel loor is still accessible.

he examinee need only review Section I (SFP Cooling & Makeup), specifically, including its lowchart ("Generalized Decision Process for SFP Makeup versus Spray").

Following the decision points on this flowchart ... i.e., SFP Area Accessible? (YES); SFP Leakage Excessive (YES; see Note 3 at the bottom of the page ... anything greater than 500 gpm is excessive). As such, the FIRST method to be used is ... "Deploy Spray Locally"

'C' is correct for the above reasons. (1) Spray (2) Locally

'A' is wrong. (1) Makeup (2) Locally In the case of the Makeup method, "locally" is actually referred to as "Internal" in the TSG. Plausible to the examinee who cannot effectively use the lowchart.

'B' is wrong. (1) Makeup (2) External Plausible for the same reason as choice 'A'.

'D' is wron . 2 External Plausible for the same reason as choices 'A' and 'B'.

LMK 2017 ILT NRC JANUARY Page: 261 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Multi le Choice Active No No 1.00 6

2.50 1455175 Q# 75 BANK LGSOPS2004.01 Selectin 8.5.b Strate er TSG-4.1 3.9 4.2 G2.1.25 Comments:

2.1.25 3.9/4.2 Ability to interpret reference materials, such as graphs, curves, tables, etc.

TSG-4.1 page 6 bank 895221 bank 895221 LMK 2017 ILT NRC JANUARY Page: 262 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 263 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 76 ID: 1650711 Points: 1.00 SRO 118 15 UNIT 1 ISO PHASE BUS COOLER TROUBLE alarm actuates. An EO reports both ISO PHASE fans are tripped and cannot be started. The crew enters ON-101 , Loss of Isolated Phase Bus Cooling.

Conditions at T =2 minutes:

- Generator amps: 27,500

- MVARs: 285

- ISO PHASE temperature: 102 degrees C, up slow Conditions at T=13 minutes:

- Generator amps: 19,500

- MVARs: 45

- ISO PHASE temperature: 104 degrees C, up slow Per ON-101, which of the following actions is required?

A. Reduce MVARs to 0, if temperature rises above105 degrees C then perform a GP-4 Rapid Plant Shutdown.

B. Continue to monitor temperatures and if temperature rises above 105 degrees C then continue reducing power in accordance with GP-5, Appendix 2.

C. Reduce MVARs to 0, if temperature rises above 105 degrees C then perform load reduction to less than 7,469 generator amps.

D. Immediately lower load to less than 7,469 generator amps.

Answer: A Answer Explanation Justification:

A. Correct Answer A: Reduction of MVARs to zero is directed in ON-101, Step 2.3 prior to steps to reduce power. Step 2.4 directs power reduction to less than 20,000 amps.

Step 2.7 directs a GP-4 shutdown if power is above 25% and temperatures cannot be maintained less than 105 degrees C. 19,500 amps is approximately 62% power B. B is NOT correct because if maximum temperature is 105 and continuing to rise. A rapid plant shutdown is required. Plausible to examinee who knows the limit of 105 degrees C but either does not recall a GP-4shutdown would is required or does not recall that 105 is max limit and machine must be immediately removed and belives power reduction is appropriate.

C. C is NOT correct. ON-101 does not contain guidance to lower load to 7,469. Plausible because a loss of stator cooling will result in an EHC load set runback if stator cooling is lost with stator current> 7,469 amps.

I D. Choice Dis NOT correct. ON-101 does not direct this action. Plausible for reasons given for Choice C.

LMK 2017 ILT NRG JANUARY Page: 264 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 76 Info Question T e: Multi le Choice Status: Active lwa s select on test? No uthorized for ractice? No 1.00 lete: 3 3.00 1650711 Q#76 NEW LOT0180.6P loss of iso hase RO: 3.3 SRO: 3.4 KA#:

Comments:

295018 AA2.01 3.3/3.4 Partial or Complete Loss of Component Cooling Water. Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Component n/a new LMK 2017 ILT NRG JANUARY Page: 265 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 266 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 77 ID; 1453889 Points: 1.00 SRO Unit 2 is operating at 100% power HPCI testing is in progress A loss of EHC caused reactor pressure to spike to 1100 psig.

5 minutes after the pressure spike, Unit 2 plant conditions are as follows:

  • All SCRAM actions are complete
  • All APRMs are reading between 3.4 and 3.8 percent power
  • All squib continuity lights are lit
  • Suppression Pool temperature is 105 degrees F and rising 1 degree every 4 minutes 20 minutes after the pressure spike
  • All APRMs are still reading between 3.4 and 3.8 percent power Given
  • T-213 INDIVIDUAL CONTROL ROD SCRAM/SOLENOID DE-ENERGIZATION
  • T-215 DE-ENERGIZATION OF SCRAM SOLENOIDS
  • T-219 MAXIMIZING CAD COOLING WATER HEADER FLOW DURING ATWS CONDITIONS Which of the following lists the procedure to be used to insert rods, and if SBLC injection is required Procedures to insert rods SBLC injection required A. T-213, T-215, T-216, and T-219 Yes B. T-213, T-215, T-216, and T-219 No
c. T-217 and T-218 No D. T-217 and T-218 Yes Answer: D

!Answer Explanation LMK 2017 ILT NRC JANUARY Page: 267 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO

<< Incorrect examinee must determine that a SCRAM setpoint was exceeded and based on A power level either RPS or ARI inserted most rods as such the SCRAM air headed is depressurized air header depressurized per T-101 RC/Q13 T-217 and T-218 are directed plausible to the examinee who does not interpret the stem as a hydraulic ATWS and either does not recall the values for note 16 reactor shutdown (IRM below range 6) or miss applies step RC/Q4 B Incorrect examinee must determine that a SCRAM setpoint was exceeded and either RPS or ARI inserted most rods as such the SCRAM air headed is depressurized air header depressurized per T-101 RC/Q13 T-217 and T-218 are directed plausible to the examinee who does not interpret the stem as a hydraulic ATWS and or does not recall requirement to inject SLC prior to 11 O degrees in the suppression pool C Incorrect plausible to examinee who either does not recall the values for note 16 reactor shutdown (IRM below range 6) or miss applies step RC/Q4 and or does not recall requirement to inject SLC prior to 11 O degrees in the suppression pool D Correct examinee must determine that a SCRAM setpoint was exceeded and based on power level either RPS or ARI inserted most rods, (but must determine/ interpret that all rods did not insert to the NON-ATWS position of beyond 02), as such the SCRAM air headed is depressurized. It the air header is depressurized per T-101 RC/Q13 T-217 and T-218 are directed and pool temperature is rising indicating a steam input to pool as such the SRO candidate must recognize (without reference) that TRIPS require him to order SLC injection prior to pool exceeding 110 degrees per T-101-RC/Q-16

-101 .,.

Insert control rods using one OR more of the following:

Scram valves Scram valves Open Closed

  • Vent/drain *Scram solenoids scram discharge (T-215) volume (T-217) *Air header (T-216)
  • Withdraw line *Maximize CRD cooling vent (T-218) water flow (T-219)

RCJQ-13 *I

-101 LMK 2017 ILT NRC JANUARY Page: 268 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO I BEFORE Supp Pool temp reaches 110°F, I THEN inject SLC (848.1.B. App. 1)

L_ ~-

RC/Q-16 - ----------

LMK 2017 ILT NRC JANUARY Page: 269 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 77 Info Question Type: Multiple Choice Status: Active

~lwavs select on test? No

[Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 3.00 System ID: 1453889 User-Defined ID: 0#77 NEW Lesson Plan Objective: LGSOPS1560.06 Topic: SRO Pool temperature RO: 4.0 SRO: 4.1 KA#: 295037 EA2.04 LMK 2017 ILT NRG JANUARY Page: 270 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR LMK 2017 ILT NRC JANUARY Page: 271 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 78 10:1433288 Points: 1.00 SRO Unit 1 is operating at 100% power At 13:02 the following annunciator was received in the MCR: 006-1-2-L CONT EL 254 PB WEST.

  • The fire is in the static inverter room in the MCR annunciator fuse panel
  • At 13:12 the fire brigade leader reports the fire is extinguished
  • As a result of the fire MCR annunciator panel 107 REACTOR AND 003 RAD have lost power
  • The CRS entered ON-122 for the loss of annunciators Which of the following identifies an additional procedure the CRS is required to enter and the EAL declaration, if any?

Additional Procedure entered EAL declaration reQuired A. T-104 None B. T-104 Unusual Event C. T-103 None D. T-103 Unusual Event Answer: C

~nswer Explanation A Incorrect ON-122 provides direction for the TRIP procedure to enter if annunciator panels which contain entry conditions to T-103 OR T-104 are lost. ON-122 step 4.4 directs T-103 entry plausible to the examinee who incorrectly recalls which Trip procedure to enter. The second part is correct the fire is extinguished in less than 15 minutes so no HU3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 MCR indication no longer applies B Incorrect Incorrect ON-122 provides direction for the TRIP procedure to enter if annunciator panels which contain entry conditions to T-103 OR T-104 are lost. ON-122 step 4.4 directs T-103 entry plausible to the examinee who incorrectly recalls which Trip procedure to enter. The second part is incorrect the fire is extinguished in less than 15 minutes so no H U3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 no longer applies C Correct since the annunciator panel that lost power has T-103 entry condition (DIV 1-4 steam leak detection) ON-122 will direct entry to T-103 for performance of T-290 The second part is correct the fire is extinguished in less than 15 minutes so no HU3 entry and per the last rev of EP-AA-1008 addendum 3 MU4 no longer applies D Incorrect plausible to the examinee who recalls T-103 entry is required but incorrectly believes either MU4 or HU3 should be ceclared.

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EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 78 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 4.00 System ID: 1433288 User-Defined ID: Q# 78 NEW Lesson Plan Objective: LOT1550.03 Topic: SRO Fire protection RO: 3.1 SRO: 3.6 KA#: 600000 AA2.17 LMK 2017 ILT NRC JANUARY Page: 273 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

RO 600000 AA2.17 301 /3.6 Plant Fire on site Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:

AA2.17 Systems that may be affected b the fire 2

.Rev1~ 3 2

,<:.~;, ;'~'

<<L,'.: 0 LMK 2017 ILT NRG JANUARY Page: 274 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 275 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 79 ID: 1454790 Points: 1.00 SRO Unit 1 is in OPCON 1

  • While the FIN team is investigating the pressure regulator becomes detached from the air line.
  • The Fin team closes HV-076-196 (AS) to stop the leak.
  • After the air isolation valve is closed the FIN team reports the status to the MCR.
  • The RO reports that neither SBGT fan is running OVERRrDE FROM ZS-76-IOOA ! G.4 l S--- - - -

ISO TRIP r-*-------------- REACToR ENCLOsuRE ISOLATION SIGNAL FROM NOTE I CHANNEi. A 1

r--- ~~

C881

~ mi~

I 1 1 I I~~ ~

'*1*1 I L~:AI-~ C881

~ a.313'*0' FPD-206-1<1 I FROM ZS-76-IOOB SOVERRIDE

<SH.2 G..5l M-26

  • { G,4 J l..

1~

/:'.

y *-.f R r- - ISO TRIP

~ ISO .TRI!"

REACTOR ENCLOSURE !SOI.A TION SIGNAL FROM NOTE I CHANNR S 1occ101 11 css1 ~c R~~~~ . - -------

1197-ZS ~

~I ~

T . ~~-t lSOlS!

~- HS Ir-~ I ~*~ I HO 1ll1~:el ~ ---=i

  • c--=---=---=---=---=---=--=- l I '

Which of the choices below correctly identifies the INOPERABLE SGTS Subsystem(s) AND a required TS action?

INOP subsystem(s) TS action A. ONLY A Restore subsystem within 7 days B. Both AAND B Begin a shutdown within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

c. ONLY A Restore subsystem within 14 days D. Both A and B Restore subsystem within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Answer: A LMK 2017 ILT NRC JANUARY Page: 276 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer Explanation A Correct Loss of air will cause HV-076-0196 to fail open this should start A SBGT only.

failure to start makes A SBGT INOP this is a 7 day LCO B Incorrect plausible to the examinee who does not recall or cannot determine from information provided that one valve opening does not start both trains of SBGT. T.S action would be correct if both trains were INOP C Incorrect A train only is correct however the T.S action is incorrect plausible to examinee who confuses SBGT T.S with CREFAS T.S D Incorrect only A is INOP and T.S is for one train INOP LMK 2017 ILT NRC JANUARY Page: 277 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 79 Info Question Type: Multiple Choice Status: Active

~lwavs select on test? No

~uthorized for practice? No Points: 1.00

[Time to Complete: 4 Difficulty: 3.00 System ID: 1454790 User-Defined ID: Q# 79 NEW Lesson Plan Objective: LOT0200.13 rropic: SRO SBGT RO: 3.1 SRO: 4.2 KA#: 295019 2.2.36 LMK 2017 ILT NRC JANUARY Page: 278 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

3.1/4.2 Partial or Complete Loss of Instrument Air Ability to analyze the effect of maintenance activities, such as degraded I power sources, on the status of limiting conditions for o erations.

LMK 2017 ILT NRC JANUARY Page: 279 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 80 10:1454228 Points; 1.00 SRO Plant conditions are as follows;

  • Reactor power is 30% down slow
  • Reactor level is -65 inches down slow
  • All steps up to and including LQ-19 of T-117 are complete
  • Reactor pressure is being maintained with SRVs
  • The main condenser vacuum breakers were opened With regard to the procedures listed below, which of the choices identifies the system(s) utilized in the EOP mitigation strategy for level control after the turbine trip until the ATWS is terminated?

T-251, Establish A HPCI Flow path Via Feedwater Only T-270, Terminate and Prevent Injection Into The RPV S06.1.D, Post SCRAM Level Control A. HPCI per T-251 but NOT RCIC per T-270 B. RCIC per T-270 but NOT HPCI per T-251 C. HPCI per T-251 AND RCIC per T-270 D. Condensate Pumps per S06.1.D Answer: C Answer Explanation A Incorrect plausible to the examinee who does not recall that T-270, terminate and prevent injection to the RPV allows RCIC to inject during an ATWS.

B Incorrect although RCIC will be injecting it is not suficient to maintain level also HPCI can be used for after T-270 is complate and the SRO moves to stepLQ-119 which will allow HPCI through feedwater only per T-251 C Correct post turbine trip vacuum breakers are opened condensate is not available due to ATWS and pressure being maintained 990-1096 HPCI is available for level control through feedwater per T-251 and RCIC is allowed to inject per T-270 D Incorrect although cond. pps are available with an ATWS in progress reactor pressure will not be lowered per stop sign in T-101 RCP-18 LMK 2017 ILT NRC JANUARY Page: 280 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 80 Info Multi le Choice Active No No 1.00 3

3.00 1454228 Q# 80 NEW LGSOPS1560.06 SRO ATWS turb tri 3.7 4.7 295005 2.4.6 Comments:

295005 2.4.6 3.7/4.7 Main Turbine Generator Trip Emergency Procedures I Plan Knowledge of EOP miti ation strate ies.

43.5 T-101 Rev< 2 ft;s:;{\ 2 LMK 2017 ILT NRG JANUARY Page: 281 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 282 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 283 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 81 10:1433008 Points: 1.00 SRO A LOCA occurred on unit 1 Plant conditions are as follows:

  • Reactor water level is - 10 inches steady
  • Reactor pressure is 960 psig steady
  • Suppression pool water level is 15 feet steady
  • Suppression pool water temperature on SPOTMOS Tl-41-101 A & B is 135° F up slow
  • B RHR is in suppression pool cooling
  • B RHR suction temperature is 149° F LMK 2017 ILT NRC JANUARY Page: 284 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Given the following information:

CURVE SP/T-1 LEGEND

~ RPV PRESS 0 - 55 psig 56 - 300 prig

~ 301 - 500 psig

--L 501 - 700 prig 701 - 900 psig 001 - 1170 prig CURVE SP/T-1

_J HEAT CAPACITY TEMP. LIMIT 25(}

230 21()

CL L- 19()

I e 170 E

i! 15(}

80.. BO c:.

0

.ill lll}

!Q.

Q.

I en 9()

70 50 j(}

12 Suppression Pool Water Level (ft)

Which of the following (1) is required to be directed by the CRS and (2) The reason for this action?

A. (1) Depressurize the reactor to <900 psig per T-102 (2) Suppression pool temperature is approaching HCTL Limit S. (1) Emergency Slowdown IAW T-112 (2) HCTL is being exceeded C. (1) Depressurize the reactor to 750 psig per T-102 (2) HCTL is being exceeded D. (1) Emergency Slowdown IAW T-112 (2) Suppression pool temperature is approaching HCTL Limit LMK 2017 ILT NRC JANUARY Page: 285 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer: B Answer Explanation A Incorrect (1) Depressurize the reactor to <900 psig per T-102 (2) Suppression pool temperature is approaching HCTL Limit HTCL is being exceeded, a blowdown is required per SPfr-7 of T-102 This action and reason are plausible to the examinee who does not recall T-102 note 2 which makes the Tl-41-101 A&B not usable B Correct HTCL is being exceeded so a blowdown is required per T-112 from step SPfr-8 of T-102 C Incorrect (1) Depressurize the reactor to <900 psig per T-102 (2) HCTL is being exceeded Plausible to the examinee who confuses step SPfr-7 (cannot be maintained) with steps like SP/L-15 (cannot be Restored and Maintained D Incorrect (1) Emergency Slowdown IAW T-112 (2) Suppression pool temperature is approaching HCTL Limit Plausible to the Examinee who does not recognize that HCTL has already been exceeded and believe a blowdown is warranted prior to exceeding HCTL WHEN WHEN safe side of safe side of Curve Curve SP/L-t SPIT-1 CANNOT CANNOT ' '"'-..

be restored be maintained, AND

~ maintained, contim.1e I.t:ifl1 continue SP!T-7 I

  • L SPlL-15
  1. 2 I

SPOTMOS probes located at Supp Pool level of 17. 8 ft. RHR suction temp it h RHR operating below 17. 8 ft is alid Supp Pool temp.

LMK 2017 ILT NRG JANUARY Page: 286 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 81 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 1433008 User-Defined ID: Q#81NEW Lesson Plan Objective: LGSOPS1506.6 Topic: SRO Pool temp RO: 4.2 SRO: 4.2 KA#: :295026 2.4.47 LMK 2017 ILT NRC JANUARY Page: 287 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Comments:

295026 2.4.47 4.2/4.2 Suppression Pool High Water Temperature 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

LMK 2017 ILT NRC JANUARY Page: 288 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 82 10:1454368 Points: 1.00 SRO Unit 2 is operating at 100% power, with a normal electrical lineup.

  • A grid disturbance results in 500 KV grid voltage lowering to 497 KV Which of the choices identifies the adverse generator condition that is prevented by adjusting VARs as directed by E-5, Grid Emergency and if Technical Specification 3.8.1.1., Sources Operating entry is required?

Adverse condition TS 3 8 1 1 Entry Required A. Under Excitation Yes B. Under Excitation No

c. Overheating No D. Overheating Yes Answer: D Answer Explanation rrhe examinee must understand that lowering grid voltage will cause VARS to rise. Excessive vars twill lead to machine overheating. While lowering power will reduce vars it will not both comply with

~he LD request for max MWE and stabilize the plant.

A Incorrect Over heating the stator windings is correct. Plausible to candidate who does not recall basis for VAR limits and machine heating B Incorrect will not maintain max MWe and under excitation would be correct if voltage was rising resulting in lowering VARS on the main generator (i.e., move down on the Generator Capability Curve). T.S entry is requireddue to bus voltage <498 D correct reducing vars will reduce heat from the stator The given conditions (lowering grid voltage) will cause the generator automatic voltage regulator to attempt to raise grid voltage, causing the generator to pick up additional VARS (i.e., move up on the Generator Capability Curve). Without operator action, this would result in exceedingthe generator capability curve T.S Entry is required due to bus voltage <498 C This would be true if grid voltage was rising, resulting in lowering VARS on the main generator (i.e., move down on the Generator Capability Curve). I>entry is required LMK 2017 ILT NRG JANUARY Page: 289 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 82 Info Question Tvoe: Multiple Choice Status: Active Alwavs select on test? No Authorized for practice? No Points: 1.00 rfime to Complete: 3 Difficulty: 3.00 Svstem ID: 1454368 User-Defined ID: Q#82 NEW Lesson Plan Objective: LGSOPS0032.10 rropic: SRO RO: 3.6 SRO: 3.8 KA#: 70000 A2.10 LMK 2017 ILT NRC JANUARY Page: 290 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Comments:

APE: 700000 A2.10 3.6/3.8 Ability to determine and/or interpret the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:AA2.10 Generator overheating and the re uired actions LMK 2017 ILT NRC JANUARY Page: 291 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 292 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 83 10:1455099 Points: 1.00 SRO Unit 1 was operating at 100% power when the following occurred

  • Reactor SCRAM on HI Drywall pressure
  • Drywall pressure is currently at 12 psig
  • Drywall radiation monitors are reading 200 R/hr up slow
  • RPV Level is unknown T-116 step RF-3 directs assessing core damage Which of the following describes if core damage is occurring and the required action to take based on the conditions given above?

Core Damage Required Action A. Is occurring Continue in T-102 and T-116 B. Is occurring EnterSAMPS

c. Is NOT occurring Continue in T-102 and T-116 D. Is NOT occurring EnterSAMPS Answer: B

\Answer Explanation LMK 2017 ILT NRC JANUARY Page: 293 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE : Drywell radiation levels The candidate must determine that a steam leak into primary containment exists causing the DW pressure ise and that there is indication of core damage from the given radiation levels in containment and as such SAMPS should be entered and TRIPS exited.

TRIPS NOTE 19 8 "Core damage is occuring" refers to ongoing fuel degradation caused by loss of Adequate Core Cooling (TSG-3.8). Indications include:

- Rising Pri Cnt radiation levels

- Rising Pri Cnt H 2 levels

- Rising MSL, SJAE, offgas OR Rx bldg radiation levels

~ RPV Jevelfpressure history prior to loss of RPV level indication From TSG-3.8

(-300 µCi/gm coolant activity dispersed in the drywell)

From EP-AA-1008 Addendum 3 LMK 2017 ILT NRG JANUARY Page: 294 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO FC Initiating Condition:

Primary Containment Radiation Operating Mode Applicability:

1, 2, 3 Fission Product Barrier (FPB) Threshold:

LOSS Drywell radiation monitor reading> 1.90 E+02 Rfhr (190 Rfhr).

Basis:

The radiation monitor reading corresponds to an instantaneous release of all rea coolant mass into the primary containment, assuming that reactor coolant act*

equals 300 µCi/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate ra e of 2% to 5% fuel dad damage. Since this condition indicates that a significant amou t of fuel dad damage has occurred, it represents a loss of the Fuel Clad Barrier.

The radiation monitor reading in this threshold is higher than that specified for R S Barrier RC5 Loss Threshold since it indicates a loss of both the Fuel Clad Barner a d the RCS Barrier_ Note that a combination of the two monitor readings appropriat ty escalates the emergency classification level to a Site Area Emergency.

There is no Fuel Clad Barner Potential loss threshold associated with Prima Containment Radiation.

Basis Reference(s):

1. NEI 99--01Rev6, Table 9-F-2 A Incorrect Samps are required to be entered if core damage is occurring. TRIP note 19 reminds the SRO of indications of core damage. one of these indications is rising containment radiation. Plausible to the candidate that believes even with core damage under the current circumstances SAM PS are not required to be entered.

B Correct: TRIP note 19 reminds the SRO of indications of core damage. one of these indications is rising containment radiation. SAMPS are entered if core damage exists per note 19 core damage does exist C Incorrect: Core Damage is occurring. Plausable to the candidate that incorrectly determines that Radiation levels need to be higher than 200 R/hr to indicate core damage.

D Incorrect: Core Damage is occurring. Plausable to the candidate that incorrectly determines that Radiation levels need to be higher than 200 R/hr to indicate core damage.

LMK 2017 ILT NRC JANUARY Page: 295 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 83 Info Question T e: Multi le Choice Status: Active No No 1.00 3

2.00 1455099 Q# 83 NEW LGSOPS1560.6 SRO DW ress and rad monitorin 3.3 3.6 295010 AA2.03 Comments:

SRO 2

295010 AA2.03 3.3/3.6 High Drywell Pressure Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE :

Dr well radiation levels lower 5

43.5 LMK 2017 ILT NRC JANUARY Page: 296 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 297 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 298 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 84 10:1455896 Points: 1.00 SRO Unit 1 was at 100% power when a condenser vacuum leak developed.

Power has been reduced to 70% with condenser vacuum continuing to lower.

Off gas flow has risen from 20 SCFM to 75 SCFM Current condenser vacuum is 21.2 "Hg down slow.

Current offgas recombiner outlet temperature is 440 °F Based on the given plant conditions WHICH ONE of the following identifies the action(s) required and follow up procedure to be directed per OT-116 "Loss of Condenser Vacuum"?

Action(s) reQuired Follow up procedure to direct A. Manually TRIP Main Turbine WITHOUT MA-AA-716-050-1000, Condenser Air performing a GP-4 shutdown In-leakage Testing Guide And Limits B. Manually TRIP Main Turbine WITHOUT ON-103, Control Of Sustained performing a GP-4 shutdown Combustion In The Off Gas System

c. Manually TRIP Main Turbine AFTER MA-AA-716-050-1000, Condenser Air performing a GP-4 shutdown In-leakage Testing Guide And Limits D. Manually TRIP Main Turbine AFTER ON-103, Control Of Sustained performing a GP-4 shutdown Combustion In The Off Gas System Answer: A

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 299 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO From the stem of the question the student identifies that 21.2" Hg condenser vacuum. Based on

~his information the Main Turbine should have tripped on Low Vacuum (set point of 21.5 " Hg)

OT-116 Attachment 1 step 1:

1. IF condenser vacuum reaches 21.5" Hg Vac. as confirmed by Control Room instrumentation, rTHEN manually TRIP Main Turbine.

~dditionally, the Bases of OT-116 states 6.1 If Condenser vacuum drops to the Main Turbine trip setpoint, the operator is directed to manually trip the turbine. This action is specified to ensure Main Turbine operation is suspended for Condenser vacuum conditions less than the automatic trip setpoint value. This will minimize

~he potential for Condenser/Turbine exhaust hood over pressurization and resultant rupture of the diaphragms on each Condenser shell. It should be noted that a Main Turbine trip at Reactor powers above the Turbine Trip Scram bypass setpoint (nominal 29.5% rated thermal power) will result in a Reactor scram. This protective action is expected and should not limit the operator's actions in ripping the Main Turbine.

This acknowledges that the priority is to trip the turbine and that a reactor scram should be expected if power is above 29.5%.

Additional information provided in the stem of Recombiner outlet temperature of 440 °F was included to make ON-103 distractor more plausible. Value of 440 °F was derived based on normal full power recombiner performance results in an outlet temperature of 480 °F. For additional reference the setpoint for ARC-MCR-127 81, 1 Unit Recombiner Outlet Hi Temp does not occur until 840 °F.

A Correct as described above MA-AA-716-050-1000 is directed from OT-116 as a follow up action B Wrong - Plausible if the student confuses the bases for breaking condenser vacuum on loss of sealing steam with the bases for tripping the Main Turbine on low condenser vacuum. From the stem off gas flow increases from 20 to 75 SCFM, symptoms for ON-103 Control of sustained combustion in the off gas system include a sudden change in off gas system flows, although this is one symptom and ON-103 is directed from OT-116 if indications of combustion exist in the off gas system the SRO must determine that the increase in flow is the result of a leak and not combustion supported by offgas recombiner outlet temperature in the normal range.

C Wrong - Plausible if the student does not recognize that condenser vacuum is below the Turbine trip setpoint (21.5 " Hg) and applies normal step OT-116 step 3.4 actions to perform a GP-4 shutdown.

D Wrong - Plausible if the student does not recognize that condenser vacuum is below the Turbine trip setpoint (21.5 " Hg) and applies normal step OT-116 step 3.4 actions to perform a GP-4 shutdown and if the student confuses the bases for breaking condenser vacuum on loss of sealing steam with the bases for tripping the Main Turbine on low condenser vacuum.From the stem off gas flow increases from 20 to 75 SCFM, symptoms for ON-103 Control of sustained combustion in the off gas system include a sudden change in off gas system flows, although this is one symptom and ON-103 is directed from OT-116 if indications of combustion exist in the off gas system the SRO must determine that the increase in flow is the result of a leak and not combustion supported by offgas recombiner outlet temperature in the normal range.

LMK 2017 ILT NRC JANUARY Page: 300 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 84 Info Question Type: Multiple Choice Status: Active

~lways select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 4.00 System ID: 1455896 User-Defined ID: 0#84 NEW Lesson Plan Objective: LGSOPS1540.5 (OT-116)

Topic: SRO- Loss of Condenser VAC RO:

SRO: 4.4 KA#: 295002 2.4.49 LMK 2017 ILT NRC JANUARY Page: 301 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 295002 2.4.49 SRO 4.4 APE: 295002 Loss of Main Condenser Vacuum 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system com onents and controls.

Hi h 3 - Reactor Pressure Control 43.5 Rev;+' 3

  1. ~;:1tt 8 LMK 2017 ILT NRG JANUARY Page: 302 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 303 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 85 ID: 1455121 Points: 1.00 SRO An emergency has been declared due to a steam leak in the Unit 2 Reactor Enclosure. The following alarms are in:

SOUTH ST ACK HI RAD SOUTH STACK HI HI RAD Unit 2 reactor enclosure HVAC rad monitors read as follows

- Unit 2 RE Exhaust Rad RRSH-26-2R605A =1.5 mR/hr RRSH-26-2R605B = 1.4 mR/hr RRSH-26-2R605C = 1.3 mR/hr RRSH-26-2R605D = 1.5 mR/hr All available methods to isolate the leak have been attempted without success.

The following MCA radiological effluents indications exist:

- WIDE RANGE MONITOR RE26076-4 = 2.224E+02 µCi/Sec

- WIDE RANGE MONITOR RE26076-2 = 1.136E-06 µCi/cc

- NORTH ST ACK VENT RE26075A-1 = 2.992E-10 µCi/cc

- NORTH ST ACK VENT RE26075B-1 = 2.927E-10 µCi/cc

- SOUTH ST ACK VENT RE26285A-3 = 4.584E-04 µCi/cc

- SOUTH ST ACK VENT RE26285B-3 = 4.182E-04 µCi/cc Table R1 - Effluent Monitor Thresholds General Emergency Site Area Emergency Alert Unusual Event 1.92 E+08 µCi/sec 1.92 E+07 µCi/sec 1.92 E+06 µCi/sec 2.20 E+04 µCi/sec North Stack (WR Monitor: RIX-26-076-4) 2.71 E-01 uCi/cc 2.71 E-02 uCi/cc 2.71 E-03 uCi/cc 3.09 E-05 uCi/cc South (Unit 1: RY26-185A-3 / RY26-185B-3 or Unit 2 RY26-285A-3 / RY26-285B-3)

Stack WHICH ONE of the following identifies the CURRENT source of the offsite release and the required procedure action?

A. North Stack Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination B. North Stack Enter and execute T-104 Radiological Release C. South Stack Enter and execute T-104 Radiological Release D. South Stack Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination LMK 2017 ILT NRG JANUARY Page: 304 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer: A Answer Explanation ANSWER North Stack, Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination: Correct. With Reactor Enclosure Exhaust Rad greater than 1.35 mR/hr, a Secondary Containment Isolation will occur and the release will continue through Standby Gas which discharges through the North Stack.

With SOUTH STACK HI HI RAD in alarm, the ARC directs performance of ST-6-104-880-0. The Unit 2 South Stack Noble Gas channel is below the ALERT threshold of table R-1, therefore meeting T-104 entry is not required.

DISTRACTOR North Stack, Enter and execute T-104 Radiological Release:

Incorrect, Release point correct but the ALERT limit has not been exceeded for entry into T-104.

Plausible to the examines who does not recall the T-104 entry (alert rad level)

DISTRACTOR South Stack, Enter and execute T-104 Radiological Release:

Incorrect, the release rates are below any of the EAL thresholds and T-104 entry is not required since no ALERT thresholds have been met for release rates. Also, the South Stack release will stop following a Secondary Containment isolation signal.

Plausible to the examines who does not recognize that the unit 2 reactor hvac has isolated and does not recall the T-104 entry (alert rad level)

DISTRACTOR South Stack, Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination: Incorrect, the South Stack release will stop following a Secondary Containment isolation signal.

Plausible to the examines who does not recognize that the unit 2 reactor hvac has isolated LMK 2017 ILT NRC JANUARY Page: 305 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 85 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00

!Time to Complete: 4 Difficulty: 2.50 System ID: 1455121 User-Defined ID: Q# 85 BANK Lesson Plan Objective: LLOT1790.4 (SRO) Assess Rad Effleunt EAL Table to determine release Topic:

point and required action RO: 3.6 SRO: 4.3 KA#: 295017 AA2.04 LMK 2017 ILT NRG JANUARY Page: 306 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

295017 AA2.04 3.6/4.3 High Off-Site Release Rate Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: tSource of 43.5 T-104 13 EP-AA-1008 2

addendu 3 2012 Cert Exam 1006662 2010 NRC exam 2012 Cert Exam 1006662 2010 NRG exam 2012 Cert Exam 1006662 2010 NRG exam also 295038EA2.04 4.1 /4.5 LMK 2017 ILT NRC JANUARY Page: 307 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 308 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO 86 ID: 1659209',

  • Points: 1.00 SRO Unit 1 is operating at 100% power when the following occurs; T=10:00
  • The following alarms come in o 109-A1, 1 SERVICE WATER HI RADIATION o 109-A2, 1 SERVICE WATER RAD MONITOR HI Hl/INOP DNSCL o 109-81, 1 REAC ENCL COOLING WATER HI RADIATION T= 10:15
  • Chemistry reports the service water alarms are valid with the following readings o 6 times normal full power background (NFPB)

T= 11:17

  • Chemistry reports the following service water rad monitor readings o 6.2 times normal full power background (NFPB)
  • Chemistry reports that an analysis of the effluent shows a dose of 3 mRem TEDE for 60 minutes of exposure Which of the following describes the component to isolate per S10.0.A, Service Water High Radiation, to reduce the radioactive input to service water, and the required EAL declaration if any?

Component to isolate EAL declaration A. The in-service RWCU NON-regen UNUSUAL EVENT heat exchanger B. The in-service RWCU NON-regen NONE heat exchanger C. The in-service RECW heat exchanger UNUSUAL EVENT D. The in-service RECW heat exchanger NONE Answer: c

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 309 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO The SRO candidate must determine that the SW rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3, even though service water does not directly discharge to he river A incorrect although RWCU is a cause for RECW hi rad, there are other possibilities (RWCU pp, recirc seal) as such the S10 procedure will direct removal of the in service RECW heat exchanger.

B incorrect although RWCU is a cause for RECW hi rad, there are other possibilities (RWCU pp, recirc seal) as such the S1 O procedure will direct removal of the in service RECW heat exchanger. No EAL is plausible if the candidate does not recall that the service water rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3 C correct candidate determine SW hi hi rad is a result of the RECW hi rad and correctly recalls 810.0.A step 4.7 isolate RECW heat exchanger.and correctly determines UE for effluent monitor

>2 times alarm value and hat the service water rad monitor is a discharge permit specified monitor per OP-LG-1008 addendum 3 D incorrect plausible to examinee who miss uses EAL and or does not recognize that the service water rad monitor is a discharqe permit specified monitor per OP-LG-1008 addendum 3 LMK 2017 ILT NRC JANUARY Page: 310 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 86 Info Question Type: Multiple Choice Status: Active lA.lways select on test? No lA.uthorized for practice? No Points: 1.00 lrime to Complete: 2 Difficulty: 3.00 System ID: 1659209 User-Defined ID: Q# 86 NEW Lesson Plan Objective: LOT1710.08 lropic: SW rad RO: 2.9 SRO: 3.0 KA#: 400000 A2.04 LMK 2017 ILT NRC JANUARY Page: 311 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2 400000 A2.04 2.9/3.0 Component cooling water system (CCWS) Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Radiation monitorin s stem alarm 43.4,5 S13.0.B LMK 2017 ILT NRG JANUARY Page: 312 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 313 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 87 ID: 1455692 Points: 1.00 SRO Unit 2 is operating at 100% power when the following alarms are received simultaneously:

  • ARC-MCR-207-B2, SRV ACOUSTIC MONITOR POWER LOSS OR CABLE FAULT
  • ARC-MCR-208-AS, OPRM/APRM TROUBLE
  • ARC-MCR-208-04, RBM DOWNSCALE/TROUBLE
  • ARC-MCR-221-FS, 2A APRM UPS INVERTER TROUBLE
  • No other alarms were received on alarm panel 208 Given the above annunciators, which of the following is required?

A. Insert an "A" RPS half SCRAM per OT-117, RPS Failure B. Isolate RWCU and enter Tech Spec. 3.6.3 C. Enter OT-114, Inadvertent Opening Of A Relief Valve D. Enter ON-113, Loss Of RECW Answer: A

!Answer Explanation LMK 2017 ILT NRC JANUARY Page: 314 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO

!The listed annunciators in the stem are expected for a loss of 2A-Y185 2A APRM UPS Power.

Upon a loss of 2A-Y185 the appropriate Event procedure to enter is E-2AY185. Loss of power to 12AY185 will cause a loss of power to APRM voter units 1 and 3 causing a half scram

!The Note prior to step 2.3 of E-2AY185 states:

  • ARC-MCR-208, A1, "NEUTRON MONITORING SYSTEM TRIP"
  • ARC-MCR-208, 81, "AUTO SCRAM CHANNEL A 1"
  • ARC-MCR-208, 82, "AUTO SCRAM CHANNEL A2" Stem conditions state no other alarms were received on alarm panel 208, candidate must recognize an RPS failure occurred Initial Action in step 2.3 states:

2.3 IF "A" RPS fails to actuate a HALF SCRAM condition THEN ENTER OT-117 "RPS Failures" AND EXECUTE concurrently.

Within OT-117, if there is a failure to half scam, step 3.2.1 directs inserting a manual half scram on the affected RPS side Candidate is required to demonstrate an understanding of the difference between a loss of 12AY185 2A APRM UPS power and 2AY160 RPS UPS power.

Candidate must also recall actions required by E-2AY185/E-2A Y160 and apply those actions to

~he given conditions. An RPS half SCRAM occurs on loss of either power supply where as a RWCU isolation only occurs on a loss of 2A-Y160.

A Correct for the above reasons 8 Wrong - Plausible if the candidate confuses the expected plant response on the loss of 2A-Y185 and believes that a RWCU NSSSS Isolation should have occurred and did not and directs the RWCU system be isolated to comply with Tech Spec 3.6.3 C Wrong - Plausible if the candidate recalls procedure E-2AY185 directs entering OT-114 (step 2.4) but does not recall that this step only applies if an SRV is confirmed to be open.

D Wrong - Plausible if the candidate mis-diagnosis the event as a loss of 2AY-160 and recalls the first action step of E-2A Y160 is to enter ON-113 LMK 2017 ILT NRG JANUARY Page: 315 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 87 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 1455692 User-Defined ID: Q #87 NEW Lesson Plan Objective: LGSOPS007 4A.11 rropic: SRO - Impact of Power suppy dearaded in APRM/LPRM System RO: 2.7 SRO: 3.1 KA#: 1215005 A2.01 LMK 2017 ILT NRG JANUARY Page: 316 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

RO 2

215005 A2.01 RO 2.7 SRO 3.1 215005 Average Power Range Monitor/Local Power Range Monitor A2. Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or LMK 2017 ILT NRG JANUARY Page: 317 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 318 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 319 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 88 ID: 1455679 Points: 1.00 SRO Unit 1 is in OPCON 4 with the following battery conditions:

Battery Float Current 1A10101 2.6 1A20101 2.1 1810101 0.8 1820101 1.6 1C0101 1.1 100101 1.2 WHICH ONE of the following:

(1) Identifies the battery, that if restored to Operable, would allow exiting Tech Spec LCO 3.8.2.2?

And (2) Correctly completes the following about the design of the Class 1E batteries:

Each Class 1E battery bank is sized to have sufficient capacity without its charger to independently supply the large break LOOP/LOCA load profile tor (2)

A. (1) 1A10101 (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. (1) 1C0101 (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

c. (1) 1A10101 (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
0. (1) 1C0101 (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Answer: B

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 320 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Provide

References:

U1 Tech Spec 3.8.2.2 Candidate will assess the float current table and determine that there are 4 batteries INOP due to heir float currents. 1A1D101 and 1A2D101 are both INOP due to exceeding 2 amps, 1CD101 and 1DD101 are both INOP due to exceeding 1 amp.

rTech Spec 3.8.2.2 LCO requires a minimum of two divisions to be Operable. This is not the case due to Div 1, 3, and 4 all being INOP due to associated battery float current limits being exceeded. Action b.2 applies to all 4 batteries and is the source of part 1 of the answer. If action b2 is successful for 1CD101, Unit 1 will now have two Operable divisions (Division 2 and Division

3) and LCO 3.8.2.2 may be exited. However, if action b2 is successful for 1A1D101, three divisions will remain INOP due to Div 1 remaining INOP due to battery 1A2D101 remaining INOP.

From LGS UFSAR section 8.3.2.1.1.2 Class 1E Batteries Each Class 1E battery bank is sized to have sufficient capacity without its charger to independently supply the large break LOOP/LOCA load profile for A hours.

A Wrong - Plausible to the candidate that mistakenly believes that restoring 1A1 D101 to Operable status would result in Division 1 being restored to Operable and the candidate that applies the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> duration associated with establishing an alternate AC Source described in SE-1 "Loss of all AC Power (Station Blackout)" Bases coping time from the Station Blackout Analysis.

B Correct for the reasons stated above C Wrong - Plausible to the candidate that mistakenly believes that restoring 1A1D101 to Operable status would result in Division 1 being restored to Operable D Wrong - Plausible to the candidate that mistakenly applies the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> duration associated with establishing an alternate AC Source described in SE-1 "Loss of all AC Power (Station Blackout)" Bases coping time from the Station Blackout Analysis.

LMK 2017 ILT NRG JANUARY Page: 321 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 88 Info Question Tvoe: Multiole Choice Status: Active IAlwavs select on test? No

!Authorized for practice? No Points: 1.00 rnme to Complete: 5 Difficulty: 2.00 Svstem ID: 1455679 User-Defined ID: Q# 88 NEW Lesson Plan Obiective: LGSOPS0095.9A Topic: 'SRO ONLY) - Tech Spec - Shutdown with 3 DC Divisions INOP RO: 3.9 SRO: 4.0 KA#: 263000 G2.1.27 LMK 2017 ILT NRC JANUARY Page: 322 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

SRO 3

N/A 263000 G2.1.27 R0-3.9 SRO - 4.0 263000 D.C. Electrical Distribution 2.1.27 Knowledge of system ur ose and/or function 55.43 (2) Facility operating limitations in the technical s ecification and their bases Tech Spec 3.8.2.2 UFSAR 8.3.2.1.1.2 1248501 LMK 2017 ILT NRC JANUARY Page: 323 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 324 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 89 10:1455217 Points: 1.00 SRO Unit 1 is in OPCON 2 with reactor startup in progress.

All IRM's are on Range 6 and reading as follows:

"A" 22I125 "B" 24I125 "C" 31 I 125 "D" 24 I 125 "E" 55I125 "F" 54I125 "G" 33 I 125 "H" 31 I 125

  • The RO ranges up IRMs B,C,G, and H to range 7 and
  • The A,D,E and F IRMs are inadvertently ranged up to range 8 and the RO continues to pull control rods.

WHICH of the following identifies (1) all of the INOP IRMs AND (2) the required Tech Spec actions?

A. (1) A AND D (2) Place an A side Half SCRAM in within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B. (1) A, D, E, AND F (2) Place a ROD BLOCK in within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. (1) AAND D (2) Startup may continue D. (1) A, D, E, AND F (2) Place a ROD BLOCK in within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Answer: C

!Answer Explanation LMK 2017 ILT NRC JANUARY Page: 325 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO A and D IRM are INOP for rod block instrumentation TS 3.3.6. G and H are only up ranged 1 time so no downscale rod block exist on them. Stem indicates the RO continues to pull rods after A and D IRM are< 3 /125 of scale rod block shound be generated Ranging from 6 to 7 will divide all readings by 3.16. A,D,E,F are ranged to 8 which will divide the reading by 3.16 again which will result in A and D IRM reading less than 3/125ths of scale which will result in a rod block. operators continue to pull control rods rod block must have not come in.

Since only 6 IRMs are required for both RPS and Rod Block 1 IRM may be bypassed on each side. A and D IRM may be bypassed and startup may continue.

A incorrect plausible to candidate who belives an IRM downscale will generate a 1/2 scram B incorrect plausible to the examinee who correctly inedtifies that a ROD block should have been generated but does not recall the required number of IRM required per TS C Correct A and D IRM INOP for Rod Block function but 6 IRMs remain operable, starup may continue D incorrect plausible to he examinee who correctly inedtifies that a ROD block should have been generated but does not recall the required number of IRM required per TS and incorrectly belives B IRM is INOP LMK 2017 ILT NRG JANUARY Page: 326 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 89 Info Question T e: Multi le Choice Status: Active No No 1.00 3

3.00 1455217 Q# 89 NEW LGSOPS007 4.24A SRO Unit 1 is in OPCON 2 with reactor startup in progress. All IRMs are on Ran e 6 and read in RO: 3.4 SRO: 4.7 KA#: 215003 2.2.40 Comments:

2 215003 2.2.40 3.4/4. 7 Ability to apply Technical S ecifications for a s stem.

hi her 43.2 LMK 2017 ILT NRC JANUARY Page: 327 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 328 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 329 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 90 ID; 1454750 Points: 1.00 SRO A turbine trip with failure of bypass valves to open occurred on unit 1. After the event the plant is being prepared for startup.

Engineering reports the SRV's lifted at the following pressures during the transient.

f'.d SRV Lift Lifted SRV Lift Lifted SRV Lift Lifted set at rl,,i set at '1?:j set at point

~~0~~\ point

~~>~,

point H 1170 1175 ~j,! D 1180 1180 ~)'.:'. A 1190 1190 J 1170 1160 rt110' E 1180 1218 l(11;;

B 1190 1188 L 1170 1159 > K 1180 1181  !*.*;

c 1190 1190

~fu1>> ,.>

N 1170 1133 M 1180 1183 '"':"' F 1190 1153

'~4 %~

~i s 1180 1190 G 1190 1230 u/

Maintenance reports there are 3 spare SRV's with a lift set point of 1170 available on site Procurement reports that it will take 2 weeks to secure 1 additional SRV, AND 3 weeks to secure a second additional SRV.

LMK 2017 ILT NRG JANUARY Page: 330 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO REACTOR COOLANT SYSTEM 314.4 2 SAFETY/RF! IEE VA! YF'i LIMITING CONQHHJN FOR OPERATION 3.4.2 The safety valve function of at least 12 of the following reactor coolant system safety/relief valves sha11 be OPERABLE with the specified code safety va1ve function lift settings:*#

4 safety/relief valves a 1170 psig +/-31 5 safety/relief valves a 1180 psig +/-31 5 safety/relief valves a 1190 pstg +/-31 APPUCAB I lITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACT10N:

J. With the safety valve function of one or more of the above required safety/relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. DELETED
  • ~. DELETED SlJRVE It! ANCE Rrntl!RFMENIS 4.4.2.1 DELETED 4.4.2.2 At least 112 of the safety relief valves shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations in accordance with the Surveillance Frequency Control Program, and they shall be rotated such that all 14 safety relief va1ves are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations in accordance with the Surveil la nee Frequency Contra l Program. A11 safety valves will be recertification tested to meet a +/-1% tolerance prior to returning the valves to service.
  • The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
  1. Up to 2 inoperable valves may be replaced with spare OPERABLE valves with lower setpolnts until the next refueling.

Of the choices below which one of the following will allow the mode switch to be placed in startup the earliest?

A. After SRV replacement with onsite spare SRV's, a risk assessment IS NOT required B. After SRV replacement with onsite spare SRV's, a risk assessment _lS_required C. After procurement of an additional SRV with a lift set point of 1180 D. After procurement of 2 additional SRV's with a lift set point of 1190 LMK 2017 ILT NRC JANUARY Page: 331 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer: A Answer Explanation Per T.S 3.4.2 SRV set point acceptable tolerance is+/- 3% examinee must determine that N,E,F,& Gare outside of 3% and inoperable Per T .S 3.4.2 only 12 of 14 are required Per the # note up to 2 SRV's may be replaced with lower set point SRV until the next refuel outage SRO must recall TS 3.0.4.b requirements tor when a risk assessment is required without reference A Correct replacing the N SRV and any 2 other SRV's will meet the requirements of T.S 3.4.2 using # note up to 2 SRV's may be replaced with lower set point SRV until the next refuel outage B Incorrect plausible to the examinee who does not recognize the # note and believe that using lower setpoint SRV could be used with a risk assessment C Incorrect plausible to the examinee who does not apply note# but does recognize that only 12 SRV's are needed D Incorrect plausible to the examinee who does apply the note # but does recognize that only 12 SRV's are required LMK 2017 ILT NRG JANUARY Page: 332 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 90 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 4.00 System ID: 1454750 User-Defined ID: Q# 90 NEW Lesson Plan Objective: LGSOPS1800.58 rropic: SRO SRV hi rector pressure RO: 4.1 SRO: 4.3 KA#: 239002 A2.06 LMK 2017 ILT NRC JANUARY Page: 333 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

SRO 2

1 239002 A2.06 4.1 /4.3 Relief/Safety Valves Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations
Reactor high 186 LMK 2017 ILT NRG JANUARY Page: 334 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 335 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 91 ID: 1453648 Points: 1.00 SRO ONLY Unit 2 is operating at 100% power.

Multiple cell failures on the 'A' ASD results in the following Recirc indications:

'A' Becirc 'B' Becirc Loop Flow 28 Mlbm/hr 45 Mlbm/hr WHICH ONE of the following is the maximum allowable 'B' Recirc loop flow that will satisfy Tech Specs 3.4.1.3, and the Basis for the Tech Spec Becirc flow mismatch limitations? (Assume 'A' flow remains constant)

HIGHEST 'B' Becirc flow value that will Basis for Tech Spec Becirc flow mismatch satisfy Tech Specs limitations A. 33 Mlbm/hr Prevents undue stress on the vessel nozzles and bottom head region B. Prevents undue stress on the vessel 38 Mlbm/hr nozzles and bottom head region

c. 33 Mlbm/hr Ensure an adequate core flow coastdown from either recirc loop following a LOCA D. 38 Mlbm/hr Ensure an adequate core flow coastdown from either recirc loop following a LOCA Answer: D

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 336 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Ill'"-"""""-'~ is correct. Refer to Tech Spec 3.4.1.3 action a which states "Recirculation loop flow mismatch shall be maintained: a. Within 5% of each other with core flow greater than or equal to 0% of rated core flow, orb. within 10% of each other with core flow less than 70% of rated core low. From the daily ST, ST-6-107-590-2, Note 1 on page 85, (Rev. 134) states "If core flow<

70%, THEN VERIFY DIFFERENCE s 10 Mlbm/hr OR IF;?: 70%, THEN VERIFY DIFFERENCE s 5Mlbm/hr. Therefore, when 'B' Recirc flow is reduced to 38 Mlbm/hr, total core flow will be less han 70% and the 10 Mlbm/hr flow mismatch requirement will be met.

ia;_~...MIJ21IllD.lr..J:'..CBJilJllllS....UO.QU.e....&lm:S.S...J2D..lb.e.Jl:e&!se.l..DJl~lils...ania.J:2.QIIQJJn..bie&.!a..LlltgJQl]_iS incorrect. This reduction is sufficient to meet the required 10% flow mismatch (actual value is 5%

not the highest allowable value) The basis of the flow mismatch Tech Spec is wrong but plausible due to it actually being the basis for recirc loop temperature difference prior to a start of an idle recirc pump.

~..,,...,:i..is incorrect. This reduction is sufficient to meet the required 10% flow mismatch (actual alue is 5% not the hi hest allowable value LMK 2017 ILT NRG JANUARY Page: 337 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 91 Info Puestion Type: Multiple Choice Status: Active

~lways select on test? No

~uthorized for practice? No Points: 1.00 rfime to Complete: 4 Difficulty: 3.00 System ID: 1453648 User-Defined ID: Q#91BANK Lesson Plan Objective: LGSOPS1800.58 (SRO) Recall Tech Spec 3.4.1.3 SR requirements for Recirc rTopic:

Flow mismatch RO: 3.0 SRO: 3.2 KA#: 202002 A2.04 LMK 2017 ILT NRC JANUARY Page: 338 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or modified after 2015 cert Also 295001 2.2.12 3.7/4.1 LMK 2017 ILT NRC JANUARY Page: 339 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO 92 ID: 1454490 SRO Unit 1 is operating at 100% power when a LOCA occurs Plant conditions are as follows;

  • Drywell pressure is 14 psig
  • Drywell temperature is 248 degrees
  • Reactor level is -140 inches up slow with HPCI
  • Suppression pool level is 42 feet
  • D12 bus lockout occurs
  • D13 load center breaker trips and cannot be reclosed Which of the following describes (1) the T-225 action to be taken by the RS and (2) whether local manual operation, outside the MCA, of RHRSW Heat Exchanger lnle nd/or Outlet Valve(s) is required to complete the action?

A. (1) Spray the Drywall (2) No B. (1) Spray the Suppression Pool (2) No C. (1) Spray the Drywell (2) Yes D. (1) Spray the Suppression P (2) Yes Answer: D Answer Explanation A Incorrect pla 1ble to examinee who does not diagnose >37.4 feet suppression pool level, and that d ell spray is prohibited per PC/P-10 of T-102. plausible to the examinee who does not call that Div 3 power supplies the A AHR htx outlet valve.

B lncorre plausible to the examinee who does not recall that Div 3 power supplies the A RHR x outlet valve.

C Inc rect plausible to examinee who does not diagnose >37.4 feet suppression pool level, a that drywell spray is prohibited per PC/P-10 of T-102.

D orrect examinee recognizes sate to spray but realizes suppression pool level is too high to spray the Drywell and directs pool spray. With a loss of D13 load center the A RHRSW outlet valve to the RHR HTX has no power and must be opened manually. 812.1.A which is directed from T-225 includes direction tor manual operation of RHRSW valves it required.

LMK 2017 ILT NRG JANUARY Page: 340 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 92 Info Question T e: Multi le Choice Status: Active lwa s select on test? No uthorized for ractice? No 1.00 lete: 3 3.00 1454490 Q# 92 NEW LGSOPS1560.06 SRO FLA action cont. SPRAY 3.8 SRO: 4.0 KA#: 226001 2.4.35 Comments:

2.4.35 3.8/4.0 RHR/LPCI: Containment Spray System Mode Knowledge of local auxiliary operator tasks during an emergency and the resultant o erational effects.

Hi her

,ffev,

,#t'.';/;'

LMK 2017 ILT NRG JANUARY Page: 341 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01January2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 342 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 343 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 93 10:1454412 Points: 1.00 SRO Plant conditions are as follows:

Unit 1

  • Reactor power is 100%
  • RWCU resin spill has occurred in the Reactor Enclosure (RE)
  • RE HVAC Exhaust radiation level is 11 mR/hr
  • RWCU 'A' Pump Room radiation level is 120 mR/hr
  • RWCU Regen Heat Exchanger Room radiation level is 122 mR/hr Access to Unit 1 Reactor Enclosure is required.

Unit 2

  • OPCON 5 Drywell purge in progress WHICH ONE of the following identifies (1) the T-103 action required for Unit 1?

(2) the status of Unit 2 drywell purge?

A. (1) Restore Reactor Enclosure HVAC per T-103 Secondary Containment Control, Step SCC/T-3 (2) Isolated B. (1) Restore Reactor Enclosure HVAC per T-103 Secondary Containment Control, Step SCC/T-3 (2) In service C. (1) Ensure Reactor HVAC isolation and SGTS initiation perT-103 Secondary Containment Control, Step SCC-4 (2) Isolated D. (1) Ensure Reactor HVAC isolation and SGTS initiation per T-103 Secondary Containment Control, Step SCC-4 (2) In service Answer: C

\Answer Explanation LMK 2017 ILT NRG JANUARY Page: 344 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO A Incorrect The SRO candidate must demonstrate TRIP step knowledge by understanding SCCff-3 only applies if reactor enclosure rad is< 1.35 mR/H plausible if the examines does not recall requirement for rad to be below 1.35 or confuses this with T-104 RR-3 which allows start of REFUEL HVAC regardless for rad if entry is required B Incorrect At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge. The SRO candidate must demonstrate TRIP step knowledge by understanding SCCff-3 only applies if reactor enclosure rad is< 1.35 mR/H plausible if the examines does not recall requirement for rad to be below 1.35 or confuses this with T-104 RR-3 which allows start of REFUEL HVAC regardless for rad if entry is required C Correct At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge. Ensure Reactor HVAC isolation and SGTS initiation per T-103 Secondary Containment Control, Step SCC-4 D Incorrect At >1.35 mR/H reactor HVAC will isolate and SBGT will start and Isolate unit 2 purge ..

rr-104 RR-3 LMK 2017 ILT NRC JANUARY Page: 345 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 93 Info Question Tvoe: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 iTime to Complete: 3 Difficulty: 3.00 System ID: 1454412 User-Defined ID: 0#93 NEW Lesson Plan Objective: LGSOPS1560.06 Topic: SRO Reactor encl hi rad RO: 3.4 SRO: 3.6 KA#: 290001 A2.03 LMK 2017 ILT NRG JANUARY Page: 346 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

Secondary Containment Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditionsor operations: High area radiation 43.4 & 43.5 ReV'< 2

  1. 'h'~ 3 LMK 2017 ILT NRG JANUARY Page: 347 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 94 ID: 1455644 Points: 1.00 SRO A large fire is burning at the 2C Main Power Transformer. What are the SE-8 "Fire" requirements for controlling access of an offsite fire department?

The offsite fire department is to be escorted by _ _ __

A. Radiation Protection B. any Fire Brigade Member qualified Equipment Operator C. a Fire Brigade Leader qualified Equipment Operator D. Plant Security Answer: D

~nswer Explanation

~t Limerick most Equipment operators are fire brigade qualified and any Equipment operator with more than 6 months in position is leader qualified as such there is an abundance of fire brigade I leader qualified people on site to support choices B and C A Wrong - Plausible to the examinee who recalls that RadPro responds to Fires within the Protected Area Boundary and translates this into they would be responsible to escort the responding fire department. For fires within the Protected Area Boundary that do not contain a radiological concern (as is the case for this fire at the Main Power Transformer),

the RP response (SE-8 section 4.12) parallels that of a EMT for the Fire Brigade Members.

B Wrong - Plausible if the examinee assumes that the Offsite Fire Department should be escorted by an individual knowledgable in the equipment locations in the plant and fire fighting techniques.

C Wrong - Plausible if the examinee assumes that the Offsite Fire Department should be escorted by an individual in charge of fire fighting activities D Correct - SE-8 "Fire" Shift Supervisor Response section step 4.8.5.6 has the SRO request plant security to escort offsite Fire Departments

~pplicable to SROs and NOT General Employee Knowledge due to Licensed Operators having sole responsibility to direct actions from procedure SE-8 "Fire" LMK 2017 ILT NRG JANUARY Page: 348 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 94 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 rnme to Complete: 3 Difficulty: 2.00 System ID: 1455644 User-Defined ID: 0#94 NEW Lesson Plan Objective: LLOT1563.04 (E/SE PROCEDURES) lropic: SRO - requirements for controlling vital/ controlled access RO:

SRO: 3.2 KA#: 2.1.13 LMK 2017 ILT NRG JANUARY Page: 349 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

2.1.13 SRO Importance SRO 3.2 Knowledge of facility requirements for controlling vital/controlled access.

Ffev s

  1. 4 Applicable to SROs and NOT General Employee Knowledge due to Licensed Operators having sole responsibility to direct actions from procedure SE-8 "Fire" LMK 2017 ILT NRG JANUARY Page: 350 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 95 ID: 1455601 Points: 1.00 SRO Given the following:

  • Unit 2 is operating at 85% power
  • The 28 Reactor Feed Pump (RFP) has been experiencing fluctuating speed changes
  • To support trouble shooting, l&C is requesting to connect a strip chart recorder to monitor the signal to the Woodward Governor for the 28 RFP
  • The strip chart recorder will be attached to existing test points in the system Refer to Attachment 4 "Risk and Rigor Determination Matrix" of MA-AA-716-004 "Conduct of Troubleshooting" to classify this activity This is a __ (1 }__ Risk troubleshooting activity, and requires Operations Department approval by the_(2)_.

A. (1) High (2) Shift Manager

8. (1) High (2) Work Control Supervisor C. (1) Medium (2) Shift Manager D. (1) Medium (2) Work Control Supervisor Answer: 8 Answer Explanation A Wrong - plausible if the student confuse the risk category of With test points (C) with that of without test points (A) Shift manager required approval 8 Correct - This is High Risk Troubleshooting per MA-AA-716-004 Attachment 4 due to DFLCS and the Woodward Governor being control systems that directly involve power generation support (1.2) and being Logic systems that can directly or indirectly cause a reactor scram (1.3). The risk category is C due to hooking up the recorder using existing test points. This requires the WCS approval C Wrong - plausible if the student confuse the risk level classification as Medium due to mis applying 2.3 as Level control changes in the reactor and confuses the risk category of With test points (C) with that of without test points (A) (shift manager required approval D Wrong - plausible if the student confuse the risk level classification as Medium due to mis applying 2.3 as Level control changes in the reactor.

LMK 2017 ILT NRC JANUARY Page: 351 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 95 Info Question T e: Multi le Choice Status: Active No uthorized for ractice? No 1.00 lete: 3 2.50 1455601 Q #95 MODIFIED LGSOPS2005A 6.8 ADMIN PROCED SRO 3.8 2.2.20 Comments:

Modified PBAPS 2008 ILT NRC SRO #21 Modified PBAPS 2008 ILT NRC SRO #21 N/A LMK 2017 ILT NRC JANUARY Page: 352 of 37 4 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 353 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 96 10: 1685046 Points: 1.00 SRO Given the following:

  • A loss of coolant accident has occurred
  • 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> have elapsed since the LOCA signal
  • Plant operators have arrived at the following SE-10 step:

4.25 WHEN greater than three hours have elapsed following the LOCA signal, Il:lEN. INJECT SLC per S48.1.B, Standby Liquid Control System Manual Initiation. (CM-4)

WHICH ONE of the following describes the basis for performance of this step?

A. Provides an additional source of injection to the reactor to help recover RPV water level B. Ensures sufficient negative reactivity is present to ensure reactor remains shutdown due to changes in core geometry C. Ensures Hot Shutdown Boron Weight is injected before suppression pool temperature exceeds the Heat Capacity Temperature Limit D. Minimizes radioactive release by adding sodium pentaborate to the suppression pool to satisfy the methodology for Alternate Source Term Answer: D

!Answer Explanation LMK 2017 ILT NRG JANUARY Page: 354 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO K&A Rating: G2.3.14 (3.8)

K&A Statement: Knowledge of radiation or contamination hazards that may arise during normal, abnormal or emergency conditions or activities Justification:

A. Incorrect but plausible: Establishing SLC injection in 4.25 is not as a means for level control but as a means to control radiological dose following a loss of coolant accident involving core damage. Since SLC is identified as an Alternate Injection System it would likely be started to augment RPV injection in an earlier step of the Level branch, before RPV water level reaches the top of the active fuel. This is a plausible distracter for those candidates that do not recognize the radiological impact from SLC injection once T AF has been reached and also plausible for level control as injection requirements 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after shutdown are much lower and closer to the capacity of the SLC pumps B. Incorrect but plausible: Boration of the reactor coolant is performed to reduce power levels in the core by neutron moderation. This is plausible distracter for those candidates who believe that dose mitigation is achieved with boration of the coolant in the vessel versus the Suppression Pool volume C. Incorrect but plausible: to the examinee who mistakes the basis for this injection with the basis for injecting SLC prior to Suppression Pool Temperature exceeded 110 degrees F from T-101 Step RC/Q-16 D. Correct: Design basis analyses credit SLC injection for limiting the radiological dose following loss of coolant accidents involving core damage. Radiation induced reactions are predicted to convert large fractions of dissolved ionic iodine into elemental iodine and organic iodides which can escape into the containment atmosphere. The rate of these reactions is strongly dependent on suppression pool pH. If the bulk Suppression Pool pH is maintained greater than 7, very little of the dissolved iodine will be converted to volatile forms and most of the iodine fission products will be retained in the suppression pool, thereby preventing iodine re-evolution. Over time, the pH in the Suppression Pool will tend to lower due to the addition of acidic chemicals. The sodium pentaborate solution used in the SLC system is derived from a strong base and therefore raises suppression pool pH

References:

SE-10, Rev. 56 Applicant Ref: None UFSAR Section 9.3.5, Rev. 15 S48.1.B, Rev. 13 LLOT0048, Rev. 0 TS Bases 3/4.1.5, amendment 186 Learning Objective: LLOT0048: IL 1, IL 10 LLOT1563: 03 Question source: Bank NMP 8/2009 Question History: Not used on 2008 or 2010 LGS initial exams Cognitive level: Memory/Fundamental knowledge: x Comprehensive/Analysis:

LMK 2017 ILT NRG JANUARY Page: 355 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 10CFR Part 55: 43{b)(4), 43(b)(1)

Comments: This question is SRO only as it requires knowledge of administrative procedures that specify implementation and coordination of plant emergency procedures regarding radiation hazards that may arise during abnormal plant conditions and knowledge of conditions and limitations in the facility license.

LMK 2017 ILT NRC JANUARY Page: 356 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 96 Info Question T e: Multi le Choice Status: Active No No 1.00 2

3.00 1685046 Q# 96 BANK POOL PH 3.8 2.3.14 Comments:

Knowledge of radiation or contamination hazards that may arise during normal, abnormal or emergency conditions or activities lower n/a LMK 2017 ILT NRC JANUARY Page: 357 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 358 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 97 ID: 1685033 Points: 1.00 SRO LGS has declared a GENERAL EMERGENCY.

Command & Control has been transferred to the TSC.

Consider the following ERO personnel:

1. Shift Manager I Shift Emergency Director
2. Radiation Protection Manager
3. Station Emergency Director WHICH ONE of the following identifies (from the above list) ALL of those who can APPROVE an "Authorization for Emergency Exposure" form for a worker to receive exposure greater than 25 Rem TEDE?

A. 1, 3 B. 2,3

c. 2 D. 3 Answer: D nswer Explanation Refer to EP-AA-113-F-02 (Authorization for Emergency Exposure). The Shift Manager I Shift Emergency Director may approve ,ori.Qr to transferring Command and Control to the Station Emergency Director. After the transfer of command and control, only the Station Emergency Director can approve the emergency exposure.

µ.<.-...LW-r..u..>.~._._._ Plausible to the examinee who recognizes that the Station Emergency Director has overall command and control of the ERO, but who believes that the expertise that only the RPM assesses is necessa to ultimate! a rove the ex osure re uest.

LMK 2017 ILT NRC JANUARY Page: 359 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Question 97 Info Question T e: Multi le Choice Status: Active lwa s select on test? No uthorized for ractice? No 1.00 lete: 3 2.00 1685033 Q# 97 BANK 2015 NRG EAL OBJECTIVES SRO Recall who can A RO: 2.4 SRO: 4.4 KA#: 2.4.38 Comments:

2.4/4.4 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if re uired.

bank 1150031 2015 NRG LMK 2017 ILT NRC JANUARY Page: 360 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 361 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 98 10:1454851 Points: 1.00 SRO Given the following:

Unit 2 is operating at 100% power

  • 111 RECIRC-ES NSSSS Isolation Sys Out Of SERVICE (Outboard), has repeatedly alarmed due to the surveillance test
  • The CRS determined the alarm to be a nuisance and authorized placing the annunciator mode switch in MANUAL
  • The ST did NOT provide steps for changing the annunciator mode switch position Which one of the following describes the action required by OP-AA-103-102 "Watch-Standing Practices" AND OP-LG-103-102-1001 "Alarms And Indications" for these conditions?

An __ (1 )__ must be used if the annunciator mode switch is in manual greater than __ (2) __ .

A. (1) Equipment Status Tag (EST) (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. (1) Equipment Status Tag (EST) (2) 1 shift C. (1) Equipment Deficiency Tag (EDT} (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. (1) Equipment Deficiency Tag (EDT) (2) 1 shift Answer: B Answer Explanation Correct: B For nuisance alarms, OP-AA-103-102 requires use of an EST if the annunciator mode switch will be in manual for greater than 1 shift. If the test procedure gives direction for controlling the annunciator mode switch, an EST is not required.

Distractors:

~ Correct tag; wrong time.

C Incorrect tag; incorrect time. Plausible because an EDT is used in cases where an annunciator alarms (and an alarm condition does NOT exist) due Ito an equipment/instrumentation failure. The applicant may confuse the specific cases involving annunciators when an EST is used versus an EDT.

D Incorrect tag; correct time. Plausible because an EDT is used in cases where an annunciator alarms (and an alarm condition does NOT exist) due Ito an equipment/instrumentation failure. The applicant may confuse the specific cases involvinq annunciators when an EST is used versus an EDT.

LMK 2017 ILT NRC JANUARY Page: 362 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 98 Info Question T e: Multi le Choice Status: Active No No 1.00 4

3.00 1454851 Q# 98 NEW LOT1572 COND. OF OPS SRO INOP annun 3.0 3.3 2.2.43 Comments:

3.0/3.3 Knowledge of the process used to track inoperable alarms.

lower n/a 43.5 OP-LG-103-102-1001 LMK 2017 ILT NRC JANUARY Page: 363 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRC JANUARY Page: 364 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 99 10:1454568 Points: 1.00 SRO Fuel is being loaded into the core on Unit 1, with the following:

- '1 A' SAM count rate is 3.5 cps and has a signal-to-noise ratio of 2.5

- '1 B' SAM count rate is 1.1 cps and has a signal-to-noise ratio of 7.0

- '1 C' SAM count rate is 2.0 cps and has a signal-to-noise ratio of 1.5

- '1 D' SAM count rate is 2.5 cps and has a signal-to-noise ratio of 2.3 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least two source range monitor (SRM) channels* shall be OPERABLE and inserted to the normal operating level with:

a. Continuous visual indication in the control room,
b. At least one with audible alarm in the control room,
c. One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and
d. Unless adequate shutdown margin has been demonstrated, the shorting links shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn.**

APPLICABILITY: OPERATIONAL CONDITION 5.

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS and insert all insertable control rods.

LMK 2017 ILT NRC JANUARY Page: 365 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO

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2.2 111 t I JI t I J 1 I 1

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~ I'\ J I I I I I I 1 I I II

§ ::: I \I I I I I I I I II III

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1' 0

I t I 2 ' 10 14 11 u 21 JO SIGNAL TO NOISE RATIO SRM COUNT RATE VERSUS SIGNAL TO NOISE RATIO FIGURE 3.3.6-1 WHICH ONE of the following describes the limitations, if any, regarding loading fuel into the core?

A. Fuel may be loaded into any quadrant.

B. All fuel loading must be suspended immediately.

C. Fuel may be loaded into "A" or "D" core quadrants ONLY.

D. Fuel may be loaded into "A", "C" or "D" core quadrants ONLY.

LMK 2017 ILT NRC JANUARY Page: 366 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Answer: C Answer Explanation "A" SRM is operable even though 3.5 CPS is above the graph. The signal to noise ratio is used twhen counts are low and background noise may override the SRM signal. as seen on the graph once count rate exceeds approximately 2.3 any signal to noise ratio> approximately 2 will result in an operable SRM SRM Band C are below the line for signal to noise ratio and therefore INOP Correct: C

'18" and "1C" SRMs are INOPERABLE {"1C" due to inadequate Signal-To-Noise Ratio per Technical Specification Figure 3.3.6-1). Therefore, fuel movement is only permitted in quadrants "A" and "D" per Technical Specification 3.9.2 {detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal")

Limerick Core quadrants are laid out as follows:

AB DC Incorrect: A With "1 B" and "1 C" SRMs INOPERABLE, fuel movement is permitted in quadrants "A" and "D" per Technical Specification 3.9.2 only (detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal"). Plausible to the candidate that mistakenly determines no SRMs are INOP due to assessing Signal to noise ratio incorrectly.

Incorrect: B With "1 B" and "1 C" SRMs INOPERABLE, fuel movement is still permitted, but only in quadrants "A" and "D" per Technical Specification 3.9.2 {detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant, with adjacent being defined as "NOT diagonal"). Plausible to the candidate that mistakenly determines one or more additional inoperable SRMs due to assessing Signal to noise ration incorrectly.

Incorrect: D Fuel cannot be loaded into quadrant "C" because the "1 C" SRM detector is INOPERABLE, and Technical Specification 3.9.2 requires a detector in the quadrant where CORE ALTERATIONS are being performed and one in an adjacent quadrant (adjacent being defined as "NOT diagonal"). Plausible to the candidate that mistakenly determines no additional SRMs are INOP due to assessinq Signal to noise ratio incorrectlv.

LMK 2017 ILT NRC JANUARY Page: 367 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 99 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Jime to Complete: 3 Difficulty: 2.00 System ID: 1454568 User-Defined ID: 0#99 BANK Lesson Plan Objective: LGSOPS1800.68 (SRO ONLY) - Tech Spec - SRM Operability During Fuel iTopic:

Loading RO: 3.0 SRO: 4.1 KA#: 2.1.36 LMK 2017 ILT NRC JANUARY Page: 368 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Comments:

3 N/A 2.1.36 IMPORTANCE RO 3.0 SRO 4.1 Knowledge of procedures and limitations involved in core alterations.

41.10; 43.6 Technical Specification 3.9.2 and Technical Specification Fi ure 3.3.6-1 LMK 2017 ILT NRG JANUARY Page: 369 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO LMK 2017 ILT NRG JANUARY Page: 370 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO 100 10:1454415 Points: 1.00.

SRO Unit 1 is operating at 100% power.

A-2141 mR/hr up slow B - 2170 mR/hr up slow C - 2156 mR/hr up slow D - 2196 mR/hr up slow

  • The HWC system is functioning correctly
1. 109 RAD-F1, 1 MAIN STEAM LINE DIVISION 1 RAD MONITOR HI/DOWNSCALE
2. 109 RAD-F2, 1 MAIN STEAM LINE RAD MON CID HI/DOWNSCALE WHICH ONE of the following identifies the procedure(s) requiring entry and an action(s) required as a result of the above conditions?

ON-102, Air Ejector Discharge or Main Steam Line High Radiation T-101, RPV Control T-103, Secondary Containment Control Procedure(s) requiring entry Actjon(s) required A. ON-102 but NOT T-103 Reduce reactor power to lower MSL Rad levels below 1.5X NFPB

8. ON-102 AND T-103 Reduce reactor power to lower MSL Rad levels below 1.5X NFPB
c. ON-102 but NOT T-103 Shutdown the reactor and close the MSIVs D. ON-102 AND T-103 Shutdown the reactor and close the MSIVs Answer: B

!Answer Explanation LMK 2017 ILT NRC JANUARY Page: 371 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO From the stem the SRO candidate identifies that Main Steam Line (MSL) radiation is elevated and above 1.5 X Normal Full Power Background (NFPB) (the alarm set points are 1.5 X NFPB) for 109-F1 and 2 . Also from the stem the students determine that MSL Rad is below 3 X NFPB (based on the absence of ARC-MCR-107 11, Main steam line high-high radiation). Based in this information the appropriate procedures are both ON-102 and T-103. The appropriate action for

~hese conditions is found in ON-102 step 2.2:

~.2 IF power reduction is required to maintain air ejector discharge radiation level below HiHi Alarm setpoint (ARC-MCR-*09 G1)

OR main steam line radiation level below 1.5x normal full power background, lrHEN REDUCE reactor power in accordance with GP-5 Appendix 2, Section 3.1, Reducing Rx Power, AND Reactor Maneuvering Shutdown Instructions to maintain air ejector discharge radiation level below Hi Hi Alarm setpoint (ARC-MCR-*09 G1)

AND Main Steam Line radiation level below 1.5 x normal full power background. (CM-1 T03582)

A Wrong - Does not identify T-103 entry. Plausible to the student that believes T-103 entry is not required until 3X NFPB B Correct - See discussion above C Wrong - Does not identify T-103 entry and identifies that wrong actions for the given conditions. Plausible to the student that believes T-103 entry is not required until 3X NFPB and believes that closure of the MSIVs is required at 1.5 X NFPB. This is requred above 3 x N FPB D Wrong - Identifies that wrong actions for the given conditions. Plausible to the student that believes that closure of the MS IVs is required at 1.5 X NFPB. This is requred above 3 x NFPB LMK 2017 ILT NRC JANUARY Page: 372 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRC test SRO Question 100 Info Question Tvpe: Multiple Choice Status: Active

~lwavs select on test? No

~uthorized for practice? No Points: 1.00 rT'ime to Complete: 5 Difficulty: 2.00 Svstem ID: 1454415 User-Defined ID: 0#100 NEW Lesson Plan Objective: LGSOPS0026A. IL 12 Topic: SRO - Interpreting MSL Rad Monitor Readings RO: 2.9 SRO: 2.9 KA#: 272000 G2.3.5 LMK 2017 ILT NRG JANUARY Page: 373 of 374 17 January 2017

EXAMINATION ANSWER KEY ILT 15-01 January 2017 NRG test SRO Comments:

3 N/A 2.3.5 IMPORTANCE RO 2.9 SRO 2.9 0

1 29 23 LMK 2017 ILT NRG JANUARY Page: 374 of 374 17 January 2017

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