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{{#Wiki_filter:Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
{{#Wiki_filter:Limerick Generating Station                     ILT05-I NRC Initial Licensinq Examination
: 1. WHICH ONE of the following describes the reason for a reactor scram that occurs as a result of a Main Turbine trip?
: 1. WHICH ONE of the following describes the reason for a reactor scram that occurs as a result of a Main Turbine trip?
A. Limits positive reactivity due to a reduced void concentration when turbine stop valves close. B. Minimizes level transient that occurs when feed pumps swap to high pressure steam. C. Limits positive reactivity due to increased feedwater su b-cooling when extraction steam is lost. D. Minimizes level transient that occurs when voids collapse due to turbine control valves closing.
A. Limits positive reactivity due to a reduced void concentration when turbine stop valves close.
Page 2 of 200 Limerick Generatinq Station lLTO5-1 NRC Initial Licensinq Examination Time Allowance (minutes) 2 I Answer Kev PRA RO SRO 1 OCFR55.41 1 OCFR55.43 Y (b) (5) N/A Choice c Correct: Low Incorrect 2.5 Incorrect 295005 AK3.01 t------ Incorrect Importance:
B. Minimizes level transient that occurs when feed pumps swap to high pressure steam.
RO / SRO 3.8 I 3.8 A B C D Basis or Justification Void concentration will rapidly decrease on closing of the turbine steam admission valves resulting in a large positive reactivity addition.
C. Limits positive reactivity due to increased feedwater su b-cooling when extraction steam is lost.
While the reactor feed pumps do swap from cross-around (LP) steam to main steam (HP) and this does contribute to the post-scram level transient that will occur, it is not part of the basis for the scram. While this will occur, the Reactor power rise will be slight and gradual. This is not the reason for the Scram. While this level transient will occur, it is not part of the basis for the scram I Psychometrics Source: Reference(sk Learning 0 bjective:
D. Minimizes level transient that occurs when voids collapse due to turbine control valves closing.
Knowledge/Ability WA Source Documentation New Exam Item Modified Bank Item ILT Exam Bank Previous NRC Exam 0 Other Exam Bank LGS UFSAR, Chapter 15.2, LGS Tech Specs, LSSS LLOTI 575.03 (Description of K&A, from catalog) Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP: Reactor scram Required Materials:
Page 2 of 200
 
Limerick Generatinq Station                           lLTO5-1 NRC Initial Licensinq Examination I                                                 Answer Kev c          Choice Correct:
Incorrect A
B Basis or Justification Void concentration will rapidly decrease on closing of the turbine steam admission valves resulting in a large positive reactivity addition.
While the reactor feed pumps do swap from cross-around(LP) steam to main steam (HP) and this does contribute to the post-scram level transient that will occur, it is not part of the basis for the scram.
Incorrect        C    While this will occur, the Reactor power rise will be slight and gradual. This is not the reason for the Scram.
-t    Incorrect        D    While this level transient will occur, it is not part of the basis for the scram I                                               Psychometrics Time Allowance            PRA                  RO                      SRO (minutes)                            10CFR55.41                10CFR55.43 Low          2.5              2                  Y                (b) (5)                    N/A Source Documentation Source:                  New Exam Item                                   Previous NRC Exam Modified Bank Item                           0Other Exam Bank ILT Exam Bank Reference(sk        LGS UFSAR, Chapter 15.2, LGS Tech Specs, LSSS Learning            LLOTI575.03 0bjective:
Knowledge/Ability 295005                                                Importance: RO / SRO WA                  AK3.01                                                              3.8 I 3.8 (Description of K&A, from catalog)
Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP:
Reactor scram Required Materials:
Notes and Comments:
Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
Prepared By:
: 2. Unit 2 plant conditions are as follows: 0 Reactor power is 100% 0 Plant Monitoring System (PMS) is inoperable Five minutes later control rod 30-31 inadvertently scrams.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                       ILT05-I NRC Initial Licensinq Examination
: 2. Unit 2 plant conditions are as follows:
0   Reactor power is 100%
0   Plant Monitoring System (PMS) is inoperable Five minutes later control rod 30-31 inadvertently scrams.
WHICH ONE of the following can be used to confirm that control rod 30-31 is fully inserted?
WHICH ONE of the following can be used to confirm that control rod 30-31 is fully inserted?
A. "XX' (two Xs) on the Four Rod Display.
A. XX (two X s ) on the Four Rod Display.
B. Green "IN" light is lit on the Full Core Display.
B. Green IN light is lit on the Full Core Display.
C. "- -'I (two dashed lines) on the Four Rod Display. D. Blue "SCRAM" light is lit on the Full Core Display. Page 4 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination C D Answer Key A "- -" indication on the Four Rod Display indicates an odd numbered reed switch is made up. The blue "SCRAM" light on the Full Core Display indicates that the scram valves are open, and does not indicate control rod position.
C. - -I (two dashed lines) on the Four Rod Display.
I Choice Level of Knowledge LOW I Basis or Justification Difficulty Time Allowance PRA RO SRO 2.0 3 N (b) (10) (b) (5) (minutes) 1 OCFR55.41 1 OCFR55.43 Correct: Knowledge/Ability KIA Incorrect 295006 Importance:
D. Blue SCRAM light is lit on the Full Core Display.
RO / SRO AA2.02 4.3 / 4.4 Incorrect The full in and full out lights on the Full Core Display continue to function with PMS and RDCS inoperable.
Page 4 of 200
Two X's on the Four Rod Display indicate that control rod indication is unknown, due to more than one reed switch being made up. Source: Reference(s): Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank ARC 108 Reactor, E-4 0 Previous NRC Exam 0 Other Exam Bank Learning 0 bjective:
 
LLOTOO80.02 Required Materials:
Limerick Generating Station                           ILT05-1 NRC Initial Licensing Examination Answer Key I          Choice            I                                Basis or Justification Correct:                The full in and full out lights on the Full Core Display continue to function with PMS and RDCS inoperable.
Incorrect                Two Xs on the Four Rod Display indicate that control rod indication is unknown, due to more than one reed switch being made up.
Incorrect          C    A - - indication on the Four Rod Display indicates an odd numbered reed switch is made up.
D    The blue SCRAM light on the Full Core Display indicates that the scram valves are open, and does not indicate control rod position.
Level of     Difficulty Time Allowance           PRA                 RO                     SRO Knowledge                    (minutes)                            10CFR55.41              10CFR55.43 LOW          2.0               3                 N               (b) (10)                 (b) (5)
Source Documentation Source:                  New Exam Item                              0Previous NRC Exam 0 Modified Bank Item                          0Other Exam Bank 0 ILT Exam Bank Reference(s):        ARC 108 Reactor, E-4 Learning            LLOTOO80.02 0bjective:
Knowledge/Ability 295006                                               Importance:   RO / SRO KIA                  AA2.02                                                           4.3 / 4.4 Required Materials:
Notes and Comments:
Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                    ILT05-I NRC Initial Licensing Examination
: 3. LGS site conditions are as follows:
Both units are at 100% power 0  Both units Auxiliary transformers are supplying their respective Unit Auxiliary busses 0  The 10 Station Auxiliary Bus is de-energized for maintenance 0  All other station electrical busses are energized Subsequently, the 20 Station Auxiliary Bus supply breaker (205) trips open.
WHICH ONE of the following identifies the status of the 22 Auxiliary Bus and the D22 Safeguard Bus twenty (20) seconds later?
22 Auxiliarv Bus            D22 Safeguard Bus A.        De-energized                  De-energized B.        Energized                    De-energized C.        De-energized                  Energized D.        Energized                    Energized Page 6 of 200
 
Limerick Generating Station                        ILT05-1 NRC Initial Licensing Examination r-    ~                                        Answer Key Correct:            D    The 22 Aux Bus will continue to be supplied by the Unit 2 Main Generator D22 Diesel Generators will start and supply the D22 Safeguard Bus in approximately I O seconds.
Incorrect          A    Both busses will be energized as described above.
Incorrect Incorrect IBl      While this choice is correct for the 22 Aux Bus, it is incorrect for D22 Safeguard Bus, which will be energized by the D22 D/G within 10 seconds While this choice is correct for the D22 Safeguard Bus, it is incorrect for the 22 Aux Bus, which will remain energized from the Unit 2 Main Generator.
                                                                                                                ~
Psychometrics Level of      Difficulty  Time Allowance          PRA                RO                        SRO Knowledge                      (minutes)                          10CFR55.41                10CFR55.43      -
HIGH          3.5              3                Y                (b) (10)                  (b) (5)
Source:                 [XI New Exam Item                              Previous NRC Exam 0Modified Bank Item                          0Other Exam Bank I7 ILT Exam Bank Reference(s):         E10/20, Steps 2.1 and 2.3.1 Learning              LLOT0640.08 0bjective:
Knowledge/Ability 295003                                                Importance:    RO / SRO WA                    AA2.04                                                            3.5 13.7 Required Materials :
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                    lLTO5-I NRC Initial Licensing Examination
: 4. Unit I plant conditions are as follows:
0  Reactor Power is 100%
0  Division 4 DC (125 VDC Bus D) is de-energized The following events then occur:
0  Drywell Pressure rises to 2.0 psig Both HPCl Exhaust Diaphragms rupture on pump start 0  HPCl room temperature rises and stabilizes at 198°F 0  No operator action is taken WHICH ONE of the following describes the status of HPCl steam line containment isolation valves after the events above?
INBOARD ISOL (I    F002)        OUTBOARD ISOL (1F003)
A.        Closed                            Open B.        Closed                            Closed C.        Open                              Closed D.        Open                              Open Page 8 of 200
 
Limerick Generating Station                        ILT05-1 NRC Initial Licensing Examination Answer Key SRQ Basis or Justification Correct:          C    A HPCl isolation signal is present due to high turbine exhaust rupture diaphragm pressure. The 1F003 valve isolates, however, the 1F002 valve does not isolate due to NO control power to the isolation logic.
Incorrect          A    The 1FOO2 valve does not isolate due to NO control power to the isolation logic Incorrect          B    The IF002 valve does not isolate due to NO control power to the isolation logic Incorrect          D    The 1F003 valve isolates Level of    Difficulty  Time Allowance        PRA                  RO                    SRO Knowledge                      (minutes)                        10CFR55.41              IOCFR55.43 HIGH          3.0              3              Y                (b) (7)                  N/A Source Documentation Source:                    New Exam Item                             0Previous NRC Exam 0Modified Bank Item                             Other Exam Bank 0 ILT Exam Bank Reference(s):          GP-8.1, Rev.11, Pg. 31; GE Elemental Dwgs. M-1-E41-1030-F-004, Shts. 1 & 2 M-1-E41-1030-F-005, Shts 1 & 2 Learning               LLOT0340.14 Objective:
Knowledge/Ability 295004                                            I Importance:  RO / SRO WA                  I AA1.02                                                       3.8 / 4.1 Required Materials:
Notes and Comments:
Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensing Examination
Prepared By:
: 3. LGS site conditions are as follows: Both units are at 100% power 0 Both units' Auxiliary transformers are supplying their respective Unit Auxiliary busses 0 The 10 Station Auxiliary Bus is de-energized for maintenance 0 All other station electrical busses are energized Subsequently, the 20 Station Auxiliary Bus supply breaker (205) trips open. WHICH ONE of the following identifies the status of the 22 Auxiliary Bus and the D22 Safeguard Bus twenty (20) seconds later?
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
22 Auxiliarv Bus D22 Safeguard Bus A. De-energized De-energized B. Energized De-energized C. De-energized Energized D. En erg ized Energized Page 6 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Correct: Incorrect r- ~ Answer Key D The 22 Aux Bus will continue to be supplied by the Unit 2 Main Generator D22 Diesel Generators will start and supply the D22 Safeguard Bus in approximately IO seconds. Both busses will be energized as described above.
 
A ~ Psychometrics Level of Difficulty Time Allowance PRA RO SRO HIGH 3.5 3 Y (b) (10) (b) (5) 1 OCFR55.41 1 OCFR55.43 Knowledge (minutes) - While this choice is correct for the 22 Aux Bus, it is incorrect for D22 Safeguard Bus, which will be energized by the D22 D/G within 10 seconds IBl Incorrect Source: Reference(s):
Limerick Generating Station                   ILT05-I NRC Initial Licensing Examination
Learning 0 bjective:
: 5. Unit 1 plant conditions are as follows:
Knowledge/Ability WA While this choice is correct for the D22 Safeguard Bus, it is incorrect for the 22 Aux Bus, which will remain energized from the Unit 2 Main Generator.
0   Drywell Temperature is 140°F 0   Drywell Pressure is 1.0 psig and rising slowly 0    OT-101, HIGH DRYWELL PRESSURE, is being executed WHICH ONE of the following is a reason why Drywell cooling is maximized?
Incorrect
A. Ensure continued operation of the Reactor Recirculation Pump motors.
[XI New Exam Item 0 Modified Bank Item I7 ILT Exam Bank E10/20, Steps 2.1 and 2.3.1 LLOT0640.08 Previous NRC Exam 0 Other Exam Bank 295003 Importance:
B. Slow the rate of pressure rise to allow time to bypass the potential Drywell Chilled Water system isolation.
RO / SRO AA2.04 3.5 13.7 Required Materials
: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station lLTO5-I NRC Initial Licensing Examination
: 4. Unit I plant conditions are as follows: 0 Reactor Power is 100% 0 Division 4 DC (125 VDC Bus "D") is de-energized The following events then occur: 0 Drywell Pressure rises to 2.0 psig Both HPCl Exhaust Diaphragms rupture on pump start 0 HPCl room temperature rises and stabilizes at 198°F 0 No operator action is taken WHICH ONE of the following describes the status of HPCl steam line containment isolation valves after the events above?
INBOARD ISOL (I F002) OUTBOARD ISOL (1 F003) A. Closed Open B. Closed Closed C. Open Closed D. Open Open Page 8 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Correct: Incorrect C A Incorrect B SRQ Basis or Justification Incorrect A HPCl isolation signal is present due to high turbine exhaust rupture diaphragm pressure. The 1 F003 valve isolates, however, the 1 F002 valve does not isolate due to NO control power to the isolation logic. The 1 FOO2 valve does not isolate due to NO control power to the isolation logic D The I F002 valve does not isolate due to NO control power to the isolation logic Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 HIGH 3.0 3 Y (b) (7) The 1 F003 valve isolates SRO I OCFR55.43 N/A WA I AA1.02 Source: 3.8 / 4.1 Reference(s):
Learning Objective:
Knowledge/Ability Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam Other Exam Bank GP-8.1, Rev.11, Pg. 31; GE Elemental Dwgs. M-1-E41-1030-F-004, Shts.
1 & 2 LLOT0340.14 M-1-E41-1030-F-005, Shts 1 & 2 295004 I Importance:
RO / SRO Required Materials: Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensing Examination
: 5. Unit 1 plant conditions are as follows: 0 Drywell Temperature is 140°F 0 0 Drywell Pressure is 1.0 psig and rising slowly OT-101, HIGH DRYWELL PRESSURE, is being executed WHICH ONE of the following is a reason why Drywell cooling is maximized?
A. Ensure continued operation of the Reactor Recirculation Pump motors. B. Slow the rate of pressure rise to allow time to bypass the potential Drywell Chilled Water system isolation.
C. Protect the integrity of the ADS valve solenoids.
C. Protect the integrity of the ADS valve solenoids.
D. Slow the rate of pressure rise to allow Drywell venting. Page 10 of 200 Limerick Generating Station ILT05-1 NRC initial Licensing Examination Answer Key Level of Difficulty Time Allowance PRA RO Knowledge (min Utes) 1 OCFR55.41 LOW 2.5 2 N (b) (5) Choice SRO 1 OCFR55.43 N/A ID Correct: Knowledge/Ability WA Incorrect I A 29501 0 Importance:
D. Slow the rate of pressure rise to allow Drywell venting.
RO / SRO AK3.02 3.4 I 3.4 IB Incorrect Incorrect I c 3R-0 Basis or Justification Per OT-I 01 bases, the Drywell may be vented if pressure is less than 1.68 psig. Therefore, slowing the rate of Drywell pressure rise allows time to vent. The reason for Maximizing Drywell cooling is to slow the rise or prevent reaching 1.68 psig in the Drywell. It is not to protect the Recirc pumps. The Drywell chill water isolation may be bypassed after entry into and meeting the Drywell temperature requirements of T-I 02 The design Drywell temperature of 340°F is to protect the ADS solenoids.
Page 10 of 200
This is beyond the bases for OT-I 01. Source: Reference( s) : Learning 0 bjective:
 
Source Documentation
Limerick Generating Station                         ILT05-1 NRC initial Licensing Examination Answer Key 3R-0 Choice                                          Basis or Justification Correct:
[xi New Exam Item 0 Modified Bank Item 0 ILT Exam Bank OT-I 01, Bases Step 2.1 LLOTI 540.05 0 Previous NRC Exam Other Exam Bank Required Materials:
I D      Per OT-I01 bases, the Drywell may be vented if pressure is less than 1.68 psig. Therefore, slowing the rate of Drywell pressure rise allows time to vent.
Incorrect      I  A    The reason for Maximizing Drywell cooling is to slow the rise or prevent reaching 1.68 psig in the Drywell. It is not to protect the Recirc pumps.
Incorrect Incorrect II Bc The Drywell chill water isolation may be bypassed after entry into and meeting the Drywell temperature requirementsof T-I 02 The design Drywell temperature of 340°F is to protect the ADS solenoids.
This is beyond the bases for OT-I 01.
Level of    Difficulty  Time Allowance        PRA                  RO                      SRO Knowledge                      (minUtes)                        10CFR55.41                10CFR55.43 LOW          2.5              2                N                (b) (5)                   N/A Source Documentation Source:                [xi New Exam Item                           0Previous NRC Exam 0Modified Bank Item                             Other Exam Bank 0ILT Exam Bank Reference(s ):        OT-I01, Bases Step 2.1 Learning              LLOTI540.05 0bjective:
Knowledge/Ability 295010                                              Importance: RO / SRO WA                    AK3.02                                                          3.4 I 3.4 Required Materials:
Notes and Comments:
Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
Prepared By:
: 6. Unit 2 plant conditions are as follows: 0 The "2B" Recirc. Pump has tripped 0 Reactor power is 68% 0 All feedwater heaters are in service 0 Four OPRM channels are operable The unit is in the Restricted Region of the Power to Flow map Subsequently, the "2A Recirc Pump inadvertently trips.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
WHICH ONE of the following describes the required action and the basis for this action? A. SCRAM to prevent the occurrence of thermal hydraulic instabilities.
 
Limerick Generating Station                     ILT05-1 NRC Initial Licensinq Examination
: 6. Unit 2 plant conditions are as follows:
0 The 2B Recirc. Pump has tripped 0 Reactor power is 68%
0 All feedwater heaters are in service 0 Four OPRM channels are operable The unit is in the Restricted Region of the Power to Flow map Subsequently, the 2A Recirc Pump inadvertently trips.
WHICH ONE of the following describes the required action and the basis for this action?
A. SCRAM to prevent the occurrence of thermal hydraulic instabilities.
B. Restart a Recirc Pump to prevent RPV thermal stratification.
B. Restart a Recirc Pump to prevent RPV thermal stratification.
C. SCRAM to avoid the reactivity effects of starting a Recirc Pump in natural circulation.
C. SCRAM to avoid the reactivity effects of starting a Recirc Pump in natural circulation.
D. Insert control rods to exit the Restricted Region of the Power to Flow map. Page 12 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Choice Correct: C Answer Key Basis or Justification Although allowed by Tech. Specs., Exelon has decided to continue to direct that a manual scram be inserted with the plant in natural circulation.
D. Insert control rods to exit the Restricted Region of the Power to Flow map.
I Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
Page 12 of 200
I OCFR55.41 LOW 2.0 2 N (b) (8) to (IO) SRO 1 OCFR55.43 NIA A scram is required, however, not to avoid THI.
 
See basis for answer C. lA/ Incorrect:
Limerick Generatinq Station                         ILT05-1 NRC Initial Licensing Examination Answer Key I
Source: Reference (s) : Learning Objective:
Choice                                            Basis or Justification Correct:          C      Although allowed by Tech. Specs., Exelon has decided to continue to direct that a manual scram be inserted with the plant in natural circulation.
KnowledgelAbility KIA By procedure, Limerick does not allow restarting a Recirc. Pump in natural circulation with the Reactor critical.
Incorrect:
IBl Incorrect
lA/        A scram is required, however, not to avoid THI. See basis for answer C.
[XI New Exam Item Modified Bank Item ILT Exam Bank OT-I f2 Bases, step 2.1 LLOTI 540.05 0 Previous NRC Exam Other Exam Bank 295001 Importance:
Incorrect IBl        By procedure, Limerick does not allow restarting a Recirc. Pump in natural circulation with the Reactor critical.
RO / SRO AKI .01 3.5 13.6 This is not an allowed action in natural circulation.
Incorrect I D /      This is not an allowed action in natural circulation.
ID/ Incorrect Required Materials:
Level of      Difficulty    Time Allowance          PRA                  RO                  SRO Knowledge                        (minutes)                            IOCFR55.41            10CFR55.43 LOW            2.0                2                N              (b) (8) to (IO)            NIA Source:                  [XI New Exam Item                             0 Previous NRC Exam Modified Bank Item                             Other Exam Bank ILT Exam Bank Reference(s):          OT-I f 2 Bases, step 2.1 Learning              LLOTI540.05 Objective:
KnowledgelAbility 295001                                                   Importance: RO / SRO KIA                    AKI .01                                                         3.5 13.6 Required Materials:
Notes and Comments:
Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILTO5-1 NRC Initial Licensinq Examination
Prepared By:
: 7. Unit 1 plant conditions are as follows: 0 Reactor power is 35% 0 GEN STATOR COOLANT TROUBLE (125 B4) Annunciator is alarming An EO verifies the Stator Cooling Water return temperature is 82OC and rising. WHICH ONE of the following describes the automatic response of EHC due to the conditions above? A. LOAD SET will reduce to 21.4% Bypass valves will remain closed B. LOAD SET will reduce to 21.4% Bypass valves will open C. LOAD LIMIT will reduce to 21.4% Bypass valves will open D. LOAD LIMIT will reduce to 21.4% Bypass valves remain closed Page 14 of 200
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
-- ~ Incorrect Limerick Generating Station ILTO5-I NRC Initial Licensing Examination D This is incorrect as load limit does not runback, also bypass valves will open Answer Key Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 1 OCFR55.41 1 OCFR55.43 5 High 3.0 4 Y b)7 N 295007 AA1.05 Importance: RO
 
/ SRO 3.7 / 3.8 Source : Reference(s):
Limerick Generatinq Station                   ILTO5-1 NRC Initial Licensinq Examination
Learning 0 bjective:
: 7. Unit 1 plant conditions are as follows:
Knowledge/Ability WA Source Documentation New Exam Item 0 Modified Bank Item c] ILT Exam Bank c] Previous NRC Exam 0 Other Exam Bank ON-I 14, Step 2.10 LLOT0590.03 (Description of K&A, from catalog) Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE:
0   Reactor power is 35%
Reactorrrurbine Pressure Regulating System !quired Materials: Notes and Comments:
0   GEN STATOR COOLANT TROUBLE (125 B4) Annunciator is alarming An EO verifies the Stator Cooling Water return temperature is 82OC and rising.
Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination ATTACHMENT:
WHICH ONE of the following describes the automatic response of EHC due to the conditions above?
SE-1 Provided 8. The Main Control Room has become uninhabitable and SE-1, Remote Shutdown, is in progress at the Remote Shutdown Panel with the following conditions:
A. LOAD SET will reduce to 21.4%
0 All SE-1 immediate operator actions are complete 0 All Remote Shutdown Panel transfer switches are in "EMERGENCY" 0 Reactor Level is +IO" 0 Reactor Pressure is 490 psig WHICH ONE of the following identifies the EARLIEST point from now where Shutdown Cooling can be placed in service? A. 1.0 Hours B. 1.5 Hours C. 2.0 Hours D. 2.5 Hours Page 16 of 200 Limerick Generating Station ILTO5-I NRC Initial Licensinq Examination B A C I Choice Basis or Justification Using Attachment 2 and 3 to SE-1 and at the maximum cooldown rate, it would take at least 1.5 hours to go from 470 degrees F (490 psig) to 320 degrees F (75 psig) This would mean exceeding the maximum cooldown rate This does not identify the minimum amount of time before SDC can be placed in service. I Correct: D Incorrect This does not identify the minimum amount of time before SDC can be placed in service. 1 Incorrect Level of Difficulty Time Allowance PRA HIGH 3.5 5 Y Knowledge (minutes)
Bypass valves will remain closed B. LOAD SET will reduce to 21.4%
Incorrect I----- RO SRO 1 OCFR55.41 1 OCFR55.43 (b) (IO) (b) (5) Source: Reference(s):
Bypass valves will open C. LOAD LIMIT will reduce to 21.4%
Learning 0 bjective:
Bypass valves will open D. LOAD LIMIT will reduce to 21.4%
New Exam Item 0 Modified Bank Item 0 ILT Exam Bank SEI, Attachments 2 & 3 LLOT0735.04
Bypass valves remain closed Page 14 of 200
[7 Previous NRC Exam 0 Other Exam Bank Knowledge/Ability WA 29501 6 Importance:
 
RO / SRO 2.1.25 2.8 t 3.1 Required Materials:
Limerick Generating Station                         ILTO5-I NRC Initial Licensing Examination Answer Key
      ~
Incorrect          D   This is incorrect as load limit does not runback, also bypass valves will open Psychometrics Level of       Difficulty Time Allowance         PRA                 RO                     SRO Knowledge                     (minutes)                           10CFR55.41               10CFR55.43 5   High           3.0             4                               Y b)7                       N Source Documentation Source:                     New Exam Item                             c]Previous NRC Exam 0Modified Bank Item                         0Other Exam Bank c]ILT Exam Bank Reference(s):          ON-I 14, Step 2.10 Learning                LLOT0590.03 0bjective:
Knowledge/Ability 295007                                                Importance: RO / SRO WA                      AA1.05                                                        3.7 / 3.8 (Description of K&A, from catalog)
Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE:
Reactorrrurbine Pressure Regulating System
  !quired Materials:
Notes and Comments:
Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                     ILT05-1 NRC Initial Licensinq Examination ATTACHMENT: SE-1 Provided
: 8. The Main Control Room has become uninhabitable and SE-1, Remote Shutdown, is in progress at the Remote Shutdown Panel with the following conditions:
0 All SE-1 immediate operator actions are complete 0 All Remote Shutdown Panel transfer switches are in EMERGENCY 0 Reactor Level is + I O 0 Reactor Pressure is 490 psig WHICH ONE of the following identifies the EARLIEST point from now where Shutdown Cooling can be placed in service?
A. 1.0 Hours B. 1.5 Hours C. 2.0 Hours D. 2.5 Hours Page 16 of 200
 
Limerick Generating Station                       ILTO5-I NRC Initial Licensinq Examination I         Choice                                         Basis or Justification I      Correct:          B    Using Attachment 2 and 3 to SE-1 and at the maximum cooldown rate, it would take at least 1.5 hours to go from 470 degrees F (490 psig) to 320 degrees F (75 psig)
Incorrect          A    This would mean exceeding the maximum cooldown rate 1    Incorrect          C    This does not identify the minimum amount of time before SDC can be placed in service.
I-----Incorrect          D   This does not identify the minimum amount of time before SDC can be placed in service.
Level of     Difficulty Time Allowance         PRA                 RO                    SRO Knowledge                     (minutes)                         10CFR55.41             10CFR55.43 HIGH          3.5              5                Y                (b) (IO)               (b) (5)
Source:                   New Exam Item                           [7 Previous NRC Exam 0Modified Bank Item                         0Other Exam Bank 0ILT Exam Bank Reference(s):        SEI, Attachments 2 & 3 Learning            LLOT0735.04 0bjective:
Knowledge/Ability 295016                                            Importance: RO / SRO WA                  2.1.25                                                     2.8 t 3.1 Required Materials:
SE-1 Notes and Comments:
SE-1 Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination
Prepared By:
: 9. Both units are at 100% power: 0 0 0 A loss of the 220 KV switchyard occurs followed immediately by a lockout of the 4A Auto Transformer The D12 and D14 Diesel Generators fail to start All other Diesel Generators start as designed WHICH ONE of the following systems can be used to provide alternate cooling to the TECW heat exchangers and the procedural direction for using this system? Alternate Cooling Water for TECW Heat Exchanqers A. ESW B. ESW C. RECW D. RECW Procedural Direction E-l0/20, Loss Of Offsite Power E-I, Station Blackout E-l0/20, Loss Of Offsite Power E-I, Station Blackout Page 18 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Incorrect Answer Key D RECW is not hard piped to backup TECW. The correct procedure is E- 10/20. Since six of the Diesel Generators start, this is not a Station Blackout.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
I Choice I Basis or Justification Level of Knowledge High ESW can be used to backup normal Service Water for TECW and RECW by performing manual local valve manipulations per E-I 0/20. /A( Correct: Difficulty Time Allowance PRA RO SRO 3.5 4 Y (7) N/A 1 OCFR55.41 1 OCFR55.43 (minutes)
 
The correct procedure is E-10/20. Since six of the Diesel Generators start, this is not a Station Blackout.
Limerick Generating Station                   lLTO5-1 NRC Initial Licensing Examination
Incorrect 29501 8 AA1.01 RECW is not hard piped to backup TECW. (c/ Incorrect Importance:
: 9. Both units are at 100% power:
RO / SRO 3.6 13.5 Source: Reference(s):
0   A loss of the 220 KV switchyard occurs followed immediately by a lockout of the 4A Auto Transformer 0    The D12 and D14 Diesel Generators fail to start 0    All other Diesel Generators start as designed WHICH ONE of the following systems can be used to provide alternate cooling to the TECW heat exchangers and the procedural direction for using this system?
Learning Objective:
Alternate Cooling Water for TECW Heat Exchanqers                         Procedural Direction A.       ESW                               E-l0/20, Loss Of Offsite Power B.      ESW                              E-I, Station Blackout C.      RECW                              E-l0/20, Loss Of Offsite Power D.      RECW                              E-I, Station Blackout Page 18 of 200
Knowledg e/Ability KIA Source Documentation 0 New Exam item Modified Bank item ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank E-I 0/20, Attachment 5 LLOT0430.07 (Description of K&A, from catalog)
 
Limerick Generating Station                         ILT05-1 NRC Initial Licensinq Examination Answer Key I           Choice           I                             Basis or Justification Correct:                  ESW can be used to backup normal Service Water for TECW and RECW
                      /A(        by performing manual local valve manipulations per E-I 0/20.
Incorrect                The correct procedure is E-10/20. Since six of the Diesel Generators start, this is not a Station Blackout.
Incorrect                 RECW is not hard piped to backup TECW.
(c/       RECW is not hard piped to backup TECW. The correct procedure is E-Incorrect         D 10/20. Since six of the Diesel Generators start, this is not a Station Blackout.
Level of    Difficulty  Time Allowance          PRA                RO                     SRO Knowledge                        (minutes)                        10CFR55.41              10CFR55.43 High          3.5                 4                Y                (7)                     N/A Source Documentation Source:                0New Exam item                               0Previous NRC Exam Modified Bank item                         0Other Exam Bank ILT Exam Bank Reference(s):        E-I 0/20, Attachment 5 Learning              LLOT0430.07 Objective:
Knowledge/Ability 295018                                              Importance: RO / SRO KIA                  AA1.01                                                            3.6 13.5 (Description of K&A, from catalog)
Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Backup systems Required Materials:
Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Backup systems Required Materials:
Notes and Comments:
Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Prepared By:
- Limerick Generating Station ILT05-1 NRC Initial Licensing Examination IO. Unit 1 Reactor Power is 100% with Instrument Air and Service Air in a normal lineup, when the following annunciator alarms:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
0 IA INSTRUMENT AIR HEADER LO PRESS (I 18 B2) The following indications are observed:
 
0 "IA Instrument Air Header Pressure is 85 psig and dropping slowly. 0 "1 B" Instrument Air Header Pressure is 108 psig and steady 0 Service Air Header Pressure is 102 psig and rising slowly 0 Backup Service Air Receiver is 100 psig and steady 10 minutes later the following indications are observed:
                                                                                -
0 "IA Instrument Air Header Pressure is 69 psig and dropping slowly 0 "1 B" Instrument Air Header Pressure is 100 psig and dropping slowly 0 Service Air Header Pressure is 99 psig and dropping slowly 0 Backup Service Air Receiver is 102 psig and dropping slowly WHICH ONE of the following identifies the source of air for the Instrument Air LOADS and Service Air LOADS? Source of Instrument Air Source of Service Air A. "I B" Instrument Air compressor Service Air Compressor B. "1 B" Instrument Air Compressor Backup Service Air Compressor C. Service Air Compressor Service Air Compressor D. Service Air Compressor Backup Service Air Compressor.
Limerick Generating Station                   ILT05-1 NRC Initial Licensing Examination IO. Unit 1 Reactor Power is 100% with Instrument Air and Service Air in a normal lineup, when the following annunciator alarms:
Page 20 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Correct: Answer Key A Question ID# 010 Both RC Level of Difficulty Time Allowance PRA Knowledge (minutes)
0 I A INSTRUMENT AIR HEADER LO PRESS ( I 18 B2)
High 4.0 6 Y Choice RO SRO 1 OCFR55.41 1 OCFR55.43 Y (b) (5) N Source: Reference (s): Learning 0 bjective:
The following indications are observed:
Knowledge/Ability WA Incorrect:
0   I A Instrument Air Header Pressure is 85 psig and dropping slowly.
I B [E3 New Exam Item 0 Modified Bank Item [7 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank M-I 5 LLOT0730.02, 04, 07, IO 29501 9 Importance:
0 1B Instrument Air Header Pressure is 108 psig and steady 0 Service Air Header Pressure is 102 psig and rising slowly 0 Backup Service Air Receiver is 100 psig and steady 10 minutes later the following indications are observed:
RO / SRO AK3.01 3.3 13.4 Incorrect ERej Basis or Justification "1 B" Compressor will begin supplying the "IA" loads on higher pressure due to check valves at the individual load. Service Air Compressor remains in service for service air loads. The Backup Service Air Compressor, which is normally lined up to Unit 1, will only supply Unit 1 Service Air, if service air header pressure drops below 92 psig.. Service Air Compressor would only supply IA if both the 1A & 1 B IA header pressures were low. See B and C above Required Materials:
0   I A Instrument Air Header Pressure is 69 psig and dropping slowly 0 1 B Instrument Air Header Pressure is 100 psig and dropping slowly 0 Service Air Header Pressure is 99 psig and dropping slowly 0 Backup Service Air Receiver is 102 psig and dropping slowly WHICH ONE of the following identifies the source of air for the Instrument Air LOADS and Service Air LOADS?
Source of Instrument Air         Source of Service Air A. I B Instrument Air compressor   Service Air Compressor B. 1 B Instrument Air Compressor Backup Service Air Compressor C. Service Air Compressor             Service Air Compressor D. Service Air Compressor             Backup Service Air Compressor.
Page 20 of 200
 
Limerick Generating Station                           ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 010 Both RC     ERej Choice                                             Basis or Justification Correct:          A    1B Compressor will begin supplying the IA loads on higher pressure due to check valves at the individual load. Service Air Compressor remains in service for service air loads.
Incorrect:      I  B    The Backup Service Air Compressor, which is normally lined up to Unit 1, will only supply Unit 1 Service Air, if service air header pressure drops below 92 psig..
Incorrect                Service Air Compressor would only supply IA if both the 1A & 1B IA header pressures were low.
See B and C above Level of    Difficulty  Time Allowance          PRA                  RO                    SRO Knowledge                      (minutes)                          10CFR55.41              10CFR55.43 High          4.0              6                Y              Y (b) ( 5 )                N Source:                [E3 New Exam Item                              0Previous NRC Exam 0Modified Bank Item                            0Other Exam Bank
[7 ILT Exam Bank Reference(s):        M-I 5 Learning              LLOT0730.02, 04,07, I O 0bjective:
Knowledge/Ability 295019                                                Importance:  RO / SRO WA                    AK3.01                                                            3.3 13.4 Required Materials:
Notes and Comments:
Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination 1 I. Unit 2 has just entered Opcon 4 in preparation for a refueling outage. A failure of HV-51-2F008 results in a loss of Shutdown Cooling and necessitates establishing Alternate Shutdown Cooling using SRV's and Suppression Pool Cooling. Conditions have been established as follows: Suppression Pool Cooling is in service with "2A" RHR. Suppression Pool pressure is 0 psig SRV handswitches for the "2K" and "2M" SRVs are in the OPEN position Injection to the RPV has been established with the "2D" RHR pump via HV-51-2F017D RPV Level is 150" on Shutdown Range RPV pressure is 40 psig WHICH ONE of the following describes the action required in order to establish Alternate Decay Heat removal? A. Reduce RPV injection until RPV Level is 5 100". B. Increase RPV injection until RPV Level is 2 200". C. Reduce RPV injection until RPV pressure is 5 25 psig. D. Increase RPV injection until RPV pressure is 2 50 psig. Page 22 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination D Answer Key 50# DIP is required across the SRV's in order to open and establish alternate heat removal. Choice I Basis or Justification Incorrect Incorrect Incorrect Correct A While 100 is an important milestone in OT-100 Reactor High Level, when trying to prevent filling MS lines, filling the MSLS is required for this procedure.
Prepared By:
Level is high enough to fill the MSL's and no additional Level is required.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
B C In order to establish Alternate heat removal the SRV's must open which requires 50# D/P. Correct conditions require raising pressure, not lowering.
 
Level of Difficulty Time Allowance PRA RO 1 OCFR55.41 Knowledge (minutes)
Limerick Generating Station                   ILT05-1 NRC Initial Licensing Examination 1I. Unit 2 has just entered Opcon 4 in preparation for a refueling outage.
High 4.0 5 Y Y (b) (7) SRO 1 OCFR55.43 N Source: Reference( s) : Learning 0 bjective : [XI New Exam Item Modified Bank Item ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank ON-121, Step 2.1.7, Attachment 6 S41.7.B, Step 4.2 LLOT-5010.01 Knowledge/Abili ty 29502 1 KIA 1 AA1.04 Importance:
A failure of HV-51-2F008 results in a loss of Shutdown Cooling and necessitates establishing Alternate Shutdown Cooling using SRVs and Suppression Pool Cooling.
RO / SRO 3.7 13.7 (Description of K&A, from catalog)
Conditions have been established as follows:
Ability to operate and or monitor the following as they apply to LOSS OF SHUTDOWN COOLING: Alternate Heat Removal Methods Required Materials Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
Suppression Pool Cooling is in service with 2A RHR.
: 12. Unit I plant conditions are as follows: 0 Reactor level is 20" 0 Reactor Pressure is 350 psig 0 Drywell Pressure is 25 psig 0 "1 B" RHR Pump is operating at 8200 gpm with the following valve indications:
Suppression Pool pressure is 0 psig SRV handswitches for the 2Kand 2M SRVs are in the OPEN position Injection to the RPV has been established with the 2D RHR pump via HV-51-2F017D RPV Level is 150 on Shutdown Range RPV pressure is 40 psig WHICH ONE of the following describes the action required in order to establish Alternate Decay Heat removal?
HV-51-1 F016B, OUTBOARD SPRAY, green light lit HV-51-1 F017B, LPCl INJECTION, red, green and white lights lit HV-51-1 F021 B, INBOARD SPRAY, red light lit HV-51-1F024B, FULL FLOW TEST, red, green and white lights lit The CRS has directed the PRO to place ''I B" RHR in Drywell Spray. WHICH ONE of the following actions must be performed to initiate Drywell Spray? A. Arm and depress "I B" RHR manual LOCA initiation pushbutton and open HV-51-1F016B. B. Close HV-51-1 FO21 B, then open HV-51-1 F016B, then reopen HV-51-1 F021 B. C. Close HV-51-1F017B and open HV-51-1F016B.
A. Reduce RPV injection until RPV Level is 5 100.
D. Close HV-51-1 F024B and open HV-51-1 FOI 6B. Page 24 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.0 4 Y Y (b) (7) Answer Key SRO 1 OCFR55.43 N Question ID# 012 Both RC Reference@):
B. Increase RPV injection until RPV Level is 2 200.
Choice 0 Modified Bank Item 0 ILT Exam Bank 0 Other Exam Bank T-225, Step 4.5 IC Correct lA Incorrect Incorrect r Incorrect Basis or Justification 17B valve must be closed in order to open 16B - all other conditions for opening 16B are already . LOCA Signal already present. PB not required.
C. Reduce RPV injection until RPV pressure is 5 25 psig.
Also 178 must be closed. This valve manipulation only required if LOCA signal not present. 17B must also be closed.. ~~ ~ ~~ ~~ 24B dose not need to be closed Source Documentation Source: I New Exam Item Previous NRC Exam Learning Objective:
D. Increase RPV injection until RPV pressure is 2 50 psig.
I LL0T0370.09 Knowledge/Ability 295024 WA 1 EA1.04 Importance:
Page 22 of 200
RO / SRO 4.1 13.9 (Description of K&A, from catalog) Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:
 
Limerick Generating Station                           ILT05-1 NRC Initial Licensinq Examination Answer Key Choice            I                                Basis or Justification Correct          D      50# DIP is required across the SRVs in order to open and establish alternate heat removal.
Incorrect         A     While 1 0 0 is an important milestone in OT-100 Reactor High Level, when trying to prevent filling MS lines, filling the MSLS is required for this procedure.
Incorrect          B      Level is high enough to fill the MSLs and no additional Level is required.
Incorrect          C     In order to establish Alternate heat removal the SRVs must open which requires 50# D/P. Correct conditions require raising pressure, not lowering.
Level of     Difficulty   Time Allowance           PRA                   RO                   SRO Knowledge                       (minutes)                             10CFR55.41            10CFR55.43 High         4.0               5                 Y               Y (b) (7)                   N Source:                 [XI New Exam Item                               0Previous NRC Exam Modified Bank Item                           0Other Exam Bank ILT Exam Bank Reference(s):          ON-121, Step 2.1.7, Attachment 6 S41.7.B, Step 4.2 Learning              LLOT-5010.01 0bjective:
Knowledge/Ability KIA                 1 295021 AA1.04 (Description of K&A, from catalog)
Importance: RO / SRO 3.7 13.7 Ability to operate and or monitor the following as they apply to LOSS OF SHUTDOWN COOLING:
Alternate Heat Removal Methods Required Materials Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   ILT05-1 NRC Initial Licensinq Examination
: 12. Unit Iplant conditions are as follows:
0 Reactor level is 20 0 Reactor Pressure is 350 psig 0 Drywell Pressure is 25 psig 0 1B RHR Pump is operating at 8200 gpm with the following valve indications:
HV-51-1F016B, OUTBOARD SPRAY, green light lit HV-51-1F017B, LPCl INJECTION, red, green and white lights lit HV-51-1F021B, INBOARD SPRAY, red light lit HV-51-1F024B, FULL FLOW TEST, red, green and white lights lit The CRS has directed the PRO to place I B RHR in Drywell Spray.
WHICH ONE of the following actions must be performed to initiate Drywell Spray?
A. Arm and depress I   B RHR manual LOCA initiation pushbutton and open HV-51-1F016B.
B. Close HV-51-1FO21B, then open HV-51-1F016B, then reopen HV-51-1F021B.
C. Close HV-51-1F017B and open HV-51-1F016B.
D. Close HV-51-1F024B and open HV-51-1FOI 6B.
Page 24 of 200
 
Limerick Generating Station                       ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 012 Both RC Choice                                         Basis or Justification Correct IC        17B valve must be closed in order to open 16B - all other conditions for opening 16B are already .
r                  lA Incorrect                LOCA Signal already present. PB not required. Also 178 must be closed.
Incorrect                This valve manipulation only required if LOCA signal not present. 17B must also be closed..
                                ~~           ~ ~~         ~~
Incorrect                24B dose not need to be closed Level of    Difficulty  Time Allowance        PRA                RO                  SRO Knowledge                    (minutes)                        10CFR55.41              10CFR55.43 Low          3.0              4              Y              Y (b) (7)                  N Source Documentation Source:             I     New Exam Item                               Previous NRC Exam 0Modified Bank Item                        0Other Exam Bank 0ILT Exam Bank Reference@):          T-225, Step 4.5 Learning Objective:           I LL0T0370.09 WA                  1 Knowledge/Ability 295024 EA1.04 Importance: RO / SRO 4.1 13.9 (Description of K&A, from catalog)
Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:
RHWLPCI Required Materials:
RHWLPCI Required Materials:
Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Notes and Comments Prepared By:
__ - ___ -- Limerick Generating Station ILT05-I NRC Initial Licensing Examination
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
: 13. An ATWS is in progress on Unit 1. RPV Level was intentionally lowered per T-I 17. The following conditions currently exist: Reactor power is 6% RPV level is -1 95" and slowly rising MSIV's are closed 1 ADS SRV is open RPV pressure is I000 psig Suppression Pool temperature is 145°F and slowly rising 2 Loops of Suppression Pool Cooling are in service Suppression Pool pressure is 6 psig & slowly rising Suppression Pool level is 24.5' and stable WHICH ONE of the following describes the required action and the reason for taking the action? A. Reduce RPV pressure to less than 900 psig, in order to maintain on the safe side of SP/L-1 SRV Tail Pipe Level Limit. B. Perform Emergency Blowdown per T-I 12, due to unable to restore and maintain RPV Level above -1 86". C. Reduce RPV pressure to less than 900 psig, in order to maintain on the safe side of SP/T-1 Heat Capacity Temperature Limit. D. Perform Emergency Blowdown per T-I 12, due to the safe side of SP/T- I, Heat Capacity Temperature Limit, cannot be maintained.
 
Page 26 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Incorrect Answer Key D Choice Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Incorrect SRO 1 OCFR55.43 A High 3.5 4 Y Y (b) (IO) Y (b) (5) Basis or Justification 295026 EA2.03 SP temp is 20°F from HCTL and rising slowly despite having 2 loops of SP Cooling in service. T-102 SPK-8 directs that if SP temp cannot be maintained on the safe side of HCTL, then maintain RPV pressure on the safe side of HCTL. SP level is high but 3.5 feet away from SP/L-l limit and level is stable - Reducing pressure for the purposes of maintaining this curve is not warranted.
_ _-       ___     --
While RPV Level is e-186, it is only 9" OOB and rising slowly. The criteria for T-l17LQ is level can be restored.
Limerick Generating Station                   ILT05-I NRC Initial Licensing Examination
With SRV's being used for pressure control, it is not unusual to go e-186 for short periods of time.
: 13. An ATWS is in progress on Unit 1.
T-I12 is not warranted under these conditions.
RPV Level was intentionally lowered per T - I 17.
SP temp is still 20°F away from HCTL and rising slowly. T-I12 is not warranted at this point Importance: RO  
The following conditions currently exist:
/ SRO 3.9 / 4.0 Source: Learning 0 bjective:
Reactor power is 6%
Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank T-102 sh.1 LLOTI 560.04 KnowledgelAbility (Description of K&A, from catalog) Ability to determine and/or interpret the following as it applies to Suppression Pool water temperature:
RPV level is -1 95 and slowly rising MSIVs are closed 1 ADS SRV is open RPV pressure is I 0 0 0 psig Suppression Pool temperature is 145°F and slowly rising 2 Loops of Suppression Pool Cooling are in service Suppression Pool pressure is 6 psig & slowly rising Suppression Pool level is 24.5 and stable WHICH ONE of the following describes the required action and the reason for taking the action?
A. Reduce RPV pressure to less than 900 psig, in order to maintain on the safe side of SP/L-1 SRV Tail Pipe Level Limit.
B. Perform Emergency Blowdown per T-I 12, due to unable to restore and maintain RPV Level above -1 86.
C. Reduce RPV pressure to less than 900 psig, in order to maintain on the safe side of SP/T-1 Heat Capacity Temperature Limit.
D. Perform Emergency Blowdown per T - I 12, due to the safe side of SP/T-I,Heat Capacity Temperature Limit, cannot be maintained.
Page 26 of 200
 
Limerick Generating Station                           ILT05-1 NRC Initial Licensing Examination Answer Key Choice                                           Basis or Justification SP temp is 20°F from HCTL and rising slowly despite having 2 loops of SP Cooling in service. T-102 SPK-8 directs that if SP temp cannot be maintained on the safe side of HCTL, then maintain RPV pressure on the safe side of HCTL.
Incorrect          A    SP level is high but 3.5feet away from SP/L-l limit and level is stable -
Reducing pressure for the purposes of maintaining this curve is not warranted.
While RPV Level is e-186, it is only 9OOB and rising slowly. The criteria for T-l17LQ is level can be restored. With SRVs being used for pressure control, it is not unusual to go e-186 for short periods of time. T-I12 is not warranted under these conditions.
Incorrect          D    SP temp is still 20°F away from HCTL and rising slowly. T-I12 is not warranted at this point Level of      Difficulty  Time Allowance          PRA                RO                     SRO Knowledge                      (minutes)                          10CFR55.41              10CFR55.43 High          3.5              4                 Y              Y (b) ( I O )            Y (b) (5)
Source Documentation Source:                    New Exam Item                               0Previous NRC Exam 0Modified Bank Item                           0Other Exam Bank 0ILT Exam Bank T-102 sh.1 Learning              LLOTI560.04 0bjective:
KnowledgelAbility 295026                                                Importance: RO / SRO EA2.03                                                          3.9 / 4.0 (Description of K&A, from catalog)
Ability to determine and/or interpret the following as it applies to Suppression Pool water temperature:
Reactor Pressure Required Materials:
Reactor Pressure Required Materials:
T-102 Sht. I Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
T-102 Sht. I Notes and Comments Prepared By:
___ __ __ Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
: 14. A LOCA is in progress on Unit 2. Drywell Temperature is 148°F. The CRS directs the PRO to maximize drywell cooling.
 
___                                             ____
Limerick Generatinq Station                   ILT05-1 NRC Initial Licensing Examination
: 14. A LOCA is in progress on Unit 2.
Drywell Temperature is 148°F.
The CRS directs the PRO to maximize drywell cooling.
Per T-I02 Bases, WHICH ONE of the following describes the minimum number of components that must be in service in order to maximize drywell cooling for the above conditions?
Per T-I02 Bases, WHICH ONE of the following describes the minimum number of components that must be in service in order to maximize drywell cooling for the above conditions?
Drywell Fans DWCW Pumps A. One Fan per Cooler B. One Fan per Cooler C. Two Fans per Cooler D. Two Fans per Cooler One Two One Two Page 28 of 200 Limerick Generating Station ILT05-I NRC Initial Licensing Examination C D Answer Key Does not meet the criteria wJrespect to the number of required DWCW pps. In addition specifics 2 DW Fans per cooler.
Drywell Fans                     DWCW Pumps A. One Fan per Cooler                       One B. One Fan per Cooler                       Two C. Two Fans per Cooler                     One D. Two Fans per Cooler                     Two Page 28 of 200
Fans are in parallel and are 100% capacity.
 
Does not represent the minimum number.
Limerick Generating Station                         ILT05-I NRC Initial Licensing Examination Answer Key I          Choice            I                              Basis or Justification I    Correct:          B  1 Meets the criteria specified in T-102 Bases, for step DW/T-5 r    Incorrect:
2 DW fans in-service - DW fans are 100% capacity and in parallel.
Incorrect A
I Choice I Basis or Justification Level of Difficulty Time Allowance PRA RO 1 OCFR55.41 Knowledge (m in u tes)
C
Low 2.5 3 Y (b) (7) I Correct: SRO 1 OCFR55.43 N B 1 Meets the criteria specified in T-102 Bases, for step DW/T-5 Knowledge/Ability WA Incorrect:
                              !
r 295028 Importance:
Does not meet the criteria specified in T-I 02 Bases, step DW/T-5. Only has one DWCW pp cunning vs. two Does not meet the criteria wJrespect to the number of required DWCW pps.
RO J SRO EK2.04 3.6 J 3.6 Does not meet the criteria specified in T-I 02 Bases, step DW/T-5. Only has one DWCW pp cunning vs. two A! Incorrect Incorrect I Source: Reference(s):
In addition specifics 2 DW Fans per cooler. Fans are in parallel and are 100% capacity.
Learning 0 bjective: Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank T-102 Bases, DW/T-5 17 Previous NRC Exam 0 Other Exam Bank LOT-1560.06 Required Materials:
Incorrect          D    Does not represent the minimum number. 2 DW fans in-service - DW fans are 100% capacity and in parallel.
T-I 02 Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
I Level of     Difficulty   Time Allowance         PRA               RO                     SRO Knowledge                     (minutes)                         10CFR55.41              10CFR55.43 Low           2.5             3                 Y               (b) (7)                   N Source Documentation Source:                  New Exam Item                            17Previous NRC Exam 0Modified Bank Item                          0Other Exam Bank 0ILT Exam Bank Reference(s):         T-102 Bases, DW/T-5 Learning              LOT-1560.06 0bjective:
: 15. Unit 2 was manually scrammed due to a leak in the Suppression Pool. 0 0 0 Suppression Pool level is 20' and lowering RClC is being used for RPV level control HPCl is being used for RPV pressure control Suppression Pool level drops to 17.9'. WHICH ONE of the following describes the required action and the reason for it? A. RClC must be secured due to insufficient net positive suction head.
Knowledge/Ability 295028                                             Importance:   RO J SRO WA                    EK2.04                                                         3.6 J 3.6 Required Materials:
B. HPCl must be secured due to insufficient net positive suction head. C. RClC must be secured in order to prevent direct pressurization of the Suppression Pool. D. HPCl must be secured in order to prevent direct pressurization of the Su p p ression Pool.
T-I 02 Notes and Comments Prepared By:
Page 30 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 2.5 3 Y Y (b) (5) Answer Key SRO 1 OCFR55.43 N/A NPSH limit for HPCl would be at 15.42 ft, where it is already secured at 18' IBl for the reason above Incorrect 295030 EK3.02 RClC Turbine exhaust pressure is insufficient to cause pressurization of the Suppression Pool in excess of PCPL. Incorrect Importance:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
RO / SRO 3.5 / 3.7 Source: Reference(s):
 
Learning 0 bjective:
Limerick Generating Station                     ILT05-1 NRC Initial Licensing Examination
Knowledge/Ability WA Source Documentation
: 15. Unit 2 was manually scrammed due to a leak in the Suppression Pool.
[XI New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam c] Other Exam Bank T-102, sh.
0   Suppression Pool level is 20 and lowering 0    RClC is being used for RPV level control 0    HPCl is being used for RPV pressure control Suppression Pool level drops to 17.9.
1 LLOTI 560.05 (Description of K&A, from catalog) Knowledge of the reasons for the following responses as they apply to Low SP Water Level: HPCl Operation Required Materials:
WHICH ONE of the following describes the required action and the reason for it?
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
A. RClC must be secured due to insufficient net positive suction head.
- Limerick Generatinn Station lLTO5-1 NRC Initial Licensing Examination
B. HPCl must be secured due to insufficient net positive suction head.
: 16. A loss of all high pressure injection has occurred on Unit 1 with conditions as follows: 0 All rods in 0 RPV Water Level is -170 and dropping 0 No low pressure ECCS pumps can be started 0 RPV pressure has been recorded at 900 psig and is being maintained with SRV's The crew is attempting to restore the "1 B" CRD pump and line up per T-240. WHICH ONE of the following describes steam cooling conditions under which adequate core cooling is assured? RPV Level RPV Pressure lniection A. -1 75" 795 psig None B. -1 85" 800 psig "1 B" CRD pump C. -1 95" 910 psig None D. -205" 890 psig "1 B" CRD pump Page 32 of 200 Limerick Generatina Station ILT05-I NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.5 5 Y (b) (8-10) ~~ Answer Key SRO 1 OCFR55.43 NIA Question ID# 016 Both-R( Source: Reference(s):
C. RClC must be secured in order to prevent direct pressurization of the Suppression Pool.
Objective:
D. HPCl must be secured in order to prevent direct pressurization of the Su pp ression Pool.
Knowledge/Ability WA Learning Choice New Exam Item 0 Modified Bank Item ILT Exam Bank 0 Previous NRC Exam 1 0 Other Exam Bank T-I 11 BASES, LR-12 through LR-17 LOT-1560.03 WA 295031 Importance:
Page 30 of 200
RO / SRO EKI .01 4.6 14.7 Correct: 1 ~ Incorrect Incorrect Incorrect A B C D SRd Basis or Justification Core Cooling is assured in steam cooling as long as level is between -161 and -201, with no injection and pressure less than the value recorded in T- I I I LR-14. Even though pressure is <I OO# below recorded value, this supply calls for a new pressure load.
 
Calculations for MZI RWL assures that there is no sub cooling at the core inlet. Since any injection would invalidate this assumption, adequate Core Cooling can't be assured if RPV level is <-I61 and water is being injected. Once stabilized, if RPV pressure rises above the value recorded in CR-14, MZIRWL calculations are no longer valid and the core may not be adequately cooled. The candidate would select this answer if he didn't recognize that the safe area of this curve is below the curve. This is a common error because this varies between curves. It is also incorrect because water is being injected. Required Materials:
Limerick Generating Station                     ILT05-1 NRC Initial Licensinq Examination Answer Key Incorrect IBl      NPSH limit for HPCl would be at 15.42 ft, where it is already secured at 18 for the reason above Incorrect               RClC Turbine exhaust pressure is insufficient to cause pressurizationof the Suppression Pool in excess of PCPL.
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Level of    Difficulty  Time Allowance        PRA                RO                         SRO Knowledge                      (minutes)                      10CFR55.41                  10CFR55.43 Low          2.5               3             Y            Y (b) (5)                       N/A Source Documentation Source:                [XI New Exam Item                       0Previous NRC Exam 0Modified Bank Item                     c]Other Exam Bank 0ILT Exam Bank Reference(s):        T-102, sh. 1 Learning              LLOTI560.05 0bjective:
- Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination
Knowledge/Ability 295030                                          Importance: RO / SRO WA                    EK3.02                                                          3.5 / 3.7 (Description of K&A, from catalog) Knowledge of the reasons for the following responses as they apply to Low SP Water Level: HPCl Operation Required Materials:
: 17. Unit 1 conditions are as follows: 0 Core reload has just commenced during a refueling outage. 0 SRM count rate is 30 cps While lowering a fuel assembly not adjacent to an SRM, count rate increases to 65 cps and stabilizes.
Notes and Comments Prepared By:
WHICH ONE of the following describes the required action, if any? A. Immediately evacuate the refuel floor.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                    -
Limerick Generatinn Station                   lLTO5-1 NRC Initial Licensing Examination
: 16. A loss of all high pressure injection has occurred on Unit 1 with conditions as follows:
0   All rods in 0   RPV Water Level is -170 and dropping 0   No low pressure ECCS pumps can be started 0   RPV pressure has been recorded at 900 psig and is being maintained with SRVs The crew is attempting to restore the 1B CRD pump and line up per T-240.
WHICH ONE of the following describes steam cooling conditions under which adequate core cooling is assured?
RPV Level           RPV Pressure               lniection A.           -1 75           795 psig                   None B.           -185            800 psig                   1B CRD pump C.           -1 95           910 psig                   None D.           -205             890 psig                   1B CRD pump Page 32 of 200
 
Limerick Generatina Station                         ILT05-I NRC Initial Licensing Examination
    ~~
Answer Key Question ID# 016 Both-R(     SRd Choice                                           Basis or Justification Correct:         A     Core Cooling is assured in steam cooling as long as level is between -161 and -201, with no injection and pressure less than the value recorded in T-IIILR-14. Even though pressure is <I     OO# below recorded value, this supply calls for a new pressure load.
1  ~  Incorrect          B    Calculations for MZI RWL assures that there is no sub cooling at the core inlet. Since any injection would invalidate this assumption, adequate Core Cooling cant be assured if RPV level is <-I61 and water is being injected.
Incorrect          C    Once stabilized, if RPV pressure rises above the value recorded in CR-14, MZIRWL calculations are no longer valid and the core may not be adequately cooled.
Incorrect          D    The candidate would select this answer if he didnt recognize that the safe area of this curve is below the curve. This is a common error because this varies between curves. It is also incorrect because water is being injected.
Level of    Difficulty  Time Allowance          PRA                RO                    SRO Knowledge                      (minutes)                          10CFR55.41            10CFR55.43 High        3.5                5              Y              (b) (8-10)                NIA Source:                  New Exam Item                            0Previous NRC Exam 0Modified Bank Item                      1  0Other Exam Bank ILT Exam Bank Reference(s):        T-I 11 BASES, LR-12 through LR-17 Learning            LOT-1560.03 Objective:
Knowledge/Ability WA 295031                                          Importance:  RO / SRO WA                    EKI .01                                                        4.6 14.7 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   ILTO5-1 NRC Initial Licensing Examination
: 17. Unit 1 conditions are as follows:
0 Core reload has just commenced during a refueling outage.
0 SRM count rate is 30 cps While lowering a fuel assembly not adjacent to an SRM, count rate increases to 65 cps and stabilizes.
WHICH ONE of the following describes the required action, if any?
A. Immediately evacuate the refuel floor.
B. Suspend component movement.
B. Suspend component movement.
C. Continue lowering fuel assembly.
C. Continue lowering fuel assembly.
D. Raise the fuel assembly from the core so that it clears the upper grid. Page 34 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination A C D Correct: is reached This would only be appropriate in the event of criticality.
D. Raise the fuel assembly from the core so that it clears the upper grid.
FH-105 requires suspension of component movement when one doubling is reached This action is not required if it is the 1'' through 4'h fuel assembly adjacent to the detector at the start of a core reload. Incorrect Level of Difficulty Time Allowance PRA RO Knowledge (min Utes) 1 OCFR55.41 Low 2.0 3 Y (b) (8-10) I Incorrect SRO 1 OCFR55.43 N/A Incorrect Source: Reference( s ): Learning Objective:
Page 34 of 200
Knowledge/Ability KIA New Exam Item 0 Modified Bank Item ILT Exam Bank Previous NRC Exam Other Exam Bank FH-105, STEP 3.7 LLOT0760.12 295023 Importance:
 
RO / SRO 2.2.28 3.5 / 3.3 Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination
Limerick Generating Station                         ILT05-1 NRC Initial Licensinq Examination Correct:
: 18. An ATWS is in progress on Unit 1. Reactor Power is 100%. A Group 1 NSSSS isolation occurs and SRV's open to lower RPV pressure.
is reached Incorrect          A    This would only be appropriate in the event of criticality.
The PRO is controlling RPV pressure 990 - 1096 psig with SRV's. The highest recorded RPV steam dome pressure was 1340 psig. WHICH ONE of the following describes actions that satisfy the MOST LIMITING Tech Spec requirements?
I    Incorrect          C    FH-105 requires suspension of component movement when one doubling is reached Incorrect          D    This action is not required if it is the 1'' through 4'h fuel assembly adjacent to the detector at the start of a core reload.
Level of     Difficulty   Time Allowance         PRA                     RO                       SRO Knowledge                     (minUtes)                             10CFR55.41                 10CFR55.43 Low           2.0               3                 Y               (b) (8-10)                     N/A Source:                   New Exam Item                                   Previous NRC Exam 0Modified Bank Item                                 Other Exam Bank ILT Exam Bank Reference(s):        FH-105, STEP 3.7 Learning            LLOT0760.12 Objective:
Knowledge/Ability 295023                                                 Importance:   RO / SRO KIA                  2.2.28                                                               3.5 / 3.3 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                 lLTO5-1 NRC Initial Licensing Examination
: 18. An ATWS is in progress on Unit 1.
Reactor Power is 100%.
A Group 1 NSSSS isolation occurs and SRVs open to lower RPV pressure.
The PRO is controlling RPV pressure 990 - 1096 psig with SRVs.
The highest recorded RPV steam dome pressure was 1340 psig.
WHICH ONE of the following describes actions that satisfy the MOST LIMITING Tech Spec requirements?
A. Notify the NRC and be in at least STARTUP within 6 hours.
A. Notify the NRC and be in at least STARTUP within 6 hours.
B. Place RPS in the tripped condition within 6 hours and be in HOT SHUTDOWN within I2 hours. C. Notify the NRC within I hour and be in HOT SHUTDOWN within 2 hours. D. Be in HOT SHUTDOWN within 12 hours and COLD SHUTDOWN within the next 24 hours.
B. Place RPS in the tripped condition within 6 hours and be in HOT SHUTDOWN within I 2 hours.
Page 36 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
C. Notify the NRC within Ihour and be in HOT SHUTDOWN within 2 hours.
I OCFR55.41 High 3.5 5 N (b) (8-1 0) Answer Key SRO 1 OCFR55.43 NIA Choice Source: Reference(s):
D. Be in HOT SHUTDOWN within 12 hours and COLD SHUTDOWN within the next 24 hours.
Learning 0 bjective:
Page 36 of 200
KnowledgelAbility KIA Correct: New Exam Item Modified Bank Item ILT Exam Bank Previous NRC Exam Other Exam Bank LGS Tech Specs LLOTI 540.05 295025 Importance:
 
RO I SRO EKI .05 4.41 4.7 Incorrect Incorrect Incorrect C A B D Basis or Justification Reactor Coolant System Pressure Safety Limit has been violated. Tech Spec action must satisfy 2.1 and 6.7.1 States the NRC must be notified and meets 3.0.3 for LCO not met and 3.3.4 for ATWS Instrumentation but is not conservative enough to meet 2.1 and 6.7.1 Meets 3.3.1 for RPS Instrumentation but is not conservative enough to meet 2.1 and does not meet 6.7.1 This meets 3.4.2 for SRV's and 3.4.6.2 for Reactor Steam Dome Pressure, but is not conservative enough to meet 2.1 and does not meet 6.7.1 Required Materials: Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Limerick Generatinq Station                       ILT05-1 NRC Initial Licensinq Examination Answer Key Choice                                         Basis or Justification Correct:         C   Reactor Coolant System Pressure Safety Limit has been violated. Tech Spec action must satisfy 2.1 and 6.7.1 Incorrect          A    States the NRC must be notified and meets 3.0.3 for LCO not met and 3.3.4 for ATWS Instrumentation but is not conservative enough to meet 2.1 and 6.7.1 Incorrect          B    Meets 3.3.1 for RPS Instrumentation but is not conservative enough to meet 2.1 and does not meet 6.7.1 Incorrect          D    This meets 3.4.2 for SRV's and 3.4.6.2 for Reactor Steam Dome Pressure, but is not conservative enough to meet 2.1 and does not meet 6.7.1 Level of    Difficulty  Time Allowance        PRA                RO                    SRO Knowledge                      (minutes)                        IOCFR55.41            10CFR55.43 High          3.5              5              N              (b) (8-10)              NIA Source:                    New Exam Item                              Previous NRC Exam Modified Bank Item                        Other Exam Bank ILT Exam Bank Reference(s):        LGS Tech Specs Learning              LLOTI540.05 0bjective:
~ - Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
KnowledgelAbility 295025                                            Importance:  RO I SRO KIA                  EKI .05                                                    4.41 4.7 Required Materials:
: 19. Unit 1 plant conditions are as follows: 0 Reactor Power is 8% 0 'W IRM is failed upscale  
Notes and Comments Prepared By:
&Q, \@(ob Reactor mode switch is in STARTUP " I D" An electrical fault results in the loss of 1AY160. WHICH ONE of the following identifies the impact on IRMs and status of RPS? A. IRM Channels A, C, E, and G lose power, Full Reactor Scram. B. ONLY IRM Channels A, and C, lose power, Full Reactor Scram.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
C. IRM Channels A, C, E, and G lose power, Reactor 1/2 Scram ONLY. D. ONLY IRM Channels A, and Cy lose power, Reactor 1/2 Scram ONLY. Page 38 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge High I Answer Kev Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 3 N (b) 7 N I Question ID# 0'19 Both RC Source: Reference(s):
 
Learning Objective:
                      ~             -
Correct: New Exam Item Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam Other Exam Bank E-1AY160, Step 1.2 and 1.22, AND GP-2, Caution before step 3.4.7 LLOT0250.07 Incorrect:
Limerick Generatinq Station                     ILT05-1 NRC Initial Licensinq Examination
Knowledge/Ability WA Incorrect:
: 19. Unit 1 plant conditions are as follows:
21 5003 Importance:
0   Reactor Power is 8%
RO / SRO K2.01 2.5 / 2.7 r--- Incorrect:
0   Reactor mode switch is in STARTUP
A B C D Basis or Justification ~ ~ IRM Channels A, C, E, and G loss power on a loss of 1AY160, Full Reactor Scram occurs due to mode switch in startup and RPS A side % scram loss of 1AY160 and RPS B side % scram (D IRM upscale) ONLY IRM Channels A, and C, loss power is incorrect as E & G channels also lose power, Full Reactor Scram is correct IRM Channels A, C, E, and G loss power is correct, Reactor 1/2 Scram is incorrect as full reactor scram will occur ONLY IRM Channels A, and C is incorrect as E & G channels also lose power, Reactor 1/2 Scram is incorrect as full reactor scram will occur Source Documentation Required Materials: Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generating Station lLT05-I NRC Initial Licensinq Examination
              'W IRM is failed upscale         &Q,     \@(ob
: 20. Unit 1 Plant conditions are as follows: 0 Reactor Startup is in progress 0 "1A and "I D" IRM's are on range 1 0 All other IRM's are on range 2 "1A SRM is being withdrawn when the count rate drops to 90 CPS. WHICH ONE of the following identifies the impact on the Reactor Manual Control System (RMCS)?
            " ID" An electrical fault results in the loss of 1AY160.
A. No rod blocks are enforced. B. Only a rod withdraw block is enforced.
WHICH ONE of the following identifies the impact on IRMs and status of RPS?
A. IRM Channels A, C, E, and G lose power, Full Reactor Scram.
B. ONLY IRM Channels A, and C, lose power, Full Reactor Scram.
C. IRM Channels A, C, E, and G lose power, Reactor 1/2 Scram ONLY.
D. ONLY IRM Channels A, and Cylose power, Reactor 1/2 Scram ONLY.
Page 38 of 200
 
Limerick Generating Station                         ILT05-1 NRC Initial Licensing Examination I                                                 Answer Kev I Question ID# 0'19 Both RC
                                  ~                    ~
Basis or Justification Correct:           A   IRM Channels A, C, E, and G loss power on a loss of 1AY160, Full Reactor Scram occurs due to mode switch in startup and RPS A side % scram loss of 1AY160 and RPS B side % scram (D IRM upscale)
Incorrect:          B    ONLY IRM Channels A, and C, loss power is incorrect as E & G channels also lose power, Full Reactor Scram is correct Incorrect:          C    IRM Channels A, C, E, and G loss power is correct, Reactor 1/2 Scram is r---
incorrect as full reactor scram will occur Incorrect:          D    ONLY IRM Channels A, and C is incorrect as E & G channels also lose power, Reactor 1/2 Scram is incorrect as full reactor scram will occur Level of      Difficulty  Time Allowance          PRA                  RO                    SRO Knowledge                      (minutes)                          10CFR55.41            10CFR55.43 High          3.0              3                N                (b) 7                    N Source Documentation Source:                  New Exam Item                            0Previous NRC Exam Modified Bank Item                            Other Exam Bank 0ILT Exam Bank Reference(s):        E-1AY160, Step 1.2 and 1.22, AND GP-2, Caution before step 3.4.7 Learning              LLOT0250.07 Objective:
Knowledge/Ability 215003                                              Importance:  RO / SRO WA                    K2.01                                                          2.5 / 2.7 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   lLT05-I NRC Initial Licensinq Examination
: 20. Unit 1 Plant conditions are as follows:
0 Reactor Startup is in progress 0   1 A and ID IRMs are on range 1 0 All other IRMs are on range 2 1 A SRM is being withdrawn when the count rate drops to 90 CPS.
WHICH ONE of the following identifies the impact on the Reactor Manual Control System (RMCS)?
A. No rod blocks are enforced.
B. Only a rod withdraw block is enforced.
C. Only a rod insert block is enforced.
C. Only a rod insert block is enforced.
D. Both rod insert and withdrawal rod blocks are enforced.
D. Both rod insert and withdrawal rod blocks are enforced.
Page 40 of 200 Limerick Generatinq Station ILT05-1 NRC initial Licensina Examination Choice Correct: B Incorrect A Incorrect C D Incorrect Answer Key Basis or Justification Only a rod withdraw blocks is enforced, is correct as all IRMs are not above range 2 and SRM CPS are less than 100 with detector not full in No rod blocks are enforced, is not correct.
Page 40 of 200
It would be correct if all IRMs were above range 2 Only a rod insert block is enforced.
 
This is not correct as SRM CPS less than 100 with detector not full in does not enforce an insert block Rod insert and withdrawal rod blocks are enforced SRM CPS are less than 100 with detector not full in Level of Difficulty Time Allowance PRA Low 3.5 4 N Knowledge (minutes)
Limerick Generatinq Station                         ILT05-1 NRC initial Licensina Examination Answer Key Choice                                            Basis or Justification Correct:          B    Only a rod withdraw blocks is enforced, is correct as all IRMs are not above range 2 and SRM CPS are less than 100 with detector not full in Incorrect          A    No rod blocks are enforced, is not correct. It would be correct if all IRMs were above range 2 Incorrect          C    Only a rod insert block is enforced. This is not correct as SRM CPS less than 100 with detector not full in does not enforce an insert block Incorrect          D    Rod insert and withdrawal rod blocks are enforced SRM CPS are less than 100 with detector not full in Level of     Difficulty   Time Allowance         PRA                   RO                    SRO Knowledge                     (minutes)                         10CFR55.41               10CFR55.43 Low          3.5              4                N                (b) ( 5 )                 N Source:                 Ix] New Exam Item                           0Previous NRC Exam Modified Bank Item                       0Other Exam Bank 0ILT Exam Bank Reference(s):        GP-2Appendix 1, step 3.3.7 and NOTE Learning              LLOT0240.06:
RO SRO 1 OCFR55.41 1 OCFR55.43 (b) (5) N Source: Reference(s):
0bjective:
Learning 0 bjective:
Knowledge/Ability 215004                                                Importance:   RO / SRO WA                    K5.03                                                           2.8 12.8 Required Materials:
Ix] New Exam Item Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank GP-2 Appendix 1, step 3.3.7 and NOTE LLOT0240.06:
Notes and Comments Prepared By:
Required Materials:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Knowledge/Ability WA Notes and Comments 21 5004 Importance:
 
RO / SRO K5.03 2.8 12.8 Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination 21. Unit 2 is at 100% power. #2 APRM output fails to 2%. WHICH ONE of the following completes the statement below? "The "2B" Rod Block Monitor channel 91 A. initiates a rod block B. automatically goes to Bypass mode C. automatically swaps to reference  
Limerick Generatinq Station                 ILT05-1 NRC Initial Licensing Examination
#3 APRM D. automatically swaps to reference  
: 21. Unit 2 is at 100% power.
##4 APRM Page 42 of 200 Limerick Generating Station ILT05-I NRC Initial Licensing Examination Correct: I Answer Key B The RBM sees less than 30% power from its reference APRM and Auto Bypasses I Choice I Basis or Justification Incorrect A Rod Block results an Upscale, Downscale, or hop condition.
      #2 APRM output fails to 2%.
Failure of the reference APRM will NOT cause a RBM hop or Downscale.
WHICH ONE of the following completes the statement below?
Incorrect Incorrect C The reference APRM would only swap if the primary APRM channel were INOP or Bypassed. This failure does not constitute these conditions. The alternate reference APRM for #2 is #4. ##4 APRM is the correct alternate, however, the reference APRM would only swap if the primary APRM channel were INOP or Bypassed.
91 The 2B Rod Block Monitor channel A. initiates a rod block B. automatically goes to Bypass mode C. automatically swaps to reference #3 APRM D. automatically swaps to reference ##4APRM Page 42 of 200
D I I I Level of Knowledge Low Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 lOCFR55.43 3.0 4 N (b) (2) N Source: Reference(s):
 
Learning 0 bject ive: KnowledgelAbility WA Required Materials: New Exam Item 0 Modified Bank Item ILT Exam Bank Previous NRC Exam Other Exam Bank ARC 108, A-5 . LLOT0280.09a 21 5005 Importance:
Limerick Generating Station                       ILT05-I NRC Initial Licensing Examination I                                               Answer Key I          Choice            I                            Basis or Justification Correct:          B     The RBM sees less than 30% power from its reference APRM and Auto Bypasses Incorrect         A     Rod Block results an Upscale, Downscale, or hop condition. Failure of the reference APRM will NOT cause a RBM hop or Downscale.
RO I SRO K1.03 3.4 13.5 Notes and Comments Prepared By: Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILTOS-I NRC Initial Licensing Examination
Incorrect         C     The reference APRM would only swap if the primary APRM channel were INOP or Bypassed. This failure does not constitute these conditions. The alternate reference APRM for #2 is #4.
: 22. The CRS has ordered a GP-4 shutdown as a result of the "1 E" SRV being stuck open.
Incorrect          D    ##4APRM is the correct alternate, however, the reference APRM would only swap if the primary APRM channel were INOP or Bypassed.
Following the performance of GP-4 actions plant conditions are as follows: 0 Reactor power is 28% 0 CRS has entered T-I 17 0 "IE" SRV is still open 0 Suppression Pool temperature is 112&deg;F and going up 0 T-270 is complete, injection has been terminated Reactor level is  
I                   I       I Level of     Difficulty Time Allowance         PRA               RO                   SRO Knowledge                      (minutes)                       10CFR55.41             10CFR55.43 Low          3.0               4               N               (b) (2)                 N Source:                 New Exam Item                               Previous NRC Exam 0Modified Bank Item                           Other Exam Bank ILT Exam Bank Reference(s):        ARC 108, A-5       .
-100" when reactor power is noted to be below 4%. WHICH ONE of the following describes the correct RPV water level band and the basis for this band? A. -60" to -100" in order to lower power by reducing core inlet subcooling.
Learning            LLOT0280.09a 0bjective:
B. -60" to -100" in order to lower power by reducing natural circulation driving load and core flow. C. -1 00" to -1 86" in order to lower power by reducing core inlet subcooling.
KnowledgelAbility 215005                                            Importance:   RO I SRO WA                  K1.03                                                         3.4 13.5 Required Materials:
D. -1 00" to -186" in order to lower power by reducing natural circulation driving head and core flow. Page 44 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination D Answer Key Conditions are set for level lowering to below TAF.
Notes and Comments Prepared By:
The bases for this level lowering is reduction of natural circulation driving head I Choice I Basis or Justification A Correct: This is the appropriate level band and reasons for the first level lowering.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
This is N/A once SP temp is I IO" and SRV is open B C Incorrect This level condition is not appropriate, the reason is associated with the -161 to -186 level band This level band is correct, the reason is associated with the higher level band Level of Difficulty Time Allowance Knowledge (minutes)
 
High 3.0 5 Incorrect PRA RO SRO 1 OCFR55.41 1 OCFR55.43 Y (b) (5) N Incorrect 295037 EK.2.09 Importance:
Limerick Generating Station                     ILTOS-I NRC Initial Licensing Examination
RO / SRO 4.0 / 4.2 I Source: L Reference s : Learning Objective:
: 22. The CRS has ordered a GP-4 shutdown as a result of the 1E SRV being stuck open.
I; Knowledge/Ability Source Documentation New Exam Item Modified Bank Item 17 ILT Exam Bank 0 Previous NRC Exam Other Exam Bank T-I 17, T-I 17 Bases, LQ-6 through LQ-11 and LQ-16.
Following the performance of GP-4 actions plant conditions are as follows:
LLOTI 560.05 (Description of K&A, from catalog)
0   Reactor power is 28%
Knowledge of the interrelations between SCRAM Condition Present and Reactor Power above APRM down SCL or unknown & the following  
0   CRS has entered T-I 17 0   IE SRV is still open 0   Suppression Pool temperature is 112&deg;F and going up 0   T-270 is complete, injection has been terminated Reactor level is -100 when reactor power is noted to be below 4%.
... Reactor Water Level Required Materials:
WHICH ONE of the following describes the correct RPV water level band and the basis for this band?
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
A. -60 to -100 in order to lower power by reducing core inlet subcooling.
- Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
B. -60 to -100 in order to lower power by reducing natural circulation driving load and core flow.
C. -1 00 to -1 86 in order to lower power by reducing core inlet subcooling.
D. -100 to -186 in order to lower power by reducing natural circulation driving head and core flow.
Page 44 of 200
 
Limerick Generating Station                         ILT05-1 NRC Initial Licensing Examination Answer Key I          Choice            I                              Basis or Justification Correct:          D    Conditions are set for level lowering to below TAF. The bases for this level lowering is reduction of natural circulation driving head Incorrect          A     This is the appropriate level band and reasons for the first level lowering.
This is N/A once SP temp is II O " and SRV is open Incorrect          B     This level condition is not appropriate, the reason is associated with the
                                -161 to -186 level band Incorrect          C    This level band is correct, the reason is associated with the higher level band Level of   Difficulty   Time Allowance         PRA                  RO                    SRO Knowledge                     (minutes)                         10CFR55.41              10CFR55.43 High         3.0               5                 Y               (b) (5)                   N Source Documentation I Source:                   New Exam Item                              0Previous NRC Exam LReference s :
Modified Bank Item 17 ILT Exam Bank T-I 17, T-I 17 Bases, LQ-6 through LQ-11 and LQ-16.
Other Exam Bank ILearning
            ;
Objective:
LLOTI 560.05 Knowledge/Ability 295037 EK.2.09 (Description of K&A, from catalog)
Importance: RO / SRO 4.0 / 4.2 Knowledge of the interrelations between SCRAM Condition Present and Reactor Power above APRM down SCL or unknown & the following...Reactor Water Level Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                      -
Limerick Generating Station                       ILT05-1 NRC Initial Licensinq Examination
: 23. Unit 2 is operating at 100% when a Turbine Trip occurs. Two minutes later the following conditions are noted:
: 23. Unit 2 is operating at 100% when a Turbine Trip occurs. Two minutes later the following conditions are noted:
Reactor Power is 0% 0 Rod 26-1 I is at position "48" 0 Rod 50-31 is at position "48" 0 Rod 22-51 is at position "48" 0 All other control rods are at "00" SLC is not running Subsequently, the RO begins to insert rods. WHICH ONE of the following describes control rod positions that meet the criteria for NO ATWS? A. Rods 26-1 I, 50-31, and 22-51 are at position "04". B. Rod 26-1 I and 50-31 are at position "02" and 22-51 is at position "04". C. Rods 26-1 1 and 50-31 are at position "00" and 22-51 is at position "48". D. Rod 26-1 1 is at position "00" and rods 50-31 and 22-51 are at position "4 8 " . Page 46 of 200 Limerick Generating Station lLTO5-I NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 4 Y (b) (IO) SRO I OCFR55.43 (b) (5) Source: Reference (s): Learning 0 bjective:
Reactor Power is 0%
New Exam Item 0 Modified Bank Item 0 ILT Exam Bank Previous NRC Exam 0 Other Exam Bank T-I 01, note 14, Tech Specs definition of Shutdown Margin LLOTI 560.03 Required Materials:
0   Rod 26-1 Iis at position 48 0   Rod 50-31 is at position 48 0   Rod 22-51 is at position 48 0   All other control rods are at 00 SLC is not running Subsequently, the RO begins to insert rods.
KnowledgeIAbility WA Notes and Comments 295037 Importance:
WHICH ONE of the following describes control rod positions that meet the criteria for NO ATWS?
RO I SRO EA 2.05 4.2 I 4.3 Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
A. Rods 26-1 I,   50-31, and 22-51 are at position 04.
~ Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
B. Rod 26-1 Iand 50-31 are at position 02 and 22-51 is at position 04.
: 24. A radiological accident has caused the following annunciators to alarm: NORTH STACK HI-HI RADIATION (003 El) NORTH STACK HI RADIATION (003 E2) WHICH ONE of the following areas is the location of the radiation release, and what is the required action to mitigate the release?
C. Rods 26-1 1 and 50-31 are at position 00 and 22-51 is at position 48.
A. Standby Gas Treatment Exhaust Enter and execute T-I 04 Radiological Release.
D. Rod 26-1 1 is at position 00 and rods 50-31 and 22-51 are at position 48 .
 
Page 46 of 200
 
Limerick Generating Station                       lLTO5-I NRC Initial Licensing Examination Level of     Difficulty   Time Allowance       PRA                 RO                   SRO Knowledge                     (minutes)                         10CFR55.41           IOCFR55.43 High         3.0             4               Y               (b) (IO)               (b) (5)
Source:                   New Exam Item                             Previous NRC Exam 0Modified Bank Item                       0Other Exam Bank 0ILT Exam Bank Reference(s):        T-I 01, note 14, Tech Specs definition of Shutdown Margin Learning              LLOTI560.03 0bjective:
KnowledgeIAbility 295037                                             Importance: RO I SRO WA                    EA 2.05                                                   4.2 I 4.3 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
~
Limerick Generatinq Station                   ILT05-1 NRC Initial Licensing Examination
: 24. A radiological accident has caused the following annunciators to alarm:
NORTH STACK HI-HI RADIATION (003 E l )
NORTH STACK HI RADIATION (003 E2)
WHICH ONE of the following areas is the location of the radiation release, and what is the required action to mitigate the release?
A. Standby Gas Treatment Exhaust Enter and execute T - I 04 Radiological Release.
B. Standby Gas Treatment Exhaust Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination.
B. Standby Gas Treatment Exhaust Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination.
C. Reactor Enclosure Equipment Compartment Exhaust Evacuate all unnecessary personnel per SE-24, Plant Evacuations.
C. Reactor Enclosure Equipment Compartment Exhaust Evacuate all unnecessary personnel per SE-24, Plant Evacuations.
D. Reactor Enclosure Equipment Compartment Exhaust Enter and execute T-I 03, Secondary Containment Control. Page 48 of 200 Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination Choice Correct: B Incorrect A Basis or Justification Possible source, ST must be performed and LGS Emergency Plan annex, Table 3-1 must be consulted Possible source but alarm alone is not sufficient reason to enter and execute T-I 04 ___~ I n correct C Not a possible source based on the given conditions, although the action is plausible given this source Incorrect Source Documentation D Not a possible source based on the given conditions, although the action is plausible given this source Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.5 4 N (b) (7) SRO 1 OCFR55.43 N Required Materials:
D. Reactor Enclosure Equipment Compartment Exhaust Enter and execute T - I 03, Secondary Containment Control.
Source: Reference(s)
Page 48 of 200
: Learning 0 bjective: Notes and Comments [XI New Exam Item 0 Modified Bank Item 0 ILT Exam Bank Previous NRC Exam Other Exam Bank ARC-MCR-003-EII ST-6-104-880-0, T-I 04 LLOT0720.03 Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author KnowledgelAbility KIA 295038 Importance:
 
RO I SRO EK2.03 3.6 13.8
Limerick Generatinq Station                         ILT05-I NRC Initial Licensinq Examination Choice                                         Basis or Justification Correct:         B     Possible source, ST must be performed and LGS Emergency Plan annex, Table 3-1 must be consulted Incorrect          A    Possible source but alarm alone is not sufficient reason to enter and execute T-I 04
.__ Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
_ _ _ ~
: 25. Given the following plant conditions: The Main Control Room has been abandoned due to a fire 0 Immediate actions of SE-I have been completed The Remote Shutdown Panel has been manned All Remote Shutdown Panel transfer switches have been placed in EM ERG EN CY Reactor pressure is 980 psig and rising slowly WHICH ONE of the following identifies the systems available for RPV level control? A. RClC controlled manually, ONLY. B. HPCl controlled manually, ONLY. C. RClC controlled manually with HPCI cycling in AUTO. D. HPCl controlled manually with RClC cycling in AUTO. Page 50 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 2.5 3 Y (b) (5) Answer Key SRO 1 OCFR55.43 N Question ID# 025 Both RC Source: Reference( s): Learning Objective:
Incorrect          C     Not a possible source based on the given conditions, although the action is plausible given this source Incorrect         D     Not a possible source based on the given conditions, although the action is plausible given this source Level of     Difficulty   Time Allowance         PRA                 RO                   SRO Knowledge                     (minutes)                         10CFR55.41             10CFR55.43 High         3.5             4                 N               (b) (7)                   N Source Documentation Source:                 [XI New Exam Item                               Previous NRC Exam 0Modified Bank Item                             Other Exam Bank 0 ILT Exam Bank Reference(s):        ARC-MCR-003-EII ST-6-104-880-0, T-I 04 Learning              LLOT0720.03 0bjective:
Choice New Exam Item c] Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam Other Exam Bank SE-1 step4.3 LLOT0735.02, .03 Correct: Incorrect Incorrect Incorrect C A B D $Fa Basis or Justification RClC is the primary means of level control from the Remote Shutdown Panel, but must be started up and shutdown manually. HPCl will cycle in AUTO as long as it has not been disabled.
KnowledgelAbility 295038                                               Importance: RO I SRO KIA                  EK2.03                                                         3.6 13.8 Required Materials:
RClC manual control is available, but HPCl will cycle in AUTO as long as it has not been disabled.
Notes and Comments Prepared By:
HPCl manual control is not available from the RSP. It can either be allowed to cycle in AUTO, or completely disabled from the RSP. __~ __~ __ ~~ HPCl will cycle in AUTO as long as it has not been disabled. RClC must be started up and shutdown manually.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Knowledge/Ability WA 29501 6 AK2.01 Importance: RO I SRO 4.4 / 4.5 (Description of K&A, from catalog)
 
Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and.. .Remote Shutdown Panel Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
                        .__
__ Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
Limerick Generating Station                   ILT05-1 NRC Initial Licensinq Examination
: 26. Unit 2 Plant conditions are as follows: 0 0 Reactor is scrammed 0 Main Turbine is tripped 0 Turbine speed is 100 RPM and slowly coasting down 0 Sealing Steam header pressure is 0 psig Main Condenser vacuum is 20" and dropping The CRS orders the PRO to break Main Condenser vacuum.
: 25. Given the following plant conditions:
Per OT-I 16 Bases, WHICH ONE of the following describes the reason for this action? A. Rapidly reduce turbine speed to prevent damage due to windage.
The Main Control Room has been abandoned due to a fire 0   Immediate actions of SE-I have been completed The Remote Shutdown Panel has been manned All Remote Shutdown Panel transfer switches have been placed in EMERGENCY Reactor pressure is 980 psig and rising slowly WHICH ONE of the following identifies the systems available for RPV level control?
A. RClC controlled manually, ONLY.
B. HPCl controlled manually, ONLY.
C. RClC controlled manually with HPCI cycling in AUTO.
D. HPCl controlled manually with RClC cycling in AUTO.
Page 50 of 200
 
Limerick Generating Station                       ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 025 Both RC   $Fa Choice                                          Basis or Justification Correct:          C    RClC is the primary means of level control from the Remote Shutdown Panel, but must be started up and shutdown manually. HPCl will cycle in AUTO as long as it has not been disabled.
Incorrect          A    RClC manual control is available, but HPCl will cycle in AUTO as long as it has not been disabled.
Incorrect          B    HPCl manual control is not available from the RSP. It can either be allowed to cycle in AUTO, or completely disabled from the RSP.
_    _  ~_  _ ~     __     ~~
Incorrect          D    HPCl will cycle in AUTO as long as it has not been disabled. RClC must be started up and shutdown manually.
Level of    Difficulty  Time Allowance        PRA                  RO                    SRO Knowledge                    (minutes)                          10CFR55.41            10CFR55.43 Low          2.5              3              Y                  (b) (5)                  N Source:                  New Exam Item                              0Previous NRC Exam c]Modified Bank Item                            Other Exam Bank 0ILT Exam Bank Reference(s):        SE-1 step4.3 Learning              LLOT0735.02, .03 Objective:
Knowledge/Ability 295016                                              Importance: RO I SRO WA                    AK2.01                                                        4.4 / 4.5 (Description of K&A, from catalog)
Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and.. .Remote Shutdown Panel Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
__
Limerick Generating Station                   ILT05-1 NRC Initial Licensing Examination
: 26. Unit 2 Plant conditions are as follows:
0 Main Condenser vacuum is 20 and dropping 0 Reactor is scrammed 0 Main Turbine is tripped 0 Turbine speed is 100 RPM and slowly coasting down 0 Sealing Steam header pressure is 0 psig The CRS orders the PRO to break Main Condenser vacuum.
Per OT-I 16 Bases, WHICH ONE of the following describes the reason for this action?
A. Rapidly reduce turbine speed to prevent damage due to windage.
B. Reduce differential pressure across turbine seals to prevent turbine exhaust hood over-pressurization.
B. Reduce differential pressure across turbine seals to prevent turbine exhaust hood over-pressurization.
C. Rapidly reduce turbine speed to prevent damage due to uneven rotor heating. D. Reduce differential pressure across turbine seals to prevent drawing cold air across the hot rotor. Page 52 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.5 4 Y (b) (7) Answer Key SRO 1 OCFR55.43 N Question ID# 026 Both R( Source: Reference( s) : Learning Objective:
C. Rapidly reduce turbine speed to prevent damage due to uneven rotor heating.
Choice New Exam Item 0 Modified Bank Item 0 ILT Exam Bank OT-I 16 BASES, step 3.3 LLOTI 540.05 0 Previous NRC Exam 0 Other Exam Bank Correct: Knowledge/Ability WA Incorrect 295002 Importance:
D. Reduce differential pressure across turbine seals to prevent drawing cold air across the hot rotor.
RO / SRO AK2.11 2.6 12.7 Incorrect Incorrect D A B C gij" Basis or Justification With no sealing steam pressure, main condenser vacuum will draw cold air across the seals and the hot turbine rotor Preventing windage damage is the reason why vacuum should not be broken greater than 1200 RPM Preventing Turbine exhaust hood over-pressurization is the reason for tripping the Main Turbine at 21.5" VAC Uneven rotor heating is a problem if sealing steam is applied to a stationary turbine rotor Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Page 52 of 200
__ Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination
 
: 27. A reactor startup is in progress on Unit 2. Reactor Power is 3%. 0 A Reactor Scram is attempted 0 Ten control rods remain at position "04" to "48" WHICH ONE of the following describes the required operator action?
Limerick Generating Station                       ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 026 Both R(   gij" Choice                                        Basis or Justification Correct:           D    With no sealing steam pressure, main condenser vacuum will draw cold air across the seals and the hot turbine rotor Incorrect         A    Preventing windage damage is the reason why vacuum should not be broken greater than 1200 RPM Incorrect         B   Preventing Turbine exhaust hood over-pressurization is the reason for tripping the Main Turbine at 21.5" VAC Incorrect          C    Uneven rotor heating is a problem if sealing steam is applied to a stationary turbine rotor Level of    Difficulty  Time Allowance        PRA                RO                    SRO Knowledge                      (minutes)                         10CFR55.41            10CFR55.43 Low          3.5              4              Y                (b) (7)                  N Source:                  New Exam Item                            0Previous NRC Exam 0Modified Bank Item                        0Other Exam Bank 0ILT Exam Bank Reference(s) :        OT-I 16 BASES, step 3.3 Learning              LLOTI 540.05 Objective:
A. Enter T-100, bypass RWM and insert control rods with S73.0.D. B. Enter T-100, insert control rods with T-213. C. Enter T-101, bypass RWM and insert control rods with S73.0.D. D. Enter T-I 01, insert control rods with T-213.
Knowledge/Ability 295002                                            Importance:  RO / SRO WA                    AK2.11                                                      2.6 12.7 Required Materials:
Page 54 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Difficulty Time Allowance PRA RO (minutes) 10CFR55.41 I Answer Key SRO 1 OCFR55.43 Choice 3.0 Correct: 3 N N 1 A Reference@):
Notes and Comments Prepared By:
Learning 0 bjective:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Knowledge/Ability WA Incorrect 0 Modified Bank Item ILT Exam Bank T-100 Bases step RC/Q-3 LLOTI 540.02 Other Exam Bank 29501 5 Importance:
 
RO / SRO AA2.01 4.1 / 4.3 B Incorrect C ID Incorrect Basis or Justification As Reactor power is below 4% entry into T-I 00 is appropriate, Bypass RWM and Insert Control Rods with S73.0.D is directed T-213 is not directed in T-I00 As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate and T-213 is not directed in T-I 00 Level of Knowledge Source Documentation Source: I [E3 New Exam Item 0 Previous NRC Exam Required Materials:
Limerick Generating Station                      ILTO5-1 NRC Initial Licensing Examination
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination
: 27. A reactor startup is in progress on Unit 2.
: 28. Unit I plant conditions are as follows: Reactor power is 100% Drywell cooling is maximized An inadvertent Group VlllA isolation occurs. WHICH ONE of the following describes the status of Drywell Chilled Water service to the Drywell and Recirc Pump cooling water one minute later? Drywell Chilled Water Recirc Pump Coolinq Water A. In Service In Service B. In Service Isolated C. Isolated In Service D. Isolated Isolated Page 56 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Difficulty Time Allowance PRA RO (minutes)
Reactor Power is 3%.
I OCFR55.41 Answer Key SRO 10CFR55.43 I Question ID# 028 Both RC Low 2.5 2 N Correct: Incorrect (b) (8, 9, 10) N Incorrect I------ Source: Reference(s):
0  A Reactor Scram is attempted 0 Ten control rods remain at position 04 to 48 WHICH ONE of the following describes the required operator action?
Learning 0 bjective:
A. Enter T-100, bypass RWM and insert control rods with S73.0.D.
1 Incorrect New Exam Item 0 Modified Bank Item 0 ILT Exam Bank GP-8.1 for Group VlllA LLOT0180.05 Previous NRC Exam 0 Other Exam Bank D Knowledge/Ability WA A 295020 Importance:
B. Enter T-100, insert control rods with T-213.
RO / SRO AKI .05 3.3 13.6 B C $*W Basis or Justification An inadvertent VlllA isolation would result in both DWCW and Recirc Pump cooling water isolating Both will isolate DWCW will also isolate Recirc Pump cooling water will also isolate Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
C. Enter T-101, bypass RWM and insert control rods with S73.0.D.
: 29. Unit 1 plant conditions are as follows: 0 Reactor power is 100% 0 Hydrogen Water Chemistry is not in service The following annunciators are received:
D. Enter T - I 01, insert control rods with T-213.
0 0 MAIN STEAM LINE DIV 1 RAD MONITOR HVDOWNSCALE (109 FI) MAIN STEAM LINE DIV 2 RAD MONITOR HVDOWNSCALE (I09 F2) Subsequently the following annunciator is received: MAIN STEAM LINE HIGH HIGH RADIATION (107 11) WHICH ONE of the following describes the procedure(s), which must be entered for valid alarms, and the required operator action(s)?
Page 54 of 200
A. Enter ON-I 02 ONLY; reduce reactor power in accordance with GP-5, Appendix 2. B. Enter T-103 ONLY; perform a GP-3 Normal Plant Shutdown.
 
C. Enter ON-I02 and T-103; p.erform a rapid plant shutdown and close the MSIV's. D. Enter ON-I02 and T-103; perform a rapid plant shutdown and Emergency Blowdown per T-I 12. Page 58 of 200 Limerick Generating Station ILT05-I NRC Initial Licensing Examination C A B D I Answer Key ~~ Main steam line high rad requires entry into ON-102 and 1-103. The high- high rad alarm indicates three times NFPB. Per T-I03 this requires a rapid plant shutdown and closure of the MSIV's While reducing power is an immediate action per ON-102, question conditions also require entry into T-103 and the actions described in "C" above ON-I02 entry is also required and a GP-3 shutdown would be appropriate per T-103 if 2 or more areas exceeded MSO rad level, but is not adequate for the stated conditions An emergency blow-down would be appropriate per T-I 03 if two or more areas exceeded MSO and a primary system was discharging into the Reactor Enclosure. but is not reauired for MSL Hiah-Hiah Rad onlv Choice Correct: Difficulty Time Allowance PRA RO (minutes) 1 OCFR55.41 High 4.0 5 Y Y (b)(10) Incorrect SRO 1 OCFR55.43 y (b)(2) Incorrect 295033 (32.4.4 Incorrect Importance:
Limerick Generating Station                          ILT05-1 NRC Initial Licensinq Examination Answer Key Choice                                            Basis or Justification Correct:          A      As Reactor power is below 4% entry into T-I 00 is appropriate, Bypass RWM and Insert Control Rods with S73.0.D is directed Incorrect          B      T-213 is not directed in T-I00 Incorrect          C      As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate Incorrect I D        As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate and T-213 is not directed in T-I 00 Level of     Difficulty    Time Allowance        PRA                RO                    SRO Knowledge                      (minutes)                          10CFR55.41            10CFR55.43 I
RO I SRO 4.0 14.3 I Basis or Justification Source: Reference(s):
3.0                3                N                                        N          1 Source Documentation Source:              I   [E3 New Exam Item                            0Previous NRC Exam 0Modified Bank Item                            Other Exam Bank ILT Exam Bank Reference@):          T-100 Bases step RC/Q-3 Learning              LLOTI 540.02 0bjective:
Learning Objective: Source Documentation New Exam Item 0 Modified Bank Item ILT Exam Bank 0 Previous NRC Exam [7 Other Exam Bank ARC-MCR-109-F1, ARC-MCR-109-F2, ARC-MCR-107-11, ON-I 02 Step 1.2, T-I 03 LLOTI 560.02, LLOT1550.01 KnowledgelAbility WA (Description of K&A, from catalog) High Secondary Containment Radiation Levels: Ability to recognize abnormal indications for system operating parameters which are entry level conditions for emergency and abnormal operating procedures. Required Materials:
Knowledge/Ability 295015                                              Importance: RO / SRO WA                    AA2.01                                                        4.1 / 4.3 Required Materials:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
Notes and Comments Prepared By:
: 30. Plant conditions are as follows: 0 A LOCA is in progress 0 Drywell Hydrogen is 3% 0 Drywell Oxygen is 8% 0 Suppression Pool Hydrogen is 7% Suppression Pool Oxygen is 4% WHICH ONE of the following identifies the flowpath for combustible gas monitoring and control?
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
A. DW/G-3 and SP/G-I B. DW/G-2 and SP/G-2 C. DW/G-3 and SP/G-3 D. DW/G-2 and SPIG-1 Page 60 of 200 Limerick Generatinlq Station ILT05-1 NRC Initial Licensing Examination Difficulty Time Allowance PRA RO (minutes) 1 OCFR55.41 High 3.5 4 Y Y (b)(lO) Answer Key SRO 1 OCFR55.43 Y (b)(5) Question ID# 030 'Both RC Source: Reference(s):
 
Learning Objective:
Limerick Generatinq Station                  ILT05-I NRC Initial Licensing Examination
I Choice New Exam Item Modified Bank Item ILT Exam Bank Previous NRC Exam 0 Other Exam Bank - Modified LOR Exam bank item T-102, sheet 2 and T-102 Bases Step PC/G-5 LLOTI 560.06 I Correct: Knowledge/Ability K/A 1 Incorrect 500000 Importance:
: 28. Unit Iplant conditions are as follows:
RO / SRO EA 2.03 3.3 / 3.8 Incorrect Incorrect I A B C D Basis or Justification Applying the containment H2 and 02 levels to the tables, PC/G-1 and PC/G-2 in T-102, sh. 2, results in the use of flowpaths DW/G-3 and SP/G-1 Neither of these flowpaths are correct per PC/G-1 and PC/G-2, T-102, sh. 2 The drywell flowpath is correct; the suppression pool flowpath is not, per PC/G-1 and PC/G-2, T-102, sh.
Reactor power is 100%
: 2. The suppression pool flowpath is correct; the drywell flowpath is not, per PC/G-1 and PUG-2, T-102, sh.
Drywell cooling is maximized An inadvertent Group VlllA isolation occurs.
: 2. Required Materials:
WHICH ONE of the following describes the status of Drywell Chilled Water service to the Drywell and Recirc Pump cooling water one minute later?
T-I02 sht. 2 Notes and Comments Prepared By: Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
Drywell Chilled Water        Recirc Pump Coolinq Water A.       In Service                    In Service B.      In Service                      Isolated C.       Isolated                      In Service D.       Isolated                      Isolated Page 56 of 200
: 31. A steam leak in the Unit 2 RCIC room resulted in a scram and Emergency Blowdown per T-I 12. Conditions are as follows: 0 Reactor pressure is 90 psig and dropping 0 Reactor level is
 
-30" and dropping 0 Drywell pressure is 1.2 psig and steady The PRO has been directed to maintain RPV level with low pressure ECCS. WHICH ONE of the following actions will result in injecting to the RPV with low pressure ECCS? (No other operator actions are taken) A. Arm and depress the Core Spray Div. I Manual Initiation Pushbutton.
Limerick Generating Station                        ILT05-1 NRC Initial Licensing Examination Answer Key I Question ID# 028 Both RC $*W Basis or Justification Correct:          D    An inadvertent VlllA isolation would result in both DWCW and Recirc Pump cooling water isolating Incorrect          A    Both will isolate I------
B. Start the "2A Core Spray Pump and take the HV-52-2F005A, Inboard Injection Valve, to OPEN. C. Arm and depress the Core Spray Div. 3 Manual Initiation Pushbutton.
1 Incorrect Incorrect B
D. Start the "2C" RHR Pump, HV-51-2F017C LPCI, Injection Valve, will OPEN automatically.
C DWCW will also isolate Recirc Pump cooling water will also isolate Difficulty  Time Allowance        PRA                  RO                  SRO (minutes)                         IOCFR55.41            10CFR55.43 Low          2.5              2                N            (b) (8, 9, 10)              N Source:                  New Exam Item                              Previous NRC Exam 0Modified Bank Item                        0Other Exam Bank 0ILT Exam Bank Reference(s):       GP-8.1 for Group VlllA Learning            LLOT0180.05 0bjective:
Page 62 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Difficulty Time Allowance (minutes)
Knowledge/Ability 295020                                            Importance: RO / SRO WA                  AKI .05                                                      3.3 13.6 Required Materials:
High 3.5 4 Answer Key PRA RO SRO I OCFR55.41 1 OCFR55.43 Y Y (b)(7) N Question ID# 031 Both RC Source: Reference(s):
Notes and Comments Prepared By:
Learning Objective:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
I Choice New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 17 Other Exam Bank S52.7A, note above step 4,4 LLOT0350.
 
IO Correct: Knowledge/Ability K/A Incorrect 209001 Importance:
Limerick Generating Station                    ILT05-1 NRC Initial Licensinq Examination
RO'/ SRO PWG 2.1.30 3.9 13.4 I incorrect L I Incorrect A B C D Basis or Justification I Div 1 Manual Initiation Pushbutton will provide a Div 1 LOCA Signal, Start the "1A pump and open the injection valves as long as the Reactor low pressure permissive is met. The HV-52-2F005 will not open unless there is a LOCA signal present Div 3 Manual Initiation Pushbutton will start the "IC' Core Spray Pump, but it will not make up the open logic for the injection valves. Only the Div l(2) Pushbuttons will do that The HV-51-2F017C will not open automatically unless there is a LOCA signal present. Required Materials: Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author 
: 29. Unit 1 plant conditions are as follows:
~~ Limerick Generating Station ILTO5-1 NRC Initial Licensinq Examination
0  Reactor power is 100%
: 32. Unit 2 plant conditions are as follows: 0 Reactor power is 100% 0 Division 3 Safeguard 125Vf+%WDC is inoperable due to maintenance on the battery charger e&& 43(ob An inadvertent Group I isolation causes a reactor scram.
0  Hydrogen Water Chemistry is not in service The following annunciators are received:
Unit 2 RClC starts on low reactor level A steam leak develops in the RClC room. RClC room temperature reaches 21 0&deg;F WHICH ONE of the following operator actions places the RClC system in the configuration required by current plant conditions?
0  MAIN STEAM LINE DIV 1 RAD MONITOR HVDOWNSCALE (109 F I )
A. Trip the RClC Turbine. B. Depress the RClC Manual Isolation Pushbutton.
0  MAIN STEAM LINE DIV 2 RAD MONITOR HVDOWNSCALE (I09 F2)
C. Take the handswitch for the HV-49-2F007, RClC Steam Line Inboard Isolation to CLOSE. D. Take the handswitch for the HV-49-2FOO8, RClC Steam Line Outboard I sol ation to CLOSE. Page 64 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Correct: Answer Key C Question ID# 032 Both RC Incorrect Choice A Difficulty Time Allowance PRA RO 1 OCFR55.41 (minutes)
Subsequently the following annunciator is received:
High 3.0 4 Y Y (b)(5) SRO 1 OCFR55.43 N lB Incorrect Source: Reference(s):
MAIN STEAM LINE HIGH HIGH RADIATION (107 11)
Learning 0 bject ive
WHICH ONE of the following describes the procedure(s), which must be entered for valid alarms, and the required operator action(s)?
: Incorrect 0 [xi New Exam Item 0 Modified Bank Item ILT Exam Bank c] Previous NRC Exam c] Other Exam Bank E-2FC, GE DWG M-1-E51-1040-E-028, Sht.1 LLOT0380.05, LLOT0380.12 Basis or Justification With a loss of Div 3 DC, the 2F007 will fail to isolate on High RClC room temperature (205OF) and must be closed WA I A205 The RClC Turbine will trip on a Div 1 NS4 isolation signal on High RClC Room temperature Manual isolation will not close 2F007 valve due to loss of Div 3 DC 3.3 13.3 ~ ~ The 2F008 will close on a Div I NS4 Isolation signal on High RClC Room temperature Knowledge/Ability 1 217000 I Importance:
A. Enter ON-I 02 ONLY; reduce reactor power in accordance with GP-5, Appendix 2.
RO / SRO Required Materials:
B. Enter T-103 ONLY; perform a GP-3 Normal Plant Shutdown.
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station lLTO5-1 NRC Initial Licensinq Examination
C. Enter ON-I02 and T-103; p.erform a rapid plant shutdown and close the MSIVs.
: 33. Unit 1 plant conditions are as follows: 0 Reactor water level is 35" 0 "1 B" RHR is in Suppression Pool cooling Div 2 Safeguard DC Bus is subsequently deenergized.
D. Enter ON-I02 and T-103; perform a rapid plant shutdown and Emergency Blowdown per T-I 12.
WHICH ONE of the following describes the effect, if any, on "1 B" RHR Loop if Reactor Water level lowers to -140"? A. "IB" RHR loop will realign to the LPCl mode. B. "IB" RHR pump will load shed and remain shutdown.
Page 58 of 200
C. "1 B" RHR loop will remain in Suppression Pool cooling. D. "1 B" RHR pump will continue to run; minimum flow valve will open. Page 66 of 200 Limerick Generating Station ILT05-1 NRC Initial LicensinQ Examination Incorrect: Answer Kev A Choice High Correct: 1 c Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 1 OCFR55.43 3.0 4 Y Y (b)(7) N Source: Reference( s): Learning 0 bjective:
 
IB Incorrect:
Limerick Generating Station                        ILT05-I  NRC Initial Licensing Examination I                                                Answer Key Choice            I                ~~
0 New Exam Item Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank E-IFB U/1, GE DWG. M-1-Ell-1040-E-039 SH.l LLOT0370.3e Incorrect:
Basis or Justification Correct:          C    Main steam line high rad requires entry into ON-102 and 1-103. The high-high rad alarm indicates three times NFPB. Per T-I03 this requires a rapid plant shutdown and closure of the MSIVs Incorrect          A    While reducing power is an immediate action per ON-102, question conditions also require entry into T-103 and the actions described in C above Incorrect         B    ON-I02 entry is also required and a GP-3 shutdown would be appropriate per T-103 if 2 or more areas exceeded MSO rad level, but is not adequate for the stated conditions Incorrect         D    An emergency blow-down would be appropriate per T-I 03 if two or more areas exceeded MSO and a primary system was discharging into the Reactor Enclosure. but is not reauired for MSL Hiah-Hiah Rad onlv Difficulty  Time Allowance          PRA                RO                    SRO (minutes)                          10CFR55.41            10CFR55.43 High          4.0              5                Y              Y (b)(10)              y (b)(2)
I D Knowledge/Ability KIA ?BE? Basis or Justification 203000 Importance:
Source Documentation Source:                  New Exam Item                             0Previous NRC Exam 0Modified Bank Item                         [7 Other Exam Bank ILT Exam Bank Reference(s):        ARC-MCR-109-F1, ARC-MCR-109-F2, ARC-MCR-107-11, ON-I 02 Step 1.2, T-I 03 Learning            LLOTI560.02, LLOT1550.01 Objective:
RO / SRO K6.02 2.8 / 3.0 RHR will remain in suppression pool cooling as F024 (SP cooling valve (and F017B (LPCI Inject valve) will not reposition during the LOCA due to the Loss of Div 2 DC F024 and F017B will not reposition due to loss of Div 2 DC RHR pump will not load shed during a LOCA Min flow valve will not open Required Materials:
KnowledgelAbility 295033                                              Importance: RO I SRO WA                   (32.4.4                                                        4.0 14.3 (Description of K&A, from catalog) High Secondary Containment Radiation Levels: Ability to recognize abnormal indications for system operating parameters which are entry level conditions for emergency and abnormal operating procedures.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generatinq Station                   ILT05-1 NRC Initial Licensing Examination
: 30. Plant conditions are as follows:
0   A LOCA is in progress 0   Drywell Hydrogen is 3%
0   Drywell Oxygen is 8%
0   Suppression Pool Hydrogen is 7%
Suppression Pool Oxygen is 4%
WHICH ONE of the following identifies the flowpath for combustible gas monitoring and control?
A. DW/G-3 and SP/G-I B. DW/G-2 and SP/G-2 C. DW/G-3 and SP/G-3 D. DW/G-2 and SPIG-1 Page 60 of 200
 
Limerick Generatinlq Station                         ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 030 Both RC I         Choice                                           Basis or Justification I    Correct:                Applying the containment H2and 0 2 levels to the tables, PC/G-1 and PC/G-A    2 in T-102, sh. 2, results in the use of flowpaths DW/G-3 and SP/G-1 1     Incorrect         B    Neither of these flowpaths are correct per PC/G-1 and PC/G-2, T-102, sh. 2 Incorrect          C    The drywell flowpath is correct; the suppression pool flowpath is not, per PC/G-1 and PC/G-2, T-102, sh. 2.
I Incorrect          D    The suppression pool flowpath is correct; the drywell flowpath is not, per PC/G-1 and PUG-2, T-102, sh. 2.
Difficulty  Time Allowance          PRA                  RO                    SRO (minutes)                           10CFR55.41              10CFR55.43 High          3.5              4                Y                Y (b)(lO)                Y (b)(5)
Source:                  New Exam Item                                  Previous NRC Exam Modified Bank Item                          0Other Exam Bank - Modified LOR ILT Exam Bank                                  Exam bank item Reference(s):       T-102, sheet 2 and T-102 Bases Step PC/G-5 Learning            LLOTI560.06 Objective:
Knowledge/Ability 500000                                              Importance:  RO / SRO K/A                  EA 2.03                                                        3.3 / 3.8 Required Materials:
T-I02 sht. 2 Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                  ILT05-1 NRC Initial Licensinq Examination
: 31. A steam leak in the Unit 2 RCIC room resulted in a scram and Emergency Blowdown per T-I 12.
Conditions are as follows:
0  Reactor pressure is 90 psig and dropping 0  Reactor level is -30 and dropping 0  Drywell pressure is 1.2 psig and steady The PRO has been directed to maintain RPV level with low pressure ECCS.
WHICH ONE of the following actions will result in injecting to the RPV with low pressure ECCS? (No other operator actions are taken)
A. Arm and depress the Core Spray Div. IManual Initiation Pushbutton.
B. Start the  2 A Core Spray Pump and take the HV-52-2F005A, Inboard Injection Valve, to OPEN.
C. Arm and depress the Core Spray Div. 3 Manual Initiation Pushbutton.
D. Start the 2C RHR Pump, HV-51-2F017C LPCI, Injection Valve, will OPEN automatically.
Page 62 of 200
 
Limerick Generating Station                        ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 031 Both RC I         Choice                                          Basis or Justification                           I Correct:          A    Div 1 Manual Initiation Pushbutton will provide a Div 1 LOCA Signal, Start the 1 A pump and open the injection valves as long as the Reactor low pressure permissive is met.
Incorrect          B    The HV-52-2F005 will not open unless there is a LOCA signal present I    incorrect          C    Div 3 Manual Initiation Pushbutton will start the I C  Core Spray Pump, but it will not make up the open logic for the injection valves. Only the Div l(2)
L I    Incorrect          D Pushbuttons will do that The HV-51-2F017C will not open automatically unless there is a LOCA signal present.
Difficulty  Time Allowance          PRA                RO                        SRO (minutes)                         IOCFR55.41                10CFR55.43 High          3.5                4              Y                Y (b)(7)                    N Source:                  New Exam Item                            0Previous NRC Exam 0Modified Bank Item                        17Other Exam Bank 0ILT Exam Bank Reference(s):       S52.7A, note above step 4,4 Learning            LLOT0350.I O Objective:
Knowledge/Ability 209001                                            Importance:       RO/ SRO K/A                  PWG 2.1.30                                                        3.9 13.4 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                                                                  ~~
Limerick Generating Station                    ILTO5-1 NRC Initial Licensinq Examination
: 32. Unit 2 plant conditions are as follows:
0  Reactor power is 100%
0  Division 3 Safeguard 1 2 5 V f + % W D C is inoperable due to maintenance on the battery charger          e&&      43(ob An inadvertent Group Iisolation causes a reactor scram.
Unit 2 RClC starts on low reactor level A steam leak develops in the RClC room. RClC room temperature reaches 210&deg;F WHICH ONE of the following operator actions places the RClC system in the configuration required by current plant conditions?
A. Trip the RClC Turbine.
B. Depress the RClC Manual Isolation Pushbutton.
C. Take the handswitch for the HV-49-2F007, RClC Steam Line Inboard Isolation to CLOSE.
D. Take the handswitch for the HV-49-2FOO8, RClC Steam Line Outboard Isolation to CLOSE.
Page 64 of 200
 
Limerick Generating Station                          ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 032 Both RC Choice                                            Basis or Justification Correct:          C      With a loss of Div 3 DC, the 2F007 will fail to isolate on High RClC room temperature (205OF)and must be closed Incorrect          A      The RClC Turbine will trip on a Div 1 NS4 isolation signal on High RClC Room temperature Incorrect l B        Manual isolation will not close 2F007 valve due to loss of Div 3 DC 0
                                  ~       ~
Incorrect                The 2F008 will close on a Div INS4 Isolation signal on High RClC Room temperature Difficulty    Time Allowance          PRA                RO                     SRO (minutes)                         10CFR55.41                10CFR55.43 High          3.0               4                Y              Y (b)(5)                    N Source:                [xi New Exam Item                            c]Previous NRC Exam 0Modified Bank Item                          c]Other Exam Bank ILT Exam Bank Reference(s):          E-2FC, GE DWG M-1-E51-1040-E-028, Sht.1 Learning              LLOT0380.05, LLOT0380.12 0bjective:
1 Knowledge/Ability 217000                                              I Importance:    RO / SRO WA                  I A205                                                            3.3 13.3 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generatinq Station                      lLTO5-1 NRC Initial Licensinq Examination
: 33. Unit 1 plant conditions are as follows:
0  Reactor water level is 35 0   1B RHR is in Suppression Pool cooling Div 2 Safeguard DC Bus is subsequently deenergized.
WHICH ONE of the following describes the effect, if any, on 1B RHR Loop if Reactor Water level lowers to -140?
A. I B  RHR loop will realign to the LPCl mode.
B. I B  RHR pump will load shed and remain shutdown.
C. 1 B RHR loop will remain in Suppression Pool cooling.
D. 1 B RHR pump will continue to run; minimum flow valve will open.
Page 66 of 200
 
Limerick Generating Station                        ILT05-1 NRC Initial LicensinQExamination Answer Kev
                              ?BE?
Choice                                          Basis or Justification Correct:      1  c    RHR will remain in suppression pool cooling as F024 (SP cooling valve (and F017B (LPCI Inject valve) will not reposition during the LOCA due to the Loss of Div 2 DC Incorrect:          A    F024 and F017B will not reposition due to loss of Div 2 DC Incorrect:
IB      RHR pump will not load shed during a LOCA Incorrect:      I  D    Min flow valve will not open Difficulty  Time Allowance          PRA                RO                      SRO (minutes)                        10CFR55.41              10CFR55.43 High          3.0              4                Y              Y (b)(7)                  N Source:                  0New Exam Item                              0Previous NRC Exam Modified Bank Item                      0Other Exam Bank 0ILT Exam Bank Reference(s):          E-IFB U/1, GE DWG. M-1-Ell-1040-E-039 SH.l Learning              LLOT0370.3e 0bjective:
Knowledge/Ability 203000                                              Importance: RO / SRO KIA                    K6.02                                                        2.8 / 3.0 Required Materials:
Notes and Comments:
Existing bank question, Stem and Distractors Modified Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generatina Station                    ILT05-1 NRC Initial Licensing Examination
: 34. Unit 1 plant conditions are as follows:
0  OPCON4 0    I A  RHR is in shutdown cooling Reactor water level drops from +70 to -1 0.
WHICH ONE of the following identifies current RHR pump and valve status?
HV-51-1F006A                HV-51-1FOO9 Shutdown Cooling          Shutdown Cooling 1 A RHR Pump            Suction Valve            Isolation valve A.                Running                  Open                      Open B.                Running                  Open                      Closed C.                Tripped                Closed                      Open D.                Tripped                  Open                      Closed Page 68 of 200
 
Limerick Generating Station                          ILT05-1 NRC Initial Licensing Examination I                                                Answer Key I                              Basis or Justification Correct:          D    When level decreases to below + I 2.5 Shutdown Cooling will isolate FOO9, which in turn trips the ARHR pump, F006 remains open as there is no auto closure A    Incorrect as FOO9 will close with level below +125 and pump will trip Incorrect                Incorrect as pump will trip when level drops below 12.5 due to FOO9 closure I    Incorrect          C    Incorrect as F006A will not automatically close and FOO9 y level drops below +I  25 Ji close when Level of    Difficulty  Time Allowance          PRA                RO                  SRO Knowledge                      (minutes)                          10CFR55.41            10CFR55.43 High          3.0              3                Y              y W(7)                  N Source Documentation Source:                  New Exam Item                                Previous NRC Exam 0Modified Bank Item                          0Other Exam Bank 17 ILT Exam Bank Reference(s):        S51.8.8, step 3.2 Learning            LLOT0370.14~
Objective:
KnowledgelAbility 205000                                              Importance:  RO / SRO WA                  K6.04                                                        3.6 13.6 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generatinq Station                    ILT05-1 NRC Initial Licensing Examination
: 35. Unit 1 plant conditions are as follows:
0  Reactor power is 100%
0  The RO selects Single-Element control on the Feedwater Master Level Controller (L IC-M 1- 1R600)
WHICH ONE of the following describes the response, if any, of the Master Level Controller to a Reactor SCRAM?
A. Controller will swap to three-element when SCRAM Profile is activated.
B. Controller will swap to three-element when SCRAM Profile is reset.
C. Controller will swap to three-element when Reactor power is below 20%.
D. Controller will remain in single-element.
Page 70 of 200
 
Limerick Generating Station                            iLT05-I NRC initial Licensinq Examination Answer Key SBtI I          Choice                                              Basis or Justification 1      Correct:            A    SCRAM profile will swap controller to three element even if operator selected single element.
I1    Incorrect Incorrect B
C This is incorrect as FW will swap to single element when SCRAM profile is reset This is incorrect as FW will swap to single element at -20%
1ncorrect            D    This is incorrect a controller will not remain in single element if single is selected (IF FW flow failure had caused swap to single element this would be correct).
Level of      Difficulty  Time Allowance          PRA                  RO                      SRO Knowledge                      (minutes)                            10CFR55.41              10CFR55.43 High          3.0              3                Y                  y (b)(7)                    N Source:                    New Exam Item                              0Previous NRC Exam 0Modified Bank Item                                Other Exam Bank ILT Exam Bank Reference(s):        S.06.1 .D Unit 1, Attachment 1 Learning              LLOT0550.08 Objective:  '
Knowledge/Ability 259002                                                Importance:    RO I SRO WA                    K5.01                                                            3.1 13.1 REQUIRED MATERIALS:
Notes and Comments:
Notes and Comments:
Existing bank question, Stem and Distractors Modified Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generatina Station ILT05-1 NRC Initial Licensing Examination
: 34. Unit 1 plant conditions are as follows: 0 OPCON4 0 "IA" RHR is in shutdown cooling Reactor water level drops from +70" to -1 0". WHICH ONE of the following identifies current RHR pump and valve status?
HV-51-1 F006A HV-51-1 FOO9 Shutdown Cooling Shutdown Cooling "1A RHR Pump Suction Valve Isolation valve A. B. C. D. Running Open Open Running Open Closed Closed Open Tripped Tripped Open Closed Page 68 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination C I Answer Key Incorrect as F006A will not automatically close and FOO9 yiJ close when level drops below
+I 25" Correct: Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3 Y y W(7) Incorrect SRO 1 OCFR55.43 N I Incorrect KnowledgelAbility WA I Basis or Justification 205000 Importance:
RO / SRO K6.04 3.6 13.6 D When level decreases to below +I 2.5" Shutdown Cooling will isolate FOO9, which in turn trips the ARHR pump, F006 remains open as there is no auto closure Incorrect as FOO9 will close with level below +125" and pump will trip A Incorrect as pump will trip when level drops below 12.5" due to FOO9 closure Source Documentation Source: Reference(s):
Learning Objective:
New Exam Item 0 Modified Bank Item 17 ILT Exam Bank Previous NRC Exam 0 Other Exam Bank S51.8.8, step 3.2 LLOT0370.14~
Required Materials:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
: 35. Unit 1 plant conditions are as follows: 0 Reactor power is 100% 0 The RO selects Single-Element control on the Feedwater Master Level Controller (L I C-M 1 - 1 R600) WHICH ONE of the following describes the response, if any, of the Master Level Controller to a Reactor SCRAM? A. Controller will swap to three-element when SCRAM Profile is activated.
B. Controller will swap to three-element when SCRAM Profile is reset. C. Controller will swap to three-element when Reactor power is below 20%. D. Controller will remain in single-element.
Page 70 of 200 Limerick Generating Station iLT05-I NRC initial Licensinq Examination Answer Key Level of Difficulty Time Allowance PRA RO 1 OCFR55.41 Knowledge (minutes)
High 3.0 3 Y y (b)(7) I Choice SRO 1 OCFR55.43 N Correct: 1 Source: Reference(s):
Learning Objective:
' Knowledge/Ability WA Incorrect I New Exam Item 0 Modified Bank Item ILT Exam Bank 0 Previous NRC Exam Other Exam Bank S.06.1 .D Unit 1, Attachment 1 LLOT0550.08 259002 Importance:
RO I SRO K5.01 3.1 13.1 1 Incorrect 1 ncorrect A B C D SBtI Basis or Justification SCRAM profile will swap controller to three element even if operator selected single element. This is incorrect as FW will swap to single element when SCRAM profile is reset This is incorrect as FW will swap to single element at
-20% This is incorrect a controller will not remain in single element if single is selected (IF FW flow failure had caused swap to single element this would be correct).
This is incorrect a controller will not remain in single element if single is selected (IF FW flow failure had caused swap to single element this would be correct).
REQUIRED MATERIALS
: Notes and Comments:
This question relates to the LGS plant specific FW controllers.
This question relates to the LGS plant specific FW controllers.
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
Prepared By:
: 36. Unit 1 plant conditions are as follows: 0 HPCl is in service for RPV pressure control (CST to CST) 0 FIC-055-1 R600 "HPCI FLOW CONTROL VALVE AUTO/MAN switch" is in AUTO HV-55-1 F008 "HPCI, Test Loop Shutoff" is throttled to maintain pump discharge pressure 150 psig over Reactor pressure.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
0 The RO throttles HV-55-1 F008 in the closed direction for one second WHICH ONE of the following describes HPCl turbine speed and flowrate one minute later? HPCl Turbine Speed Flowrate A. No change Higher B. Higher No change C. Lower No change D. No change Lower Page 72 of 200 Limerick Gene rat in g Station ILT05-I NRC Initial Licensinq Examination  
 
~ Correct: Incorrect Answer Key B With Flow Controller in AUTO, system flow is maintained constant.
Limerick Generating Station                   ILT05-1 NRC Initial Licensing Examination
IF F008 is throttled closed HPCl speed will need to increase to maintain the same flow Flow Controller is in Auto, maintaining system flow constant A Choice I Basis or Justification Incorrect D Flow Controller is in Auto, maintaining system flow constant.
: 36. Unit 1 plant conditions are as follows:
To maintain constant flow w/F008 throttled closed, speed goes up. /c/ Incorrect Level of Knowledge High Difficulty Time Allowance PRA RO SRO lOCFR55.41 1 OCFR55.43 (minutes) 2.5 3 N y (W(7) N I Psvchometrics I Source: Reference( s ): Learning 0 bjective:
0   HPCl is in service for RPV pressure control (CST to CST) 0   FIC-055-1 R600 HPCI FLOW CONTROL VALVE AUTO/MAN switch is in AUTO HV-55-1F008 HPCI, Test Loop Shutoff is throttled to maintain pump discharge pressure 150 psig over Reactor pressure.
New Exam Item Modified Bank Item ILT Exam Bank S55.1 .D, note Step 4.4.3 LLOT0340.12 c] Previous NRC Exam Other Exam Bank Source Documentation KnowledgetAbility WA 206000 HPCl Importance:
0   The RO throttles HV-55-1F008 in the closed direction for one second WHICH ONE of the following describes HPCl turbine speed and flowrate one minute later?
RO I SRO AI .09 3.4 t 3.5 Required Materials:
HPCl Turbine Speed             Flowrate A.         No change                   Higher B.         Higher                     No change C.         Lower                       No change D.         No change                   Lower Page 72 of 200
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
 
~~ Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
Limerick Generating Station                           ILT05-I NRC Initial Licensinq Examination Answer Key Choice
              ~
I                              Basis or Justification Correct:           B     With Flow Controller in AUTO, system flow is maintained constant. IF F008 is throttled closed HPCl speed will need to increase to maintain the same flow Incorrect          A      Flow Controller is in Auto, maintaining system flow constant Incorrect
                      /c/        To maintain constant flow w/F008 throttled closed, speed goes up.
Incorrect           D      Flow Controller is in Auto, maintainingsystem flow constant.
I                                                  Psvchometrics                                          I Level of     Difficulty   Time Allowance         PRA               RO                     SRO Knowledge                        (minutes)                        10CFR55.41               10CFR55.43 High          2.5               3               N               y (W(7)                   N Source Documentation Source:                     New Exam Item                             c]Previous NRC Exam Modified Bank Item                           Other Exam Bank ILT Exam Bank Reference(s ):        S55.1.D, note Step 4.4.3 Learning              LLOT0340.12 0bjective:
KnowledgetAbility 206000 HPCl                                         Importance:   RO I SRO WA                    A I .09                                                         3.4 t 3.5 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
~~
Limerick Generatinq Station                     ILT05-1 NRC Initial Licensinq Examination
: 37. Unit 1 plant conditions are as follows:
: 37. Unit 1 plant conditions are as follows:
ADS Auto Inhibit switches are in "NORM" 0 RPV water level is -1 0" and lowering 0 RPV pressure is 400 psig and steady 0 Drywell pressure is 1.8 psig 0 Core Spray pumps "I B" and "I D" are running 0 Core Spray pumps "1A and "IC" are tripped and cannot be started 0 ALL RHR pumps are tripped and cannot be started Subsequently, RPV water level drops to  
ADS Auto Inhibit switches are in NORM 0   RPV water level is -1 0 and lowering 0   RPV pressure is 400 psig and steady 0   Drywell pressure is 1.8 psig 0   Core Spray pumps I   B and I D are running 0   Core Spray pumps 1 A and IC are tripped and cannot be started 0   ALL RHR pumps are tripped and cannot be started Subsequently, RPV water level drops to -1 33.
-1 33". WHICH ONE of the following identifies the response of DIV 1 and DIV 3 ADS subsystems? (Assume no operator actions)
WHICH ONE of the following identifies the response of DIV 1 and DIV 3 ADS subsystems? (Assume no operator actions)
DIV I ADS DIV 3 ADS A. initiates after 105 second TD Will not initiate B. Initiates after 525 second TD Will not initiate C. Will not initiate Initiates after 105 second TD D. Will not initiate Initiates after 525 second TD Page 74 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination B Correct: DIV 1 ADS will not initiate without correct pumps running DIV 3 will initiate as described above Incorrect:
DIV IADS                            DIV 3 ADS A. initiates after 105 second TD               Will not initiate B. Initiates after 525 second TD               Will not initiate C. Will not initiate                           Initiates after 105 second TD D. Will not initiate                           Initiates after 525 second TD Page 74 of 200
r D Incorrect DIV 1 will not initiate is correct but, DIV 3 initiating after 525 seconds is incorrect as -129 and 1.68# conditions bypass 420 sec timer. C Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.5 4 Y Y (b)(7) A SRO I OCFR55.43 N Basis or Justification DIV 1 ADS will not initiate as no Div 1 Core Spray or RHR pumps are running DIV 3 will initiate as B & D core spray pumps are running 105 sec is correct as -129 and HI DW pressure are met. DIV I will not initiate without correct pumps running DIV 3 will initiate as described above 209001 K3.02 Importance:
 
RO / SRO 3.8 i 3.9 Source: Reference(s):
Limerick Generating Station                           ILT05-1 NRC Initial Licensing Examination Basis or Justification Correct:           C    DIV 1 ADS will not initiate as no Div 1 Core Spray or RHR pumps are running DIV 3 will initiate as B & D core spray pumps are running 105 sec is correct as -129 and HI DW pressure are met.
Learning 0 bjective:
r    Incorrect:          A    DIV Iwill not initiate without correct pumps running DIV 3 will initiate as described above Incorrect           B    DIV 1 ADS will not initiate without correct pumps running DIV 3 will initiate as described above D   DIV 1 will not initiate is correct but, DIV 3 initiating after 525 seconds is incorrect as -129 and 1.68# conditions bypass 420 sec timer.
Knowledge/Ability K/A Source Documentation New Exam Item 0 ILT Exam Bank Previous NRC Exam 0 Other Exam Bank Modified Bank Item B21-1060 (ADS)
Level of     Difficulty Time Allowance           PRA                 RO                   SRO Knowledge                     (minutes)                             10CFR55.41           IOCFR55.43 High           3.5             4                 Y               Y (b)(7)                 N Source Documentation Source:                   New Exam Item                                   Previous NRC Exam Modified Bank Item                          0Other Exam Bank 0ILT Exam Bank Reference(s):          B21-1060 (ADS) Sh. 3 Learning              LLOT0350.04~
Sh. 3 LLOT0350.04~ (Description of K&A, from catalog) Knowledge of the effect that a loss or malfunction of core spray will have on the following:
0bjective:
ADS Logic REQUIRED MATERIALS:
Knowledge/Ability 209001                                                Importance: RO / SRO K/A                    K3.02                                                          3.8 i 3.9 (Description of K&A, from catalog)
Knowledge of the effect that a loss or malfunction of core spray will have on the following: ADS Logic REQUIRED MATERIALS:
Notes and Comments:
Notes and Comments:
Existing Question, Stem and Distractors Modified Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
Existing Question, Stem and Distractors Modified Prepared By:
: 38. Unit 1 plant conditions are as follows: 0 An ATWS has occurred 0 No operator actions are taken 0 Reactor level is -40" and slowly lowering Reactor power is 30% and slowly lowering Three minutes later Reactor power is 27% and slowly lowering.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
WHICH ONE of the following identifies lights and alarms for the given con d it ions?
 
Limerick Generatinq Station                     ILT05-1 NRC Initial Licensing Examination
: 38. Unit 1 plant conditions are as follows:
0   An ATWS has occurred 0   No operator actions are taken 0   Reactor level is -40 and slowly lowering Reactor power is 30% and slowly lowering Three minutes later Reactor power is 27% and slowly lowering.
WHICH ONE of the following identifies lights and alarms for the given cond itions?
A. Squib valve continuity lights NOT lit; CORE SPRAY LINE INTERNAL BREAK alarm annunciated.
A. Squib valve continuity lights NOT lit; CORE SPRAY LINE INTERNAL BREAK alarm annunciated.
B. Squib valve continuity lights NOT lit, STANDBY LIQUID TANK LO-LO LEVEL alarm annunciated.
B. Squib valve continuity lights NOT lit, STANDBY LIQUID TANK LO-LO LEVEL alarm annunciated.
C. Squib valve continuity lights lit, RWCU SYSTEM ISOLATED alarm annunciated.
C. Squib valve continuity lights lit, RWCU SYSTEM ISOLATED alarm annunciated.
D. Squib valve continuity lights lit, DIV 1/11 RRCS CHANNEL ACTIVATED alarm annunciated.
D. Squib valve continuity lights lit, DIV 1/11 RRCS CHANNEL ACTIVATED alarm annunciated.
Page 76 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Correct: Incorrect Answer Key A Squib valve continuity Light not lit is correct as 3 minutes after -40" is reached with power above 4% SLC will have initiated.
Page 76 of 200
Additionally injection will result in "core spray line internal break" alarm Is incorrect as SLC tank low-low level would not be alarming at this point.
 
B Choice I Basis or Justification Incorrect Incorrect C Squib valve continuity lights lit is wrong as SLC will have initiated D Squib valve continuity lights lit is wrong as SLC will have initiated Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3 Y Y (b)(5) I I SRO 1 OCFR55.43 N Source: Reference(s):
Limerick Generating Station                           ILT05-1 NRC Initial Licensinq Examination Answer Key Choice            I                                Basis or Justification Correct:           A     Squib valve continuity Light not lit is correct as 3 minutes after -40 is reached with power above 4% SLC will have initiated. Additionally injection will result in core spray line internal break alarm Incorrect          B    Is incorrect as SLC tank low-low level would not be alarming at this point.
Learning Objective:
Incorrect         C     Squib valve continuity lights lit is wrong as SLC will have initiated Incorrect          D     Squib valve continuity lights lit is wrong as SLC will have initiated I      I Level of     Difficulty Time Allowance           PRA                 RO                     SRO Knowledge                       (minutes)                           10CFR55.41             10CFR55.43 High         3.0               3                 Y               Y (b)(5)                   N Source:                 N N e w Exam Item                                 Previous NRC Exam 2001 0Modified Bank Item                            c]Other Exam Bank 0ILT Exam Bank Reference(s):        S48.1.B, section 4.0, ANN 113, B5 Learning              LLOT0310.06 Objective:
Knowledge/Ability WA NNew Exam Item 0 Modified Bank Item 0 ILT Exam Bank Previous NRC Exam 2001 c] Other Exam Bank S48.1 .B, section 4.0, ANN 11 3, B5 LLOT0310.06 21 1000 Importance:
Knowledge/Ability 211000                                                Importance:   RO / SRO WA                    A1.10                                                           3.7 / 3.7 REQUIRED MATERIALS:
RO / SRO A1.10 3.7 / 3.7 REQUIRED MATERIALS:
Notes and Comments Prepared By:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILTO5-1 NRC Initial Licensinn Examination
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
: 39. Unit 2 plant conditions are as follows: 0 0 0 Turbine shell warming is in progress Turbine first stage pressure rises to 200 psig PIS-001-652A and D are lit on panels 10609 and lOC61 I in the Aux Equipment Room respectively WHICH ONE of the following identifies the plant response?
 
A. Full Reactor SCRAM on Turbine Stop Valve closure. B. Full Reactor SCRAM on Turbine Control Valve closure. C. Half SCRAM ONLY on Turbine Stop Valve closure. D. Half SCRAM ONLY on Turbine Control Valve closure.
Limerick Generating Station                   ILTO5-1 NRC Initial Licensinn Examination
Page 78 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination B Correct: Turbine control valve closure scram is wrong as turbine control valves are open to support shell warming Incorrect Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 4.5 3 Y y (b)(7) Incorrect Incorrect SRO 1 OCFR55.43 N I Basis or Justification I 212000 RPS K4.12 Importance:
: 39. Unit 2 plant conditions are as follows:
RO / SRO 3.9 / 4.1 Cpp I This answer is wrong as a complete SCRAM will occur D This answer is wrong as a complete SCRAM will occur Source: Reference( s): Learning 0 bject ive
0     Turbine shell warming is in progress 0    Turbine first stage pressure rises to 200 psig 0    PIS-001-652A and D are lit on panels 10609 and lOC61 Iin the Aux Equipment Room respectively WHICH ONE of the following identifies the plant response?
: Knowledge/Ability KIA Source Documentation
A. Full Reactor SCRAM on Turbine Stop Valve closure.
[xi New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank GP-2 Appendix 3, step 3.2.8 caution ANN 107, A2 LLOT0300.04 (Description of K&A, from catalog) Knowledge of RPS design feature andlor interlocks which provide for bypassing of selected SCRAM signals (manually and automatically):
B. Full Reactor SCRAM on Turbine Control Valve closure.
C. Half SCRAM ONLY on Turbine Stop Valve closure.
D. Half SCRAM ONLY on Turbine Control Valve closure.
Page 78 of 200
 
Limerick Generatinq Station                         ILT05-1 NRC Initial Licensing Examination I                            Basis or Justification                        I Correct:
Incorrect          B      Turbine control valve closure scram is wrong as turbine control valves are open to support shell warming Incorrect               I Cpp This answer is wrong as a complete SCRAM will occur Incorrect          D      This answer is wrong as a complete SCRAM will occur Level of     Difficulty   Time Allowance         PRA                 RO                     SRO Knowledge                     (minutes)                         10CFR55.41               10CFR55.43 High         4.5               3               Y               y (b)(7)                   N Source Documentation Source:                 [xi New Exam Item                           0Previous NRC Exam 0Modified Bank Item                         0Other Exam Bank 0ILT Exam Bank Reference(s):        GP-2 Appendix 3, step 3.2.8 caution ANN 107,A2 Learning              LLOT0300.04 0bjective:
Knowledge/Ability 212000 RPS                                          Importance: RO / SRO KIA                  K4.12                                                          3.9 / 4.1 (Description of K&A, from catalog)
Knowledge of RPS design feature andlor interlocks which provide for bypassing of selected SCRAM signals (manually and automatically):
REQUIRED MATERIALS:
REQUIRED MATERIALS:
Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
Notes and Comments Prepared By:
: 40. Unit 1 plant conditions are as follows: 0 Reactor power 100% 0 Reactor level 35" LT-42-IN004A "Feedwater Narrow Range Level Transmitter" fails downscale Subsequently, LT-42-IN004C "Feedwater Narrow Range Level Transmitter" fails upscale.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                     ILT05-1 NRC Initial Licensing Examination
: 40. Unit 1 plant conditions are as follows:
0 Reactor power 100%
0 Reactor level 35 LT-42-IN004A Feedwater Narrow Range Level Transmitter fails downscale Subsequently, LT-42-IN004C Feedwater Narrow Range Level Transmitter fails upscale.
WHICH ONE of the following describes the impact, if any, on feedwater level control and Reactor level?
WHICH ONE of the following describes the impact, if any, on feedwater level control and Reactor level?
A. B. C. D. Feedwater Master Level Controller will swap to single element, Reactor level will go up. Feedwater Master Level Controller will swap to single element, Reactor level will remain at 35". Feedwater Master Level Controller will remain in three element, Reactor level will remain at 35". Individual Reactor Feed Pump speed controllers will swap to manual, Reactor level will go up.
A. Feedwater Master Level Controller will swap to single element, Reactor level will go up.
Page 80 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge High Answer Key Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.5 3 Y Y (b)(7) N Question ID# 040 Both RC Source: Reference(s):
B. Feedwater Master Level Controller will swap to single element, Reactor level will remain at 35.
Learning Objective:
C. Feedwater Master Level Controller will remain in three element, Reactor level will remain at 35.
Choice Correct: Incorrect:
D. Individual Reactor Feed Pump speed controllers will swap to manual, Reactor level will go up.
Incorrect:
Page 80 of 200
0 New Exam Item 0 Modified Bank Item 0 ILT Exam Bank S06.1 .H U/1, Attachment 1 LLOT0550.1 OC Previous NRC Exam Other Exam Bank Incorrect:
 
Knowledge/Ability WA C 259001 Importance:
Limerick Generating Station                         ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 040 Both RC swicj Choice                                           Basis or Justification Correct:           C   A failure of two level transmitter (1/2 hour apart) will not result in a FW failure, Master level controller will remain in 3 element, and Reactor level will remain unchanged Incorrect:          A    This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart), additionally level will remain at 35 Incorrect:          B    This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart)
RO / SRO K6.07 3.8 / 3.8 A B D swicj" Basis or Justification A failure of two level transmitter (1/2 hour apart) will not result in a FW failure, Master level controller will remain in 3 element, and Reactor level will remain unchanged This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart), additionally level will remain at 35" This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart) A failure of two level transmitters (1/2 hour apart) will not result in speed controllers swapping to manual (two failure simultaneously, or three failures would), additionally reactor level will not go up REQUIRED MATERIALS: Notes and Comments:
Incorrect:          D    A failure of two level transmitters (1/2 hour apart) will not result in speed controllers swapping to manual (two failure simultaneously, or three failures would), additionally reactor level will not go up Level of      Difficulty  Time Allowance          PRA                  RO                        SRO Knowledge                      (minutes)                            10CFR55.41              10CFR55.43 High          3.5              3                Y              Y (b)(7)                    N Source:                  0New Exam Item                                  Previous NRC Exam 0Modified Bank Item                              Other Exam Bank 0ILT Exam Bank Reference(s):          S06.1.H U/1, Attachment 1 Learning              LLOT0550.1OC Objective:
Modified Question from LOR bank Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Knowledge/Ability 259001                                                Importance:    RO / SRO WA                    K6.07                                                            3.8 / 3.8 REQUIRED MATERIALS:
-. Limerick Generating Station ILTO5-I NRC Initial Licensing Examination
Notes and Comments:
: 41. Unit 1 plant conditions are as follows: An ATWS is in progress 0 Reactor power is 50% and steady 0 Reactor water level is 35" and steady e Reactor pressure is 1045 psig and steady RRCS DIV "1 B" AND DIV "2A Manual Initiation Pushbuttons are armed and depressed.
Modified Question from LOR bank Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                    -
                                    .
Limerick Generating Station                     ILTO5-I NRC Initial Licensing Examination
: 41. Unit 1 plant conditions are as follows:
An ATWS is in progress 0   Reactor power is 50% and steady 0   Reactor water level is 35 and steady e   Reactor pressure is 1045 psig and steady RRCS DIV 1B AND DIV 2A Manual Initiation Pushbuttons are armed and depressed.
WHICH ONE of the following identifies RRCS response?
WHICH ONE of the following identifies RRCS response?
A. ARI will initiate immediately.
A. ARI will initiate immediately.
B. Recirc Pumps will trip in 9 seconds. C. SLC will initiate if APRM's are not downscale in 1 18 seconds.
B. Recirc Pumps will trip in 9 seconds.
C. SLC will initiate if APRMs are not downscale in 1 18 seconds.
D. DIV I / II RRCS annunciators will illuminate, ARI solenoids remain deenergized.
D. DIV I / II RRCS annunciators will illuminate, ARI solenoids remain deenergized.
Page 82 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Choice Correct: D Incorrect A Answer Key Basis or Justification RRCS manual initiation requires depressing both pushbuttons in the SAME Division, the noted action (one pushbutton in separate divisions) will not initiate RRCS ARI will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met Incorrect B Recirc pump trip does not initiate from manual RRCS initiation, and conditions for automatic initiation are not met SLC will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met Icl Incorrect Level of Knowledge Low I Psvchometrics I Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 3 Y Y (b)(7) N Source: Reference(s):
Page 82 of 200
Learning Objective: Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank GP-18 Attachment 4, ANN 004 F-5 LLOT0315.05 Knowledge/Ability KIA 21 2000 Importance:
 
RO I SRO A4.16 4.4 14.4 REQUIRED MATERIALS:
Limerick Generating Station                       ILT05-1 NRC Initial Licensinq Examination Answer Key Choice                                          Basis or Justification Correct:          D    RRCS manual initiation requires depressing both pushbuttons in the SAME Division, the noted action (one pushbutton in separate divisions) will not initiate RRCS Incorrect          A    ARI will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met Incorrect         B   Recirc pump trip does not initiate from manual RRCS initiation, and conditions for automatic initiation are not met Incorrect Icl      SLC will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met I                                               Psvchometrics                                             I Level of    Difficulty Time Allowance           PRA                 RO                     SRO Knowledge                      (minutes)                         10CFR55.41               10CFR55.43 Low          3.0               3                 Y             Y (b)(7)                   N Source Documentation Source:                   New Exam Item                             0Previous NRC Exam 0Modified Bank Item                       0Other Exam Bank 0ILT Exam Bank Reference(s):        GP-18 Attachment 4, ANN 004 F-5 Learning              LLOT0315.05 Objective:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination
Knowledge/Ability 212000                                              Importance:   RO I SRO KIA                  A4.16                                                         4.4 14.4 REQUIRED MATERIALS:
: 42. Unit I plant conditions are as follows: Reactor power is 100% 0 Normal Reactor Enclosure ventilation is in service 0 Both Standby Gas Treatment System fans are in AUTO Reactor water level master trip units, LIS-42-1 N681A and LIS-42-1 N681 B, fail downscale. WHICH ONE of the following identifies the status of Standby Gas Treatment System (SGTS) five minutes later? A. "OA SGTS Fan and "OB" SGTS Fan running. B. Only "OA' SGTS Fan running. C. Only "OB" SGTS Fan running. D. Both SGTS Fans off. Page 84 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
Notes and Comments Prepared By:
I OCFR55.41 Answer Key SRO I OCFR55.43 Question-ID# 042 Both RC Choice Correct: I B Incorrect:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Incorrect A - C ~~~ Incorrect:
 
D Basis or Justification "A Reactor enclosure isolation and "A SGTS start will occur on LIS-42-IN681A and B downscale failure Incorrect as B Fan will not start
Limerick Generatinq Station                   ILT05-I NRC Initial Licensinq Examination
____~ ~ Incorrect as B Fan will not start Incorrect as A Fan will start Source : Reference(s):
: 42. Unit Iplant conditions are as follows:
Learning Objective:
Reactor power is 100%
Knowledge/Ability WA Source Documentation New Exam Item Modified Bank Item 0 ILT Exam Bank Previous NRC Exam 0 Other Exam Bank ANN 004 E-I LLOT0200.1 OB 261 000 K6.08 Importance:
0 Normal Reactor Enclosure ventilation is in service 0 Both Standby Gas Treatment System fans are in AUTO Reactor water level master trip units, LIS-42-1N681A and LIS-42-1N681B, fail downscale.
RO / SRO 3.1 /3.1 (Description of K&A, from catalog) Knowledge of the effect that a Loss or Malfunction of the following will have on the SGTS system: Reactor vessel level Required Materials:
WHICH ONE of the following identifies the status of Standby Gas Treatment System (SGTS) five minutes later?
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
A. O A SGTS Fan and OB SGTS Fan running.
: 43. Unit I plant conditions are as follows: 0 Reactor power is 100% 0 Reactor level is 35" A Condensate min flow controller malfunction results in the following:
B. Only OASGTS Fan running.
0 Reactor Feed Pump (RFP) suction pressure drops to 230 psi for 6 seconds and then goes up to 250 psig WHICH ONE of the following identifies the subsequent Feedwater system status? A. "IA" RFP is tripped, "IB" and "IC" RFP's are running. B. "1 C" RFP is tripped, "1A and "1 B" RFP's are running.
C. Only OBSGTS Fan running.
C. "I A' and "1 B" RFP's are tripped, "1 C" RFP is running. D. All RFPs are tripped.
D. Both SGTS Fans off.
Page 86 of 200 Limerick Generating Station ILTO5-1 NRC Initial Licensinq Examination B Answer Key Basis or Justification  
Page 84 of 200
'1 C' RFP will trip on Low suction after 5 seconds pressure due to suction pressure less than 233 psi for 5 Choice A Correct: "1A RFP will not trip as "C" RFP trips first followed by "1 B" at 10 seconds and "1A at 15 seconds Incorrect Level of Knowledge Incorrect Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 Incorrect 256000 K1.02 Importance:
 
RO / SRO 3.3 f 3.3 "1 B" and "1A tripped is wrong as "1 C RFP will trip first 7 D All RFPs tripped is wrong as suction pressure stabilized prior to trip of all 3 1 RFPs Psychometrics Source: Reference(s):
Limerick Generating Station                       ILT05-1 NRC Initial Licensinq Examination Answer Key Question-ID# 042 Both RC Choice                                           Basis or Justification Correct:       I   B     A Reactor enclosure isolation and A SGTS start will occur on LIS-42-IN681A and B downscale failure Incorrect:          A    Incorrect as B Fan will not start
Learning Objective:
                            -                    _ _ _ _ ~       ~
Knowledge/Ability KIA Source Documentation New Exam Item [7 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam Other Exam Bank ANN 104 Cond E-2 ANN'S 102 Feed AI, BI, C1 LLOT0520.08 (Description of K&A, from catalog) Knowledge of the Physical connections and/or cause - effect relationship between condensate system and the following: Reactor Feedwater System REQUIRED MATERIALS: Notes and Comments Prepared By: Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author
Incorrect          C    Incorrect as B Fan will not start
- - Limerick Generating Station ILT05-1 NRC Initial Licensinn Examination
      ~~~
: 44. Unit 1 has been scrammed due to a LOCA. RClC auto-initiated following the SCRAM. Conditions are as follows: 0 0 RPV water level has recovered to +35" and is steady Drywell pressure is 2.5 psig and steady The CRS has directed that RClC be secured WHICH ONE of the following will shutdown the RClC turbine and leave RClC ready for auto injection?
Incorrect:          D    Incorrect as A Fan will start Level of        Difficulty  Time Allowance          PRA                RO                  SRO Knowledge                        (minutes)                         IOCFR55.41            IOCFR55.43 Source Documentation Source:                      New Exam Item                               Previous NRC Exam Modified Bank Item                         0Other Exam Bank 0ILT Exam Bank Reference(s):            ANN 004 E-I Learning                  LLOT0200.1OB Objective:
A. Reset the RClC initiation signal seal-in. Depress the RClC turbine manual isolation push button. Close the RClC trip throttle valve (HV-50-112).
Knowledge/Ability 261000                                                  Importance: RO / SRO WA                        K6.08                                                      3.1 /3.1 (Description of K&A, from catalog)
B. Depress the RClC turbine manual isolation pushbutton. Close the RClC steam supply valve (HV-50-1 F045). Reset the RClC trip throttle valve (HV-50-112).
Knowledge of the effect that a Loss or Malfunction of the following will have on the SGTS system:
Reactor vessel level Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                       ILT05-1 NRC Initial Licensing Examination
: 43. Unit Iplant conditions are as follows:
0 Reactor power is 100%
0 Reactor level is 35 A Condensate min flow controller malfunction results in the following:
0 Reactor Feed Pump (RFP) suction pressure drops to 230 psi for 6 seconds and then goes up to 250 psig WHICH ONE of the following identifies the subsequent Feedwater system status?
A. I A  RFP is tripped, IB and I C  RFPs are running.
B. 1C RFP is tripped,     1 A and 1B RFPs are running.
C. I Aand 1 B RFPs are tripped, 1C RFP is running.
D. All RFPs are tripped.
Page 86 of 200
 
Limerick Generating Station                         ILTO5-1 NRC Initial Licensinq Examination Answer Key Choice                                            Basis or Justification Correct:          B    1C  RFP will trip on Low suction after 5 seconds pressure due to suction pressure less than 233 psi for 5 Incorrect          A      1 A RFP will not trip as C RFP trips first followed by 1B at 10 seconds and 1 A at 15 seconds Incorrect 7        1B and  1 A tripped is wrong as 1C RFP will trip first Incorrect          D 1 All RFPs tripped is wrong as suction pressure stabilized prior to trip of all 3 RFPs Psychometrics Level of    Difficulty  Time Allowance            PRA                  RO                      SRO Knowledge                      (minutes)                           10CFR55.41                10CFR55.43 Source Documentation Source:                    New Exam Item                             0Previous NRC Exam
[7 Modified Bank Item                             Other Exam Bank 0ILT Exam Bank Reference(s):        ANN 104 Cond E-2 ANNS 102 Feed AI, BI, C1 Learning              LLOT0520.08 Objective:
Knowledge/Ability 256000                                                Importance: RO / SRO KIA                  K1.02                                                            3.3 f 3.3 (Description of K&A, from catalog)
Knowledge of the Physical connections and/or cause - effect relationship between condensate system and the following: Reactor Feedwater System REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   ILT05-1 NRC Initial Licensinn Examination
: 44. Unit 1 has been scrammed due to a LOCA.
RClC auto-initiated following the SCRAM. Conditions are as follows:
RPV water level has recovered to +35 and is steady 0    Drywell pressure is 2.5 psig and steady 0    The CRS has directed that RClC be secured WHICH ONE of the following will shutdown the RClC turbine and leave RClC ready for auto injection?
A. Reset the RClC initiation signal seal-in.
Depress the RClC turbine manual isolation pushbutton.
Close the RClC trip throttle valve (HV-50-112).
B. Depress the RClC turbine manual isolation pushbutton.
Close the RClC steam supply valve (HV-50-1F045).
Reset the RClC trip throttle valve (HV-50-112).
C. Reset the RClC initiation signal seal-in.
C. Reset the RClC initiation signal seal-in.
Depress the RClC turbine trip pushbutton. Close the RClC steam supply valve (HV-50-1 F045). Reset the RClC trip throttle valve (HV-50-112).
Depress the RClC turbine trip pushbutton.
Close the RClC steam supply valve (HV-50-1F045).
Reset the RClC trip throttle valve (HV-50-112).
D. Depress the RClC turbine trip pushbutton.
D. Depress the RClC turbine trip pushbutton.
Place the RClC pump discharge flow controller in MANUAL. Set the RClC pump discharge flow controller to 0%. Close the RClC trip throttle valve (HV-50-112).
Place the RClC pump discharge flow controller in MANUAL.
Page 88 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 2.5 3 Y y (bN7) Answer Key SRO 1 OCFR55.43 N Choice Source: Reference(s):
Set the RClC pump discharge flow controller to 0%.
Learning 0 bjective:
Close the RClC trip throttle valve (HV-50-112).
Correct: New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank S49.2A section 4.1, S49.1 C section 4.3 LOT0380.08 Incorrect KIA Incorrect Incorrect C A B D Basis or Justification Since the initiation signal is no longer present the operator can reset it, Trip the turbine and close the steam supply. Resetting the Trip throttle valve leaves RClC ready for auto injection Once the initiation signal is reset, the manual isolation will not work These steps will shutdown RCIC, but the isolation must be reset in order to be ready for auto injection These steps will shutdown RCIC if the initiation signal were still present. RClC will not be ready to auto inject I Knowledge/Ability 21 7000 1 Importance:
Page 88 of 200
RO / SRO (Description of K&A, from catalog) Ability to manually operate and/or monitor in the control room --Manually initiated controls Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station . ILT05-1 NRC Initial Licensing Examination
 
Limerick Generating Station                           ILT05-1 NRC Initial Licensinq Examination Answer Key Choice                                           Basis or Justification Correct:           C     Since the initiation signal is no longer present the operator can reset it, Trip the turbine and close the steam supply. Resetting the Trip throttle valve leaves RClC ready for auto injection Incorrect          A    Once the initiation signal is reset, the manual isolation will not work Incorrect          B    These steps will shutdown RCIC, but the isolation must be reset in order to be ready for auto injection Incorrect          D    These steps will shutdown RCIC if the initiation signal were still present.
RClC will not be ready to auto inject Level of    Difficulty  Time Allowance            PRA                  RO                    SRO Knowledge                      (minutes)                            10CFR55.41              10CFR55.43 High          2.5              3                Y                y (bN7)                    N Source:                    New Exam Item                              0Previous NRC Exam 0Modified Bank Item                          0Other Exam Bank 0ILT Exam Bank Reference(s):        S49.2A section 4.1, S49.1C section 4.3 Learning              LOT0380.08 0bjective:
I Knowledge/Ability     217000                                          1 Importance:   RO / SRO KIA (Description of K&A, from catalog)
Ability to manually operate and/or monitor in the control room
  --Manually initiated controls Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station .             ILT05-1 NRC Initial Licensing Examination
: 45. WHICH ONE of the following identifies SRV indications during an ADS automatic blowdown?
: 45. WHICH ONE of the following identifies SRV indications during an ADS automatic blowdown?
Amber White "Has Lifted Light" "Solenoid Energized Light" Lit Not Lit A. B. Lit Lit C. Not Lit Lit D. Not Lit Not Lit Page 90 of 200 Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) lOCFR55.41 Low 2.0 2 Y Y (b)(7) Answer Kev SRO 1 OCFR55.43 N Question I.D# 045 Both RC Knowledge/Ability WA Choice Correct: . 21 8000 Importance:
Amber                             White Has Lifted Light             Solenoid Energized Light A.        Lit                             Not Lit B.         Lit                               Lit C.       Not Lit                             Lit D.       Not Lit                           Not Lit Page 90 of 200
RO / SRO A3.01 4.21 4.3 Incorrect A Incorrect C Incorrect D Basis or Justification  
 
~ During an automatic blowdown both amber "has lifted" (Acoustic monitor) and white solenoid (ADS Div I & 3) lights will light.
  . Limerick Generatinq Station Question I.D# 045 Both RC Choice Correct:
This is incorrect as white solenoid energized light will be lit on ADS auto initiation This is incorrect as Amber "has lifted" light will be lit This is incorrect as both lights will be lifted if there was no increased Drywell pressure this would be true Source Documentation Source: Reference(s):
Incorrect Incorrect Incorrect Level of A
Learning 0 bjective:
C D
New Exam Item (7 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank OT-114, ARC 110 B-2 LLOT0330.07a Required Materials:
Difficulty initiation Answer Kev ILT05-I NRC Initial Licensinq Examination Basis or Justification
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
                                                                ~
: 46. Unit I is operating at 100%. An instrument failure results in an inadvertent RPV low-low level signal
During an automatic blowdown both amber has lifted (Acoustic monitor) and white solenoid (ADS Div I& 3) lights will light.
(-38"). WHICH ONE of the following describes the response of the Bypass Leakage Barrier Blocks and Vents?
This is incorrect as white solenoid energized light will be lit on ADS auto This is incorrect as Amber has lifted light will be lit This is incorrect as both lights will be lifted if there was no increased Drywell pressure this would be true Time Allowance          PRA                    RO                      SRO Knowledge                    (minutes)                            10CFR55.41                10CFR55.43 Low          2.0              2              Y                Y (b)(7)                    N Source Documentation Source:                   New Exam Item                             0Previous NRC Exam (7 Modified Bank Item                         0Other Exam Bank 0ILT Exam Bank Reference(s):        OT-114, ARC 110 B-2 Learning              LLOT0330.07a 0bjective:
A. Instrument Gas Block Valves are closed and the vents are open. B. Recirc Pump Seal Purge Block Valves are closed and the vents are open. C. Main Steam Line Drain Block Valves are closed and the vents are open. D. N2 Supply Block Valves are closed and the vents are open. Page 92 of 200 Limerick Generating Station iLT05-1 NRC initial Licensing Examination Incorrect Answer Key C This is incorrect as main steam line vent valves do not automatically open Choice I Basis or Justification Level of Difficulty Time Allowance PRA Low 3.5 3 Y Knowledge (minutes)
Knowledge/Ability 218000                                                Importance: RO / SRO WA                    A3.01                                                            4.21 4.3 Required Materials:
Correct: RO SRO 1 OCFR55.41 1 OCFR55.43 Y (b)(5) N NZ Supply valve closes and vent valve opens on a Lo-Lo Reactor level lD1 signal (VIIIB) 223002 A2.05 ~~ Incorrect:
Notes and Comments Prepared By:
1 A 1 This is incorrect as instrument gas block valves isolate at Lo-Lo-Lo Level Importance:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
RO I SRO 3.31 3.6 This is incorrect as recirc vent valves do not automatically open on an isolation Incorrect Source: Reference(s):
 
Learning Objective:
Limerick Generating Station                   ILT05-1 NRC Initial Licensing Examination
KnowledgeIAbility KIA Source Documentation 0 New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam Other Exam Bank GP-8.1, Reactor Level 2-L0w, Low section LLOTOI 80.08d (Description of K&A, from catalog) Ability to predict the impact of Nuclear Boiler Instrumentation failure on the primary containment isolations systemhuclear steam supply shutoff and base on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations.  
: 46. Unit Iis operating at 100%.
!quired Materials: Notes and Comments: Modified LOR Bank Question Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
An instrument failure results in an inadvertent RPV low-low level signal
- -- .- Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
(-38).
WHICH ONE of the following describes the response of the Bypass Leakage Barrier Blocks and Vents?
A. Instrument Gas Block Valves are closed and the vents are open.
B. Recirc Pump Seal Purge Block Valves are closed and the vents are open.
C. Main Steam Line Drain Block Valves are closed and the vents are open.
D. N2 Supply Block Valves are closed and the vents are open.
Page 92 of 200
 
Limerick Generating Station                         iLT05-1 NRC initial Licensing Examination Answer Key Choice           I                               Basis or Justification Correct:
lD1      NZSupply valve closes and vent valve opens on a Lo-Lo Reactor level signal (VIIIB)
          ~~
Incorrect:     1   A   1 This is incorrect as instrument gas block valves isolate at Lo-Lo-Lo Level Incorrect                This is incorrect as recirc vent valves do not automatically open on an isolation Incorrect         C    This is incorrect as main steam line vent valves do not automatically open Level of      Difficulty  Time Allowance          PRA                RO                    SRO Knowledge                      (minutes)                          10CFR55.41              10CFR55.43 Low          3.5              3                Y              Y (b)(5)                 N Source Documentation Source:                  0New Exam Item                               0Previous NRC Exam 0Modified Bank Item                             Other Exam Bank 0ILT Exam Bank Reference(s):          GP-8.1, Reactor Level 2-L0w, Low section Learning              LLOTOI80.08d Objective:
KnowledgeIAbility      223002                                            Importance: RO I SRO KIA                    A2.05                                                            3.31 3.6 (Description of K&A, from catalog)
Ability to predict the impact of Nuclear Boiler Instrumentationfailure on the primary containment isolations systemhuclear steam supply shutoff and base on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations.
  !quired Materials:
Notes and Comments:
Modified LOR Bank Question Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                        .-
                                                                                  - --
Limerick Generating Station                 ILT05-1 NRC Initial Licensinq Examination
: 47. D11 Diesel Generator is operating in parallel with the 101 Safeguard Bus with the following indications:
: 47. D11 Diesel Generator is operating in parallel with the 101 Safeguard Bus with the following indications:
60Hz 2000Kw 1600 KVAR WHICH ONE of the following actions will restore the diesel generator within operating I i m its? A. Place Speed Governor in RAISE to adjust real load to 2100 KW. B. Place Speed Governor in LOWER to adjust real load to 1900 KW. C. Place Voltage Regulator in RAISE to adjust reactive load to 1700 KVAR. D. Place Voltage Regulator in LOWER to adjust reactive load to 1500 KVAR. Page 94 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Choice Correct: D Incorrect:
60Hz 2000Kw 1600 KVAR WHICH ONE of the following actions will restore the diesel generator within operating Iimits?
A Incorrect:
A. Place Speed Governor in RAISE to adjust real load to 2100 KW.
B Basis or Justification Reducing VARS to less than 1500 restores WARS to less than 75% KW, which corresponds to a Power Factor of 0.8 Raising KW would also restore the ratio of KVAR to KW, but KW would have to be raised to 2133 KW. Lowering KW would make the D/G further from its operating limit.
B. Place Speed Governor in LOWER to adjust real load to 1900 KW.
Raising KVAR would also make the D/G further from its operating limit.
C. Place Voltage Regulator in RAISE to adjust reactive load to 1700 KVAR.
Icl Incorrect: Level of Difficulty Time Allowance PRA Knowledge (minutes)
D. Place Voltage Regulator in LOWER to adjust reactive load to 1500 KVAR.
High 2.5 3 Y RO SRO 1 OCFR55.41 1 OCFR55.43 y (W7) N ~ ~ ~~ Source Documentation Source: New Exam Item Previous NRC Exam 0 Modified Bank Item Other Exam Bank Reference( s): Learning Objective:
Page 94 of 200
0 ILT Exam Bank S92.1 .O, caution above step 4.5.5 LLOTO670.02 Required Materials:
 
KnowledgelAbility WA Notes and Comments 264000 Importance:
Limerick Generating Station                       ILT05-1 NRC Initial Licensing Examination Choice                                         Basis or Justification Correct:           D   Reducing VARS to less than 1500 restores W A R S to less than 75% KW, which corresponds to a Power Factor of 0.8 Incorrect:          A    Raising KW would also restore the ratio of KVAR to KW, but KW would have to be raised to 2133 KW.
RO / SRO A4.01 3.3 I 3.4 Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Incorrect:          B    Lowering KW would make the D/G further from its operating limit.
__ - __ Limerick Generating Station ILT05-I NRC Initial Licensing Examination
Incorrect:
: 48. Unit 1 plant conditions are as follows: a "IA CRD pump is in service 0 Reactor power is 100% 0 Reactor level is 35" A failure of a level instrument line results in the following annunciators:
Icl      Raising KVAR would also make the D/G further from its operating limit.
EXCESS FLOW CHECK VALVE OPERATED C218 (1 12 E5) 0 DIV 3 REACTOR LO-LO-LO Level (1 13 E3) WHICH ONE of the following identifies the effect, if any, on the CRD system and the action required to restore CRD, if any?
Level of     Difficulty Time Allowance         PRA               RO                  SRO Knowledge                     (minutes)                       10CFR55.41            10CFR55.43 High         2.5             3               Y               y (W7)                   N
A. "IA CRD pump trips. Can be restarted from the MCR. B. "1A CRD pump remains running. No action required.
~                               ~         ~~
C. "IA CRD pump trips and cannot be restored.  
Source Documentation Source:                 New Exam Item                               Previous NRC Exam 0Modified Bank Item                           Other Exam Bank 0ILT Exam Bank Reference(s):       S92.1.O, caution above step 4.5.5 Learning            LLOTO670.02 Objective:
"1 B" CRD pump must be placed in-service from the MCR. D. "1A CRD pump trips. Can only be restarted from 4 KV switchgear.
KnowledgelAbility 264000                                           Importance: RO / SRO WA                  A4.01                                                     3.3 I 3.4 Required Materials:
Page 96 of 200 Limerick Generating Station ILT05-I NRC Initial Licensina Examination Correct: Incorrect Incorrect Answer Key A B C Question Id# 048 Both R( Incorrect D Level of Knowledge High Basis or Justification Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 2.5 3 Y y (b)(5) N A CRD will trip due to Div Ill LOCA signal and LOCA load shed it can be restarted from the MCR This is incorrect as a CRD pump will trip due to Div Ill LOCA load shed Source: Reference(s):
Notes and Comments Prepared By:
Learning 0 bjective:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
This is incorrect as a CRD can be restarted ONew Exam Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank Modified Bank Item SE-10, step 4.6 LLOT0660.05b This is incorrect as CRD can be restarted from the MCR KnowledgeIAbility WA 262001 Importance:
 
RO I SRO A2.02 3.6 I 3.9 Required Materials:
    -
Limerick Generating Station                     ILT05-I NRC Initial Licensing Examination
: 48. Unit 1 plant conditions are as follows:
a   I A CRD pump is in service 0   Reactor power is 100%
0   Reactor level is 35 A failure of a level instrument line results in the following annunciators:
EXCESS FLOW CHECK VALVE OPERATED C218 (1 12 E5) 0 DIV 3 REACTOR LO-LO-LO Level (1 13 E3)
WHICH ONE of the following identifies the effect, if any, on the CRD system and the action required to restore CRD, if any?
A. I A CRD pump trips.
Can be restarted from the MCR.
B. 1 A CRD pump remains running.
No action required.
C. I A CRD pump trips and cannot be restored.
1 B CRD pump must be placed in-service from the MCR.
D. 1 A CRD pump trips.
Can only be restarted from 4 KV switchgear.
Page 96 of 200
 
Limerick Generating Station                         ILT05-I NRC Initial Licensina Examination Answer Key Question Id# 048 Both R(
Basis or Justification Correct:          A    A CRD will trip due to Div Ill LOCA signal and LOCA load shed it can be restarted from the MCR Incorrect          B    This is incorrect as a CRD pump will trip due to Div Ill LOCA load shed Incorrect          C    This is incorrect as a CRD can be restarted Incorrect          D    This is incorrect as CRD can be restarted from the MCR Level of    Difficulty  Time Allowance          PRA                RO                    SRO Knowledge                      (minutes)                          10CFR55.41              10CFR55.43 High          2.5              3                Y                y (b)(5)                  N Source:                ONew Exam Item                               0Previous NRC Exam Modified Bank Item                      0Other Exam Bank 0ILT Exam Bank Reference(s):        SE-10, step 4.6 Learning              LLOT0660.05b 0bjective:
KnowledgeIAbility 262001                                               Importance:   RO I SRO WA                    A2.02                                                           3.6 I 3.9 Required Materials:
Notes and Comments:
Notes and Comments:
This question was extensively modified from Question 373224 (ILT LERT EXAM 2005) Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
This question was extensively modified from Question 373224 (ILT LERT EXAM 2005)
: 49. Unit 1 Plant conditions are as follows: 0 Reactor is scrammed 0 Reactor pressure is 600 psig 0 Division I DC is lost 0 Reactor water level is +I 15" Which one of the following can be used to lower Reactor pressure?
Prepared By:
A. "1 B" SRV from the MCR. B. "1 C" SRV from the RSP. C. "1 J" SRV from the AER. D. "1 S" SRV from the AER. Page 98 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3 Y Y (b)(7) Answer Key SRO 1 OCFR55.43 N Question ID# 049 Both RC Source: Reference(s):
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Learning 0 bjective:
 
Knowledge/Ability WA I Choice New Exam Item Modified Bank Item ILT Exam Bank 0 Previous NRC Exam 0801#221 0 Other Exam Bank OT-I 10 Step 3.1.4 LLOTOI 20.12a 239002 Importance:
Limerick Generating Station                   ILT05-I NRC Initial Licensinq Examination
RO i SRO K4.05 3.6 i 3.7 ID Correct: iA Incorrect Incorrect I B IC Incorrect Basis or Justification S SRV is an ADS SRV and has power in the AER. While it is not one of the preferred SRV's (B,J,C) for use in OT-I IO, as the preferred SRVs are not available a non-preferred SRV is directed. While B SRV is one of the preferred SRV's for use with high level it cannot be operated from the MCR due to the Loss of Div I DC While C SRV is one of the preferred SRV's for use with high level it cannot be operated from the MCR due to the Loss of Div I DC While J SRV is one of the preferred SRV's for use with high level, control is not availabre in the AER Required Materials:
: 49. Unit 1 Plant conditions are as follows:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
0   Reactor is scrammed 0   Reactor pressure is 600 psig 0   Division I DC is lost 0   Reactor water level is +   I 15 Which one of the following can be used to lower Reactor pressure?
~ - ~~ Limerick Genera t ing Stat ion ILT05-1 NRC Initial Licensing Examination
A. 1B SRV from the MCR.
: 50. Unit I plant conditions are as follows: 0 Reactor power is 100% 0 "1A RECW pump is blocked for bearing replacement 0 "1B" RECW pump trips and cannot be restarted WHICH ONE of the following identifies the effect on the Reactor Recirc Pumps and required operator action? A. Seal cavity temperature rises. Reduce pump speed to maintain cavity temperature below 200OF. B. Seal cavity temperature rises. Trip the RECIRC pumps within IO minutes. C. Pump motor temperature rises. Trip the RECIRC pumps if motor winding temperature exceeds 20OoF. D. Pump motor temperature rises. Trip the RECIRC pumps within 10 minutes. Page 100 of 200 Li mer ic k G e n e rat inq Stat ion ILT05-I NRC Initial Licensing Examination A Answer Key On high seal cavity temperature ON-I 13 directs reducing speed to maintain temperature this occurs at a cavity temperature of 175OF not ZOOOF I Choice I Basis or Justification Incorrect:
B. 1C SRV from the RSP.
Correct: D Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler) Loss of RECW will result in an increase in seal cavity temperature ON-I 13 directs tripping a RECIRC pump within 10 minutes of a loss of RECW Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 2.5 3 Y Y (b)(5) Incorrect:
C. 1J SRV from the AER.
SRO 1 OCFR55.43 N 202001 A2.17 Incorrect: Importance: RO
D. 1S SRV from the AER.
/ SRO 3.1 13.2 Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler) I I I Source: Reference(s):
Page 98 of 200
Learning 0 bjective:
 
KnowledgelAbility KIA Source Documentation Ix] New Exam Item 0 Modified Bank Item c] ILT Exam Bank ON-I 13 step 2.1, S43.0.D LLOT0030.07b:
Limerick Generating Station                       ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 049 Both RC I         Choice                                         Basis or Justification Correct:
Previous NRC Exam 0 Other Exam Bank (Description of K&A, from catalog) Ability to predict the impact of a loss of seal cooling water on the RECIRC system; and based on those predictions use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations. Required Materials: Notes and Comments Prepared By: Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination 51, Unit 2 plant conditions are as follows: "2A" RECW pump is running with its handswitch in AUTO after START 0 "2B" RECW pump is off with its handswitch in AUTO after STOP A complete Loss Of Offsite Power (LOOP) occurs. All 4 KV systems operate as designed with all buses re-energizing SIMULTANEOUSLY.
I D      S SRV is an ADS SRV and has power in the AER. While it is not one of the preferred SRVs (B,J,C) for use in OT-I I O , as the preferred SRVs are not available a non-preferred SRV is directed.
Incorrect Incorrect iA I  B While B SRV is one of the preferred SRVs for use with high level it cannot be operated from the MCR due to the Loss of Div I DC While C SRV is one of the preferred SRVs for use with high level it cannot be operated from the MCR due to the Loss of Div I DC Incorrect I C      While J SRV is one of the preferred SRVs for use with high level, control is not availabre in the AER Level of    Difficulty  Time Allowance          PRA              RO                        SRO Knowledge                    (minutes)                        10CFR55.41                10CFR55.43 High          3.0              3                Y              Y (b)(7)                    N Source:                  New Exam Item                            0 Previous NRC Exam 0801#221 Modified Bank Item                      0Other Exam Bank ILT Exam Bank Reference(s):        OT-I 10 Step 3.1.4 Learning            LLOTOI20.12a 0bjective:
Knowledge/Ability 239002                                          Importance:      RO i SRO WA                  K4.05                                                          3.6 i 3.7 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                          ~         -                                           ~~
Limerick Generat ing Stat ion                 ILT05-1 NRC Initial Licensing Examination
: 50. Unit Iplant conditions are as follows:
0 Reactor power is 100%
0   1 A RECW pump is blocked for bearing replacement 0 1B RECW pump trips and cannot be restarted WHICH ONE of the following identifies the effect on the Reactor Recirc Pumps and required operator action?
A. Seal cavity temperature rises.
Reduce pump speed to maintain cavity temperature below 200OF.
B. Seal cavity temperature rises.
Trip the RECIRC pumps within I O minutes.
C. Pump motor temperature rises.
Trip the RECIRC pumps if motor winding temperature exceeds 20OoF.
D. Pump motor temperature rises.
Trip the RECIRC pumps within 10 minutes.
Page 100 of 200
 
Limerick Ge ne ratinq Station                        ILT05-I NRC Initial Licensing Examination Answer Key I            Choice              I                            Basis or Justification Correct:                    Loss of RECW will result in an increase in seal cavity temperature ON-I 13 directs tripping a RECIRC pump within 10 minutes of a loss of RECW Incorrect:          A      On high seal cavity temperature ON-I 13 directs reducing speed to maintain temperature this occurs at a cavity temperature of 175OF not ZOOOF Incorrect:                   Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler)
Incorrect:         D       Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler)
I                      I        I Level of     Difficulty   Time Allowance         PRA               RO                     SRO Knowledge                         (minutes)                         10CFR55.41             10CFR55.43 High           2.5                 3               Y               Y (b)(5)                   N Source Documentation Source:                   Ix] New Exam Item                               Previous NRC Exam 0Modified Bank Item                           0Other Exam Bank c]ILT Exam Bank Reference(s):          ON-I 13 step 2.1, S43.0.D Learning              LLOT0030.07b:
0bjective:
KnowledgelAbility 202001                                                Importance: RO / SRO KIA                    A2.17                                                            3.1 13.2 (Description of K&A, from catalog)
Ability to predict the impact of a loss of seal cooling water on the RECIRC system; and based on those predictions use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   lLTO5-1 NRC Initial Licensing Examination 51,   Unit 2 plant conditions are as follows:
2A RECW pump is running with its handswitch in AUTO after START 0 2B RECW pump is off with its handswitch in AUTO after STOP A complete Loss Of Offsite Power (LOOP) occurs.
All 4 KV systems operate as designed with all buses re-energizing SIMULTANEOUSLY.
WHICH ONE of the following describes the response of the RECW pumps?
WHICH ONE of the following describes the response of the RECW pumps?
A. "2A' RECW pump auto re-starts. "2B" RECW pump auto starts in standby. B. "2A RECW pump auto re-starts. "2B" RECW pump does NOT auto start in standby. C. "2A" RECW pump does NOT auto re-start. "2B" RECW pump auto starts in standby. D. "2A RECW pump does NOT auto re-start. "2B" RECW pump does NOT auto start in standby. Page 102 of 200 Limerick Generating Station ILTOS-1 NRC Initial Licensinq Examination A Answer Key When their respective safeguard MCC's re-energized both RECW pumps auto start on low heat exchange outlet pressure Choice Correct: C Incorrect 2A portion of this distractor is incorrect, 2B portion is correct for the reason stated above In correct D Incorrect Both the 2A and 2B portions of this distractor are incorrect as stated above. I Basis or Justification Level of Difficulty Time Allowance PRA RO Knowledge (mi nu tes) 1 OCFR55.41 Low 3.0 3 Y y (W(7) SRO 1 OCFR55.43 N 2A portion of this distractor is correct, 28 portion is incorrect, for the reason stated above Knowledge/Ability K/A 400000 Importance:
A. 2A RECW pump auto re-starts.
RO I SRO K4.01 3.4 / 3.9 Source Documentation Source: Learning Objective:
2B RECW pump auto starts in standby.
New Exam Item Modified Bank Item ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank E-565 LLOT0460.07 Required Materials: Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
B. 2 A RECW pump auto re-starts.
: 52. Unit 1 plant conditions are as follows: 0 Reactor startup is in progress 0 Reactor power is 20% Control rod withdrawal is in progress. WHICH ONE of the following will result in a rod withdraw block? A. RBM upscale B. RBM downscale C. Control rod withdrawn past its withdraw limit D. RDCS Activities Control Disagree condition Page 104 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Incorrect to a malfunction of RMCS A RBM upscale will not result in a rod block as Reactor power is less than 30% Incorrect Incorrect B RBM downscale will not result in a block as Reactor power is less than 30% C CR withdraw will not result in a Rod block as Reactor power is above RWM LPSP (18%) Level of Difficulty Time Allowance PFW RO Knowledge (minutes) 10CFR55.41 Low 3.0 3 Y Y (b)(7) SRO 1 OCFR55.43 N KnowledgelAbility 201 002 WA I K3.02 Source: Reference(s):
2B RECW pump does NOT auto start in standby.
Learning 0 bject ive: Importance:
C. 2A RECW pump does NOT auto re-start.
RO I SRO 2.9 13.2 [XI New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam Other Exam Bank S73.O.B, step 4.2 & note above step, ANN 108 D-4 LLOT0080.06  
2B RECW pump auto starts in standby.
= (Description of K&A, from catalog) Knowledge of the effect that a loss or malfunction of RMCS will have on RBM Required Materials:
D. 2 A RECW pump does NOT auto re-start.
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
2B RECW pump does NOT auto start in standby.
~ _~ Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
Page 102 of 200
: 53. Unit 1 plant conditions are as follows: 0 Reactor "STARTUP" is in progress 0 Reactor power is 12?h Insert limit for current RWM rod group is "00" 0 Withdraw limit for the current RWM rod group is "12" 0 Control rod 10-39 is selected Control rod 10-39, the first rod of the current group, is withdrawn to position "14" with no further operator action taken. WHICH ONE of the following identifies the ability to move control rod 10-39?
 
Limerick Generating Station                         ILTOS-1 NRC Initial Licensinq Examination Answer Key Choice            I                              Basis or Justification Correct:          A    When their respective safeguard MCCs re-energized both RECW pumps auto start on low heat exchange outlet pressure Incorrect                2A portion of this distractor is correct, 28 portion is incorrect, for the reason stated above Incorrect          C     2A portion of this distractor is incorrect, 2B portion is correct for the reason stated above Incorrect          D     Both the 2A and 2B portions of this distractor are incorrect as stated above.
Level of     Difficulty   Time Allowance         PRA                   RO                       SRO Knowledge                     (minutes)                           10CFR55.41                 10CFR55.43 Low           3.0             3                 Y               y (W(7)                       N Source Documentation Source:                   New Exam Item                             0Previous NRC Exam Modified Bank Item                         0Other Exam Bank ILT Exam Bank E-565 Learning              LLOT0460.07 Objective:
Knowledge/Ability 400000                                                Importance:    RO I SRO K/A                    K4.01                                                            3.4 / 3.9 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   ILT05-I NRC Initial Licensinq Examination
: 52. Unit 1 plant conditions are as follows:
0   Reactor startup is in progress 0   Reactor power is 20%
Control rod withdrawal is in progress.
WHICH ONE of the following will result in a rod withdraw block?
A. RBM upscale B. RBM downscale C. Control rod withdrawn past its withdraw limit D. RDCS Activities Control Disagree condition Page 104 of 200
 
Limerick Generating Station                         ILT05-1 NRC Initial Licensing Examination to a malfunction of RMCS Incorrect          A     RBM upscale will not result in a rod block as Reactor power is less than 30%
Incorrect         B     RBM downscale will not result in a block as Reactor power is less than 30%
Incorrect          C     CR withdraw will not result in a Rod block as Reactor power is above RWM LPSP (18%)
Level of     Difficulty   Time Allowance         PFW                 RO                   SRO Knowledge                     (minutes)                         10CFR55.41             10CFR55.43 Low           3.0               3               Y               Y (b)(7)                   N Source:                 [XI New Exam Item                           0Previous NRC Exam 0Modified Bank Item                           Other Exam Bank 0ILT Exam Bank Reference(s):          S73.O.B, step 4.2 & note above step, ANN 108 D-4 Learning              LLOT0080.06 =
0bjective:
WA                  I KnowledgelAbility 201002 K3.02 (Description of K&A, from catalog)
Importance:  RO ISRO 2.9 13.2 Knowledge of the effect that a loss or malfunction of RMCS will have on RBM Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                                                                          ~ _~
Limerick Generating Station                     ILT05-1 NRC Initial Licensinq Examination
: 53. Unit 1 plant conditions are as follows:
0   Reactor STARTUP is in progress 0   Reactor power is 12?h Insert limit for current RWM rod group is 00 0   Withdraw limit for the current RWM rod group is 12 0   Control rod 10-39 is selected Control rod 10-39, the first rod of the current group, is withdrawn to position 14 with no further operator action taken.
WHICH     ONE of the following identifies the ability to move control rod 10-39?
A. Control rod can be withdrawn and inserted without additional actions.
A. Control rod can be withdrawn and inserted without additional actions.
B. Control rod can only be inserted without additional action. C. Control rod insertion capability requires rod to be bypassed in the RWM. D. Control rod insertion or withdraw capability requires a substitute position to be entered into RWM. Page 106 of 200 Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Source Documentation Source: New Exam Item 0 Previous NRC Exam I 0 Modified Bank Item 0 ILT Exam Bank 0 Other Exam Bank Refere n ce(s): Learning LLOT0093f 0 bjective:
B. Control rod can only be inserted without additional action.
ON-I 23 step 2.12 Answer Key Incorrect Incorrect Incorrect A Rod cannot be withdrawn as RWM will enforce a withdraw block C Rod does not need to be bypassed to allow insertion D This is not correct as substitute rod position is only used if there is no position indication Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.0 3 N Y (b)(7) SRO 1 OCFR55.43 N Knowledge/Ability WA Required Materials:
C. Control rod insertion capability requires rod to be bypassed in the RWM.
201 006 Importance:
D. Control rod insertion or withdraw capability requires a substitute position to be entered into RWM.
RO / SRO K4.06 3.2 / 3.4 Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Page 106 of 200
% Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
 
: 54. Unit 1 plant conditions are as follows: 0 0 0 Reactor was scrammed due to a condensate line rupture. Reactor level is  
Limerick Generating Station                       ILT05-I NRC Initial Licensinq Examination Answer Key Incorrect         A   Rod cannot be withdrawn as RWM will enforce a withdraw block Incorrect          C   Rod does not need to be bypassed to allow insertion Incorrect          D   This is not correct as substitute rod position is only used if there is no position indication Level of     Difficulty Time Allowance         PRA                 RO                       SRO Knowledge                   (minutes)                           10CFR55.41                 10CFR55.43 Low           3.0             3               N               Y (b)(7)                     N Source Documentation Source:                  New Exam Item                            0Previous NRC Exam I                        0Modified Bank Item                        0Other Exam Bank 0ILT Exam Bank Reference(s):        ON-I23 step 2.12 Learning            LLOT0093f 0bjective:
-35" and lowering DI 24 safeguard load center transformer breaker tripped on over current The RO is directed to start Standby Liquid Control to augment Reactor level. 0 "1A and "IC" SLC injection pumps are started and verified to be injecting WHICH ONE of the following describes the RWCU system response?
Knowledge/Ability 201006                                            Importance:     RO / SRO WA                  K4.06                                                           3.2 / 3.4 Required Materials:
A. HV-44-1 F004 "RWCU Outboard Suction Valve" closes.
Notes and Comments Prepared By:
B. HV-44-1 FOOI "RWCU Inboard Suction Valve" closes.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
C. HV-44-1 F004 "RWCU Outboard Suction Valve" and HV-44-1 FOOI "RWCU Inboard Suction Valve" close. D. HV-44-1 F040 "RWCU Inlet Suction Valve" closes.
 
Page 108 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Incorrect Answer Kev A ~ Question ID# 054 Both RC Incorrect Choice D Level of Knowledge High IC Incorrect Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 3 N Y (b)(7) N Source: Reference( s): Learning Objective:
% Limerick Generatinq Station                     ILT05-1 NRC Initial Licensing Examination
sm Basis or Justification New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank - LORT GP-8.1, Signal Y LLOTOI 10.05 "A or "C SLC pump start close Fool valve as "B" was not started (D124 is power supply for the '73'' pump) F004 did not close KnowledgelAbility KIA F004 does not close as "B" SLC pump did not start 204000 Importance:
: 54. Unit 1 plant conditions are as follows:
RO I SRO A3.03 3.6 13.6 While Fool did close answer is incorrect as F004 did not close due to "B SLC pump not started F040 does not receive and isolation signal on SLC start I Psvchometrics I Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
0   Reactor was scrammed due to a condensate line rupture.
: 55. Unit 1 plant conditions are as follows: 0 Reactor Power is 100% 0 lAY160 trips due to a ground fault 30 minutes later a Reactor SCRAM and turbine trip occur. 0 Reactor pressure is 900 psig and steady 0 Turbine speed is 300 RPM and dropping WHICH ONE of the following identifies the ability to lower Reactor pressure using the bypass valves?
0    Reactor level is -35 and lowering 0    D I 24 safeguard load center transformer breaker tripped on over current The RO is directed to start Standby Liquid Control to augment Reactor level.
0   1 A and I C  SLC injection pumps are started and verified to be injecting WHICH     ONE of the following describes the RWCU system response?
A. HV-44-1F004 RWCU Outboard Suction Valve closes.
B. HV-44-1FOOI RWCU Inboard Suction Valve closes.
C. HV-44-1F004 RWCU Outboard Suction Valve and HV-44-1FOOI RWCU Inboard Suction Valve close.
D. HV-44-1F040 RWCU Inlet Suction Valve closes.
Page 108 of 200
 
Limerick Generating Station                         ILT05-1 NRC Initial Licensinq Examination Answer Kev sm
  ~
QuestionID# 054 Both RC Choice                                           Basis or Justification Aor  C SLC pump start close Fool valve as B was not started (D124 is power supply for the 73 pump) F004 did not close Incorrect          A    F004 does not close as B SLC pump did not start Incorrect Incorrect IC  D While Fool did close answer is incorrect as F004 did not close due to B SLC pump not started F040 does not receive and isolation signal on SLC start I                                             Psvchometrics                                             I Level of    Difficulty  Time Allowance        PRA                  RO                  SRO Knowledge                    (minutes)                          10CFR55.41          10CFR55.43 High          3.0            3                N                Y (b)(7)                N Source:                  New Exam Item                            0Previous NRC Exam 0Modified Bank Item                          0Other Exam Bank - LORT 0ILT Exam Bank Reference(s):        GP-8.1, Signal Y Learning            LLOTOI10.05 Objective:
KnowledgelAbility 204000                                            Importance: RO I SRO KIA                  A3.03                                                      3.6 13.6 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generatinq Station                   ILT05-1 NRC Initial Licensing Examination
: 55. Unit 1 plant conditions are as follows:
0   Reactor Power is 100%
0   lAY160 trips due to a ground fault 30 minutes later a Reactor SCRAM and turbine trip occur.
0   Reactor pressure is 900 psig and steady 0   Turbine speed is 300 RPM and dropping WHICH ONE of the following identifies the ability to lower Reactor pressure using the bypass valves?
A. Bypass valves cannot be used to control Reactor pressure.
A. Bypass valves cannot be used to control Reactor pressure.
B. Bypass valves can be opened by raising the Bypass Jack. C. Bypass valves can be opened by lowering Pressure Set. D. Bypass valves can be opened by raising Maximum Combined Flow. Page 11 0 of 200 Limerick Generatinq Station ILTO5-1 NRC Initial Licensinn Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 3.0 3 Y Y (b)(7) Answer Key SRO N 1 OCFR55.43 - Question ID# 055 Both RC Reference(s):
B. Bypass valves can be opened by raising the Bypass Jack.
Learning 0 bjective:
C. Bypass valves can be opened by lowering Pressure Set.
Choice 0 ILT Exam Bank E-1AY160 Attachment
D. Bypass valves can be opened by raising Maximum Combined Flow.
#1 LLOT0560.01 Ok Correct: Incorrect Incorrect Incorrect A B C D SR! Basis or Justification Due to Loss of 1AY160 and PMG (Turbine speed 300 RPM) bypass will not operate Bypass jack will not operate due to loss of 1 AY160 Pressure set will not operate due to the loss of 1AY160 Raising max combine flow (1 15%) will not open bypass valves (CV's are closed) Source Documentation Source: I New Exam Item Previous NRC Exam KnowledgelAbility KIA 262002 K3.15 Importance: RO I SRO 2.6 12.7 (Description of K&A, from catalog) Knowledge of the effect that a loss or malfunction of UPS will have on Main Turbine Operation Required Materials: Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination
Page 110 of 200
: 56. A loss of instrument air is in progress on Unit I. "1 A and "1 B" Instrument Air Headers are at 20 psig and lowering.
 
WHICH ONE of the following describes the response of Main Steam system valves? A. Only Outboard MSIVs close. All SRVs can be opened. B. Only Inboard MSlVs close. Only ADS and RSP SRVs can be opened. C. Inboard and Outboard MSlVs close. All SRVs can be opened.
Limerick Generatinq Station                         ILTO5-1 NRC Initial Licensinn Examination Answer Key Question ID# 055 Both RC     SR!
D. Inboard and Outboard MSlVs close. Only ADS and RSP SRVs can be opened Page 112 of 200 Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Low 4.0 3 Y Y (b)(9) Correct: SRO 1 OCFR55.43 N Incorrect I 300000 K1.03 Incorrect Importance:
Choice                                           Basis or Justification Correct:           A     Due to Loss of 1AY160 and PMG (Turbine speed 300 RPM) bypass will not operate Incorrect          B    Bypass jack will not operate due to loss of 1AY160 Incorrect          C    Pressure set will not operate due to the loss of 1AY160 Incorrect          D    Raising max combine flow (115%) will not open bypass valves (CVs are closed)
RO / SRO 2.8 / 2.9 Incorrect D A B C Outboard MSIVs close on loss of instrument air inboard MSlVs close on loss of PClG (PCIG is lost due to loss of Instrument Air Only ADS and RSP SRVs have accumulator and can be opened with Loss of PClG This is incorrect as inboard MSlVs also close. Also non ADS SRVs cannot be opened from handswitches due to loss of PClG This is incorrect as outboard MSlVs also close This is incorrect as non-ADS SRVs cannot be opened from handswitches due to loss of PClG Source: Reference(s):
Level of    Difficulty  Time Allowance        PRA                RO                    SRO Knowledge                    (minutes)                          10CFR55.41            10CFR55.43 -
Learning 0 bjective:
Low          3.0              3                Y              Y (b)(7)                N Source Documentation Source:             I     New Exam Item                               Previous NRC Exam 0ILT Exam Bank Reference(s):          E-1AY160 Attachment #1 Learning              LLOT0560.01Ok 0bjective:
Knowledge/Ability WA Source Documentation
KnowledgelAbility 262002                                             Importance: RO I SRO KIA                    K3.15                                                        2.6 12.7 (Description of K&A, from catalog)
[XI New Exam Item 0 Modified Bank Item 0 ILT Exam Bank ON-I 19 Attachment 1 L LOT0730.08 0 Previous NRC Exam Other Exam Bank (Description of K&A, from catalog) Knowledge of the connections and/or cause effect relationships between instrument air and containment air Required Materials:
Knowledge of the effect that a loss or malfunction of UPS will have on Main Turbine Operation Required Materials:
Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination
Notes and Comments Prepared By:
: 57. Unit 1 plant conditions are as follows: 0 An ATWS is in progress 0 Reactor power is 40% and steady 0 Reactor level is -60" and steady A turbine trip occurs; and Reactor power remains at 40%. WHICH ONE of the following identifies conditions that will result in a RRCS feedwater runback, and when the runback will occur? A. Reactor pressure 1160 psig. Runback occurs in 11 8 seconds. B. Reactor pressure 1160 psig. Runback occurs in 25 seconds. C. Reactor pressure 1096 psig. Runback occurs in 30 seconds. D. Reactor pressure 1096 psig. Runback occurs in 9 seconds. Page 114 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PFW RO Knowledge (mi nu tes) lOCFR55.41 HIGH 3.0 3 Y NIA Answer Kev SRO 1 OCFR55.43 NIA Reactor pressure 1096 is incorrect (1 096 is the Reactor Scram setpoint) additionally 30 seconds is the Feedwater runback length once initiated Ici Incorrect Source: Reference(s):
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Learning Objective: Reactor pressure 1096 is incorrect additionally 9 seconds is incorrect (9 seconds is the RRCS Recirc pump RPT Breaker time delay) iDi Incorrect New Exam Item Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank GE Elementary Drawing G31-I 020 LLOT0315.04 ARC 004, B-4 KnowledgelAbility WA 21 6000 Importance:
 
RO / SRO 2.4.50 3.3 13.3 Required Materials:
Limerick Generatinq Station                     ILT05-I NRC Initial Licensing Examination
Notes and Comments: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station  
: 56. A loss of instrument air is in progress on Unit I.
~ ILT05-1 NRC Initial Licensing Examination
1A and 1B Instrument Air Headers are at 20 psig and lowering.
: 58. WHICH ONE of the following lists contains ONLY Non-Safeguard DC System loads? A. Turbine Enclosure Area Rad Monitors Refuel Floor HVAC Isolation logic Primary RPS/UPS Inverter Power Recirc MG Set Emergency Lube Oil Pumps B. 13.2 KV Breaker Control Power Main Control Room Annunciator Emergency Lighting Panels Primary RPS/UPS inverter Power C. Primary APRM Inverter Power Reactor Enclosure HVAC Isolation logic 4KV Breaker Control Power RFP Emergency Lube Oil Pumps D. Recirc MG Set Emergency Lube Oil Pumps Primary APRM Inverter Power Emergency Lighting Panels Main Control Room Annunciator Page 11 6 of 200 Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination Incorrect: Answer Key A Question ID# 058 Both RC Incorrect:
WHICH ONE of the following describes the response of Main Steam system valves?
Choice C ID Correct: Level of Difficulty Time Allowance Knowledge (minutes)
A. Only Outboard MSIVs close.
Low 3.0 3 PRA RO SRO 1 OCFR55.41 I OCFR55.43 Y (b) (7) N Incorrect:  
All SRVs can be opened.
---I 263000 K2.01 Importance:
B. Only Inboard MSlVs close.
RO / SRO 3.1 / 3.4 Basis or Justification All 4 loads are Now Safeguard DC Refuel Floor HVAC isolation logic and Primary RPS/UPS Inverter Power are Safeguard DC loads Primary RPS/UPS inverter Power is a Safeguard DC load Reactor Enclosure HVAC Isolation logic and 4KV Breaker Control Power are Safeguard DC loads Source: Reference(s):
Only ADS and RSP SRVs can be opened.
Learning 0 bject ive: Knowledge/Ability KIA Source Documentation New Exam Item Modified Bank Item ILT Exam Bank 0 Previous NRC Exam Other Exam Bank E-33, Sh 1-3 E-619, Sh 1-3 LLOT0690.04 (Description of K&A, from catalog) Knowledge of electrical power supplies to the following:
C. Inboard and Outboard MSlVs close.
Major DC loads Required Materials:
All SRVs can be opened.
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
D. Inboard and Outboard MSlVs close.
- Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
Only ADS and RSP SRVs can be opened Page 112 of 200
 
Limerick Generating Station                         ILT05-I NRC Initial Licensinq Examination Correct:         D     Outboard MSIVs close on loss of instrument air inboard MSlVs close on loss of PClG (PCIG is lost due to loss of Instrument Air Only ADS and RSP SRVs have accumulator and can be opened with Loss of PClG I    Incorrect          A    This is incorrect as inboard MSlVs also close. Also non ADS SRVs cannot be opened from handswitches due to loss of PClG Incorrect          B    This is incorrect as outboard MSlVs also close Incorrect          C    This is incorrect as non-ADS SRVs cannot be opened from handswitches due to loss of PClG Level of    Difficulty  Time Allowance          PRA                RO                    SRO Knowledge                      (minutes)                         10CFR55.41              10CFR55.43 Low          4.0               3                Y            Y (b)(9)                  N Source Documentation Source:                [XI New Exam Item                         0Previous NRC Exam 0Modified Bank Item                           Other Exam Bank 0ILT Exam Bank Reference(s):        ON-I 19 Attachment 1 Learning            LLOT0730.08 0bjective:
Knowledge/Ability 300000                                            Importance: RO / SRO WA                    K1.03                                                        2.8 / 2.9 (Description of K&A, from catalog)
Knowledge of the connections and/or cause effect relationships between instrument air and containment air Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   lLTO5-1 NRC Initial Licensinq Examination
: 57. Unit 1 plant conditions are as follows:
0   An ATWS is in progress 0   Reactor power is 40% and steady 0 Reactor level is -60 and steady A turbine trip occurs; and Reactor power remains at 40%.
WHICH ONE of the following identifies conditions that will result in a RRCS feedwater runback, and when the runback will occur?
A. Reactor pressure 1160 psig.
Runback occurs in 118 seconds.
B. Reactor pressure 1160 psig.
Runback occurs in 25 seconds.
C. Reactor pressure 1096 psig.
Runback occurs in 30 seconds.
D. Reactor pressure 1096 psig.
Runback occurs in 9 seconds.
Page 114 of 200
 
Limerick Generating Station                         ILT05-1 NRC Initial Licensing Examination Answer Kev Incorrect Ici      Reactor pressure 1096 is incorrect (1096 is the Reactor Scram setpoint) additionally 30 seconds is the Feedwater runback length once initiated Incorrect iDi      Reactor pressure 1096 is incorrect additionally 9 seconds is incorrect (9 seconds is the RRCS Recirc pump RPT Breaker time delay)
Level of    Difficulty  Time Allowance        PFW              RO                      SRO Knowledge                      (minutes)                        10CFR55.41              10CFR55.43 HIGH          3.0              3              Y                NIA                      NIA Source:                    New Exam Item                           0Previous NRC Exam Modified Bank Item                     0Other Exam Bank 0ILT Exam Bank Reference(s):        GE Elementary Drawing G31-I020 ARC 004, B-4 Learning              LLOT0315.04 Objective:
KnowledgelAbility 216000                                            Importance:     RO / SRO WA                    2.4.50                                                       3.3 13.3 Required Materials:
Notes and Comments:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station ~
ILT05-1 NRC Initial Licensing Examination
: 58. WHICH ONE of the following lists contains ONLY Non-Safeguard DC System loads?
A. Turbine Enclosure Area Rad Monitors Refuel Floor HVAC Isolation logic Primary RPS/UPS Inverter Power Recirc MG Set Emergency Lube Oil Pumps B. 13.2 KV Breaker Control Power Main Control Room Annunciator Emergency Lighting Panels Primary RPS/UPS inverter Power C. Primary APRM Inverter Power Reactor Enclosure HVAC Isolation logic 4KV Breaker Control Power RFP Emergency Lube Oil Pumps D. Recirc MG Set Emergency Lube Oil Pumps Primary APRM Inverter Power Emergency Lighting Panels Main Control Room Annunciator Page 116 of 200
 
Limerick Generating Station                       ILTO5-1 NRC Initial Licensing Examination Answer Key Question ID# 058 Both RC Choice                                         Basis or Justification Correct:
Incorrect:
ID  A All 4 loads are Now Safeguard DC Refuel Floor HVAC isolation logic and Primary RPS/UPS Inverter Power are Safeguard DC loads
  ---  Incorrect:
Incorrect:          C Primary RPS/UPS inverter Power is a Safeguard DC load Reactor Enclosure HVAC Isolation logic and 4KV Breaker Control Power are Safeguard DC loads Level of    Difficulty  Time Allowance        PRA                RO                  SRO Knowledge                      (minutes)                         10CFR55.41            IOCFR55.43 Low          3.0               3            Y                (b) (7)                N Source Documentation Source:                    New Exam Item                         0Previous NRC Exam Modified Bank Item                         Other Exam Bank ILT Exam Bank Reference(s):        E-33, Sh 1-3 E-619, Sh 1-3 Learning              LLOT0690.04 0bjective:
Knowledge/Ability 263000                                            Importance: RO / SRO KIA                    K2.01                                                    3.1 / 3.4 (Description of K&A, from catalog)
Knowledge of electrical power supplies to the following: Major DC loads Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                  -
Limerick Generatinq Station                 ILT05-1 NRC Initial Licensinq Examination
: 59. WHICH ONE of the following describes the reason Drywell Vacuum Relief Valves open?
: 59. WHICH ONE of the following describes the reason Drywell Vacuum Relief Valves open?
A. Prevent drawing excess negative pressure in the Drywell. B. Prevent drawing excess negative pressure in the Suppression Pool. C. Equalize pressure between the SRV Downcomer and the Suppression Pool. D. Ensure the Suppression Pool pressure remains higher than Drywell pressure.
A. Prevent drawing excess negative pressure in the Drywell.
Page 11 8 of 200 Limerick Generatinq Station I LT05-1 NRC Initial Licensing Examination Incorrect Incorrect Answer Key B Vacuum Breaker Operate on to ensure Drywell is not drawn negative C While some equalization will occur when Vacuum Breaker opens it is not the reason they open Choice I Basis or Justification Level of Difficulty Time Allowance PRA . RO Knowledge (minutes) 1 OCFR55.41 Low 3.0 3 Y Y (b)(5) Vacuum Breakers Relief's will open on Drywell Pressure lower than Suppression Pool Pressure Correct: SRO 1 OCFR55.43 N 223001 K5.01 The exact opposite is true, as Vacuum Breakers relieve the higher Suppression Pool pressure to the Drywell. Incorrect Importance:
B. Prevent drawing excess negative pressure in the Suppression Pool.
RO / SRO 3.1 / 3.3 Source: Reference( s): Learning 0 bjective:
C. Equalize pressure between the SRV Downcomer and the Suppression Pool.
Knowledge/Ability WA Source Documentation New Exam Item 0 Modified Bank Item [XI ILT Exam Bank Previous NRC Exam 0999#119 0 Other Exam Bank ANN 114 G-I LLOTOI 30.02f (Description of K&A, from catalog)
D. Ensure the Suppression Pool pressure remains higher than Drywell pressure.
Knowledge of the Operational implications of Vacuum Breaker/relief operations as applies to Primary Containment system and auxiliaries Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
Page 118 of 200
 
Limerick Generatinq Station                         ILT05-1 NRC Initial Licensing Examination Answer Key Choice            I                              Basis or Justification Correct:                  Vacuum Breakers Relief's will open on Drywell Pressure lower than Suppression Pool Pressure Incorrect          B     Vacuum Breaker Operate on to ensure Drywell is not drawn negative Incorrect          C     While some equalization will occur when Vacuum Breaker opens it is not the reason they open Incorrect                The exact opposite is true, as Vacuum Breakers relieve the higher Suppression Pool pressure to the Drywell.
Level of     Difficulty   Time Allowance       PRA             . RO                   SRO Knowledge                       (minutes)                         10CFR55.41             10CFR55.43 Low           3.0               3               Y               Y (b)(5)                 N Source Documentation Source:                     New Exam Item                               Previous NRC Exam 0999#119 0Modified Bank Item                          0Other Exam Bank
[XI ILT Exam Bank Reference(s):        ANN 114 G-I Learning              LLOTOI30.02f 0bjective:
Knowledge/Ability 223001                                              Importance: RO / SRO WA                    K5.01                                                        3.1 / 3.3 (Description of K&A, from catalog)
Knowledge of the Operational implications of Vacuum Breaker/relief operations as applies to Primary Containment system and auxiliaries Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                 ILT05-1 NRC Initial Licensing Examination
: 60. Unit 1 is at 100% power when the following alarm is received:
: 60. Unit 1 is at 100% power when the following alarm is received:
IDB-1 250V DC MCC UNDERVOLTAGE (122 G-2) WHICH ONE of the following identifies the system that is no longer operable, and the required action? A. ADS, station an Equipment Operator in the AER for SRV operation.
IDB-1 250V DC MCC UNDERVOLTAGE (122 G-2)
B. RPS, stop all "B" side RPS testing. C. HPCI, declare HPCI INOPERABLE per Technical Specification. D. RCIC, perform T-249 for RCIC. Page 120 of 200 Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination Correct: Incorrect:
WHICH ONE of the following identifies the system that is no longer operable, and the required action?
C HPCl is INOP due to loss of power to initiation logic and MOV's on a loss of Div 2 DC, HPCl should be declared INOP as a result of the loss of initiation logic ADS is supplied by Div 1 and Div 3 DC A Incorrect:
A. ADS, station an Equipment Operator in the AER for SRV operation.
r B While "B" RPS will swap to its AC power source, it is still operable I Incorrect:
B. RPS, stop all Bside RPS testing.
D RClC is supplied by Div 1 and Div 3 DC Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 10CFR55.41 Low 3.5 3 Y Y (b) (IO) Source: SRO 10CFR55.43 N Reference(s):
C. HPCI, declare HPCI INOPERABLE per Technical Specification.
Learning Objective:
D. RCIC, perform T-249 for RCIC.
Knowledge/Ability WA Source Documentation New Exam Item Modified Bank Item ILT Exam Bank [7 Previous NRC Exam 0 Other Exam Bank ARC-MCR-122 G2, ARC MCR-117 AI LLOT0690.02 263000 2.4.31 Importance:
Page 120 of 200
RO I SRO 3.3 13.4 (Description of K&A, from catalog) DC Electrical Distribution:
 
Knowledge of annunciators alarms and indicationsland use of the response instructions Required Materials:
Limerick Generating Station                         lLTO5-1 NRC Initial Licensinq Examination Correct:           C     HPCl is INOP due to loss of power to initiation logic and MOVs on a loss of Div 2 DC, HPCl should be declared INOP as a result of the loss of initiation logic Incorrect:          A      ADS is supplied by Div 1 and Div 3 DC r    Incorrect:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
Incorrect:
: 61. WHICH ONE of the following identifies values for both frequency and voltage that will satisfy the requirement for a diesel generator breaker to automatically close in on its associated bus? Frequency Voltaqe A. 56.2 Hz 4.1 KV B. 57.4 Hz 4.0 KV C. 58.6 Hz 3.9 KV D. 59.8 Hz 3.8 KV Page 122 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Correct: Incorrect Incorrect Answer Key B A C Question ID# 061 Both RC Level of Difficulty Time Allowance PRA HIGH 3.5 4 Y Knowledge (minutes)
B D
RO SRO 1 OCFR55.41 1 OCFR55.43 Y (b) (7) N ID Incorrect 264000 A3.03 SQ>Q Basis or Justification Importance:
I While B RPS will swap to its AC power source, it is still operable RClC is supplied by Div 1 and Div 3 DC Level of     Difficulty   Time Allowance       PRA                 RO                       SRO Knowledge                       (minutes)                       10CFR55.41                 10CFR55.43 Low           3.5               3             Y             Y (b) (IO)                     N Source Documentation Source:                     New Exam Item                          [7 Previous NRC Exam Modified Bank Item                      0Other Exam Bank ILT Exam Bank Reference(s):         ARC-MCR-122 G2, ARC MCR-117 A I Learning               LLOT0690.02 Objective:
RO / SRO 3.4 J3.4 Frequency and Voltage are required to be 95% of rated in order to energize the Diesel Ready to Load relay and close the output Breaker. These values would be 57 Hz and 3.952 KV Voltage meets the requirement, Frequency does not Frequency meets the requirement, voltage does NOT Frequency meets the requirement, voltage does not Source: Reference(s):
Knowledge/Ability 263000                                              Importance: RO ISRO WA                     2.4.31                                                        3.3 13.4 (Description of K&A, from catalog)
Learning 0 bj ect ive : Knowledg eJAbility WA Source Documentation New Exam Item Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank E-I 64 LLOT0670.02. LLOT0660.04 (Description of K&A, from catalog) Ability to monitor automatic operations of the Emergency Generators including: Indicating lights, meters and recorders Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
DC Electrical Distribution: Knowledge of annunciators alarms and indicationslanduse of the response instructions Required Materials:
: 62. Unit 1 conditions are as follows: 0 Reactor is shutdown 0 Drywell pressure is 12 psig and steady 0 Reactor pressure is 430 psig and steady "1A RHR is placed in Suppression Pool Spray. Reactor pressure drops to 280 psig DIV 1 LPCl INJECTION VALVE DELTA P PERMISSIVE (I 13A F4) annunciator is in alarm WHICH ONE of the following identifies the response of "IA" RHR? A. Suppression Pool Spray automatically isolates and can be immediately re-established.
Notes and Comments Prepared By:
B. Suppression Pool Spray automatically isolates and cannot be re- established until "IA LPCl Injection Valve is closed. C. Suppression Pool Spray remains in service and must be manually secured to prevent pump runout. D. Suppression Pool Spray remains in service and "IA" LPCl injection valve remains closed. Page 124 of 200 Limer/ck Generating Station ILTO5-I NRC Initial Licensing Examination Incorrect Answer Key A Question ID# 062 Both RC Incorrect Incorrect Choice B D Correct: Level of Difficulty Time Allowance PRA RO Knowledge (mi nu tes) 10CFR55.41 Low 4.0 3 Y y (b)(7) C SRO I OCFR55.43 230000 A4.02 Importance:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
RO / SRO 3.8/ 3.6 I Basis or Justification LPCl Injection valve opens (Delta P ANN) as Suppression Pool Spray was placed in service after LPCl initiation signal was present (LOCA signal) it will not automatically isolate and must be manually secured to prevent pump runout with LPCl Injection valve open This is incorrect as spray does not isolate (LOCA) signal received previously) additionally, it cannot be re-established until LPCl injection valve is closed This is incorrect as spray does not isolate (LOCA signal received previously)  
 
~ This is incorrect as LPCl injection valve will open (Delta P ANN) + Source: L Objective:
Limerick Generating Station                      ILT05-1 NRC Initial Licensinq Examination
Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank c] Previous NRC Exam 0 Other Exam Bank ARC-MCR-113 F4, T-225 step 4.2.2 LLOT0370.09 b (Description of K&A, from catalog) Ability to manually operate and/or monitor in the control Room. Spray valves Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination ATTACHMENT:
: 61.       WHICH ONE of the following identifies values for both frequency and voltage that will satisfy the requirement for a diesel generator breaker to automatically close in on its associated bus?
ON-I 26 Provided 63. Unit 1 generator load has been raised in support of a PJM Grid Emergency.
Frequency             Voltaqe A.         56.2 Hz             4.1 KV B.         57.4 Hz             4.0KV C.         58.6 Hz             3.9 KV D.         59.8 Hz             3.8 KV Page 122 of 200
Unit I Main Generator conditions are as follows: 1175MWe 0 230 MVAR's (lagging)
 
Subsequently, I GEN HYDROGEN AND SEAL OIL SYS TROUBLE ALARM annunciates at 125 GEN. An EO is dispatched and reports that generator hydrogen pressure is 60 psig and steady. WHICH ONE of the following describes the required action(s)?
Limerick Generating Station                     ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 061 Both RC     SQ>Q Basis or Justification Correct:          B    Frequency and Voltage are required to be 95% of rated in order to energize the Diesel Ready to Load relay and close the output Breaker. These values would be 57 Hz and 3.952 KV Incorrect          A    Voltage meets the requirement, Frequency does not Incorrect         C    Frequency meets the requirement, voltage does NOT Incorrect ID      Frequency meets the requirement, voltage does not Level of    Difficulty  Time Allowance        PRA                RO                   SRO Knowledge                    (minutes)                      10CFR55.41              10CFR55.43 HIGH          3.5              4             Y              Y (b) (7)                  N Source Documentation Source:                  New Exam Item                          0Previous NRC Exam Modified Bank Item                    0Other Exam Bank 0ILT Exam Bank Reference(s):        E-I64 Learning              LLOT0670.02. LLOT0660.04 0bjective:
A. Raise hydrogen pressure to 65 psig. B. Reduce generator output below I 125 MWe. C. Reduce reactive load to 200 MVAR's lagging. D. Perform a GP-4 Shutdown, trip the Main Turbine. Page 126 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
KnowledgeJAbility 264000                                            Importance: RO / SRO WA                    A3.03                                                      3.4 J3.4 (Description of K&A, from catalog)
I OCFR55.41 High 3.5 4 N Y (b)(5) Answer Key SRO 1 OCFR55.43 N Choice Correct: Source: Reference(s):
Ability to monitor automatic operations of the Emergency Generators including: Indicating lights, meters and recorders Required Materials:
Learning 0 bjective:
Notes and Comments Prepared By:
Knowledge/Ability WA Incorrect:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
New Exam Item 0 Modified Bank Item 0 ILT Exam Bank ON-126, Attachment 1 LLOT0600.10 Previous NRC Exam Other Exam Bank 245000 Importance:
 
RO / SRO AI .Ol 2.7 / 2.7 Incorrect:
Limerick Generatinq Station                    ILT05-1 NRC Initial Licensing Examination
: 62. Unit 1 conditions are as follows:
0   Reactor is shutdown 0  Drywell pressure is 12 psig and steady 0  Reactor pressure is 430 psig and steady 1 A RHR is placed in Suppression Pool Spray.
Reactor pressure drops to 280 psig DIV 1 LPCl INJECTION VALVE DELTA P PERMISSIVE
( I 13A F4) annunciator is in alarm WHICH ONE of the following identifies the response of  I A  RHR?
A. Suppression Pool Spray automatically isolates and can be immediately re-established.
B. Suppression Pool Spray automatically isolates and cannot be re-established until  I A LPCl Injection Valve is closed.
C. Suppression Pool Spray remains in service and must be manually secured to prevent pump runout.
D. Suppression Pool Spray remains in service and I A  LPCl injection valve remains closed.
Page 124 of 200
 
Limer/ck Generating Station                          ILTO5-I NRC Initial Licensing Examination Answer Key Question ID# 062 Both RC Choice                                          Basis or Justification Correct:          C    LPCl Injection valve opens (Delta P ANN) as Suppression Pool Spray was placed in service after LPCl initiation signal was present (LOCA signal) it will not automatically isolate and must be manually secured to prevent pump runout with LPCl Injection valve open Incorrect         A   This is incorrect as spray does not isolate (LOCA) signal received previously) additionally, it cannot be re-established until LPCl injection valve is closed Incorrect          B    This is incorrect as spray does not isolate (LOCA signal received previously)
                                ~
Incorrect          D    This is incorrect as LPCl injection valve will open (Delta P ANN)
I Level of    Difficulty  Time Allowance          PRA                  RO                    SRO Knowledge                      (minutes)                          10CFR55.41              IOCFR55.43
+
Low          4.0              3                Y                y (b)(7)
Source Documentation Source:                  New Exam Item                              c]Previous NRC Exam L                        0Modified Bank Item 0ILT Exam Bank ARC-MCR-113 F4, T-225 step 4.2.2 0Other Exam Bank LLOT0370.09b Objective:
230000                                          Importance:  RO / SRO A4.02                                                          3.8/ 3.6 (Description of K&A, from catalog)
Ability to manually operate and/or monitor in the control Room. Spray valves Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generatinq Station                  ILT05-1 NRC Initial Licensing Examination ATTACHMENT: ON-I 26 Provided
: 63. Unit 1 generator load has been raised in support of a PJM Grid Emergency.
Unit IMain Generator conditions are as follows:
1175MWe 0  230 MVAR's (lagging)
Subsequently, IGEN HYDROGEN AND SEAL OIL SYS TROUBLE ALARM annunciates at 125 GEN.
An EO is dispatched and reports that generator hydrogen pressure is 60 psig and steady.
WHICH ONE of the following describes the required action(s)?
A. Raise hydrogen pressure to 65 psig.
B. Reduce generator output below I125 MWe.
C. Reduce reactive load to 200 MVAR's lagging.
D. Perform a GP-4 Shutdown, trip the Main Turbine.
Page 126 of 200
 
Limerick Generating Station                        ILT05-1 NRC Initial Licensing Examination Answer Key Choice                                          Basis or Justification Correct:           B    Reduction in real load to less than 1125 MWe will restore the MW /MWe output to a value consistent with the 60 psig H2heating curve.
Incorrect:          A    H2Pressure would have to be restored to 75 psig in order to restore the MW/MWe output to within the armature heating curve.
Incorrect:          C    Reducing MVAR will not reduce the MW/MWe output to within the armature heating curve.
Incorrect:          D    A GP-4 Shutdown and trip of the Main Turbine would only be required if Hydrogen Pressure could not be maintained above 55 psig.
Level of    Difficulty  Time Allowance        PRA                RO                    SRO Knowledge                    (minutes)                          IOCFR55.41              10CFR55.43 High          3.5            4               N                Y (b)(5)                  N Source:                  New Exam Item                                Previous NRC Exam 0Modified Bank Item                            Other Exam Bank 0ILT Exam Bank Reference(s):        ON-126, Attachment 1 Learning              LLOT0600.10 0bjective:
Knowledge/Ability 245000                                            Importance:  RO / SRO WA                    AI.Ol                                                        2.7 / 2.7 Required Materials:
ON-126 Notes and Comments Prepared By:
Rick Rhode (61 0) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                    ILT05-1 NRC Initial Licensinq Examination
: 64. Unit 1 plant conditions are as follows:
0   Reactor power is 100%
A failure of 1BY 185 occurs.
WHICH ONE of the following identifies the status of APRM and RPS?
APRMS                    -
RPS A.       Indicating 0% Power          Full Scram B. Indicating 100% Power        Half Scram ONLY C.       Failed Downscale          Full Scram D.       Failed Downscale          Half Scram ONLY Page 128 of 200
 
Limerick Generating Station                        ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 064 Both RC Choice                                          Basis or Justification Correct:           B    APRMs power supply is auctioneered, therefore, APRMs are still indicating on a loss of IBY185. Loss of 1BY185 also results in a K SCRAM due to loss of power to 2 PRNMS voter units.
Incorrect          A    While APRMs would be indicating, this is incorrect because a full scram would not occur.
                              ~~
Incorrect          C    This is incorrect because it requires a loss of both I A Y I85 and 1BY185 for the APRMs to fail downscale. In addition, a full scram would not occur.
Incorrect          D    While a half scram would occur, this is incorrect because it requires a loss of both 1AY185 and 1BY185 for the APRMs to fail downscale.
Level of    Difficulty  Time Allowance          PRA                RO                      SRO Knowledge                      (minutes)                        10CFR55.41                10CFR55.43 High          3.5                3                N              Y (b)(7)                    N Source Documentation New Exam Item                            0Previous NRC Exam 0Modified Bank Item                            Other Exam Bank ILT Exam Bank ANN 123 F-5, ANN 108 D-4, ANN 108 A-I LLOT0275.I3c Objective:
I Knowledge/Ability 215002 K2.03 (Description of K&A, from catalog)
                                              ~~~~              ~~ ~
Importance:    RO I SRO 2.8 12.9 Knowledge of electrical power supplies to the APRM channels Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                  ILT05-1 NRC Initial Licensing Examination
: 65. Plant conditions are as follows:
0  Control Room Ventilation system is operating in the normal mode A control room intake high radiation isolation signal is received on the ID channel ONLY.
WHICH ONE of the following describes the subsequent Control Room Ventilation system status?
CREFAS FAN RUNNING            OUTSIDE AIR ENTERING MCR A.              OA                                Yes B.              OA                                No C.              OB                                Yes D.              OB                                No Page 130 of 200
 
Limerick Generatinq Station                              ILTO5-I NRC Initial Licensina Examination Answer Key Question ID# 065 Both RC rFRq Choice                                                Basis or Justification Correct:
I D        D RAD Signal will start the OB Fan and result in normal CR ventilation isolation. It will not lineup the correct dampers to supply outside air to the MCR (Additional channel isolations needed)
Incorrect:
IA        Outside air will not be lined up as correct dampers to supply outside air to MCR are not opened on a D only isolation signal also OA Fan will not start on a D RAD signal
    ~~~
Incorrect:
Incorrect:
B A C D Basis or Justification Reduction in real load to less than 1125 MWe will restore the MW /MWe output to a value consistent with the 60 psig H2 heating curve. H2 Pressure would have to be restored to 75 psig in order to restore the MW/MWe output to within the armature heating curve. Reducing MVAR will not reduce the MW/MWe output to within the armature heating curve. A GP-4 Shutdown and trip of the Main Turbine would only be required if Hydrogen Pressure could not be maintained above 55 psig. Required Materials:
ON-126 Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
: 64. Unit 1 plant conditions are as follows: 0 Reactor power is 100% A failure of 1 BY 185 occurs. WHICH ONE of the following identifies the status of APRM and RPS? APRM'S - RPS A. Indicating 0% Power Full Scram B. Indicating 100% Power Half Scram ONLY C. Failed Downscale Full Scram D. Failed Downscale Half Scram ONLY Page 128 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge Answer Key Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 Question ID# 064 Both RC High Choice Correct: 3.5 3 N Y (b)(7) N Incorrect Incorrect Incorrect B A C D Basis or Justification APRM's power supply is auctioneered, therefore, APRM's are still indicating on a loss of I BY185. Loss of 1 BY1 85 also results in a K SCRAM due to loss of power to 2 PRNMS voter units.
While APRM's would be indicating, this is incorrect because a full scram would not occur. ~~ This is incorrect because it requires a loss of both IAYI 85 and 1 BY185 for the APRM's to fail downscale.
In addition, a full scram would not occur. While a half scram would occur, this is incorrect because it requires a loss of both 1AY185 and 1BY185 for the APRM's to fail downscale.
Objective: Source Documentation New Exam Item 0 Modified Bank Item ILT Exam Bank 0 Previous NRC Exam Other Exam Bank ANN 123 F-5, ANN 108 D-4, ANN 108 A-I LLOT0275.
I 3c Knowledge/Ability I 21 5002 K2.03 Importance: RO I SRO 2.8 12.9 ~~~~ ~~ ~ (Description of K&A, from catalog) Knowledge of electrical power supplies to the APRM channels Required Materials:
Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
: 65. Plant conditions are as follows: 0 Control Room Ventilation system is operating in the normal mode A control room intake high radiation isolation signal is received on the 'ID" channel ONLY. WHICH ONE of the following describes the subsequent Control Room Ventilation system status? CREFAS FAN RUNNING OUTSIDE AIR ENTERING MCR A. "OA Yes B. "OA No C. "OB" Yes D. "OB" No Page 130 of 200 Limerick Generatinq Station ILTO5-I NRC Initial Licensina Examination
~~~ Incorrect:
Question ID# 065 Both RC C Choice Level of Difficulty Time Allowance PRA RO 1 OCFR55.41 Knowledge (minutes)
ID Correct: SRO 1 OCFR55.43 Answer Key rFRq Basis or Justification "D" RAD Signal will start the OB Fan and result in normal CR ventilation isolation.
It will not lineup the correct dampers to supply outside air to the MCR (Additional channel isolations needed) Outside air will not be lined up as correct dampers to supply outside air to MCR are not opened on a "D" only isolation signal also OA Fan will not start on a "D" RAD signal OA Fan will not start on a "D" RAD signal 290003 K4.01 IA Incorrect:
Importance:
RO / SRO 3.1 / 3.2 lB Incorrect:
Same text as "A distractor Source: I 0 bjective:
Source Documentation
[XI New Exam Item 0 Modified Bank Item ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank P&ID M-26 sht 5 detail "D", M-78 sht 1 LLOT0450.7a Knowledge/Ability KIA (Description of K&A, from catalog) Knowledge of Control Room HVAC: design features and/or interlocks which provide for system initiationdreconfiguration Recirculation System Required Materials:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author 
- Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
: 66. Unit 1 plant conditions are as follows: 0 Div II DC is deenergized 0 A digital feedwater malfunction is causing RPV level control problems 0 A GP-4 shutdown is performed Following the scram, RPV level drops and is automatically restored by RCIC. WHICH ONE of the following describes the status of the "IA" and "1 B" Reactor Recirc Pumps? "IA' Recirc Pump "1 B" Recirc Pump A. Running Running B. Running Tripped C. Tripped Running D. Tripped Tripped Page 132 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO HIGH 3.5 4 Y N Knowledge (minutes) 1 OCFR55.41 Correct: SRO 1 OCFR55.43 Y (b)( 5) Incorrect:
r Incorrect:
Incorrect:
Incorrect:
D A B C Basis or Justification RPT breaker logic will normally trip both RPT's on -38. RClC auto start indicates this parameter is reached. The loss of Div II DC will prevent one RPT breaker per pump from tripping, but the other one will trip and therefore, both pumps will be deenergized.
lB  C OA Fan will not start on a D RAD signal Same text as  A distractor Level of      Difficulty    Time Allowance            PRA                RO                    SRO Knowledge                        (minutes)                            10CFR55.41            10CFR55.43 I
Neither pump will be running due to RPT breakers for both pumps tripping The "I B" will be tripped, however the "1A will also be tripped. The "1A will be tripped, however the "1 B" will also be tripped.
Source Documentation Source:                  [XI New Exam Item                                0Previous NRC Exam 0Modified Bank Item                              0Other Exam Bank ILT Exam Bank P&ID M-26 sht 5 detail D, M-78 sht 1 LLOT0450.7a 0bjective:
Source: Reference( s): Learning Objective:
Knowledge/Ability 290003                                                    Importance: RO / SRO KIA                    K4.01                                                            3.1 / 3.2 (Description of K&A, from catalog)
Knowledge/Ability KIA Source Documentation HNew Exam Item OModified Bank Item 0 ILT Exam Bank Previous NRC Exam 0 Other Exam Bank (LOR) E-I FB, ARC MCR 11 I C-5, ARC MCR 11 2 D-3, GP-18, step 1 .O LLOT0315.06 2.4.21 I Importance:
Knowledge of Control Room HVAC: design features and/or interlocks which provide for system initiationdreconfiguration Recirculation System Required Materials:
RO / SRO 3.7/ 4.3 (Description of K&A, from catalog) Knowledge of the parameters and logic used to assess the status of safety functions iquired Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                    ILT05-1 NRC Initial Licensinq Examination
: 66. Unit 1 plant conditions are as follows:
0  Div II DC is deenergized 0  A digital feedwater malfunction is causing RPV level control problems 0  A GP-4 shutdown is performed Following the scram, RPV level drops and is automatically restored by RCIC.
WHICH ONE of the following describes the status of the IA and 1B Reactor Recirc Pumps?
I A Recirc Pump          1B Recirc Pump A.          Running                  Running B.          Running                  Tripped C.          Tripped                  Running D.          Tripped                  Tripped Page 132 of 200
 
Limerick Generatinq Station                          ILT05-1 NRC Initial Licensinq Examination Basis or Justification Correct:          D    RPT breaker logic will normally trip both RPTs on -38. RClC auto start indicates this parameter is reached. The loss of Div II DC will prevent one RPT breaker per pump from tripping, but the other one will trip and r
therefore, both pumps will be deenergized.
Incorrect:          A    Neither pump will be running due to RPT breakers for both pumps tripping Incorrect:          B    The I B will be tripped, however the 1 A will also be tripped.
Incorrect:          C    The 1 A will be tripped, however the 1B will also be tripped.
Level of      Difficulty  Time Allowance            PRA                RO                      SRO Knowledge                      (minutes)                          10CFR55.41                10CFR55.43 HIGH          3.5              4                Y                  N                      Y (b)(5)
Source Documentation Source:                  HNew Exam Item                                 Previous NRC Exam OModified Bank Item                         0Other Exam Bank (LOR) 0ILT Exam Bank Reference(s):        E-I FB, ARC MCR 11IC-5, ARC MCR 112 D-3, GP-18, step 1.O Learning              LLOT0315.06 Objective:
Knowledge/Ability 2.4.21                                               I Importance: RO / SRO KIA                                                                                    3.7/ 4.3 (Description of K&A, from catalog)
Knowledge of the parameters and logic used to assess the status of safety functions iquired Materials:
Notes and Comments:
Notes and Comments:
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
Prepared By:
: 67. Unit I plant conditions are as follows: Drywell pressure 0.5 psig and rising 0 Reactor pressure 1045 psig and steady 0 HPCl room temperature 175OF and rising 0 SDV level in AER is 10% and rising WHICH ONE of the following alarms is consistent with the noted conditions?
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
A. DIV 1 DRYWELL HI PRESS (I 13 E4) B. REACTOR HI PRESSURE TRIP (107 GI) C. B REAC ENCL HVAC PCL 1 BC208 TROUBLE (004 A3) D. SCRAM DISCHARGE VOLUME HI LEVEL TRIP (107 Cl) Page 134 of 200 Limerick Generatinq Station ILTO5-1 NRC Initial Licensinq Examination C Answer Key 1 BC208 panel trouble and HPCl room temp are consistent I Choice D I Basis or Justification SDV level is below the ALARM setpoint 1 Correct: Level of Knowledge Low Incorrect:
 
Difficulty Time Allowance PRA RO SRO 10CFR55.41 1 OCFR55.43 (minutes) 3.5 3 N N Y (b)(5) I Incorrect:
Limerick Generating Station                   ILT05-1 NRC Initial Licensinq Examination
Source: Reference@):
: 67. Unit Iplant conditions are as follows:
Learning Objective:
Drywell pressure 0.5 psig and rising 0 Reactor pressure 1045 psig and steady 0 HPCl room temperature 175OF and rising 0 SDV level in AER is 10% and rising WHICH ONE of the following alarms is consistent with the noted conditions?
Knowledge/Ability WA Incorrect:
A. DIV 1 DRYWELL HI PRESS ( I 13 E4)
L New Exam Item 0 Modified Bank Item 0 ILT Exam Bank Modified 0 Previous NRC Exam Other Exam Bank ANN'S 004 A3 LLOTI 560.02 2.4.46 Importance:
B. REACTOR HI PRESSURE TRIP (107 G I )
RO / SRO 3.5 13.6 Drywell pressure value is below Alarm setpoint Reactor pressure valve is below the ALARM setpoint Bl I Psvc hometrics I Required Materials:
C. B REAC ENCL HVAC PCL 1BC208 TROUBLE (004 A3)
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensing Examination
D. SCRAM DISCHARGE VOLUME HI LEVEL TRIP (107 C l )
: 68. Both units are at 100% when the following alarms: 0 LIQUID RADWASTE DISCHARGE HI RADIATION (003 A5) The Radwaste Operator contacts the MCR and ,reports the following in alarm in the Radwaste Control Room: LIQUID RADWASTE DISCHARGE RAD MONITOR HIHI/INOP (OA304, C-1) WHICH ONE of the following flowpaths will automatically isolate based on these conditions?
Page 134 of 200
A. Equipment Drain Sample Tank Discharge to CST B. Waste Sludge Tank Discharge to External Processing C. Reactor Enclosure Floor Drain Sump Discharge to Liquid Radwaste D. Floor Drain Sample Tank Discharge to Cooling Tower Blowdown Line Page 136 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Incorrect Incorrect I Choice I Basis or Justification B Waste Sludge Tank to external processing isolates on Low Waste Sludge Tank level only (Pump off, discharge valve closes) The only control functions associated with RE Floor Drain Sump pumps are Low-Low Level and Primary Containment Isolation Hi Rad Lockout (Post LOCA Rad Monitor Hi-Hi) will deenergize the pumps. C Liquid Radwaste discharge to Cooling Tower Blowdown Line isolates on Hi IDl Hi Rad. Correct: Level of Difficulty Time Allowance PRA RO Low 3.0 3 N N Knowledge (minutes) 1 OCFR55.41 Equipment Drain Sample Tank to CST isolates on EDST Level only (Pump off, discharge valve closes)
 
Incorrect SRO 1 OCFR55.43 N Source: Reference@): New Exam Item 0 Modified Bank Item 0 ILT Exam Bank Previous NRC Exam 0 Other Exam Bank ARC-MCR-003 RAD-A-5, ARC-BOP-OAC304-C-1 Learning 0 bjective:
Limerick Generatinq Station                       ILTO5-1 NRC Initial Licensinq Examination Answer Key I          Choice            I                            Basis or Justification 1     Correct:          C    1BC208 panel trouble and HPCl room temp are consistent Incorrect:              Drywell pressure value is below Alarm setpoint I     Incorrect:
Knowledge/Ability WA I LL0T-0705-04 2.3.1 1 Importance: RO  
B l  Reactor pressure valve is below the ALARM setpoint L
/ SRO 2.7 13.2 Notes and Comments Prepared By: Rick Rhode (610) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
I Incorrect:          D   SDV level is below the ALARM setpoint Psvc hometrics                                      I Level of     Difficulty Time Allowance         PRA                 RO                 SRO Knowledge                    (minutes)                        10CFR55.41           10CFR55.43 Low            3.5             3               N                 N                 Y (b)(5)
: 69. An Equipment Operator (EO) is required to enter an area in the Main Condenser with a general area radiation level of 3 Rem/hr in order to perform a surveillance test. The EO'S radiation history is as follows: 0 1760 mRem cumulative exposure for the current year (TEDE) 0 I9 Rem lifetime exposure to this date (TEDE) 0 NRC form 4 completed and on file 0 No dose extensions have been obtained The surveillance test will take 45 minutes to complete. WHICH ONE of the following radiation exposure limits, if any, would be exceeded if the EO performs the surveillance test?
Source:                   New Exam Item                           0Previous NRC Exam 0Modified Bank Item                         Other Exam Bank 0ILT Exam Bank                             Modified Reference@):          ANNS 004 A3 Learning              LLOTI560.02 Objective:
Knowledge/Ability 2.4.46                                           Importance: RO / SRO WA                                                                              3.5 13.6 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                 ILT05-I NRC Initial Licensing Examination
: 68. Both units are at 100% when the following alarms:
0 LIQUID RADWASTE DISCHARGE HI RADIATION (003 A5)
The Radwaste Operator contacts the MCR and ,reports the following in alarm in the Radwaste Control Room:
LIQUID RADWASTE DISCHARGE RAD MONITOR HIHI/INOP (OA304, C-1)
WHICH ONE of the following flowpaths will automatically isolate based on these conditions?
A. Equipment Drain Sample Tank Discharge to CST B. Waste Sludge Tank Discharge to External Processing C. Reactor Enclosure Floor Drain Sump Discharge to Liquid Radwaste D. Floor Drain Sample Tank Discharge to Cooling Tower Blowdown Line Page 136 of 200
 
Limerick Generating Station                       ILT05-1 NRC Initial Licensing Examination Answer Key I         Choice           I                             Basis or Justification Correct:
IDl      Liquid Radwaste discharge to Cooling Tower Blowdown Line isolates on Hi Hi Rad.
Incorrect                Equipment Drain Sample Tank to CST isolates on EDST Level only (Pump off, discharge valve closes)
Incorrect          B     Waste Sludge Tank to external processing isolates on Low Waste Sludge Tank level only (Pump off, discharge valve closes)
Incorrect          C    The only control functions associated with RE Floor Drain Sump pumps are Low-Low Level and Primary Containment Isolation Hi Rad Lockout (Post LOCA Rad Monitor Hi-Hi) will deenergize the pumps.
Level of     Difficulty Time Allowance         PRA                 RO                   SRO Knowledge                     (minutes)                         10CFR55.41           10CFR55.43 Low          3.0                3              N                  N                    N Source:                   New Exam Item                               Previous NRC Exam 0Modified Bank Item                         0Other Exam Bank 0ILT Exam Bank Reference@):          ARC-MCR-003 RAD-A-5, ARC-BOP-OAC304-C-1 Learning 0bjective:         I LL0T-0705-04 Knowledge/Ability 2.3.1 1                                           Importance: RO / SRO WA                                                                                2.7 13.2 Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   ILT05-1 NRC Initial Licensing Examination
: 69. An Equipment Operator (EO) is required to enter an area in the Main Condenser with a general area radiation level of 3 Rem/hr in order to perform a surveillance test.
The EOS radiation history is as follows:
0 1760 mRem cumulative exposure for the current year (TEDE) 0 I 9 Rem lifetime exposure to this date (TEDE) 0 NRC form 4 completed and on file 0 No dose extensions have been obtained The surveillance test will take 45 minutes to complete.
WHICH ONE of the following radiation exposure limits, if any, would be exceeded if the EO performs the surveillance test?
A. No limits are exceeded.
A. No limits are exceeded.
B. Administrative Dose Control Level ONLY. C. Administrative Dose control Level AND NRC Exposure Limit ONLY. D. Administrative Dose Control Level, NRC Exposure Limit, AND Emergency Exposure Limit. Page I38 of 200 Limerick Generating Station lLT05-1 NRC Initial Licensinq Examination Level of Difficulty Time Allowance PRA RO High 3.0 4 Y N Knowledge (minutes) 1 OCFR55.41 Answer Key SRO 1 OCFR55.43 Y (b)(4) auestion ID# 069 ROISRC Source: Reference(s):
B. Administrative Dose Control Level ONLY.
Learning Objective:
C. Administrative Dose control Level AND NRC Exposure Limit ONLY.
Choice 0 New Exam Item Modified Bank Item ILT Exam Bank Previous NRC Exam 2002 0 Other Exam Bank RP-AA-203 sects 4.1 .I, 4.2,4.5 LLOTI 760.04,.05 Correct: Incorrect Incorrect Incorrect B A C D Basis or Justification 3 Rem = 3000 mRem 3000 mRem X .75 = 2250 mRem 2250 mRem  
D. Administrative Dose Control Level, NRC Exposure Limit, AND Emergency Exposure Limit.
+ 1760 mRem = 401 0 mRem 4010 mRem exceeds 2000 mRem TEDE Admin Dose Control Level Admin Dose Control Level is exceeded 4010 mRem <NRC Limit of 5000 mRem 4010 mRem <NRC Limit of 5000 mRem 401 0 mRem <Emergency Exposure Limit of 10,000 mRem for protecting station property KnowledgelAbility WA 2.3.4 Importance:
Page I38 of 200
RO / SRO 2.5 13.1 (Description of K&A, from catalog) Knowledge of radiation exposure limits and contamination controVincluding permissible levels in excess of those authorized..
 
Limerick Generating Station                     lLT05-1 NRC Initial Licensinq Examination Answer Key auestion ID# 069 ROISRC Choice                                       Basis or Justification Correct:           B   3 Rem = 3000 mRem 3000 mRem X .75= 2250 mRem 2250 mRem + 1760 mRem = 4010 mRem 4010 mRem exceeds 2000 mRem TEDE Admin Dose Control Level Incorrect          A    Admin Dose Control Level is exceeded Incorrect          C    4010 mRem <NRC Limit of 5000 mRem Incorrect          D    4010 mRem <NRC Limit of 5000 mRem 4010 mRem <Emergency Exposure Limit of 10,000 mRem for protecting station property Level of    Difficulty  Time Allowance        PRA              RO                    SRO Knowledge                    (minutes)                      10CFR55.41            10CFR55.43 High          3.0              4              Y                N                  Y (b)(4)
Source:                  0New Exam Item                            Previous NRC Exam 2002 Modified Bank Item                    0Other Exam Bank ILT Exam Bank Reference(s):        RP-AA-203 sects 4.1 .I, 4.2,4.5 Learning              LLOTI760.04,.05 Objective:
KnowledgelAbility 2.3.4                                           Importance: RO / SRO WA                                                                            2.5 13.1 (Description of K&A, from catalog)
Knowledge of radiation exposure limits and contamination controVincluding permissible levels in excess of those authorized..
Required Materials:
Required Materials:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensinq Examination ATTACHMENT: GP-2, Appendix 1 Provided 70. A reactor startup is in progress on Unit 2. All Group I and Group 2 control rods are fully withdrawn. SRM count rate data since the startup began is as follows: 0 Channel YA" has gone from 240 cps to 975 cps 0 Channel "1 B" has gone from 225 cps to 91 5 cps 0 Channel "IC" has gone from 220 cps to 890 cps 0 Channel "ID" has gone from 235 cps to 940 cps WHICH ONE of the following identifies control rod notch positions where control rod withdraw shall be restricted to single notch movement?
Notes and Comments Prepared By:
A. Between "00" and "08" B. Between "I 2" and '7 8" C. Between "18" and "30" D. Between "30" and "48" Page 140 of 200 Li me rick Genera t i n g Station lLTO5-1 NRC Initial Licensing Examination Correct: 1 Answer Key A Question ID# 070 Both RC Incorrect Incorrect Incorrect I Choice B C D Level of Difficulty Time Allowance Knowledge (minutes)
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Low 3.0 3 PRA RO SRO 1 OCFR55.41 1 OCFR55.43 N N N Basis or Justification After 75% rod density (Group 1-2 fully withdrawn), control rod withdraw between notch positions 00 to 12 shall be restricted to single notch movements until criticality is achieved.
 
00 to 08 falls within this band. Single notch is require between 04 to 30 applies once the SRM count rate reaches four doublings. SRM count rate is only doubled at this point, so the 00 to 12 requirement still applies. 12 to 18 falls outside that band. Due to the reasons stated above, the 00 to 12 requirement still applies. I8 to 30 falls outside that band. KnowledgelAbility WA Due to the reasons stated above, the 00 to 12 requirement still applies.
Limerick Generating Station                     ILT05-I NRC Initial Licensinq Examination ATTACHMENT: GP-2, Appendix 1 Provided
30 to 48 falls outside that band. 2.2.1 Importance:
: 70. A reactor startup is in progress on Unit 2.
RO I SRO 3.7 13.6 Source: Reference( s): Learning 0 bjective:
All Group Iand Group 2 control rods are fully withdrawn.
Source Documentation 0 New Exam Item 0 Modified Bank Item ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank GP-2, Appendix I, Caution after step 3.2.7 LLOTI 530.02 Required Materials:
SRM count rate data since the startup began is as follows:
GP-2, Appendix 1 Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination
0   Channel Y A  has gone from 240 cps to 975 cps 0   Channel 1B has gone from 225 cps to 915 cps 0   Channel I C  has gone from 220 cps to 890 cps 0   Channel I D  has gone from 235 cps to 940 cps WHICH ONE of the following identifies control rod notch positions where control rod withdraw shall be restricted to single notch movement?
: 71. Unit 1 PRO is performing ST-6-051-231-1, "IA' RHR Pump, Valve, and Flow Test. At step 4.3.6, the PRO discovers that HV-51-1 F021A is incorrectly identified as HV-51-1 F022A. WHICH ONE of the following identifies the status of the Surveillance Test and the action required to correct the error?
A. Between 00 and 08 B. Between I   2 and 78 C. Between 18 and 30 D. Between 30 and 48 Page 140 of 200
A. Stop the test. Identify the component number error in an action item to revise the procedure per AD-LG-101-1004, "Procedure Performance Improvement System (PPIs)," prior to resuming the ST. B. Stop the test. Initiate a Temporary Change to correct the component number error per AD-LG-101-1002, "Temporary Changes to Approved Documents and Partial Procedure Use," prior to resuming the ST. C. Continue the test. When it is complete, identify the component number error in an action item to revise the procedure per AD-LG-101-1004, "Procedure Performance Improvement System (PPIs)."
 
D. Continue the test. When it is complete, initiate a Temporary Change to correct the component number error per AD-LG-101-1002, "Temporary Changes to Approved Documents and Partial Procedure Use." Page 142 of 200 Limerick Generating Station lLTO5-I NRC Initial Licensing Examination Level of Knowledge Answer Key Difficulty Question ID# 071 Both RC Low Choice 2.5 3 N Y (b)(lO) Y (b)(3) Correct: Incorrect:
Li merick Generat ing Station                       lLTO5-1 NRC Initial Licensing Examination 1                                               Answer Key Question ID# 070 Both RC I         Choice                                           Basis or Justification Correct:          A    After 75% rod density (Group 1-2 fully withdrawn), control rod withdraw between notch positions 00 to 12 shall be restricted to single notch movements until criticality is achieved. 00 to 08 falls within this band.
Incorrect:
Incorrect          B    Single notch is require between 04 to 30 applies once the SRM count rate reaches four doublings. SRM count rate is only doubled at this point, so the 00 to 12 requirement still applies. 12 to 18 falls outside that band.
Incorrect:
Incorrect          C    Due to the reasons stated above, the 00 to 12 requirement still applies. I 8 to 30 falls outside that band.
B A C D Basis or Justification The test must stop.
Incorrect          D    Due to the reasons stated above, the 00 to 12 requirement still applies. 30 to 48 falls outside that band.
An equipment number error requires a Temporary Change I.A.W. AD-LG-101-1002, before the test can continue.
Level of    Difficulty  Time Allowance          PRA                RO                       SRO Knowledge                    (minutes)                          10CFR55.41              10CFR55.43 Low          3.0             3                N                  N                        N Source Documentation Source:                0New Exam Item                               0Previous NRC Exam 0Modified Bank Item                         0Other Exam Bank ILT Exam Bank Reference(s):        GP-2, Appendix I,Caution after step 3.2.7 Learning            LLOTI530.02 0bjective:
The status of the test is correct, but the procedure process cited is not correct . The procedure process cited is correct, however the test cannot continue. ~ ~ Both the status of the test and the procedure process cited are incorrect.
KnowledgelAbility 2.2.1                                              Importance:    RO I SRO WA                                                                                  3.7 13.6 Required Materials:
Psychometrics I SRo I Time Allowance RO (minutes)
GP-2, Appendix 1 Notes and Comments Prepared By:
I pRA 1 lOCFR55.41 I 10CFR55.43 I Source: Learning Objective:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Knowledge/Ability L Source Documentation New Exam Item Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank AD-LG-I 01-1 002 LLOTI 570.01 2.2.1 1 1 Importance:
 
RO / SRO (Description of K&A, from catalog) Knowledge of the process for controlling temporary changes. Required Materials:
Limerick Generatinq Station                     ILT05-I NRC Initial Licensing Examination
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination
: 71. Unit 1 PRO is performing ST-6-051-231-1, I A  RHR Pump, Valve, and Flow Test.
: 72. YA" Reactor Feed Pump impeller needs to be repaired at power. 0 Only one manual valve is available for isolation of the pump suction 0 Pump suction pressure is 450 psig 0 Pump suction temperature is 36OoF WHICH ONE of the following clearance requirements will allow this work to be performed per OP-MA-109-1 OI? .A. A clearance Technical Evaluation shall be performed.
At step 4.3.6, the PRO discovers that HV-51-1F021A is incorrectly identified as HV-51-1F022A.
WHICH ONE of the following identifies the status of the Surveillance Test and the action required to correct the error?
A. Stop the test. Identify the component number error in an action item to revise the procedure per AD-LG-101-1004, Procedure Performance Improvement System (PPIs), prior to resuming the ST.
B. Stop the test. Initiate a Temporary Change to correct the component number error per AD-LG-101-1002, Temporary Changes to Approved Documents and Partial Procedure Use, prior to resuming the ST.
C. Continue the test. When it is complete, identify the component number error in an action item to revise the procedure per AD-LG-101-1004, Procedure Performance Improvement System (PPIs).
D. Continue the test. When it is complete, initiate a Temporary Change to correct the component number error per AD-LG-101-1002, Temporary Changes to Approved Documents and Partial Procedure Use.
Page 142 of 200
 
Limerick Generating Station                         lLTO5-I NRC Initial Licensing Examination Answer Key Question ID# 071 Both RC Choice                                           Basis or Justification Correct:           B   The test must stop. An equipment number error requires a Temporary Change I.A.W. AD-LG-101-1002, before the test can continue.
Incorrect:          A  The status of the test is correct, but the procedure process cited is not correct.
Incorrect:          C  The procedure process cited is correct, however the test cannot continue.
                              ~             ~
Incorrect:          D    Both the status of the test and the procedure process cited are incorrect.
Psychometrics                                             I Level of Knowledge Low Difficulty 2.5 Time Allowance (minutes) 3 I   pRA N
1           RO 10CFR55.41 Y (b)(lO)
I     10CFR55.43 SRo Y (b)(3)
I ISource:                   New Exam Item Source Documentation Modified Bank Item 0Previous NRC Exam 0Other Exam Bank 0ILT Exam Bank AD-LG-I 01-1002 Learning              LLOTI570.01 Objective:
1 Importance:
LKnowledge/Ability 2.2.1 1 (Descriptionof K&A, from catalog)
Knowledge of the process for controlling temporary changes.
RO / SRO Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   lLTO5-1 NRC Initial Licensinq Examination
: 72. YA Reactor Feed Pump impeller needs to be repaired at power.
0 Only one manual valve is available for isolation of the pump suction 0 Pump suction pressure is 450 psig 0 Pump suction temperature is 36OoF WHICH ONE of the following clearance requirements will allow this work to be performed per OP-MA-109-1OI?
        .A. A clearance Technical Evaluation shall be performed.
B. The work shall be performed under an Exceptional Clearance.
B. The work shall be performed under an Exceptional Clearance.
C. A component walkdown shall be performed prior to application.
C. A component walkdown shall be performed prior to application.
D. The single isolation valve shall be restrained and locked in the closed position.
D. The single isolation valve shall be restrained and locked in the closed position.
Page 144 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Difficulty Time Allowance PRA RO (minutes) 1 OCFR55.41 2.5 3 N Y (b)(lO) Answer Key SRO 1 OCFR55.43 N Question ID# 072 Both RC 2.2.13 Choice Correct: Importance:
Page 144 of 200
RO / SRO 3.6 13.8 Incorrect:
 
~ In correct: Incorrect:
Limerick Generating Station                       ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 072 Both RC     9FtQ Choice                                         Basis or Justification Correct:           B   When 2-valve protection is required but not available then the clearance shall be designated as Exceptional.
B A C D 9FtQ Basis or Justification When 2-valve protection is required but not available then the clearance shall be designated as "Exceptional".
Incorrect:          A  A technical review is required only when there are questions about a systems response to the proposed isolation technique (such as logic
A technical review is required only when there are questions about a systems response to the proposed isolation technique (such as logic system response) A walkdown is suggested in circumstances where clearance information or documentation is missing or in question A Blocking device (such as a lock, restraint, or gag) is only required for a component that can fail to a position other than the tagged position.
      ~
Level of Knowledge Source: Reference@):
system response)
Learning 0 bjective:
Incorrect:          C  A walkdown is suggested in circumstances where clearance informationor documentation is missing or in question Incorrect:          D  A Blocking device (such as a lock, restraint, or gag) is only required for a component that can fail to a position other than the tagged position.
Knowledge/Ability WA Source Documentation New Exam Item Modified Bank Item 0 ILT Exam Bank Previous NRC Exam [XI Other Exam Bank (CAT) OP-MA-109-101, attachment 4 OP-MA-109-101 DB16 objective  
Level of       Difficulty Time Allowance        PRA                RO                      SRO Knowledge                     (minutes)                          10CFR55.41              10CFR55.43 2.5            3                N              Y (b)(lO)                   N Source Documentation Source:                    New Exam Item                               Previous NRC Exam Modified Bank Item                     [XI Other Exam Bank (CAT) 0ILT Exam Bank Reference@):            OP-MA-109-101, attachment 4 Learning                OP-MA-109-101 DB16 objective #2 0bjective:
#2 (Description of K&A, from catalog) Knowledge of Clearance and Tagging procedures Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensinq Examination
Knowledge/Ability 2.2.13                                              Importance:    RO / SRO WA                                                                                    3.6 13.8 (Description of K&A, from catalog)
: 73. Given the following values from the most recent P-I : 0 MFLCPR 0.954 0 MFLPD 1.015 0 MAPRAT 0.991 0 FLLLP 0.967 WHICH ONE of the following identifies the thermal limit(s) that require action, if any? A. MFLPD ONLY. B. MFLPD and MAPRAT ONLY.
Knowledge of Clearance and Tagging procedures Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                 ILT05-I NRC Initial Licensinq Examination
: 73. Given the following values from the most recent P - I :
0 MFLCPR       0.954 0 MFLPD         1.015 0 MAPRAT       0.991 0 FLLLP         0.967 WHICH ONE of the following identifies the thermal limit(s) that require action, if any?
A. MFLPD ONLY.
B. MFLPD and MAPRAT ONLY.
C. MFLPD, MAPRAT, and FLLLP.
C. MFLPD, MAPRAT, and FLLLP.
D. All values are acceptable; no action is required.
D. All values are acceptable; no action is required.
Page 146 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO HIGH 2.5 3 N N Knowledge (minutes) 1 OCFR55.41 Answer Key SRO I OCFR55.43 N Question'ID#
Page 146 of 200
073 Both RC KIA I Choice 3.0 13.0 Correct: Incorrect:
 
Incorrect:
Limerick Generating Station                         ILT05-1 NRC Initial Licensing Examination Answer Key Question'ID# 073 Both RC   ggg I         Choice                         ~~
In correct: r B A C D ggg Basis or Justification  
Basis or Justification Correct:          B    MFLPD (>I     .O) and MAPRAT (20.99) require entry into GP-14
~~ MFLPD (>I .O) and MAPRAT (20.99) require entry into GP-14 ~ MFLPD does require action (see above) but this choice omits MAPRAT, which also requires action ~ FLLLP does not require action MFLPD and MAPRAT require action Source: Reference(s):
                              ~
Learning Objective:
Incorrect:          A    MFLPD does require action (see above) but this choice omits MAPRAT, which also requires action
Source Documentation 0 New Exam Item 0 Modified NRC Bank Item ILT Exam Bank Previous NRC Exam Other Exam Bank (LOR-modified)
                              ~
GP-5, Sect 3.1 .I LLOT0741.04 KnowledgeIAbility 2.1 .I9 I Importance:
Incorrect:          C    FLLLP does not require action r    Incorrect:          D    MFLPD and MAPRAT require action Level of      Difficulty  Time Allowance            PRA              RO                    SRO Knowledge                      (minutes)                         10CFR55.41              IOCFR55.43 HIGH          2.5              3                  N                N                    N Source Documentation Source:                0New Exam Item                                 Previous NRC Exam 0Modified NRC Bank Item                       Other Exam Bank (LOR-modified)
RO / SRO Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensina Examination
ILT Exam Bank Reference(s):        GP-5, Sect 3.1.I Learning              LLOT0741.04 Objective:
: 74. Unit I is in OPCON 2 with reactor startup in progress. All IRM's are on Range 6 and reading as follows: "A' - 37/125ths "B" - 23/125ths  
KnowledgeIAbility 2.1 . I 9                                        I Importance:   RO / SRO KIA                                                                                3.0 13.0 Required Materials:
'tC" - 31/125ths "D" - 38/125ths "E" - 28/125ths "F" - 39/125ths "G" - 33/125ths "H" - 26/125ths WHICH ONE of the following identifies the Rod Block and RPS status if all IRM Range Switches are positioned to Range 5? A. Control Rod Withdraw Block ONLY B. Control Rod Withdraw Block AND "A side '/2 Scram ONLY C. Control Rod Withdraw Block AND "B" side % Scram ONLY D. Control Rod Withdraw Block AND full Scram Page 148 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Correct: Incorrect:
Notes and Comments Prepared By:
Incorrect:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
I Answer Key C A B I Question ID# 074 Both RC c ~ Level of Knowledge High I Choice Difficulty Time Allowance PRA RO SRO (minutes)
 
I OCFR55.41 1 OCFR55.43 3 3 Y Y (b)(lO) Y (b)(3) Knowledge/Ability WA 1 Incorrect:
Limerick Generating Station                   ILT05-1 NRC Initial Licensina Examination
1 D 2.1.28 Importance:
: 74. Unit I is in OPCON 2 with reactor startup in progress.
RO / SRO 4.0 / 3.5 geq Basis or Justification Ranging from 6 to 5 will multiply all readings by 3.16, which will result in exceeding 120/125ths on channel 'IF. This channel inputs to "B" RPS resulting in a % scram. Any channel over 85/125ths results in a Rod Withdraw Block. There will be a % scram on "B" RPS, in addition to the Rod Withdraw Block. There will be a K scram on "B", not "A", RPS There will be a K scram on only "B" RPS I Psychometrics I I Source Documentation Source: Reference(s):
All IRMs are on Range 6 and reading as follows:
Learning Objective: New Exam Item 0 Modified Bank Item 0 ILT Exam Bank Tech Specs 2.2.1 and 3.3.6 LLOT0250.08,09 0 Previous NRC Exam Other Exam Bank Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC initial Licensing Examination
A - 37/125ths B- 23/125ths tC - 31/125ths D - 38/125ths E - 28/125ths F - 39/125ths G - 33/125ths H - 26/125ths WHICH ONE of the following identifies the Rod Block and RPS status if all IRM Range Switches are positioned to Range 5?
A. Control Rod Withdraw Block ONLY B. Control Rod Withdraw Block AND A side /2 Scram ONLY C. Control Rod Withdraw Block AND B side % Scram ONLY D. Control Rod Withdraw Block AND full Scram Page 148 of 200
 
Limerick Generating Station                       ILT05-1 NRC Initial Licensing Examination I                                               Answer Key Ic Question ID# 074 Both RC geq I           Choice                                       Basis or Justification Correct:          C  Ranging from 6 to 5 will multiply all readings by 3.16, which will result in exceeding 120/125ths on channel IF. This channel inputs to B RPS resulting in a % scram. Any channel over 85/125ths results in a Rod Withdraw Block.
Incorrect:          A  There will be a % scram on B RPS, in addition to the Rod Withdraw Block.
Incorrect:          B  There will be a K scram on B, not A,RPS 1    Incorrect:      1  D  There will be a K scram on only BRPS I~                                            Psychometrics                                               I Level of    Difficulty Time Allowance        PRA                  RO                      SRO Knowledge                    (minutes)                          IOCFR55.41              10CFR55.43 High          3              3              Y                Y (b)(lO)                Y (b)(3)
I                                         Source Documentation Source:                 New Exam Item                             0Previous NRC Exam 0Modified Bank Item                           Other Exam Bank 0ILT Exam Bank Reference(s):        Tech Specs 2.2.1 and 3.3.6 Learning            LLOT0250.08,09 Objective:
Knowledge/Ability 2.1.28                                            Importance:    RO / SRO WA                                                                                4.0 / 3.5 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                     ILT05-I NRC initial Licensing Examination
: 75. Given the following conditions:
: 75. Given the following conditions:
Both units are operating at full power The entire shift attended the morning Shift Turnover Meeting given by the Control Room Supervisor (CRS) and Shift Manager (SM)
Both units are operating at full power The entire shift attended the morning Shift Turnover Meeting given by the Control Room Supervisor (CRS) and Shift Manager (SM)
At 1100, the 3rd RO relieves the Unit 2 RO for lunch.
At 1100, the 3rdRO relieves the Unit 2 RO for lunch.
The Unit 2 RO will be eating lunch in the Main Control Room (MCR) Lunchroom.
The Unit 2 RO will be eating lunch in the Main Control Room (MCR)
Lunchroom.
WHICH ONE of the following identifies the required MINIMUM TURNOVER ACTIVITY and MAXIMUM DURATION of the RO's mid-shift turnover for the given conditions?
WHICH ONE of the following identifies the required MINIMUM TURNOVER ACTIVITY and MAXIMUM DURATION of the RO's mid-shift turnover for the given conditions?
A. Read the MCR logs through the last previous day on shift.
A. Read the MCR logs through the last previous day on shift.
The relief duration shall be a MAXIMUM of 30 minutes. B. Read the MCR logs through the last previous day on shift. The relief duration shall be a MAXIMUM of 60 minutes. C. Review the Shift Turnover Checklist and review updated plant status. The relief duration shall be a MAXIMUM of 30 minutes. D. Review the Shift Turnover Checklist and review updated plant status. The relief duration shall be a MAXIMUM of 60 minutes ' Page 150 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination D A B -I+ Answer Key Basis or Justification Mid-shift turnover of less than 1 hour consists of a review of the Shift Turnover checklist and update of plant status, provided the original watch stander remains in the Main Control Room area Reading the MCR logs through the last previous day on shift applies to a full shift turnover, short turnover duration is 60 minutes, not 30. Duration is correct, turnover criteria described applies to full turnover, not short duration Turnover criteria is correct, short turnover duration is 60 minutes, not 30 Choice Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
The relief duration shall be a MAXIMUM of 30 minutes.
I OCFR55.41 Low 2.5 3 N Y (b)(lO) Correct: SRO 1 OCFR55.43 N Incorrect:
B. Read the MCR logs through the last previous day on shift.
Source: Reference(s):
The relief duration shall be a MAXIMUM of 60 minutes.
Learning 0 bjective:
C. Review the Shift Turnover Checklist and review updated plant status.
Incorrect:
The relief duration shall be a MAXIMUM of 30 minutes.
New Exam Item Modified Bank Item 0 ILT Exam Bank OP-AA-112-101 , Sect 4.1.7 LLOTI 574.24 Previous NRC Exam Other Exam Bank Incorrect:
D. Review the Shift Turnover Checklist and review updated plant status.
KnowledgelAbility KIA 2.1.3 Importance:
The relief duration shall be a MAXIMUM of 60 minutes
RO / SRO 3.0 13.4 Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Stat ion ILTO5-1 NRC Initial Licensing Examination
                                  ' Page 150 of 200
: 76. Unit 1 Plant conditions are as follows: 0 Reactor power is 100% 0 Reactor level is 35" and steady Narrow Range RPV Level Transmitters LT-042-1 N004A, B, and C suffer hardware failures with outputs at 0 mA, resulting in the following:
 
0 FEEDWATER FAILURE (107 D4) annunciator is in alarm WHICH ONE of the following identifies the effect on individual Reactor Feed Pump M/A stations: FIC-M 1-1 RGOIA(B,C)  
Limerick Generatinq Station                           ILT05-1 NRC Initial Licensing Examination Answer Key Choice                                              Basis or Justification Correct:          D    Mid-shift turnover of less than 1 hour consists of a review of the Shift Turnover checklist and update of plant status, provided the original watch stander remains in the Main Control Room area Incorrect:          A    Reading the MCR logs through the last previous day on shift applies to a full shift turnover, short turnover duration is 60 minutes, not 30.
"A(B,C) RFPT Speed Controllers", and the procedure entered to address initial plant response?
Incorrect:          B    Duration is correct, turnover criteria described applies to full turnover, not short duration Incorrect:        -I+    Turnover criteria is correct, short turnover duration is 60 minutes, not 30 Level of     Difficulty Time Allowance           PRA                 RO                     SRO Knowledge                     (minutes)                           IOCFR55.41             10CFR55.43 Low           2.5               3                 N               Y (b)(lO)                   N Source:                     New Exam Item                                 Previous NRC Exam Modified Bank Item                           Other Exam Bank 0ILT Exam Bank Reference(s):          OP-AA-112-101, Sect 4.1.7 Learning                LLOTI 574.24 0bjective:
Effect on FIC-M1-I RGOIA(B,C)
KnowledgelAbility 2.1.3                                                 Importance:   RO / SRO KIA                                                                                  3.0 13.4 Required Materials:
Procedure Entered A. Swaps to Manual OT-I 00 B. Swaps to Manual OT-I I 0 C. Remains in Auto OT-I 00 D. Remains in Auto OT-I 10 Page 152 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA Knowledge (minutes)
Notes and Comments Prepared By:
High 3.0 4 Y Answer Key RO SRO 1 OCFR55.41 I OCFR55.43 y (b)(5) y (b)(5) CQuestion ID# 076 SRO Or Source: Reference (s): Learning 0 bjective:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
I Choice [XI New Exam Item 0 Modified Bank Item 0 ILT Exam Bank S06.1 .H U/1, Alarm Identity IXX-FW302.1TFFE S06.1 .D U/1 Appendix 1 LLOT0550.1 Od 0 Previous NRC Exam 0 Other Exam Bank Correct: Knowledge/Ability WA In correct: 259002 Importance:
 
RO / SRO A2.03 3.6 I3.7 Incorrect Incorrect B A C D i Basis or Justification With 3 level transmitters failed downscale, individual RFP MIA stations will automatically swap to manual.
Limerick Generating Station                    ILTO5-1 NRC Initial Licensing Examination
Additionally due to the failure of the level signal, the recirc pumps will run back. This combination of RFPs in manual coincident with a Recirc pump run back, result in level going up requiring in entry into OT-I IO REACTOR HIGH LEVEL This is incorrect as OT-100 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up This is incorrect as individual RFP M/A stations will swap to manual, and OT-I00 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up This is incorrect as individual RFP M/A stations will swap to manual. (Description of K&A, from catalog) Ability to predict the impact of the following on Reactor water level control and based on those predictions use procedures to correct, control or mitigate the consequence of those abnormal conditions or operations:
: 76. Unit 1 Plant conditions are as follows:
Loss of Reactor Water Level Input. bquired Materials: Notes and Comments:
0   Reactor power is 100%
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
0   Reactor level is 35and steady Narrow Range RPV Level Transmitters LT-042-1 N004A, B, and C suffer hardware failures with outputs at 0 mA, resulting in the following:
- . ___ Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
0   FEEDWATER FAILURE (107 D4) annunciator is in alarm WHICH ONE of the following identifies the effect on individual Reactor Feed Pump M/A stations: FIC-M1-1 RGOIA(B,C) A(B,C) RFPT Speed Controllers, and the procedure entered to address initial plant response?
: 77. Unit 1 plant conditions are as follows: 0 Reactor power is 10% 0 Reactor level is -200" and lowering 0 All MSlVs are closed 0 Suppression Pool temperature is 12OoF and rising 0 A blowdown is in progress with 3 SRV's open 0 Reactor pressure is 650 psig and lowering The Floor Supervisor reports T-251 is complete for Unit I WHICH ONE of the following identifies the required operator action?
Effect on                         Procedure FIC-M1-I RGOIA(B,C)               Entered A. Swaps to Manual                     OT-I 00 B. Swaps to Manual                     OT-I I0 C. Remains in Auto                     OT-I 00 D. Remains in Auto                     OT-I 10 Page 152 of 200
A. Immediately inject with HPCI. Restore level to -60" to -1 00". B. Immediately inject with HPCI. Restore level to -1 61 " to -1 86". C. Inject with HPCl when Reactor pressure is below 400 psig. Restore level to -60" to -1 00". D. Inject with HPCl when Reactor pressure is below 400 psig. Restore level to -1 61 " to -1 86". Page 154 of 200 Limerick Generating Statio n lLTO5-1 NRC Initial Licensinq Examination D A Correct: As Blowdown is already in progress, injection cannot occur until MIN ALT FLOODING PRESSUE is met. With only 3 SRVs open that occurs at 400 psig. Level band is -161" to -186" as Supp pool temp is greater than I10 degrees Injecting immediately is incorrect as Blowdown has already started. -60 to -100" is incorrect as Supp pool temp is greater than 110 degrees Incorrect:
 
Incorrect B Injecting immediately is incorrect as Blowdown has already started. Level of Knowledge High Incorrect
Limerick Generatinq Station                           ILT05-1 NRC Initial Licensing Examination Answer Key CQuestion ID# 076 SRO Or        i I           Choice                                            Basis or Justification Correct:          B    With 3 level transmitters failed downscale, individual RFP MIA stations will automatically swap to manual. Additionally due to the failure of the level signal, the recirc pumps will run back. This combination of RFPs in manual coincident with a Recirc pump run back, result in level going up requiring in entry into OT-I I O REACTOR HIGH LEVEL Incorrect:          A    This is incorrect as OT-100 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up Incorrect          C    This is incorrect as individual RFP M/A stations will swap to manual, and OT-I00 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up Incorrect           D     This is incorrect as individual RFP M/A stations will swap to manual.
-60" to -1 00" is incorrect as Supp pool temp is greater than 1 10 degrees Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 I OCFR55.43 4.0 4 Y Y (b)(lO) Y (b)(5) I Psvchometrics I Source: Reference (s): Learning Objective: New Exam Item 0 Modified Bank Item 0 ILT Exam Bank T-I 17 BASES, Step LQ-21 LLOTI 560.05 0 Previous NRC Exam Other Exam Bank Source Documentation KnowledgelAbility KIA 295037 Importance:
Level of     Difficulty  Time Allowance          PRA                RO                    SRO Knowledge                        (minutes)                          10CFR55.41              IOCFR55.43 High          3.0              4                Y                y (b)(5)                y (b)(5)
RO I SRO, 2.1 20 4.3 14.2 T-I 17 Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination ATTACHMENT:
Source:                  [XI New Exam Item                            0Previous NRC Exam 0Modified Bank Item                          0Other Exam Bank 0ILT Exam Bank Reference(s):          S06.1 .HU/1, Alarm Identity IXX-FW302.1TFFE S06.1 .D U/1 Appendix 1 Learning              LLOT0550.1Od 0bjective:
SAMP-I I Sheet 1 Provided 78. Unit 1 plant conditions are as follows: SAMP-I and SAMP-2 have been entered The Reactor was shutdown 20 minutes ago Reactor Level is -320" and dropping Reactor pressure is 800 psig and steady RClC is injecting at 600 GPM ALL other high pressure injection systems are unavailable Suppression pool level is 22' Suppression pool pressure is 20 psig WHICH ONE of the following SAMP-I sheets must be executed?
Knowledge/Ability 259002                                                Importance: RO / SRO WA                    A2.03                                                          3.6 I3.7 (Descriptionof K&A, from catalog)
A. Sheet 4 B. Sheet5 C. Sheet6 D. Sheet7 Page 156 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge High Answer Key Difficulty Time Allowance PRA RO SRO (minutes)
Ability to predict the impact of the following on Reactor water level control and based on those predictions use procedures to correct, control or mitigate the consequence of those abnormal conditions or operations: Loss of Reactor Water Level Input.
I OCFR55.41 1 OCFR55.43 4.0 4 Y Y (b)(l 0) Y (b)(5) Question ID# 078 SRO Or Source: Reference( s): Learning Objective:
bquired Materials:
Choice New Exam Item Modified Bank Item ILT Exam Bank 0 Previous NRC Exam Other Exam Bank (LOR) SAMP 1, Sheet 1 LLOTI 562.6 Correct: Knowledge/Ability WA Incorrect:
Notes and Comments:
295031 Importance:
Prepared By:
RO I SRO 2.4.6 3.1 14.0 Incorrect Incorrect D A B C / Basis or Justification Sheet 7, To determine correct answer the candidate must determine that level cannot be restored to -31 1" (insufficient injection source are available for the current reactor pressure, AND attempts to blowdown as directed prior to reaching current reactor level must have been unsuccessful precluding use of low pressure systems), injection is unsafe as plotted on the MDRIR curve (20 minutes, Rx press 800 psig, injection rate 600 gpm), AND that conditions are unsafe as plotted on PSP curve (pool level 22', and pressure 20 psig).
Rick Rhode (61 0) 718-4085 Limerick Regulatory Exam Author
Sheet 4 is incorrect as level cannot be restored above -31 1. The candidate must determine that insufficient injection source are available for the current Reactor pressure, AND attempts to blowdown as directed prior to reaching current reactor level must have been unsuccessful precluding use of low pressure systems.
 
Sheet 5 is incorrect as RPV injection is unsafe on MDRIR as plotted (20 minutes, Rx press 800 psig, injection rate 600 gpm) Sheet 6 is incorrect as conditions are unsafe as plotted on PSP curve (pool level 22', and pressure 20 psig) Required Materials:
___                              .
SAMPI Sht 1 Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensing Examination ATTACHMENT:
Limerick Generating Station                     ILT05-1 NRC Initial Licensinq Examination
OT-I 12, Partial Provided 79. Unit 1 Reactor Power is 100%. The following transient occurs with the indicated plant conditions:
: 77. Unit 1 plant conditions are as follows:
0 1B Recirc Pump trips 0 IA Recirc Pump speed is 65% 0 ALL four OPRM Operator Display Assemblies indicate Reactor power is 58% 0 XR-042-1 R613 indicates core plate differential pressure is 1.3 psid 0 XR-042-1 R613 indicates core flow is 42 x 1 O6 Ibm/hr WHICH ONE of the following is the required operator action? A. Immediately Scram the Reactor B. Restart "I B" Recirc Pump, and raise core flow with "I B" Recirc Pump.
0   Reactor power is 10%
C. Reduce Recirc Pump speed to less than 60% and manually scram the reactor. D. Insert control rods until the Restricted Region of the Power/Flow Map is exited. Page 158 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination  
0   Reactor level is -200 and lowering 0   All MSlVs are closed 0   Suppression Pool temperature is 12OoFand rising 0   A blowdown is in progress with 3 SRVs open 0   Reactor pressure is 650 psig and lowering The Floor Supervisor reports T-251 is complete for Unit I WHICH ONE of the following identifies the required operator action?
~ D A Answer Key Because the speed of the operating Recirc Pump is >60%, the Core Flow and Reactor power indications provided should be used to determine operating point. With the given information, the plant is in the Restricted Region, and the correct action is an immediate exit by the insertion of control rods or the raising of Recirculation flow. Immediately scram the reactor is not correct because the operating point is not in the Exclusion Region, therefore, a reactor scram is not required.
A. Immediately inject with HPCI.
Choice Correct: B Incorrect:
Restore level to -60 to -1 00.
Restart 1 B Recirc Pump and raise core flow with 1 B recirc pump is wrong as restarting a pump to raise flow is not allowed in OT-I I2 Incorrect C Incorrect Reduce Recirc pump speed to less than 60% and manually scram the reactor is not correct as reducing speed drive the reactor further into the restricted region.
B. Immediately inject with HPCI.
I Basis or Justification Level of Difficulty Time Allowance Knowledge (minutes)
Restore level to -1 61 to -1 86.
PRA RO SRO I OCFR55.41 1 OCFR55.43 High 3.0 5 N Y (b)(lO) Y (b)(5) Source: Reference(s):
C. Inject with HPCl when Reactor pressure is below 400 psig.
Learning Objective:
Restore level to -60 to -1 00.
Knowledge/Ability WA New Exam Item Modified Bank Item ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank OT-I 12, Step 3.7 LLOT0040.07g 295001 Importance:
D. Inject with HPCl when Reactor pressure is below 400 psig.
RO / SRO AA2.01 3.5 f 3.8 OT-112, Power to Flow Maps Attachment 1 & 2 only Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Restore level to -1 61 to -1 86.
__ Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination
Page 154 of 200
: 80. The Main Control Room has been abandoned due to a fire. Equipment Operators are going to enter a locked high radiation area in order to manually operate Primary Containment Isolation Valves. The highest dose rate in the area is 1250 mRem/hr.
 
Per RP-LG-460-1010 and RP-LG-460-1016, WHICH ONE of the following describes the type of Locked High Radiation Area and the highest level authorization required for issuing the key? Tvpe of LHRA Highest Authorization Required A. B. C. D. Level 1 Level 1 Level 2 Level 2 Radiation Protection Manager Plant Manager Radiation Protection Manager Plant Manager Page 160 of 200 Limerick Generating Stat ion ILT05-I NRC Initial Licensina Examination Incorrect: Answer Key B Question ID# 080 SRO Or incorrect Correct: C Level of Difficulty Time Allowance PRA RO Low 4.0 4 N N Knowledge (minutes) 1 OCFR55.41 SRO 1 OCFR55.43 (b) (4) ID Incorrect Source: Reference(s):
Limerick Generating Station                          lLTO5-1 NRC Initial Licensinq Examination Correct:           D    As Blowdown is already in progress, injection cannot occur until MIN ALT FLOODING PRESSUE is met. With only 3 SRVs open that occurs at 400 psig. Level band is -161 to -186 as Supp pool temp is greater than I 1 0 degrees Incorrect:          A    Injecting immediately is incorrect as Blowdown has already started. -60 to
Learning Objective:
                                -100 is incorrect as Supp pool temp is greater than 110 degrees Incorrect           B     Injecting immediately is incorrect as Blowdown has already started.
Knowledge/Ability KIA Y Basis or Justification 0 New Exam Item ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank Modified Bank Item RP-LG-460-1010, RP-LG-460-1016.
Incorrect                -60 to -1 00 is incorrect as Supp pool temp is greater than 110 degrees I                                              Psvchometrics                                              I Level of    Difficulty Time Allowance         PRA                 RO                   SRO Knowledge                      (minutes)                         10CFR55.41             IOCFR55.43 High          4.0               4               Y             Y (b)(lO)               Y (b)(5)
LLOTI 760.01 29501 6 Importance:
Source Documentation Source:                   New Exam Item                           0Previous NRC Exam 0Modified Bank Item                           Other Exam Bank 0ILT Exam Bank Reference(s):        T-I 17 BASES, Step LQ-21 Learning              LLOTI560.05 Objective:
RO / SRO 2.3.1 2.6 13.0 ~~ The area is a Level 1 LHRA (2 1000 hr/hr and <I 5 Whr) per RP-LG-460-101 0. This requires authorization from the RP Manager for issuing the key per RP-LG-460-1016.
KnowledgelAbility 295037                                             Importance:   RO ISRO, KIA                  2.12 0                                                        4.3 14.2 T-I 17 Notes and Comments Prepared By:
The level is correct, but the Plant Manager's authorization is not required.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Level 2 LHRA would be an area with dose rate 2 15 Whr. The RP Manager may not be the sole authorization for this entry. Level 2 LHRA would be an area with dose rate 2 15 Whr. The Plant Manager may authorization for this entry. I I Notes and Comments:
 
Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author 
Limerick Generating Station                   lLTO5-1 NRC Initial Licensinq Examination ATTACHMENT: SAMP-I Sheet 1 Provided I
- Limerick Generating Station ILT05-I NRC Initial Licensing Examination
: 78. Unit 1 plant conditions are as follows:
SAMP-I and SAMP-2 have been entered The Reactor was shutdown 20 minutes ago Reactor Level is -320 and dropping Reactor pressure is 800 psig and steady RClC is injecting at 600 GPM ALL other high pressure injection systems are unavailable Suppression pool level is 22 Suppression pool pressure is 20 psig WHICH ONE of the following SAMP-I sheets must be executed?
A. Sheet 4 B. Sheet5 C. Sheet6 D. Sheet7 Page 156 of 200
 
Limerick Generating Station                               ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 078 SRO Or        /
Choice                                                Basis or Justification Correct:          D      Sheet 7, To determine correct answer the candidate must determine that level cannot be restored to -31 1 (insufficient injection source are available for the current reactor pressure, AND attempts to blowdown as directed prior to reaching current reactor level must have been unsuccessful precluding use of low pressure systems), injection is unsafe as plotted on the MDRIR curve (20 minutes, Rx press 800 psig, injection rate 600 gpm), AND that conditions are unsafe as plotted on PSP curve (pool level 22, and pressure 20 psig).
Incorrect:         A      Sheet 4 is incorrect as level cannot be restored above -31 1. The candidate must determine that insufficient injection source are available for the current Reactor pressure, AND attempts to blowdown as directed prior to reaching current reactor level must have been unsuccessful precluding use of low pressure systems.
Incorrect          B      Sheet 5 is incorrect as RPV injection is unsafe on MDRIR as plotted (20 minutes, Rx press 800 psig, injection rate 600 gpm)
Incorrect          C      Sheet 6 is incorrect as conditions are unsafe as plotted on PSP curve (pool level 22, and pressure 20 psig)
Level of    Difficulty    Time Allowance            PRA                    RO                      SRO Knowledge                        (minutes)                              IOCFR55.41                10CFR55.43 High          4.0                4                  Y                Y (b)(l 0)                  Y (b)(5)
Source:                    New Exam Item                                0Previous NRC Exam Modified Bank Item                                Other Exam Bank (LOR)
ILT Exam Bank Reference(s):        SAMP 1, Sheet 1 Learning              LLOTI 562.6 Objective:
Knowledge/Ability 295031                                                    Importance:    RO I SRO WA                    2.4.6                                                                  3.1 14.0 Required Materials:
SAMPI Sht 1 Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   ILT05-I NRC Initial Licensing Examination ATTACHMENT: OT-I 12, Partial Provided
: 79. Unit 1 Reactor Power is 100%.
The following transient occurs with the indicated plant conditions:
0   1B Recirc Pump trips 0   I A Recirc Pump speed is 65%
0   ALL four OPRM Operator Display Assemblies indicate Reactor power is 58%
0   XR-042-1R613 indicates core plate differential pressure is 1.3 psid 0   XR-042-1R613 indicates core flow is 42 x 1O6 Ibm/hr WHICH ONE of the following is the required operator action?
A. Immediately Scram the Reactor B. Restart I B Recirc Pump, and raise core flow with I B Recirc Pump.
C. Reduce Recirc Pump speed to less than 60% and manually scram the reactor.
D. Insert control rods until the Restricted Region of the Power/Flow Map is exited.
Page 158 of 200
 
Limerick Generating Station                         ILT05-1 NRC Initial Licensinq Examination Answer Key Choice        ~
I                              Basis or Justification Correct:          D     Because the speed of the operating Recirc Pump is >60%, the Core Flow and Reactor power indications provided should be used to determine operating point. With the given information, the plant is in the Restricted Region, and the correct action is an immediate exit by the insertion of control rods or the raising of Recirculation flow.
Incorrect:          A    Immediately scram the reactor is not correct because the operating point is not in the Exclusion Region, therefore, a reactor scram is not required.
Incorrect          B     Restart 1B Recirc Pump and raise core flow with 1B recirc pump is wrong as restarting a pump to raise flow is not allowed in OT-I I 2 Incorrect         C     Reduce Recirc pump speed to less than 60% and manually scram the reactor is not correct as reducing speed drive the reactor further into the restricted region.
Level of     Difficulty   Time Allowance         PRA                RO                      SRO Knowledge                       (minutes)                         IOCFR55.41               10CFR55.43 High         3.0               5                 N             Y (b)(lO)                 Y (b)(5)
Source:                   New Exam Item                            0Previous NRC Exam Modified Bank Item                       0Other Exam Bank ILT Exam Bank Reference(s):        OT-I 12, Step 3.7 Learning              LLOT0040.07g Objective:
Knowledge/Ability 295001                                              Importance:    RO / SRO WA                    AA2.01                                                         3.5 f 3.8 OT-112, Power to Flow Maps Attachment 1 & 2 only Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
_ _
Limerick Generatinq Station                   ILT05-1 NRC Initial Licensing Examination
: 80. The Main Control Room has been abandoned due to a fire.
Equipment Operators are going to enter a locked high radiation area in order to manually operate Primary Containment Isolation Valves.
The highest dose rate in the area is 1250 mRem/hr.
Per RP-LG-460-1010 and RP-LG-460-1016,WHICH ONE of the following describes the type of Locked High Radiation Area and the highest level authorization required for issuing the key?
Tvpe of LHRA                 Highest Authorization Required A.           Level 1                  Radiation Protection Manager B.           Level 1                          Plant Manager C.           Level 2                   Radiation Protection Manager D.            Level 2                          Plant Manager Page 160 of 200
 
Limerick Generating Station                          ILT05-I NRC Initial Licensina Examination Answer Key Question ID# 080 SRO Or Y
                                  ~~
Basis or Justification Correct:                 The area is a Level 1 LHRA ( 2 1000 hr/hr and < I 5 Whr) per RP-LG-460-1010. This requires authorizationfrom the RP Manager for issuing the key per RP-LG-460-1016.
Incorrect:         B      The level is correct, but the Plant Managers authorization is not required.
incorrect          C      Level 2 LHRA would be an area with dose rate 2 15 Whr. The RP Manager may not be the sole authorization for this entry.
Incorrect ID        Level 2 LHRA would be an area with dose rate 2 15 Whr. The Plant Manager may authorization for this entry.
I                                                                                                            I Level of      Difficulty    Time Allowance          PRA                RO                    SRO Knowledge                      (minutes)                           10CFR55.41              10CFR55.43 Low            4.0              4                N                  N                    (b) (4)
Source:                0New Exam Item                                0Previous NRC Exam Modified Bank Item                        0Other Exam Bank ILT Exam Bank Reference(s):        RP-LG-460-1010, RP-LG-460-1016.
Learning              LLOTI760.01 Objective:
Knowledge/Ability 295016                                                Importance:  RO / SRO KIA                  2.3.1                                                          2.6 13.0 Notes and Comments:
Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                                                  -
Limerick Generating Station                   ILT05-I NRC Initial Licensing Examination
: 81. Unit 2 is in OPCON 3 preparing for a refueling outage with the following conditions:
: 81. Unit 2 is in OPCON 3 preparing for a refueling outage with the following conditions:
0 RPV Level is 85" 0 0 0 0 0 0 "2B" loop of SDC is in service Reactor coolant temperature is 3OO0F RPV pressure is 54 psig ?A' RHR Heat Exchanger is being drained for maintenance A Group I Isolation signal is in for I&C testing Cooling Tower draining is in progress An electrical fault causes a loss of 044k 1>22 MY&& 11131~b Subsequently, Reactor coolant temperature is 325OF and RPV pressure is 85 psig. WHICH ONE of the following describes the action required and the procedure used to perform the required action?
0     RPV Level is 85 0   2B loop of SDC is in service 0    Reactor coolant temperature is 3OO0F 0    RPV pressure is 54 psig 0    ?A RHR Heat Exchanger is being drained for maintenance 0    A Group IIsolation signal is in for I&C testing 0    Cooling Tower draining is in progress An electrical fault causes a loss of 044k 1>22         MY&&     11131~b Subsequently, Reactor coolant temperature is 325OF and RPV pressure is 85 psig.
A. Use dedicated LPCl Pumps for Shutdown Cooling per S51.8.H. B. Line up for RHR Alternate Decay Heat Removal per S51.8.L. C. Reduce RPV pressure using Main Steam Line Drains per ON-121. D. Reduce RPV pressure using ADS SRV's per ON-I 21. Page 162 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination  
WHICH ONE of the following describes the action required and the procedure used to perform the required action?
~~ Correct: Incorrect: Answer Key D RPV pressure is sufficient to cause a SDC isolation. Pressure must be reduced before SDC can be restored.
A. Use dedicated LPCl Pumps for Shutdown Cooling per S51.8.H.
The cooling tower draining makes the Main Condenser unavailable per ON-I 21 bases and therefore, pressure must be reduced with SRV's. Dedicated LPCl Pumps will not work because SDC is isolated.
B. Line up for RHR Alternate Decay Heat Removal per S51.8.L.
A Choice I Basis or Justification Level of Difficulty Time Allowance PRA RO Knowledge (minutes)
C. Reduce RPV pressure using Main Steam Line Drains per ON-121.
I OCFR55.41 SRO 1 OCFR55.43 RHR Alternate SDC lineup will not work because current plant conditions will not support it.
D. Reduce RPV pressure using ADS SRVs per ON-I 21.
IBl Incorrect High Although this choice correctly identifies that RPV pressure must be reduced, MSL drains will not work because the condenser is not available.
Page 162 of 200
ici Incorrect 4.0 4 Y Y (b)(lO) y (b) (5) 295021 AA2.06 Importance:
 
RO / SRO 3.2 / 3.3 Source: Reference(s):
Limerick Generatinq Station                         ILT05-1 NRC Initial Licensing Examination Answer Key Choice
Learning 0 bjective:
                ~~
Knowledge/Ability K/A Source Documentation New Exam Item Modified Bank Item ILT Exam Bank ON-121, Attachment 5 LLOT0370.13 Previous NRC Exam 0 Other Exam Bank (Description of K&A, from catalog) Ability to determine and/or interpret the following as they apply to a loss of shutdown cooling: Reactor Pressure Required Materials: Notes and Comments:
I                              Basis or Justification Correct:           D   RPV pressure is sufficient to cause a SDC isolation. Pressure must be reduced before SDC can be restored. The cooling tower draining makes the Main Condenser unavailable per ON-I 21 bases and therefore, pressure must be reduced with SRVs.
Prepared By: Rick Rhode (61 0) 71 8-4085. Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensing Examination ATTACHMENT:
Incorrect:          A    Dedicated LPCl Pumps will not work because SDC is isolated.
TURBINE BACKPRESSURE OPERATION LIMIT GRAPH Provided
Incorrect IBl      RHR Alternate SDC lineup will not work because current plant conditions will not support it.
: 82. Unit 1 conditions are as follows: 0 Reactor Power is 75% 0 BESSI System is not in operation The following annunciators are received:
Incorrect ici      Although this choice correctly identifies that RPV pressure must be reduced, MSL drains will not work because the condenser is not available.
TURBINE HIGH BACK PRESSURE (106 D2) 1A CONDENSOR LO VACUUM (104 E-5) The following parameters are observed:
Level of      Difficulty  Time Allowance          PRA                RO                    SRO Knowledge                      (minutes)                        IOCFR55.41              10CFR55.43 High            4.0             4               Y               Y (b)(lO)               y (b) ( 5 )
0 LP Turbine Inlet Pressure is 100 psig 0 "IA LP Turbine Back Pressure is 7.2 in Hg Abs 0 "IB" LP Turbine Back Pressure is 6.6 in Hg Abs 0 "IC" LP Turbine Back Pressure is 6.0 in Hg Abs 0 Main Condenser vacuum has dropped from 26 in Hg Vac to 23 in Hg Vac Main Condenser vacuum is 23 in Hg Vac and steady.
Source Documentation Source:                     New Exam Item                                 Previous NRC Exam Modified Bank Item                       0Other Exam Bank ILT Exam Bank Reference(s):          ON-121, Attachment 5 Learning                LLOT0370.13 0bjective:
WHICH ONE of the following identifies the required operator action and the procedure used to perform the required action? A: Trip the Main Turbine per GP-5. B. Trip the Main Turbine per OT-I 16. C. Reduce reactor power per GP-5. D. Reduce reactor power per OT-I 16. Page 164 of 200 Limerick Generating Station ILT05-I NRC initial Licensinn Examination Incorrect Answer Key D Question ID# 082 SRO 01 Level of Difficulty Time Allowance Knowledge (minutes)
Knowledge/Ability 295021                                                Importance: RO / SRO K/A                    AA2.06                                                        3.2 / 3.3 (Description of K&A, from catalog)
High 3.0 3 Choice PRA RO SRO 1 OCFR55.41 I OCFR55.43 Y Y (b) (IO) Y (b) (5) IC Correct: Source: Reference( s ): Learning Objective:
Ability to determine and/or interpret the following as they apply to a loss of shutdown cooling: Reactor Pressure Required Materials:
lA Incorrect: New Exam Item 0 Modified Bank Item ILT Exam Bank 0 Previous NRC Exam Other Exam Bank GP-5 Attachment 7 LLOT0500.06a IB Incorrect i Basis or Justification Student must plot values on Turbine Backpressure Operation Limit Graph to determine that turbine is operating in the limited region and power must be reduced IAW GP-5 to restore backpressure to the unlimited region If turbine backpressure could not be restored, then a GP-4 Shutdown is directed. Tripping the turbine at this time is not directed.
Notes and Comments:
Tripping the turbine is directed by OT-I 16 if Main Condenser vacuum reaches 21.5 in Hg Vac Reducing reactor power is directed by OT-I 16 until condenser vacuum stops dropping. Since vacuum is steady, a power reduction is not directed by OT-I 16 Knowledge/Ability 295002 WA 1 AA2.01 ~ Importance: RO  
Prepared By:
/ SRO 2.9 13.1 (Description of K&A, from catalog) Ability to determine and/or interpret condenser vacuurn/absolute pressure as it applies to a loss of main condenser vacuum !quired Materials:
Rick Rhode (610) 718-4085.
TURBINE BACKPRESSURE OPERATION LIMIT GRAPH Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Limerick Regulatory Exam Author
- Limerick Generating Station lLTO5-I NRC Initial Licensing Examination
 
: 83. Unit 1 conditions are as follows: 0 Reactor power is 100% 0 HPCl is running in Full Flow Test for required surveillance WHICH ONE of the following identifies the Technical Specification limit for Suppression Pool temperature and the bases for the limit?
Limerick Generating Station                   ILT05-I NRC Initial Licensing Examination ATTACHMENT: TURBINE BACKPRESSURE OPERATION LIMIT GRAPH Provided
: 82. Unit 1 conditions are as follows:
0   Reactor Power is 75%
0   BESSI System is not in operation The following annunciators are received:
TURBINE HIGH BACK PRESSURE (106 D2) 1A CONDENSOR LO VACUUM (104 E-5)
The following parameters are observed:
0   LP Turbine Inlet Pressure is 100 psig 0   I A LP Turbine Back Pressure is 7.2 in Hg Abs 0   I B  LP Turbine Back Pressure is 6.6 in Hg Abs 0   I C  LP Turbine Back Pressure is 6.0 in Hg Abs 0   Main Condenser vacuum has dropped from 26 in Hg Vac to 23 in Hg Vac Main Condenser vacuum is 23 in Hg Vac and steady.
WHICH ONE of the following identifies the required operator action and the procedure used to perform the required action?
A: Trip the Main Turbine per GP-5.
B. Trip the Main Turbine per OT-I 16.
C. Reduce reactor power per GP-5.
D. Reduce reactor power per OT-I 16.
Page 164 of 200
 
Limerick Generating Station                           ILT05-I NRC initial Licensinn Examination Answer Key Question ID# 082 SRO 01 i Choice                                           Basis or Justification Correct:
I C      Student must plot values on Turbine Backpressure Operation Limit Graph to determine that turbine is operating in the limited region and power must be reduced IAW GP-5 to restore backpressure to the unlimited region Incorrect:
l A      If turbine backpressure could not be restored, then a GP-4 Shutdown is directed. Tripping the turbine at this time is not directed.
Incorrect Incorrect IB  D Tripping the turbine is directed by OT-I 16 if Main Condenser vacuum reaches 21.5 in Hg Vac Reducing reactor power is directed by OT-I 16 until condenser vacuum stops dropping. Since vacuum is steady, a power reduction is not directed by OT-I 16 Level of      Difficulty  Time Allowance          PRA                  RO                    SRO Knowledge                      (minutes)                          10CFR55.41                IOCFR55.43 High          3.0                3              Y              Y (b) (IO)                Y (b) (5)
Source:                    New Exam Item                            0Previous NRC Exam 0Modified Bank Item                              Other Exam Bank ILT Exam Bank Reference(s ):          GP-5 Attachment 7 Learning                LLOT0500.06a Objective:
1
                                                                                              ~
Knowledge/Ability 295002                                                 Importance:   RO / SRO WA                      AA2.01                                                          2.9 13.1 (Description of K&A, from catalog)
Ability to determine and/or interpret condenser vacuurn/absolute pressure as it applies to a loss of main condenser vacuum
  !quired Materials:
TURBINE BACKPRESSURE OPERATION LIMIT GRAPH Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                                          -
Limerick Generating Station                   lLTO5-I NRC Initial Licensing Examination
: 83. Unit 1 conditions are as follows:
0   Reactor power is 100%
0   HPCl is running in Full Flow Test for required surveillance WHICH ONE of the following identifies the Technical Specification limit for Suppression Pool temperature and the bases for the limit?
A. 105OF Provides sufficient temperature margin to allow SBLC injection to shutdown the reactor during an ATWS without exceeding HCTL.
A. 105OF Provides sufficient temperature margin to allow SBLC injection to shutdown the reactor during an ATWS without exceeding HCTL.
B. 105OF Maintain bulk water temperature such that there is adequate NPSH for ECCS pumps following a blowdown.
B. 105OF Maintain bulk water temperature such that there is adequate NPSH for ECCS pumps following a blowdown.
C. 95OF Provides sufficient temperature margin to allow SBLC injection to shutdown the reactor during an ATWS without exceeding HCTL.
C. 95OF Provides sufficient temperature margin to allow SBLC injection to shutdown the reactor during an ATWS without exceeding HCTL.
D. 95OF Maintain bulk water temperature such that there is adequate NPSH for ECCS pumps following a blowdown.
D. 95OF Maintain bulk water temperature such that there is adequate NPSH for ECCS pumps following a blowdown.
Page 166 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Incorrect Answer Key D CQuestion ID# 083 SRO Or Level of Difficulty Time Allowance PRA RO Low 2.0 3 N N Knowledge (minutes) 1 OCFR55.41 I Choice SRO 1 OCFR55.43 Y (b)(2) I Correct: I B Source: Reference(s):
Page 166 of 200
Learning Objective:
 
Knowledge/Ability WA ic Incorrect New Exam Item Modified Bank Item ILT Exam Bank Tech Spec basis 3.6.2.1 LLOTOI 30.04f Previous NRC Exam Other Exam Bank 29501 3 Importance:
Limerick Generating Station                         ILT05-1 NRC Initial Licensinq Examination Answer Key CQuestion ID# 083 SRO Or I         Choice                                           Basis or Justification I     Correct:       I   B     Tech Spec 3.6.2.1 limits suppression pool max temperature to 105OF with testing that adds heat to the suppression pool. The basis for the limit is to maintain water temperature and suppression chamber conditions such that there is adequate NPSH for ECCS pumps following a blowdown.
RO / SRO 2.2.25 4.0 / 4.0 Basis or Justification Tech Spec 3.6.2.1 limits suppression pool max temperature to 105OF with testing that adds heat to the suppression pool.
The temperature limit is correct, however the basis is incorrect. This is the Trip Procedure basis suppression pool limit (110 degrees F) once T-I 02 or T-117 is entered.
The basis for the limit is to maintain water temperature and suppression chamber conditions such that there is adequate NPSH for ECCS pumps following a blowdown.
Incorrect Incorrect ic  D This is the temperature limit for NO testing in progress that adds heat to the suppression pool and the Trip Bases temperature limit described above.
The temperature limit is correct, however the basis is incorrect.
The Tech Spec basis is correct, however, the temperature limit is for NO testing in progress that adds heat to the suppression pool.
This is the Trip Procedure basis suppression pool limit (1 10 degrees F) once T-I 02 or T-1 17 is entered. This is the temperature limit for NO testing in progress that adds heat to the suppression pool and the Trip Bases temperature limit described above. The Tech Spec basis is correct, however, the temperature limit is for NO testing in progress that adds heat to the suppression pool. Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
Level of    Difficulty  Time Allowance          PRA                RO                      SRO Knowledge                      (minutes)                        10CFR55.41              10CFR55.43 Low          2.0              3                N                  N                    Y (b)(2)
: 84. A grid disturbance has caused as loss of power to the IO Station Aux Transformer and the 20 Regulating Transformer. Conditions are as follows: 0 Unit 2 Reactor has scrammed 0 D23 and D24 Diesel Generators have started and are supplying their respective busses 0 021 and D22 Diesel Generators did NOT start On Unit 2, WHICH ONE of the following identifies an instrument that can be used to determine reactor pressure and the procedure entered due to the given conditions?
Source:                  New Exam Item                                Previous NRC Exam Modified Bank Item                          Other Exam Bank ILT Exam Bank Reference(s):        Tech Spec basis 3.6.2.1 Learning            LLOTOI30.04f Objective:
Instrument Procedure A. Wide Range PAMS E- 1 B. Wide Range PAMS E-1 0/20 C. HPCl Steam Line Pressure E- 1 D. HPCl Steam Line Pressure E-I 0/20 Page 168 of 200 Limerick Generating Station ILT05-I NRC Initial Licensing Examination Time Allowance PRA RO (minutes) 1 OCFR55.41 3 Y Y (b)(lO) I SRO 1 OCFR55.43 Y (b)(5) Correct: Incorrect:
Knowledge/Ability 295013                                            Importance:    RO / SRO WA                  2.2.25                                                        4.0 / 4.0 Notes and Comments Prepared By:
Source: Reference( s ) : Learning 0 bjective:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Knowiedge/Ability WA incorrect
 
[XI New Exam item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam c] Other Exam Bank E-I, E-I 0/20 LLOT0275.13 295003 Importance:
Limerick Generating Station                 ILT05-1 NRC Initial Licensing Examination
RO / SRO AA2.02 4.2 / 4.3 Incorrect r--- D A B C I Basis or Justification Unit 2 is in a Loss of Offsite Power (E-l0/20).
: 84. A grid disturbance has caused as loss of power to the I O Station Aux Transformer and the 20 Regulating Transformer.
Due to the loss of D21 and D22, PAMS is not available. HPCl Steam Line Pressure is available on both units. The procedure reference is not correct. PAMS is not available.
Conditions are as follows:
The procedure reference is correct.
0   Unit 2 Reactor has scrammed 0   D23 and D24 Diesel Generators have started and are supplying their respective busses 0   021 and D22 Diesel Generators did NOT start On Unit 2, WHICH ONE of the following identifies an instrument that can be used to determine reactor pressure and the procedure entered due to the given conditions?
PAMS is not available. The procedure reference is not correct. The instrument is correct.
Instrument                           Procedure A. Wide Range PAMS                               E-1 B. Wide Range PAMS                             E-10/20 C. HPCl Steam Line Pressure                       E-1 D. HPCl Steam Line Pressure                   E-I 0/20 Page 168 of 200
Knowledge Required Materials: Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensina Examination
 
: 85. Unit I plant conditions are as follows: 0 Reactor Power is 100% 0 A steam leak occurs in HPCl room 0 DIV 2 STEAM LEAK DET SYS HI TEMPmROUBLE (107, G5) annunciator is alarming Based on the given conditions, WHICH ONE of the following identifies RPV water level instrumentation that can be used and the T-200 procedures that are entered?
Limerick Generating Station                         ILT05-I NRC Initial Licensing Examination I
A. B. C. d. RPV Water Level Instrument Wide Range Recorder XR42-I R623A on 1OC601 Wide Range Recorder XR42-I R623A on 1 OC601 Upset Range Recorder LR-42-1 R608 on I OC603 Upset Range Recorder LR-42-1 R608 on 1 OC603 Procedures Entered T-290, T-291 ONLY T-290, T-291, T-250 T-290, T-291 ONLY T-290, T-291, T-250 Page 170 of 200 Limerick Generating Station ILT05-I NRC Initial Licensinq Examination incorrect: Answer Key A 1 Question ID# 085 SRO Or incorrect I Choice C Incorrect D Level of Knowledge High i Basis or Justification Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 3 Y Y (b)(lO) Y (b)(5) A DIV II steam leak detection alarm requires entry into T-103, which directs us of PAMs FZ and EQ PMS instruments only for reading Reactor Level.
I Basis or Justification Correct:        D      Unit 2 is in a Loss of Offsite Power (E-l0/20). Due to the loss of D21 and D22, PAMS is not available. HPCl Steam Line Pressure is available on both units.
XR42-1 R623A on I OC601 is a PAM and can be used, 1-290, T-291, and T- 250 should be performed.
Incorrect:        A      The procedure reference is not correct. PAMS is not available.
In the case of T-250 The candidate must realize that the Div II alarms indicates that a temperature is above MNO which meets the conditions of stop sign SCC/T-4, requiring T-250 be performed per step SCC/T-5 XR42-1 R623A on 1 OC601 is correct, but, as noted above T-250 should be performed per step SCCTT-5 Source: Reference(s): LR-42-1 R608 on 1 OC601 is a not a PAM and cannot be used New Exam Item 17 Modified Bank Item 17 ILT Exam Bank T-291 Attachment 2 Previous NRC Exam 0 Other Exam Bank LR-42-1 R608 on 1 OC601 is a not a PAM and cannot be used WA I EA2.02 I Psvchometrics I 3.3 13.5 Learning 0 bjective : I LL0T1561.03 Knowledge/Ability I 295032 I Importance:
incorrect        B    The procedure reference is correct. PAMS is not available.
RO I SRO (Description of K&A, from catalog) Ability to determine and/or interpret equipment operability as it applies to high secondary containment area temperature  
r---  Incorrect        C      The procedure reference is not correct. The instrument is correct.
?quired Materials:
Time Allowance          PRA                  RO                  SRO Knowledge                   (minutes)                            10CFR55.41            10CFR55.43 3                Y              Y (b)(lO)              Y (b)(5)
Notes and Comments Prepared By: Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Source:                [XI New Exam item                              0Previous NRC Exam 0Modified Bank Item                            c]Other Exam Bank 0ILT Exam Bank Reference(s ):      E-I, E-I0/20 Learning            LLOT0275.13 0bjective:
- - Limerick Generating Station ILT05-I NRC Initial Licensing Examination
Knowiedge/Ability 295003                                              Importance:  RO / SRO WA                    AA2.02                                                      4.2 / 4.3 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                   ILT05-1 NRC Initial Licensina Examination
: 85. Unit Iplant conditions are as follows:
0 Reactor Power is 100%
0 A steam leak occurs in HPCl room 0 DIV 2 STEAM LEAK DET SYS HI TEMPmROUBLE (107, G5) annunciator is alarming Based on the given conditions, WHICH ONE of the following identifies RPV water level instrumentation that can be used and the T-200 procedures that are entered?
RPV Water Level                               Procedures Instrument                                   Entered A. Wide Range Recorder                         T-290, T-291 ONLY XR42-I R623A on 1OC601 B. Wide Range Recorder                         T-290, T-291, T-250 XR42-I R623A on 1OC601 C. Upset Range Recorder                       T-290, T-291 ONLY LR-42-1 R608 on IOC603
: d. Upset Range Recorder                       T-290, T-291, T-250 LR-42-1R608 on 1OC603 Page 170 of 200
 
Limerick Generating Station                           ILT05-I NRC Initial Licensinq Examination Answer Key 1 Question ID# 085 SRO Or       i I           Choice                                             Basis or Justification A DIV I I steam leak detection alarm requires entry into T-103, which directs us of PAMs FZ and EQ PMS instruments only for reading Reactor Level.
XR42-1R623A on IOC601 is a PAM and can be used, 1-290, T-291, and T-250 should be performed. In the case of T-250 The candidate must realize that the Div II alarms indicates that a temperature is above MNO which meets the conditions of stop sign SCC/T-4, requiring T-250 be performed per step SCC/T-5 incorrect:          A      XR42-1R623A on 1OC601 is correct, but, as noted above T-250 should be performed per step SCCTT-5 incorrect          C      LR-42-1R608 on 1OC601 is a not a PAM and cannot be used Incorrect          D      LR-42-1R608 on 1OC601 is a not a PAM and cannot be used I                                                   Psvchometrics                                               I Level of    Difficulty    Time Allowance          PRA                  RO                  SRO Knowledge                        (minutes)                          10CFR55.41              10CFR55.43 High          3.0                3                 Y              Y (b)(lO)              Y (b)(5)
Source:                      New Exam Item                                  Previous NRC Exam 17 Modified Bank Item                        0Other Exam Bank 17 ILT Exam Bank Reference(s):          T-291 Attachment 2 Learning 0bjective:           II Knowledge/Ability 295032 LL0T1561.03 I Importance: RO ISRO WA                    I EA2.02                                                          3.3 13.5 (Description of K&A, from catalog) Ability to determine and/or interpret equipment operability as it applies to high secondary containment area temperature
  ?quiredMaterials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                                                  -
Limerick Generating Station                   ILT05-I NRC Initial Licensing Examination
: 86. A LOCA is in progress on Unit 1 with the following conditions:
: 86. A LOCA is in progress on Unit 1 with the following conditions:
0 0 0 0 0 0 Drywell pressure is 24 psig and rising slowly Drywell temperature is 32OoF and rising slowly RPV pressure is 350 psig and dropping slowly Suppression Pool pressure is 19 psig and rising slowly Suppression Pool temperature is 96OF and rising slowly Suppression Pool level is 22' and rising slowly WHICH ONE of the following describes the required operator action and the basis for the required action?
0   Drywell pressure is 24 psig and rising slowly 0    Drywell temperature is 32OoF and rising slowly 0    RPV pressure is 350 psig and dropping slowly 0    Suppression Pool pressure is 19 psig and rising slowly 0    Suppression Pool temperature is 96OF and rising slowly 0    Suppression Pool level is 22' and rising slowly WHICH ONE of the following describes the required operator action and the basis for the required action?
A. Spray the Drywell per T-225 B. Perform an Emergency Blowdown per T-I12 C. Spray the Drywell per T-225 D. Perform an Emergency Blowdown per T-I 12 BAS IS Reduce containment pressure while preventing excessive negative pressure In the Drywell Transfer RPV energy to the Suppression Pool due to steam in the pool airspace preventing containment function Reduce containment temperature in order to prevent exceeding the Drywell tern pe ratu re limit Transfer RPV energy to the Suppression Pool before conditions threaten the integrity of the SRV tailpipes Page 172 of 200 Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Incorrect Answer Key C Question ID# 086 SRO Or Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3 Y y (b)(lO) Correct: SRO I OCFR55.43 Y (b)(5) 1 Incorrect:
BAS IS A. Spray the Drywell           Reduce containment pressure while per T-225                 preventing excessive negative pressure In the Drywell B. Perform an Emergency      Transfer RPV energy to the Suppression Blowdown per T-I12        Pool due to steam in the pool airspace preventing containment function C. Spray the Drywell          Reduce containment temperature in order to per T-225                  prevent exceeding the Drywell ternperature limit D. Perform an Emergency      Transfer RPV energy to the Suppression Blowdown per T-I 12        Pool before conditions threaten the integrity of the SRV tailpipes Page 172 of 200
I A EA2.04 3.9 / 3.9 Incorrect u I Basis or Justification  
 
~~~ Suppression Pool Water level and pressure are in the UNSAFE region of the PSP Curve. T-I 02 directs a T-I 12 blowdown based on steam in the suppression pool airspace preventing pressure suppression function if conditions further degrade. This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray. This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray. While the action is correct, the basis is not. At the given RPV pressure, Suppression Pool level would have to be 38.7 ft, in order to threaten the integrity of the SRV tailpipes.
Limerick Generating Station                           ILT05-I NRC Initial Licensinq Examination Answer Key Question ID# 086 SRO Or     I
Source: Reference(s):
                                ~~~
Learning 0 bj ect ive: Knowledge/Ability WA Source Documentation New Exam Item ILT Exam Bank T-102, T-102 Bases LLOTI 560.06 0 Previous NRC Exam Other Exam Bank Modified Bank Item 295024 I Importance:
Basis or Justification Correct:                Suppression Pool Water level and pressure are in the UNSAFE region of the PSP Curve. T-I 02 directs a T-I 12 blowdown based on steam in the suppression pool airspace preventing pressure suppression function if conditions further degrade.
RO / SRO (Description of K&A, from catalog) Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE.. .Suppression Chamber Pressure REQUIRED MATERIALS:
1    Incorrect:      I  A    This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray.
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
Incorrect          C    This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray.
~~ ~ Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination
u      Incorrect Level of    Difficulty While the action is correct, the basis is not. At the given RPV pressure, Suppression Pool level would have to be 38.7 ft, in order to threaten the integrity of the SRV tailpipes.
: 87. Unit 1 Plant conditions are as follows: Reactor Power is 100%
Time Allowance            PRA                  RO                    SRO Knowledge                        (minutes)                          10CFR55.41              IOCFR55.43 High          3.0                3                Y              y (b)(lO)                Y (b)(5)
0 I&C reports that "IC" Main Steam ine (R , SL) High Flow Transrr ters PDT-41-1 N088B and PDT-41-IN088C have failed their Surveillance Test 0 All other MSL Flow Transmitters are OPERABLE WHICH ONE of the following describes the status of the MSIV isolation logic and the required action?
Source Documentation Source:                  New Exam Item                               0Previous NRC Exam Modified Bank Item                              Other Exam Bank ILT Exam Bank Reference(s):        T-102, T-102 Bases Learning              LLOTI560.06 0bjective:
Knowledge/Ability 295024                                               I Importance: RO / SRO WA                    EA2.04                                                          3.9 / 3.9 (Description of K&A, from catalog) Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE...Suppression Chamber Pressure REQUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                ~~                         ~
Limerick Generating Station                     ILT05-1 NRC Initial Licensinq Examination
: 87. Unit 1 Plant conditions are as follows:
Reactor Power is 100%
0   I&C reports that I C  Main Steam ine (R
                                                      , SL) High Flow Transrr ters PDT-41-1N088B and PDT-41-IN088C have failed their Surveillance Test 0   All other MSL Flow Transmitters are OPERABLE WHICH ONE of the following describes the status of the MSIV isolation logic and the required action?
A. Div 4 MSlV isolation logic is INOPERABLE.
A. Div 4 MSlV isolation logic is INOPERABLE.
Place ONE Channel in the tripped condition within 24 hours. B. "IC" MSL MSlV isolation logic is INOPERABLE.
Place ONE Channel in the tripped condition within 24 hours.
Place ONE Channel tripped condition within I2 hours. C. Div 1 and 2 MSlV isolation logic are INOPERABLE.
B. IC MSL MSlV isolation logic is INOPERABLE.
Place ONE Channel in the tripped condition within 6 hours. D. Div 1 and 2 MSlV isolation logic are INOPERABLE. Place ONE Channel in the tripped condition within 1 hour. Page 174 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Knowledge High Answer Key Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 5 N Y (b)(5) y (bP) Question ID#
Place ONE Channel tripped condition within I 2 hours.
087 SR-0 Or Source: Reference(s):
C. Div 1 and 2 MSlV isolation logic are INOPERABLE.
Learning 0 bjective:
Place ONE Channel in the tripped condition within 6 hours.
I Choice [XI New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank Unit 1 Tech Specs, LCO 3.3.2 LLOTOI 80.1 OC Correct: KnowledgeiAbility WA Incorrect:
D. Div 1 and 2 MSlV isolation logic are INOPERABLE.
Incorrect 223002 Importance:
Place ONE Channel in the tripped condition within 1 hour.
RO i SRO A2.08 2.7 i 3.1 I I Incorrect D A B C I Basis or Justification 88C is Div
Page 174 of 200
: 1. 88B is Div 2. therefore there is only one Div 1 and Div 2 instrument operable for the "1 C MSL. Less than required number for 2 trip systems place one in the tripped condition within 1 hour. If only one trip system is affected for instrumentation not common to RPS, and placing it in the tripped condition would not cause an isolation; you have 24 hours until having to place it in the tripped condition.
 
If only one trip system were affected, this would be a correct answer. A common misconception is that a streamline is a trip system. If only one trip system is affected for instrumentation common to RPS, and placing it in the tripped condition would not cause an isolation, you have 12 hours until having to place it in the tripped condition The number of affected systems per line is correct however the time to place in the tripped condition is wrong. 6 hours is for one trip system where placing it in the tripped condition will cause an isolation.
Limerick Generating Station                           ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 087 SR-0 Or     I I         Choice                                             Basis or Justification Correct:           D     88C is Div 1. 88B is Div 2. therefore there is only one Div 1 and Div 2 instrument operable for the 1C MSL. Less than required number for 2 trip systems place one in the tripped condition within 1 hour.
I Psvchometrics I Source Documentation REQUIRED MATERIALS: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
Incorrect:          A      If only one trip system is affected for instrumentation not common to RPS, and placing it in the tripped condition would not cause an isolation; you have 24 hours until having to place it in the tripped condition. If only one trip system were affected, this would be a correct answer.
: 88. Unit 2 is in OPCON 5. Plant status is as follows: Fuel Shuffle Part 2 is 80% complete in Quadrant IV The 201 Safeguards Transformer has been de-energized The 101 Safeguards Transformer is supplying all 4KV busses D21 and D23 Diesel Generators are INOPERABLE for planned maintenance Surveillance testing has just been completed on D24 Diesel Generator Control rod stroke timing is in progress in Quadrant II The "C" traversing in-core probe is being inserted into the RPV for a TIP Drive PMT Seal repair is in progress on a CRDM hydraulic line in the undervessel area The inside EO reports that the D24 Diesel Generator Fuel Oil Storage Tank indicates 32,500 gallons.
Incorrect          B    A common misconception is that a streamline is a trip system. If only one trip system is affected for instrumentation common to RPS, and placing it in the tripped condition would not cause an isolation, you have 12 hours until I
WHICH ONE of the following describes the action required by Tech Specs? A. Stop control rod stroke timing.
having to place it in the tripped condition I    Incorrect C    The number of affected systems per line is correct however the time to place in the tripped condition is wrong. 6 hours is for one trip system where placing it in the tripped condition will cause an isolation.
B. Suspend all undervessel work. C. Suspend operation of the overhead crane over the RPV. D. Stop the traversing in-core probe PMT and withdraw probe from core. Page 176 of 200 Limerick Generatina Station ILTO5-1 NRC Initial Licensing Examination Correct: Answer Key 4- A Question ID#
I                                                 Psvchometrics                                             I Level of    Difficulty  Time Allowance          PRA                  RO                      SRO Knowledge                      (minutes)                          10CFR55.41              10CFR55.43 High          3.0                5                N                Y (b)(5)                y (bP)
088 SRO 01 Level of Difficulty Low 4.0 Knowledge Choice Time Allowance PRA RO SRO 1 OCFR55.41 1 OCFR55.43 (minutes) 4 Y N Y (b)(2) 264000 2.2.22 IB Incorrect:
Source Documentation Source:                [XI New Exam Item                              0Previous NRC Exam 0Modified Bank Item                            0Other Exam Bank 0ILT Exam Bank Reference(s):        Unit 1 Tech Specs, LCO 3.3.2 Learning            LLOTOI80.1OC 0bjective:
Importance:
KnowledgeiAbility 223002                                                Importance: RO i SRO WA                    A2.08                                                            2.7 i 3.1 REQUIRED MATERIALS:
RO / SRO 4.0 14.0 Incorrect Basis or Justification Tech Spec 3.8.1.2 requires suspension of Core Alterations with the AC electrical power sources inoperable in OPCON 5. Control rod movement with fuel in the vessel must be stopped. Work on a CRDM hydraulic line does not qualify as an Operation with Potential for Draining the Vessel. Operation of the Overhead Crane must be suspended over the Spent Fuel Pool but not over the Reactor Cavity. Inserting a TIP is not considered a Core Alteration.
Notes and Comments Prepared By:
Source: Reference(s):
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Learning 0 bjective:
 
KnowledgelAbility WA Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank Tech Spec 3.8.1.2, GP-6.2 LLOT0670.13 Previous NRC Exam Other Exam Bank (Description of K&A, from catalog) Knowledge of limiting conditions for operational and safety limits. REQUIRED MATERIALS:
Limerick Generating Station                     ILT05-1 NRC Initial Licensing Examination
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination
: 88. Unit 2 is in OPCON 5. Plant status is as follows:
: 89. Unit 2 conditions are as follows: 0 An inadvertent Group I isolation resulted in MSlV closure and Scram 0 RClC is being used for pressure and level control 0 RClC is currently in injection mode and maintaining RPV level at 35" in Auto 0 RPV pressure is 900 psig and lowering slowly 0 ST-6-107-640-2, Rx Vessel Temperature And Pressure Monitoring, is in progress Subsequently, the RClC Flow Controller fails in AUTO. The RClC Flow Controller is switched to MANUAL and adjusted so that level is +35" and steady. WHICH ONE of the following describes the operator action required to maintain RPV level over the next 30 minutes and the procedure used to perform the required action?
Fuel Shuffle Part 2 is 80% complete in Quadrant IV The 201 Safeguards Transformer has been de-energized The 101 Safeguards Transformer is supplying all 4KV busses D21 and D23 Diesel Generators are INOPERABLE for planned maintenance Surveillance testing has just been completed on D24 Diesel Generator Control rod stroke timing is in progress in Quadrant II The C traversing in-core probe is being inserted into the RPV for a TIP Drive PMT Seal repair is in progress on a CRDM hydraulic line in the undervessel area The inside EO reports that the D24 Diesel Generator Fuel Oil Storage Tank indicates 32,500 gallons.
0 pe ra tor Action A. Throttle closed HV-49-2F013, RClC Pump Discharge to Feedwater B. Raise output of the RClC flow Controller C. Throttle open HV-49-2F013, RClC Pump Discharge to Feedwater D. Lower output of the RClC flow Controller Procedure S49.7.A, Transfer of RClC From Pressure Control Mode to Injection Mode and Back OP-LG-I 08-1 01-1 001, Simple Quick Actsnransient Acts S49.7.A, Transfer of RClC From Pressure Control Mode to Injection Mode and Back OP-LG-108-101-1001, Simple Quick Actsnransient Acts Page 178 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination D A B C Answer Key With the RClC flow controller in MANUAL, it is maintaining constant speed. With the turbine at constant speed, as, RPV pressure goes down, injection will rise and RPV level will rise. The controller output must be lowered to reduce turbine speed. This is a simple quick act per OP-LG-108-101-1001.
WHICH ONE of the following describes the action required by Tech Specs?
This valve would be closed to transfer to pressure control mode. Given the conditions, pressure is going down with just the steam used to drive RCIC, therefore, level will go up. Transfer to pressure control would not be appropriate. The procedure would be appropriate if this were the correct action. Raising RClC controller output would only exacerbate the level trend that will result from the given conditions. The procedure would be appropriate if this were the correct action.
A. Stop control rod stroke timing.
This valve would be opened to transfer from level control to pressure to pressure control mode. The procedure would be appropriate if this were the correct action.
B. Suspend all undervessel work.
Choice Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3 Y y (b)(5) I Basis or Justification SRO 1 OCFR55.43 y W(5) Correct: Source: Reference( s): Learning 0 bjective:
C. Suspend operation of the overhead crane over the RPV.
I n correct: New Exam Item Modified Bank Item c] ILT Exam Bank 0 Previous NRC Exam Other Exam Bank S49.7 .A LLOT0380.08 Incorrect Knowledge/Ability WA Incorrect 21 7000 Importance:
D. Stop the traversing in-core probe PMT and withdraw probe from core.
RO / SRO A2.10 3.1 / 3.1 !QUIRED MATERIALS:
Page 176 of 200
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author 
 
- Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
Limerick Generatina Station                         ILTO5-1 NRC Initial Licensing Examination Answer Key 4-Question ID# 088 SRO 01 Choice                                           Basis or Justification Correct:          A    Tech Spec 3.8.1.2 requires suspension of Core Alterations with the AC electrical power sources inoperable in OPCON 5. Control rod movement with fuel in the vessel must be stopped.
: 90. Unit 1 Plant conditions are as follows: 0 Reactor Power is 100% 0 An electrical fault on a turbine control valve solenoid results in the closure of the #2 Turbine Control Valve WHICH ONE of the following identifies the initial EHC response and the requ i red p roced u ra I act ions? Initial EHC Response Procedural Action A. BPV(s) remain closed, reactor Reduce reactor power to less than 90% per OT-I02 pressure rises to Scram setpoint without operator action B. BPV(s) remain closed, reactor Reduce reactor power until pressure is less than 1053 psig per OT-I 04 pressure rises to Scram setpoint without operator action C. BPV(s) open, reactor pressure rises and stabilizes without operator action Reduce reactor power to less than 90% per OT-I02 D. BPV(s) open, reactor pressure rises and stabilizes without operator action per OT-I 04 Reduce reactor power until pressure is less than I053 psig Page 180 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Knowledge High '3.0 Answer Key Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 4 N y (b)(5) y Question ID#
090 SRO- Or Knowledge/Ability WA Choice Correct: 241 000 Importance:
RO / SRO A2.04 3.7 / 3.8 Incorrect:
Incorrect t--- Incorrect C A B D I Basis or Justification Reactor pressure will increase slightly requiring entry into OT-I 02. OT-I02 requires power to be lowered to below 90% on a control valve closure.
This is incorrect as Reactor pressure will not reach the scram setpoint. Electrical failure of the solenoid for the control valve does not affect bypass valve response. The procedural action is correct.
This is incorrect as Reactor pressure will not reach the scram setpoint. Electrical failure of the solenoid for the control valve does not affect bypass valve response.
While power may rise slightly, if OT-104 were entered, it does NOT reference pressure.
The pressure response is correct, however the procedural action is not. While power may rise slightly, if OT-I04 were entered, it does NOT reference pressure.
Source : Reference(s):
Learning 0 bjective:
Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam c] Other Exam Bank OT-102, step 3.5 T.S. 3.2.3.b LLOT0590.02a Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-I NRC Initial Licensing Examination
: 91. Unit I plant conditions are as follows: 0 95%power 0 "I C" RHR pump has been INOP for 19 days HPCl Full Flow Test is being performed.
Maximum flow flow achieved is 5150 gpm. WHICH ONE of the following describes the required Tech Spec actions?
A. Be in STARTUP in 6 hours, HOT SHUTDOWN in the following 6 hours and COLD SHUTDOWN in the subsequent 24 hours. B. Restore the "IC" RHR Pump to operable within the next 1 I days or be in HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN in the next 24 hours. C. Restore the "1 C" RHR pump or the HPCl system to operable within 8 hours or be in HOT SHUTDOWN in the next 12 hours and in COLD SHUTDOWN in the next +%hours. r,/3(ob a4 D. Restore the HPCl system to operable within 14 days or be in at least HOT SHUTDOWN within the next 12 hours and reduce reactor steam dome pressure to 5 200 psig within the following 24 hours. Page 182 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Low 3.0 4 Y N Knowledge (minutes) 1 OCFR55.41 Answer Key SRO 1 OCFR55.43 Y (b)(2)(5)
Choice Source: Reference(s):
Learning Objective:
Correct: UNew Exam Item Modified Bank Item ILT Exam Bank T. S. 3.5.1.b and 3.5.1.c.2 LLOT0340.16 0 Previous NRC Exam Other Exam Bank (LOR modified)
Incorrect:
Incorrect:
Knowledge/Ability KIA Incorrect 206000 Importance:
I B      Work on a CRDM hydraulic line does not qualify as an Operation with Potentialfor Draining the Vessel.
RO I SRO 2.1.12 2.9 14.0 Incorrect C A B D jr Basis or Justification Tech Spec 3.5.1 -with HPCl system INOP and one ECCS Subsystem INOP - Restore one of them to OPERABLE within the next 8 hours This is a Tech Spec 3.0.3 action applicable only when LCO's cannot be met This would be the correct action if HPCI were operable.
Incorrect                Operation of the Overhead Crane must be suspended over the Spent Fuel Pool but not over the Reactor Cavity.
This would be correct if "IC" RHR were operable with HPCl INOP Required Materials:
Inserting a TIP is not considered a Core Alteration.
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination ATTACHMENT: EAL Matrix Provided
Level of      Difficulty  Time Allowance          PRA                RO                  SRO Knowledge                      (minutes)                        10CFR55.41            10CFR55.43 Low            4.0               4                Y                N                Y (b)(2)
: 92. Units 2 plant conditions are as follows: A steam leak is in progress in the Outboard MSlV Room 0 Outboard MSlV room temperature is 18OoF and steady No other areas are exceeding Maximum Safe Operating temperatures Security reports the blowout panel from the steam chase to the North Stack has actuated The reactor is manually scrammed All efforts to isolate the leak have failed Field Team Monitoring reports that the dose rate has been 200 mRem/hr TEDE at the Site Boundary for the last hour, WHICH ONE of the following identifies the TRIP procedure(s) that require(s) entry and if an Emergency Blowdown is required per T-I 12? TRIP Procedure Entry T-I 12 Emerqency Required Blowdown Required A. T-I03 ONLY B. T-I03 ONLY Yes No C. T-I 03 AND T-I 04 Yes D. T-I 03 AND T-I 04 No Page 184 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 High 3.0 3 N Y (b) 10 Answer Key SRO 1 OCFR55.43 y (b)(5) Question ID# 092 SRO Or Source: Reference(s):
Source Documentation Source:                    New Exam Item                              Previous NRC Exam 0Modified Bank Item                            Other Exam Bank 0ILT Exam Bank Reference(s):         Tech Spec 3.8.1.2, GP-6.2 Learning              LLOT0670.13 0bjective:
Learning 0 bjective:
KnowledgelAbility 264000                                              Importance: RO / SRO WA                    2.2.22                                                      4.0 14.0 (Description of K&A, from catalog)
I Choice 0 New Exam Item Modified Bank Item 0 ILT Exam Bank [XI Previous NRC Exam 0 Other Exam Bank Emergency Action Level Matrix (Table 3-I), T-103, T-I04 LLOTl560.02,06 Correct: KnowledgelAbility WA Incorrect:
Knowledge of limiting conditions for operational and safety limits.
I n cor re ct 2.4.1 Importance: RO I SRO 2.3 14.1 I n correct D A B C / Basis or Justification Site boundary release is at Site Area Emergency level, therefore entry into T-104 is required per EAL Matrix. Release is not at or approaching General Emergency level and 2 areas are not exceeding MSO, therefore T- 112 is not required.
REQUIRED MATERIALS:
T-I04 entry is required and T-I 12 is not for the reasons given above. T-104 entry is required for the reason given above. T-I 12 is not required for the reason given above Required Materials:
Notes and Comments Prepared By:
EAL Matrix Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick GeneratinQ Station ILT05-I NRC Initial Licensinq Examination ATTACHMENT:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
T-228, Partial Provided
 
: 93. Unit 1 plant conditions are as follows: 0 A LOCA occurred 24 hours ago 0 T-I 01 and T-I 02 have been implemented T-I02 has directed inerting/purging the Drywell Suppression Pool level is 24 Feet 0 Drywell pressure is 2 psig The following containment parameters exists: 0 DW Ha is 5% and increasing 0 DW 02 is 4% and increasing SP HZ is 3% and increasing 0 SP 02 is 2% and increasing WHICH ONE of the following identifies the preferred method of Drywell inerting/purging, if any? A. Drywell purge with air. B. Drywell inerting with nitrogen (Low Flow Mode). C. Drywell inerting with nitrogen (High Flow Mode).
Limerick Generatinq Station                    ILT05-I NRC Initial Licensing Examination
D. Drywell purging is not required until Drywell 02 exceeds 5%. Page 186 of 200 Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination Level of Difficulty Time Allowance Knowledge (minutes) Answer Key PRA RO SRO 1 OCFR55.41 1 OCFR55.43 Basis or Justification Source: Reference(s):
: 89. Unit 2 conditions are as follows:
Learning 0 bjective: ~~ ~~ ~~ Per T-228, Drywell inerting with Low Flow and High Flow are allowed given the conditions.
0  An inadvertent Group Iisolation resulted in MSlV closure and Scram 0  RClC is being used for pressure and level control 0  RClC is currently in injection mode and maintaining RPV level at 35 in Auto 0  RPV pressure is 900 psig and lowering slowly 0  ST-6-107-640-2, Rx Vessel Temperature And Pressure Monitoring, is in progress Subsequently, the RClC Flow Controller fails in AUTO.
Low Flow is the preferred flowpath per the note in section 4.3 and Table
The RClC Flow Controller is switched to MANUAL and adjusted so that level is
: 1. per T-228 Not allowed due to high drywell pressure (>.75 psig) New Exam Item 0 Modified Bank Item ILT Exam Bank 0 Previous NRC Exam Other Exam Bank T-228 section 4.3, 4.5 and 4.6 LLOTI 561 -03 Allowed but not preferred per the note in section 4.3 and Table 1 of T-228 Knowledge/Ability K/A Does not apply to the given conditions  
      +35 and steady.
WHICH ONE of the following describes the operator action required to maintain RPV level over the next 30 minutes and the procedure used to perform the required action?
0perator Action                  Procedure A. Throttle closed HV-49-2F013,        S49.7.A, Transfer of RClC From RClC Pump Discharge to            Pressure Control Mode to Injection Feedwater                          Mode and Back B. Raise output of the RClC flow      OP-LG-I 08-101-1001, Simple Quick Controller                        Actsnransient Acts C. Throttle open HV-49-2F013,          S49.7.A, Transfer of RClC From RClC Pump Discharge to            Pressure Control Mode to Injection Feedwater                          Mode and Back D. Lower output of the RClC flow      OP-LG-108-101-1001, Simple Quick Controller                        Actsnransient Acts Page 178 of 200
 
Limerick Generating Station                           ILT05-1 NRC Initial Licensinq Examination Answer Key Choice            I                                Basis or Justification Correct:          D    With the RClC flow controller in MANUAL, it is maintaining constant speed.
With the turbine at constant speed, as, RPV pressure goes down, injection will rise and RPV level will rise. The controller output must be lowered to reduce turbine speed. This is a simple quick act per OP-LG-108-101-1001.
I ncorrect:          A    This valve would be closed to transfer to pressure control mode. Given the conditions, pressure is going down with just the steam used to drive RCIC, therefore, level will go up. Transfer to pressure control would not be appropriate. The procedure would be appropriate if this were the correct action.
Incorrect          B    Raising RClC controller output would only exacerbate the level trend that will result from the given conditions. The procedure would be appropriate if this were the correct action.
Incorrect          C    This valve would be opened to transfer from level control to pressure to pressure control mode. The procedure would be appropriate if this were the correct action.
Level of      Difficulty  Time Allowance            PRA                RO                    SRO Knowledge                        (minutes)                           10CFR55.41              10CFR55.43 High            3.0                3                Y                y (b)(5)                y W(5)
Source:                     New Exam Item                              0Previous NRC Exam Modified Bank Item                              Other Exam Bank c]ILT Exam Bank Reference(s):          S49.7.A Learning              LLOT0380.08 0bjective:
Knowledge/Ability 217000                                                  Importance:    RO / SRO WA                      A2.10                                                          3.1 / 3.1
  !QUIRED MATERIALS:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
                                        -
Limerick Generatinq Station                    ILT05-1 NRC Initial Licensinq Examination
: 90. Unit 1 Plant conditions are as follows:
0    Reactor Power is 100%
0    An electrical fault on a turbine control valve solenoid results in the closure of the #2 Turbine Control Valve WHICH ONE of the following identifies the initial EHC response and the required proceduraI act ions?
Initial EHC Response                      Procedural Action A. BPV(s) remain closed, reactor                Reduce reactor power to less pressure rises to Scram setpoint            than 90% per OT-I02 without operator action B. BPV(s) remain closed, reactor              Reduce reactor power until pressure rises to Scram setpoint            pressure is less than 1053 psig without operator action                    per OT-I 04 C. BPV(s) open, reactor pressure              Reduce reactor power to less rises and stabilizes without                than 90% per OT-I02 operator action D. BPV(s) open, reactor pressure              Reduce reactor power until rises and stabilizes without                pressure is less than I053 psig operator action                            per OT-I 04 Page 180 of 200
 
Limerick Generatinq Station                          ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 090 SRO-Or I Choice                                            Basis or Justification Correct:          C    Reactor pressure will increase slightly requiring entry into OT-I 02. OT-I02 requires power to be lowered to below 90% on a control valve closure.
Incorrect:         A    This is incorrect as Reactor pressure will not reach the scram setpoint.
Electricalfailure of the solenoid for the control valve does not affect bypass valve response. The procedural action is correct.
Incorrect          B    This is incorrect as Reactor pressure will not reach the scram setpoint.
Electricalfailure of the solenoid for the control valve does not affect bypass valve response. While power may rise slightly, if OT-104 were entered, it
---t    Incorrect          D does NOT reference pressure.
The pressure response is correct, however the procedural action is not.
While power may rise slightly, if OT-I04 were entered, it does NOT reference pressure.
Level of      Difficulty  Time Allowance          PRA                RO                      SRO Knowledge                      (minutes)                           10CFR55.41              10CFR55.43 High          '3.0              4                N              y (b)(5)                  y Source Documentation Source:                    New Exam Item                              0Previous NRC Exam 0Modified Bank Item                          c]Other Exam Bank 0ILT Exam Bank Reference(s):        OT-102,step 3.5 T.S. 3.2.3.b Learning              LLOT0590.02a 0bjective:
Knowledge/Ability 241000                                                Importance: RO / SRO WA                    A2.04                                                            3.7 / 3.8 Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                  ILT05-I NRC Initial Licensing Examination
: 91. Unit Iplant conditions are as follows:
0 95%power 0 IC RHR pump has been INOP for 19 days HPCl Full Flow Test is being performed. Maximum flow flow achieved is 5150 gpm.
WHICH ONE of the following describes the required Tech Spec actions?
A. Be in STARTUP in 6 hours, HOT SHUTDOWN in the following 6 hours and COLD SHUTDOWN in the subsequent 24 hours.
B. Restore the IC RHR Pump to operable within the next 1Idays or be in HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN in the next 24 hours.
C. Restore the 1C RHR pump or the HPCl system to operable within 8 hours or be in HOT SHUTDOWN in the next 12 hours and in COLD SHUTDOWN in the next +%hours.
a4                r,/3(ob D. Restore the HPCl system to operable within 14 days or be in at least HOT SHUTDOWN within the next 12 hours and reduce reactor steam dome pressure to 5 200 psig within the following 24 hours.
Page 182 of 200
 
Limerick Generating Station                          ILT05-1 NRC Initial Licensing Examination Answer Key jr Choice                                            Basis or Justification Correct:          C      Tech Spec 3.5.1 -with HPCl system INOP and one ECCS Subsystem INOP - Restore one of them to OPERABLE within the next 8 hours Incorrect:          A      This is a Tech Spec 3.0.3 action applicable only when LCOs cannot be met Incorrect          B      This would be the correct action if HPCI were operable.
Incorrect          D      This would be correct if IC RHR were operable with HPCl INOP Level of      Difficulty  Time Allowance        PRA                  RO                  SRO Knowledge                        (minutes)                        10CFR55.41            10CFR55.43 Low          3.0                4              Y                  N                Y (b)(2)(5)
Source:                  U N e w Exam Item                            0Previous NRC Exam Modified Bank Item                            Other Exam Bank (LOR modified)
ILT Exam Bank Reference(s):          T. S. 3.5.1.b and 3.5.1.c.2 Learning              LLOT0340.16 Objective:
Knowledge/Ability 206000                                                Importance:  RO ISRO KIA                    2.1.12                                                        2.9 14.0 Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generating Station                      lLTO5-1 NRC Initial Licensing Examination ATTACHMENT: EAL Matrix Provided
: 92. Units 2 plant conditions are as follows:
A steam leak is in progress in the Outboard MSlV Room 0  Outboard MSlV room temperature is 18OoFand steady No other areas are exceeding Maximum Safe Operating temperatures Security reports the blowout panel from the steam chase to the North Stack has actuated The reactor is manually scrammed All efforts to isolate the leak have failed Field Team Monitoring reports that the dose rate has been 200 mRem/hr TEDE at the Site Boundary for the last hour, WHICH ONE of the following identifies the TRIP procedure(s) that require(s) entry and if an Emergency Blowdown is required per T - I 12?
TRIP Procedure Entry                  T-I 12 Emerqency Required                    Blowdown Required A.        T-I03 ONLY                              Yes B.        T-I03 ONLY                                No C.      T - I 03 AND T-I 04                        Yes D.      T-I 03 AND T - I 04                        No Page 184 of 200
 
Limerick Generatinq Station                        ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 092 SRO Or /
I            Choice                                          Basis or Justification Correct:          D  Site boundary release is at Site Area Emergency level, therefore entry into T-104 is required per EAL Matrix. Release is not at or approaching General Emergency level and 2 areas are not exceeding MSO, therefore T-112 is not required.
Incorrect:          A  T-I04 entry is required and T-I 12 is not for the reasons given above.
I ncorrect          B  T-104 entry is required for the reason given above.
Incorrect          C  T-I 12 is not required for the reason given above Level of      Difficulty Time Allowance          PRA                  RO                  SRO Knowledge                    (minutes)                          10CFR55.41              10CFR55.43 High            3.0            3                N                Y (b) 10              y (b)(5)
Source:                  0New Exam Item                              [XI Previous NRC Exam Modified Bank Item                      0Other Exam Bank 0ILT Exam Bank Reference(s):          Emergency Action Level Matrix (Table 3-I), T-103, T-I04 Learning              LLOTl560.02,06 0bjective:
KnowledgelAbility 2.4.1                                                Importance:  RO I SRO WA                                                                                  2.3 14.1 Required Materials:
EAL Matrix Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick GeneratinQ Station                    ILT05-I NRC Initial Licensinq Examination ATTACHMENT: T-228, Partial Provided
: 93. Unit 1 plant conditions are as follows:
0  A LOCA occurred 24 hours ago 0  T - I 01 and T-I 02 have been implemented T-I02 has directed inerting/purging the Drywell Suppression Pool level is 24 Feet 0  Drywell pressure is 2 psig The following containment parameters exists:
0 DW Ha is 5% and increasing 0 DW 0 2 is 4% and increasing SP HZis 3% and increasing 0 SP 0 2 is 2% and increasing WHICH ONE of the following identifies the preferred method of Drywell inerting/purging, if any?
A. Drywell purge with air.
B. Drywell inerting with nitrogen (Low Flow Mode).
C. Drywell inerting with nitrogen (High Flow Mode).
D. Drywell purging is not required until Drywell 0 2 exceeds 5%.
Page 186 of 200
 
Limerick Generatinq Station                          ILT05-I NRC Initial Licensing Examination Answer Key
                              ~~      ~~        ~~
Basis or Justification Per T-228, Drywell inerting with Low Flow and High Flow are allowed given the conditions. Low Flow is the preferred flowpath per the note in section 4.3 and Table 1. per T-228 Not allowed due to high drywell pressure (>.75 psig)
Allowed but not preferred per the note in section 4.3 and Table 1 of T-228 Does not apply to the given conditions Level of    Difficulty  Time Allowance          PRA                RO                    SRO Knowledge                      (minutes)                        10CFR55.41            10CFR55.43 Source:                  New Exam Item                              0Previous NRC Exam 0Modified Bank Item                            Other Exam Bank ILT Exam Bank Reference(s):        T-228 section 4.3, 4.5 and 4.6 Learning              LLOTI561-03 0bjective:
Knowledge/Ability 2.3.9                                                Importance:  RO I SRO K/A                                                                                  2.5 13.4 Required Materials:
T-228 Assessment Table, and section first pages Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
__
Limerick Generatina Station                    ILT05-I NRC Initial Licensinq Examination
: 94. Unit 1 plant conditions are as follows:
0  35%power 0  Control rod scram time testing is in progress per ST-6-107-790-1 0  All Unit 1 control rods are OPERABLE 0  Control rod 30-31 is withdrawn from position 12 to position 48 to support scram time testing The following sequence of events occur:
13:OO:OO  - Control rod HCU toggle switches  Aand B for Rod 30-31 are taken to TEST and then immediately back to NORMAL 13:00:08 - Control rod 30-31 is at Position 1.88 05 a
WHICH ONE of the following describes the required action?
A. Restore Control Rod 30-31 to position 12.
B. Disarm HCU 30-31 Directional Control Valves.
C. Demonstrate insertion capability and restore Control Rod 30-31 to position 12.
D. Demonstrate insertion capability and restore Control Rod 30-31 to position 48.
Page 188 of 200
 
Limerick Generating Station                        ILT05-1 NRC Initial Licensing Examination Answer Key
                              ?a Question ID# 094 SRO Or Choice                                        Basis or Justification C    T.S 3.1.3.2 determines that 30-31 is INOP due to Scram time exceeding
                                                                                              ..      7 seconds. T.S. 3.1.3.1 Action b.1 J .
Incorrect:          A    30-31 is not OPERABLE, therefore it cannot just be regored to position 12.
B    The rod is INOP, Incorrect ID        While 30-31 must have insertion capability demonstrated, its original position is 12, not 48.
Level of    Difficulty  Time Allowance          PRA              RO                    SRO Knowledge                      (minutes)                        10CFR55.41            10CFR55.43 Low          3.0              3                N            Y (b)(10)              y (b)(2)
Source Documentation Source:                    New Exam Item                              Previous NRC Exam 0Modified Bank Item                          Other Exam Bank ILT Exam Bank Reference(s):        TS 3.1.3.2 AND 3.1.3.1 Learning              LLOT0060.12 0bjective:
Knowledge/Ability 201002 2.1.32                                      Importance:  RO ISRO WA                                                                                3.4 13.8 (Description of K&A, from catalog)
Ability to explain and apply system limits and precautions.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author


====2.3.9 Importance====
Limerick Generating Station                    ILT05-1 NRC Initial Licensing Examination
: 95. The CRS directed a manual scram on Unit 2 from 100% power due to a stuck open SRV.
The scram was unsuccessful and RRCS was manually initiated.
Immediately after RRCS initiation, reactor power dropped to I.2% on all APRMs.
Currently, Unit 2 plant conditions are as follows:
0  All APRMs indicate 1.2%
0  All IRMs are on Range 6 and stable 0  All SRM count rates are 55,000 cps and stable 0  ALL blue SCRAM lights are lit on the Full Core Display 0  Suppression Pool temperature is 108F and rising WHICH ONE of the following describes the correct mitigation strategy for control rod insertion and SLC?
Control Rods                            SLC A. Perform T-217 and T-218                  Do NOT inject SLC B. Perform T-217 and T-218                  Manually inject SLC C. Perform T-213, T-215, T-216,              Do NOT inject SLC and T-219 D. Perform T-213, T-215, T-216,              Manually inject SLC and T-219 Page 190 of 200


RO I SRO 2.5 13.4 Required Materials:
Limerick Generating Station                           ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 095 SRO Or I            Choice                                              Basis or Justification 1        Correct:           B      The Blue scram lights lit indicate that Scram solenoid valves are open, which requires 1-217 and T-218. The given conditions indicate that the reactor is not shutdown, therefore, before Suppression Pool Temperature reaches 1IOOF, SLC injection is required per T-101.
T-228 Assessment Table, and section first pages Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
I      Incorrect:          A      While T-217 and T-218 are required, T-I01 requires SLC injection.
__ Limerick Generatina Station ILT05-I NRC Initial Licensinq Examination
Incorrect            C      T-213, T-215, T-216, and T-219 are not required because the scram valves are open. In addition, T-101 requires SLC injection.
: 94. Unit 1 plant conditions are as follows: 0 35%power 0 Control rod scram time testing is in progress per ST-6-107-790-1 0 All Unit 1 control rods are OPERABLE 0 Control rod 30-31 is withdrawn from position "12" to position "48" to support scram time testing The following sequence of events occur:
Incorrect            D      While SLC injection is required per T-101; T-213, T-215, T-216, and T-219 are not required because the scram valves are open.
13:OO:OO - Control rod HCU toggle switches 'A and "B" for Rod 30-31 are 13:00:08 - Control rod 30-31 is at Position
Psychometrics Level of       Difficulty     Time Allowance         PRA                 RO                    SRO Knowledge                         (minutes)                           10CFR55.41             10CFR55.43 5    High          3.5                4                                Y b 10                 Y b 5 Source Documentation 1 Source:                   0New Exam Item                                  Previous NRC Exam I
'1.88" "05 " WHICH ONE of the following describes the required action?
Modified Bank Item                          Other Exam Bank 0ILT Exam Bank T-I 01 Learning                  LLOTI560.06 0bjective:
taken to "TEST" and then immediately back to "NORMAL" a A. Restore Control Rod 30-31 to position "12". B. Disarm HCU 30-31 Directional Control Valves. C. Demonstrate insertion capability and restore Control Rod 30-31 to position "12". D. Demonstrate insertion capability and restore Control Rod 30-31 to position "48". Page 188 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA Low 3.0 3 N Knowledge (minutes) Answer Key
I Knowledge/Ability 2.4.6 WA (Description of K&A, from catalog)
?a RO SRO 10CFR55.41 1 OCFR55.43 Y (b)(10) y (b)(2) Question ID# 094 SRO Or 201 002 2.1.32 Choice Importance:
Importance:  RO / SRO 3.1 /4.0 Knowledge of symptom based EOP mitigation strategies.
RO I SRO 3.4 13.8 C I nco rrect : A B ID Incorrect Basis or Justification T.S 3.1.3.2 determines that 30-31 is INOP due to Scram time exceeding 7 seconds. T.S. 3.1.3.1 Action b.1 .J 30-31 is not OPERABLE, therefore it cannot just be regored to position 12. .. The rod is INOP, While 30-31 must have insertion capability demonstrated, its original position is 12, not 48. Source: Reference(s):
      ~~                  ~~
Learning 0 bjective:
Knowledge/Ability WA Source Documentation New Exam Item 0 Modified Bank Item ILT Exam Bank TS 3.1.3.2 AND 3.1.3.1 LLOT0060.12 Previous NRC Exam Other Exam Bank (Description of K&A, from catalog) Ability to explain and apply system limits and precautions.
Required Materials:
Required Materials:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
Notes and Comments Prepared By:
: 95. The CRS directed a manual scram on Unit 2 from 100% power due to a stuck open SRV. The scram was unsuccessful and RRCS was manually initiated.
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
Immediately after RRCS initiation, reactor power dropped to I .2% on all APRM's. Currently, Unit 2 plant conditions are as follows: 0 All APRM's indicate 1.2% 0 All IRM's are on Range 6 and stable 0 All SRM count rates are 55,000 cps and stable 0 ALL blue SCRAM lights are lit on the Full Core Display 0 Suppression Pool temperature is 108'F and rising WHICH ONE of the following describes the correct mitigation strategy for control rod insertion and SLC? Control Rods SLC A. Perform T-217 and T-218 Do NOT inject SLC B. Perform T-217 and T-218 Manually inject SLC C. Perform T-213, T-215, T-216, Do NOT inject SLC and T-219 D. Perform T-213, T-215, T-216, Manually inject SLC and T-219 Page 190 of 200 Limerick Gene rating Station ILT05-1 NRC Initial Licensinq Examination Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 1 OCFR55.41 1 OCFR55.43 5 High 3.5 4 Y b 10 Yb5 Answer Key 2.4.6 Question ID# 095 SRO Or Importance:
 
RO / SRO 3.1 /4.0 I Choice 1 Correct: I Incorrect:
Limerick Generating Station                   ILT05-1 NRC Initial Licensing Examination
Incorrect Incorrect B A C D Basis or Justification The Blue scram lights lit indicate that Scram solenoid valves are open, which requires 1-217 and T-218.
: 96. WHICH ONE of the following identifies Work Execution Centerwork Control Center Supervisor (WCS) staffing requirements per OP-AA-I 01-11Iand OP-LG-101-111?
The given conditions indicate that the reactor is not shutdown, therefore, before Suppression Pool Temperature reaches 1 IOOF, SLC injection is required per T-1 01 . While T-217 and T-218 are required, T-I01 requires SLC injection.
T-213, T-215, T-216, and T-219 are not required because the scram valves are open. In addition, T-101 requires SLC injection.
While SLC injection is required per T-101; T-213, T-215, T-216, and T-219 are not required because the scram valves are open. 1 Source: I Learning 0 bjective:
Knowledge/Ability I WA Source Documentation 0 New Exam Item 0 ILT Exam Bank Previous NRC Exam Other Exam Bank Modified Bank Item T-I 01 LLOTI 560.06 (Description of K&A, from catalog) Knowledge of symptom based EOP mitigation strategies. ~~ ~~ Required Materials:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
: 96. WHICH ONE of the following identifies Work Execution Centerwork Control Center Supervisor (WCS) staffing requirements per OP-AA-I 01-1 1 I and OP- LG-101-111?
A. WCS may be credited as Shift Technical Advisor and Incident Assessor simultaneously.
A. WCS may be credited as Shift Technical Advisor and Incident Assessor simultaneously.
B. WCS may be credited as Incident Assessor and NRC Communicator simultaneously.
B. WCS may be credited as Incident Assessor and NRC Communicator simultaneously.
C. If the WCS is credited as Shift Technical Advisor then Incident Assessor function is NOT required.
C. If the WCS is credited as Shift Technical Advisor then Incident Assessor function is NOT required.
D. If the WCS is credited as Incident Assessor then Shift Technical Advisor function is NOT required.
D. If the WCS is credited as Incident Assessor then Shift Technical Advisor function is NOT required.
Page 192 of 200 Limerick Gen erati nq Station ILT05-1 NRC Initial Licensing Examination I ~~ Answer Key Level of Difficulty Time Allowance PRA RO Knowledge (minutes) 1 OCFR55.41 Question ID# 096 SRO Or SRO 1 OCFR55.43 I Choice Low 1 Correct: 2.0 3 N N Y (b)(2) 1 Incorrect:
Page 192 of 200
I Incorrect I Incorrect C A B D i Basis or Justification  
 
~ ~ ~~ If WCS is STA then IA function is not required (OP-AA-101-1 I 1, 4.5.2) ~ WCS cannot be both STA and IA (OP-LG-I 01-1 11, Attachment
Limerick Generatinq Station                     ILT05-1 NRC Initial Licensing Examination
: 3) ~~ WCS cannot be both IA and NRC Communicator (OP-LG-101-1 1 I, Attachment
    ~~
: 3) If WCS is the IA, they support the STA function, the STA is stili required Source: Reference(s):
Answer Key Question ID# 096 SRO Or i I           Choice                                       Basis or Justification 1
Learning 0 bjective:
                                        ~     ~~       ~
Knowledge/Abiiity KIA Source Documentation New Exam item 0 Modified Bank item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank OP-AA-101-11 I, page 5, step 4.5 OP-LG-101-111, page 11 #3 LLOTI 574.01 a 2.1.4 importance:
Correct:          C  If WCS is STA then IA function is not required (OP-AA-101-1I1, 4.5.2) 1      Incorrect:          A
RO / SRO 2.3 f 3.4 (Description of K&A, from catalog) Knowledge of Shift Staffing requirements Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author
                                                      ~
- __ ~~ - Limerick Generating Station ILT05-1 NRC Initial Licensing Examination
WCS cannot be both STA and IA (OP-LG-I 01-111, Attachment 3)
: 97. The "A' Chlorine detector fails upscale.
I
Subsequently, a loss of Div 3 DC power occurs. WHICH ONE of the following describes the status of the "A CREFAS Fan and the procedure entered? "A' CREFAS Fan Procedure A. Running S78.0.B Verification of MCR HVAC Isolation Signal B. Not Running S78.0.B Verification of MCR HVAC Isolation Signal C. Running S78.8.A Manual Initiation of MCR HVAC Isolation D. Not Running S78.8.A Manual Initiation of MCR HVAC Isolation Page 194 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO High 3.0 4 N N Knowledge (minutes) 1 OCFR55.41 Answer Key SRO 1 OCFR55.43 Y (b)(5) Question ID# 097 SRO Or 290003 A2.01 I Choice Importance:
                                  ~~
RO / SRO 3.1 13.2 1 Correct: I nco rrect : Incorrect Incorrect A B C D I Basis or Justification The "A" Chlorine detector causes a partial chlorine isolation.
I      Incorrect          B  WCS cannot be both IA and NRC Communicator (OP-LG-101-11I, Attachment 3)
The Loss of Div 3 DC completes the isolation and causes the "A CREFAS Fan to start due to de-energizing the trip logic. Therefore, a manual isolation is not required and only verification of the existing isolation. The procedure reference is correct, however the "A CREFAS is running. ~~~ The fan status is correct, however manual isolation is not required and only verification of the existing isolation.
I      Incorrect          D  If WCS is the IA, they support the STA function, the STA is stili required Level of      Difficulty Time Allowance        PRA                RO                      SRO Knowledge                      (minutes)                         10CFR55.41              10CFR55.43 Low          2.0             3                N                  N                    Y (b)(2)
The "A CREFAS is running and manual isolation is not required and only verification of the existing isolation.
Source Documentation Source:                    New Exam item                         0Previous NRC Exam 0Modified Bank item                     0Other Exam Bank 0ILT Exam Bank Reference(s):          OP-AA-101-11 I,page 5, step 4.5 OP-LG-101-111, page 11 #3 Learning              LLOTI 574.01a 0bjective:
Source: Reference(s):
Knowledge/Abiiity 2.1.4                                             importance:   RO / SRO KIA                                                                                2.3 f 3.4 (Description of K&A, from catalog)
Learning 0 bjective:
Knowledge of Shift Staffing requirements Required Materials:
Knowledge/Ability WA Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank E-IFC, SE-2 LLOT0450.03,07 (Description of K&A, from catalog) Ability to predict the impact of the following on the Control Room HVAC, and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiationheconfiguration Required Materials:
Notes and Comments Prepared By:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
              -             __         -                                          ~~
Limerick Generating Station                   ILT05-1 NRC Initial Licensing Examination
: 97. The   AChlorine detector fails upscale.
Subsequently, a loss of Div 3 DC power occurs.
WHICH ONE of the following describes the status of the     A CREFAS Fan and the procedure entered?
ACREFAS Fan                       Procedure A. Running                 S78.0.B Verification of MCR HVAC Isolation Signal B. Not Running               S78.0.B Verification of MCR HVAC Isolation Signal C. Running                 S78.8.A Manual Initiation of MCR HVAC Isolation D. Not Running               S78.8.A Manual Initiation of MCR HVAC Isolation Page 194 of 200
 
Limerick Generatinq Station                         ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 097 SRO Or       I I           Choice                                           Basis or Justification 1       Correct:           A   The A Chlorine detector causes a partial chlorine isolation. The Loss of Div 3 DC completes the isolation and causes the A CREFAS Fan to start due to de-energizing the trip logic. Therefore, a manual isolation is not required and only verification of the existing isolation.
Incorrect:          B    The procedure reference is correct, however the A CREFAS is running.
                                        ~~~
Incorrect          C    The fan status is correct, however manual isolation is not required and only verification of the existing isolation.
Incorrect          D    The A CREFAS is running and manual isolation is not required and only verification of the existing isolation.
Level of      Difficulty  Time Allowance          PRA                RO                      SRO Knowledge                        (minutes)                           10CFR55.41              10CFR55.43 High            3.0               4                N                  N                      Y (b)(5)
Source Documentation Source:                    New Exam Item                             0Previous NRC Exam 0Modified Bank Item                           0Other Exam Bank 0ILT Exam Bank Reference(s):          E-IFC, SE-2 Learning              LLOT0450.03,07 0bjective:
Knowledge/Ability 290003                                                Importance: RO / SRO WA                    A2.01                                                            3.1 13.2 (Description of K&A, from catalog)
Ability to predict the impact of the following on the Control Room HVAC, and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiationheconfiguration Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generatinq Station                   ILT05-1 NRC Initial Licensinq Examination
: 98. WHICH ONE of the following procedure revisions requires a Station Qualified Reviewer (SQR) review per AD-AA-101 and AD-AA-102?
: 98. WHICH ONE of the following procedure revisions requires a Station Qualified Reviewer (SQR) review per AD-AA-101 and AD-AA-102?
A. Changes to references in a Surveillance Test.
A. Changes to references in a Surveillance Test.
B. Editorial changes to an Operation's T&RM. C. Addition of clarifying information in the form of a list of required tools in a systems procedure.
B. Editorial changes to an Operation's T&RM.
C. Addition of clarifying information in the form of a list of required tools in a systems procedure.
D. Changes to activities in an Off-Normal Procedure.
D. Changes to activities in an Off-Normal Procedure.
Page 196 of 200 Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA Low 2.5 4 N Knowledge (mi nu tes) Answer Key RO SRO 1 OCFR55.41 1 OCFR55.43 N Y (b)(3) Choice ID Correct: Incorrect:
Page 196 of 200
I A IB Incorrect IC Incorrect i Basis or Justification Changes to activities in a procedure requires a SQR review Changes to reference are excluded from requiring SQR review Editorial change are excluded from requiring SQR review Addition of clarifying information is excluded from requiring SQR review Source: Reference( s): Learning 0 bjective:
 
Knowledge/Ability WA Source Documentation 0 New Exam Item Modified NRC Bank Item c] ILT Exam Bank c] Previous NRC Exam 0 Other Exam Bank extensively modified ILT exam bank item AD-AA-101, Page 3, step 4.3.5 LLOTI 570.01 3 2.2.6 I Importance:
Limerick Generating Station                         ILT05-1 NRC Initial Licensing Examination Answer Key i
RO / SRO 2.3 13.3 (Description of K&A, from catalog) Knowledge of the process for making changes in procedures as described in the safety analysis report. Required Materials:
Choice                                           Basis or Justification Correct:
Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick G enerat i ng Station ILT05-1 NRC Initial Licensing Examination
Incorrect:
II DA Changes to activities in a procedure requires a SQR review Changes to reference are excluded from requiring SQR review Incorrect IB      Editorial change are excluded from requiring SQR review Incorrect IC      Addition of clarifying information is excluded from requiring SQR review Level of    Difficulty  Time Allowance          PRA                  RO                  SRO Knowledge                      (minutes)                          10CFR55.41            10CFR55.43 Low          2.5              4                N                    N                Y (b)(3)
Source Documentation Source:                  0New Exam Item                               c]Previous NRC Exam Modified NRC Bank Item                    0Other Exam Bank extensively modified ILT exam bank item c]ILT Exam Bank Reference(s):          AD-AA-101, Page 3, step 4.3.5 Learning              LLOTI570.013 0bjective:
Knowledge/Ability 2.2.6                                               I Importance: RO / SRO WA                                                                                  2.3 13.3 (Description of K&A, from catalog)
Knowledge of the process for making changes in procedures as described in the safety analysis report.
Required Materials:
Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
 
Limerick Generat ing Station                     ILT05-1 NRC Initial Licensing Examination
: 99. Fuel is being loaded into the core on Unit 1 with the following conditions:
: 99. Fuel is being loaded into the core on Unit 1 with the following conditions:
0 "IA" SRM count rate is 3.5 cps and has a signal-to-noise ratio of 2.0 0 "1 B" SRM was declared inoperable last shift due to spiking 0 "IC" SRM count rate is 2.0 cps and has a signal-to-noise ratio of I .5 0 "ID" SRM count rate is 2.5 cps and has a signal-to-noise ratio of 2.0 WHICH ONE of the following describes the limitations, if any, regarding loading fuel into the core? A. Fuel may be loaded into any quadrant.
0   I A  SRM count rate is 3.5 cps and has a signal-to-noise ratio of 2.0 0   1B SRM was declared inoperable last shift due to spiking 0   IC SRM count rate is 2.0 cps and has a signal-to-noise ratio of I.5 0   I D  SRM count rate is 2.5 cps and has a signal-to-noise ratio of 2.0 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.
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 'ID" core quadrants ONLY.
C. Fuel may be loaded into A or D core quadrants ONLY.
Page 198 of 200 Limerick Generating Station ILTO5-I NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO Knowledge (mi nu tes) lOCFR55.41 Answer Key SRO 1 OCFR55.43 Question ID#
D. Fuel may be loaded into A , C or ID core quadrants ONLY.
099 SRO Or High Choice 3.0 4 N N (b) (7) Correct: Knowledge/Ability WA In correct: 2.2.28 Importance:
Page 198 of 200
RO / SRO 2.6 / 3.5 Incorrect Incorrect C A B D Basis or Justification "B" and "C' SRM's are inoperable
 
('IC due to inadequate signalhoise ratio, per T.S. fig 3.3.6-1) Therefore, Fuel movement is only permitted in quadrants "A and "D" per T.S. 3.9.2 See above See above Fuel cannot be loaded into quadrant "C" because its SRM is inoperable.
Limerick Generating Station                         ILTO5-I NRC Initial Licensing Examination Answer Key Question ID# 099 SRO Or Choice                                           Basis or Justification Correct:           C     B and CSRMs are inoperable (ICdue to inadequate signalhoise ratio, per T.S. fig 3.3.6-1) Therefore, Fuel movement is only permitted in quadrants Aand D per T.S. 3.9.2 Incorrect:          A    See above Incorrect          B    See above Incorrect          D    Fuel cannot be loaded into quadrant C because its SRM is inoperable.
___ Source: Reference(s):
Level of      Difficulty  Time Allowance          PRA                RO                      SRO Knowledge                      (minutes)                          10CFR55.41              10CFR55.43 High          3.0              4                N                  N                    (b) (7)
Learning 0 bjective: Source Documentation  
___
~ New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank T.S. 3.9.2 and Figure 3.3.6-1 LLOT0240.10 Required Materials: Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author Limerick Generatinq Station ILTO!%I NRC Initial Licensing Examination ATTACHMENT:
Source Documentation                                       ~
GP-I2 Provided 100. Unit 1 is at 100% power when the following occurs:
Source:                    New Exam Item                             0Previous NRC Exam 0Modified Bank Item                         0Other Exam Bank 0ILT Exam Bank Reference(s):        T.S. 3.9.2 and Figure 3.3.6-1 Learning              LLOT0240.10 0bjective:
At 0100, Chemistry reports the following results of a Reactor water sample: Conductivity is 2.5 pmho/cm pH is 5.4 Chloride concentration is 0.1 +y~+ b p 0 Hotwell conductivity is -c 0.1 pmho/cm and steady The RO reports a rising trend in Main Steam Line radiation. WHICH ONE of the following describes the required action(s)?
Knowledge/Ability 2.2.28                                              Importance:  RO / SRO WA                                                                                  2.6 / 3.5 Required Materials:
A. Check RWCU and Condensate Deep Bed Demin effluent conductivity to identify the source. B. Reduce power per GP-5, Appendix 2 and sequentially remove Circulating Water system loops from service to identify the source.
Notes and Comments Prepared By:
C. Begin a GP-3 shutdown by 0200 and place reactor in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours. D. Perform an engineering evaluation to determine the effects of any out- of-limit conditions on the structural integrity of the Reactor Coolant system. Page 200 of 200 Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination A B Answer Kev Basis or Justification ON-I 16 directs that with Conductivity  
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author
>I .O pmho/cm AND Main Steam line radiation high AND ph low, to determine if RWCU or Condensate Deep Beds are passing resin This action would be correct if hot well conductivity were rising, which is not indicated - I C Choice ~~~ This action would be appropriate if GP-12 action level 3 (>5 ymhokm) were reached Correct: D Incorrect:
 
This action would be appropriate if the plant was in any OPCON other than 1,2or3 Incorrect Level of Knowledge High Incorrect Difficulty Time Allowance PRA RO SRO (minutes) 1 OCFR55.41 1 OCFR55.43 3.0 4 N Y (b)(lO) Y (b)(5) 2.1.34 Importance: RO
Limerick Generatinq Station                   ILTO!%I NRC Initial Licensing Examination ATTACHMENT: GP-I2 Provided 100. Unit 1 is at 100% power when the following occurs:
/ SRO 2.3 12.9 Source : Reference (s ): Learning 0 bjective : Knowledge/Ability K/A Source Documentation New Exam Item 0 Modified Bank Item 0 ILT Exam Bank 0 Previous NRC Exam 0 Other Exam Bank GP-12, Sect 3.3, ON-I 16, T&RM 3.4.4 LLOTI 030.12 (Description of K&A, from catalog) Ability to maintain primary and secondary plant chemistry within allowable limits. Required Materials:
At 0100, Chemistry reports the following results of a Reactor water sample:
GP-12 Notes and Comments Prepared By: Rick Rhode (61 0) 71 8-4085 Limerick Regulatory Exam Author}}
Conductivity is 2.5 pmho/cm pH is 5.4 Chloride concentration is 0.1 +y~+       pb 0 Hotwell conductivity is -c 0.1 pmho/cm and steady The RO reports a rising trend in Main Steam Line radiation.
WHICH ONE of the following describes the required action(s)?
A. Check RWCU and Condensate Deep Bed Demin effluent conductivity to identify the source.
B. Reduce power per GP-5, Appendix 2 and sequentially remove Circulating Water system loops from service to identify the source.
C. Begin a GP-3 shutdown by 0200 and place reactor in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours.
D. Perform an engineering evaluation to determine the effects of any out-of-limit conditions on the structural integrity of the Reactor Coolant system.
Page 200 of 200
 
Limerick Generatinq Station                       ILT05-1 NRC Initial Licensing Examination Answer Kev -
I Choice                                        Basis or Justification Correct:          A    ON-I 16 directs that with Conductivity > I .O pmho/cm AND Main Steam line radiation high AND ph low, to determine if RWCU or Condensate Deep Beds are passing resin Incorrect:          B    This action would be correct if hot well conductivity were rising, which is not indicated
                                                                                          ~~~
Incorrect          C    This action would be appropriate if GP-12 action level 3 (>5 ymhokm) were reached Incorrect          D   This action would be appropriate if the plant was in any OPCON other than 1,2or3 Level of     Difficulty Time Allowance         PRA                 RO                     SRO Knowledge                      (minutes)                         10CFR55.41               10CFR55.43 High          3.0             4               N               Y (b)(lO)                 Y (b)(5)
Source Documentation Source:                   New Exam Item                           0Previous NRC Exam 0Modified Bank Item                       0Other Exam Bank 0ILT Exam Bank Reference(s):          GP-12, Sect 3.3, ON-I 16, T&RM 3.4.4 Learning              LLOTI030.12 0bjective:
Knowledge/Ability 2.1.34                                              Importance: RO / SRO K/A                                                                                  2.3 12.9 (Description of K&A, from catalog)
Ability to maintain primary and secondary plant chemistry within allowable limits.
Required Materials:
GP-12 Notes and Comments Prepared By:
Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author}}

Revision as of 12:55, 23 November 2019

Final - RO & SRO Written Examination with Answer Key (401-5 Format) (Folder 3)
ML063240233
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 10/10/2006
From:
Exelon Generation Co
To: Todd Fish
Operations Branch I
Sykes, Marvin D.
References
Download: ML063240233 (200)
v • d • e


Text

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination

1. WHICH ONE of the following describes the reason for a reactor scram that occurs as a result of a Main Turbine trip?

A. Limits positive reactivity due to a reduced void concentration when turbine stop valves close.

B. Minimizes level transient that occurs when feed pumps swap to high pressure steam.

C. Limits positive reactivity due to increased feedwater su b-cooling when extraction steam is lost.

D. Minimizes level transient that occurs when voids collapse due to turbine control valves closing.

Page 2 of 200

Limerick Generatinq Station lLTO5-1 NRC Initial Licensinq Examination I Answer Kev c Choice Correct:

Incorrect A

B Basis or Justification Void concentration will rapidly decrease on closing of the turbine steam admission valves resulting in a large positive reactivity addition.

While the reactor feed pumps do swap from cross-around(LP) steam to main steam (HP) and this does contribute to the post-scram level transient that will occur, it is not part of the basis for the scram.

Incorrect C While this will occur, the Reactor power rise will be slight and gradual. This is not the reason for the Scram.

-t Incorrect D While this level transient will occur, it is not part of the basis for the scram I Psychometrics Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 Low 2.5 2 Y (b) (5) N/A Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(sk LGS UFSAR, Chapter 15.2, LGS Tech Specs, LSSS Learning LLOTI575.03 0bjective:

Knowledge/Ability 295005 Importance: RO / SRO WA AK3.01 3.8 I 3.8 (Description of K&A, from catalog)

Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP:

Reactor scram Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination

2. Unit 2 plant conditions are as follows:

0 Reactor power is 100%

0 Plant Monitoring System (PMS) is inoperable Five minutes later control rod 30-31 inadvertently scrams.

WHICH ONE of the following can be used to confirm that control rod 30-31 is fully inserted?

A. XX (two X s ) on the Four Rod Display.

B. Green IN light is lit on the Full Core Display.

C. - -I (two dashed lines) on the Four Rod Display.

D. Blue SCRAM light is lit on the Full Core Display.

Page 4 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key I Choice I Basis or Justification Correct: The full in and full out lights on the Full Core Display continue to function with PMS and RDCS inoperable.

Incorrect Two Xs on the Four Rod Display indicate that control rod indication is unknown, due to more than one reed switch being made up.

Incorrect C A - - indication on the Four Rod Display indicates an odd numbered reed switch is made up.

D The blue SCRAM light on the Full Core Display indicates that the scram valves are open, and does not indicate control rod position.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 LOW 2.0 3 N (b) (10) (b) (5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0 Modified Bank Item 0Other Exam Bank 0 ILT Exam Bank Reference(s): ARC 108 Reactor, E-4 Learning LLOTOO80.02 0bjective:

Knowledge/Ability 295006 Importance: RO / SRO KIA AA2.02 4.3 / 4.4 Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

3. LGS site conditions are as follows:

Both units are at 100% power 0 Both units Auxiliary transformers are supplying their respective Unit Auxiliary busses 0 The 10 Station Auxiliary Bus is de-energized for maintenance 0 All other station electrical busses are energized Subsequently, the 20 Station Auxiliary Bus supply breaker (205) trips open.

WHICH ONE of the following identifies the status of the 22 Auxiliary Bus and the D22 Safeguard Bus twenty (20) seconds later?

22 Auxiliarv Bus D22 Safeguard Bus A. De-energized De-energized B. Energized De-energized C. De-energized Energized D. Energized Energized Page 6 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination r- ~ Answer Key Correct: D The 22 Aux Bus will continue to be supplied by the Unit 2 Main Generator D22 Diesel Generators will start and supply the D22 Safeguard Bus in approximately I O seconds.

Incorrect A Both busses will be energized as described above.

Incorrect Incorrect IBl While this choice is correct for the 22 Aux Bus, it is incorrect for D22 Safeguard Bus, which will be energized by the D22 D/G within 10 seconds While this choice is correct for the D22 Safeguard Bus, it is incorrect for the 22 Aux Bus, which will remain energized from the Unit 2 Main Generator.

~

Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 -

HIGH 3.5 3 Y (b) (10) (b) (5)

Source: [XI New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank I7 ILT Exam Bank Reference(s): E10/20, Steps 2.1 and 2.3.1 Learning LLOT0640.08 0bjective:

Knowledge/Ability 295003 Importance: RO / SRO WA AA2.04 3.5 13.7 Required Materials :

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-I NRC Initial Licensing Examination

4. Unit I plant conditions are as follows:

0 Reactor Power is 100%

0 Division 4 DC (125 VDC Bus D) is de-energized The following events then occur:

0 Drywell Pressure rises to 2.0 psig Both HPCl Exhaust Diaphragms rupture on pump start 0 HPCl room temperature rises and stabilizes at 198°F 0 No operator action is taken WHICH ONE of the following describes the status of HPCl steam line containment isolation valves after the events above?

INBOARD ISOL (I F002) OUTBOARD ISOL (1F003)

A. Closed Open B. Closed Closed C. Open Closed D. Open Open Page 8 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key SRQ Basis or Justification Correct: C A HPCl isolation signal is present due to high turbine exhaust rupture diaphragm pressure. The 1F003 valve isolates, however, the 1F002 valve does not isolate due to NO control power to the isolation logic.

Incorrect A The 1FOO2 valve does not isolate due to NO control power to the isolation logic Incorrect B The IF002 valve does not isolate due to NO control power to the isolation logic Incorrect D The 1F003 valve isolates Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 HIGH 3.0 3 Y (b) (7) N/A Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0 ILT Exam Bank Reference(s): GP-8.1, Rev.11, Pg. 31; GE Elemental Dwgs. M-1-E41-1030-F-004, Shts. 1 & 2 M-1-E41-1030-F-005, Shts 1 & 2 Learning LLOT0340.14 Objective:

Knowledge/Ability 295004 I Importance: RO / SRO WA I AA1.02 3.8 / 4.1 Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

5. Unit 1 plant conditions are as follows:

0 Drywell Temperature is 140°F 0 Drywell Pressure is 1.0 psig and rising slowly 0 OT-101, HIGH DRYWELL PRESSURE, is being executed WHICH ONE of the following is a reason why Drywell cooling is maximized?

A. Ensure continued operation of the Reactor Recirculation Pump motors.

B. Slow the rate of pressure rise to allow time to bypass the potential Drywell Chilled Water system isolation.

C. Protect the integrity of the ADS valve solenoids.

D. Slow the rate of pressure rise to allow Drywell venting.

Page 10 of 200

Limerick Generating Station ILT05-1 NRC initial Licensing Examination Answer Key 3R-0 Choice Basis or Justification Correct:

I D Per OT-I01 bases, the Drywell may be vented if pressure is less than 1.68 psig. Therefore, slowing the rate of Drywell pressure rise allows time to vent.

Incorrect I A The reason for Maximizing Drywell cooling is to slow the rise or prevent reaching 1.68 psig in the Drywell. It is not to protect the Recirc pumps.

Incorrect Incorrect II Bc The Drywell chill water isolation may be bypassed after entry into and meeting the Drywell temperature requirementsof T-I 02 The design Drywell temperature of 340°F is to protect the ADS solenoids.

This is beyond the bases for OT-I 01.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minUtes) 10CFR55.41 10CFR55.43 LOW 2.5 2 N (b) (5) N/A Source Documentation Source: [xi New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s ): OT-I01, Bases Step 2.1 Learning LLOTI540.05 0bjective:

Knowledge/Ability 295010 Importance: RO / SRO WA AK3.02 3.4 I 3.4 Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

6. Unit 2 plant conditions are as follows:

0 The 2B Recirc. Pump has tripped 0 Reactor power is 68%

0 All feedwater heaters are in service 0 Four OPRM channels are operable The unit is in the Restricted Region of the Power to Flow map Subsequently, the 2A Recirc Pump inadvertently trips.

WHICH ONE of the following describes the required action and the basis for this action?

A. SCRAM to prevent the occurrence of thermal hydraulic instabilities.

B. Restart a Recirc Pump to prevent RPV thermal stratification.

C. SCRAM to avoid the reactivity effects of starting a Recirc Pump in natural circulation.

D. Insert control rods to exit the Restricted Region of the Power to Flow map.

Page 12 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key I

Choice Basis or Justification Correct: C Although allowed by Tech. Specs., Exelon has decided to continue to direct that a manual scram be inserted with the plant in natural circulation.

Incorrect:

lA/ A scram is required, however, not to avoid THI. See basis for answer C.

Incorrect IBl By procedure, Limerick does not allow restarting a Recirc. Pump in natural circulation with the Reactor critical.

Incorrect I D / This is not an allowed action in natural circulation.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 LOW 2.0 2 N (b) (8) to (IO) NIA Source: [XI New Exam Item 0 Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): OT-I f 2 Bases, step 2.1 Learning LLOTI540.05 Objective:

KnowledgelAbility 295001 Importance: RO / SRO KIA AKI .01 3.5 13.6 Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILTO5-1 NRC Initial Licensinq Examination

7. Unit 1 plant conditions are as follows:

0 Reactor power is 35%

0 GEN STATOR COOLANT TROUBLE (125 B4) Annunciator is alarming An EO verifies the Stator Cooling Water return temperature is 82OC and rising.

WHICH ONE of the following describes the automatic response of EHC due to the conditions above?

A. LOAD SET will reduce to 21.4%

Bypass valves will remain closed B. LOAD SET will reduce to 21.4%

Bypass valves will open C. LOAD LIMIT will reduce to 21.4%

Bypass valves will open D. LOAD LIMIT will reduce to 21.4%

Bypass valves remain closed Page 14 of 200

Limerick Generating Station ILTO5-I NRC Initial Licensing Examination Answer Key

~

Incorrect D This is incorrect as load limit does not runback, also bypass valves will open Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 5 High 3.0 4 Y b)7 N Source Documentation Source: New Exam Item c]Previous NRC Exam 0Modified Bank Item 0Other Exam Bank c]ILT Exam Bank Reference(s): ON-I 14, Step 2.10 Learning LLOT0590.03 0bjective:

Knowledge/Ability 295007 Importance: RO / SRO WA AA1.05 3.7 / 3.8 (Description of K&A, from catalog)

Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE:

Reactorrrurbine Pressure Regulating System

!quired Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination ATTACHMENT: SE-1 Provided

8. The Main Control Room has become uninhabitable and SE-1, Remote Shutdown, is in progress at the Remote Shutdown Panel with the following conditions:

0 All SE-1 immediate operator actions are complete 0 All Remote Shutdown Panel transfer switches are in EMERGENCY 0 Reactor Level is + I O 0 Reactor Pressure is 490 psig WHICH ONE of the following identifies the EARLIEST point from now where Shutdown Cooling can be placed in service?

A. 1.0 Hours B. 1.5 Hours C. 2.0 Hours D. 2.5 Hours Page 16 of 200

Limerick Generating Station ILTO5-I NRC Initial Licensinq Examination I Choice Basis or Justification I Correct: B Using Attachment 2 and 3 to SE-1 and at the maximum cooldown rate, it would take at least 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to go from 470 degrees F (490 psig) to 320 degrees F (75 psig)

Incorrect A This would mean exceeding the maximum cooldown rate 1 Incorrect C This does not identify the minimum amount of time before SDC can be placed in service.

I-----Incorrect D This does not identify the minimum amount of time before SDC can be placed in service.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.5 5 Y (b) (IO) (b) (5)

Source: New Exam Item [7 Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): SEI, Attachments 2 & 3 Learning LLOT0735.04 0bjective:

Knowledge/Ability 295016 Importance: RO / SRO WA 2.1.25 2.8 t 3.1 Required Materials:

SE-1 Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination

9. Both units are at 100% power:

0 A loss of the 220 KV switchyard occurs followed immediately by a lockout of the 4A Auto Transformer 0 The D12 and D14 Diesel Generators fail to start 0 All other Diesel Generators start as designed WHICH ONE of the following systems can be used to provide alternate cooling to the TECW heat exchangers and the procedural direction for using this system?

Alternate Cooling Water for TECW Heat Exchanqers Procedural Direction A. ESW E-l0/20, Loss Of Offsite Power B. ESW E-I, Station Blackout C. RECW E-l0/20, Loss Of Offsite Power D. RECW E-I, Station Blackout Page 18 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key I Choice I Basis or Justification Correct: ESW can be used to backup normal Service Water for TECW and RECW

/A( by performing manual local valve manipulations per E-I 0/20.

Incorrect The correct procedure is E-10/20. Since six of the Diesel Generators start, this is not a Station Blackout.

Incorrect RECW is not hard piped to backup TECW.

(c/ RECW is not hard piped to backup TECW. The correct procedure is E-Incorrect D 10/20. Since six of the Diesel Generators start, this is not a Station Blackout.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 Y (7) N/A Source Documentation Source: 0New Exam item 0Previous NRC Exam Modified Bank item 0Other Exam Bank ILT Exam Bank Reference(s): E-I 0/20, Attachment 5 Learning LLOT0430.07 Objective:

Knowledge/Ability 295018 Importance: RO / SRO KIA AA1.01 3.6 13.5 (Description of K&A, from catalog)

Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Backup systems Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination IO. Unit 1 Reactor Power is 100% with Instrument Air and Service Air in a normal lineup, when the following annunciator alarms:

0 I A INSTRUMENT AIR HEADER LO PRESS ( I 18 B2)

The following indications are observed:

0 I A Instrument Air Header Pressure is 85 psig and dropping slowly.

0 1B Instrument Air Header Pressure is 108 psig and steady 0 Service Air Header Pressure is 102 psig and rising slowly 0 Backup Service Air Receiver is 100 psig and steady 10 minutes later the following indications are observed:

0 I A Instrument Air Header Pressure is 69 psig and dropping slowly 0 1 B Instrument Air Header Pressure is 100 psig and dropping slowly 0 Service Air Header Pressure is 99 psig and dropping slowly 0 Backup Service Air Receiver is 102 psig and dropping slowly WHICH ONE of the following identifies the source of air for the Instrument Air LOADS and Service Air LOADS?

Source of Instrument Air Source of Service Air A. I B Instrument Air compressor Service Air Compressor B. 1 B Instrument Air Compressor Backup Service Air Compressor C. Service Air Compressor Service Air Compressor D. Service Air Compressor Backup Service Air Compressor.

Page 20 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 010 Both RC ERej Choice Basis or Justification Correct: A 1B Compressor will begin supplying the IA loads on higher pressure due to check valves at the individual load. Service Air Compressor remains in service for service air loads.

Incorrect: I B The Backup Service Air Compressor, which is normally lined up to Unit 1, will only supply Unit 1 Service Air, if service air header pressure drops below 92 psig..

Incorrect Service Air Compressor would only supply IA if both the 1A & 1B IA header pressures were low.

See B and C above Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.0 6 Y Y (b) ( 5 ) N Source: [E3 New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank

[7 ILT Exam Bank Reference(s): M-I 5 Learning LLOT0730.02, 04,07, I O 0bjective:

Knowledge/Ability 295019 Importance: RO / SRO WA AK3.01 3.3 13.4 Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination 1I. Unit 2 has just entered Opcon 4 in preparation for a refueling outage.

A failure of HV-51-2F008 results in a loss of Shutdown Cooling and necessitates establishing Alternate Shutdown Cooling using SRVs and Suppression Pool Cooling.

Conditions have been established as follows:

Suppression Pool Cooling is in service with 2A RHR.

Suppression Pool pressure is 0 psig SRV handswitches for the 2Kand 2M SRVs are in the OPEN position Injection to the RPV has been established with the 2D RHR pump via HV-51-2F017D RPV Level is 150 on Shutdown Range RPV pressure is 40 psig WHICH ONE of the following describes the action required in order to establish Alternate Decay Heat removal?

A. Reduce RPV injection until RPV Level is 5 100.

B. Increase RPV injection until RPV Level is 2 200.

C. Reduce RPV injection until RPV pressure is 5 25 psig.

D. Increase RPV injection until RPV pressure is 2 50 psig.

Page 22 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice I Basis or Justification Correct D 50# DIP is required across the SRVs in order to open and establish alternate heat removal.

Incorrect A While 1 0 0 is an important milestone in OT-100 Reactor High Level, when trying to prevent filling MS lines, filling the MSLS is required for this procedure.

Incorrect B Level is high enough to fill the MSLs and no additional Level is required.

Incorrect C In order to establish Alternate heat removal the SRVs must open which requires 50# D/P. Correct conditions require raising pressure, not lowering.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.0 5 Y Y (b) (7) N Source: [XI New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ON-121, Step 2.1.7, Attachment 6 S41.7.B, Step 4.2 Learning LLOT-5010.01 0bjective:

Knowledge/Ability KIA 1 295021 AA1.04 (Description of K&A, from catalog)

Importance: RO / SRO 3.7 13.7 Ability to operate and or monitor the following as they apply to LOSS OF SHUTDOWN COOLING:

Alternate Heat Removal Methods Required Materials Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

12. Unit Iplant conditions are as follows:

0 Reactor level is 20 0 Reactor Pressure is 350 psig 0 Drywell Pressure is 25 psig 0 1B RHR Pump is operating at 8200 gpm with the following valve indications:

HV-51-1F016B, OUTBOARD SPRAY, green light lit HV-51-1F017B, LPCl INJECTION, red, green and white lights lit HV-51-1F021B, INBOARD SPRAY, red light lit HV-51-1F024B, FULL FLOW TEST, red, green and white lights lit The CRS has directed the PRO to place I B RHR in Drywell Spray.

WHICH ONE of the following actions must be performed to initiate Drywell Spray?

A. Arm and depress I B RHR manual LOCA initiation pushbutton and open HV-51-1F016B.

B. Close HV-51-1FO21B, then open HV-51-1F016B, then reopen HV-51-1F021B.

C. Close HV-51-1F017B and open HV-51-1F016B.

D. Close HV-51-1F024B and open HV-51-1FOI 6B.

Page 24 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 012 Both RC Choice Basis or Justification Correct IC 17B valve must be closed in order to open 16B - all other conditions for opening 16B are already .

r lA Incorrect LOCA Signal already present. PB not required. Also 178 must be closed.

Incorrect This valve manipulation only required if LOCA signal not present. 17B must also be closed..

~~ ~ ~~ ~~

Incorrect 24B dose not need to be closed Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 4 Y Y (b) (7) N Source Documentation Source: I New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference@): T-225, Step 4.5 Learning Objective: I LL0T0370.09 WA 1 Knowledge/Ability 295024 EA1.04 Importance: RO / SRO 4.1 13.9 (Description of K&A, from catalog)

Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:

RHWLPCI Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

_ _- ___ --

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

13. An ATWS is in progress on Unit 1.

RPV Level was intentionally lowered per T - I 17.

The following conditions currently exist:

Reactor power is 6%

RPV level is -1 95 and slowly rising MSIVs are closed 1 ADS SRV is open RPV pressure is I 0 0 0 psig Suppression Pool temperature is 145°F and slowly rising 2 Loops of Suppression Pool Cooling are in service Suppression Pool pressure is 6 psig & slowly rising Suppression Pool level is 24.5 and stable WHICH ONE of the following describes the required action and the reason for taking the action?

A. Reduce RPV pressure to less than 900 psig, in order to maintain on the safe side of SP/L-1 SRV Tail Pipe Level Limit.

B. Perform Emergency Blowdown per T-I 12, due to unable to restore and maintain RPV Level above -1 86.

C. Reduce RPV pressure to less than 900 psig, in order to maintain on the safe side of SP/T-1 Heat Capacity Temperature Limit.

D. Perform Emergency Blowdown per T - I 12, due to the safe side of SP/T-I,Heat Capacity Temperature Limit, cannot be maintained.

Page 26 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Choice Basis or Justification SP temp is 20°F from HCTL and rising slowly despite having 2 loops of SP Cooling in service. T-102 SPK-8 directs that if SP temp cannot be maintained on the safe side of HCTL, then maintain RPV pressure on the safe side of HCTL.

Incorrect A SP level is high but 3.5feet away from SP/L-l limit and level is stable -

Reducing pressure for the purposes of maintaining this curve is not warranted.

While RPV Level is e-186, it is only 9OOB and rising slowly. The criteria for T-l17LQ is level can be restored. With SRVs being used for pressure control, it is not unusual to go e-186 for short periods of time. T-I12 is not warranted under these conditions.

Incorrect D SP temp is still 20°F away from HCTL and rising slowly. T-I12 is not warranted at this point Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 Y Y (b) ( I O ) Y (b) (5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank T-102 sh.1 Learning LLOTI560.04 0bjective:

KnowledgelAbility 295026 Importance: RO / SRO EA2.03 3.9 / 4.0 (Description of K&A, from catalog)

Ability to determine and/or interpret the following as it applies to Suppression Pool water temperature:

Reactor Pressure Required Materials:

T-102 Sht. I Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

___ ____

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

14. A LOCA is in progress on Unit 2.

Drywell Temperature is 148°F.

The CRS directs the PRO to maximize drywell cooling.

Per T-I02 Bases, WHICH ONE of the following describes the minimum number of components that must be in service in order to maximize drywell cooling for the above conditions?

Drywell Fans DWCW Pumps A. One Fan per Cooler One B. One Fan per Cooler Two C. Two Fans per Cooler One D. Two Fans per Cooler Two Page 28 of 200

Limerick Generating Station ILT05-I NRC Initial Licensing Examination Answer Key I Choice I Basis or Justification I Correct: B 1 Meets the criteria specified in T-102 Bases, for step DW/T-5 r Incorrect:

Incorrect A

C

!

Does not meet the criteria specified in T-I 02 Bases, step DW/T-5. Only has one DWCW pp cunning vs. two Does not meet the criteria wJrespect to the number of required DWCW pps.

In addition specifics 2 DW Fans per cooler. Fans are in parallel and are 100% capacity.

Incorrect D Does not represent the minimum number. 2 DW fans in-service - DW fans are 100% capacity and in parallel.

I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 Y (b) (7) N Source Documentation Source: New Exam Item 17Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T-102 Bases, DW/T-5 Learning LOT-1560.06 0bjective:

Knowledge/Ability 295028 Importance: RO J SRO WA EK2.04 3.6 J 3.6 Required Materials:

T-I 02 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

15. Unit 2 was manually scrammed due to a leak in the Suppression Pool.

0 Suppression Pool level is 20 and lowering 0 RClC is being used for RPV level control 0 HPCl is being used for RPV pressure control Suppression Pool level drops to 17.9.

WHICH ONE of the following describes the required action and the reason for it?

A. RClC must be secured due to insufficient net positive suction head.

B. HPCl must be secured due to insufficient net positive suction head.

C. RClC must be secured in order to prevent direct pressurization of the Suppression Pool.

D. HPCl must be secured in order to prevent direct pressurization of the Su pp ression Pool.

Page 30 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Incorrect IBl NPSH limit for HPCl would be at 15.42 ft, where it is already secured at 18 for the reason above Incorrect RClC Turbine exhaust pressure is insufficient to cause pressurizationof the Suppression Pool in excess of PCPL.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 Y Y (b) (5) N/A Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item c]Other Exam Bank 0ILT Exam Bank Reference(s): T-102, sh. 1 Learning LLOTI560.05 0bjective:

Knowledge/Ability 295030 Importance: RO / SRO WA EK3.02 3.5 / 3.7 (Description of K&A, from catalog) Knowledge of the reasons for the following responses as they apply to Low SP Water Level: HPCl Operation Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generatinn Station lLTO5-1 NRC Initial Licensing Examination

16. A loss of all high pressure injection has occurred on Unit 1 with conditions as follows:

0 All rods in 0 RPV Water Level is -170 and dropping 0 No low pressure ECCS pumps can be started 0 RPV pressure has been recorded at 900 psig and is being maintained with SRVs The crew is attempting to restore the 1B CRD pump and line up per T-240.

WHICH ONE of the following describes steam cooling conditions under which adequate core cooling is assured?

RPV Level RPV Pressure lniection A. -1 75 795 psig None B. -185 800 psig 1B CRD pump C. -1 95 910 psig None D. -205 890 psig 1B CRD pump Page 32 of 200

Limerick Generatina Station ILT05-I NRC Initial Licensing Examination

~~

Answer Key Question ID# 016 Both-R( SRd Choice Basis or Justification Correct: A Core Cooling is assured in steam cooling as long as level is between -161 and -201, with no injection and pressure less than the value recorded in T-IIILR-14. Even though pressure is <I OO# below recorded value, this supply calls for a new pressure load.

1 ~ Incorrect B Calculations for MZI RWL assures that there is no sub cooling at the core inlet. Since any injection would invalidate this assumption, adequate Core Cooling cant be assured if RPV level is <-I61 and water is being injected.

Incorrect C Once stabilized, if RPV pressure rises above the value recorded in CR-14, MZIRWL calculations are no longer valid and the core may not be adequately cooled.

Incorrect D The candidate would select this answer if he didnt recognize that the safe area of this curve is below the curve. This is a common error because this varies between curves. It is also incorrect because water is being injected.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 5 Y (b) (8-10) NIA Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 1 0Other Exam Bank ILT Exam Bank Reference(s): T-I 11 BASES, LR-12 through LR-17 Learning LOT-1560.03 Objective:

Knowledge/Ability WA 295031 Importance: RO / SRO WA EKI .01 4.6 14.7 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination

17. Unit 1 conditions are as follows:

0 Core reload has just commenced during a refueling outage.

0 SRM count rate is 30 cps While lowering a fuel assembly not adjacent to an SRM, count rate increases to 65 cps and stabilizes.

WHICH ONE of the following describes the required action, if any?

A. Immediately evacuate the refuel floor.

B. Suspend component movement.

C. Continue lowering fuel assembly.

D. Raise the fuel assembly from the core so that it clears the upper grid.

Page 34 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Correct:

is reached Incorrect A This would only be appropriate in the event of criticality.

I Incorrect C FH-105 requires suspension of component movement when one doubling is reached Incorrect D This action is not required if it is the 1 through 4'h fuel assembly adjacent to the detector at the start of a core reload.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minUtes) 10CFR55.41 10CFR55.43 Low 2.0 3 Y (b) (8-10) N/A Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): FH-105, STEP 3.7 Learning LLOT0760.12 Objective:

Knowledge/Ability 295023 Importance: RO / SRO KIA 2.2.28 3.5 / 3.3 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination

18. An ATWS is in progress on Unit 1.

Reactor Power is 100%.

A Group 1 NSSSS isolation occurs and SRVs open to lower RPV pressure.

The PRO is controlling RPV pressure 990 - 1096 psig with SRVs.

The highest recorded RPV steam dome pressure was 1340 psig.

WHICH ONE of the following describes actions that satisfy the MOST LIMITING Tech Spec requirements?

A. Notify the NRC and be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

B. Place RPS in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in HOT SHUTDOWN within I 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

C. Notify the NRC within Ihour and be in HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

D. Be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 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 />.

Page 36 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice Basis or Justification Correct: C Reactor Coolant System Pressure Safety Limit has been violated. Tech Spec action must satisfy 2.1 and 6.7.1 Incorrect A States the NRC must be notified and meets 3.0.3 for LCO not met and 3.3.4 for ATWS Instrumentation but is not conservative enough to meet 2.1 and 6.7.1 Incorrect B Meets 3.3.1 for RPS Instrumentation but is not conservative enough to meet 2.1 and does not meet 6.7.1 Incorrect D This meets 3.4.2 for SRV's and 3.4.6.2 for Reactor Steam Dome Pressure, but is not conservative enough to meet 2.1 and does not meet 6.7.1 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 3.5 5 N (b) (8-10) NIA Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): LGS Tech Specs Learning LLOTI540.05 0bjective:

KnowledgelAbility 295025 Importance: RO I SRO KIA EKI .05 4.41 4.7 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

~ -

Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination

19. Unit 1 plant conditions are as follows:

0 Reactor Power is 8%

0 Reactor mode switch is in STARTUP

'W IRM is failed upscale &Q, \@(ob

" ID" An electrical fault results in the loss of 1AY160.

WHICH ONE of the following identifies the impact on IRMs and status of RPS?

A. IRM Channels A, C, E, and G lose power, Full Reactor Scram.

B. ONLY IRM Channels A, and C, lose power, Full Reactor Scram.

C. IRM Channels A, C, E, and G lose power, Reactor 1/2 Scram ONLY.

D. ONLY IRM Channels A, and Cylose power, Reactor 1/2 Scram ONLY.

Page 38 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination I Answer Kev I Question ID# 0'19 Both RC

~ ~

Basis or Justification Correct: A IRM Channels A, C, E, and G loss power on a loss of 1AY160, Full Reactor Scram occurs due to mode switch in startup and RPS A side % scram loss of 1AY160 and RPS B side % scram (D IRM upscale)

Incorrect: B ONLY IRM Channels A, and C, loss power is incorrect as E & G channels also lose power, Full Reactor Scram is correct Incorrect: C IRM Channels A, C, E, and G loss power is correct, Reactor 1/2 Scram is r---

incorrect as full reactor scram will occur Incorrect: D ONLY IRM Channels A, and C is incorrect as E & G channels also lose power, Reactor 1/2 Scram is incorrect as full reactor scram will occur Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 N (b) 7 N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): E-1AY160, Step 1.2 and 1.22, AND GP-2, Caution before step 3.4.7 Learning LLOT0250.07 Objective:

Knowledge/Ability 215003 Importance: RO / SRO WA K2.01 2.5 / 2.7 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLT05-I NRC Initial Licensinq Examination

20. Unit 1 Plant conditions are as follows:

0 Reactor Startup is in progress 0 1 A and ID IRMs are on range 1 0 All other IRMs are on range 2 1 A SRM is being withdrawn when the count rate drops to 90 CPS.

WHICH ONE of the following identifies the impact on the Reactor Manual Control System (RMCS)?

A. No rod blocks are enforced.

B. Only a rod withdraw block is enforced.

C. Only a rod insert block is enforced.

D. Both rod insert and withdrawal rod blocks are enforced.

Page 40 of 200

Limerick Generatinq Station ILT05-1 NRC initial Licensina Examination Answer Key Choice Basis or Justification Correct: B Only a rod withdraw blocks is enforced, is correct as all IRMs are not above range 2 and SRM CPS are less than 100 with detector not full in Incorrect A No rod blocks are enforced, is not correct. It would be correct if all IRMs were above range 2 Incorrect C Only a rod insert block is enforced. This is not correct as SRM CPS less than 100 with detector not full in does not enforce an insert block Incorrect D Rod insert and withdrawal rod blocks are enforced SRM CPS are less than 100 with detector not full in Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 4 N (b) ( 5 ) N Source: Ix] New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-2Appendix 1, step 3.3.7 and NOTE Learning LLOT0240.06:

0bjective:

Knowledge/Ability 215004 Importance: RO / SRO WA K5.03 2.8 12.8 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

21. Unit 2 is at 100% power.
  1. 2 APRM output fails to 2%.

WHICH ONE of the following completes the statement below?

91 The 2B Rod Block Monitor channel A. initiates a rod block B. automatically goes to Bypass mode C. automatically swaps to reference #3 APRM D. automatically swaps to reference ##4APRM Page 42 of 200

Limerick Generating Station ILT05-I NRC Initial Licensing Examination I Answer Key I Choice I Basis or Justification Correct: B The RBM sees less than 30% power from its reference APRM and Auto Bypasses Incorrect A Rod Block results an Upscale, Downscale, or hop condition. Failure of the reference APRM will NOT cause a RBM hop or Downscale.

Incorrect C The reference APRM would only swap if the primary APRM channel were INOP or Bypassed. This failure does not constitute these conditions. The alternate reference APRM for #2 is #4.

Incorrect D ##4APRM is the correct alternate, however, the reference APRM would only swap if the primary APRM channel were INOP or Bypassed.

I I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 4 N (b) (2) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): ARC 108, A-5 .

Learning LLOT0280.09a 0bjective:

KnowledgelAbility 215005 Importance: RO I SRO WA K1.03 3.4 13.5 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILTOS-I NRC Initial Licensing Examination

22. The CRS has ordered a GP-4 shutdown as a result of the 1E SRV being stuck open.

Following the performance of GP-4 actions plant conditions are as follows:

0 Reactor power is 28%

0 CRS has entered T-I 17 0 IE SRV is still open 0 Suppression Pool temperature is 112°F and going up 0 T-270 is complete, injection has been terminated Reactor level is -100 when reactor power is noted to be below 4%.

WHICH ONE of the following describes the correct RPV water level band and the basis for this band?

A. -60 to -100 in order to lower power by reducing core inlet subcooling.

B. -60 to -100 in order to lower power by reducing natural circulation driving load and core flow.

C. -1 00 to -1 86 in order to lower power by reducing core inlet subcooling.

D. -100 to -186 in order to lower power by reducing natural circulation driving head and core flow.

Page 44 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key I Choice I Basis or Justification Correct: D Conditions are set for level lowering to below TAF. The bases for this level lowering is reduction of natural circulation driving head Incorrect A This is the appropriate level band and reasons for the first level lowering.

This is N/A once SP temp is II O " and SRV is open Incorrect B This level condition is not appropriate, the reason is associated with the

-161 to -186 level band Incorrect C This level band is correct, the reason is associated with the higher level band Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 5 Y (b) (5) N Source Documentation I Source: New Exam Item 0Previous NRC Exam LReference s :

Modified Bank Item 17 ILT Exam Bank T-I 17, T-I 17 Bases, LQ-6 through LQ-11 and LQ-16.

Other Exam Bank ILearning

Objective:

LLOTI 560.05 Knowledge/Ability 295037 EK.2.09 (Description of K&A, from catalog)

Importance: RO / SRO 4.0 / 4.2 Knowledge of the interrelations between SCRAM Condition Present and Reactor Power above APRM down SCL or unknown & the following...Reactor Water Level Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

23. Unit 2 is operating at 100% when a Turbine Trip occurs. Two minutes later the following conditions are noted:

Reactor Power is 0%

0 Rod 26-1 Iis at position 48 0 Rod 50-31 is at position 48 0 Rod 22-51 is at position 48 0 All other control rods are at 00 SLC is not running Subsequently, the RO begins to insert rods.

WHICH ONE of the following describes control rod positions that meet the criteria for NO ATWS?

A. Rods 26-1 I, 50-31, and 22-51 are at position 04.

B. Rod 26-1 Iand 50-31 are at position 02 and 22-51 is at position 04.

C. Rods 26-1 1 and 50-31 are at position 00 and 22-51 is at position 48.

D. Rod 26-1 1 is at position 00 and rods 50-31 and 22-51 are at position 48 .

Page 46 of 200

Limerick Generating Station lLTO5-I NRC Initial Licensing Examination Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.0 4 Y (b) (IO) (b) (5)

Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T-I 01, note 14, Tech Specs definition of Shutdown Margin Learning LLOTI560.03 0bjective:

KnowledgeIAbility 295037 Importance: RO I SRO WA EA 2.05 4.2 I 4.3 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

~

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

24. A radiological accident has caused the following annunciators to alarm:

NORTH STACK HI-HI RADIATION (003 E l )

NORTH STACK HI RADIATION (003 E2)

WHICH ONE of the following areas is the location of the radiation release, and what is the required action to mitigate the release?

A. Standby Gas Treatment Exhaust Enter and execute T - I 04 Radiological Release.

B. Standby Gas Treatment Exhaust Perform ST-6-104-880-0, Gaseous Effluent Dose Rate Determination.

C. Reactor Enclosure Equipment Compartment Exhaust Evacuate all unnecessary personnel per SE-24, Plant Evacuations.

D. Reactor Enclosure Equipment Compartment Exhaust Enter and execute T - I 03, Secondary Containment Control.

Page 48 of 200

Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination Choice Basis or Justification Correct: B Possible source, ST must be performed and LGS Emergency Plan annex, Table 3-1 must be consulted Incorrect A Possible source but alarm alone is not sufficient reason to enter and execute T-I 04

_ _ _ ~

Incorrect C Not a possible source based on the given conditions, although the action is plausible given this source Incorrect D Not a possible source based on the given conditions, although the action is plausible given this source Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 N (b) (7) N Source Documentation Source: [XI New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0 ILT Exam Bank Reference(s): ARC-MCR-003-EII ST-6-104-880-0, T-I 04 Learning LLOT0720.03 0bjective:

KnowledgelAbility 295038 Importance: RO I SRO KIA EK2.03 3.6 13.8 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

.__

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

25. Given the following plant conditions:

The Main Control Room has been abandoned due to a fire 0 Immediate actions of SE-I have been completed The Remote Shutdown Panel has been manned All Remote Shutdown Panel transfer switches have been placed in EMERGENCY Reactor pressure is 980 psig and rising slowly WHICH ONE of the following identifies the systems available for RPV level control?

A. RClC controlled manually, ONLY.

B. HPCl controlled manually, ONLY.

C. RClC controlled manually with HPCI cycling in AUTO.

D. HPCl controlled manually with RClC cycling in AUTO.

Page 50 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 025 Both RC $Fa Choice Basis or Justification Correct: C RClC is the primary means of level control from the Remote Shutdown Panel, but must be started up and shutdown manually. HPCl will cycle in AUTO as long as it has not been disabled.

Incorrect A RClC manual control is available, but HPCl will cycle in AUTO as long as it has not been disabled.

Incorrect B HPCl manual control is not available from the RSP. It can either be allowed to cycle in AUTO, or completely disabled from the RSP.

_ _ ~_ _ ~ __ ~~

Incorrect D HPCl will cycle in AUTO as long as it has not been disabled. RClC must be started up and shutdown manually.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 3 Y (b) (5) N Source: New Exam Item 0Previous NRC Exam c]Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): SE-1 step4.3 Learning LLOT0735.02, .03 Objective:

Knowledge/Ability 295016 Importance: RO I SRO WA AK2.01 4.4 / 4.5 (Description of K&A, from catalog)

Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and.. .Remote Shutdown Panel Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

__

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

26. Unit 2 Plant conditions are as follows:

0 Main Condenser vacuum is 20 and dropping 0 Reactor is scrammed 0 Main Turbine is tripped 0 Turbine speed is 100 RPM and slowly coasting down 0 Sealing Steam header pressure is 0 psig The CRS orders the PRO to break Main Condenser vacuum.

Per OT-I 16 Bases, WHICH ONE of the following describes the reason for this action?

A. Rapidly reduce turbine speed to prevent damage due to windage.

B. Reduce differential pressure across turbine seals to prevent turbine exhaust hood over-pressurization.

C. Rapidly reduce turbine speed to prevent damage due to uneven rotor heating.

D. Reduce differential pressure across turbine seals to prevent drawing cold air across the hot rotor.

Page 52 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 026 Both R( gij" Choice Basis or Justification Correct: D With no sealing steam pressure, main condenser vacuum will draw cold air across the seals and the hot turbine rotor Incorrect A Preventing windage damage is the reason why vacuum should not be broken greater than 1200 RPM Incorrect B Preventing Turbine exhaust hood over-pressurization is the reason for tripping the Main Turbine at 21.5" VAC Incorrect C Uneven rotor heating is a problem if sealing steam is applied to a stationary turbine rotor Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 4 Y (b) (7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s) : OT-I 16 BASES, step 3.3 Learning LLOTI 540.05 Objective:

Knowledge/Ability 295002 Importance: RO / SRO WA AK2.11 2.6 12.7 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination

27. A reactor startup is in progress on Unit 2.

Reactor Power is 3%.

0 A Reactor Scram is attempted 0 Ten control rods remain at position 04 to 48 WHICH ONE of the following describes the required operator action?

A. Enter T-100, bypass RWM and insert control rods with S73.0.D.

B. Enter T-100, insert control rods with T-213.

C. Enter T-101, bypass RWM and insert control rods with S73.0.D.

D. Enter T - I 01, insert control rods with T-213.

Page 54 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice Basis or Justification Correct: A As Reactor power is below 4% entry into T-I 00 is appropriate, Bypass RWM and Insert Control Rods with S73.0.D is directed Incorrect B T-213 is not directed in T-I00 Incorrect C As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate Incorrect I D As Reactor power is below 4% entry into T-I 00 (vice T-I 01) is appropriate and T-213 is not directed in T-I 00 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 I

3.0 3 N N 1 Source Documentation Source: I [E3 New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference@): T-100 Bases step RC/Q-3 Learning LLOTI 540.02 0bjective:

Knowledge/Ability 295015 Importance: RO / SRO WA AA2.01 4.1 / 4.3 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination

28. Unit Iplant conditions are as follows:

Reactor power is 100%

Drywell cooling is maximized An inadvertent Group VlllA isolation occurs.

WHICH ONE of the following describes the status of Drywell Chilled Water service to the Drywell and Recirc Pump cooling water one minute later?

Drywell Chilled Water Recirc Pump Coolinq Water A. In Service In Service B. In Service Isolated C. Isolated In Service D. Isolated Isolated Page 56 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key I Question ID# 028 Both RC $*W Basis or Justification Correct: D An inadvertent VlllA isolation would result in both DWCW and Recirc Pump cooling water isolating Incorrect A Both will isolate I------

1 Incorrect Incorrect B

C DWCW will also isolate Recirc Pump cooling water will also isolate Difficulty Time Allowance PRA RO SRO (minutes) IOCFR55.41 10CFR55.43 Low 2.5 2 N (b) (8, 9, 10) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-8.1 for Group VlllA Learning LLOT0180.05 0bjective:

Knowledge/Ability 295020 Importance: RO / SRO WA AKI .05 3.3 13.6 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

29. Unit 1 plant conditions are as follows:

0 Reactor power is 100%

0 Hydrogen Water Chemistry is not in service The following annunciators are received:

0 MAIN STEAM LINE DIV 1 RAD MONITOR HVDOWNSCALE (109 F I )

0 MAIN STEAM LINE DIV 2 RAD MONITOR HVDOWNSCALE (I09 F2)

Subsequently the following annunciator is received:

MAIN STEAM LINE HIGH HIGH RADIATION (107 11)

WHICH ONE of the following describes the procedure(s), which must be entered for valid alarms, and the required operator action(s)?

A. Enter ON-I 02 ONLY; reduce reactor power in accordance with GP-5, Appendix 2.

B. Enter T-103 ONLY; perform a GP-3 Normal Plant Shutdown.

C. Enter ON-I02 and T-103; p.erform a rapid plant shutdown and close the MSIVs.

D. Enter ON-I02 and T-103; perform a rapid plant shutdown and Emergency Blowdown per T-I 12.

Page 58 of 200

Limerick Generating Station ILT05-I NRC Initial Licensing Examination I Answer Key Choice I ~~

Basis or Justification Correct: C Main steam line high rad requires entry into ON-102 and 1-103. The high-high rad alarm indicates three times NFPB. Per T-I03 this requires a rapid plant shutdown and closure of the MSIVs Incorrect A While reducing power is an immediate action per ON-102, question conditions also require entry into T-103 and the actions described in C above Incorrect B ON-I02 entry is also required and a GP-3 shutdown would be appropriate per T-103 if 2 or more areas exceeded MSO rad level, but is not adequate for the stated conditions Incorrect D An emergency blow-down would be appropriate per T-I 03 if two or more areas exceeded MSO and a primary system was discharging into the Reactor Enclosure. but is not reauired for MSL Hiah-Hiah Rad onlv Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 4.0 5 Y Y (b)(10) y (b)(2)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item [7 Other Exam Bank ILT Exam Bank Reference(s): ARC-MCR-109-F1, ARC-MCR-109-F2, ARC-MCR-107-11, ON-I 02 Step 1.2, T-I 03 Learning LLOTI560.02, LLOT1550.01 Objective:

KnowledgelAbility 295033 Importance: RO I SRO WA (32.4.4 4.0 14.3 (Description of K&A, from catalog) High Secondary Containment Radiation Levels: Ability to recognize abnormal indications for system operating parameters which are entry level conditions for emergency and abnormal operating procedures.

Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

30. Plant conditions are as follows:

0 A LOCA is in progress 0 Drywell Hydrogen is 3%

0 Drywell Oxygen is 8%

0 Suppression Pool Hydrogen is 7%

Suppression Pool Oxygen is 4%

WHICH ONE of the following identifies the flowpath for combustible gas monitoring and control?

A. DW/G-3 and SP/G-I B. DW/G-2 and SP/G-2 C. DW/G-3 and SP/G-3 D. DW/G-2 and SPIG-1 Page 60 of 200

Limerick Generatinlq Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 030 Both RC I Choice Basis or Justification I Correct: Applying the containment H2and 0 2 levels to the tables, PC/G-1 and PC/G-A 2 in T-102, sh. 2, results in the use of flowpaths DW/G-3 and SP/G-1 1 Incorrect B Neither of these flowpaths are correct per PC/G-1 and PC/G-2, T-102, sh. 2 Incorrect C The drywell flowpath is correct; the suppression pool flowpath is not, per PC/G-1 and PC/G-2, T-102, sh. 2.

I Incorrect D The suppression pool flowpath is correct; the drywell flowpath is not, per PC/G-1 and PUG-2, T-102, sh. 2.

Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 3.5 4 Y Y (b)(lO) Y (b)(5)

Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank - Modified LOR ILT Exam Bank Exam bank item Reference(s): T-102, sheet 2 and T-102 Bases Step PC/G-5 Learning LLOTI560.06 Objective:

Knowledge/Ability 500000 Importance: RO / SRO K/A EA 2.03 3.3 / 3.8 Required Materials:

T-I02 sht. 2 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

31. A steam leak in the Unit 2 RCIC room resulted in a scram and Emergency Blowdown per T-I 12.

Conditions are as follows:

0 Reactor pressure is 90 psig and dropping 0 Reactor level is -30 and dropping 0 Drywell pressure is 1.2 psig and steady The PRO has been directed to maintain RPV level with low pressure ECCS.

WHICH ONE of the following actions will result in injecting to the RPV with low pressure ECCS? (No other operator actions are taken)

A. Arm and depress the Core Spray Div. IManual Initiation Pushbutton.

B. Start the 2 A Core Spray Pump and take the HV-52-2F005A, Inboard Injection Valve, to OPEN.

C. Arm and depress the Core Spray Div. 3 Manual Initiation Pushbutton.

D. Start the 2C RHR Pump, HV-51-2F017C LPCI, Injection Valve, will OPEN automatically.

Page 62 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 031 Both RC I Choice Basis or Justification I Correct: A Div 1 Manual Initiation Pushbutton will provide a Div 1 LOCA Signal, Start the 1 A pump and open the injection valves as long as the Reactor low pressure permissive is met.

Incorrect B The HV-52-2F005 will not open unless there is a LOCA signal present I incorrect C Div 3 Manual Initiation Pushbutton will start the I C Core Spray Pump, but it will not make up the open logic for the injection valves. Only the Div l(2)

L I Incorrect D Pushbuttons will do that The HV-51-2F017C will not open automatically unless there is a LOCA signal present.

Difficulty Time Allowance PRA RO SRO (minutes) IOCFR55.41 10CFR55.43 High 3.5 4 Y Y (b)(7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 17Other Exam Bank 0ILT Exam Bank Reference(s): S52.7A, note above step 4,4 Learning LLOT0350.I O Objective:

Knowledge/Ability 209001 Importance: RO/ SRO K/A PWG 2.1.30 3.9 13.4 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

~~

Limerick Generating Station ILTO5-1 NRC Initial Licensinq Examination

32. Unit 2 plant conditions are as follows:

0 Reactor power is 100%

0 Division 3 Safeguard 1 2 5 V f + % W D C is inoperable due to maintenance on the battery charger e&& 43(ob An inadvertent Group Iisolation causes a reactor scram.

Unit 2 RClC starts on low reactor level A steam leak develops in the RClC room. RClC room temperature reaches 210°F WHICH ONE of the following operator actions places the RClC system in the configuration required by current plant conditions?

A. Trip the RClC Turbine.

B. Depress the RClC Manual Isolation Pushbutton.

C. Take the handswitch for the HV-49-2F007, RClC Steam Line Inboard Isolation to CLOSE.

D. Take the handswitch for the HV-49-2FOO8, RClC Steam Line Outboard Isolation to CLOSE.

Page 64 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 032 Both RC Choice Basis or Justification Correct: C With a loss of Div 3 DC, the 2F007 will fail to isolate on High RClC room temperature (205OF)and must be closed Incorrect A The RClC Turbine will trip on a Div 1 NS4 isolation signal on High RClC Room temperature Incorrect l B Manual isolation will not close 2F007 valve due to loss of Div 3 DC 0

~ ~

Incorrect The 2F008 will close on a Div INS4 Isolation signal on High RClC Room temperature Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y Y (b)(5) N Source: [xi New Exam Item c]Previous NRC Exam 0Modified Bank Item c]Other Exam Bank ILT Exam Bank Reference(s): E-2FC, GE DWG M-1-E51-1040-E-028, Sht.1 Learning LLOT0380.05, LLOT0380.12 0bjective:

1 Knowledge/Ability 217000 I Importance: RO / SRO WA I A205 3.3 13.3 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station lLTO5-1 NRC Initial Licensinq Examination

33. Unit 1 plant conditions are as follows:

0 Reactor water level is 35 0 1B RHR is in Suppression Pool cooling Div 2 Safeguard DC Bus is subsequently deenergized.

WHICH ONE of the following describes the effect, if any, on 1B RHR Loop if Reactor Water level lowers to -140?

A. I B RHR loop will realign to the LPCl mode.

B. I B RHR pump will load shed and remain shutdown.

C. 1 B RHR loop will remain in Suppression Pool cooling.

D. 1 B RHR pump will continue to run; minimum flow valve will open.

Page 66 of 200

Limerick Generating Station ILT05-1 NRC Initial LicensinQExamination Answer Kev

?BE?

Choice Basis or Justification Correct: 1 c RHR will remain in suppression pool cooling as F024 (SP cooling valve (and F017B (LPCI Inject valve) will not reposition during the LOCA due to the Loss of Div 2 DC Incorrect: A F024 and F017B will not reposition due to loss of Div 2 DC Incorrect:

IB RHR pump will not load shed during a LOCA Incorrect: I D Min flow valve will not open Difficulty Time Allowance PRA RO SRO (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y Y (b)(7) N Source: 0New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): E-IFB U/1, GE DWG. M-1-Ell-1040-E-039 SH.l Learning LLOT0370.3e 0bjective:

Knowledge/Ability 203000 Importance: RO / SRO KIA K6.02 2.8 / 3.0 Required Materials:

Notes and Comments:

Existing bank question, Stem and Distractors Modified Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatina Station ILT05-1 NRC Initial Licensing Examination

34. Unit 1 plant conditions are as follows:

0 OPCON4 0 I A RHR is in shutdown cooling Reactor water level drops from +70 to -1 0.

WHICH ONE of the following identifies current RHR pump and valve status?

HV-51-1F006A HV-51-1FOO9 Shutdown Cooling Shutdown Cooling 1 A RHR Pump Suction Valve Isolation valve A. Running Open Open B. Running Open Closed C. Tripped Closed Open D. Tripped Open Closed Page 68 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination I Answer Key I Basis or Justification Correct: D When level decreases to below + I 2.5 Shutdown Cooling will isolate FOO9, which in turn trips the ARHR pump, F006 remains open as there is no auto closure A Incorrect as FOO9 will close with level below +125 and pump will trip Incorrect Incorrect as pump will trip when level drops below 12.5 due to FOO9 closure I Incorrect C Incorrect as F006A will not automatically close and FOO9 y level drops below +I 25 Ji close when Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y y W(7) N Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 17 ILT Exam Bank Reference(s): S51.8.8, step 3.2 Learning LLOT0370.14~

Objective:

KnowledgelAbility 205000 Importance: RO / SRO WA K6.04 3.6 13.6 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

35. Unit 1 plant conditions are as follows:

0 Reactor power is 100%

0 The RO selects Single-Element control on the Feedwater Master Level Controller (L IC-M 1- 1R600)

WHICH ONE of the following describes the response, if any, of the Master Level Controller to a Reactor SCRAM?

A. Controller will swap to three-element when SCRAM Profile is activated.

B. Controller will swap to three-element when SCRAM Profile is reset.

C. Controller will swap to three-element when Reactor power is below 20%.

D. Controller will remain in single-element.

Page 70 of 200

Limerick Generating Station iLT05-I NRC initial Licensinq Examination Answer Key SBtI I Choice Basis or Justification 1 Correct: A SCRAM profile will swap controller to three element even if operator selected single element.

I1 Incorrect Incorrect B

C This is incorrect as FW will swap to single element when SCRAM profile is reset This is incorrect as FW will swap to single element at -20%

1ncorrect D This is incorrect a controller will not remain in single element if single is selected (IF FW flow failure had caused swap to single element this would be correct).

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y y (b)(7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): S.06.1 .D Unit 1, Attachment 1 Learning LLOT0550.08 Objective: '

Knowledge/Ability 259002 Importance: RO I SRO WA K5.01 3.1 13.1 REQUIRED MATERIALS:

Notes and Comments:

This question relates to the LGS plant specific FW controllers.

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

36. Unit 1 plant conditions are as follows:

0 HPCl is in service for RPV pressure control (CST to CST) 0 FIC-055-1 R600 HPCI FLOW CONTROL VALVE AUTO/MAN switch is in AUTO HV-55-1F008 HPCI, Test Loop Shutoff is throttled to maintain pump discharge pressure 150 psig over Reactor pressure.

0 The RO throttles HV-55-1F008 in the closed direction for one second WHICH ONE of the following describes HPCl turbine speed and flowrate one minute later?

HPCl Turbine Speed Flowrate A. No change Higher B. Higher No change C. Lower No change D. No change Lower Page 72 of 200

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Answer Key Choice

~

I Basis or Justification Correct: B With Flow Controller in AUTO, system flow is maintained constant. IF F008 is throttled closed HPCl speed will need to increase to maintain the same flow Incorrect A Flow Controller is in Auto, maintaining system flow constant Incorrect

/c/ To maintain constant flow w/F008 throttled closed, speed goes up.

Incorrect D Flow Controller is in Auto, maintainingsystem flow constant.

I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 N y (W(7) N Source Documentation Source: New Exam Item c]Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s ): S55.1.D, note Step 4.4.3 Learning LLOT0340.12 0bjective:

KnowledgetAbility 206000 HPCl Importance: RO I SRO WA A I .09 3.4 t 3.5 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

~~

Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination

37. Unit 1 plant conditions are as follows:

ADS Auto Inhibit switches are in NORM 0 RPV water level is -1 0 and lowering 0 RPV pressure is 400 psig and steady 0 Drywell pressure is 1.8 psig 0 Core Spray pumps I B and I D are running 0 Core Spray pumps 1 A and IC are tripped and cannot be started 0 ALL RHR pumps are tripped and cannot be started Subsequently, RPV water level drops to -1 33.

WHICH ONE of the following identifies the response of DIV 1 and DIV 3 ADS subsystems? (Assume no operator actions)

DIV IADS DIV 3 ADS A. initiates after 105 second TD Will not initiate B. Initiates after 525 second TD Will not initiate C. Will not initiate Initiates after 105 second TD D. Will not initiate Initiates after 525 second TD Page 74 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Basis or Justification Correct: C DIV 1 ADS will not initiate as no Div 1 Core Spray or RHR pumps are running DIV 3 will initiate as B & D core spray pumps are running 105 sec is correct as -129 and HI DW pressure are met.

r Incorrect: A DIV Iwill not initiate without correct pumps running DIV 3 will initiate as described above Incorrect B DIV 1 ADS will not initiate without correct pumps running DIV 3 will initiate as described above D DIV 1 will not initiate is correct but, DIV 3 initiating after 525 seconds is incorrect as -129 and 1.68# conditions bypass 420 sec timer.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.5 4 Y Y (b)(7) N Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): B21-1060 (ADS) Sh. 3 Learning LLOT0350.04~

0bjective:

Knowledge/Ability 209001 Importance: RO / SRO K/A K3.02 3.8 i 3.9 (Description of K&A, from catalog)

Knowledge of the effect that a loss or malfunction of core spray will have on the following: ADS Logic REQUIRED MATERIALS:

Notes and Comments:

Existing Question, Stem and Distractors Modified Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

38. Unit 1 plant conditions are as follows:

0 An ATWS has occurred 0 No operator actions are taken 0 Reactor level is -40 and slowly lowering Reactor power is 30% and slowly lowering Three minutes later Reactor power is 27% and slowly lowering.

WHICH ONE of the following identifies lights and alarms for the given cond itions?

A. Squib valve continuity lights NOT lit; CORE SPRAY LINE INTERNAL BREAK alarm annunciated.

B. Squib valve continuity lights NOT lit, STANDBY LIQUID TANK LO-LO LEVEL alarm annunciated.

C. Squib valve continuity lights lit, RWCU SYSTEM ISOLATED alarm annunciated.

D. Squib valve continuity lights lit, DIV 1/11 RRCS CHANNEL ACTIVATED alarm annunciated.

Page 76 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice I Basis or Justification Correct: A Squib valve continuity Light not lit is correct as 3 minutes after -40 is reached with power above 4% SLC will have initiated. Additionally injection will result in core spray line internal break alarm Incorrect B Is incorrect as SLC tank low-low level would not be alarming at this point.

Incorrect C Squib valve continuity lights lit is wrong as SLC will have initiated Incorrect D Squib valve continuity lights lit is wrong as SLC will have initiated I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b)(5) N Source: N N e w Exam Item Previous NRC Exam 2001 0Modified Bank Item c]Other Exam Bank 0ILT Exam Bank Reference(s): S48.1.B, section 4.0, ANN 113, B5 Learning LLOT0310.06 Objective:

Knowledge/Ability 211000 Importance: RO / SRO WA A1.10 3.7 / 3.7 REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILTO5-1 NRC Initial Licensinn Examination

39. Unit 2 plant conditions are as follows:

0 Turbine shell warming is in progress 0 Turbine first stage pressure rises to 200 psig 0 PIS-001-652A and D are lit on panels 10609 and lOC61 Iin the Aux Equipment Room respectively WHICH ONE of the following identifies the plant response?

A. Full Reactor SCRAM on Turbine Stop Valve closure.

B. Full Reactor SCRAM on Turbine Control Valve closure.

C. Half SCRAM ONLY on Turbine Stop Valve closure.

D. Half SCRAM ONLY on Turbine Control Valve closure.

Page 78 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination I Basis or Justification I Correct:

Incorrect B Turbine control valve closure scram is wrong as turbine control valves are open to support shell warming Incorrect I Cpp This answer is wrong as a complete SCRAM will occur Incorrect D This answer is wrong as a complete SCRAM will occur Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 4.5 3 Y y (b)(7) N Source Documentation Source: [xi New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-2 Appendix 3, step 3.2.8 caution ANN 107,A2 Learning LLOT0300.04 0bjective:

Knowledge/Ability 212000 RPS Importance: RO / SRO KIA K4.12 3.9 / 4.1 (Description of K&A, from catalog)

Knowledge of RPS design feature andlor interlocks which provide for bypassing of selected SCRAM signals (manually and automatically):

REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

40. Unit 1 plant conditions are as follows:

0 Reactor power 100%

0 Reactor level 35 LT-42-IN004A Feedwater Narrow Range Level Transmitter fails downscale Subsequently, LT-42-IN004C Feedwater Narrow Range Level Transmitter fails upscale.

WHICH ONE of the following describes the impact, if any, on feedwater level control and Reactor level?

A. Feedwater Master Level Controller will swap to single element, Reactor level will go up.

B. Feedwater Master Level Controller will swap to single element, Reactor level will remain at 35.

C. Feedwater Master Level Controller will remain in three element, Reactor level will remain at 35.

D. Individual Reactor Feed Pump speed controllers will swap to manual, Reactor level will go up.

Page 80 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 040 Both RC swicj Choice Basis or Justification Correct: C A failure of two level transmitter (1/2 hour apart) will not result in a FW failure, Master level controller will remain in 3 element, and Reactor level will remain unchanged Incorrect: A This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart), additionally level will remain at 35 Incorrect: B This is incorrect as FW will not swap to single element on level transmitter failures (1/2 hour apart)

Incorrect: D A failure of two level transmitters (1/2 hour apart) will not result in speed controllers swapping to manual (two failure simultaneously, or three failures would), additionally reactor level will not go up Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 3 Y Y (b)(7) N Source: 0New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S06.1.H U/1, Attachment 1 Learning LLOT0550.1OC Objective:

Knowledge/Ability 259001 Importance: RO / SRO WA K6.07 3.8 / 3.8 REQUIRED MATERIALS:

Notes and Comments:

Modified Question from LOR bank Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

.

Limerick Generating Station ILTO5-I NRC Initial Licensing Examination

41. Unit 1 plant conditions are as follows:

An ATWS is in progress 0 Reactor power is 50% and steady 0 Reactor water level is 35 and steady e Reactor pressure is 1045 psig and steady RRCS DIV 1B AND DIV 2A Manual Initiation Pushbuttons are armed and depressed.

WHICH ONE of the following identifies RRCS response?

A. ARI will initiate immediately.

B. Recirc Pumps will trip in 9 seconds.

C. SLC will initiate if APRMs are not downscale in 1 18 seconds.

D. DIV I / II RRCS annunciators will illuminate, ARI solenoids remain deenergized.

Page 82 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice Basis or Justification Correct: D RRCS manual initiation requires depressing both pushbuttons in the SAME Division, the noted action (one pushbutton in separate divisions) will not initiate RRCS Incorrect A ARI will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met Incorrect B Recirc pump trip does not initiate from manual RRCS initiation, and conditions for automatic initiation are not met Incorrect Icl SLC will not initiate as RRCS is not initiated, and conditions for automatic initiation are not met I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y Y (b)(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-18 Attachment 4, ANN 004 F-5 Learning LLOT0315.05 Objective:

Knowledge/Ability 212000 Importance: RO I SRO KIA A4.16 4.4 14.4 REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-I NRC Initial Licensinq Examination

42. Unit Iplant conditions are as follows:

Reactor power is 100%

0 Normal Reactor Enclosure ventilation is in service 0 Both Standby Gas Treatment System fans are in AUTO Reactor water level master trip units, LIS-42-1N681A and LIS-42-1N681B, fail downscale.

WHICH ONE of the following identifies the status of Standby Gas Treatment System (SGTS) five minutes later?

A. O A SGTS Fan and OB SGTS Fan running.

B. Only OASGTS Fan running.

C. Only OBSGTS Fan running.

D. Both SGTS Fans off.

Page 84 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question-ID# 042 Both RC Choice Basis or Justification Correct: I B A Reactor enclosure isolation and A SGTS start will occur on LIS-42-IN681A and B downscale failure Incorrect: A Incorrect as B Fan will not start

- _ _ _ _ ~ ~

Incorrect C Incorrect as B Fan will not start

~~~

Incorrect: D Incorrect as A Fan will start Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 IOCFR55.43 Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): ANN 004 E-I Learning LLOT0200.1OB Objective:

Knowledge/Ability 261000 Importance: RO / SRO WA K6.08 3.1 /3.1 (Description of K&A, from catalog)

Knowledge of the effect that a Loss or Malfunction of the following will have on the SGTS system:

Reactor vessel level Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

43. Unit Iplant conditions are as follows:

0 Reactor power is 100%

0 Reactor level is 35 A Condensate min flow controller malfunction results in the following:

0 Reactor Feed Pump (RFP) suction pressure drops to 230 psi for 6 seconds and then goes up to 250 psig WHICH ONE of the following identifies the subsequent Feedwater system status?

A. I A RFP is tripped, IB and I C RFPs are running.

B. 1C RFP is tripped, 1 A and 1B RFPs are running.

C. I Aand 1 B RFPs are tripped, 1C RFP is running.

D. All RFPs are tripped.

Page 86 of 200

Limerick Generating Station ILTO5-1 NRC Initial Licensinq Examination Answer Key Choice Basis or Justification Correct: B 1C RFP will trip on Low suction after 5 seconds pressure due to suction pressure less than 233 psi for 5 Incorrect A 1 A RFP will not trip as C RFP trips first followed by 1B at 10 seconds and 1 A at 15 seconds Incorrect 7 1B and 1 A tripped is wrong as 1C RFP will trip first Incorrect D 1 All RFPs tripped is wrong as suction pressure stabilized prior to trip of all 3 RFPs Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Source Documentation Source: New Exam Item 0Previous NRC Exam

[7 Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ANN 104 Cond E-2 ANNS 102 Feed AI, BI, C1 Learning LLOT0520.08 Objective:

Knowledge/Ability 256000 Importance: RO / SRO KIA K1.02 3.3 f 3.3 (Description of K&A, from catalog)

Knowledge of the Physical connections and/or cause - effect relationship between condensate system and the following: Reactor Feedwater System REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinn Examination

44. Unit 1 has been scrammed due to a LOCA.

RClC auto-initiated following the SCRAM. Conditions are as follows:

RPV water level has recovered to +35 and is steady 0 Drywell pressure is 2.5 psig and steady 0 The CRS has directed that RClC be secured WHICH ONE of the following will shutdown the RClC turbine and leave RClC ready for auto injection?

A. Reset the RClC initiation signal seal-in.

Depress the RClC turbine manual isolation pushbutton.

Close the RClC trip throttle valve (HV-50-112).

B. Depress the RClC turbine manual isolation pushbutton.

Close the RClC steam supply valve (HV-50-1F045).

Reset the RClC trip throttle valve (HV-50-112).

C. Reset the RClC initiation signal seal-in.

Depress the RClC turbine trip pushbutton.

Close the RClC steam supply valve (HV-50-1F045).

Reset the RClC trip throttle valve (HV-50-112).

D. Depress the RClC turbine trip pushbutton.

Place the RClC pump discharge flow controller in MANUAL.

Set the RClC pump discharge flow controller to 0%.

Close the RClC trip throttle valve (HV-50-112).

Page 88 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice Basis or Justification Correct: C Since the initiation signal is no longer present the operator can reset it, Trip the turbine and close the steam supply. Resetting the Trip throttle valve leaves RClC ready for auto injection Incorrect A Once the initiation signal is reset, the manual isolation will not work Incorrect B These steps will shutdown RCIC, but the isolation must be reset in order to be ready for auto injection Incorrect D These steps will shutdown RCIC if the initiation signal were still present.

RClC will not be ready to auto inject Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y y (bN7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): S49.2A section 4.1, S49.1C section 4.3 Learning LOT0380.08 0bjective:

I Knowledge/Ability 217000 1 Importance: RO / SRO KIA (Description of K&A, from catalog)

Ability to manually operate and/or monitor in the control room

--Manually initiated controls Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station . ILT05-1 NRC Initial Licensing Examination

45. WHICH ONE of the following identifies SRV indications during an ADS automatic blowdown?

Amber White Has Lifted Light Solenoid Energized Light A. Lit Not Lit B. Lit Lit C. Not Lit Lit D. Not Lit Not Lit Page 90 of 200

. Limerick Generatinq Station Question I.D# 045 Both RC Choice Correct:

Incorrect Incorrect Incorrect Level of A

C D

Difficulty initiation Answer Kev ILT05-I NRC Initial Licensinq Examination Basis or Justification

~

During an automatic blowdown both amber has lifted (Acoustic monitor) and white solenoid (ADS Div I& 3) lights will light.

This is incorrect as white solenoid energized light will be lit on ADS auto This is incorrect as Amber has lifted light will be lit This is incorrect as both lights will be lifted if there was no increased Drywell pressure this would be true Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 2 Y Y (b)(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam (7 Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): OT-114, ARC 110 B-2 Learning LLOT0330.07a 0bjective:

Knowledge/Ability 218000 Importance: RO / SRO WA A3.01 4.21 4.3 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

46. Unit Iis operating at 100%.

An instrument failure results in an inadvertent RPV low-low level signal

(-38).

WHICH ONE of the following describes the response of the Bypass Leakage Barrier Blocks and Vents?

A. Instrument Gas Block Valves are closed and the vents are open.

B. Recirc Pump Seal Purge Block Valves are closed and the vents are open.

C. Main Steam Line Drain Block Valves are closed and the vents are open.

D. N2 Supply Block Valves are closed and the vents are open.

Page 92 of 200

Limerick Generating Station iLT05-1 NRC initial Licensing Examination Answer Key Choice I Basis or Justification Correct:

lD1 NZSupply valve closes and vent valve opens on a Lo-Lo Reactor level signal (VIIIB)

~~

Incorrect: 1 A 1 This is incorrect as instrument gas block valves isolate at Lo-Lo-Lo Level Incorrect This is incorrect as recirc vent valves do not automatically open on an isolation Incorrect C This is incorrect as main steam line vent valves do not automatically open Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 3 Y Y (b)(5) N Source Documentation Source: 0New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): GP-8.1, Reactor Level 2-L0w, Low section Learning LLOTOI80.08d Objective:

KnowledgeIAbility 223002 Importance: RO I SRO KIA A2.05 3.31 3.6 (Description of K&A, from catalog)

Ability to predict the impact of Nuclear Boiler Instrumentationfailure on the primary containment isolations systemhuclear steam supply shutoff and base on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations.

!quired Materials:

Notes and Comments:

Modified LOR Bank Question Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

.-

- --

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

47. D11 Diesel Generator is operating in parallel with the 101 Safeguard Bus with the following indications:

60Hz 2000Kw 1600 KVAR WHICH ONE of the following actions will restore the diesel generator within operating Iimits?

A. Place Speed Governor in RAISE to adjust real load to 2100 KW.

B. Place Speed Governor in LOWER to adjust real load to 1900 KW.

C. Place Voltage Regulator in RAISE to adjust reactive load to 1700 KVAR.

D. Place Voltage Regulator in LOWER to adjust reactive load to 1500 KVAR.

Page 94 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Choice Basis or Justification Correct: D Reducing VARS to less than 1500 restores W A R S to less than 75% KW, which corresponds to a Power Factor of 0.8 Incorrect: A Raising KW would also restore the ratio of KVAR to KW, but KW would have to be raised to 2133 KW.

Incorrect: B Lowering KW would make the D/G further from its operating limit.

Incorrect:

Icl Raising KVAR would also make the D/G further from its operating limit.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y y (W7) N

~ ~ ~~

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S92.1.O, caution above step 4.5.5 Learning LLOTO670.02 Objective:

KnowledgelAbility 264000 Importance: RO / SRO WA A4.01 3.3 I 3.4 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

48. Unit 1 plant conditions are as follows:

a I A CRD pump is in service 0 Reactor power is 100%

0 Reactor level is 35 A failure of a level instrument line results in the following annunciators:

EXCESS FLOW CHECK VALVE OPERATED C218 (1 12 E5) 0 DIV 3 REACTOR LO-LO-LO Level (1 13 E3)

WHICH ONE of the following identifies the effect, if any, on the CRD system and the action required to restore CRD, if any?

A. I A CRD pump trips.

Can be restarted from the MCR.

B. 1 A CRD pump remains running.

No action required.

C. I A CRD pump trips and cannot be restored.

1 B CRD pump must be placed in-service from the MCR.

D. 1 A CRD pump trips.

Can only be restarted from 4 KV switchgear.

Page 96 of 200

Limerick Generating Station ILT05-I NRC Initial Licensina Examination Answer Key Question Id# 048 Both R(

Basis or Justification Correct: A A CRD will trip due to Div Ill LOCA signal and LOCA load shed it can be restarted from the MCR Incorrect B This is incorrect as a CRD pump will trip due to Div Ill LOCA load shed Incorrect C This is incorrect as a CRD can be restarted Incorrect D This is incorrect as CRD can be restarted from the MCR Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y y (b)(5) N Source: ONew Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): SE-10, step 4.6 Learning LLOT0660.05b 0bjective:

KnowledgeIAbility 262001 Importance: RO I SRO WA A2.02 3.6 I 3.9 Required Materials:

Notes and Comments:

This question was extensively modified from Question 373224 (ILT LERT EXAM 2005)

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination

49. Unit 1 Plant conditions are as follows:

0 Reactor is scrammed 0 Reactor pressure is 600 psig 0 Division I DC is lost 0 Reactor water level is + I 15 Which one of the following can be used to lower Reactor pressure?

A. 1B SRV from the MCR.

B. 1C SRV from the RSP.

C. 1J SRV from the AER.

D. 1S SRV from the AER.

Page 98 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 049 Both RC I Choice Basis or Justification Correct:

I D S SRV is an ADS SRV and has power in the AER. While it is not one of the preferred SRVs (B,J,C) for use in OT-I I O , as the preferred SRVs are not available a non-preferred SRV is directed.

Incorrect Incorrect iA I B While B SRV is one of the preferred SRVs for use with high level it cannot be operated from the MCR due to the Loss of Div I DC While C SRV is one of the preferred SRVs for use with high level it cannot be operated from the MCR due to the Loss of Div I DC Incorrect I C While J SRV is one of the preferred SRVs for use with high level, control is not availabre in the AER Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b)(7) N Source: New Exam Item 0 Previous NRC Exam 0801#221 Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): OT-I 10 Step 3.1.4 Learning LLOTOI20.12a 0bjective:

Knowledge/Ability 239002 Importance: RO i SRO WA K4.05 3.6 i 3.7 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

~ - ~~

Limerick Generat ing Stat ion ILT05-1 NRC Initial Licensing Examination

50. Unit Iplant conditions are as follows:

0 Reactor power is 100%

0 1 A RECW pump is blocked for bearing replacement 0 1B RECW pump trips and cannot be restarted WHICH ONE of the following identifies the effect on the Reactor Recirc Pumps and required operator action?

A. Seal cavity temperature rises.

Reduce pump speed to maintain cavity temperature below 200OF.

B. Seal cavity temperature rises.

Trip the RECIRC pumps within I O minutes.

C. Pump motor temperature rises.

Trip the RECIRC pumps if motor winding temperature exceeds 20OoF.

D. Pump motor temperature rises.

Trip the RECIRC pumps within 10 minutes.

Page 100 of 200

Limerick Ge ne ratinq Station ILT05-I NRC Initial Licensing Examination Answer Key I Choice I Basis or Justification Correct: Loss of RECW will result in an increase in seal cavity temperature ON-I 13 directs tripping a RECIRC pump within 10 minutes of a loss of RECW Incorrect: A On high seal cavity temperature ON-I 13 directs reducing speed to maintain temperature this occurs at a cavity temperature of 175OF not ZOOOF Incorrect: Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler)

Incorrect: D Pump motor temperature is unaffected by a LOSS of RECW (DWCW supplies motor cooler)

I I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 2.5 3 Y Y (b)(5) N Source Documentation Source: Ix] New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank c]ILT Exam Bank Reference(s): ON-I 13 step 2.1, S43.0.D Learning LLOT0030.07b:

0bjective:

KnowledgelAbility 202001 Importance: RO / SRO KIA A2.17 3.1 13.2 (Description of K&A, from catalog)

Ability to predict the impact of a loss of seal cooling water on the RECIRC system; and based on those predictions use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations.

Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination 51, Unit 2 plant conditions are as follows:

2A RECW pump is running with its handswitch in AUTO after START 0 2B RECW pump is off with its handswitch in AUTO after STOP A complete Loss Of Offsite Power (LOOP) occurs.

All 4 KV systems operate as designed with all buses re-energizing SIMULTANEOUSLY.

WHICH ONE of the following describes the response of the RECW pumps?

A. 2A RECW pump auto re-starts.

2B RECW pump auto starts in standby.

B. 2 A RECW pump auto re-starts.

2B RECW pump does NOT auto start in standby.

C. 2A RECW pump does NOT auto re-start.

2B RECW pump auto starts in standby.

D. 2 A RECW pump does NOT auto re-start.

2B RECW pump does NOT auto start in standby.

Page 102 of 200

Limerick Generating Station ILTOS-1 NRC Initial Licensinq Examination Answer Key Choice I Basis or Justification Correct: A When their respective safeguard MCCs re-energized both RECW pumps auto start on low heat exchange outlet pressure Incorrect 2A portion of this distractor is correct, 28 portion is incorrect, for the reason stated above Incorrect C 2A portion of this distractor is incorrect, 2B portion is correct for the reason stated above Incorrect D Both the 2A and 2B portions of this distractor are incorrect as stated above.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y y (W(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank E-565 Learning LLOT0460.07 Objective:

Knowledge/Ability 400000 Importance: RO I SRO K/A K4.01 3.4 / 3.9 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination

52. Unit 1 plant conditions are as follows:

0 Reactor startup is in progress 0 Reactor power is 20%

Control rod withdrawal is in progress.

WHICH ONE of the following will result in a rod withdraw block?

A. RBM upscale B. RBM downscale C. Control rod withdrawn past its withdraw limit D. RDCS Activities Control Disagree condition Page 104 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination to a malfunction of RMCS Incorrect A RBM upscale will not result in a rod block as Reactor power is less than 30%

Incorrect B RBM downscale will not result in a block as Reactor power is less than 30%

Incorrect C CR withdraw will not result in a Rod block as Reactor power is above RWM LPSP (18%)

Level of Difficulty Time Allowance PFW RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y Y (b)(7) N Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): S73.O.B, step 4.2 & note above step, ANN 108 D-4 Learning LLOT0080.06 =

0bjective:

WA I KnowledgelAbility 201002 K3.02 (Description of K&A, from catalog)

Importance: RO ISRO 2.9 13.2 Knowledge of the effect that a loss or malfunction of RMCS will have on RBM Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

~ _~

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

53. Unit 1 plant conditions are as follows:

0 Reactor STARTUP is in progress 0 Reactor power is 12?h Insert limit for current RWM rod group is 00 0 Withdraw limit for the current RWM rod group is 12 0 Control rod 10-39 is selected Control rod 10-39, the first rod of the current group, is withdrawn to position 14 with no further operator action taken.

WHICH ONE of the following identifies the ability to move control rod 10-39?

A. Control rod can be withdrawn and inserted without additional actions.

B. Control rod can only be inserted without additional action.

C. Control rod insertion capability requires rod to be bypassed in the RWM.

D. Control rod insertion or withdraw capability requires a substitute position to be entered into RWM.

Page 106 of 200

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Answer Key Incorrect A Rod cannot be withdrawn as RWM will enforce a withdraw block Incorrect C Rod does not need to be bypassed to allow insertion Incorrect D This is not correct as substitute rod position is only used if there is no position indication Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N Y (b)(7) N Source Documentation Source: New Exam Item 0Previous NRC Exam I 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): ON-I23 step 2.12 Learning LLOT0093f 0bjective:

Knowledge/Ability 201006 Importance: RO / SRO WA K4.06 3.2 / 3.4 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

% Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

54. Unit 1 plant conditions are as follows:

0 Reactor was scrammed due to a condensate line rupture.

0 Reactor level is -35 and lowering 0 D I 24 safeguard load center transformer breaker tripped on over current The RO is directed to start Standby Liquid Control to augment Reactor level.

0 1 A and I C SLC injection pumps are started and verified to be injecting WHICH ONE of the following describes the RWCU system response?

A. HV-44-1F004 RWCU Outboard Suction Valve closes.

B. HV-44-1FOOI RWCU Inboard Suction Valve closes.

C. HV-44-1F004 RWCU Outboard Suction Valve and HV-44-1FOOI RWCU Inboard Suction Valve close.

D. HV-44-1F040 RWCU Inlet Suction Valve closes.

Page 108 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Kev sm

~

QuestionID# 054 Both RC Choice Basis or Justification Aor C SLC pump start close Fool valve as B was not started (D124 is power supply for the 73 pump) F004 did not close Incorrect A F004 does not close as B SLC pump did not start Incorrect Incorrect IC D While Fool did close answer is incorrect as F004 did not close due to B SLC pump not started F040 does not receive and isolation signal on SLC start I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 N Y (b)(7) N Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank - LORT 0ILT Exam Bank Reference(s): GP-8.1, Signal Y Learning LLOTOI10.05 Objective:

KnowledgelAbility 204000 Importance: RO I SRO KIA A3.03 3.6 13.6 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

55. Unit 1 plant conditions are as follows:

0 Reactor Power is 100%

0 lAY160 trips due to a ground fault 30 minutes later a Reactor SCRAM and turbine trip occur.

0 Reactor pressure is 900 psig and steady 0 Turbine speed is 300 RPM and dropping WHICH ONE of the following identifies the ability to lower Reactor pressure using the bypass valves?

A. Bypass valves cannot be used to control Reactor pressure.

B. Bypass valves can be opened by raising the Bypass Jack.

C. Bypass valves can be opened by lowering Pressure Set.

D. Bypass valves can be opened by raising Maximum Combined Flow.

Page 110 of 200

Limerick Generatinq Station ILTO5-1 NRC Initial Licensinn Examination Answer Key Question ID# 055 Both RC SR!

Choice Basis or Justification Correct: A Due to Loss of 1AY160 and PMG (Turbine speed 300 RPM) bypass will not operate Incorrect B Bypass jack will not operate due to loss of 1AY160 Incorrect C Pressure set will not operate due to the loss of 1AY160 Incorrect D Raising max combine flow (115%) will not open bypass valves (CVs are closed)

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 -

Low 3.0 3 Y Y (b)(7) N Source Documentation Source: I New Exam Item Previous NRC Exam 0ILT Exam Bank Reference(s): E-1AY160 Attachment #1 Learning LLOT0560.01Ok 0bjective:

KnowledgelAbility 262002 Importance: RO I SRO KIA K3.15 2.6 12.7 (Description of K&A, from catalog)

Knowledge of the effect that a loss or malfunction of UPS will have on Main Turbine Operation Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination

56. A loss of instrument air is in progress on Unit I.

1A and 1B Instrument Air Headers are at 20 psig and lowering.

WHICH ONE of the following describes the response of Main Steam system valves?

A. Only Outboard MSIVs close.

All SRVs can be opened.

B. Only Inboard MSlVs close.

Only ADS and RSP SRVs can be opened.

C. Inboard and Outboard MSlVs close.

All SRVs can be opened.

D. Inboard and Outboard MSlVs close.

Only ADS and RSP SRVs can be opened Page 112 of 200

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Correct: D Outboard MSIVs close on loss of instrument air inboard MSlVs close on loss of PClG (PCIG is lost due to loss of Instrument Air Only ADS and RSP SRVs have accumulator and can be opened with Loss of PClG I Incorrect A This is incorrect as inboard MSlVs also close. Also non ADS SRVs cannot be opened from handswitches due to loss of PClG Incorrect B This is incorrect as outboard MSlVs also close Incorrect C This is incorrect as non-ADS SRVs cannot be opened from handswitches due to loss of PClG Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 4.0 3 Y Y (b)(9) N Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ON-I 19 Attachment 1 Learning LLOT0730.08 0bjective:

Knowledge/Ability 300000 Importance: RO / SRO WA K1.03 2.8 / 2.9 (Description of K&A, from catalog)

Knowledge of the connections and/or cause effect relationships between instrument air and containment air Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination

57. Unit 1 plant conditions are as follows:

0 An ATWS is in progress 0 Reactor power is 40% and steady 0 Reactor level is -60 and steady A turbine trip occurs; and Reactor power remains at 40%.

WHICH ONE of the following identifies conditions that will result in a RRCS feedwater runback, and when the runback will occur?

A. Reactor pressure 1160 psig.

Runback occurs in 118 seconds.

B. Reactor pressure 1160 psig.

Runback occurs in 25 seconds.

C. Reactor pressure 1096 psig.

Runback occurs in 30 seconds.

D. Reactor pressure 1096 psig.

Runback occurs in 9 seconds.

Page 114 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Kev Incorrect Ici Reactor pressure 1096 is incorrect (1096 is the Reactor Scram setpoint) additionally 30 seconds is the Feedwater runback length once initiated Incorrect iDi Reactor pressure 1096 is incorrect additionally 9 seconds is incorrect (9 seconds is the RRCS Recirc pump RPT Breaker time delay)

Level of Difficulty Time Allowance PFW RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.0 3 Y NIA NIA Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GE Elementary Drawing G31-I020 ARC 004, B-4 Learning LLOT0315.04 Objective:

KnowledgelAbility 216000 Importance: RO / SRO WA 2.4.50 3.3 13.3 Required Materials:

Notes and Comments:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ~

ILT05-1 NRC Initial Licensing Examination

58. WHICH ONE of the following lists contains ONLY Non-Safeguard DC System loads?

A. Turbine Enclosure Area Rad Monitors Refuel Floor HVAC Isolation logic Primary RPS/UPS Inverter Power Recirc MG Set Emergency Lube Oil Pumps B. 13.2 KV Breaker Control Power Main Control Room Annunciator Emergency Lighting Panels Primary RPS/UPS inverter Power C. Primary APRM Inverter Power Reactor Enclosure HVAC Isolation logic 4KV Breaker Control Power RFP Emergency Lube Oil Pumps D. Recirc MG Set Emergency Lube Oil Pumps Primary APRM Inverter Power Emergency Lighting Panels Main Control Room Annunciator Page 116 of 200

Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination Answer Key Question ID# 058 Both RC Choice Basis or Justification Correct:

Incorrect:

ID A All 4 loads are Now Safeguard DC Refuel Floor HVAC isolation logic and Primary RPS/UPS Inverter Power are Safeguard DC loads

--- Incorrect:

Incorrect: C Primary RPS/UPS inverter Power is a Safeguard DC load Reactor Enclosure HVAC Isolation logic and 4KV Breaker Control Power are Safeguard DC loads Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 Low 3.0 3 Y (b) (7) N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): E-33, Sh 1-3 E-619, Sh 1-3 Learning LLOT0690.04 0bjective:

Knowledge/Ability 263000 Importance: RO / SRO KIA K2.01 3.1 / 3.4 (Description of K&A, from catalog)

Knowledge of electrical power supplies to the following: Major DC loads Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination

59. WHICH ONE of the following describes the reason Drywell Vacuum Relief Valves open?

A. Prevent drawing excess negative pressure in the Drywell.

B. Prevent drawing excess negative pressure in the Suppression Pool.

C. Equalize pressure between the SRV Downcomer and the Suppression Pool.

D. Ensure the Suppression Pool pressure remains higher than Drywell pressure.

Page 118 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key Choice I Basis or Justification Correct: Vacuum Breakers Relief's will open on Drywell Pressure lower than Suppression Pool Pressure Incorrect B Vacuum Breaker Operate on to ensure Drywell is not drawn negative Incorrect C While some equalization will occur when Vacuum Breaker opens it is not the reason they open Incorrect The exact opposite is true, as Vacuum Breakers relieve the higher Suppression Pool pressure to the Drywell.

Level of Difficulty Time Allowance PRA . RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 Y Y (b)(5) N Source Documentation Source: New Exam Item Previous NRC Exam 0999#119 0Modified Bank Item 0Other Exam Bank

[XI ILT Exam Bank Reference(s): ANN 114 G-I Learning LLOTOI30.02f 0bjective:

Knowledge/Ability 223001 Importance: RO / SRO WA K5.01 3.1 / 3.3 (Description of K&A, from catalog)

Knowledge of the Operational implications of Vacuum Breaker/relief operations as applies to Primary Containment system and auxiliaries Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

60. Unit 1 is at 100% power when the following alarm is received:

IDB-1 250V DC MCC UNDERVOLTAGE (122 G-2)

WHICH ONE of the following identifies the system that is no longer operable, and the required action?

A. ADS, station an Equipment Operator in the AER for SRV operation.

B. RPS, stop all Bside RPS testing.

C. HPCI, declare HPCI INOPERABLE per Technical Specification.

D. RCIC, perform T-249 for RCIC.

Page 120 of 200

Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination Correct: C HPCl is INOP due to loss of power to initiation logic and MOVs on a loss of Div 2 DC, HPCl should be declared INOP as a result of the loss of initiation logic Incorrect: A ADS is supplied by Div 1 and Div 3 DC r Incorrect:

Incorrect:

B D

I While B RPS will swap to its AC power source, it is still operable RClC is supplied by Div 1 and Div 3 DC Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 3 Y Y (b) (IO) N Source Documentation Source: New Exam Item [7 Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ARC-MCR-122 G2, ARC MCR-117 A I Learning LLOT0690.02 Objective:

Knowledge/Ability 263000 Importance: RO ISRO WA 2.4.31 3.3 13.4 (Description of K&A, from catalog)

DC Electrical Distribution: Knowledge of annunciators alarms and indicationslanduse of the response instructions Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

61. WHICH ONE of the following identifies values for both frequency and voltage that will satisfy the requirement for a diesel generator breaker to automatically close in on its associated bus?

Frequency Voltaqe A. 56.2 Hz 4.1 KV B. 57.4 Hz 4.0KV C. 58.6 Hz 3.9 KV D. 59.8 Hz 3.8 KV Page 122 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 061 Both RC SQ>Q Basis or Justification Correct: B Frequency and Voltage are required to be 95% of rated in order to energize the Diesel Ready to Load relay and close the output Breaker. These values would be 57 Hz and 3.952 KV Incorrect A Voltage meets the requirement, Frequency does not Incorrect C Frequency meets the requirement, voltage does NOT Incorrect ID Frequency meets the requirement, voltage does not Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.5 4 Y Y (b) (7) N Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): E-I64 Learning LLOT0670.02. LLOT0660.04 0bjective:

KnowledgeJAbility 264000 Importance: RO / SRO WA A3.03 3.4 J3.4 (Description of K&A, from catalog)

Ability to monitor automatic operations of the Emergency Generators including: Indicating lights, meters and recorders Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

62. Unit 1 conditions are as follows:

0 Reactor is shutdown 0 Drywell pressure is 12 psig and steady 0 Reactor pressure is 430 psig and steady 1 A RHR is placed in Suppression Pool Spray.

Reactor pressure drops to 280 psig DIV 1 LPCl INJECTION VALVE DELTA P PERMISSIVE

( I 13A F4) annunciator is in alarm WHICH ONE of the following identifies the response of I A RHR?

A. Suppression Pool Spray automatically isolates and can be immediately re-established.

B. Suppression Pool Spray automatically isolates and cannot be re-established until I A LPCl Injection Valve is closed.

C. Suppression Pool Spray remains in service and must be manually secured to prevent pump runout.

D. Suppression Pool Spray remains in service and I A LPCl injection valve remains closed.

Page 124 of 200

Limer/ck Generating Station ILTO5-I NRC Initial Licensing Examination Answer Key Question ID# 062 Both RC Choice Basis or Justification Correct: C LPCl Injection valve opens (Delta P ANN) as Suppression Pool Spray was placed in service after LPCl initiation signal was present (LOCA signal) it will not automatically isolate and must be manually secured to prevent pump runout with LPCl Injection valve open Incorrect A This is incorrect as spray does not isolate (LOCA) signal received previously) additionally, it cannot be re-established until LPCl injection valve is closed Incorrect B This is incorrect as spray does not isolate (LOCA signal received previously)

~

Incorrect D This is incorrect as LPCl injection valve will open (Delta P ANN)

I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43

+

Low 4.0 3 Y y (b)(7)

Source Documentation Source: New Exam Item c]Previous NRC Exam L 0Modified Bank Item 0ILT Exam Bank ARC-MCR-113 F4, T-225 step 4.2.2 0Other Exam Bank LLOT0370.09b Objective:

230000 Importance: RO / SRO A4.02 3.8/ 3.6 (Description of K&A, from catalog)

Ability to manually operate and/or monitor in the control Room. Spray valves Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination ATTACHMENT: ON-I 26 Provided

63. Unit 1 generator load has been raised in support of a PJM Grid Emergency.

Unit IMain Generator conditions are as follows:

1175MWe 0 230 MVAR's (lagging)

Subsequently, IGEN HYDROGEN AND SEAL OIL SYS TROUBLE ALARM annunciates at 125 GEN.

An EO is dispatched and reports that generator hydrogen pressure is 60 psig and steady.

WHICH ONE of the following describes the required action(s)?

A. Raise hydrogen pressure to 65 psig.

B. Reduce generator output below I125 MWe.

C. Reduce reactive load to 200 MVAR's lagging.

D. Perform a GP-4 Shutdown, trip the Main Turbine.

Page 126 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Choice Basis or Justification Correct: B Reduction in real load to less than 1125 MWe will restore the MW /MWe output to a value consistent with the 60 psig H2heating curve.

Incorrect: A H2Pressure would have to be restored to 75 psig in order to restore the MW/MWe output to within the armature heating curve.

Incorrect: C Reducing MVAR will not reduce the MW/MWe output to within the armature heating curve.

Incorrect: D A GP-4 Shutdown and trip of the Main Turbine would only be required if Hydrogen Pressure could not be maintained above 55 psig.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 3.5 4 N Y (b)(5) N Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): ON-126, Attachment 1 Learning LLOT0600.10 0bjective:

Knowledge/Ability 245000 Importance: RO / SRO WA AI.Ol 2.7 / 2.7 Required Materials:

ON-126 Notes and Comments Prepared By:

Rick Rhode (61 0) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

64. Unit 1 plant conditions are as follows:

0 Reactor power is 100%

A failure of 1BY 185 occurs.

WHICH ONE of the following identifies the status of APRM and RPS?

APRMS -

RPS A. Indicating 0% Power Full Scram B. Indicating 100% Power Half Scram ONLY C. Failed Downscale Full Scram D. Failed Downscale Half Scram ONLY Page 128 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 064 Both RC Choice Basis or Justification Correct: B APRMs power supply is auctioneered, therefore, APRMs are still indicating on a loss of IBY185. Loss of 1BY185 also results in a K SCRAM due to loss of power to 2 PRNMS voter units.

Incorrect A While APRMs would be indicating, this is incorrect because a full scram would not occur.

~~

Incorrect C This is incorrect because it requires a loss of both I A Y I85 and 1BY185 for the APRMs to fail downscale. In addition, a full scram would not occur.

Incorrect D While a half scram would occur, this is incorrect because it requires a loss of both 1AY185 and 1BY185 for the APRMs to fail downscale.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.5 3 N Y (b)(7) N Source Documentation New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank ANN 123 F-5, ANN 108 D-4, ANN 108 A-I LLOT0275.I3c Objective:

I Knowledge/Ability 215002 K2.03 (Description of K&A, from catalog)

~~~~ ~~ ~

Importance: RO I SRO 2.8 12.9 Knowledge of electrical power supplies to the APRM channels Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

65. Plant conditions are as follows:

0 Control Room Ventilation system is operating in the normal mode A control room intake high radiation isolation signal is received on the ID channel ONLY.

WHICH ONE of the following describes the subsequent Control Room Ventilation system status?

CREFAS FAN RUNNING OUTSIDE AIR ENTERING MCR A. OA Yes B. OA No C. OB Yes D. OB No Page 130 of 200

Limerick Generatinq Station ILTO5-I NRC Initial Licensina Examination Answer Key Question ID# 065 Both RC rFRq Choice Basis or Justification Correct:

I D D RAD Signal will start the OB Fan and result in normal CR ventilation isolation. It will not lineup the correct dampers to supply outside air to the MCR (Additional channel isolations needed)

Incorrect:

IA Outside air will not be lined up as correct dampers to supply outside air to MCR are not opened on a D only isolation signal also OA Fan will not start on a D RAD signal

~~~

Incorrect:

Incorrect:

lB C OA Fan will not start on a D RAD signal Same text as A distractor Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 I

Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank ILT Exam Bank P&ID M-26 sht 5 detail D, M-78 sht 1 LLOT0450.7a 0bjective:

Knowledge/Ability 290003 Importance: RO / SRO KIA K4.01 3.1 / 3.2 (Description of K&A, from catalog)

Knowledge of Control Room HVAC: design features and/or interlocks which provide for system initiationdreconfiguration Recirculation System Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

66. Unit 1 plant conditions are as follows:

0 Div II DC is deenergized 0 A digital feedwater malfunction is causing RPV level control problems 0 A GP-4 shutdown is performed Following the scram, RPV level drops and is automatically restored by RCIC.

WHICH ONE of the following describes the status of the IA and 1B Reactor Recirc Pumps?

I A Recirc Pump 1B Recirc Pump A. Running Running B. Running Tripped C. Tripped Running D. Tripped Tripped Page 132 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination Basis or Justification Correct: D RPT breaker logic will normally trip both RPTs on -38. RClC auto start indicates this parameter is reached. The loss of Div II DC will prevent one RPT breaker per pump from tripping, but the other one will trip and r

therefore, both pumps will be deenergized.

Incorrect: A Neither pump will be running due to RPT breakers for both pumps tripping Incorrect: B The I B will be tripped, however the 1 A will also be tripped.

Incorrect: C The 1 A will be tripped, however the 1B will also be tripped.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 HIGH 3.5 4 Y N Y (b)(5)

Source Documentation Source: HNew Exam Item Previous NRC Exam OModified Bank Item 0Other Exam Bank (LOR) 0ILT Exam Bank Reference(s): E-I FB, ARC MCR 11IC-5, ARC MCR 112 D-3, GP-18, step 1.O Learning LLOT0315.06 Objective:

Knowledge/Ability 2.4.21 I Importance: RO / SRO KIA 3.7/ 4.3 (Description of K&A, from catalog)

Knowledge of the parameters and logic used to assess the status of safety functions iquired Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

67. Unit Iplant conditions are as follows:

Drywell pressure 0.5 psig and rising 0 Reactor pressure 1045 psig and steady 0 HPCl room temperature 175OF and rising 0 SDV level in AER is 10% and rising WHICH ONE of the following alarms is consistent with the noted conditions?

A. DIV 1 DRYWELL HI PRESS ( I 13 E4)

B. REACTOR HI PRESSURE TRIP (107 G I )

C. B REAC ENCL HVAC PCL 1BC208 TROUBLE (004 A3)

D. SCRAM DISCHARGE VOLUME HI LEVEL TRIP (107 C l )

Page 134 of 200

Limerick Generatinq Station ILTO5-1 NRC Initial Licensinq Examination Answer Key I Choice I Basis or Justification 1 Correct: C 1BC208 panel trouble and HPCl room temp are consistent Incorrect: Drywell pressure value is below Alarm setpoint I Incorrect:

B l Reactor pressure valve is below the ALARM setpoint L

I Incorrect: D SDV level is below the ALARM setpoint Psvc hometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.5 3 N N Y (b)(5)

Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Modified Reference@): ANNS 004 A3 Learning LLOTI560.02 Objective:

Knowledge/Ability 2.4.46 Importance: RO / SRO WA 3.5 13.6 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

68. Both units are at 100% when the following alarms:

0 LIQUID RADWASTE DISCHARGE HI RADIATION (003 A5)

The Radwaste Operator contacts the MCR and ,reports the following in alarm in the Radwaste Control Room:

LIQUID RADWASTE DISCHARGE RAD MONITOR HIHI/INOP (OA304, C-1)

WHICH ONE of the following flowpaths will automatically isolate based on these conditions?

A. Equipment Drain Sample Tank Discharge to CST B. Waste Sludge Tank Discharge to External Processing C. Reactor Enclosure Floor Drain Sump Discharge to Liquid Radwaste D. Floor Drain Sample Tank Discharge to Cooling Tower Blowdown Line Page 136 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key I Choice I Basis or Justification Correct:

IDl Liquid Radwaste discharge to Cooling Tower Blowdown Line isolates on Hi Hi Rad.

Incorrect Equipment Drain Sample Tank to CST isolates on EDST Level only (Pump off, discharge valve closes)

Incorrect B Waste Sludge Tank to external processing isolates on Low Waste Sludge Tank level only (Pump off, discharge valve closes)

Incorrect C The only control functions associated with RE Floor Drain Sump pumps are Low-Low Level and Primary Containment Isolation Hi Rad Lockout (Post LOCA Rad Monitor Hi-Hi) will deenergize the pumps.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N N N Source: New Exam Item Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference@): ARC-MCR-003 RAD-A-5, ARC-BOP-OAC304-C-1 Learning 0bjective: I LL0T-0705-04 Knowledge/Ability 2.3.1 1 Importance: RO / SRO WA 2.7 13.2 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

69. An Equipment Operator (EO) is required to enter an area in the Main Condenser with a general area radiation level of 3 Rem/hr in order to perform a surveillance test.

The EOS radiation history is as follows:

0 1760 mRem cumulative exposure for the current year (TEDE) 0 I 9 Rem lifetime exposure to this date (TEDE) 0 NRC form 4 completed and on file 0 No dose extensions have been obtained The surveillance test will take 45 minutes to complete.

WHICH ONE of the following radiation exposure limits, if any, would be exceeded if the EO performs the surveillance test?

A. No limits are exceeded.

B. Administrative Dose Control Level ONLY.

C. Administrative Dose control Level AND NRC Exposure Limit ONLY.

D. Administrative Dose Control Level, NRC Exposure Limit, AND Emergency Exposure Limit.

Page I38 of 200

Limerick Generating Station lLT05-1 NRC Initial Licensinq Examination Answer Key auestion ID# 069 ROISRC Choice Basis or Justification Correct: B 3 Rem = 3000 mRem 3000 mRem X .75= 2250 mRem 2250 mRem + 1760 mRem = 4010 mRem 4010 mRem exceeds 2000 mRem TEDE Admin Dose Control Level Incorrect A Admin Dose Control Level is exceeded Incorrect C 4010 mRem <NRC Limit of 5000 mRem Incorrect D 4010 mRem <NRC Limit of 5000 mRem 4010 mRem <Emergency Exposure Limit of 10,000 mRem for protecting station property Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 Y N Y (b)(4)

Source: 0New Exam Item Previous NRC Exam 2002 Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): RP-AA-203 sects 4.1 .I, 4.2,4.5 Learning LLOTI760.04,.05 Objective:

KnowledgelAbility 2.3.4 Importance: RO / SRO WA 2.5 13.1 (Description of K&A, from catalog)

Knowledge of radiation exposure limits and contamination controVincluding permissible levels in excess of those authorized..

Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination ATTACHMENT: GP-2, Appendix 1 Provided

70. A reactor startup is in progress on Unit 2.

All Group Iand Group 2 control rods are fully withdrawn.

SRM count rate data since the startup began is as follows:

0 Channel Y A has gone from 240 cps to 975 cps 0 Channel 1B has gone from 225 cps to 915 cps 0 Channel I C has gone from 220 cps to 890 cps 0 Channel I D has gone from 235 cps to 940 cps WHICH ONE of the following identifies control rod notch positions where control rod withdraw shall be restricted to single notch movement?

A. Between 00 and 08 B. Between I 2 and 78 C. Between 18 and 30 D. Between 30 and 48 Page 140 of 200

Li merick Generat ing Station lLTO5-1 NRC Initial Licensing Examination 1 Answer Key Question ID# 070 Both RC I Choice Basis or Justification Correct: A After 75% rod density (Group 1-2 fully withdrawn), control rod withdraw between notch positions 00 to 12 shall be restricted to single notch movements until criticality is achieved. 00 to 08 falls within this band.

Incorrect B Single notch is require between 04 to 30 applies once the SRM count rate reaches four doublings. SRM count rate is only doubled at this point, so the 00 to 12 requirement still applies. 12 to 18 falls outside that band.

Incorrect C Due to the reasons stated above, the 00 to 12 requirement still applies. I 8 to 30 falls outside that band.

Incorrect D Due to the reasons stated above, the 00 to 12 requirement still applies. 30 to 48 falls outside that band.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N N N Source Documentation Source: 0New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): GP-2, Appendix I,Caution after step 3.2.7 Learning LLOTI530.02 0bjective:

KnowledgelAbility 2.2.1 Importance: RO I SRO WA 3.7 13.6 Required Materials:

GP-2, Appendix 1 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination

71. Unit 1 PRO is performing ST-6-051-231-1, I A RHR Pump, Valve, and Flow Test.

At step 4.3.6, the PRO discovers that HV-51-1F021A is incorrectly identified as HV-51-1F022A.

WHICH ONE of the following identifies the status of the Surveillance Test and the action required to correct the error?

A. Stop the test. Identify the component number error in an action item to revise the procedure per AD-LG-101-1004, Procedure Performance Improvement System (PPIs), prior to resuming the ST.

B. Stop the test. Initiate a Temporary Change to correct the component number error per AD-LG-101-1002, Temporary Changes to Approved Documents and Partial Procedure Use, prior to resuming the ST.

C. Continue the test. When it is complete, identify the component number error in an action item to revise the procedure per AD-LG-101-1004, Procedure Performance Improvement System (PPIs).

D. Continue the test. When it is complete, initiate a Temporary Change to correct the component number error per AD-LG-101-1002, Temporary Changes to Approved Documents and Partial Procedure Use.

Page 142 of 200

Limerick Generating Station lLTO5-I NRC Initial Licensing Examination Answer Key Question ID# 071 Both RC Choice Basis or Justification Correct: B The test must stop. An equipment number error requires a Temporary Change I.A.W. AD-LG-101-1002, before the test can continue.

Incorrect: A The status of the test is correct, but the procedure process cited is not correct.

Incorrect: C The procedure process cited is correct, however the test cannot continue.

~ ~

Incorrect: D Both the status of the test and the procedure process cited are incorrect.

Psychometrics I Level of Knowledge Low Difficulty 2.5 Time Allowance (minutes) 3 I pRA N

1 RO 10CFR55.41 Y (b)(lO)

I 10CFR55.43 SRo Y (b)(3)

I ISource: New Exam Item Source Documentation Modified Bank Item 0Previous NRC Exam 0Other Exam Bank 0ILT Exam Bank AD-LG-I 01-1002 Learning LLOTI570.01 Objective:

1 Importance:

LKnowledge/Ability 2.2.1 1 (Descriptionof K&A, from catalog)

Knowledge of the process for controlling temporary changes.

RO / SRO Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination

72. YA Reactor Feed Pump impeller needs to be repaired at power.

0 Only one manual valve is available for isolation of the pump suction 0 Pump suction pressure is 450 psig 0 Pump suction temperature is 36OoF WHICH ONE of the following clearance requirements will allow this work to be performed per OP-MA-109-1OI?

.A. A clearance Technical Evaluation shall be performed.

B. The work shall be performed under an Exceptional Clearance.

C. A component walkdown shall be performed prior to application.

D. The single isolation valve shall be restrained and locked in the closed position.

Page 144 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 072 Both RC 9FtQ Choice Basis or Justification Correct: B When 2-valve protection is required but not available then the clearance shall be designated as Exceptional.

Incorrect: A A technical review is required only when there are questions about a systems response to the proposed isolation technique (such as logic

~

system response)

Incorrect: C A walkdown is suggested in circumstances where clearance informationor documentation is missing or in question Incorrect: D A Blocking device (such as a lock, restraint, or gag) is only required for a component that can fail to a position other than the tagged position.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 2.5 3 N Y (b)(lO) N Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item [XI Other Exam Bank (CAT) 0ILT Exam Bank Reference@): OP-MA-109-101, attachment 4 Learning OP-MA-109-101 DB16 objective #2 0bjective:

Knowledge/Ability 2.2.13 Importance: RO / SRO WA 3.6 13.8 (Description of K&A, from catalog)

Knowledge of Clearance and Tagging procedures Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination

73. Given the following values from the most recent P - I :

0 MFLCPR 0.954 0 MFLPD 1.015 0 MAPRAT 0.991 0 FLLLP 0.967 WHICH ONE of the following identifies the thermal limit(s) that require action, if any?

A. MFLPD ONLY.

B. MFLPD and MAPRAT ONLY.

C. MFLPD, MAPRAT, and FLLLP.

D. All values are acceptable; no action is required.

Page 146 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question'ID# 073 Both RC ggg I Choice ~~

Basis or Justification Correct: B MFLPD (>I .O) and MAPRAT (20.99) require entry into GP-14

~

Incorrect: A MFLPD does require action (see above) but this choice omits MAPRAT, which also requires action

~

Incorrect: C FLLLP does not require action r Incorrect: D MFLPD and MAPRAT require action Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 HIGH 2.5 3 N N N Source Documentation Source: 0New Exam Item Previous NRC Exam 0Modified NRC Bank Item Other Exam Bank (LOR-modified)

ILT Exam Bank Reference(s): GP-5, Sect 3.1.I Learning LLOT0741.04 Objective:

KnowledgeIAbility 2.1 . I 9 I Importance: RO / SRO KIA 3.0 13.0 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensina Examination

74. Unit I is in OPCON 2 with reactor startup in progress.

All IRMs are on Range 6 and reading as follows:

A - 37/125ths B- 23/125ths tC - 31/125ths D - 38/125ths E - 28/125ths F - 39/125ths G - 33/125ths H - 26/125ths WHICH ONE of the following identifies the Rod Block and RPS status if all IRM Range Switches are positioned to Range 5?

A. Control Rod Withdraw Block ONLY B. Control Rod Withdraw Block AND A side /2 Scram ONLY C. Control Rod Withdraw Block AND B side % Scram ONLY D. Control Rod Withdraw Block AND full Scram Page 148 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination I Answer Key Ic Question ID# 074 Both RC geq I Choice Basis or Justification Correct: C Ranging from 6 to 5 will multiply all readings by 3.16, which will result in exceeding 120/125ths on channel IF. This channel inputs to B RPS resulting in a % scram. Any channel over 85/125ths results in a Rod Withdraw Block.

Incorrect: A There will be a % scram on B RPS, in addition to the Rod Withdraw Block.

Incorrect: B There will be a K scram on B, not A,RPS 1 Incorrect: 1 D There will be a K scram on only BRPS I~ Psychometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 3 3 Y Y (b)(lO) Y (b)(3)

I Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): Tech Specs 2.2.1 and 3.3.6 Learning LLOT0250.08,09 Objective:

Knowledge/Ability 2.1.28 Importance: RO / SRO WA 4.0 / 3.5 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC initial Licensing Examination

75. Given the following conditions:

Both units are operating at full power The entire shift attended the morning Shift Turnover Meeting given by the Control Room Supervisor (CRS) and Shift Manager (SM)

At 1100, the 3rdRO relieves the Unit 2 RO for lunch.

The Unit 2 RO will be eating lunch in the Main Control Room (MCR)

Lunchroom.

WHICH ONE of the following identifies the required MINIMUM TURNOVER ACTIVITY and MAXIMUM DURATION of the RO's mid-shift turnover for the given conditions?

A. Read the MCR logs through the last previous day on shift.

The relief duration shall be a MAXIMUM of 30 minutes.

B. Read the MCR logs through the last previous day on shift.

The relief duration shall be a MAXIMUM of 60 minutes.

C. Review the Shift Turnover Checklist and review updated plant status.

The relief duration shall be a MAXIMUM of 30 minutes.

D. Review the Shift Turnover Checklist and review updated plant status.

The relief duration shall be a MAXIMUM of 60 minutes

' Page 150 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key Choice Basis or Justification Correct: D Mid-shift turnover of less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> consists of a review of the Shift Turnover checklist and update of plant status, provided the original watch stander remains in the Main Control Room area Incorrect: A Reading the MCR logs through the last previous day on shift applies to a full shift turnover, short turnover duration is 60 minutes, not 30.

Incorrect: B Duration is correct, turnover criteria described applies to full turnover, not short duration Incorrect: -I+ Turnover criteria is correct, short turnover duration is 60 minutes, not 30 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 Low 2.5 3 N Y (b)(lO) N Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): OP-AA-112-101, Sect 4.1.7 Learning LLOTI 574.24 0bjective:

KnowledgelAbility 2.1.3 Importance: RO / SRO KIA 3.0 13.4 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILTO5-1 NRC Initial Licensing Examination

76. Unit 1 Plant conditions are as follows:

0 Reactor power is 100%

0 Reactor level is 35and steady Narrow Range RPV Level Transmitters LT-042-1 N004A, B, and C suffer hardware failures with outputs at 0 mA, resulting in the following:

0 FEEDWATER FAILURE (107 D4) annunciator is in alarm WHICH ONE of the following identifies the effect on individual Reactor Feed Pump M/A stations: FIC-M1-1 RGOIA(B,C) A(B,C) RFPT Speed Controllers, and the procedure entered to address initial plant response?

Effect on Procedure FIC-M1-I RGOIA(B,C) Entered A. Swaps to Manual OT-I 00 B. Swaps to Manual OT-I I0 C. Remains in Auto OT-I 00 D. Remains in Auto OT-I 10 Page 152 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key CQuestion ID# 076 SRO Or i I Choice Basis or Justification Correct: B With 3 level transmitters failed downscale, individual RFP MIA stations will automatically swap to manual. Additionally due to the failure of the level signal, the recirc pumps will run back. This combination of RFPs in manual coincident with a Recirc pump run back, result in level going up requiring in entry into OT-I I O REACTOR HIGH LEVEL Incorrect: A This is incorrect as OT-100 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up Incorrect C This is incorrect as individual RFP M/A stations will swap to manual, and OT-I00 REACTOR LOW LEVEL, is for low reactor level, Reactor level will go up Incorrect D This is incorrect as individual RFP M/A stations will swap to manual.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.0 4 Y y (b)(5) y (b)(5)

Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): S06.1 .HU/1, Alarm Identity IXX-FW302.1TFFE S06.1 .D U/1 Appendix 1 Learning LLOT0550.1Od 0bjective:

Knowledge/Ability 259002 Importance: RO / SRO WA A2.03 3.6 I3.7 (Descriptionof K&A, from catalog)

Ability to predict the impact of the following on Reactor water level control and based on those predictions use procedures to correct, control or mitigate the consequence of those abnormal conditions or operations: Loss of Reactor Water Level Input.

bquired Materials:

Notes and Comments:

Prepared By:

Rick Rhode (61 0) 718-4085 Limerick Regulatory Exam Author

___ .

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

77. Unit 1 plant conditions are as follows:

0 Reactor power is 10%

0 Reactor level is -200 and lowering 0 All MSlVs are closed 0 Suppression Pool temperature is 12OoFand rising 0 A blowdown is in progress with 3 SRVs open 0 Reactor pressure is 650 psig and lowering The Floor Supervisor reports T-251 is complete for Unit I WHICH ONE of the following identifies the required operator action?

A. Immediately inject with HPCI.

Restore level to -60 to -1 00.

B. Immediately inject with HPCI.

Restore level to -1 61 to -1 86.

C. Inject with HPCl when Reactor pressure is below 400 psig.

Restore level to -60 to -1 00.

D. Inject with HPCl when Reactor pressure is below 400 psig.

Restore level to -1 61 to -1 86.

Page 154 of 200

Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination Correct: D As Blowdown is already in progress, injection cannot occur until MIN ALT FLOODING PRESSUE is met. With only 3 SRVs open that occurs at 400 psig. Level band is -161 to -186 as Supp pool temp is greater than I 1 0 degrees Incorrect: A Injecting immediately is incorrect as Blowdown has already started. -60 to

-100 is incorrect as Supp pool temp is greater than 110 degrees Incorrect B Injecting immediately is incorrect as Blowdown has already started.

Incorrect -60 to -1 00 is incorrect as Supp pool temp is greater than 110 degrees I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 4.0 4 Y Y (b)(lO) Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): T-I 17 BASES, Step LQ-21 Learning LLOTI560.05 Objective:

KnowledgelAbility 295037 Importance: RO ISRO, KIA 2.12 0 4.3 14.2 T-I 17 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensinq Examination ATTACHMENT: SAMP-I Sheet 1 Provided I

78. Unit 1 plant conditions are as follows:

SAMP-I and SAMP-2 have been entered The Reactor was shutdown 20 minutes ago Reactor Level is -320 and dropping Reactor pressure is 800 psig and steady RClC is injecting at 600 GPM ALL other high pressure injection systems are unavailable Suppression pool level is 22 Suppression pool pressure is 20 psig WHICH ONE of the following SAMP-I sheets must be executed?

A. Sheet 4 B. Sheet5 C. Sheet6 D. Sheet7 Page 156 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 078 SRO Or /

Choice Basis or Justification Correct: D Sheet 7, To determine correct answer the candidate must determine that level cannot be restored to -31 1 (insufficient injection source are available for the current reactor pressure, AND attempts to blowdown as directed prior to reaching current reactor level must have been unsuccessful precluding use of low pressure systems), injection is unsafe as plotted on the MDRIR curve (20 minutes, Rx press 800 psig, injection rate 600 gpm), AND that conditions are unsafe as plotted on PSP curve (pool level 22, and pressure 20 psig).

Incorrect: A Sheet 4 is incorrect as level cannot be restored above -31 1. The candidate must determine that insufficient injection source are available for the current Reactor pressure, AND attempts to blowdown as directed prior to reaching current reactor level must have been unsuccessful precluding use of low pressure systems.

Incorrect B Sheet 5 is incorrect as RPV injection is unsafe on MDRIR as plotted (20 minutes, Rx press 800 psig, injection rate 600 gpm)

Incorrect C Sheet 6 is incorrect as conditions are unsafe as plotted on PSP curve (pool level 22, and pressure 20 psig)

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 4.0 4 Y Y (b)(l 0) Y (b)(5)

Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank (LOR)

ILT Exam Bank Reference(s): SAMP 1, Sheet 1 Learning LLOTI 562.6 Objective:

Knowledge/Ability 295031 Importance: RO I SRO WA 2.4.6 3.1 14.0 Required Materials:

SAMPI Sht 1 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensing Examination ATTACHMENT: OT-I 12, Partial Provided

79. Unit 1 Reactor Power is 100%.

The following transient occurs with the indicated plant conditions:

0 1B Recirc Pump trips 0 I A Recirc Pump speed is 65%

0 ALL four OPRM Operator Display Assemblies indicate Reactor power is 58%

0 XR-042-1R613 indicates core plate differential pressure is 1.3 psid 0 XR-042-1R613 indicates core flow is 42 x 1O6 Ibm/hr WHICH ONE of the following is the required operator action?

A. Immediately Scram the Reactor B. Restart I B Recirc Pump, and raise core flow with I B Recirc Pump.

C. Reduce Recirc Pump speed to less than 60% and manually scram the reactor.

D. Insert control rods until the Restricted Region of the Power/Flow Map is exited.

Page 158 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice ~

I Basis or Justification Correct: D Because the speed of the operating Recirc Pump is >60%, the Core Flow and Reactor power indications provided should be used to determine operating point. With the given information, the plant is in the Restricted Region, and the correct action is an immediate exit by the insertion of control rods or the raising of Recirculation flow.

Incorrect: A Immediately scram the reactor is not correct because the operating point is not in the Exclusion Region, therefore, a reactor scram is not required.

Incorrect B Restart 1B Recirc Pump and raise core flow with 1B recirc pump is wrong as restarting a pump to raise flow is not allowed in OT-I I 2 Incorrect C Reduce Recirc pump speed to less than 60% and manually scram the reactor is not correct as reducing speed drive the reactor further into the restricted region.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 3.0 5 N Y (b)(lO) Y (b)(5)

Source: New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): OT-I 12, Step 3.7 Learning LLOT0040.07g Objective:

Knowledge/Ability 295001 Importance: RO / SRO WA AA2.01 3.5 f 3.8 OT-112, Power to Flow Maps Attachment 1 & 2 only Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

_ _

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

80. The Main Control Room has been abandoned due to a fire.

Equipment Operators are going to enter a locked high radiation area in order to manually operate Primary Containment Isolation Valves.

The highest dose rate in the area is 1250 mRem/hr.

Per RP-LG-460-1010 and RP-LG-460-1016,WHICH ONE of the following describes the type of Locked High Radiation Area and the highest level authorization required for issuing the key?

Tvpe of LHRA Highest Authorization Required A. Level 1 Radiation Protection Manager B. Level 1 Plant Manager C. Level 2 Radiation Protection Manager D. Level 2 Plant Manager Page 160 of 200

Limerick Generating Station ILT05-I NRC Initial Licensina Examination Answer Key Question ID# 080 SRO Or Y

~~

Basis or Justification Correct: The area is a Level 1 LHRA ( 2 1000 hr/hr and < I 5 Whr) per RP-LG-460-1010. This requires authorizationfrom the RP Manager for issuing the key per RP-LG-460-1016.

Incorrect: B The level is correct, but the Plant Managers authorization is not required.

incorrect C Level 2 LHRA would be an area with dose rate 2 15 Whr. The RP Manager may not be the sole authorization for this entry.

Incorrect ID Level 2 LHRA would be an area with dose rate 2 15 Whr. The Plant Manager may authorization for this entry.

I I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 4.0 4 N N (b) (4)

Source: 0New Exam Item 0Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): RP-LG-460-1010, RP-LG-460-1016.

Learning LLOTI760.01 Objective:

Knowledge/Ability 295016 Importance: RO / SRO KIA 2.3.1 2.6 13.0 Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

81. Unit 2 is in OPCON 3 preparing for a refueling outage with the following conditions:

0 RPV Level is 85 0 2B loop of SDC is in service 0 Reactor coolant temperature is 3OO0F 0 RPV pressure is 54 psig 0 ?A RHR Heat Exchanger is being drained for maintenance 0 A Group IIsolation signal is in for I&C testing 0 Cooling Tower draining is in progress An electrical fault causes a loss of 044k 1>22 MY&& 11131~b Subsequently, Reactor coolant temperature is 325OF and RPV pressure is 85 psig.

WHICH ONE of the following describes the action required and the procedure used to perform the required action?

A. Use dedicated LPCl Pumps for Shutdown Cooling per S51.8.H.

B. Line up for RHR Alternate Decay Heat Removal per S51.8.L.

C. Reduce RPV pressure using Main Steam Line Drains per ON-121.

D. Reduce RPV pressure using ADS SRVs per ON-I 21.

Page 162 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key Choice

~~

I Basis or Justification Correct: D RPV pressure is sufficient to cause a SDC isolation. Pressure must be reduced before SDC can be restored. The cooling tower draining makes the Main Condenser unavailable per ON-I 21 bases and therefore, pressure must be reduced with SRVs.

Incorrect: A Dedicated LPCl Pumps will not work because SDC is isolated.

Incorrect IBl RHR Alternate SDC lineup will not work because current plant conditions will not support it.

Incorrect ici Although this choice correctly identifies that RPV pressure must be reduced, MSL drains will not work because the condenser is not available.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) IOCFR55.41 10CFR55.43 High 4.0 4 Y Y (b)(lO) y (b) ( 5 )

Source Documentation Source: New Exam Item Previous NRC Exam Modified Bank Item 0Other Exam Bank ILT Exam Bank Reference(s): ON-121, Attachment 5 Learning LLOT0370.13 0bjective:

Knowledge/Ability 295021 Importance: RO / SRO K/A AA2.06 3.2 / 3.3 (Description of K&A, from catalog)

Ability to determine and/or interpret the following as they apply to a loss of shutdown cooling: Reactor Pressure Required Materials:

Notes and Comments:

Prepared By:

Rick Rhode (610) 718-4085.

Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensing Examination ATTACHMENT: TURBINE BACKPRESSURE OPERATION LIMIT GRAPH Provided

82. Unit 1 conditions are as follows:

0 Reactor Power is 75%

0 BESSI System is not in operation The following annunciators are received:

TURBINE HIGH BACK PRESSURE (106 D2) 1A CONDENSOR LO VACUUM (104 E-5)

The following parameters are observed:

0 LP Turbine Inlet Pressure is 100 psig 0 I A LP Turbine Back Pressure is 7.2 in Hg Abs 0 I B LP Turbine Back Pressure is 6.6 in Hg Abs 0 I C LP Turbine Back Pressure is 6.0 in Hg Abs 0 Main Condenser vacuum has dropped from 26 in Hg Vac to 23 in Hg Vac Main Condenser vacuum is 23 in Hg Vac and steady.

WHICH ONE of the following identifies the required operator action and the procedure used to perform the required action?

A: Trip the Main Turbine per GP-5.

B. Trip the Main Turbine per OT-I 16.

C. Reduce reactor power per GP-5.

D. Reduce reactor power per OT-I 16.

Page 164 of 200

Limerick Generating Station ILT05-I NRC initial Licensinn Examination Answer Key Question ID# 082 SRO 01 i Choice Basis or Justification Correct:

I C Student must plot values on Turbine Backpressure Operation Limit Graph to determine that turbine is operating in the limited region and power must be reduced IAW GP-5 to restore backpressure to the unlimited region Incorrect:

l A If turbine backpressure could not be restored, then a GP-4 Shutdown is directed. Tripping the turbine at this time is not directed.

Incorrect Incorrect IB D Tripping the turbine is directed by OT-I 16 if Main Condenser vacuum reaches 21.5 in Hg Vac Reducing reactor power is directed by OT-I 16 until condenser vacuum stops dropping. Since vacuum is steady, a power reduction is not directed by OT-I 16 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.0 3 Y Y (b) (IO) Y (b) (5)

Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s ): GP-5 Attachment 7 Learning LLOT0500.06a Objective:

1

~

Knowledge/Ability 295002 Importance: RO / SRO WA AA2.01 2.9 13.1 (Description of K&A, from catalog)

Ability to determine and/or interpret condenser vacuurn/absolute pressure as it applies to a loss of main condenser vacuum

!quired Materials:

TURBINE BACKPRESSURE OPERATION LIMIT GRAPH Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generating Station lLTO5-I NRC Initial Licensing Examination

83. Unit 1 conditions are as follows:

0 Reactor power is 100%

0 HPCl is running in Full Flow Test for required surveillance WHICH ONE of the following identifies the Technical Specification limit for Suppression Pool temperature and the bases for the limit?

A. 105OF Provides sufficient temperature margin to allow SBLC injection to shutdown the reactor during an ATWS without exceeding HCTL.

B. 105OF Maintain bulk water temperature such that there is adequate NPSH for ECCS pumps following a blowdown.

C. 95OF Provides sufficient temperature margin to allow SBLC injection to shutdown the reactor during an ATWS without exceeding HCTL.

D. 95OF Maintain bulk water temperature such that there is adequate NPSH for ECCS pumps following a blowdown.

Page 166 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key CQuestion ID# 083 SRO Or I Choice Basis or Justification I Correct: I B Tech Spec 3.6.2.1 limits suppression pool max temperature to 105OF with testing that adds heat to the suppression pool. The basis for the limit is to maintain water temperature and suppression chamber conditions such that there is adequate NPSH for ECCS pumps following a blowdown.

The temperature limit is correct, however the basis is incorrect. This is the Trip Procedure basis suppression pool limit (110 degrees F) once T-I 02 or T-117 is entered.

Incorrect Incorrect ic D This is the temperature limit for NO testing in progress that adds heat to the suppression pool and the Trip Bases temperature limit described above.

The Tech Spec basis is correct, however, the temperature limit is for NO testing in progress that adds heat to the suppression pool.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 3 N N Y (b)(2)

Source: New Exam Item Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): Tech Spec basis 3.6.2.1 Learning LLOTOI30.04f Objective:

Knowledge/Ability 295013 Importance: RO / SRO WA 2.2.25 4.0 / 4.0 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

84. A grid disturbance has caused as loss of power to the I O Station Aux Transformer and the 20 Regulating Transformer.

Conditions are as follows:

0 Unit 2 Reactor has scrammed 0 D23 and D24 Diesel Generators have started and are supplying their respective busses 0 021 and D22 Diesel Generators did NOT start On Unit 2, WHICH ONE of the following identifies an instrument that can be used to determine reactor pressure and the procedure entered due to the given conditions?

Instrument Procedure A. Wide Range PAMS E-1 B. Wide Range PAMS E-10/20 C. HPCl Steam Line Pressure E-1 D. HPCl Steam Line Pressure E-I 0/20 Page 168 of 200

Limerick Generating Station ILT05-I NRC Initial Licensing Examination I

I Basis or Justification Correct: D Unit 2 is in a Loss of Offsite Power (E-l0/20). Due to the loss of D21 and D22, PAMS is not available. HPCl Steam Line Pressure is available on both units.

Incorrect: A The procedure reference is not correct. PAMS is not available.

incorrect B The procedure reference is correct. PAMS is not available.

r--- Incorrect C The procedure reference is not correct. The instrument is correct.

Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 3 Y Y (b)(lO) Y (b)(5)

Source: [XI New Exam item 0Previous NRC Exam 0Modified Bank Item c]Other Exam Bank 0ILT Exam Bank Reference(s ): E-I, E-I0/20 Learning LLOT0275.13 0bjective:

Knowiedge/Ability 295003 Importance: RO / SRO WA AA2.02 4.2 / 4.3 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensina Examination

85. Unit Iplant conditions are as follows:

0 Reactor Power is 100%

0 A steam leak occurs in HPCl room 0 DIV 2 STEAM LEAK DET SYS HI TEMPmROUBLE (107, G5) annunciator is alarming Based on the given conditions, WHICH ONE of the following identifies RPV water level instrumentation that can be used and the T-200 procedures that are entered?

RPV Water Level Procedures Instrument Entered A. Wide Range Recorder T-290, T-291 ONLY XR42-I R623A on 1OC601 B. Wide Range Recorder T-290, T-291, T-250 XR42-I R623A on 1OC601 C. Upset Range Recorder T-290, T-291 ONLY LR-42-1 R608 on IOC603

d. Upset Range Recorder T-290, T-291, T-250 LR-42-1R608 on 1OC603 Page 170 of 200

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Answer Key 1 Question ID# 085 SRO Or i I Choice Basis or Justification A DIV I I steam leak detection alarm requires entry into T-103, which directs us of PAMs FZ and EQ PMS instruments only for reading Reactor Level.

XR42-1R623A on IOC601 is a PAM and can be used, 1-290, T-291, and T-250 should be performed. In the case of T-250 The candidate must realize that the Div II alarms indicates that a temperature is above MNO which meets the conditions of stop sign SCC/T-4, requiring T-250 be performed per step SCC/T-5 incorrect: A XR42-1R623A on 1OC601 is correct, but, as noted above T-250 should be performed per step SCCTT-5 incorrect C LR-42-1R608 on 1OC601 is a not a PAM and cannot be used Incorrect D LR-42-1R608 on 1OC601 is a not a PAM and cannot be used I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y Y (b)(lO) Y (b)(5)

Source: New Exam Item Previous NRC Exam 17 Modified Bank Item 0Other Exam Bank 17 ILT Exam Bank Reference(s): T-291 Attachment 2 Learning 0bjective: II Knowledge/Ability 295032 LL0T1561.03 I Importance: RO ISRO WA I EA2.02 3.3 13.5 (Description of K&A, from catalog) Ability to determine and/or interpret equipment operability as it applies to high secondary containment area temperature

?quiredMaterials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

86. A LOCA is in progress on Unit 1 with the following conditions:

0 Drywell pressure is 24 psig and rising slowly 0 Drywell temperature is 32OoF and rising slowly 0 RPV pressure is 350 psig and dropping slowly 0 Suppression Pool pressure is 19 psig and rising slowly 0 Suppression Pool temperature is 96OF and rising slowly 0 Suppression Pool level is 22' and rising slowly WHICH ONE of the following describes the required operator action and the basis for the required action?

BAS IS A. Spray the Drywell Reduce containment pressure while per T-225 preventing excessive negative pressure In the Drywell B. Perform an Emergency Transfer RPV energy to the Suppression Blowdown per T-I12 Pool due to steam in the pool airspace preventing containment function C. Spray the Drywell Reduce containment temperature in order to per T-225 prevent exceeding the Drywell ternperature limit D. Perform an Emergency Transfer RPV energy to the Suppression Blowdown per T-I 12 Pool before conditions threaten the integrity of the SRV tailpipes Page 172 of 200

Limerick Generating Station ILT05-I NRC Initial Licensinq Examination Answer Key Question ID# 086 SRO Or I

~~~

Basis or Justification Correct: Suppression Pool Water level and pressure are in the UNSAFE region of the PSP Curve. T-I 02 directs a T-I 12 blowdown based on steam in the suppression pool airspace preventing pressure suppression function if conditions further degrade.

1 Incorrect: I A This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray.

Incorrect C This is a legitimate reason for spraying the drywell if conditions supported this action. Current conditions are unsafe to spray.

u Incorrect Level of Difficulty While the action is correct, the basis is not. At the given RPV pressure, Suppression Pool level would have to be 38.7 ft, in order to threaten the integrity of the SRV tailpipes.

Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 IOCFR55.43 High 3.0 3 Y y (b)(lO) Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): T-102, T-102 Bases Learning LLOTI560.06 0bjective:

Knowledge/Ability 295024 I Importance: RO / SRO WA EA2.04 3.9 / 3.9 (Description of K&A, from catalog) Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE...Suppression Chamber Pressure REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

~~ ~

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination

87. Unit 1 Plant conditions are as follows:

Reactor Power is 100%

0 I&C reports that I C Main Steam ine (R

, SL) High Flow Transrr ters PDT-41-1N088B and PDT-41-IN088C have failed their Surveillance Test 0 All other MSL Flow Transmitters are OPERABLE WHICH ONE of the following describes the status of the MSIV isolation logic and the required action?

A. Div 4 MSlV isolation logic is INOPERABLE.

Place ONE Channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. IC MSL MSlV isolation logic is INOPERABLE.

Place ONE Channel tripped condition within I 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

C. Div 1 and 2 MSlV isolation logic are INOPERABLE.

Place ONE Channel in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D. Div 1 and 2 MSlV isolation logic are INOPERABLE.

Place ONE Channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Page 174 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 087 SR-0 Or I I Choice Basis or Justification Correct: D 88C is Div 1. 88B is Div 2. therefore there is only one Div 1 and Div 2 instrument operable for the 1C MSL. Less than required number for 2 trip systems place one in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Incorrect: A If only one trip system is affected for instrumentation not common to RPS, and placing it in the tripped condition would not cause an isolation; you have 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until having to place it in the tripped condition. If only one trip system were affected, this would be a correct answer.

Incorrect B A common misconception is that a streamline is a trip system. If only one trip system is affected for instrumentation common to RPS, and placing it in the tripped condition would not cause an isolation, you have 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until I

having to place it in the tripped condition I Incorrect C The number of affected systems per line is correct however the time to place in the tripped condition is wrong. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is for one trip system where placing it in the tripped condition will cause an isolation.

I Psvchometrics I Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 5 N Y (b)(5) y (bP)

Source Documentation Source: [XI New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): Unit 1 Tech Specs, LCO 3.3.2 Learning LLOTOI80.1OC 0bjective:

KnowledgeiAbility 223002 Importance: RO i SRO WA A2.08 2.7 i 3.1 REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

88. Unit 2 is in OPCON 5. Plant status is as follows:

Fuel Shuffle Part 2 is 80% complete in Quadrant IV The 201 Safeguards Transformer has been de-energized The 101 Safeguards Transformer is supplying all 4KV busses D21 and D23 Diesel Generators are INOPERABLE for planned maintenance Surveillance testing has just been completed on D24 Diesel Generator Control rod stroke timing is in progress in Quadrant II The C traversing in-core probe is being inserted into the RPV for a TIP Drive PMT Seal repair is in progress on a CRDM hydraulic line in the undervessel area The inside EO reports that the D24 Diesel Generator Fuel Oil Storage Tank indicates 32,500 gallons.

WHICH ONE of the following describes the action required by Tech Specs?

A. Stop control rod stroke timing.

B. Suspend all undervessel work.

C. Suspend operation of the overhead crane over the RPV.

D. Stop the traversing in-core probe PMT and withdraw probe from core.

Page 176 of 200

Limerick Generatina Station ILTO5-1 NRC Initial Licensing Examination Answer Key 4-Question ID# 088 SRO 01 Choice Basis or Justification Correct: A Tech Spec 3.8.1.2 requires suspension of Core Alterations with the AC electrical power sources inoperable in OPCON 5. Control rod movement with fuel in the vessel must be stopped.

Incorrect:

I B Work on a CRDM hydraulic line does not qualify as an Operation with Potentialfor Draining the Vessel.

Incorrect Operation of the Overhead Crane must be suspended over the Spent Fuel Pool but not over the Reactor Cavity.

Inserting a TIP is not considered a Core Alteration.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 4.0 4 Y N Y (b)(2)

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank 0ILT Exam Bank Reference(s): Tech Spec 3.8.1.2, GP-6.2 Learning LLOT0670.13 0bjective:

KnowledgelAbility 264000 Importance: RO / SRO WA 2.2.22 4.0 14.0 (Description of K&A, from catalog)

Knowledge of limiting conditions for operational and safety limits.

REQUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination

89. Unit 2 conditions are as follows:

0 An inadvertent Group Iisolation resulted in MSlV closure and Scram 0 RClC is being used for pressure and level control 0 RClC is currently in injection mode and maintaining RPV level at 35 in Auto 0 RPV pressure is 900 psig and lowering slowly 0 ST-6-107-640-2, Rx Vessel Temperature And Pressure Monitoring, is in progress Subsequently, the RClC Flow Controller fails in AUTO.

The RClC Flow Controller is switched to MANUAL and adjusted so that level is

+35 and steady.

WHICH ONE of the following describes the operator action required to maintain RPV level over the next 30 minutes and the procedure used to perform the required action?

0perator Action Procedure A. Throttle closed HV-49-2F013, S49.7.A, Transfer of RClC From RClC Pump Discharge to Pressure Control Mode to Injection Feedwater Mode and Back B. Raise output of the RClC flow OP-LG-I 08-101-1001, Simple Quick Controller Actsnransient Acts C. Throttle open HV-49-2F013, S49.7.A, Transfer of RClC From RClC Pump Discharge to Pressure Control Mode to Injection Feedwater Mode and Back D. Lower output of the RClC flow OP-LG-108-101-1001, Simple Quick Controller Actsnransient Acts Page 178 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Choice I Basis or Justification Correct: D With the RClC flow controller in MANUAL, it is maintaining constant speed.

With the turbine at constant speed, as, RPV pressure goes down, injection will rise and RPV level will rise. The controller output must be lowered to reduce turbine speed. This is a simple quick act per OP-LG-108-101-1001.

I ncorrect: A This valve would be closed to transfer to pressure control mode. Given the conditions, pressure is going down with just the steam used to drive RCIC, therefore, level will go up. Transfer to pressure control would not be appropriate. The procedure would be appropriate if this were the correct action.

Incorrect B Raising RClC controller output would only exacerbate the level trend that will result from the given conditions. The procedure would be appropriate if this were the correct action.

Incorrect C This valve would be opened to transfer from level control to pressure to pressure control mode. The procedure would be appropriate if this were the correct action.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 Y y (b)(5) y W(5)

Source: New Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank c]ILT Exam Bank Reference(s): S49.7.A Learning LLOT0380.08 0bjective:

Knowledge/Ability 217000 Importance: RO / SRO WA A2.10 3.1 / 3.1

!QUIRED MATERIALS:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

-

Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination

90. Unit 1 Plant conditions are as follows:

0 Reactor Power is 100%

0 An electrical fault on a turbine control valve solenoid results in the closure of the #2 Turbine Control Valve WHICH ONE of the following identifies the initial EHC response and the required proceduraI act ions?

Initial EHC Response Procedural Action A. BPV(s) remain closed, reactor Reduce reactor power to less pressure rises to Scram setpoint than 90% per OT-I02 without operator action B. BPV(s) remain closed, reactor Reduce reactor power until pressure rises to Scram setpoint pressure is less than 1053 psig without operator action per OT-I 04 C. BPV(s) open, reactor pressure Reduce reactor power to less rises and stabilizes without than 90% per OT-I02 operator action D. BPV(s) open, reactor pressure Reduce reactor power until rises and stabilizes without pressure is less than I053 psig operator action per OT-I 04 Page 180 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 090 SRO-Or I Choice Basis or Justification Correct: C Reactor pressure will increase slightly requiring entry into OT-I 02. OT-I02 requires power to be lowered to below 90% on a control valve closure.

Incorrect: A This is incorrect as Reactor pressure will not reach the scram setpoint.

Electricalfailure of the solenoid for the control valve does not affect bypass valve response. The procedural action is correct.

Incorrect B This is incorrect as Reactor pressure will not reach the scram setpoint.

Electricalfailure of the solenoid for the control valve does not affect bypass valve response. While power may rise slightly, if OT-104 were entered, it

---t Incorrect D does NOT reference pressure.

The pressure response is correct, however the procedural action is not.

While power may rise slightly, if OT-I04 were entered, it does NOT reference pressure.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High '3.0 4 N y (b)(5) y Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item c]Other Exam Bank 0ILT Exam Bank Reference(s): OT-102,step 3.5 T.S. 3.2.3.b Learning LLOT0590.02a 0bjective:

Knowledge/Ability 241000 Importance: RO / SRO WA A2.04 3.7 / 3.8 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-I NRC Initial Licensing Examination

91. Unit Iplant conditions are as follows:

0 95%power 0 IC RHR pump has been INOP for 19 days HPCl Full Flow Test is being performed. Maximum flow flow achieved is 5150 gpm.

WHICH ONE of the following describes the required Tech Spec actions?

A. Be in STARTUP in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, HOT SHUTDOWN in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN in the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. Restore the IC RHR Pump to operable within the next 1Idays or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. Restore the 1C RHR pump or the HPCl system to operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in HOT SHUTDOWN in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN in the next +%hours.

a4 r,/3(ob D. Restore the HPCl system to operable within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to 5 200 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Page 182 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key jr Choice Basis or Justification Correct: C Tech Spec 3.5.1 -with HPCl system INOP and one ECCS Subsystem INOP - Restore one of them to OPERABLE within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Incorrect: A This is a Tech Spec 3.0.3 action applicable only when LCOs cannot be met Incorrect B This would be the correct action if HPCI were operable.

Incorrect D This would be correct if IC RHR were operable with HPCl INOP Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 4 Y N Y (b)(2)(5)

Source: U N e w Exam Item 0Previous NRC Exam Modified Bank Item Other Exam Bank (LOR modified)

ILT Exam Bank Reference(s): T. S. 3.5.1.b and 3.5.1.c.2 Learning LLOT0340.16 Objective:

Knowledge/Ability 206000 Importance: RO ISRO KIA 2.1.12 2.9 14.0 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station lLTO5-1 NRC Initial Licensing Examination ATTACHMENT: EAL Matrix Provided

92. Units 2 plant conditions are as follows:

A steam leak is in progress in the Outboard MSlV Room 0 Outboard MSlV room temperature is 18OoFand steady No other areas are exceeding Maximum Safe Operating temperatures Security reports the blowout panel from the steam chase to the North Stack has actuated The reactor is manually scrammed All efforts to isolate the leak have failed Field Team Monitoring reports that the dose rate has been 200 mRem/hr TEDE at the Site Boundary for the last hour, WHICH ONE of the following identifies the TRIP procedure(s) that require(s) entry and if an Emergency Blowdown is required per T - I 12?

TRIP Procedure Entry T-I 12 Emerqency Required Blowdown Required A. T-I03 ONLY Yes B. T-I03 ONLY No C. T - I 03 AND T-I 04 Yes D. T-I 03 AND T - I 04 No Page 184 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 092 SRO Or /

I Choice Basis or Justification Correct: D Site boundary release is at Site Area Emergency level, therefore entry into T-104 is required per EAL Matrix. Release is not at or approaching General Emergency level and 2 areas are not exceeding MSO, therefore T-112 is not required.

Incorrect: A T-I04 entry is required and T-I 12 is not for the reasons given above.

I ncorrect B T-104 entry is required for the reason given above.

Incorrect C T-I 12 is not required for the reason given above Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 3 N Y (b) 10 y (b)(5)

Source: 0New Exam Item [XI Previous NRC Exam Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): Emergency Action Level Matrix (Table 3-I), T-103, T-I04 Learning LLOTl560.02,06 0bjective:

KnowledgelAbility 2.4.1 Importance: RO I SRO WA 2.3 14.1 Required Materials:

EAL Matrix Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick GeneratinQ Station ILT05-I NRC Initial Licensinq Examination ATTACHMENT: T-228, Partial Provided

93. Unit 1 plant conditions are as follows:

0 A LOCA occurred 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago 0 T - I 01 and T-I 02 have been implemented T-I02 has directed inerting/purging the Drywell Suppression Pool level is 24 Feet 0 Drywell pressure is 2 psig The following containment parameters exists:

0 DW Ha is 5% and increasing 0 DW 0 2 is 4% and increasing SP HZis 3% and increasing 0 SP 0 2 is 2% and increasing WHICH ONE of the following identifies the preferred method of Drywell inerting/purging, if any?

A. Drywell purge with air.

B. Drywell inerting with nitrogen (Low Flow Mode).

C. Drywell inerting with nitrogen (High Flow Mode).

D. Drywell purging is not required until Drywell 0 2 exceeds 5%.

Page 186 of 200

Limerick Generatinq Station ILT05-I NRC Initial Licensing Examination Answer Key

~~ ~~ ~~

Basis or Justification Per T-228, Drywell inerting with Low Flow and High Flow are allowed given the conditions. Low Flow is the preferred flowpath per the note in section 4.3 and Table 1. per T-228 Not allowed due to high drywell pressure (>.75 psig)

Allowed but not preferred per the note in section 4.3 and Table 1 of T-228 Does not apply to the given conditions Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): T-228 section 4.3, 4.5 and 4.6 Learning LLOTI561-03 0bjective:

Knowledge/Ability 2.3.9 Importance: RO I SRO K/A 2.5 13.4 Required Materials:

T-228 Assessment Table, and section first pages Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

__

Limerick Generatina Station ILT05-I NRC Initial Licensinq Examination

94. Unit 1 plant conditions are as follows:

0 35%power 0 Control rod scram time testing is in progress per ST-6-107-790-1 0 All Unit 1 control rods are OPERABLE 0 Control rod 30-31 is withdrawn from position 12 to position 48 to support scram time testing The following sequence of events occur:

13:OO:OO - Control rod HCU toggle switches Aand B for Rod 30-31 are taken to TEST and then immediately back to NORMAL 13:00:08 - Control rod 30-31 is at Position 1.88 05 a

WHICH ONE of the following describes the required action?

A. Restore Control Rod 30-31 to position 12.

B. Disarm HCU 30-31 Directional Control Valves.

C. Demonstrate insertion capability and restore Control Rod 30-31 to position 12.

D. Demonstrate insertion capability and restore Control Rod 30-31 to position 48.

Page 188 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key

?a Question ID# 094 SRO Or Choice Basis or Justification C T.S 3.1.3.2 determines that 30-31 is INOP due to Scram time exceeding

.. 7 seconds. T.S. 3.1.3.1 Action b.1 J .

Incorrect: A 30-31 is not OPERABLE, therefore it cannot just be regored to position 12.

B The rod is INOP, Incorrect ID While 30-31 must have insertion capability demonstrated, its original position is 12, not 48.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 3.0 3 N Y (b)(10) y (b)(2)

Source Documentation Source: New Exam Item Previous NRC Exam 0Modified Bank Item Other Exam Bank ILT Exam Bank Reference(s): TS 3.1.3.2 AND 3.1.3.1 Learning LLOT0060.12 0bjective:

Knowledge/Ability 201002 2.1.32 Importance: RO ISRO WA 3.4 13.8 (Description of K&A, from catalog)

Ability to explain and apply system limits and precautions.

Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

95. The CRS directed a manual scram on Unit 2 from 100% power due to a stuck open SRV.

The scram was unsuccessful and RRCS was manually initiated.

Immediately after RRCS initiation, reactor power dropped to I.2% on all APRMs.

Currently, Unit 2 plant conditions are as follows:

0 All APRMs indicate 1.2%

0 All IRMs are on Range 6 and stable 0 All SRM count rates are 55,000 cps and stable 0 ALL blue SCRAM lights are lit on the Full Core Display 0 Suppression Pool temperature is 108F and rising WHICH ONE of the following describes the correct mitigation strategy for control rod insertion and SLC?

Control Rods SLC A. Perform T-217 and T-218 Do NOT inject SLC B. Perform T-217 and T-218 Manually inject SLC C. Perform T-213, T-215, T-216, Do NOT inject SLC and T-219 D. Perform T-213, T-215, T-216, Manually inject SLC and T-219 Page 190 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensinq Examination Answer Key Question ID# 095 SRO Or I Choice Basis or Justification 1 Correct: B The Blue scram lights lit indicate that Scram solenoid valves are open, which requires 1-217 and T-218. The given conditions indicate that the reactor is not shutdown, therefore, before Suppression Pool Temperature reaches 1IOOF, SLC injection is required per T-101.

I Incorrect: A While T-217 and T-218 are required, T-I01 requires SLC injection.

Incorrect C T-213, T-215, T-216, and T-219 are not required because the scram valves are open. In addition, T-101 requires SLC injection.

Incorrect D While SLC injection is required per T-101; T-213, T-215, T-216, and T-219 are not required because the scram valves are open.

Psychometrics Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 5 High 3.5 4 Y b 10 Y b 5 Source Documentation 1 Source: 0New Exam Item Previous NRC Exam I

Modified Bank Item Other Exam Bank 0ILT Exam Bank T-I 01 Learning LLOTI560.06 0bjective:

I Knowledge/Ability 2.4.6 WA (Description of K&A, from catalog)

Importance: RO / SRO 3.1 /4.0 Knowledge of symptom based EOP mitigation strategies.

~~ ~~

Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

96. WHICH ONE of the following identifies Work Execution Centerwork Control Center Supervisor (WCS) staffing requirements per OP-AA-I 01-11Iand OP-LG-101-111?

A. WCS may be credited as Shift Technical Advisor and Incident Assessor simultaneously.

B. WCS may be credited as Incident Assessor and NRC Communicator simultaneously.

C. If the WCS is credited as Shift Technical Advisor then Incident Assessor function is NOT required.

D. If the WCS is credited as Incident Assessor then Shift Technical Advisor function is NOT required.

Page 192 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination

~~

Answer Key Question ID# 096 SRO Or i I Choice Basis or Justification 1

~ ~~ ~

Correct: C If WCS is STA then IA function is not required (OP-AA-101-1I1, 4.5.2) 1 Incorrect: A

~

WCS cannot be both STA and IA (OP-LG-I 01-111, Attachment 3)

I

~~

I Incorrect B WCS cannot be both IA and NRC Communicator (OP-LG-101-11I, Attachment 3)

I Incorrect D If WCS is the IA, they support the STA function, the STA is stili required Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.0 3 N N Y (b)(2)

Source Documentation Source: New Exam item 0Previous NRC Exam 0Modified Bank item 0Other Exam Bank 0ILT Exam Bank Reference(s): OP-AA-101-11 I,page 5, step 4.5 OP-LG-101-111, page 11 #3 Learning LLOTI 574.01a 0bjective:

Knowledge/Abiiity 2.1.4 importance: RO / SRO KIA 2.3 f 3.4 (Description of K&A, from catalog)

Knowledge of Shift Staffing requirements Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

- __ - ~~

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination

97. The AChlorine detector fails upscale.

Subsequently, a loss of Div 3 DC power occurs.

WHICH ONE of the following describes the status of the A CREFAS Fan and the procedure entered?

ACREFAS Fan Procedure A. Running S78.0.B Verification of MCR HVAC Isolation Signal B. Not Running S78.0.B Verification of MCR HVAC Isolation Signal C. Running S78.8.A Manual Initiation of MCR HVAC Isolation D. Not Running S78.8.A Manual Initiation of MCR HVAC Isolation Page 194 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Key Question ID# 097 SRO Or I I Choice Basis or Justification 1 Correct: A The A Chlorine detector causes a partial chlorine isolation. The Loss of Div 3 DC completes the isolation and causes the A CREFAS Fan to start due to de-energizing the trip logic. Therefore, a manual isolation is not required and only verification of the existing isolation.

Incorrect: B The procedure reference is correct, however the A CREFAS is running.

~~~

Incorrect C The fan status is correct, however manual isolation is not required and only verification of the existing isolation.

Incorrect D The A CREFAS is running and manual isolation is not required and only verification of the existing isolation.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 N N Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): E-IFC, SE-2 Learning LLOT0450.03,07 0bjective:

Knowledge/Ability 290003 Importance: RO / SRO WA A2.01 3.1 13.2 (Description of K&A, from catalog)

Ability to predict the impact of the following on the Control Room HVAC, and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiationheconfiguration Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILT05-1 NRC Initial Licensinq Examination

98. WHICH ONE of the following procedure revisions requires a Station Qualified Reviewer (SQR) review per AD-AA-101 and AD-AA-102?

A. Changes to references in a Surveillance Test.

B. Editorial changes to an Operation's T&RM.

C. Addition of clarifying information in the form of a list of required tools in a systems procedure.

D. Changes to activities in an Off-Normal Procedure.

Page 196 of 200

Limerick Generating Station ILT05-1 NRC Initial Licensing Examination Answer Key i

Choice Basis or Justification Correct:

Incorrect:

II DA Changes to activities in a procedure requires a SQR review Changes to reference are excluded from requiring SQR review Incorrect IB Editorial change are excluded from requiring SQR review Incorrect IC Addition of clarifying information is excluded from requiring SQR review Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 Low 2.5 4 N N Y (b)(3)

Source Documentation Source: 0New Exam Item c]Previous NRC Exam Modified NRC Bank Item 0Other Exam Bank extensively modified ILT exam bank item c]ILT Exam Bank Reference(s): AD-AA-101, Page 3, step 4.3.5 Learning LLOTI570.013 0bjective:

Knowledge/Ability 2.2.6 I Importance: RO / SRO WA 2.3 13.3 (Description of K&A, from catalog)

Knowledge of the process for making changes in procedures as described in the safety analysis report.

Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generat ing Station ILT05-1 NRC Initial Licensing Examination

99. Fuel is being loaded into the core on Unit 1 with the following conditions:

0 I A SRM count rate is 3.5 cps and has a signal-to-noise ratio of 2.0 0 1B SRM was declared inoperable last shift due to spiking 0 IC SRM count rate is 2.0 cps and has a signal-to-noise ratio of I.5 0 I D SRM count rate is 2.5 cps and has a signal-to-noise ratio of 2.0 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 ID core quadrants ONLY.

Page 198 of 200

Limerick Generating Station ILTO5-I NRC Initial Licensing Examination Answer Key Question ID# 099 SRO Or Choice Basis or Justification Correct: C B and CSRMs are inoperable (ICdue to inadequate signalhoise ratio, per T.S. fig 3.3.6-1) Therefore, Fuel movement is only permitted in quadrants Aand D per T.S. 3.9.2 Incorrect: A See above Incorrect B See above Incorrect D Fuel cannot be loaded into quadrant C because its SRM is inoperable.

Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 N N (b) (7)

___

Source Documentation ~

Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): T.S. 3.9.2 and Figure 3.3.6-1 Learning LLOT0240.10 0bjective:

Knowledge/Ability 2.2.28 Importance: RO / SRO WA 2.6 / 3.5 Required Materials:

Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

Limerick Generatinq Station ILTO!%I NRC Initial Licensing Examination ATTACHMENT: GP-I2 Provided 100. Unit 1 is at 100% power when the following occurs:

At 0100, Chemistry reports the following results of a Reactor water sample:

Conductivity is 2.5 pmho/cm pH is 5.4 Chloride concentration is 0.1 +y~+ pb 0 Hotwell conductivity is -c 0.1 pmho/cm and steady The RO reports a rising trend in Main Steam Line radiation.

WHICH ONE of the following describes the required action(s)?

A. Check RWCU and Condensate Deep Bed Demin effluent conductivity to identify the source.

B. Reduce power per GP-5, Appendix 2 and sequentially remove Circulating Water system loops from service to identify the source.

C. Begin a GP-3 shutdown by 0200 and place reactor 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 />.

D. Perform an engineering evaluation to determine the effects of any out-of-limit conditions on the structural integrity of the Reactor Coolant system.

Page 200 of 200

Limerick Generatinq Station ILT05-1 NRC Initial Licensing Examination Answer Kev -

I Choice Basis or Justification Correct: A ON-I 16 directs that with Conductivity > I .O pmho/cm AND Main Steam line radiation high AND ph low, to determine if RWCU or Condensate Deep Beds are passing resin Incorrect: B This action would be correct if hot well conductivity were rising, which is not indicated

~~~

Incorrect C This action would be appropriate if GP-12 action level 3 (>5 ymhokm) were reached Incorrect D This action would be appropriate if the plant was in any OPCON other than 1,2or3 Level of Difficulty Time Allowance PRA RO SRO Knowledge (minutes) 10CFR55.41 10CFR55.43 High 3.0 4 N Y (b)(lO) Y (b)(5)

Source Documentation Source: New Exam Item 0Previous NRC Exam 0Modified Bank Item 0Other Exam Bank 0ILT Exam Bank Reference(s): GP-12, Sect 3.3, ON-I 16, T&RM 3.4.4 Learning LLOTI030.12 0bjective:

Knowledge/Ability 2.1.34 Importance: RO / SRO K/A 2.3 12.9 (Description of K&A, from catalog)

Ability to maintain primary and secondary plant chemistry within allowable limits.

Required Materials:

GP-12 Notes and Comments Prepared By:

Rick Rhode (610) 718-4085 Limerick Regulatory Exam Author

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