ML050380262
| ML050380262 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/05/2005 |
| From: | Jason White Exelon Generation Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-352/05-301, 50-353/05-301 | |
| Download: ML050380262 (200) | |
Text
Limerick Generating Station 2005 NRC Initial Licensing Examination 1
Question: 01 01 of 100 Unit 2 plant conditions are as follows:
Reactor power is 35%
The main generator is loaded on the grid The drain valve for the "AI" Moisture Separator fails closed, and the associated dump valve fails to open. Annunciator windows E-2 (AI MOISTURE SEPARATOR DRAIN TANK HI LEVEL) and E-1 (MOISTURE SEPARATOR HI LEVEL TRIP) on 206 MAIN STEAM have alarmed.
WHICH ONE of the following describes the plant response?
- c.
Both "A" and "B" RPS channels remain energized
- d.
Both "A" and "B" RPS channels de-energize
Limerick Generating Station 2005 NRC Initial Licensing Examination
\\
Question#
01 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - since both A and B RPS will de-energize Incorrect - since both A and B RPS will de-energize Incorrect - since both A and B RPS will de-energize Correct Answer - High-High level in any one moisture separator will cause the main turbine to trip. A turbine trip at greater that 30% power will result in a full scram (A and B RPS de-energize)
Required Attachments or Reference I Unit (I, 2)
( 2 I
Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: RPS Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 02 u
02 of I00 A loss of offsite power occurs and all Unit I and Unit 2 Diesel Generators cannot be started.
Unit 1 plant conditions are as follows:
All control rods fully inserted RPV level -20 inches and lowering slowly RPV pressure 680 psig and rising slowly WHICH ONE of the following describes systems available for RPV level and pressure control three minutes after the Station Blackout?
Level Control Pressure Control
- a.
HPCl SRVs
- b.
Diesel Driven Fire Pump SRVs
- c.
HPCl Main Turbine Bypass Valves
- d.
Diesel Driven Fire Pump Main Turbine Bypass Valves
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice Basis or Justification
- a.
Correct Answer - HPCI is available for level control as it does not need AC power to function. SRVs are available for pressure control as they only need Div 1 DC power to function from the MCR.
Incorrect - Diesel Driven Fire Pump is available but cannot inject to RPV unless RPV
- b.
pressure is less than 200 psig.
Incorrect - Bypass valves are not available after one minute due to loss of EHC pumps (accumulators only provide about I minute of operation after trip of the EHC pumps)
Incorrect - Bypass valves are not available after one minute due to loss of EHC pumps (accumulators only provide about 1 minute of operation after trip of the EHC pumps)
C.
- d.
Required Attachments or Reference L
Knowledge of the operational implications of the following as they apply to partial or complete loss of AC power: Station blackout Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination 03 of I00 Question: 03 Unit I plant conditions are as follows:
u Drywell Pressure 2.0 psig rising slowly Drywell Temperature 150 O F rising slowly Rx Shut down per GP 4 Rapid Plant Shutdown to Hot Standby 1A Drywell Chiller in service I A and 1 B Chilled Water Pumps running 8 Drywell fans are running All automatic actions occur as designed No other operator actions performed.
WHICH ONE of the following actions is to lower Drywell Temperature for the conditions above?
- a.
- b.
C.
- d.
i/
Reset DWCW Isolations per GP 8.3, ISOLATION RESETS Bypass DWCW Isolations per GP 8.5, ISOLATION BYPASS OF CRUCIAL SYSTEMS Start 1 B Chiller per S87.1.A, STARTUP OF DRYWELL CHILLED WATER SYSTEM ray in service per T-225, STARTUP AND SHUTDOWN OF POOL AND DRYWELL SPRAY
Limerick Generating Station 2005 NRC initial Licensing Examination Choice
- a.
- b.
C.
- d.
I Question#
03 Basis or Justification Incorrect - DWCW Isolation can not be reset with Drywell pressure greater than I
.68 Correct Answer - 1.68 psig isolates Drywell chill water to drywell. Must Bypass isolations per GP 8.5 per T-I 02 Incorrect -The definition for T-102 "Maximize Drywell Cooling" requires only one Drywell Chiller in service Psig Incorrect - Drywell Spray is not permissible with the given Drywell parameters T-I 02 Required Attachments or Reference I
(Description of K&A, from catalog)
Ability to operate andlor monitor the following as they apply to HIGH DRWELL TEMPERATURE: Drywell cooling system Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 04 Unit 2 plant conditions are as follows:
b 04 of I00 100% reactor power RHR is aligned normally An inadvertent Division 1 LOCA signal is generated by an instrument line failure. No actions are taken by MCR Operators.
WHICH ONE of the following describes the position of the "2A" RHR pump "MINIMUM FLOW VALVE", HV-51-2F007A and "HEAT EXCHANGER BYPASS VALVE", HV-51-2F048A five (5) minutes later?
HV-51-2F007A position HV-51-2F048A position
- a.
Open Open i,
- b.
Open Closed
- c.
Closed Open
- d.
Closed Closed
Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
04 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - HV-51-2F007A is normally open when RPV pressure is greater than 75 psig, with its handswitch in AUTO. The valve will only close if RHR flow is greater than 1300 gpm. The LOCA signal will start the "2A" RHR pump, but no other valves will open to allow flow to exceed 1300 gpm at the flow switch controlling HV-51-2F007A, therefore, the valve will remain open to provide minimum flow protection for the pump. HV-51-2F048A will receive an open signal for three minutes from the LOCA signal, and will not automatically close at the end of that three minutes.
Therefore, with no operator action, both valves will be open at the end of five minutes.
Incorrect - See justification for a.
Incorrect - See justification for a.
Incorrect - See justification for a.
L Attachments or ECTION MODE design feature(s) and/or interlocks which provide Prepared by: Craig Fritz L
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 05 L
ATTACHMENT Q05 IS PROVIDED 05 of 100 Unit 1 plant conditions are as follows:
Inadvertent RClC initiation has occurred OT-I04 actions have been performed Reactor power is 99%
demanded (see attached P-I)
RClC has been shutdown WHICH ONE of the following, for the attached P-I, is a condition that requires reporting to the CRS?
- a. AGAFneed
- b. Exceeding
- c.
A thermal li
- d. Control rod
i, Cognitive (H, L)
Unit (1. 2)
Limerick Generating Station 2005 NRC Initial Licensing Examination L
PRA (Y/N)
SRO I
N N
Question#
05 Source:
Learning Reference(s):
Choice New Exam Item LLOT0740.2 T.S. GP-I4
- a.
Objective:
Knowledge/Ability:
- b.
G.2.1.I9 I Importance: 3.0/3.0 C.
- d.
Basis or Justification Incorrect -AGAF are all reading 0.999. They do not need adjustment unless they are outside 0.98 - 1.02 Incorrect - Thermal power is not exceeded on Unit 1 unless above 3440 MW thermal per GP-5.
Correct Answer - MAPRAT is being exceeded at location 45-16.
Incorrect - Control rod 38-31 is in the same position as its symmetric rods.
P I print out Req u ired Attachments or Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 06 L
06 of 100 Unit I plant conditions are as follows:
RPV level is -140 inches and lowering slowly RPV pressure is 490 psig and lowering slowly Drywell pressure is 20 psig and rising slowly All low pressure ECCS pumps are running A LOCA signal was generated five (5) minutes ago Auto ADS has NOT been inhibited The ADS Auto Inhibit switches have just been place to INHIBIT. No operator actions have been taken.
WHICH ONE of the following describes the status of the Safety Relief Valves (SRVs)?
- a. A, C, and N SRVs are open, all others are closed
- b.
E, H, K, M, S SRVs are open, all others are closed
- d.
E, H, K, M, S SRVs have opened, now all SRVs are closed u
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference( s):
Learning 0 biective:
b Question#
06 New Exam Item T-1 I 2 Bases LLOT0330.5 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - C, A, and N SRVs are the SRVs that can be operated from the Remote Shutdown Panel, but they will not open automatically.
Correct Answer - These are the 5 ADS valves, and they will open automatically based on the given conditions.
Incorrect - Cy A, and N SRVs are the SRVs that can be operated from the Remote Shutdown Panel, but they will not open automatically.
Incorrect - - These are the 5 ADS valves that will open automatically, but will not close at 490 psig.
Required Attachments or Reference I
Knowledge/Ability: I 239002 K1.08 I Importance: 4.0/4.1 (Description of K&A, from catalog)
Knowledge of the physical connections and/or cause-effect relationships between RELIEFISAFETY VALVES and the following: Automatic depressurization system Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 07 L
Unit 1 plant conditions are as follows:
07 of I00 ATWS in progress Squib valves fail to fire An Equipment Operator is directed to perform T-212, Bypassing Squib Valves For Injection.
WHICH ONE of the following describes the T-200 Locker location and what is required to verify proper revision for the conditions above?
T-200 Locker Location Revision Verification
- a.
- b.
- c.
osc
- d.
FOF Must verify revision number in PlMS Must verify red Controlled Copy stamped Must verify red Controlled Copy stamped Must verify revision number in PlMS
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Knowledge/Abiiity:
Reference( s):
Question#
07 New Exam Item LLOTI 570 5 Generic 2.1.21 1 Importance: 3.1/3.2 HU-AA-104-101, RM-AA-102 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see c justification Incorrect - see c justification Correct Answer - T-200 locker is in RP field office and all procedures in locker are kept current and red stamped by records management.
Incorrect - see c justification Required Attachments or Reference I
I I
Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 08 08 of 100 L
Unit I plant conditions are as follows:
OPCON 3 HPCl operating for RPV level and pressure control Suppression Pool level is reported to be 20 feet and lowering.
WHICH ONE of the following identifies the Suppression Pool level at which HPCI must be secured and the reason it must be secured?
Suppression Pool Level
- a.
13.5ft.
- b.
13.5ft.
- c.
18ft.
- d.
18ft.
Reason Prevent exceeding NPSH and vortex limits Prevent containment pressurization Prevent exceeding NPSH. and vortex limits Prevent containment pressurization
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
L PRA (Y/N)
SRO 1
Y N
I Choice Source:
Reference(s):
Learning P
New Exam Item T-102, Trip Bases LLOT1560.5 Basis or Justification Objective:
Knowledge/Ability:
Incorrect (see explanation for "d")
295030 EK3.02 I Importance: 3.5/3.7 Incorrect (see explanation for "d")
Incorrect (see explanation for "d")
Correct Answer. T-I 02, step SP/L-4 requires HPCl secured if suppression pool level cannot be maintained above 18 ft. T-102 Bases explains that it is to prevent direct pressurization of the suppression pool by the HPCl exhaust.
Required Attachments or Reference T-I 02 Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 09 L
09 of 100 Unit 1 is operating at 100% reactor power with RPV level at +35 inches and steady.
A Unit 1 feedwater level control malfunction causes RPV water level to lower and stabilize at +5 inches with the following plant response:
RPS "SCRAM STATUS" lights AI, A2, A3, and A4 are lit on 1 OC603 panel.
RPS "SCRAM STATUS" lights 61, 82, B3, and 84 are NOT lit on 10C603 panel.
WHICH ONE of the following describes the status of Unit I RPS?
- a. Only "A" RPS is de-energized
- b.
Only "B" RPS is de-energized
- c.
"A" and "B" RPS are de-energized
- d.
Neither "A" nor "B" RPS are de-energized
Limerick Generating Station 2005 NRC initial Licensing Examination u
Basis or Justification Choice I=
incorrect - See justification for b.
Correct Answer - with "A" RPS lights still lit, "A" RPS has failed to de-energize.
Therefore, only "B" RPS had de-energized Incorrect - See justification for b.
incorrect - See justification for b.
Required Attachments or Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 10 L
Unit 2 plant conditions are as follows:
10 of 100 100% reactor power "OB" MCR Chiller is in service D24 Diesel Generator in service for monthly run "2A" RHR Pump running in Suppression Pool Cooling Mode
" A Recirc line ruptures which results in reactor level dropping to -1 50".
WHICH ONE of the following identifies an effect of reactor level dropping below the "Level t" reactor level setpoint?
- a. "2A RHR Pump trips and restarts in 5 seconds
- b.
"2B" Core Spray Pump auto starts in I O seconds
- c.
Control Enclosure Cooling will be lost for 167 seconds
- d.
Cooling water for D24 Diesel Generator will be lost for 53 seconds
c Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
10 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect. -.Although "2A" RHR Pump does not auto start until 5 seconds after a LOCA signal, the pump will not trip a LOCA signal.
Incorrect. - "2B" Core Spray Pump will start 15 seconds following a LOCA signal.
Incorrect. - The MCR Chillers will only load shed on a Unit I LOCA signal since they are powered from Unit 1 4 KV power.
Correct Answer - Any time a Diesel starts, the associated ESW Pump will run.
However, due to load shedding on a LOCA, all ESW Pumps will trip and restart 53 seconds later. The Diesel will continue to run without cooling since ESW is the only supply of cooling water for the diesels.
I Required Attachments or Reference Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 11 I 1 of I00 L
D22 DG has just been synchronized with the I01 Safeguard Bus resulting in the following generator indications:
60.0 HZ 200 Kw 200 WAR 4280 KV WHICH ONE of the following actions are required in accordance with S92.1.O, LOCAL AND REMOTE MANUAL STARTUP OF A DIESEL GENERATOR, to restore generator parameters within acceptable limits and the reason for this action?
Required Action Reason for Action
- a.
- b.
C.
L
- d.
Lower reactive load using Voltage Regulator control Lower reactive load using Speed Governor control prevent generator overvoltage prevent generator winding overheating Raise real load using Voltage Regulator control Raise real load using Speed Governor control prevent generator overvoltage prevent generator winding overheating
Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
11 Choice Basis or Justification
- a.
Incorrect - action is to prevent generator winding overheating Incorrect - Voltage Regulator control is used to control reactive load
- b.
I c*
I Incorrect - Speed Governor is used to control real load 1 d.
I Correct Answer Required Attachments or Reference I
I I
Objective:
Knowledge/Ability: 264000 A2.04 1 Importance: 2.9/3.0 (Description of K&A, from catalog)
Ability to predict the imp predictions, use proced conditions or operations:
Consequences of operating undedover excited of the following on Emergency Generators and, based on those to correct, control or mitigate the consequences of those abnormaf Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 12 12 of 100 u Unit 2 plant conditions are as follows:
100% power Both reactor recirculation pumps are running at 80% speed The "2B" Reactor Feedwater Pump trips, and RPV level lowers to +25 inches.
WHICH ONE of the following describes the plant response, and the reason for this response?
Plant Response Reason for Response
- a.
Both reactor recirculation pumps will runback to 28% speed reduces power to restore level by reducing steam load
- b.
Both reactor recirculation pumps will runback to 42% speed reduces power to restore level by reducing steam load
- c.
Both reactor recirculation pumps reduces power to ensure adequate will runback to 28% speed NPSH to recirculation pumps L
- d.
Both reactor recirculation pumps reduces power to ensure adequate will runback to 42% speed NPSH to recirculation pumps
Source:
Reference( s):
Learning Objective:
Knowledge/Ability:
Limerick Generating Station 2005 NRC Initial Licensing Examination New Exam Item LLOT0040.03 295009 AK3.01 I Importance: 3.2/3.3 Basis or Justification Incorrect - See explanation for b.
Correct Answer - With any individual RFP flow less than 18.8%, and RPV level less than 27.5 inches, both recirc pumps will run back to 42% speed. This is for the purpose of reducing power to reduce steam flow to help turn RPV level.
Incorrect - See explanation for b.
Incorrect - See explanation for b.
Required Attachments or Reference
Limerick Generatina Station 2005 NRC Initial Licensing Examination Question: I 3 L
13 of 100 Unit 2 plant conditions are as follows:
Reactor startup is in progress with reactor power at 1 I
% and all prerequisites are met to go to OPCON I Reactor Mode Switch is in "STARTUP/HOT STANDBY" "2B" IRM is inoperable and is bypassed using the joystick on 20C603 The 2D IRM fails upscale.
WHICH ONE of the following conditions will permit the startup to continue?
- a. "2D" IRM is bypassed by placing the Reactor Mode Switch in "RUN"
- b.
"2D" IRM is bypassed using the joystick on 20C603
- c.
"2D" IRM drawer mode switch is placed to "TEST"
- d.
"20" IRM is fully withdrawn
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
Basis or Justification Correct Answer. - Placing the Reactor Mode Switch in RUN will bypass all SRM and IRM trips and rod blocks.
Incorrect - only one IRM on the "B" side (B, D, F, or H) can be bypassed at one time.
Therefore, if D is bypassed, B cannot be bypassed, and will result in a rod withdraw C.
I will provide a rod withdraw block.
block.
Incorrect - If the drawer mode switch is placed to TEST, it is out of OPERATE. This
- d.
Required Attachments or Reference Incorrect - Fully withdrawing the IRM will not bypass the IRM rod withdraw block I
I I
Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 14 14 of I00 A unit 2 plant startup is in progress per GP-2 with the following conditions:
ii Reactor Mode Switch in STARTUP All lRMs on range I O APRM#I 13.2%
APRM#2 12.3%
APRM#3 11.5%
APRMM 11.8%
WHICH ONE of the following describes the status of RPS and RDCS for the conditions above?
Status of RPS Status of RDCS
- a.
- b.
- c.
No Scram
- d.
No Scram No rod block Withdraw rod block No rod block Withdraw rod block
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice-
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See Id justification Incorrect - See d justification Incorrect - See d justification Correct Answer -Withdrawal Rod block only generated at 12%-I 3% Rx power with mode switch not in Run for at least I APRM in trip. Rx scram at 15%-20% with mode switch not in Run for at least 2 APRMs in trip.
Required Attachments or Reference I
Knowledge/Ability: I 21 5005 A I.04 I Importance: 4.1/4.1 (Description of K&A, from catalog)
Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONITOWLOCAL POWER RANGE MONITOR SYSTEM controls including: SCRAM and rod block trip setpoints Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: I 5 L
15 of 100 Unit 2 plant conditions are as follows:
"2A" Reactor Recirculation pump has tripped The CRS has entered the procedure for loss of a Reactor Recirculation Pump The RO is manually inserting control rods using the "INSERT" pushbutton to reduce power MCR annunciator 108 REACTOR window F-4 "ROD DRIFT" has alarmed.
WHICH ONE of the following describes the cause of this alarm and whether it is a normal or an abnormal condition?
- a.
- b.
C.
- d.
Cause of the Alarm Any odd reed switch closed with no rod motion signal Any even reed switch closed with no rod motion signal Any odd reed switch closed with no rod motion signal Any even reed switch closed with no rod motion signal Normal or Abnormal Normal Normal Abnormal Abnormal
Limerick Generating Station 2005
- - " NRC
- c.
Initial Licensing Examination I.
Choice
- a.
- b.
C.
- d.
I Basis or Justification Incorrect - It is not expected to get this alarm when using the NOTCH INSERT pushbutton. This alarm would not be abnormal if using the CONTINUOUS INSERT push button.
Incorrect - Only an odd reed switch made up with no rod motion signal will cause a rod drift alarm. It is not expected to get this alarm when using the NOTCH INSERT pushbutton. This alarm would not be abnormal if using the CONTINUOUS INSERT pushbutton.
Correct Answer - A rod drift alarm occurs when an odd reed switch is closed with no rod motion signal. It is unexpected to get this alarm when using the NOTCH INSERT push button.
Incorrect - Only an odd reed switch made up with no rod motion signal will cause a rod drift alarm.
Source:
Reference( s) :
Learning Objective:
Knowledge/Ability:
Required Attachments or Reference New Exam Item MCR ARC 108 REACTOR, window F-4 LLOT0080.04 201 002 K4.03 I Importance: 3.6/3.6 Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 16 L
16 of 100 Unit 1 Division 1 DC power is lost due to an electrical fault.
WHICH ONE of the following activities CANNOT be performed?
- a.
- b. Manually initiate RClC
- c.
- d. Start "OA" Control Enclosure chiller
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference (s):
Learning Objective:
Knowledge/Ability:
Question#
16 New Exam Item LLOT0380.12 21 7000 K2.02 I Importance: 2.8/2.9 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - 1A CRD pump is powered from D13, and does not use Division 1 DC power.
Correct Answer - RClC cannot be started without Division I DC power to the governor circuit.
Incorrect - While each of the five ADS valves have a solenoid powered by Division 1 DC, ADS can still be initiated from the MCR using Division 3 DC, and the Division 3 arm and depress pushbuttons.
Incorrect - OA Control Enclosure Chiller control power is from Division 3 DC, and is not affected by a loss of Division 1 DC.
Required Attachments or Reference
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 17 L
17 of 100 Unit 1 plant conditions are as follows:
An automatic reactor scram has just occurred from 100% power due to high Both RPS channels (A and B) have de-energized, and all rods fully inserted All feedwater level components are in "AUTO" mode All feedwater instrumentation is functioning properly FWLC is in single element control with three element control available drywell pressure WHICH ONE of the following describes the RPV level response during the first 10 seconds after the scram, and the reason for this response?
- a.
- b.
C.
- d.
u RPV level will initially rise due to Scram Profile activation and core void change RPV level will initially rise due to Scram Profile NOT activating and more core inlet subcooling RPV level will initially lower due to Scram Profile activation and core void change RPV level will initially lower due to Scram Profile NOT activating and more core inlet subcooling
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
Question #
17 I
Basis or Justification Incorrect - RPV level will not rise, as core void collapse will result in water from the downcomer region going into the core region to make up for the reduction in volume Source:
Reference( s):
Learning 0 bjective:
Knowledge/Ability:
- b.
New Exam Item S06.1.D LLOR0401 B.06 295006 AK3.01 I Importance: 3.8/3.9 C.
- d.
of the steam.
Incorrect - RPV level will not rise, as core void collapse will result in water from the downcomer region going into the core region to make up for the reduction in volume of the steam. Scram Profile will activate since both RPS channels de-energized.
Correct Answer - RPV level lowers due to void collapse and Scram Profile activation, which will reduce feedwater flow after the first 5 seconds after both RPS channels de-e n erg ize.
Incorrect - Scram Profile will activate since both RPS channels de-energized, and the level reduction results from core voids collapsing, requiring water from the downcomer to redace the lost volume of the steam voids in the core.
Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 18 i,
Unit 2 plant conditions are as follows:
18 of 100 An ATWS is in progress with reactor power 40%
RPV pressure is being maintained 990-1096 psig with SRVs Suppression Pool temperature 109°F and rising Suppression Pool water level 26 feet and steady Suppression Pool pressure 2.8 psig and rising slowly Drywell pressure 2.3 psig and rising slowly Main turbine is tripped The CRS directs initiation of SLC.
WHICH ONE of the following describes the reason for this action?
- a.
- b.
- c.
Prevent exceeding SRV Tailpipe Level Limit Prevent exceeding Primary Containment Pressure Limit Prevent exceeding Pressure Suppression Pressure Limit
- d.
Prevent exceeding Suppression Pool Heat Capacity Temperature Limit
Limerick Generating Station 2005 NRC initial Licensing Examination Source:
Learning Objective:
Knowledge/Ability:
Reference (s):
Question#
18 I
New Exam Item LLOTI 560.5 29501 3.K3.02 I Importance: 3.6/3.8 T-101, T-I02 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see Id justification Incorrect - see d justification Incorrect - see d justification Correct Answer - Per T-I 01 injecting SLC before Suppression Pool temperature reaches 110 degrees F is desirable to prevent exceeding the Heat Capacity Temperature Limit.
Required Attachments or Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 19 19 of 100 Unit 2 plant conditions are as follows:
OPCON 5 with Reactor Level 495 inches "28" RHR loop is operating in Shutdown Cooling mode Normal 4KV Bus lineup The 101 Safeguard Transformer Breaker trips and ALL automatic actions occur as designed.
No operator action has been taken.
WHICH ONE of the following identifies the status of the "2B" RHR Pump and the "B RHR Shutdown Clg Injection PCW" (OUTBOARD), HV-51-2FOl5B, two (2) minutes following the trip of the I01 Safeguard Transformer Breaker?
- a.
- b.
C.
L,
- d.
"2B" RHR Pump Tripped Tripped Running Running HV-51-2F015B Closed Open Closed Open
Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
19 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect -With "B loop of Shutdown Cooling in service, HV-51-2FOl5B will be open.
Since the valve does not receive an isolation signal on a loss of the 101 Safeguard Bus, the valve will remain open.
Correct Answer - "2B" RHR Pump will trip on undervoltage due to temporary loss of power to D22 which is normally powered from the I01 Safeguard Bus. The "2B" RHR Pump will not auto restart. HV-51-2F015B will remain open since there is no isolation signal for the valve.
Incorrect - See "b" Incorrect - See "b" Required Attachments or Reference (Description of K&A, from catalog)
Knowledge of the effect that a loss or malfunction of the following will have on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): A.C. electrical power.
Prepared by: Lee Stanford
Limerick Generatinu Station 2005 NRC Initial Licensinu Examination Question: 20 Unit 1 plant conditions are as follows:
L 20 of I00
- 2 APRM has an INOP trip condition All other APRMs are functioning normally WHICH ONE of the following describes the effect of the APRM failure on the "IA" and "I B" Rod Block Monitor (RBM)?
Effect on "1A RBM Effect on Ill B" RBM
- a.
Noeffect First alternate APRM lost
- b.
First alternate APRM lost First alternate APRM lost
- c.
Noeffect Primary reference APRM lost
- d.
First alternate APRM lost Primary reference APRM lost
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
20 Choice
- a.
- b.
C.
- d.
~~
Basis or Justification Incorrect - see justification for c.
Incorrect - see justification for c.
Correct Answer - #2 APRM is the primary reference APRM for the "1 B" RBM channel. It is not used at all by the "IA" RBM.
Incorrect - see justification for c.
Required Attachments or Reference (Description of K&A, from catalog)
Knowledge of the operational implications of the following concepts as they apply to ROD BLOCK MONITOR: TriD reference selection Prepared by: Craig Fritz
Limerick Generating Station 2006 NRC Initial Licensing Examination Question: 21 Unit I plant conditions are as follows:
L 21 of 100 100% power Division 3 DC bus de-energized due to ground fault "1A CRD Pump is in service No ECCS pumps are in service A LOCA occurs which results in reactor level lowering to -1 50". No operator action has been taken other than normal scram actions.
WHICH ONE of the following pumps will be running following the LOCA?
- a.
"1A"CRD
- c.
"OA" RHRSW
- d. "1 C" Core Spray
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Knowledge/Ability:
Reference(s):
Question#
21 I
New Exam Item LLOT0690.6b 295004 AK2.03 I Importance: 3.3/3.3 E-I FC Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - If I A CRD Pump is running prior to LOCA signal, breaker cannot trip on LOCA signal due to breaker control power unavailable.
Incorrect - "IC" RHR Pump logic and breaker control power unavailable due to loss of Div. 3 DC.
Incorrect - "OR' RHRSW Pump breaker control power is from Div. 1 DC. Pump breaker will trip on LOCA and does not auto restart.
Incorrect - 'I1 C" Core Spray Pump logic and breaker control power unavailable due to loss of Div. 3 DC.
Required Attachments or Reference Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 22 L
22 of I00 Unit 1 plant conditions are as follows:
Afire has occurred in the MCR The MCR has been abandoned All appropriate actions have been taken in SE-1, "Remote Shutdown" RPV pressure has been reduced to 50 psig RPV level at the Remote Shutdown Panel indicates +40 inches WHICH ONE of the following describes the available level instrumentation at the Remote Shutdown Panel, and whether the instrument indicates higher or lower than actual level in the given condition?
- a.
Wide Range; indicates higher than actual level
- b.
Wide Range; indicates lower than actual level
- c.
- d.
Shutdown Range; indicates higher than actual level Shutdown Range; indicates lower than actual level
Limerick Generatina Station 2005 NRC Initial Licensina Examination Choice
- a.
- b.
C.
- d.
Required Attachments or Reference Basis or Justification Correct Answer - Only Wide Range is available at 1 OC201, and per SE-1 caution above step 4.8.1, it will read higher than actual during cooldown.
Incorrect - See justification for a.
Incorrect - See justification for a.
Incorrect - See justification for a.
Source:
Learning Objective:
Knowledge/Ability:
Reference(s):
New Exam Item LLOT0050.03 29501 6 AA2.02 I Importance: 4.2l4.3 SE-I
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 23 Unit 2 plant conditions are as follows:
L 23 of 100 100% power "2A" RECW pump is running with its handswitch in ttAUTO" "2B" RECW pump is not running with its handswitch in "AUTO" WHICH ONE of the following conditions will result in the auto start of the "2B" RECW pump?
- a.
RECWpump ction pressure is 16 psig
- b.. RECW heat exchanger outlet pressure is 112 psig
- c..RECW heat exchanger inlet temperature is 118 deg. F
- d.
RECW heat exchanger outlet temperature is 124 deg. F
Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
23 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for b.
Correct Answer - The only condition that will cause an auto start of an RECW pump is low RECW heat exchanger outlet pressure of 118.6 psig with no LOCA signal present and the handswitch in AUTO. Therefore, "b" is correct since it provides an outlet pressure of 112 psig.
Incorrect - See justification for b.
Incorrect - See justification for b..
Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 24 24 of I00 Unit 1 is at 100% reactor power L
LISL-42-1 N680C, "Reactor Level 3 Level Switch" has failed downscale, causing the following alarm:
107 REACTOR, H-I, "REACTOR WATER BELOW LEVEL 3 TRIP" WHICH ONE of the following identifies the indication of the Scram Status lights and the position of the Scram Discharge Volume Vent and Drain Valves?
Scram Status Lights SDV Vent and Drain Valve Positions One Vent and One Drain Valve Closed
- a.
"A" Status Lights out
- b.
"A" Status Lights out
- c.
"B" Status Lights out No Vent or Drain Valves Closed One Vent and One Drain Valve Closed
- d.
"B" Status Lights out No Vent or Drain Valves Closed L
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (I, 2)
I Question #
24 H
PRA (Y/N)
SRO 1
N N
Basis or Justification Incorrect - See "b" Correct Answer - The "C" Reactor Level trip unit failing downscale should provide a half scram on the "A" side which should extinguish the "A" RPS Scram Status lights.
The Scram Discharge Volume Vent and Drains will only reposition on a full scram signal.
Incorrect - See "b" Incorrect - See "b" entati Source:
New Exam Item Learning LLOT0300.3,7 Reference( s):
ARC-MCR-107 H-1, OT-117 Objective:
Knowledge/Ability: 21 2000 A3.04 I Importance: 3.9/3.8 (Description of K&A, from catalog)
Ability to monitor automatic operation of the REACTOR PROTECTION SYSTEM including:
System status lights and alarms.
Prepared by: Lee Stanford
Limerick Generatinu Station 2005 NRC Initial Licensing Examination Question: 25 25 of I00 L,
Unit 2 plant conditions are as follows:
An ATWS is in progress, with power at 20% and stable The RRCS Manual Initiation pushbuttons have been armed and depressed Three minutes later, power is still at 20%
All RRCS functions have occurred, except the "2B SBLC pump failed to start WHICH ONE of the following describes the status of the RWCU isolation valves?
HV-44-2F001 (INBOARD)
HV-44-2F004 (OUTBOARD)
- a.
Open Open
- b.
Open Closed
- c.
Closed
- d.
Closed Open Closed
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
Question#
25 Basis or Justification Incorrect - See justification for d.
- b.
C.
- d.
Incorrect - See justification ford.
Incorrect - See justification for d.
Correct Answer - RRCS will initiate an isolation of both the inboard and outboard RWCU isolation valves if RRCS pushbuttons are armed and depressed, power is above 3.2% (APRMs not downscale), and 118 second time delay times out. Both valves will receive an isolation signal directly from the RRCS logic, and it does not matter if the SBLC pumps actually start or not.
Required Attachments or Reference Source:
Reference(s):
Learning New Exam Item GE Elementary Drawing G31-1020 LLOT0315.03 Objective:
Knowledge/Ability: 204000 K6.07 I Importance: 3.3B.5
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 26 L
MCR HVAC alignment is as follows:
"OA" CREFAS fan is operating due to a radiation isolation "OA" CREFAS fan control switch is in AUTO "OB" CREFAS fan control switch is in STBY A valid chlorine isolation signal has just been generated.
WHICH ONE of the following describes the response of the CREFAS system?
- a.
"OB" CREFAS fan starts immediately
- b. "OB" CREFAS fan starts in 30 seconds
- c.
" O K CREFAS fan trips, then restarts immediately
- d. "OK CREFAS fan trips, then restarts in 30 seconds 26 of 100
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference (s):
Learning Objective:
Knowledge/Ability:
Question#
26 New Exam Item LLOT0450, Objective 04 290003 A3.01 I Importance: 3.~3.5 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - "OB" CREFAS fan will only start if it is in AUTO, or if the "OK CREFAS fan fails to start.
Incorrect - "OB" CREFAS fan will only start if it is in AUTO, or if the "OA" CREFAS fan fails to start.
Incorrect - " O A CREFAS fan will trip, but will only restart after a 30 second time delay to allow time for HV78-020A(B,C,D) to close.
Correct Answer - Chlorine isolation signal wilt cause "OA" CREFAS fan to trip and restart 30 seconds later.
Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 27 Unit 2 initial plant conditions are as follows:
b 27 of 100 100% reactor power "2A" RWCU pump is not available A loss of offsite power occurs at LGS. The Power System'Director reports that due to significant storm damage, offsite power may not be restored for up to three (3) days.
The CRS has directed the PRO to supply ESW to the RECW and TECW heat exchangers.
WHICH ONE of the following describes the reasons for these actions?
- a.
- b.
C.
u
- d.
Reason for Aligning ESW to RECW Provide RECW to DWCW to cool the primary containment Keep RWCU in service to minimize bottom head stratification Provide RECW to DWCW to cool the primary containment Keep RWCU in service to minimize bottom head stratification Reason for Aligning ESW to TECW To provide cooling to the Condensate Pump bearing oil coolers To provide cooling to the Condensate Pump bearing oil coolers To provide cooling to Instrument Air compressors To provide cooling to Instrument Air compressors
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference(s):
Learning Question#
27 New Exam Item E10/20, S13.6.D LLOTO430.07, LLOT0460.07,08 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - Condensate pumps are not safeguard powered, and will be unavailable during a LOOP.
Incorrect - Condensate pumps are not safeguard powered, and will be unavailable during a LOOP. "2A" RWCU pump is inop. The other RWCU pumps ("ZB" and "2C")
are also not available, since they are not safeguard powered.
Correct Answer - E l O/ZO provides guidance for performing S I 3.6.D to provide RECW cooling to DWCW for containment cooling. TECW can be used to cool the instrument air compressors (which are powered from safeguard power) to provide air for plant components.
Incorrect - "2A" RWCU pump is inop. The other RWCU pumps ("ZB" and "2C") are also not available, since they are not safeguard powered.
Required Attachments or Reference I
L I Obiective:
I I
Knowledge/Ability: I 29501 8 AK3.07 I Importance: 3.1/3.2 (Description of K&A, from catalog)
Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Cross-connecting with backup systems Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 28 b
28 of 100 Unit 2 plant conditions are as follows:
Reactor startup in progress, with reactor power at 4%
Reactor pressure is 960 psig Feedwater injection to the RPV is through Startup Bypass Valve LV-C-06-238A An instrument air line break occurs that results in a loss of air to LV-C-06-238A only.
WHICH ONE of the following describes the response of LV-C-06-238A, and an alternative method for maintaining RPV level?
- a.
- b.
C.
- d.
b Response of LV-C-06-238A Fails open Fails open Fails closed Fails closed Alternative Method for Maintaining RPV Level Close HV-06-238 and open HV-06-208A (A RFP Disch Valve)
Close HV-06-238 and open HV-06-220 (Pump Bypass Valve)
Open HV-06-208A (A RFP Disch Valve)
Open HV-06-220 (Pump Bypass Valve)
Limerick Generatina Station 2005 NRC Initial Licensing Examination Learning Objective:
KnowledgelAbility:
I Choice LLOT0540.07, 14 29501 9 AK2.03 I Importance: 3.2/3.3
,1 Basis or Justification Incorrect - See justification for c.
Incorrect - See justification for c.
Correct Answer - LV-C-06-238A fails closed on a loss of air. Only HV-06-208A can pass enough water at 4% power to maintain RPV level, and water coming via the Pump Bypass line will be at condensate pump discharge pressure, and will not be high enough in pressure to inject to the vessel with RPV pressure of 960 psig.
Incorrect - See justification for c.
I Required Attachments or Reference Source :
I New Exam Item Refe re n ce(s ):
I P&ID M-06
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 29 L
29 of 100 Unit 1 plant conditions are as follows:
A LOCA has occurred RPV pressure is 60 psig and lowering slowly RPV level is -145 inches and steady Drywell temperature and pressure are on the safe side of T-I 02 Curve PC/P-2, Suppression pool level is 38.9 ft. and rising slowly.
Drywell Spray Initiation Limit WHICH ONE of the following describes the reason why drywell spray is not permitted in this condition?
- a.
- b.
C.
- d.
Adequate core cooling is not assured Suppression pool wall loading limits may be exceeded Suppression pool to drywell vacuum relief valves may not function Excessive negative drywell pressure may damage the drywell liner
Limerick Generating Station 2005 NRC Initial Licensing Examination Reference(s):
Learning (Choice LLOTI 560.5 Basis or Justification Objective:
Knowledge/Ability:
Incorrect - Adequate core cooling is assured by core submergence above top of active fuel (>-161).
Incorrect - Drywell spray does not contribute to suppression pool wall loading. This concern is a function of RPV pressure vs. suppression pool level, as determined by the SRV Tailpipe Level Limit Curve, SP/L-1.
Correct Answer - Per T-I 02 Bases, step SP/L-22, with suppression pool level not able to be maintained below 38.7 ft. (elevation of the bottom of the internal suppression pool-to-drywell vacuum breakers less vacuum breaker opening pressure in feet of water), operation of the drywell sprays must be terminated because post drywell vacuum relief cannot be assured.
incorrect - Liner damage is likely to occur only if drywell spray is initiated with conditions on the unsafe side of the Drywell Spray Initiation Limit curve. The given conditions stated in the question are that conditions are on the safe side of this curve.
295029 G2.1.32 I Importance: 3.413.8 Required Attachments or Reference L
Source:
I New Exam Item Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensing Examination Question: 30 u
30 of 100 Unit 2 plant conditions are as follows:
A LOCA has occurred RPV level is -75 inches The Reactor is shutdown with all rods in Both H2/02 Analyzers have been in service for the past hour DW 0 2 level is 6%
DW H2 level is 1.5%
SP H2 level is 0.5%
WHICH ONE of the following describes the required actions for operating the H2 Recombiners and primary containment requirements for the conditions above?
H2 Recombiners Primary Containment Requirements
- a.
Operate InerWent Drywell without exceeding General Emergency offsite release rate
- b.
Operate InertNent Drywell regardless of offsite release IneWent Drywell without exceeding General Emergency offsite release rate
'v
- c.
Do not operate
- d.
Do not operate InertNent Drywell regardless of offsite release
Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
30 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Per T-I 02 sheet #2, table PC/G-l entry into leg DW/G-2 is required for these HS 0 2 levels. This requires operation of the H2 Recombiners and Venting of DW without exceeding offsite release rates.
Incorrect - See a justification Incorrect - See a justification Incorrect - See a justification T-102 sheet #2 Required Attachments or Reference Knowledge of the inte CONCENTRATIONS s between HIGH CONTAINMENT HYDROGEN following: Hydrogen and oxygen recombiners Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 31 u
31 of 100 Unit 1 plant conditidns are as follows:
Startup in progress, with all lRMs on Range 5 SRM shorting links are installed As power has risen, all SRMs have been partially withdrawn to maintain countrate between I00 and I O5 cps The RO has just selected and fully withdrawn all four SRMs, and all SRM countrates are now less than 3 cps.
WHICH ONE of the following describes the status of the SRM system?
- a.
SRM rod withdraw block enforced due to SRMs downscale
- b.
SRM rod withdraw block will NOT enforce due to IRMs above Range 3
- c.
SRM rod withdraw block will NOT enforce due to shorting links installed
- d. SRM rod withdraw block enforced due to detectors fully withdrawn when not permitted
Limerick Generating Station 2005 NRC Initial Licensing Examination Reference(s):
Learning Objective:
Knowledge/Ability:
Question#
31 LLOT0240.6 21 5004 A I.04 I Importance: 3.5/3.5 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for b.
Correct Answer - With all IRMs above range 3, both the "SRM retracted when not permitted" and "SRM Downscale" rod blocks are bypassed. Therefore, no SRM rod withdraw block is enforced.
Incorrect - shorting links are in the RPS circuit, and do not affect SRM rod withdraw blocks Incorrect - See justification for b.
Required Attachments or Reference I
including: Control rod block status Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 32 32 of 100 b
Entry into the Unit 2 4A Feedwater heater room is required with the following conditions:
2 Equipment Operators are required The first Equipment Operator has 150 mrem TEDE for the current year The second Equipment Operator has 300 mrem TEDE for the current year Both Equipment Operators will be working in a 600 mrem/hr field None of the Equipment Operators have a High Lifetime Exposure The job will take 3 hrs to complete WHICH ONE of the following describes if the Administrative Dose Control Level will be exceed and who approves the minimum dose extension if a dose extension was required?
Administrative Dose Dose Extension Approval Control Level Exceeded
- a.
No RP Manager
- b.
Yes Station VP
- c.
Yes RP Manager L
- d.
No Station VP
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see IC justification Incorrect - see c justification Correct Answer - Admin dose control levels are 2000 mrem per year. 3 hrs x 600 mrem/hr = 1800 mrem. # I EO 150 mrem + 1800 mrem = 1950 mrem. #2 EO 300 mrem + 1800 mrem = 2100 mrem. #2 EO may exceed Admin levels. RPM authorizes all dose extensions above Admin dose control levels.
Incorrect - see c justification Required Attachments or Reference Source :
New Exam Item Learning Exelon Generic lesson plan RWT 7,17,18 Objective:
Knowledge/Ability: 2.3.04 I Importance: 2.5/3.1 (Description of K&A, from catalog)
Knowledge of radiation exposure limits and contamination controllincluding permissible levels in excessof those authorized.
Reference( s):
RP-AA-203 Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 33 33 of 100 i,
Unit 2 plant conditions are as follows:
A seismic event has occurred Reactor power 100%
HPCl is operating in Full Flow Test from Suppression Pool to Suppression Pool Suppression Pool cooling is in service with 2A RHR pump running Suppression Pool level 20 feet and lowering slowly WHICH ONE of the following describes the required action of T-102 and the reason for the action?
- a.
- b.
C.
- d.
i, Secure HPCl if Suppression Pool level drops below 18 feet due to vortex limits Secure 2A RHR pump if Suppression Pool level drops below 13.5 feet due to vortex limits Transfer HPCl suction to the CST if Suppression Pool level drops below 13.5 feet due to vortex limits Shutdown the reactor if Suppression Pool level drops below 13.5 feet due to Drywell and Suppression Pool being directly connected at 13 feet
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability:
4 New Exam Item T-I 02 and T-I 02 Bases LLOTI 560.5 21 9000 K6.06 I Importance: 3.713.7 Basis or Justification Incorrect - Vortex limits for HPCl are at 15.42 ft in SP. HPCl must be shutdown at I 8 ft in SP to prevent pressurizing SP air space due to HPCl exhaust.
Correct Answer - RHR vortex limits set at 13.42 ft in SP requires shutdown of pump.
Incorrect - HPCl must be shutdown at 18 ft in SP to prevent pressurizing SP air space due to HPCl exhaust regardless of core cooling.
Incorrect - Plant is not shutdown until 12 ft in SP. At 13 ft in SP and DW are not cross-connected.
Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 34 L
34 of 100 Unit I plant conditions are as follows:
Reactor scrammed from 100% due to High Drywell Pressure Drywell pressure is 25 psig and rising Drywell temperature is 260°F and rising Reactor pressure is 500 psig and dropping Reactor level is +35 inches GP-4 was NOT performed The CRS directs the PRO to spray the Drywell per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation, using "IA" RHR.
WHICH ONE of the following actions must be taken before Drywell Spray can be initiated?
- a. Trip both Recirc Pumps
- b. Place "OA" RHRSW in service
- c.
Close HV-51-1F017A, 1A RHR LPCl Inj PClV
- d. Arm and Depress El 1A-SGIA, INITIATION Pushbutton b
Limerick Generatina Station 2005 NRC Initial Licensina Examination Cognitive (H, L)
Unit (1. 2)
Choice H
PRA (Y/N)
SRO I
N N
- a.
- b.
C.
- d.
Basis or Justification Incorrect - Following a reactor scram, a Main Generator Lockout will occur on Reverse Power. The Generator Lockout will initiate a Fast Transfer on the Unit Aux Buses which will cause both Recirc Pumps to trip automatically.
Incorrect - RHRSW is placed in service after Drywell Spray has been initiated per Incorrect - HV-51-1 F017A, LPCl Valve will not open until a valid LOCA occurs on Reactor Level of -129 or 1.68 psig Drywell Pressure and < 455 psig Reactor Pressure, which has not been reached. The valve will still be closed.
Correct Answer - Per T-225, if a LOCA signal does not exist, the PRO must manually initiate a Divisional LOCA in order to open the Drywell Spray valves. Since pressure is above 455 psig, the PRO must arm and depress E l 1 A-S61 A, INITIATION T-225.
Pushbutton.
I Required Attachments or Reference Ability to execute procedure steps: RHWLPCI: Containment Spray Mode Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 35 35 of 100 WHICH ONE of the following describes a condition that violates a Technical Specification Safety L
OPCON 3, Drywell pressure is 60 psig Limit?
- a.
- b.
C.
- d.
OPCON 4, Reactor level is -170 inches OPCON 2, Reactor pressure is 1280 psig OPCON I, Minimum Critical Power Ratio (MCPR) is 1.I 2
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1,2)
Question#
35 Choice Basis or Justification
- a.
Incorrect - DW pressure at 60 psig exceeds the design limits of the containment, but is not a safety limit, as it will not damage the fuel cladding, reactor pressure vessel, or primary system piping.
Correct Answer - RPV level below -1 61 inches violates Safety Limit 2.1.4. This Safety Limit is only applicable in OPCON 3,4, and 5. While the plant is starting in OPCON I, when the reactor scrams at + I 2 5 inches, the plant will then be in OPCON
- b.
L PRA (Y/N)
SRO 1
Y N
3, and this Safety Limit applies.
Incorrect - RPV pressure must rise above 1325 psig to exceed safety limit 2.1.3.
C.
- d.
lncorrect - MCPR must lower below 1.07 with 2 recirc pumps in operation to exceed safety limit 2.1.2.
Required Attachments or Reference I
I I
L Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 36 36 of 100 Unit 2 plant conditions are as follows:
OPCON 2 Reactor power is 8%
Control rod 22-1 1 is at position 10 and is being withdrawn to its withdrawal limit of 12 An inadvertent two-notch withdrawal results in control rod 22-1 1 stopping at position 14.
Supervision and Reactor Engineering have been notified.
WHICH ONE of the following describes the required action(s) for the RWM latched status of control rod 22-1 I ?
- a.
- b.
C.
- d.
Immediately insert a manual reactor Scram Substitute a rod position of 12 and insert rod 1 notch orth Minimizer and insert to position 12 position 12 using the INSERT pushbutton
Limerick Generatina Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1,2)
Question #
36 H
PRA (Y/N)
SRO 2
N N
Choice Source:
Learning Objective:
KnowledgeIAbility:
Reference(s):
- a.
New Exam Item LL070095.3 G2.2.33 I Importance: 25/29 ON-I 23
- b.
- d.
Basis or Justification Incorrect - see d justification Incorrect - see d justification Incorrect - see d justification Correct Answer - One notch withdrawal error is allowed to be corrected by inserting control rod back to its target postion.
Required Attachments or Reference Prepared by: Mark Crim
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 37 37 of 100 Unit 1 plant conditions are as follows:
b Plant in OPCON 4 Shutdown cooling placed in service using ?A RHR loop 30 minutes ago Reactor level +80 inches on Upset Range Average Reactor coolant temperature 195 degrees F and stable Rx level drops to + I O inches on Narrow Range and stabilizes.
WHICH ONE of the following describes allowable actions that will permit restoration of Shutdown Cooling and the reason for the actions?
Actions that will Allow Restoration of Shutdown Cooling Reason for Actions
- a.
- b.
L C.
- d.
Restore Reactor level to +35 inches and bypass low level isolations per GP-8.5, Isolation Bypass of Crucial Systems Restore Reactor level to +35 inches and bypass low level isolations per GP-8.5, Isolation Bypass of Crucial Systems Restore Reactor level to +80 inches and reset low level isolations Restore Reactor level to +80 inches and reset low level isolations Prevent inadvertent change of OPCON Ensure adequate NPSH for the 1A RHR pump Prevent inadvertent change of OPCON Ensure adequate NPSH for the I A RHR pump
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1, 2)
Question#
37 Choice I Basis or Justification H
PRA (Y/N)
SRO 1
Y N
- a.
Incorrect - GP-8.5 does not address isolation bypass of Shutdown Cooling isolations
- b.
Incorrect - GP-8.5 does not address isolation bypass of Shutdown Cooling isolations, raising level is not to satisfy RHR pump NPSH concerns C.
Correct Answer - Must restore level >I 2.5 and then reset the low level isolation to reopen valves. If not restored decay heat will cause RPV temp to rise and cause and inadvertent change of OPCON from OPCON 4 to 3.
Incorrect - Raising level is not to satisfy RHR pump NPSH concerns.
- d.
Required Attachments or Reference SHUTDOWN COOL1 Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 38 38 of 100 Unit 1 plant conditions are as follows:
i, OPCON 5 SRM A fuel bundle is currently being lowered into the core, not directly adjacent to any WHICH ONE of the following responses requires entry into ON-120, Fuel Handling Problems?
- a. "A" SRM rises from 30 to 100 cps
- b. "B" SRM rise m 45 to 130 cps
- c. "C" SRM rises from 35 to 150 cps
- d. "D" SRM rise m 50 to 170 cps
Limerick Generating Station 2005 NRC Initial Licensing Examination
?
- d.
Question#
38 Choice I Basis or Justification Incorrect - since two doublings not reached I a.
I Incorrect - since two doublings not reached I
Cognitive (H, L)
Unit (I,
- 2)
I Incorrect - since two doublings not reached I
L PRA (Y/N)
SRO 1
N N
Correct Answer - Per ON-120, symptom 1.I, with C SRM rising from 35 to 150 cps, it has increased by more than two doublings, and ON-120 must be entered.
Source:
Learning Reference( s):
New Exam Item LLOTI 550.1 ON-I 20 Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination L Question: 39 39 of 100 Unit 1 is at 100% power.
The RO manually scrams the reactor due to rising Drywell Pressure. The following indications are observed:
All Scram Status lights are extinguished PMS indicates "ALL RODS IN" SCRAM PROFILE light is lit Reactor Level drops to -30" before recovering WHICH ONE of the following identifies the RPV level at which Setpoint Setdown will be activated and the mode of RPV level control when Setpoint Setdown is activated?
- a.
Less than +12.5" lowering, Single Element Control
- b.
Less than +12.5" lowering, Three Element Control
- c.
Greater than +20 'I rising, Single Element Control
- d.
Greater than +20" rising, Three Element Control
'L'
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference( s):
Learning Objective:
Knowledge/Ability:
Question #
39 Choice I Basis or Justification New Exam Item S0.6.1.D U/1 LLOR0401 B.6 259002 A3.06 1 Importance: 3.0/3.0
- a.
Incorrect - See "c'l
- b.
Incorrect - See "c"
- d.
Correct Answer - On a valid scram (A and B RPS de-energize), FWLC holds pre-scram FW flowrate for 5 seconds and then ramps to 10% flow at 6% per second.
When level restores above +20", FWLC transfers to single element, SCRAM PROFILE light extinguishes and Setpoint Setdown activates.
Incorrect - See "c" Required Attachments or Reference I
I I
u Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 40 Unit 2 plant conditions are as follows:
40 of 100 OPCON5 Irradiated fuel moves are in progress
- Secondary Containment Zones 2 and 3 are NOT cross-tied
- Secondary Containment ventilation controls are in a normal alignment The following indications and alarms exist in the MCR:
Annunciator 209 RAD, E-I 1 REAC ENCL REFUEL FLR VENT EXHAUST RAD MON
- Annunciator 209 RAD, E-3 1 REAC ENCL REFUEL FLR VENT EXHAUST HI RAD I AT1 0 N Refuel Floor ventilation exhaust radiation indicates 2.5 mr/hr Reactor Enclosure ventilation exhaust radiation indicates 0.8 mr/hr N B HI-HVDOWNSCALE No operator actions have been taken.
WHICH ONE of the following describes the response of SGTS fans and RERS fans to the conditions above?
- a.
One Fan running only
- b.
Both Fans running
- c.
One Fan running only
- d.
Both Fans running No Fans running One Fan running only One Fan running only No Fans running
Limerick Generating Station 2005 NRC Initial Licensing Examination Reference(s):
Learning Choice Annun 209 E-I, E-3 LLOTO200.6
- a.
Objective:
Knowledge/Ability:
- b.
261000 K1.08 I importance: 2.8/3.1 C.
- d.
Basis or Justification Incorrect - see d justification Incorrect - see d justification Incorrect - see Id justification Correct Answer - On a RF exhaust ventilation HI-HI RAD both SGTS fans start.
RERS fan auto starts ONLY on RE exhaust ventilation HI-HI RAD.
Required Attachments or Reference Source:
I New Exam Item
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 41 b
ATTACHMENT Q41 IS PROVIDED Unit 2 plant conditions are as follows:
L 41 of 100 Reactor power is 50%
EHC Load Set is adjusted to 55%
EHC Load Limit is set at 103%
Maximum Combined Flow Limit is set at I 15%
EHC pressure setpoint is set at 960 psig 3 psi bias is applied to the "6" pressure regulator Main Steam pressure at the Pressure Averaging Manifold (PAM) is 974 psig Turbine Control Valves are open for 47% steam flow Reactor power is raised and Main Steam PAM pressure rises to 984 psig. No other manual adjustments have been made.
WHICH 'ONE of the following describes the total control valve position (in % open) after the plant is stabilized?
- a.
45%
- b.
55%
- c.
80%
- d.
103%
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference(s):
I Learning 0 bjective:
Knowledge/Ability:
Question#
41 Choice Basis or Justification
- a.
Incorrect - See justification for b.
Correct Answer - PAM pressure of 984 psig, with Pressure Setpoint of 960, results in a difference out of the regulator of 24 psig. 24 psig x 3.33% (gain unit) =
approximately 80%. However, since Load Set is still set at 55%, total control valve open position is limited to 55%.
Incorrect - See justification for b.
- b.
C.
New Exam Item LLOTO590.05 241000 Al.08 I Importance: 3.3/3.2
- d.
1 Incorrect - See justification for b.
EHC logic diagram Required Attachments or Reference I
I L
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 42 42 of 100 L
Unit 2 plant conditions are as follows:
100% reactor power
+35" Reactor level Master Feedwater Level controller in "AUTO" All Reactor Feed Pump controllers in "AUTO Feedwater Level Control is selected to "3 ELEMENT" "C" Main Steam Line flow instrument fails upscale.
WHICH ONE of the following identifies the response of reactor water level and the procedural action required to mitigate this response?
- a.
- b.
C.
L
- d.
Reactor Level drops and stabilizes at a level above the scram setpoint. Place Feedwater Levet control in Single Element Control per S06.O.E, U/2 Feedwater Level Control and Reactor Feed Pump Control System Manipulation.
Reactor Level drops until scram occurs on Reactor Low Level. Restore Reactor Level using S06.1.D, U/2 Post Scram Level Control.
Reactor Level rises and stabilizes at a level below Main Turbine trip setpoint. Manually control Reactor Feed Pumps in accordance with OT-I I O, Reactor High Level.
Reactor Level rises until Main Turbine trip occurs on Reactor High Level. Restore Reactor Level using S06.1.D, U/2 Post Scram Level Control.
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Reference(s):
Question #
42 I
New Exam Item LLOT0550.7 OT-I IO, REACTOR HIGH LEVEL Choice Objective:
Knowledae/Abilitv:
- a.
259001 A2.07 I Imeortance: 3.7/3.8
- b.
C.
- d.
Basis or Justification Incorrect - FWLCS will adjust feedwater flow higher to compensate for a false high steam flow signal, therefore reactor level will rise.
Incorrect - See "a" I
Correct Answer - Feedwater flow will rise in response to the false high steam flow signal and level will stabilize at a higher reactor level. OT-I 10 directs manually controlling RFP if FWLCS malfunction occurs.
Incorrect - See "c" Required Attachments or Ref ere n ce v
., I (Description of K&A, from catalog)
Ability to (a) predict the impacts of the following on the REACTOR FEEDWATER SYSTEM; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Reactor water level control system 1 malfunctions Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 43 L
43 of 100 Unit 1 plant conditions are as follows:
Reactor power is 100%
Annunciator I09 RAD, G-2, 1 Air Ejector Offgas Discharge Hi Radiation is Air Ejector Discharge radiation level is 4.1 x I O 5 mr/hr and rising slowly alarming WHICH ONE of the following actions is required to reduce Air Ejector discharge radiation levels below 2.1 x I O4 mr/hr and the reason for lowering Air Ejector discharge radiation levels?
- a.
- b.
C.
b
- d.
Actions Required to Reduce Air Ejector Radiation Levels Reduce Reactor Power Reduce Reactor Power Isolate Steam Jet Air Ejectors Isolate Steam Jet Air Ejectors Reason for Lowering Air Ejector Discharge Radiation Levels Limit Off Site release through the North Stack Limit Off Site release through the South Stack Limit Off Site release through the North Stack Limit Off Site release through the South Stack
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Reference(s):
Question #
43 New Exam Item LLOTI 550.2 ON-I 02 Choice Objective:
Knowledge/Ability:
- a.
G2.3.11 I Importance: 2.7/3.2
- b.
C.
- d.
Basis or Justification Correct Answer - Per ON-I 02 basis, reduction of power result in acceptable short term off-gas releases after a delay in the charcoal absorbers. Off gas discharges to the North Stack.
Incorrect - Off gas does not discharge to the South Stack Incorrect - While isolating SJAE would lower radiation levels, it is not a required action and eventual loss of condenser vacuum would result.
Incorrect - While isolating SJAE would lower radiation levels, it is not a required action and eventual loss of condenser vacuum would result.
Required Attachments or Reference
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 44 44 of 100 u
Unit 1 plant conditions are as follows:
Drywell Pressure 57 psig and rising Drywell Temperature 330°F and rising Reactor Level -1 75 inches and lowering Five (5) ADS Valves are open All ECCS pumps are running All rods are in WHICH ONE of the following safety functions is the highest priority and the basis for the priority?
Highest Priority
- a.
Drywell Spray Basis for Priority Containment cooling is a higher priority than RPV integrity with the given conditions
- b.
Drywell Spray
- c.
Maximize RPV injection b
- d.
Maximize RPV injection RPV integrity is not threatened with the given conditions Adequate core cooling is required before containment cooling is permitted with the given conditions Containment integrity is not threatened with the given conditions
Limerick Generating Station 2005 NRC Initial Licensing Examination
- a.
Question#
44 Choice I Basis or Justification Incorrect - See justification for c.
- b.
C.
- d.
Incorrect - See justification for c.
Correct Answer - At -175" reactor level, fuel is uncovered. T-I 1 1 directs maximizing RPV injection with all available systems when level drops below -161" and T-112 has been performed. This is a higher priority than drywell spray because T-I02 only directs drywell sprays if adequate core cooling is assured.
Incorrect - See justification for c.
Required Attachments or Reference Cognitive (H, L)
Unit (1, 2)
T-102, T-I 1 I H
PRA (Y/N)
SRO 1
Y N
(Description of K&A, from catalog)
Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.
Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 45 L
45 of I00 Unit 2 plant conditions are as follows:
A large unisolable leak from the Reactor Recirculation System piping has resulted Both suppression pool-to-drywell vacuum relief valves on one LOCA downcomer Drywell and Suppression Pool sprays cannot be initiated Suppression Pool level is 24 ft. and rising very slowly in a high drywell pressure condition are stuck open WHICH ONE of the following describes the expected response of the primary containment and the status of containment integrity?
- a.
Drywell pressure will equalize with Suppression Pool pressure; containment integrity is NOT threatened L
- b.
C.
- d.
Drywell pressure will equalize with Suppression Pool pressure; containment integrity is threatened Drywell pressure will rise to about 5 psig greater than Suppression Pool pressure; containment integrity is NOT threatened Drywell pressure will rise to about 5 psig greater than Suppression Pool pressure; containment integrity is threatened
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
45 Choice I Basis or Justification Incorrect - See justification for b.
I suppression pool removes the pressure suppression capability of the suppression I
- d.
I Incorrect - See justification for b.
Prepared by: Craig Fritz
Limerick Generating Station 2005 N.RC Initial Licensing Examination Question: 46 u
46 of I00 Unit 2 plant conditions are as follows:
The main turbine trips with core thermal power at 3458 MWth All main turbine bypass valves open following the turbine trip RPV pressure rises until several SRVs open at the high pressure relief setpoint AI, A2, A3, and A4 "SCRAM SYSTEM LOGIC" lights on 20C603 are lit WHICH ONE of the following describes the plant response and the reason for this response?
Plant Response Reason
- a.
ARI valves will open To initiate rod insertion
- b.
ARI valves will open
- c.
Backup Scram valves will open To initiate rod insertion
- d.
To prevent exceeding RPV design pressure Backup Scram valves will open To prevent exceeding RPV design pressure
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (I, 2)
I Question #
46 H
PRA (Y/N)
SRO 2
Y N
Choice
- a.
- b.
C.
- d.
Source :
Reference( s):
Learning Basis or Justification Correct Answer - All four of the "A" SCRAM SYSTEM LOGIC lights being lit indicate that RPS has not caused a scram on the turbine trip. Since both RPS systems (A and B) have not de-energized, the backup scram valves will not function. With SRVs lifting at their pressure relief setpoint (1 170 minimum), RPV pressure exceeded 1149, and RRCS ARI will actuate. The UFSAR states that ARI is designed to "allow insertion of all control rods to begin within 15 seconds."
Incorrect - SRVs are the components designed to prevent the RPV from exceeding design pressure.
New Exam Item UFSAR section 7.6.1.8.3.1 LLOT0315.04 Incorrect - Both RPS systems have not de-energized ("A" still energized), therefore, backup scram valves will not open.
Incorrect - Both RPS systems have not de-energized ("A" still energized), therefore, backup scram valves will not open. SRVs are the components designed to prevent the RPV from exceeding design pressure.
Objective:
Knowledge/Ability:
Required Attachments or Reference 295025 EK3.06 I Importance: 4.2/4.4 Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 47 47 of 100 Unit I plant conditions are i,
100% reactor power Normal reactor enclosure ventilation in service Both Standby Gas Treatment (SGTS) fans are in "AUTO" A Drywell leak results in D 012 4W Bus.
WHICH ONE of the following identifies the status of the SGTS fans following the Bus Lockout?
II pressure rising to 3 psig. 5 minutes later, a lockout occurs on
- a.
Both Fans off
- b.
Both Fans running
- c.
"A" Fan running, "B'l Fan tripped
- d.
"A" Fan tripped, "B" Fan running
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
I Question#
47 I
Basis or Justification Incorrect - See justification for "c" Incorrect - See justification for "c" Correct Answer - Both SBGT Fans will start on Drywelf pressure greater than I
.68 psig. The "B" SBGT Fan will trip on loss of power to D12.
- d.
incorrect - See justification for "c" Required Attachments or Reference I
i, oss or malfunction of the following will have on the STANDBY A.C. electrical distribution GAS TREATMENT SYS Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 48 48 of 100 Unit 2 plant conditions are as follows:
u OPCON 5 with Core Alterations in progress D24 Bus is de-energized for relay replacement work 20Y102 Distribution Panel is blocked to replace the main breaker The Electrical Maintenance Supervisor requests various 480 VAC Motor Control Centers and 120 VAC Distribution Panels be blocked for electrical maintenance.
WHICH ONE of the following 480 VAC MCCs/l20 VAC Distribution Panels may be de-energized for maintenance while allowing Core Alterations to continue?
- a.
- b.
C.
- d.
D234-R-E 480 VAC MCC D214-G-D 480 VAC MCC 20Y101 120 VAC Distribution Panel 20Y 163 120 VAC Distribution Panel
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - This is a Division 1 MCC. In OPCON 5, 2 divisions are required to be energized. With D22 (due to loss of 20Y102) and D24 INOPERABLE, all Division 1 and 3 components must be energized per Tech Spec 3.8.3.2, ELECTRICAL POWER Correct Answer - Even though this is a division 1 MCC, D214-G-D is not required by Tech, Spec. 3.8.3.2. Therefore it could be blocked without impacting the Tech Spec LCO.
Incorrect - 2OYlO1 is a Division 1 panel. See "a" SYSTEMS DISTRIBUTION - SHUTDOWN Incorrect - 2OYA63 is a Division 3 panel. See "a" Tech Specs Required Attachments or Reference L
Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 49 L
49 of 100 Unit I plant conditions are as follows:
100% reactor power Hydrogen Water Chemistry is in service The following alarm has annunciated:
1 MAIN STEAM LINE DIVISION I RAD MONITOR HVDOWNSCALE The following readings are taken from the Main Steam Line Rad Monitors on panel lOC600:
A - 1310 mr/hr B - 1320 mr/hr C - 825 mr/hr D - 1340 mr/hr The following information was obtained from the Unit 1 Main Steam Line Rad Monitors Operator Aid on panel 10C600:
Unit 1 Main Steam Line RAD Monitors 1341 MWhr I
I C I 970 MR/hr I 1.0 I
I 1455 MWhr I
I D I 900 MR/hr I 1.0 I
1350 MR/hr I
WHICH ONE of the following identifies the Rad Monitor(s) responsible for the alarm?
- a.
- b.
C.
- d.
A B
C
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
Basis or Justification Incorrect - Setpoint for A Rad Monitor is 1341 mr/hr.
- b.
C.
- d.
Required Attachments or Reference Correct Answer - Setpoint for B Rad Monitor is 1305 mr/hr and either A or B Rad Monitor will provide a DIV i alarm.
Incorrect - Setpoint for C Rad Monitor is 1455 mr/hr and C Rad Monitor will provide a DIV II alarm. 825 mr/hr is mid range and will not provide a downscale alarm.
Incorrect - Setpoint for D Rad Monitor is 1350 mr/hr and D Rad Monitor will provide a DIV II alarm.
Cognitive (H, L)
Unit (I, 2)
L PRA (Y/N)
SRO I
N N
nually operate and/or monitor in the control room: Recorder Source:
Reference( s):
Learning I
I New Exam item ARC-MCR-109 F-1, Main Steam Line Rad Monitor Op Aid 01-014 LLOTO720.02 Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 50 50 of 100 Unit 1 is at 100% reactor power when the following sequence of events occur:
L "C" Main Steam Line ruptures in the Outboard MSlV room and the steam line fails to isolate Outboard MSlV room pressure peaks at 5 psig Reactor scrams on MSIV closure Reactor level drops to -20 inches before recovering to +35 inches Drywell pressure is 0.4 psig Reactor Enclosure Ventilation Exhaust Radiation is 1.2 mr/hr Current plant conditions have been stable for the past 5 minutes.
WHICH ONE of the foliowi identifies the current exhaust path(s) from the MSlV room?
- a.
- b.
C.
- d.
i/
Standby Gas Treatment System to North Stack Reactor Enclosure Equipment Compartment Exhaust to South Stack Outboard MSlV room Blowout Panels to Reactor Building Roof and Condenser Area re Recirculation System to Standby Gas Treatment System to
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Reference(s):
Basis or Justification Incorrect - Standby Gas Treatment System does not draw directly on the Outboard MSlV room, RERS would align to draw on the room and discharge to Standby Gas.
See "d" for further explanation.
Incorrect - This is the normal exhaust path for the Outboard MSlV room, however, due to the pressure rise in the room, the Steam Flooding Dampers will isolate to prevent the spread of steam throughout Secondary Containment.
Correct Answer - A Main Steam Line break in the Outboard MSIV room will cause pressure in the room to rise which will cause the Steam Flooding dampers to isolate.
Pressure will continue to rise until the Blowout Panels actuate Incorrect - Although this would be the exhaust path if there were a Reactor Enclosure Isolation signal, an isolation signal does not exist, therefore Standby Gas and RERS will not be running.
New Exam Item LLOTOI 90.06 M-76 Required Attachments or Reference Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination L Question: 51 51 of I00 ATTACHMENT Q51 IS PROVIDED Unit 1 initial plant conditions are as follows:
Reactor power is 100%
Steam Seal Evaporator (SSE) level as indicated by LI-07-157 on 10C653 is 0 inches Subsequently, an Equipment Operator notifies the Main Control Room that the Instrument Air line to valve LV-C-07-157, Steam Seal Evap Feed In, has ruptured.
b L-WHICH ONE of the following describes the effect of the air leak on SSE level and the action required to mitigate the level change?
Effect on SSE Level
- a.
- b.
C.
- d.
Rise Lower Rise Lower Action Required to Mitigate Level Change Close HV-007-157, SSE Cond M/U Shutoff Valve (SUP)
Close HV-007-158, SSE Steam Outlet Valve (OUTLET)
Close HV-007-156, SSE Cond M/U Bypass Valve (BYPASS)
Close 007-1 053 and 007-1075, SSE Drain Valves
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
51 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - LV-C-007-157 will fail open on a loss of Instrument Air. With the valve full open, SSE level will rise. To prevent further SSE level rise, HV-007-157 must be closed.
Incorrect - See justification for a Incorrect - See justification for a Incorrect - See justification for a M-07 Sheet. 2 Required Attachments or Reference Source:
New Exam Item Learning LLOT0495.07, LLOT2002.02 0 bjective:
Knowledge/Ability: Generic 2.4.47 I Importance: 3 ~ 3. 7 (Description of K&A, from catalog)
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
Reference (s):
M-02, M-05, M-07, ARC-MCR-I06 A-4 Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 52 L
52 of 100 With Unit 1 at 93% power, the "I B" Outboard MSlV inadvertently closes resulting in the following conditions:
Reactor power rises to 109%
Reactor pressure rises to 1064 psig Reactor level lowers to +32 inches Total core flow is 80%
No operator actions are taken.
WHICH ONE of the follo annunciators will be alarmed?
- a.
REACTOR ESS (1 07 REACTOR G-2)
- b.
REACTOR HVLO LEVEL (107 REACTOR H-2)
- c. APRMUP E TRIP/INOP (108 REACTOR B-3)
- d.
MSlV NOT FULLY OPEN TRIP (107 REACTOR E-I)
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (I,
- 2)
Question#
52 Choice Basis or Justification
- a.
Correct Answer - Reactor pressure above 1053 psig will cause this annunciator to alarm.
L PRA (Y/N)
SRO 1
N N
- b.
Incorrect - RPV level must go below +30 inches for this annunciator to alarm.
C.
Incorrect - Reactor power must be above.66w+62.8% (1 15.8%) for this annunciator to alarm.
Incorrect - More than one MSlV must close for this annunciator to alarm.
- d.
Required Attachments or Reference Knowledge/Ability: I G2.4.46 I Importance: 333.6 (Description of K&A, from catalog)
Ability to verify that the alarms are consistent with the plant conditions.
Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 53 53 of 100 Unit 2 plant conditions are as follows:
u An ATWS in progress "2L" SRV is stuck open Suppression Pool level is 17 feet and steady "2A" RHR is operating in Suppression Pool Cooling mode "2A" Core Spray pump is running on minimum flow WHICH ONE of the following instruments must be used to accurately determine when Suppression Pool temperature reaches 1 I O degrees F?
- a.
- b.
C.
- d.
"2A" RHR pump suction temperature "2A" Core Spray pump suction temperature "2A" RHR Heat exchanger outlet temperature Suppression Pool Temperature Monitoring System (SPOTMOS)
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
53 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - per T-102, SPOTMOS is to be used unless SP level is below 17.8 ft, then RHR pump suction temp should be used if RHR pump is running.
Incorrect - see a justification Incorrect - see a justification Incorrect - see a justification Required Attachments or Reference Source:
I New Exam Item Reference( s ):
T-102 Note 2 Learning LLOT1560.5 0 bjective:
Knowledge/Ability: 295026 A?.03 I Importance: 3.9/3.9 (Description of K&A, from catalog)
Ability to operate and/or monitorthe following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Temperature monitoring Prepared by: Tim Kan
Limerick Generating Station 2005 bjRC Initial Licensing Examination Question: 54 L
ATTACHMENT Q54 IS PROVIDED 54 of 100 Unit 2 plant conditions are as follows:
Drywell cooling has been lost due to an inadvertent isolation that cannot be Drywell temperature is 135 deg. F Drywell pressure is 0.8 psig and rising Suppression pool airspace temperature is 123 deg. F Suppression pool pressure is 0.4 psig Containment Leak Detector indication is normal and stable bypassed WHICH ONE of the following describes the ability to vent the drywell per OT-I 01, "High Drywell Pressure"?
- a.
Permitted until drywell pressure is less than 0.65 psig
- b.
Permitted when drywell pressure is greater than 0.95 psig
- c.
Permitted until drywell temperature is less than 134 deg. F
- d.
Permitted when drywell temperature is greater than 137 deg. F L
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
OT-101 Required Attachments or Reference Basis or Justification Cognitive (H, L)
Unit (1, 2)
Incorrect - See justification for b.
H PRA (Y/N)
SRO 2
N N
Correct Answer - Using the given suppression pool airspace temperature and suppression pool pressure, the nitrogen mass to be used for the suppression pool is 8400 Ibs (from Attachment 1); using Attachment 2, must use the next LOWER curve (8250) on OT-101 Attachment 2. 0.8 psig and 135 deg. F is above the 8250 Ibs curve. Pressure rising to greater than 0.9 psig will result in conditions on the safe side of the curve, and venting is now permitted.
Incorrect - See justification for b.
Source:
Learning Objective:
Knowledge/Ability:
Reference (s):
Incorrect - Venting will not be permitted when temperature is above 137 deg. F.
Temperature must be lower, or Drywell pressure higher for venting to be permitted.
New Exam Item None found 295028 EA2.04 I Importance: 4.1/4.2 OT-IO1 Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 55 L
55 of 100 Unit 2 is at 100% reactor power.
An internal fault causes a loss of the 2B RPS UPS Static Inverter and the static switch fails to transfer power to the alternate source.
WHICH ONE of the following identifies a system isolation that will occur and the capability to bypass the isolation?
System Isolation
- a.
PClG Bypass Capability NO
- b.
RWCU YES
- c.
MSlV NO
- d.
RECW YES
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - Instrument Gas will isolate on a loss of 2B RPS UPS Static Inverter, however, the isolation can be bypassed.
Incorrect - RWCU will isolate on a loss of 2B RPS UPS Static Inverter, however, RWCU does not have isolation bypass capability.
Incorrect - Although an MSlV half isolation signal occurs on a loss of 2B RPS UPS Static Inverter, the MSlVs will remain open. An MSlV isolation can not be bypassed.
Correct Answer - RECW to the Drywell will isolate on a loss of 2B RPS UPS Static Inverter and the isolation can be bypassed.
Req u ired Attachments or Reference Source:
Learning Objective:
Knowledge/Ability:
Reference (s):
New Exam Item LLOTOI 80.8 262002 K3.10 I Importance: 2.7/2.8 E-2BY 1 60 Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 56 L
56 of I00 Unit 1 plant conditions are as follows:
100% reactor power Normal electrical lineup An overtemperature condition occurs on the "1 A" RPSNPS Static Inverter.
WHICH ONE of the following identifies the status of RPS and the power source for the I
AYI 60 panel following the overtemperature condition?
RPS Status lAYl60 Power Source
- a.
"A" Half-Scram Safeguard 250 VDC
- b.
"A" Half-Scram Non-Safeguard 480 VAC
- c.
No Scram Safeguard 250 VDC
- d.
No Scram Non-Safeguard 480 VAC
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
56 I
Choice I Basis or Justification I
- a.
I Incorrect - See "d"
- b.
Incorrect - See "d" C.
Incorrect - See '%I"
- d.
Correct Answer - The RPS UPS Static Inverters are normally powered from Safeguard 250 VDC. On a high temperature condition, the static switch will automatically transfer to the alternate source, a 480 VAC Non-Safeguard MCC. The transfer occurs fast enough that power is not lost to the RPS system.
Required Attachments or Reference L
interlocks which provide for the following: Transfer from preferred power to alternate power supplies.
Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 57 57 of 100 L
L Unit I plant conditions are as follows:
A failure to Scram has occurred "I
B" RPS channel has failed to de-energize T-215, "De-Energization of Scram Solenoids" has been performed Some control rod motion is observed, but power is at 30%
WHICH ONE of the following describes the indications shown by the SPDS "Scram Event Indicator" before fuses are removed and I minute after the RPS fuses are removed?
Before Fuses are Removed I Minute After RPS Fuses are Removed
- a.
BLUE Border Box /
RED Border Box /
No SCRAM SCRAM RODS OUT
- b.
RED Border Box / SCRAM RED Border Box /
RODS OUT SCRAM RODS OUT
- c.
BLUE Border Box /
GREEN Border Box /
No SCRAM SCRAM RODS IN
- d.
RED Border Box / SCRAM YELLOW Border Box /
RODS OUT SCRAM CMD
c Reference (s):
Learning Objective:
Knowledge/Ability:
Limerick Generating Station 2005 NRC Initial Licensing Examination None LLOT0768.4 295037A1.09 I Importance: 2.8 / 3.0 Question#
57 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - SPDS Scram Event Indicator will turn RED with the text SCRAM RODS OUT if both channels of RPS de-energize and all rods do not fully insert Incorrect - SPDS Scram Event Indicator will not turn Red with the text SCRAM RODS OUT if one channel of RPS fails to de-energize.
Incorrect - SPDS Scram Event Indicator will turn Green only if both channels of RPS drop out and all rods are fully inserted.
Incorrect - SPDS Scram Event Indicator will turn Yellow only if both channels of RPS must de-energize and control rods are within 7 seconds of being inserted (scramming in)
Required Attachments or Reference
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 58 L
58 of 100 Unit 2 plant conditions are as follows:
A LOCA has occurred resulting in RPV level dropping below the top of active fuel Drywell pressure is 18 psig and subsequent major fuel damage All automatic actions have occurred.
WHICH ONE of the following will provide accurate indication of offsite release rate?
- a.
Off Gas post treatment Radiation Monitor
- b. South Stack Noble Gas Radiation Monitor
- c.
North Stack Wide Range Accident Radiation Monitor
- d.
Reactor Enclosure Ventilation Exhaust Radiation Monitor
Limerick Generatina Station 2005 NRC Initial Licensina Examination b
I Question #
58 I
Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - RPV level below -129 will result in a Group I isolation and MSlV closure.
With a Group 1 isolation, steam flow through the off gas system will result and off gas radiation monitors will not reflect accurate release rates Incorrect - This would be correct if an isolation signal did not exist and Reactor Enclosure normal supply and exhaust fans were still in service Correct Answer - With drywell pressure greater than I
.68 psig, reactor enclosure ventilation will isolate automatically, and the reactor enclosure will align to SGTS, which exhausts to the North Vent Stack Incorrect - Since normal reactor enclosure exhaust is through the South Vent Stack, this would be correct if an isolation signal did not exist Required Attachments or Reference L
Prepared by: Corey Goff
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 59 L
59 of 100 ATTACHMENT Q59 IS PROVIDED WHICH ONE of the following identifies the power supply for Division I DC loads following the trip of the 1 A I D103 Battery Charger?
- a.
1Al Batteryonly
- b.
1A2D103 Battery Charger only
- c.
1Al and 1A2 Batteries
- d.
1Al Battery and 1A2D103 Battery Charger
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Knowledge/Ability:
Reference( s):
Question #
59 New Exam Item LLOT0690.2 263000 K I.02 I Importance: 3.2/3.3 ARC-MCR-120 G-I, E-33 sh. 1, E-92 Sh. 1 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See "d" Incorrect - See "d" Incorrect - See "d" Correct Answer - The Division I DC Distribution system has 2 batteries and each battery has a battery charger. The battery chargers are the normal source of power for the DC system. With a trip of one of the battery chargers, the associated battery will begin to discharge. The second battery charger will continue to supply the DC bus.
E-92 Sheet 1 Required Attachments or Reference I
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 60 Unit 2 plant conditions are as follows:
L 60 of 100 100% reactor power Normal electrical lineup D22 Diesel Generator is running in standby during performance of ST-6-092-31 2-2, D22 DIESEL GENERATOR SLOW START OPERABILITY TEST RUN A fault de-energizes the Division 2 DC Bus.
WHICH ONE of the following describes the ability to trip the D22 Diesel Generator manually and automatically?
Manually Automatically
- a.
Emergency Stop on
- b.
Emergency Stop on engine only engine only Auto trips enabled Auto trips disabled
- c.
Emergency Stop on local Auto trips enabled
- d.
Emergency Stop on local Auto trips disabled panel only panel only
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1.2)
Question#
60 Choice Basis or Justification
- a.
Incorrect - Auto trips require DC control power.
H PRA (Y/N)
SRO 2
N N
- b.
Correct Answer - Diesel can only be tripped using mechanical trip on engine. Auto trips require DC control power to operate.
Incorrect - Local diesel controls require DC control power.
C.
- d.
Incorrect - See "c" Required Attachments or Reference Source:
New Exam Item Reference(s):
E-33, Load Analysis Learning LLOTO670.10 Objective:
Knowledge/Ability: 263000 K3.01 I Importance: 3.4/3.8 (Description of K&A, fro Knowledge of the effect will have on the following: Emergency generators or malfunction of the D.C. ELECTRICAL DISTRIBUTION Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 61 b
61 of 100 A Recirculation piping break occurs on Unit 1 inside primary containment resulting in RPV level lowering to -140 inches.
WHICH ONE of the following describes the status of the "IA" Instrument Air Compressor and Service Air Compressor?
- a.
- b.
- c.
Both compressors are available without SE-10-1 breaker reset required Both compressors are NOT available until breakers are reset per SE-10-1 "IA" Instrument Air Compressor is available; Service Air Compressor is NOT available until breaker is reset per SE-10-1 Service Air Compressor is available; "IA" Instrument Air Compressor is NOT available until breaker is reset per SE-10-1
- d.
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference( s):
Learning Question #
61 New Exam Item LLOT0730.15 Choice Objective:
Knowledge/Ability:
- a.
300000 K2.01 I Importance: 2.8/2.8
- b.
C.
- d.
L Basis or Justification Incorrect - See justification for d.
Incorrect - See justification for d.
Incorrect - See justification ford.
Correct Answer - "1A instrument air compressor is powered from Dl34-R-H, and Service air compressor is powered from non-safeguard power. Only "IA" Instrument air compressor has a shunt trip relay that trips the breaker on a LOCA signal, and must be manually reset. RPV level lowering to -140 inches will generate a LOCA signal, and the the breaker for "IA" Instrument Air compressor must be reset per SE-10-1 before it can be operated again. The Service Air compressor will remain available after the LOCA signal due to being powered from non-safeguard power and having no shunt tripping mechanism for the breaker.
Required Attachments or Reference I Knowledge of electrical power supplies to the following: instrument air compressor Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 62 Unit 1 initial plant conditions are as follows:
L 20% reactor power Reactor water level +35 inches 62 of 100 A feedwater transient causes RPV level to rise before the RO manually lowers level.
REACTOR FEED PUMP HI LEVEL TRIP RESET light status on 10C603 is as follows:
A not lit B lit C lit D not lit WHICH ONE of the following describes the status of the Main Turbine and RPS Main Turbine RPS
- a.
Tripped Tripped
- b.
Not Tripped Tripped
- c.
Tripped Not Tripped
- d.
Not Tripped Not Tripped
Limerick Generatinu Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
KnowledgelAbility:
Reference(s):
1 Question#
62 New Exam Item LLOTO560.5 295005 AA2.07 I importance: 333.6 ARC-MCR-106 C-I I Choice Basis or Justification Incorrect - see c justification Incorrect - see c justification Correct Answer - Main Turbine will trip due to A or IC and B or ID level trip. RPS will not trip on high level because bypass valves can pass the steam produced at 20% reactor power.
Incorrect - see c justification Required Attachments or Reference
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 63
\\-
Unit I initial plant conditions are as follows:
63 of I00 Reactor power is 80%
RPV pressure is 1027 psig "I
B" Outboard MSlV has failed closed. Current conditions are:
Reactor power is 81 %
RPV Pressure is 1060 and stable One bypass valve is 40% open WHICH ONE of the following describes the required immediate operator action per OT-102, Reactor High Pressure?
- a. Place the Reactor Mode Selector Switch to "SHUTDOWN"
- b.
Raise EHC Pressure Set until all Bypass Valves are fully closed
- c.
Depress Bypass Valve jack "CLOSE" pushbutton to fully close all Bypass Valves
- d.
Reduce Reactor power until RPV pressure is below "REACTOR HI PRESS" setpoint
Limerick Generating Station 2005 NRC Initial Licensing Examination
\\\\
Choice
- a.
Required Attachments or Reference
- b.
C.
- d.
Basis or Justification Incorrect - Scram is not required, or desired at this time, since no RPS scram setpoints have been exceeded.
Incorrect - Raising EHC pressure set will not lower RPV pressure to below 1053, as is required by OT-102. OT-102 does not direct the operator to close the BPVs. They are open to help control pressure.
Incorrect - Bypass valves cannot be closed using the jack, if they were not opened by the jack. OT-102 does not direct the operator to close the BPVs. They are open to help control pressure.
Correct Answer - OT-102, Reactor High Pressure, includes as an immediate operator action: REDUCE Reactor power in accordance with GP-5, Steady State Operations, AND Reactor Maneuvering Shutdown instructions to maintain Reactor pressure less than 1053 psig.
Source:
New Exam Item Learning LLOTl540.02 Reference(s):
OT-1 02 Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination L Question: 64 64 of 100 Unit I plant conditions are as follows:
Reactor Mode Switch is in "STARTUP" Shutdown Margin demonstration is in progress Shorting links are removed SRM's indicate the following:
" A SRM 1.4~1 O3 cps "B" SRM 6.4~1 O4 cps "C"
SRM 5. 3 ~ 1 0 ~
cps "D" SRM 2. 4 ~ 1 0 ~
cps
" A SRM detector output fails to 25x1 O5 cps.
WHICH ONE of the following describes the RPS Status based on the above conditions?
- a.
- b.
- c.
- d.
Only "A" RPS de-energized (half-scram)
Only *'B RPS de-energized (half-scram)
Both "A" and "B" RPS de-energized (full scram)
Neither "A" nor "B" RPS de-energized (no half or full scram) u
Limerick Generating Station 2005 NRC Initial Licensing Examination
- a.
- b.
C.
Question #
64 Choice 1 Basis or Justification Incorrect - see c justification Incorrect - see c justification Correct Answer - With the shorting links removed one SRM channel Trip/lNOP will cause a full scram. One SRM indicating greater than 2x1 O5 will cause the SRM to be
- d.
be upscale, and cause a full scram.
Incorrect - see c justification I
Required Attachments or Reference Cognitive (H, L)
Unit (I,
- 2)
H PRA (Y/N)
SRO 1
N N
Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR (SRM)
SYSTEM will have on the following: RPS Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination L Question: 65 65 of I00 Unit 1 plant conditions are as follows:
RPV level is -1 50 inches and slowly lowering There are no RPV injection sources available All control rods are fully inserted WHICH ONE of the following describes the earliest point at which an Emergency Blowdown will be performed per T-I 12, "Emergency Blowdown" and the reason for not performing an Emergency Blowdown until that point?
- a. -186 inches; Adequate core cooling is maintained
- b. -201 inches; Delays the emergency depressurization as long as possible
- c.
-186 inches; Fuel cladding temperature is maintained below 1800 deg. F
- d.
-201 inches; 213 core coverage is still maintained
L Source:
Reference(s):
Learning Objective:
Knowledge/Ability:
Limerick Generating Station 2005 NRC Initial "Licensing Examination New Exam Item T-I 11 and T-I 1 I Bases LLOTI 560.05 295031 EK3.04 1 Importance: 4.0/4.3 Question#
65 Choice 1 Basis or Justification
- a.
Incorrect - See justification for b.
- b.
C.
Correct Answer - With no RPV injection, when RPV level lowers to below -161 inches, the steam cooling section of T-I 1 I is entered. Fuel PCT does not exceed 1800 deg. F. until RPV level is below -201 inches, at which time T-I 11 step LR-I6 directs leaving Steam Cooling and performance of an emergency depressurization.
The bases for T-I I 1 states: "The steam cooling strategy thus delays emergency RPV depressurization for as long as possible.
Incorrect - See justification for b.
- d.
Incorrect - See justification for b.
Required Attachments or Reference
Limerick Generating Station I
2005.NRC Initial Licensing Examination Question: 66 b
66 of I00 L
Unit I plant conditions are as follows:
"IA" RHR loop is operating in Shutdown Cooling mode SHUTDOWN range RPV level currently indicates +50 inches UPSET range RPV level currently indicates +60 inches WHICH ONE of the following describes the action that will ensure natural circulation is established if the "IA" RHR pump trips and the reason for this action?
Action Reason for the Action
- a.
Raise RPV level to +65 inches on SHUTDOWN range Raise RPV level to +75 inches on UPSET range Raise RPV level to +65 inches on SHUTDOWN range Raise RPV level to +75 inches on UPSET range Ensures water level above steam separator turnaround point Ensures water level above steam separator turnaround point Ensures water level above top of jet pump ram's head Ensures water level above top of jet pump ram's head
- b.
- c.
- d.
L C.
- d.
Limerick Generating Station 2005 NRC Initial Licensing Examination Incorrect - 65 inches on SHUTDOWN is okay, but the top of the jet pump ram's head is not the reason, and would not promote natural circulation.
Incorrect - 75 inches on UPSET range does not meet the requirements of S51.8.B, and water level at the top of the jet pump ram's head would not promote natural circulation.
Question#
66 Choice I Basis or Justification Reference(s):
Learning
- a.
- b.
S51.8.B, precautions 3.3,3.4 LLOT0370.09 Correct Answer - S51.8.B, precaution 3.3 states that I' Maintaining vessel level above 60 inches on LI-42-*R605 at "OC602 OR 78 inches on LR-42-*R608 at OC603 will ensure proper natural circulation."
LI-42-R605 is the SHUTDOWN level indicator, and LR-42-*R608 is the UPSET recorder. This ensures water level is above the turnaround point in the steam separators, which allows warm water that travels upward through the core to pass over to the downcomer, helping to establish a natural circulation flowpath.
Incorrect - 75 inches on UPSET range does not meet the requirements of S51.8.B.
Required Attachments or Reference I Source:
I New Exam Item J
tween PARTIAL OR COMPLETE LOSS OF FORCED Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination
'c Question: 67 Unit 2 plant conditions are as follows:
An ATWS is in progress Reactor power is 3%
67 of I00 All three SLC pump control switches have just been taken to "START" at 20C603.
WHICH ONE of the following describes the response of the Standby Liquid Control System?
- a.
- b.
- c.
All three SLC pumps start immediately All three SLC pumps starts after a I 1 8 second time delay Ail three SLC pumps will start immediately IF reactor power rises to 4%
- d.
All three SLC pumps will start 118 seconds IF reactor power rises to 4%
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
67 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - If the control switch is actuated to start a SLC pump, the 4% power requirement and the 118 second time delay do not apply.
Incorrect - See justification for a.
Incorrect - See justification for a.
Incorrect - See justification for a.
Required Attachments or Reference Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: System initiation upon operation of SBLC control switch Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination L
Question: 68 68 of 100 Unit 2 plant conditions are as follows:
An ATWS is in progress with power at 5%
T-270 has been completed in the MCR and Aux. Equipment Room RPV pressure is 500 psig and slowly lowering Drywell pressure is 8.0 psig and slowly rising RPV level is -60 inches and steady WHICH ONE of the following describes the automatic response of the Core Spray system if RPV pressure lowers to 400 psig?
Core Spray Pumps Core Spray Injection Valves
- a.
Start Open
- b.
Will not start Open
- c.
Start Will not open
- d.
Will not start Will not open
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1, 2)
Question#
68 L
PRA (Y/N)
SRO 2
Y N
Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for d.
Incorrect - See justification ford.
Incorrect - See justification ford.
Correct Answer - With T-270 completed in the AER, a LOCA signal (>I
.68 psig dw pressure with less than 455 psig RPV pressure) will not automatically start the Core Spray pumps, or open the injection valves.
I I
I Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 69 Unit I plant conditions are as follows:
b L'
69 of 100 A Group I isolation occurred I O minutes ago The reactor is shutdown and RPV pressure is 950 psig and lowering slowly HPCl has been manually placed in service for level and pressure control RPV level is +30 inches and steady No other injection sources are operating The HPCl flow controller fails and will not control in "AUTO and is placed in "MANUAL". No other operator actions are taken.
WHICH ONE of the following describes the HPCl parameter directly controlled and the effect on RPV level over the next thirty minutes?
HPCl Parameter Directly Controlled RPV Level Response
- a.
flow remains steady
- b.
flow rises
- c.
speed remains steady
- d.
speed rises
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
Question#
69 Basis or Justification Incorrect - See justification ford.
- b.
C.
Incorrect - See justification for d.
Incorrect - See justification ford.
- d.
Required Attachments or Reference Correct Answer - With the HPCl controller in MANUAL, the controller will maintain HPCl pump speed constant. Since RPV pressure is lowering, and HPCl speed (and therefore discha pressure) remain constant, flow into the RPV will rise, causing RPV level to rise.
or malfunction of the HIGH PRESSURE COOLANT Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 70 i/
70 of 100 Unit 1 plant conditions are as follows:
Conditions exist requiring entry into T-I 12, Emergency Blowdown RPV pressure is 1000 psig All five ADS valves have just been opened by the Plant Reactor Operator WHICH ONE of the following describes the RPV level instrument response in the first five (5) seconds after the ADS valves are opened and the reason for this response?
Level Instrument Response Reason L
- a.
- b.
C.
- d.
Indicated RPV level rises Indicated RPV level rises Indicated RPV level lowers Indicated RPV level lowers Pressure drop in the reactor causes more void production in the core Lower pressure felt in the level instrument reference legs Valve opening causes more inventory loss from the RPV Lower pressure felt in the level instrument variable legs
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Opening the ADS valves causes a rapid reduction in pressure, causing rapid void production, and causing water to be displaced into the downcomer, causing indicated level to rise.
Incorrect - While level will rise, the pressure change in the reactor will be felt equally on both the variable and reference legs of the instruments, and therefore will not result directly in a change in indicated RPV level.
Incorrect - RPV level will not initially lower Incorrect - RPV level will not initially lower, and the pressure change in the reactor will be felt equally on both the variable and reference legs of the instruments, and therefore will not result directly in a change in indicated RPV level.
Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 71 L
Unit 1 plant conditions are as follows:
71 of 100 Rx power 100%
1AY160 has de-energized due to a fault 5 minutes ago Drywell temperature has risen 8 O F since the loss of lAY160.
WHICH ONE of the following describes the primary reason for the rise in drywell temperature?
- a.
RECW pump trip
- b. RECW system isolation
- c.
Drywell Chiller compressor trip
- d. Drywell Chilled Water system isolation
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
71 Choice 1 Basis or Justification
- a.
- b.
C.
- d.
Incorrect - Loss of 1AY160 will not cause an RECW pump trip.
Incorrect - RECW will isolate, but does not have a significant impact on drywell temperature.
Incorrect - Drywell chiller compressor will not receive a trip signal from a loss of 1 AY I
- 60.
Correct Answer - Loss of 1AY160 will cause DWCW isolation which will cause DW temp increase.
Attachments or llowing responses as they apply to INADVERTENT CONTAINMENT ISOLATION: Drywelkontainment temperature response Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination L Question: 72 72 of 100 Unit 1 plant conditions are as follows:
Plant startup in progress at 8% reactor power Reactor Mode Switch is in "STARTUP/HOT STANDBY" Control Rod 26-15 is at position I 2 and is the selected rod Control Rod 26-15 has as an Insert Limit of I 2 and a Withdraw Limit of 48 All other control rods are at their desired positions WHICH ONE of the following describes the indications and/or interlocks currently displayed by the Rod Worth Minimizer?
Insert Error Insert Block
- a.
No No
- b.
No Yes
- c.
Yes No
- d.
Yes Yes
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (I,
- 2)
Question#
72 L
PRA (Y/N)
SRO I
N N
Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for b.
Correct Answer - with a control rod at its insert limit, the RWM will pre-block and provide an insert block. It will beyond its insert limit.
Incorrect - See justification for b.
Incorrect - See justification for b.
provide an insert error, since the rod is not inserted Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination i/ Question: 73 73 of I00 Unit 1 plant conditions a 50% reactor power Both Reactor Recirculation Pumps are operating at approximately 60% speed An inadvertent low speed runback occurs on the I B Reactor Recirculation Pump MG set, resulting in the following conditions:
1 B Reactor Recirculation Pump MG set manual control station output meter reads 50%
Recirculation Pump MG set SPEED meter indicates 28%
An operator has been directed to lower 1 B MG set speed demand using the LOWER pushbutton at the manual control station.
WHICH ONE of the following describes the Reactor Recirculation Pump MG set manual control station output meter indicated value where 1B MG set speed will begin to lower?
- a.
28%
- b. 20%
L
Limerick Generating Station 2005 NRC Initial Licensing Examination Learning 0 bjective:
Knowledge/Ability:
Question #
73 Choice Basis or Justification
- a.
Incorrect - 28% on the output meter will only reduce speed demand to about 42%,
which is the speed limit for the high speed runback Incorrect - 20% on the output meter will only reduce speed demand to about 36%.
- b.
LLOT0040.14 202002 K3.05 I Importance: 3.2/3.3 C.
Correct Answer - 10% on the output meter (scale of 0-1 00) equates to about 28%
speed on the SPEED meter (scale of 20-100).
Incorrect - 4% on the output meter will reduce speed demand to about 23.2%, which is not the earliest point where a speed change will be observed.
- d.
Required Attachments or Reference I
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 74 b
ATTACHMENT Q74 IS PROVIDED Unit 2 plant conditions are as follows:
74 of 100 100% reactor power Main Generator output is 1175 MWe Main Generator reactive load is 240 MVAR with a power factor of 0.98 Main Generator hydrogen pressure is 75 psig The Power System Director requests maximum MVAR that can be provided by the generator without reducing MWe output.
WHICH ONE of the following describes the maximum MVAR output permitted?
- a.
250
- b.
395
- c.
470
- d.
560 u
Limerick Generating Station 2005 NRC Initial Licensing Examination Required Attachments or Reference GP-5, Attachment 5 (Estimated Generator Capability Curve at Various Hydrogen Gas Pressures)
Prepared by: Craig Frit
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 75 75 of 100 ATTACHMENT Q75 IS PROVIDED Unit 2 plant conditions are as follows:
A valid RWCU system isolation has occurred due to a low RPV level condition RPV level has been restored to +35 inches WHICH ONE of the following describes the required actions per GP-8 to realign the RWCU system for operation?
- a.
Perform an R I reset and ensure the isolation valves automatically reopen
- b. Perform an R2 reset and ensure the isolation valves automatically reopen
- c.
Perform an R I reset and manually reopen the isolation valves from the MCR
- d. Perform an R2 reset and manually reopen the isolation valves from the MCR
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see justification ford.
Incorrect - see justification for d.
Incorrect - see justification ford.
Correct Answer - The low level isolation setpoint for RWCU is -38 inches, or lo-lo level. Using GP-8, this is isolation signal "8".
GP-8 also shows the reset for this isolation signal to be an "R2" reset. Following the reset, the isolation valves must be manually reopened using the MCR handswitches to realign the system for operation.
Required Attachments or Reference GP-8 (U/2) (Do not give GP-8.1, 8.2, 8.3,8.4, or 8.5)
I Ability to manually operate and/or. monitor in the control room: Reset system isolations Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 76 l-.-,
76 of 100 Unit 1 plant conditions are as follows:
Reactor mode switch is in "STARTUP" Reactor pressure 940 psig Reactor power 3%
HPCl is in full flow test CST to CST for ST-6-055-230-1, HPCl Pump, Valve and Suppression Pool Temperature is 97°F and rising slowly Flow test WHICH ONE of the following describes required actions, if any, per Tech Specs for the conditions above?
- a.
- b.
C.
- d.
L No action until average Suppression Pool temp exceeds 105°F Restore the average Suppression Pool temp I 95°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Secure HPCl and lower average Suppression Pool temp 595°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Limerick Generating Station 2005 NRC Initial Licensing Examination 0 bjectiie:
Knowledge/Ability:
Question #
76 295026 Generic 2.23 I Importance: 3.8 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Per TS 3.6.2.1 Suppression Pool temperature limit is 105°F when performing a test that adds heat to the Suppression Pool. Testing is not required to be secured until 105°F in the Suppression Pool.
Incorrect - see a justification Incorrect - see a justification Incorrect - see a justification Tech Specs Required Attachments or Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 77 u
77 of 100 Unit 1 initial plant conditions are as follows:
100% reactor power "1 B" CRD pump is in service CST level is 32.6 ft "B" CRD Flow Control Valve is in service The following annunciators have alarmed:
I08 REACTOR G-I, " I N I B CRD WATER PUMP TRIP" 108 REACTOR G-3, " I N I B CRD PUMP SUCTION LO PRESS" 108 REACTOR H-4, "CRD CHARGING WATER LO PRESS" WHICH ONE of the following describes the action required prior to restoring CRD operation?
- a.
Raise CST le above 33 feet per S08.0.C, Transferring Water Between the RWST and the CST
- b. Place altern Placing Alte RD Drive Water Filter in service per S46.6.Cy Control Rod Drive Water Filter in Service
- c.
Open 46-IF0 ump Suction Filter Bypass Valve" per ON-L ive System Problems
- d.
Place FV-46-1 F002Ay "A CRD Flow Control Valve" in service per S46.6.By Placing Alternate CRD Hydraulic System Flow Control Valve in Service
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - Raising CST level will not allow restart of the CRD pump, because CST level was not low enough to be the cause of the trip. CST must be at or below 29 ft.
to cause the CRD pump to trip.
Incorrect - inadequate flow through the CRD drive water filters may cause an alarm, but will not cause the CRD pump to trip.
Correct Answer - Conditions that cause annunciator 108 REACTOR G-3,"INl B CRD PUMP SUCTION LO PRESS" to alarm will also cause the CRD pump to trip.
ON-1 07, step 2.2.1 directs opening the suction filter bypass valve (46-1 F045) and restarting the pump.
Incorrect - Placing the alternate CRD flow control valve in service will not allow the pump to be restarted. This action would only be correct if the conditions indicated a failed flow control valve, or if drive flow was insufficient.
Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination L Question: 78 78 of 100 Unit 2 plant conditions are as follows:
OPCON 4 "2B" RHR is in Shutdown Cooling per 331.8.8, Shutdown Cooling/Reactor "OB" RHRSW Pump is in service Reactor coolant temperature is 190°F and slowly lowering Coolant Circulation Operation Start-up And Shutdown An electrical fault causes a loss of the 20 Station Aux Bus.
WHICH ONE of the folio required action to restore cooling?
g describes the effect on "2B" RHR Shutdown Cooling and the
- a.
- b.
u C.
- d.
Effect on '28" RHR Shutdown Cooling Required Action RHR Pump trips and can not be restarted Start "2A" RHR in Shutdown Cooling mode per S51.8.B, Shutdown Cooling/Reactor Coolant Circulation Operation Start-up and Shutdown Remains in service without heat exchanger cooling water RHR Pump trips and can not be restarted Remains in service without heat exchanger cooling water Start "OA" RHRSW Pump per S12.1.A, RHR Service Water System Startup Start "2D" RHR pump in Shutdown Cooling mode per S51.8.H, Use Of Dedicated LPCl Pumps For Shutdown Cooling/Reactor Coolant Circulation Operation (Startup And Shutdown)
Start "OD" RHRSW Pump per S12.1.A, RHR Service Water System Startup
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference( s):
Learning Objective:
Knowledge/Ability:
Question#
78 New Exam Item S51.8.B, S12.1.A LLOTO400.06 205000 A208
] Importance: 3.5 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect. "2B" RHR Pump is powered from D22 through the I01 Safeguard Bus and is not affected by a loss of the 20 Station Aux Bus. Loss of D12 will cause a trip of OB^^ RHRSW Pump.
Incorrect. While it is true that "2B" RHR will remain in service without heat exchanger cooling, starting "OA" RHRSW Pump will not support "2B" Shutdown Cooling since it can only be aligned to the "2A" RHR Heat Exchanger.
Incorrect. See "a".
Correct Answer - A loss of 20 Station Aux Bus will cause a loss of 201 Safeguard Bus and a loss of D12 until Dead Bus Transfer to the 101 Safeguard Bus occurs.
This will trip the "OB" RHRSW Pump. "2B" Shutdown Cooling will remain in service without heat exchanger cooling. "OD" RHRSW can be aligned for cooling "2B" RHR Heat Exchanger.
Required Attachments or Reference
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 79 Unit 1 plant conditions are as follows:
L 79 of I00 OPCON 5 with fuel handling in-progress The LSRO on the refueling platform reports that a fuel bundle is being lowered into the core While the bundle is being lowered, the RO reports that SRM "1 B" count rate has risen from 230 cps to 475 cps.
WHICH ONE of the following describes the ability to continue lowering the bundle and what procedure provides guidance for the action?
- a.
- b.
L C.
- d.
Ability to continue lowering the bundle into the core Continued lowering of the bundle is permitted Continued lowering of the bundle is permitted Bundle lowering may not continue until cou ntrate stabilizes Bundle lowering may not continue until cou ntrate stabilizes Procedure Guidance In ON-120, "Fuel Handling Problems FH-105, Core Component Movement - Core Transfers ON-I 20, "Fuel Handling Problems FH-105, Core Component Movement - Core Transfers
'L Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
79 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for d.
Incorrect - See justification for d.
Incorrect - See justification for d.
Correct Answer - Since SRM countrate doubled once, per FH-I05 step 3.7.4 lowering of the bundle must stop until countrate stabilizes at a value of less than 2 doublings, and no spiking or indication of SRM inoperability exists, then lowering the bundle may be continued. ON-I20 entry is only required if SRM countrate doubles twice (i.e. one doubling would be from 230 to 460, a second doubling would be from 460 to 920)
Required Attachments or Reference Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 80 80 of I00 ATTACHMENT Q80/Q91 IS PROVIDED i/
Unit 1 plant conditions are as follows:
A steam leak exists in the outboard MSlV room has actuated Security reports the blowout panel from the steam chase to the North Stack area Reactor has been manually scrammed and all rods are full in Field Team Monitoring reports TEDE is 200 mrem/hr at the site Boundary and is expected to continue for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> All efforts to isolate the steam leak have failed Outboard MSlV room temperature is 180°F and steady No other areas are exceeding Maximum Safe Operating (MSO) Temperatures WHICH ONE of the following identifies the TRIP procedures that require entry and if a T-I 12 Emergency Blowdown is required?
TRIP Procedure Entry T-112, Emergency Required Blowdown Required
- a.
L/-
- b.
C.
- d.
T-I 03, Secondary Containment Control AND T-I 04, Radioactivity Release Control T-I 03, Secondary Containment Control, only T-I 03, Secondary Containment Control AND T-I 04, Radioactivity Release Control T-I 03, Secondary Containment Control, only Yes Yes No No
Limerick Generating Station 2005
,. - NRC Initial Licensing Examination Source:
Learning 0 bjective:
Knowledge/Ability:
Reference ( s ):
Question #
80 I
New Exam Item LLOTI 560.026 Generic 2.4.1 I Importance: 4.6 EP-AA-1008, T-I 03, T-I 04 Choice
- a.
- b.
C.
- d.
Basis or Justification I
Incorrect - see justification for c Incorrect - see justification for cy Correct Answer - Site boundary release is at a Site Area Emergency, therefore entry into approaching a General Emergency limit and 2 areas are not exceeding MSO, therefore T-I 12 not required.
tncorrect - see justification for c T-I 04 is required per LGS EAL annex Table 3-1. Release level is not at or Required Attachments or Reference LGS 3-1 : Emergency Action Level (EAL) Matrix T-I 03 T-I 04 I
Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 81 L,
81 of 100 Unit 1 plant conditions are as follows:
100% reactor power Normal electrical lineup A 220 W Substation fault results in a Main Generator Lockout and loss of the 10 Station Aux Transformer. All automatic actions occur as designed.
WHICH ONE of the following describes the change, if any, in reactor pressure and level I O seconds after the lockout and the procedural action required to mitigate this effect?
- a.
- b.
C.
b
- d.
Change in Reactor Pressure and Level 10 seconds after Lockout Reactor pressure and level will both be lower Procedural Action Required to Mitigate Effect Restore and maintain RPV level between
+ I 2 5 to 54 inches per T-101, RPV Control Reactor pressure will remain the same Restore and maintain RPV level between and reactor level will be lower
+I 2.5 to 54 inches per T-I 01, RPV Control Reactor pressure and level will both be Restore reactor level to +35 inches by lower manually controlling Reactor Feedwater Pumps per OT-I 00, Reactor Low Level Restore reactor level to +35 inches by manually controlling Reactor Feedwater Pumps per OT-I 00, Reactor Low Level Reactor pressure will remain the same and reactor level will be lower
c Cognitive (H, L)
Unit (I, 2)
Limerick Generating Station 2005 NRC Initial Licensing Examination H
PRA (Y/N)
SRO 1
Y 1 OCFR55.43.b.5 Question #
81 Source:
Learning Reference( s ) :
Choice New Exam Item LLOT0640.06 E-Dl 1, E-I 0
- a.
0 bjective:
Knowledge/Ability:
- b.
295003 A2.02 I Importance: 4.3 C.
- d.
Basis or Justification Correct Answer - A Generator Lockout will initiate a Main Turbine Trip and subsequent Reactor Scram if power is above 30%. Reactor Pressure will drop immediately on the scram due to void reduction. Digital Feedwater Scram Profile will initiate on the valid scram signal which will run feed flow back to 10% 5 seconds after the scram. RPV level control in T-101 Incorrect - Reactor pressure will drop following the scram.
Incorrect - When the scram occurs, level control must be directed from T-I 01.
Incorrect - Reactor pressure will drop following the scram and level control must be directed from T-IO1 following the scram.
Required Attachments or Reference Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 82 L
82 of I00 ATTACHMENT Q82 IS PROVldED Unit 2 is in OPCON 4 with the following conditions:
The reactor has been shutdown for 20 days "2A" RHR pump is operating in Shutdown Cooling Mode "28" RHR pump is inoperable RPV water temperature is currently 140 deg. F Reactor water level is being lowered following installation of the RPV Head An automatic inadvertent isolation of HV-51-2F008 occurs due to the "D" RPV pressure detector failing high.
WHICH ONE of the following describes required operator action, and the estimated minimum time before RPV temperature rises to 212 OF?
Required Action Time to 212°F
- a.
Perform Attachment 4 of ON-121, and 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />
- b.
Reset Isolation per GP-8, and restore 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> restore Shutdown Cooling Shutdown Cooling L
- c.
Perform Attachment 4 of ON-121, and 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> restore Shutdown Cooling Shutdown Cooling
- d.
Reset Isolation per GP-8, and restore 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />
Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
82 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for b.
Incorrect - See justification for b.
Correct Answer - With SDC will be lost due to an inadvertent isolation, ON-I21 must be entered. Using ON-121, Attachment 9, for a starting temperature of 140 deg. F, with the plant shutdown for 20 days the time to boiling would be about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.
Reset of isolation per GP-8 can not be performed because the isolation signal is still present.
Incorrect - See justification for b.
Required Attachments or Reference ON-I21 Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 83 83 of I00 L
Unit 2 initial plant conditions are as follows:
2 SRV is stuck open Reactor Power is 50% with an A W S in progress An EHC malfunction results in Reactor pressure at 870 psig and dropping Suppression Pool level 20 feet and stable Suppression Pool temperature 170°F and rising Suppression Pool pressure 10 psig and rising 2H SRV closes and reactor pressure rises to I 100 psig.
WHICH ONE of the following describes required actions for the conditions above?
- a.
- b.
C.
b
- d.
urize using Turbine Bypass Valves per T-I 01, RPV eactor pressure above 1096 psig Enter T-I 12, Emergency Blowdown, due to unsafe on PC/P-3 PRESS SUPP PRESS curve in T-102, Primary Containment Control Enter T-112, Emergency Blowdown, due to unsafe on SPA--I HEAT CAPACITY TEMP LIMIT curve in T-102, Primary Containment Control Reduce reactor pressure per T-101, RPV Control to maintain on the safe side of SPA--1 HEAT CAPACITY TEMP LIMIT curve in T-102, Primary Contai ment Control, due to reactor pressure above 1096 Psig
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - T-I 12, Emergency Blowdown is required due to exceeding SP/T-1 curve in T-102. T-I 01, step RC/P-1 states to exit RC/P leg if T-I 12 is required.
Incorrect - At 20 feet Suppression Pool Level and Suppression Pool Pressure at 10 psig, PC/P-3 Press Supp Press curve in T-I02 has not been exceeded.
Correct Answer - T-I 12, Emergency Blowdown is required due to exceeding SP/T-I curve in T-102. T-102 Bases does not allow reduction of Reactor Pressure to stay on safe side of curve if initial assessment of SP/T-I curve parameters indicate unsafe side has been entered.
incorrect - See justification for "c".
Required Attachments or Reference T-IO1, T-102 (Description of K&A, from catalog)
Knowledge of EOP imple Low Suppression Pool W tation hierarchy and coordination with other support procedures:
Prepared by: Tim Kan
Y/'
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 84 L
84 of 100 The following has occurred on Unit 1 :
A feedwater level control malfunction has caused RPV level to "1 B" and "1 C" RFPs failed to trip and were tripped manually by the RO The Reactor Mode switch has been placed in "SHUTDOWN" All other automatic plant functions have occurred as designed.
No other operator actions have been taken
. rise to +I30 inches "1A RFP has tripped Current plant conditions are as follows:
All control rods are fully inserted RPV level is +I24 inches and lowering slowly RPV pressure is 1060 psig and steady All SRVs are operable WHICH ONE of the following describes the proper directions to give the RO/PRO for RPV pressure control?
- a.
Immediately reduce RPV pressure below 1053 psig using the Jack to open Bypass Valves per OT-102, "Reactor High Pressure" Immediately reduce RPV pressure below 1053 psig using Pressure Set to open Bypass Valves per OT-102, "Reactor High Pressure" When RPV pressure reaches 1096 psig, then reduce pressure using "1 J" SRV per OT-I 10, "Reactor High Level" When RPV pressure reaches 1096 psig, then reduce pressure using "1 K" SRV per OT-I I O, "Reactor High Level" u
- b.
- c.
- d.
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Reference( s):
Question#
84 New Exam Item LLOTI 540.05 OT-I 02, OT-I 10 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - White 01-102 does direct reducing pressure to below 1053 psig, since the reactor is scrammed, OT-102 is no longer appropriate. Also, using BPVs with RPV level above the I I of the main steam lines will jeopardize integrity of the BPV lines to the condenser.
Incorrect -While OT-102 does direct reducing pressure to below 1053 psig, since the reactor is scrammed, OT-102 is no longer appropriate. Also, using BPVs with RPV level above the level of the main steam lines will jeopardize integrity of the BPV lines to the condenser.
Correct Answer - With RPV level at +I24 inches, the Main Steam lines are covered, and will be full (MSIVs do not automatically close on high level, and therefore are still open). OT-I10 step 3.17 directs: IF Main Steam lines are flooded AND RPV pressure reaches 1096 psig, THEN perform the following: IF the B, C, OR J SRV is available, THEN manually cycle the 6, C, OR J SRV to reduce/maintain RPV pressure below 700 psig.
Incorrect - This is incorrect, because if B, C, or J SRV is available, they are to be used for the sustained opening for depressurization to below 700 psig because they have straight tailpipe runs through the suppression pool airspace and are therefore less likelv to be broken in that area.
L Required Attachments or Reference terpret the following as they apply to HIGH REACTOR WATER Prepared by: Craig Fritz u
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 85 L
85 of 100 Unit 1 is at 100% Power when the following occurs:
A Feedwater transient results in the following:
RPV level dropped to -45 inches HPCl and RClC started and recovered level to +35 inches Reactor Scram WCS reports that Drywell Chilled Water has isolated with the following indications:
Drywell Temperature 140° F
.Drywell Pressure 0.7 psig WHICH ONE of the following describes the cause of the isolation (Valid or Inadvertent) and the effect on Drywell Pressure?
L Cause of the Isolation
- a.
Valid
- b.
Inadvertent
- c.
Valid
- d.
Inadvertent Effect on Drywell Pressure Will remain constant until GP 8.5, Isolation Bypass of Crucial Systems is performed Will rise until GP 8.5, Isolation Bypass of Crucial Systems is performed Will rise until GP-8.3, Isolation Reset is petformed Will remain constant until GP-8.3, Isolation Reset is performed
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
85 Choice
- a.
C.
Basis or Justification Incorrect - See b justification Correct Answer - Isolation is inadvertent DWCW isolates on Drywell pressure of I
.68 psig or RPV level of -129 inches. Inadvertent isolation can be bypassed using GP-8.5. With DWCW isolated, Drywell Pressure and temperature will continue to rise.
Incorrect - See b justification.
Incorrect - See b justification.
- d.
Required Attachments or Reference Prepared by: Tim Kan
Limerick Gene rating Stat ion 2005 NRC Initial Licensing Examination Question: 86 L
86 of 100 ATTACHMENT Q86 IS PROVIDED Unit I is at 100% reactor power.
A loss of power de-energizes solenoid valves SV-59-l50Ay N2 Supply to ADS Sys and SV 152A, Long Term N2 Supply To ADS System.
WHICH ONE of the following identifies the effect on the H, M and S SRVs and the action required to mitigate this effect?
Effect on H, M and S SRVs
- a.
Partial loss of N2 Supply
- b.
Total loss of N2 Supply
- c.
Partial loss of N2 Supply
- d.
Total loss of Nz Supply Action Required to Mitigate the Effect Ensure Instrument Gas Bottle 1AS252 aligned to supply SRVs per S59.8.A, Placing Automatic Depressurization System Backup Nitrogen Supply System In Operation Ensure Instrument Gas Bottle 1AS252 aligned to supply SRVs per S59.8.A, Placing Automatic Depressurization System Backup Nitrogen Supply System In Operation Align Diesel Generator Starting Air Receiver 1 A 1 T558 to supply SRVs per SE-1-1, Protected Depressurization Control (Long Term Operation)
Align Diesel Generator Starting Air Receiver 1 A1 T558 to supply SRVs per SE-1-1, Protected Depressurization Control (Long Term Operation)
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1.2)
Question#
86 H
PRA (Y/N)
SRO I
N 1 OCFR55.43.b.5 Choice
- a.
C.
- d.
Basis or Justification Correct Answer - SV-59-15OA failing closed will only affect one source of NZ to the H, S and M SRVs since each SRV can be supplied through two different supply lines.
Backup Nitrogen bottles can be aligned through the SV-59-152A which fails open on a loss of power.
Incorrect - See justification for a.
Incorrect - SE-1-1 will align Diesel Generator Starting Air Receiver to operate the C, A, N SRVs from the Remote Shutdown Panel.
Incorrect - See justification for c.
M-59 Sheet I Required Attachments or Reference I
I i/
Source:
I New Exam Item Reference(s):
M-59, S59.8.A, SE-1-1 Learning LLOT0730.13,14 0 bjective:
Knowledge/Ability: 21 8000 A2.03 I Importance: 3.6 (Description of K&A, from catalog)
Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) base se predictions, use procedures to correct, control, or mitigate the consequences of th valves normal conditions or operations: Loss of air supply to ADS Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 87 87 of 100 L
Unit 2 plant conditions are as follows:
100% reactor power RCIC blocked for turbine governor maintenance The following sequence of events occur:
1O:OO Hotwell leak results in loss of Condensate and Reactor Scram on Reactor low level 1O:Ol HPCl starts on Reactor Level 2 10:02 "B" Recirc suction line ruptures 10:04 A HPCl Isolation occurs on High Room Temperature due to steam leak 10:06 Station Blackout occurs WHICH ONE of the following identifies the type of HPCl isolation that will occur and the procedural direction that will allow bypassing the isolation to re-inject with HPCI?
Type of HPCl Isolation Procedural Direction That Will Allow Isolation Bypass
- a.
L
- b.
C.
- d.
Outboard only Inboard and Outboard Outboard only Inboard and Outboard Isolation can be bypassed with Reactor Level HPCVRCIC Isolation Logic Isolation can be bypassed with Reactor Level -161" per T-242, Defeat of HPCVRCIC Isolation Logic Isolation can be bypassed with Reactor
'Level < I 2.5 " per T-249, HPCllRClC High Area Temperature Isolation Bypass
-161" per T-242, Defeat of Isolation can be bypassed with Reactor Level 42.5 per T-249, HPCI/RCIC High Area Temperature Isolation Bypass
Limerick Generating Station 2005, NRC Initial Licensing Examination Required Attachments or Reference L
I Question #
87 I
T-I 01 T-I I 1
/Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - On a valid HPCl Isolation, both Inboard and Outboard Isolation Valves will close.
Correct Answer - An Inboard and Outboard Isolation will occur on a valid HPCl Room High Temperature. Per T-I 11, if Reactor Level drops below -1 61" and no system are injecting into the vessel, the Steam Cooling leg will direct bypassing the isolation per Incorrect - On a valid HPCl Isolation, both Inboard and Outboard Isolation Valves will close.
Incorrect - Although T-I 01 will direct performance of T-249 to bypass the HPCl isolation, a prerequisite for performing T-249 is that it can not be performed if a steam leak is known to exist in the HPCl or RClC room.
T-242.
Source:
New Exam Item Learning tLOT0340.07, LLOTI 561.04 0 bjective:
Knowledge/Ability: 206000 A2.10 1 Importance: 4.1 (Description of K&A, from catalog)
Referencets):
T-I 01, T-I 1 I
, T-242, T-249 Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 88 L
88 of I00 Unit 1 plant conditions are as follows:
OPCON 5 with Fuel Shuffle Part 2 in progress D12 Diesel Generator is blocked for Lube Oil Heat Exchanger repair D14 Diesel Generator Fuel Transfer Pump Motor Replacement in progress D14 Diesel Generator Day Tank level is 150 gallons D14 Diesel Generator Fuel Storage Tank level is 32,000 gallons Maintenance requests a clearance application for the D13 Diesel Generator Air Start Receiver 1 C1 T558 to replace relief valve PSV-020-128C-1.
WHICH ONE of the following will permit removal of D13 Diesel Generator Air Start Receiver 1 ClT558 from service without requiring LCO entry?
- a.
- b.
C.
- d.
Restore D12 Diesel Generator to operable Add 1,800 gall s to D14 Diesel Generator Storage Tank Transfer 60 gallons to the D14 Diesel Generator Day Tank Ensure D l 3 Diesel Generator Air Start Receiver I C2T558 pressure is greater than 225 psig
Limerick Generating Station 2005 NRC Initial Licensing Examination
- b.
C.
- d.
Question #
88 Choice I Basis or Justification Diesel Generators operable is to restore D12 Diesel Generator to operable.
Incorrect - Although adding 1,800 gallons will restore storage tank to operable limits, D14 D/G will still be inoperable due to day tank level and transfer pump inoperability.
Incorrect - Although adding 60 gallons will restore day tank to operable limits, D14 D/G will still be inoperable due to storage tank level and transfer pump inoperability.
Incorrect - Both air receivers are required to be greater than 225 psig for D13 DG to remain operable.
- a.
Cognitive (H, L)
Unit (I, 2)
Correct Answer - Per T.S. 3.8.1.2,2 Diesel Generators are required to be operable.
D12 Diesel Generator is inoperable due to the clearance process and D14 is inoperable due to day tank level less than 200 gallons, storage tank level less than 33,500 gallons and the transfer pump inoperable. The only action that will keep 2 H
PRA (Y/N)
SRO 1
N I
OCFR55.43.b.2 Source:
Reference( s):
Learning Objective:
Knowledge/Ability:
I I
I New Exam Item T.S. 3.8.1.2.a LLOT0670.13 264000 G2.2.24 I Importance: 3.8 Tech Spec 3.8.1.2 Required Attachments or Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination
+
89 of 100 Question: 89 Unit 2 plant conditions are as follows:
L OPCON 5 Reactor cavity flooded up to +496 inches 29 RHR is operating in Shutdown Cooling Mode Reactor vessel hydrolazing in progress from the auxiliary platform LLRT in progress for 2A Core Spray system per ST-4-LLR-161-2, A Core Both spent fuel pools are connected through the cask pit per S53.0.C, Connecting Unit 1 Fuel Pool Cooling is in service with 2 pumps and 1 demineralizer Unit 2 Fuel Pool Cooling is not in service c
Spray Pump Discharge Fuel Storage Pools to Cask Storage Pit Including Cross Connecting Fuel Storage Pools A crud burst has caused Spent Fuel Pool radiation monitor alarms, with an indicated reading of 40 mdhr.
WHICH ONE of the following describes an action that will reduce dose rates to Refuel Floor workers?
- a.
L
- b.
C.
- d.
Place Unit 2 Fuel Pool Cooling demineralizer in service per S53.1.A, Startup and Temperature Control of Fuel Pool Cooling System Secure from Core Spray valve LLRT per ST-4-LLR-161-2, A Core Spray Pump Discharge Secure 29 RHR from Shutdown Cooling mode per S51.8.9, Shutdown Cooling/Reactor Coolant Circulation Operation Start-up and Shutdown Install Fuel Pool Gates Between Fuel Storage Pool and Cask Storage Pit per M-097-009, Cask Loading Pit Gate Removal, Installation, Maintenance And Movement Of Fuel Pool Gates Between Storage/Repair Locations
Limerick Generating Station 2005 NRC Initial Licensing Examination L
Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability:
Choice
- a.
- b.
C.
- d.
New Exam Item S53.1.A LLOT0750.7 233000 G2.3.10 I Importance: 3.3 Basis or Justification Correct Answer - Placing additional Fuel Pool Cooling in service will help remove the radioactive particles in the water and reduce dose to Refuel Floor workers.
Incorrect - Securing from the Core Spray valve LLRT will prevent further air bubbles from entering the reactor, but will not help to remove radioactivity from the water, and will not reduce Refuel Floor radiation levels..
Incorrect - Securing Shutdown Cooling will not help remove radioactivity from the water, and will not reduce Refuel Floor radiation levels.
Incorrect - Installing Fuel Pool gates will not lower Refuel Floor radiation levels.
I I
Required Attachments or Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 90 90 of I00 Unit 2 plant startup is in progress with the following two activities scheduled for the next two hours:
L Main Generator purging with hydrogen Traversing In-core Probe (TIP) operations WHICH ONE of the following describes the plant personnel notifications that are required during this two hour period?
Notification for Generator Purge Notification for TIP Operations
- a.
No cutting, smoking, welding, or Access restricted to Unit 2 Reactor Enclosure elevation 253' and 269' per SE-24, lnplant Evacuations Generator Purging - C02 to H2
- b.
No cutting, s No access to TIP Room, TIP Room roof, and affected areas per S74.O.A, Operation of Traversing In-core Probe System Turbine Enclosure per S28.5.D, Generator Purging - C02 to H2 L
- c.
Access restr d to the Unit 1 and Unit 2 Turbine Enclosure until Generator purging is complete per S E-24, In pla nt Evacuations Access restricted to the Unit 1 and Unit 2 Turbine Enclosure until Generator purging is complete per SE-24, lnplant Evacuations
- d.
Access restricted to Unit 2 Reactor Enclosure elevation 253' and 269' per SE-24, lnplant Evacuations No access to TIP Room, TIP Room roof, and affected areas, per S74.O.A, Operation of Traversing In-core Probe System
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
90 Choice Basis or Justification
- a.
. Incorrect - See justification for b.
- b.
C.
Correct Answer - S28.5.D requires making announcements prohibiting hot work in the turbine enclosure. S74.0.A requires making announcements prohibiting access to the area around the TIP rooms. SE-24, while appropriate for restricting access during abnormal conditions, is not used during normal evolutions. It is plausible as a distractor since an operator may think that no access is permitted in the Turbine enclosure during generator purge with hydrogen, and because 253' elevation has access restricted during TIP operation.
Incorrect - See justification for b.
- d.
Incorrect - See justification for b.
Required Attachments or Reference I
I Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 91 91 of 100 b
ATTACHMENT Q80/Q91 IS PROVIDED Unit 1 plant conditions are as follows:
A scram has been attempted due to an inadvertent SLC initiation as required by "B" RPS fails to de-energize Manual RRCS initiation was successful in inserting rods OT-I 04, Unexpected/Unexplained Positive or Negative Reactivity Insertion WHICH ONE of the following identifies the Emergency Action Level and the role of the Shift Manager?
Emergency Action Level
- a.
MS4
- b.
MA4 L
C.
MS4
- d.
MA4 Shift Manager Role Direct Shift Communicator to initiate required State/Local notifications per EP-MA-I 14-1 00, Mid-Atlantic State/Local Notifications Direct Shift Communicator to initiate NRC Notification per EP-AA-I 14, Notifications Direct Shift Communicator to initiate NRC Notification per EP-AA-1 14y Notifications Direct Shift Communicator to initiate required State/Local notifications per EP-MA-I 14-1 00 Mid-Atlantic State/Local Notifications
L L
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
91 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for "d" Incorrect - See justification for "d" Incorrect - See justification for "d" Correct Answer - An ATWS where RPS fails to insert rods but ARI succeeds requires a Alert notification per EP-AA-1008. The Shift Communicator is required to make state and local notifications Der EP-MA-114-100.
LGS 3-1 : Emergency Action Level (EAL) Matrix Required Attachments or Reference Objective:
Knowledge/Ability: Generic 2.1.06 I importance: 4.3 (Description of K&A, from catalog)
Ability to supervise and assume management role during transients and upset conditions.
Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 92 92 of 100 Unit 1 plant conditions are as follows:
100% reactor power IA lsophase Bus Cooling Fan tripped Y B lsophase Bus Cooling Fan started automatically FIN team members remov Removing/lnstalling an lsophase Fan MCC Breaker When lsophase Cooling is Required to be in Service with the following conditions:
the I A lsophase Bus Cooling Fan breaker per S34.2.C, I A lsophase Bus Cooling Fan handswitch has been placed in OFF 1 B lsophase Bus Cooling Fan handswitch has been placed in MANUAL lsophase Bus Fan Maintenance Bypass Switch HS-091-101 has been placed in BY PASS.
WHICH ONE of the following describes the status of the 1 B lsophase Bus Cooling Fan after the 1A lsophase Bus Cooling Fan breaker is removed, and the procedure that must be used to remove the breaker?
- a.
- b.
C.
- d.
Status of I B lsophase Bus Cooling Fan after IA Fan Breaker Removed Procedure to use to remove the Y A lsophase Bus Cooling Fan Breaker Running MA-MA-71 6-004-1 000, Troubleshooting, Rework, and Testing (TRT) Control Manual for Peach Bottom and Limerick Running S93.O.B, 480 VAC Non-Safeguard MCC Compartment Removal MA-MA-71 6-004-1 000, Troubleshooting, Rework, and Testing (TRT) Control Manual for Peach Bottom and Limerick S93.0.B, 480 VAC Non-Safeguard MCC Corn part me nt Re rnova I Not running Not running
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference (s 1:
L New Exam Item S34.2.C. MA-MA-71 6-004-1 000 L
\\
I Learning Objective:
Knowledge/Ability:
Question#
92 LLOTI 570.01 Generic 2.2.1 7 1 Importance: 3.5 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see justification for b.
Correct Answer - S34.2.C is used to remove the breaker because it directs manipulation of the Maintenance Bypass switch, which prevents the running fan from tripping if the non-operating fan breaker is removed. Therefore, the operating fan will remain running. S34.2.C also directs using S93.0.B to remove the breaker. MA-AA-716-004-1000 is incorrect, since step 1.4 and 1.4.2 state that the T&RM shall not be used when an approved procedure, partial procedure, or TC could be used to cover the activity.
Incorrect - see justification for b.
Incorrect - see justification for b.
Required Attachments or Reference I Knowledge of the process for managing maintenance activities during power operations Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 93 93 of I00 Unit 2 plant conditions are as follows:
u Reactor power is 100%
There is a steam leak from the 4B Feedwater Heater Dose rates in the 4B Feedwater Heater room are 1500 mr/hour Entry is required into the 4B Feedwater Heater room to manually isolate the leak.
WHICH ONE of the following describes the type of Locked High Radiation Area per RP-LG-460-101 0 and required authorization for release of key per RP-LG-460-1016?
Type of Locked High Radiation Area for 4B Feedwater Heater Room Required Authorization for Release of Key
- a.
- b.
C.
- d.
Level 1 Level 1 Level 2 Level 2 RP Supervision Operations Shift Manager RP Supervision Operations Shift Manager
Limerick Generating Station 2005 NRC Initial Licensing Examination Question #
93 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Greater that I000 mrem/hr but less than 15000 mrem/hr is a Level I Locked High Radiation Area per RP-LG-460-1010. Locked High Radiation Areas must be controlled per 1 OCFRZO. RP supervision must maintain oversight of the keys to all Locked High Radiation Areas per RP-LG-460-I 01 6 Incorrect - see a justification Incorrect - see a justification tncorrect - see a justification Required Attachments or Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 94 L
Unit I plant startup is in progress with the following conditions:
Reactor power is 2%
RPV pressure is 850 psig with three bypass valves open RPV level is +35 inches The running CRD pump has tripped, and the standby pump cannot be started.
Accumulator trouble alarms have just been received for three withdrawn control rods.
WHICH ONE of the following describes the required operator action?
- a.
- b.
C.
- d.
b 94 of 100 Raise reactor pressure to greater than 900 psig per GP-2, Normal Plant Startup Place the reactor mode switch in the "SHUTDOWN " position per Technical Specifications Manually scram the reactor if a CRD pump cannot be started within 20 minutes per ON-107, Control Rod System Problems Declare the accumulators inoperable for the control rods with accumulator trouble alarms, and restore to operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per Technical Specifications
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference(s):
Learning 1 Question #
94 New Exam Item T.S. LCO 3.1.3.5 LLOTOO60.12 Basis or Justification Incorrect - TS LCO 3.1.3.5 action a.2.a.2 does not allow raising pressure to avoid having to place the mode switch in Shutdown.
Correct Answer - T. S. LCO 3.1.3.5 action a.2.a.2 applies, which requires placing reactor mode switch in Shutdown if less than 900 psig.
Incorrect - This would be correct if reactor pressure was 900 psig. (Action a.2.a.l)
Objective:
KnowiedgelAbility:
Incorrect - This would be correct if only one accumulator was inop. (Action a.1.a) 295006 G2. I.
12 1 importance: 4.0 Required Attachments or Reference I
I I
Cognitive (H, L)
- L PFW (Y/N)
SRO Unit (I,
- 2) 1 N
I OCFR55.43.b.5 Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 95 L
95 of 100 Unit I plant conditions are as follows:
OPCON 5 Reactor Disassembly is progress per M-041-200, Reactor Pressure Vessel Unit I Reactor Cavity is flooded and connected to the Unit I Spent Fuel Pool Seal #M (Reactor Well Bottom Seal) is deflated and removed from service Unit 1 Dryer / Separator Equipment Pit is flooded and connected to the Unit I Disassembly Reactor Cavity A dropped shroud head bolt has resulted in the puncture and complete failure of Seal #3 (Reactor Well Top Seal).
WHICH ONE of the following describes the effect on Unit 1 Spent Fuel Pool Level and the action required to terminate Unit 1 Spent Fuel Pool Level Loss?
Effect on Unit I Spent Fuel Pool Level Action Required to terminate Unit 1 Spent Fuel Pool Level Loss
- a.
Will lower until level is below top of irradiated fuel seated in the Spent Fuel Pool Will lower until level is below top of irradiated fuel seated in the Spent Fuel Pool L
- b.
- c.
Will lower until level is 10 inches above top of Spent Fuel Rack Will lower until level is 10 inches above top of Spent Fuel Rack
- d.
Install Fuel Pool Gates Between Fuel Storage Pool and Reactor Well per Install Dryer / Separator Storage Pool Stop Logs per M-041-023 M-097-009 Install Fuel Pool Gates Between Fuel Storage Pool and Reactor Well per Install Dryer / Separator Storage Pool Stop Logs per M-041-023 M-097-009
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Knowledge/Ability:
Reference(s):
Choice New Exam Item LLOT0750.1 295023 AA2.02 1 Importance: 3.7 ON-120, S53.0.A
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See c justification Incorrect - See c justification Correct Answer - During refueling operations the spent fuel pool is connected to the reactor cavity. The.Dryer / Separator Pit is also connected to the reactor cavity. A loss of both Seal #3 and Seal # will result in the lowering level in the fuel pool as well as the Dryer / Separator Pit. ON-120, Fuel Handling Problems, directs the entry into S53.O.A for lowering Fuel Pool Level. Direction is provided in S53.0.A to install the Fuel Pool Gat This action will isolate the Fuel Pool from the leaking seals in the Reactor Well.
eplacing the stoplogs in the Dryer / Separator will have no effect on minimizing fuel pool level loss.
Incorrect - See c justification Required Attachments or Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 96 The following actions have been taken on Unit 2:
b 96 of 100 A manual reactor scram was initiated from 100% power 10 minutes ago due to the RRCS was manually initiated 10 minutes ago Immediately after the RRCS initiation power dropped to 1.4% on all APRMs trip of both Reactor Recirculation pumps Current Unit 2 plant conditions are as follows:
All blue "SCRAM" lights are lit on the full core display All APRMs currently indicate 1.4%
All IRMs are currently on Range 6 and stable All SRM count rates are currently 55,000 cps Suppression pool temperature has just reached I10 deg. F WHICH ONE of the following describes the proper actions to be taken for Control Rod insertion and SLC injection per T-I 01, "RPV Control"?
Control Rods Standby Liquid Control System
- a.
Perform T-214 and T-215 per steps RC/Q-5 and RC/Q-I 3 Manually inject SLC per step RC/Q-I 6 b
- b.
Perform T-214 and T-215 per steps RC/Q-5 and RC/Q-I 3 Do not inject SLC per step RC/Q-4
- c.
Perform T-217 and T-218 per step Manually inject SLC per step RC/Q-16 RC/Q-13
- d.
Perform T-217 and T-218 per step Do not inject SLC per step RC/Q-4 RC/Q-13
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for c.
Incorrect - See justification for c.
Correct Answer - The blue "SCRAM" lights being lit on the full core display indicate the Scram Valves are open, which requires selection from the left side of RC/Q-I 3, making T-217 and T-218 acceptable choices. SLC should be injected per step RC/Q-16. With all IRMs at range 6 or SRMs >50,000, shutdown criteria (Note #16) is not met per RC/Q-4 and continuing at step RCIQ-12 only is not appropriate and does not preclude the injection of SBLC.
Incorrect - See justification for c.
T-I 01 Required Attachments or Reference Cognitive (H, L)
PFL4 (Y/N)
SRO Unit (1. 2) 12 Y
I OCFR55.43.b.5 I Source:
1 New Exam Item Reference (s):
T-I 01 Learning LLOTI 560.06 Objective:
Knowledge/Ability: 21 1000 G2.4.06 I Importance: 4.0 (Description of K&A, from catalog)
Standby Liquid Control System: Knowledge of symptom based EOP mitigation strategies Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 97 L
97 of 100 A large break LOCA has occurred on Unit 2 with the following conditions:
Reactor shutdown, all rods fully inserted RPV pressure has lowered to 40 psig Drywell pressure is 29 psig and rising slowly Drywell temperature is 315 deg. F and rising slowly Suppression Pool pressure 32 psig and rising slowly Suppression Pool temperature 160°F and rising slowly Suppression Pool level is 26 feet and steady All RPV level indicators are reading off-scale high WHICH ONE of the following describes the required utilization of "2A" and "2B" RHR loops and the basis for this decision?
Utilization of "2A and "28" RHR Basis for Decision
- a.
- b.
i, C.
- d.
Inject into the RPV with both loops of RHR per T-I 16 Place both loops of RHR in Suppression Pool Cooling per T-I 02 and S51.8.A Spray the Drywell with one loop of RHR and spray the Suppression Pool with the other loop of RHR per T-I 02 and T-225 Inject into the RPV with one loop of RHR per T-I 16 and spray the Drywell with the other loop of RHR per T-I02 and T-225 Adequate Core Cooling is not assured Primary Containment is threatened by exceeding heat capacity temperature limit of the Suppression Pool Primary Containment is threatened by direct pressurization of the Suppression Pool Adequate Core Cooling is not assured AND Primary Containment is threatened by direct pressurization of the Suppression Pool
L-u Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
97 Choice a:
- b.
C.
- d.
Basis or Justification Correct Answer - Conditions given are on the unsafe side of the Reference Leg Saturation Limit Curve (DWTT-1) in T-102. This, together with all RPV level indicators rising to offscale high, will require the operators to declare RPV level unknown, and enter T-I 16. The prioritization for RHR pumps with level unknown (adequate core cooling is NOT assured) is to establish adequate core cooling first. For this reason, both T-102 steps PC/P-5 and PC/P-9 for spraying the suppression pool and drywell provide the direction to initiate sprays "unless required for core cooling". T-102 step SPTT-5 states "IF NOT required for core cooling, THEN operate 2 loops of Supp Pool Cooling". Therefore, since core cooling is not assured, suppression pool and drywell sprays and suppression pool cooling are not permitted.
Incorrect - See justification for a.
Incorrect - See justification for a.
Incorrect - See justification for a.
T-102, T-I 16 Required Attachments or Reference Prepared by: Craig Fritz b
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 98 98 of 100 Unit I plant conditions are as follows:
c 100% reactor power "IA" RECW Pump is blocked out for maintenance "IA" RWCU Pump is in service Non-Regen Heat Exchanger outlet temperature is 120°F "1 B" RECW Pump breaker trips on overcurrent.
WHICH ONE of the following describes the status of the RWCU system one minute later and the requ ired procedural action?
- a.
- b.
L C.
- d.
tem Status One Minute Later RWCU isolated and "1A RWCU Pump tripped on tow RWCU flow "IA" RWCU Pump tripped on low RECW pressure and RWCU is not isolated RWCU isolated and "IA" RWCU Pump tripped on low RWCU flow "IA" RWCU Pump tripped on low RECW pressure and RWCU is not isolated Required Procedural Action Isolate RWCU pumps per S44.2.B, RWCU Recirculation Pump Shutdown Isolate RWCU pumps per S44.2.B, RWCU Recirculation Pump Shutdown Restart RWCU per S44.7.A, Reactor Water Cleanup Fast Startup Restart RWCU per S44.7.A, Reactor Water Cleanup Fast Startup
L' L
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for "b".
Correct Answer - "IA" RWCU Pump will trip on low RECW pressure after 10 seconds. RWCU will not isolate on high Non Regenerative Heat Exchanger temperature until temperature reaches 140°F. ON-I 13, Loss of RECW, directs isolating the RWCU pump if it trips on loss of RECW.
Incorrect - See justification for "b".
Incorrect - See justification for "b".
Required Attachments or Reference I
Source:
New Exam Item Learning LLOTI 55003 Reference(s):
ON-I 13, ARC-MCR-1 I 2 G-2 Objective:
Knowledge/Abil ity: 204000 A2.0 1 I Importance: 3.4 (Description of K&A, from catalog)
Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of component cooling water Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination L' Question: 99 99 of 100 The following annunciators have alarmed in the MCR at the following times:
0900 hour0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />s: 11 8 SERVICE 1-2, "UNIT 1 IS0 PHASE BUS COOLER TROUBLE" 0901 hour0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.428305e-4 months <br />s: 002 ENT E-I, "HIGH TOXIC CHEMICAL CONC."
WHICH ONE of the following describes the action that is the highest priority?
- a.
- b.
C.
- d.
L L
Don Self-contained Breathing Apparatus per SE-2, Toxic Gadchlorine Reduce generator reactive load to zero (0 MVAR) to minimize Generator Stator amps per ON-I 01, Loss of Isolated Phase Bus Cooling Initiate Control Room chlorine / toxic chemical isolation per S78.8.A, Manual Initiation Of Control Room Radiation Or Chlorine / Toxic Chemical Isolation.
Reduce power in accordance with GP-5 Appendix 2, Section 3.1, Reducing Rx Power, and Reactor Maneuvering Shutdown Instructions until Main Generator output current is less than 20,000 amps.
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit [I.
- 2)
Question#
99 L
PRA (Y/N)
I SRO 1
N I I OCFR55.43.b.5 Choice
- a.
Source:
Reference(s):
Learning
- b.
New Exam Item SE-2, ON-IO1, Arc 002 VENT E-I, Arc 118 SERVICE 1-2 LLOT1563.2 C.
- d.
Basis or Justification Correct Answer - Immediate operator actions per SE-2 and Arc 002 VENT E-I require Control Room operators to don SCBAs within 2 minutes for safety of the operators.
Incorrect - This is a secondary action of SE-2 Incorrect - Must assume loss of lsophase bus cooling, and it is not an immediate operator action Incorrect - Must assume loss of tsophase bus cooling, and it is not an immediate operator action Required Attachments or Reference I Obiective:
I I
KnowledgelAbility: I Generic 2.4.45 I Importance: 3.6 (Description of K&A, from catalog)
I Abilitv to Drioritize and intermet the sianificance of each annunciator or alarm.
I Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 100 Unit 1 plant conditions are as follows:
A fire has forced the evacuation of the MCR Reactor Mode Switch in "SHUTDOWN" Reactor manually scrammed Main Turbine is tripped MSlVs are closed 100 of 100 The fire spreads and results in a loss of Division 1 DC.
WHICH ONE of the following identifies the SRVs and required procedure for controlling reactor pressure and the associated reactor pressure indication to be used?
Appropriate Procedure Reactor Pressure Indication
- a.
C, A, N SRVs per SE-1, Remote Shutdown 10c201 ADS SRVs per SE-6, Alternate Remote Shutdown C, A, N SRVs per SE-1, Remote Shutdown PI-42-1 ROI 1 (PI-C61-1 ROI 1) on panel PIS-42-1 N690B, on panel 1 OC618 PIS-42-1 N690B, on panel 10C618
- b.
- c.
- d.
ADS SRVs per E-6, Alternate PI-42-1 R011 (PI-C61-1 ROI 1) on panel Remote Shutdown 1 oc201
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Reference( s):
Question # I00 Basis or Justification New Exam Item LLOT0735.05 SE-1, SE-6, E-33, E-I 02, C61-I 050-E-003 Choice
- a.
Objective:
Knowledge/Ability:
- b.
29501 6 AA2.03 I Importance: 4.4 C.
- d.
Incorrect - See justification for "b".
Correct Answer - SE-I can not be used for pressure control due to loss of Division 1 DC which de-energizes C, A, N SRV controls from the Remote Shutdown Panel. The instrumentation used for pressure indication in SE-6 is PIS-42-1 N690B.
Incorrect - See justification for "b".
Incorrect - PI-42-1 R011 Pressure Indicator is powered from Division I DC and is not available.
Required Attachments or Reference Cognitive (H, L)
H PRA (Y/N)
SRO Unit (1, 2) 1 N
1 OCFR55.43.b.5