ML050350333
| ML050350333 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/15/2004 |
| From: | Jason White Exelon Generation Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| References | |
| 50-352/05-301, 50-353/05-301 50-352/05-301, 50-353/05-301 | |
| Download: ML050350333 (200) | |
Text
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 01 01 of I00 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-I (MOISTURE SEPARATOR HI LEVEL TRIP) on 206 MAIN STEAM have alarmed.
WHICH ONE of the following describes the expected 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 Cognitive (H, L)
Unit (1, 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 2
N N
Question #
01 Source:
Learning Objective:
Knowledge/Ability:
Reference( s):
Choice New Exam Item LLOT0560.10 295005 AK2.01 I Importance: 3.8/3.9 ARC-MCR-206, E-I
- 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 L I Psychometrics I
I Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 02 02 of 100 Unit 1 plant conditions are as follows:
100% reactor power Normal electrical lineup A loss of offsite power occurs and all Unit 1 and Unit 2 Diesel Generators cannot be started.
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.
- c.
HPCl Main Turbine Bypass Valves
- d.
Reactor Feedwater Pumps Main Turbine Bypass Valves
Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data I Question # 02 Source:
Learning Reference (s):
Choice b New Exam Item LLOTI 566.02 E-I
/b Objective:
Knowledge/Ability:
Basis or Justification 295003 AKI.06 I Importance: 3.8/4.0 Correct Answer - HPCl 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 - Reactor Feedwater pumps will all trip on low suction pressure when the condensate pumps trip on loss of power 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)
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)
Required Attachments or Reference Source Documentation 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 Generatina Station 2005 NRC Initial Licensina Examination Question: 03 03 of 100 L-Unit 1 plant conditions are as follows:
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 YA Drywell Chiller in service 1 A and 1 B Chilled Water Pumps running 8 Drywell fans are running All automatic actions occur as designed xator actions performed.
WHICH ONE of the following actions is permissible to lower Drywell Temperature for the conditions above?
- a. Reset DWCW Isolations per GP 8.3, ISOLATION RESETS
- b. Bypass DWCW Isolations per GP 8.5, ISOLATION BYPASS OF CRUCIAL SYSTEMS
- c.
Start 1 B Chiller per S87.1.A, STARTUP OF DRYWELL CHILLED WATER SYSTEM
- d.
Place Drywell Spray in service per T-225, STARTUP AND SHUTDOWN OF SUPPRESSION POOL AND DRYWELL SPRAY
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 1
N N
Question #
03 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - DWCW Isolation can not be reset with Drywell pressure greater than 1.68 Psig Correct Answer - 1.68 psig isolates Drywell chill water to drywell. Must Bypass isolations per GP 8.5 per T-102 Incorrect - The definition for T-I 02 "Maximize Drywell Cooling" requires only one Drywell Chiller in service Incorrect - Drywell Spray is not permissible with the given Drywell parameters Required Attachments or Reference T-I 02 1 Psychometrics L..
I I Source Documentation Source:
New Exam Item Learning LLOTI 560.5 Reference (s) :
T-I 02, OT-I 01 0 bjective:
Knowledge/Ability: 295012 A I.02 I Importance: 3.8/3.8 (Description of K&A, from catalog)
Ability to operate and/or monitor the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell cooling system Prepared by: Tim Kan
Limerick Generatina Station 2005 NRC Initial Licensina Examination L,
Question: 04 04 of 100 Unit 2 plant conditions are as follows:
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 expected 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
- b.
Open Closed
- c.
Closed Open
..-/
- d.
Closed Closed
Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data I Question #
04 Source:
Learning 0 bjective:
Knowledge/Ability:
Reference(s):
Choice
- a.
- b.
C.
- d.
New Exam Item LLOT0370.08 203000 K4.03 I Importance: 3.Z3.3 P&l M-51 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.
v Required Attachments or Reference I Unit (1,2)
I I Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 05 05 of 100 b
ATTACHMENT Q05 IS PROVIDED Unit I plant conditions are as follows:
Inadvertent RClC initiation has occurred OT-I 04 actions have been performed A P-I has been demanded (see attached P-I)
RClC has been shutdown Reactor power is 99%
WHICH ONE of the following, for the attached P-I, is a condition that requires reporting to the CRS?
- a. AGAF needs adjustment
- b.
Exceeding rated thermal power
- c.
A thermal limit is being exceeded
- d. Control rod 38-31 is not in the correct position
-v
~
-~
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Obiective:
Reference (s ) :
Answer Key and Question Data New Exam Item LLOT0740.2 T.S. GP-I4 Question#
05 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect -AGAF are all reading 0.999. They do not need adjustment unless they are outside 0.98 - I
.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 45-1 6.
Incorrect - Control rod 38-31 is in the same position as its symmetric rods.
P I print out Required Attachments or Reference I Source Documentation I
Knowledge/Ability: I G.2.1.I 9
I Importance: 3.0/3.0 (Description of K&A, from catalog)
Ability to use plant computer to obtain and evaluate parametric information on system or component status.
Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination i-Question: 06 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 No operator actions have been taken.
WHICH ONE of the following describes the status of the Safety Relief Valves (SRVs)?
- a. All fourteen (14) SRVs are open
- b. All fourteen (14) SRVs are closed
- c.
A, C, and N SRVs are open, all others are closed
- d.
E, H, K, M, S SRVs are open, all others are closed c
Limerick Generating Station 2005 NRC Initial Licensing Examination L
Answer Key and Question Data I Question #
06 Reference (s) :
Learning Choice
- a.
- b.
C.
- d.
T-I 12 Bases LLOT0330.5 Basis or Justification Incorrect - only high pressure (above the lift setpoints of 11 70, 1180, and I190 psig) will cause all 14 SRVs to open automatically.
Incorrect - conditions given will provide an ADS initiation signal, which will open the 5 ADS/SRVs Objective:
Knowledge/Ability:
Incorrect - C, A, and N SRVs are the SRVs that can be operated from the Remote Shutdown Panel, but they will not open automatically.
239002 K1.08 I Importance: 4.0/4.1 Correct Answer - These are the 5 ADS valves, and they will open automatically based on the given conditions.
Required Attachments or Reference I Source Documentation I Source:
I New Exam Item I
Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination
..-.~
Question: 07 07 of I00 Unit 1 plant conditions are as follows:
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 where the Equipment Operator would retrieve the procedure and what is required to verify proper revision for the conditions above?
T-200 Locker Location Revision Verification
- a.
OSC Must verify revision number in PlMS
- b.
FOF Must verify red Controlled Copy stamped
- c.
osc Must verify red Controlled Copy stamped
- d.
FOF Must verify revision number in PlMS
Limerick Generatina Station 2005 NRC Initial Licensina Examination Cognitive (H, L)
Unit (1, 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 1
N N
Question #
07 Source:
Learning Objective:
Knowledge/Ability:
Reference (s):
Choice New Exam Item LLOT1570 5 Generic 2.1.21 I Importance: 3.1/3.2 HU-AA-I 04-1 01, RM-AA-102
- 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 1 Source Documentation Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 08 08 of 100 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 HPCl must be secured and the reason it must be secured?
Suppression Pool Level Reason
- a.
13.5ft.
Prevent exceeding NPSH and vortex limits
- b.
13.5ft.
Prevent containment pressurization
- c.
18 ft.
Prevent exceeding NPSH and vortex limits
- d.
18ft.
Prevent containment pressurization
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO I
Y N
Question #
08 Source:
Reference(s):
Learning Choice New Exam Item T-102, Trip Bases LLOTI 560.5
- a.
0 bjective:
Knowledge/Ability:
- b.
295030 EK3.02 I Importance: 3.5/3.7 C.
Basis or Justification Incorrect (see explanation for "d")
Incorrect (see explanation for "d")
- d.
T-I 02 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-I02 Bases explains that it is to prevent direct pressurization of the suppression pool by the HPCl exhaust.
Required Attachments or Reference I Psychometrics L.
1 I Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 09 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 I OC603 panel.
RPS "SCRAM STATUS" lights BI, B2, B3, and B4 are NOT lit on 10C603 panel.
WHICH ONE of the following describes the status of Unit 1 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 Answer Key and Question Data Question #
09 Choice
- a.
- b.
C.
- d.
Basis or Justification 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 I Source Documentation Source:
New Exam Item Learning LLOT0300.08 0 bjective:
Knowledge/Ability: 29501 5 AA 1.02 I Importance: 4.0/4.2 (Description of K&A, from catalog)
Ability to operate and/or monitor the following as they apply to INCOMPLETE SCRAM: RPS Reference(s):
OT-I 1 7 Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 10 10 of I00 Unit 2 plant conditions are as follows:
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 low low low reactor level setpoint?
- a.
"2A" RHR Pump trips and restarts in 5 seconds
- b. "2B" Core Spray Pump auto starts in 10 seconds
- c.
Control Enclosure Cooling will be lost for 167 seconds
- d.
Cooling water for D24 Diesel Generator will be lost for 53 seconds
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference(s):
Learning 0 bj ect ive :
Knowledge/Ability:
Answer Key and Question Data New Exam Item UFSAR Table 8.3-1 (b), E-164, E-321, E-350, E-360, E-453 LLOT0660.05 264000 K5.06 I Importance: 3.413.5 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 1 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.
Required Attachments or Reference I
I I
W
[ Source Documentation Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination L/
Question: I 1 I 1 of 100 D22 DG has just been synchronized with the 101 Safeguard Bus resulting in the following generator indications:
60.0 HZ 200 Kw 200 KVAR 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?
- a. Lower reactive load using Voltage Regulator control to prevent generator overvoltage
- b. Lower reactive load using Speed Governor control to prevent generator winding overheating
- c.
Raise real load using Voltage Regulator control to prevent generator overvoltage
- d. Raise real load using Speed Governor control to prevent generator winding overheating
~
~
Limerick Generatina Station 2005 NRC Initial Licensina Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 2
N N
Question#
11 Source:
Reference( s):
Learning Objective:
Knowledge/Ability:
Choice New Exam Item S92.1.O LLOT0670.2 264000 A2.04 I Importance: 2.9/3.0
- a.
- b.
C.
- d.
Basis or Justification Incorrect - action is to prevent generator winding overheating Incorrect - Voltage Regulator control is used to control reactive load Incorrect - Speed Governor is used to control real load Correct Answer Required Attachments or Reference I Psychometrics
\\-
I Source Documentation Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: I 2 12 of 100 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?
- 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 will runback to 28% speed; reduces power to ensure adequate NPSH to recirculation pumps
- d.
Both reactor recirculation pumps will runback to 42% speed; reduces power to ensure adequate NPSH to recirculation pumps
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit [I.
- 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 2
N N
Question #
12 Source:
Reference (s):
Learning Objective:
Knowledge/Ability:
Choice New Exam Item LLOT0040.03 295009 AK3.01 I Importance: 3.2/3.3
- a.
- b.
C.
- d.
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 DurDose of reducina Dower to reduce steam flow to heb turn RPV level.
Incorrect - See explanation for b.
Incorrect - See explanation for b.
Required Attachments or Reference I Psychometrics I Source Documentation Prepared by: Craig Fritz 1-
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 13 L*
13 of I00 Unit 2 plant conditions are as follows:
Reactor startup is in progress with reactor power at 1 1 % and all prerequisites are met to go to OPCON I Reactor Mode Switch is in "STARTUPIHOT 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. " 2 D IRM is fully withdrawn
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 2
N N
Question #
13 Source:
Reference(s):
Learning Objective:
Knowledge/Ability:
Choice New Exam Item GP-2, Appendix I LLOT0250.8 21 5003 A4.05 I Importance: 3.4/3.4
- a.
- b.
C.
- d.
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 block.
Incorrect - if the drawer mode switch is placed to TEST, it is out of OPERATE. This will provide a rod withdraw block.
Incorrect - Fully withdrawing the IRM will not bypass the IRM rod withdraw block Required Attachments or Reference I Psychometrics W
I Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 14 14 of 100 A unit 2 plant startup is in progress per GP-2 with the following conditions:
Reactor Mode Switch in STARTUP All IRMs on range 10 APRM # I 13.2%
APRM#2 12.3%
APRM#3 11.5%
APRM#4 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.
Half Scram No rod block
- b.
Half Scram Withdraw rod block
- c.
No Scram No rod block
- d.
No Scram Withdraw rod block
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 2
N N
Question#
14 Source:
Reference(s):
Learning Choice New Exam Item Tech Spec 2.2.1, GP-2 LLOT275.14,15
- a.
Objective:
Knowledge/Ability:
- b.
21 5005 A I.04 I Importance: 4.1/4.1 C.
- d.
Basis or Justification Incorrect - See d justification I
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 1 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 Psychometrics I
Source Documentation Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 15 15 of I00
.l-.
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 an expected or an abnormal condition?
Cause of the Alarm Expected or Abnormal
- a.
- b.
C.
u
- d.
Any odd reed switch closed with no rod motion signal Expected Any even reed switch closed with no rod motion signal Expected Any odd reed switch closed with no rod motion signal Abnormal Any even reed switch closed with no rod motion signal Abnormal
Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
Answer Key and Question Data
./
1 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 C.
1 d.
- b.
Source:
Reference( s):
Learning Objective:
Knowledge/Ability:
New Exam Item MCR ARC 108 REACTOR, window F-4 LLOT0080.04 201 002 K4.03 I Importance: 3.6/3.6 pushbutton.
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.
Required Attachments or Reference u '
I I
I Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 16 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 16 of 100
c Source:
Reference(s):
Learning Objective:
Knowledge/Ability:
Limerick Generating Station 2005 NRC Initial Licensing Examination New Exam Item LLOT0380.12 21 7000 K2.02 I Importance: 2.8/2.9 Answer Key and Question Data Question#
16 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - I A 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 I DC.
Required Attachments or Reference I Unit (I, 2)
I Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination L-Question: 17 17 of 100 Unit I plant conditions are as follows:
An automatic reactor scram has just occurred from 900% 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 I O seconds after the scram, and the reason for this response?
- a.
- b.
C.
- d.
RPV level will initially rise due to Scram Profile activation and core void collapse 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 collapse RPV level will initially lower due to Scram Profile NOT activating and more core inlet subcooling
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1.21 c
H PRA (Y/N)
SRO 1
N N
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 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-energize.
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 replace the lost volume of the steam voids in the core.
Source:
Reference (s):
Learning Objective:
Knowledge/Ability:
Required Attachments or Reference New Exam Item S06.1.D LLOR0401 B.06 295006 AK3.01 I Importance: 3.8/3.9 L I Psychometrics I Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 18 18 of I00 L
Unit 2 plant conditions are as follows:
An ATWS is in progress with reactor power 40%
RPV pressure is being maintained 990-1096 psig with SRVs Suppression Pool temperature I 1 0°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.
Prevent exceeding SRV Tailpipe Level Limit
- b. Prevent exceeding Primary Containment Pressure Limit
- c.
Prevent exceeding Pressure Suppression Pressure Limit
-L
- d.
Prevent exceeding Suppression Pool Heat Capacity Temperature Limit
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 2
N N
Question #
18 Source:
Learning Objective:
Knowledge/Ability:
Referen ce(s) :
Choice New Exam Item LLOTI 560.5 295013.K3.02 I Importance: 3.6/3.8 T-I 01, T-102
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see d justification Incorrect - see d justification Incorrect - see d justification Correct Answer - Per T-I 01 injecting SLC before Suppression Pool temperature reaches 11 0 degrees F is desirable to prevent exceeding the Heat Capacity Temperature Limit.
Required Attachments or Reference I Psychometrics I Source Documentation 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 "2B" 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 PCIV" (OUTBOARD), HV-51-2F015B, two (2) minutes following the trip of the 101 Safeguard Transformer Breaker?
"2B" RHR Pump HV-51-2F015B
- a.
Tripped Closed
- b.
Tripped Open
- c.
Running
- d.
Running L,
Closed Open
Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data 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 I01 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 101 Safeguard Bus. The "2B" RHR Pump will not auto restart. HV-51-2FO15B will remain open since there is no isolation signal for the valve.
Incorrect - See "b" Incorrect - See "b" Required Attachments or Reference I
I I Unit (I, 2)
Source Documentation Source:
New Exam Item Reference( s):
E-D22, Load Analysis Learning LLOT0370.14 Objective:
KnowledgelAbility: 205000 K6.01 1 Importance: 3. ~ 3. 4 (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 Generating Station 2005 NRC Initial Licensing Examination Question: 20 20 of I00
\\-.
Unit 1 plant conditions are as follows:
- 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 " I A and "I B" Rod Block Monitor (RBM)?
Effect on "1A" RBM Effect on "1 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
- a.
- b.
C.
Answer Key and Question Data 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.
Question#
20 Choice I Basis or Justification
- d.
Incorrect - see justification for c.
Reference (s ):
Learning Objective:
Knowledge/Ability:
Required Attachments or Reference LLOT0280.09 21 5002 K5.01
[ Importance: 2.6/2.8
[ Source Documentation 1
I Source:
I New Exam Item I
Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 21 21 of 100
'.-/
Unit I plant conditions are as follows:
100% power Division 3 DC bus de-energized due to ground fault "IA" CRD Pump is in service No ECCS pumps are in service A LOCA occurs which results in reactor level lowering to -150". No operator action has been taken other than normal scram actions.
WHICH ONE of the following pumps will be running following the LOCA?
- c.
"OA" RHRSW
- d. "1 C" Core Spray c
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Know led g e/A b il it y :
Reference(s):
Answer Key and Question Data New Exam Item LLOT0690.6b 295004 AK2.03 I Importance: 3.3/3.3 E-I FC Question #
21 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - If 1A 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 - " O A RHRSW Pump breaker control power is from Div. I DC. Pump breaker will trip on LOCA and does not auto restart.
Incorrect - "1 C" Core Spray Pump logic and breaker control power unavailable due to loss of Div. 3 DC.
Required Attachments or Reference I Source Documentation 1
Prepared by: Lee Stanford
Limerick Generatina Station 2005 NRC Initial Licensina Examination
.~
Question: 22 22 of 100 Unit I plant conditions are as follows:
A fire has occurred in the MCR The MCR has been abandoned All appropriate actions have been taken in SE-I, "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.
Shutdown Range; indicates higher than actual level
- d.
Shutdown Range; indicates lower than actual level i
Source:
Learning Reference(s):
Limerick Generating Station 2005 NRC Initial Licensing Examination New Exam Item LLOT0050.03 SE-1 Answer Key and Question Data Question #
22 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Only Wide Range is available at IOC201, 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.
Required Attachments or Reference I Source Documentation I Obiective:
I I
Knowledge/Ability: I 29501 6 AA2.02 I Importance: 4.2/4.3 (Description of K&A, from catalog)
Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT: Reactor water level Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 23 Unit 2 plant conditions are as follows:
L 100% power 23 of 100 "2A RECW pump is runnIlig with ts handswitch in "AUTO" "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. RECW pump suction pressure is 16 psig
- b. RECW heat exchanger outlet pressure is I12 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 Source:
Reference (s 1:
Answer Key and Question Data New Exam Item ARC for 118 SERVICES. H-3 Question#
23 Learning Objective:
Knowledge/Ability:
Choice LLOT0460.4 400000 K4.01 I Importance: 3 ~ 3. 9
- 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 I Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination
-u Question: 24 24 of I00 Unit 1 is at 100% reactor power LISL-42-1 N680C, "Reactor Level 3 Level Switch" has failed downscale, causing the following alarm:
107 REACTOR, H-1, "REACTOR WATER BELOW LEVEL 3 TRIP" WHICH ONE of the following identifies the expected 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
- a.
"A" Status Lights out One Vent and One Drain Valve Closed
- b.
"A" Status Lights out No Vent or Drain Valves Closed
- c.
"B" Status Lights out One Vent and One Drain Valve Closed u
- d.
"B" Status Lights out No Vent or Drain Valves Closed
Limerick Generating Station 2005 NRC Initial Licensing Examination
- d.
Answer Key and Question Data Incorrect - See "b" Question #
24 Choice I Basis or Justification Source:
Learning Reference(s):
- a.
New Exam Item LLOT0300.3, 7 ARC-MCR-I07 H-I, OT-I 17
- b.
Objective:
Knowledge/Ability:
C.
21 2000 A3.04 I Importance: 3.9/3.8 I 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" Required Attachments or Reference I Psychometrics I Source Documentation Prepared by: Lee Stanford
Limerick Generating 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-44-2FOOl (INBOARD)
HV-44-2F004 (OUTBOARD)
- a.
Open Open
- b.
Open Closed
- c.
Closed Open
- d.
Closed Closed
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability:
Answer Key and Question Data New Exam Item GE Elementary Drawing G31-1020 LLOTO315.03 204000 K6.07 I Importance: 3. ~ 3. 5 Question#
25 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 - 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 wmDs actuallv start or not.
Required Attachments or Reference I Unit (I,
- 2)
I Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 26 26 of 100 L/
MCR HVAC alignment is as follows:
" O K CREFAS fan is operating due to a radiation isolation
" O A 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 expected response of the CREFAS system?
- a. "OB" CREFAS fan starts immediately
- b. "OB" CREFAS fan starts in 30 seconds
- c.
" O A CREFAS fan trips, then restarts immediately
- d. "OA" CREFAS fan trips, then restarts in 30 seconds
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1, 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 0
N N
Question #
26 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - "OB" CREFAS fan will only start if it is in AUTO, or if the "OA" 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 - "OA" 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 will cause "OA" CREFAS fan to trip and restart 30 seconds later.
Required Attachments or Reference locumentation I Source:
I New Exam Item Reference( s):
Learning LLOT0450, Objective 04 Objective:
Knowledge/Ability: 290003 A3.01 I Importance: 3.3/3.5 (Description of K&A, from catalog)
Ability to monitor automatic operations of the CONTROL ROOM HVAC including:
Initiation/reconfiauration Prepared by: Craig Fritz
Limerick Gene rat i na Stat ion 2005 NRC Initial Licensina Examination L
Question: 27 27 of 100 Unit 2 initial plant conditions are as follows:
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?
Reason for Aligning ESW to RECW Reason for Aligning ESW to TECW
- a.
Provide RECW to DWCW to cool the primary containment To provide cooling to the Condensate Pump bearing oil coolers
- b.
Keep RWCU in service to minimize bottom head stratification To provide cooling to the Condensate Pump bearing oil coolers
- c.
Provide RECW to DWCW to cool the primary containment compressors To provide cooling to Instrument Air b
- d.
Keep RWCU in service to minimize bottom head stratification compressors To provide cooling to Instrument Air
Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data I Question #
27 Source:
Reference( s) :
Learning Objective:
Knowledge/Ability:
/Choice New Exam Item E l 0120, S I 3.6.D LLOT0430.07, LLOT0460.07,08 29501 8 AK3.07 I Importance: 3.1/3.2 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 ("2B" and "2C) are also not available, since they are not safeguard powered.
Correct Answer - E10/20 provides guidance for performing S13.6.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 ("2B" and "2C) are also not available, since they are not safeguard powered.
Req u ired Attachments or Reference u
I Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination
-I 61 ).
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.
Required Attachments or Reference
-.-/
I Psychometrics 1
Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination L-Question: 30 30 of I00 Unit 2 plant conditions are as follows:
A LOCA has occurred 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 5%
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.
- b.
C.
L
- d.
Operate Operate Do not operate Do not operate InerVVent Drywell without exceeding General Emergency offsite release rate InerVVent Drywell regardless of offsite release I ne rtNen t Drywell without exceeding General Emergency offsite release rate InerVVent Drywell regardless of offsite release
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference (s) :
Learning Objective:
Knowledge/Ability:
Answer Key and Question Data New Exam Item T-I 02 sheet #2 LLOTOI 60.2 500000 EK2.05 I Importance: 3.2/3.3 Question #
30 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Per T-I02 sheet #2, table PC/G-1 entry into leg DW/G-2 is required for these H2 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 Required Attachments or Reference T-I 02 sheet #2 Unit (1, 2)
I Source Documentation Prepared by: Tim Kan
Limerick Generatina Station 2005 NRC Initial Licensina Examination L-Question: 31 31 of I00 Unit I plant conditions are as follows:
Startup in progress, with all IRMs 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
- 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 Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 1
N N
Question#
31 Source:
Reference (s) :
Learning Objective:
Knowledge/Ability:
Choice New Exam Item LLOTO240.6 21 5004 A I.04 I Importance: 3. ~ ~ 5
- 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 LC I Psychometrics I Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination
--- Question: 32 32 of IO0 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 who gives dose extension approvals and if administrative dose control levels will be exceeded for the conditions above?
Dose Extension Approval Administrative Dose Control Level Exceeded
- a.
RPManager No
- b.
Station VP Yes
- c.
RPManager Yes
- d.
Station VP No
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 2
N N
Question #
32 Source:
Learning Objective:
Knowledge/Ability:
Reference( s):
Choice New Exam Item Exelon Generic lesson plan RWT 7,17,18 2.3.04 I Importance: 2.5/3.1 RP-AA-203
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see IC justification Incorrect - see IC justification Correct Answer - Admin dose control levels are 2000 mrem per year. 3 hrs x 600 mrem/hr = 1800 mrem. #1EO 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 I Psychometrics J
I Source Documentation Prepared by: Tim Kan
Limerick Generatina Station 2005 NRC Initial Licensing Examination Question: 33 L-33 of 100 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.
Secure HPCl if Suppression Pool level drops below 18 feet due to vortex limits
- b. Secure 2A RHR pump if Suppression Pool level drops below 13.5 feet due to vortex limits
- c. Transfer HPCl suction to the CST if Suppression Pool level drops below 13.5 feet due to vortex limits
- d. Shutdown the reactor if Suppression Pool level drops below 13.5 feet due to Drywell and Suppression Pool being directly connected at I 3 feet V
Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data Question#
33 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - Vortex limits for HPCl are at 15.42 ft in SP. HPCI must be shutdown at 18 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.
Required Attachments or Reference T-I 02 1 Source Documentation Source:
New Exam Item Reference(s):
T-102 and T-I02 Bases Learning LLOTI 560.5 Objective:
Knowledge/Ability: 21 9000 K6.06 I Importance: 3.7~3.7 (Description of K&A, from catalog)
Knowledge of the effects that a loss or malfunction of the following will have on the RHR/LPCI:
TORUS/SUPPRESSION POOL COOL1 NG MODE: Suppression pool Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination 34 of 100 u Question: 34 Unit 1 plant conditions are as follows:
Reactor scrammed from 100% due to High Drywell Pressure GP-4 was NOT performed 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 cts the PRO to spray the Drywell per T-225, Startup and Shutdown -f Suppression Pool and Drywell Spray Operation, using "1A" 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 E l 1 A-S61 A, INITIATION Pushbutton u
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (I, 2)
Answer Key and Question Data H
PRA (WN)
SRO 1
N N
Question#
34 Reference(s):
Learning Choice T-225 LLOT0370.09
- a.
Objective:
Knowledge/Ability:
- b.
226001 G I.20 I Importance: 4.3/4.2 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 T-225.
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 c 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 Push button.
Required Attachments or Reference
[ Psychometrics I Source Documentation I Source:
I New Exam Item Prepared by: Lee Stanford
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 35
-u-35 of I00 Unit 1 initial plant conditions are as follows:
Reactor power is 100%
Reactor level is +35 inches RPV steam dome pressure is 1035 psig WHICH ONE of the following describes a condition that will violate a Technical Specification Safety Limit?
- a.
Drywell pressure rises to 60 psig
- b. Reactor level drops to -1 70 inches
- c.
Reactor pressure rises to 1280 psig
- d. Minimum Critical Power Ratio (MCPR) lowers to 1.I2
Limerick Generating Station 2005 NRC Initial Licensing Examination
-v Answer Key and Question Data I Question #
35 Cognitive (H, L)
Unit (I,
- 2)
Basis or Justification L
PRA (Y/N)
SRO 1
Y N
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 1, when the reactor scrams at + I 2 5 inches, the plant will then be in OPCON 3, and this Safety Limit applies.
Incorrect - RPV pressure must rise above 1325 psig to exceed safety limit 2.1.3.
Source:
Reference(s):
Learning 0 bjective:
Knowledge/AbiIity:
Incorrect - MCPR must lower below 1.07 with 2 recirc pumps in operation to exceed safety limit 2.1.2.
New Exam Item Technical Specifications section 2.2 LLOTI 800.04 Generic 2.2.22 I Importance: 3.4/4.1 Required Attachments or Reference L.
I I
[ Psychometrics I Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination
.d Question: 36 36 of I00 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) per ON-I 23, Mispositioned Control Rod (s)?
- a.
Immediately insert a manual reactor Scram
- b. Substitute a rod position of 12 and insert rod I notch
- c.
Bypass the Rod Worth Minimizer and insert to position 12
- d.
Insert control rod to position 12 using the INSERT pushbutton L-
Limerick Generating Station 2005 NRC Initial Licensing Examination L
Answer Key and Question Data I Question #
36 Source:
Learning Reference (s):
Basis or Justification New Exam Item LLOTO095.3 ON-I 23 Incorrect - see d justification Objective:
Knowledge/Ability:
Incorrect - see d justification G2.2.33 I Importance: 2.U2.9 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 I Source Documentation Prepared by: Mark Crim
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 37 37 of I00 Unit 1 plant conditions are as follows:
Plant in OPCON 4 Shutdown cooling placed in service using IA 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.
Restore Reactor level to +35 inches and bypass low level isolations per GP-8.5, Isolation Bypass of Crucial Systems Prevent inadvertent change of OPCON
- b.
Restore Reactor level to +35 inches and bypass low level isolations per GP-8.5, Isolation Bypass of Crucial Systems Ensure adequate NPSH for the 1A RHR pump L
- c.
Restore Reactor level to +80 inches and reset low level isolations OPCON Prevent inadvertent change of
- d.
Restore Reactor level to +80 inches and reset low level isolations Ensure adequate NPSH for the I A RHR pump
Limerick Generatina Station 2005 NRC Initial Licensina Examination Answer Key and Question Data I Question #
37 Source:
Learning 0 bjective:
Knowledge/Ability:
Reference(s):
I New Exam Item LLOT0370.13 295021 K I.01 I Importance: 3.6/3.8 S51.8.B, OT-I 21 Basis or Justification Incorrect - GP-8.5 does not address isolation bypass of Shutdown Cooling isolations Incorrect - GP-8.5 does not address isolation bypass of Shutdown Cooling isolations, raising level is not to satisfy RHR pump NPSH concerns 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.
Required Attachments or Reference I Source Documentation Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination 38 of I00 Question: 38 L
Unit 1 plant conditions are as follows:
OPCON 5 A fuel bundle is currently being IJwered into the core, not directly adjacent to any SRM 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 rises from 45 to 130 cps
- c.
"C" SRM rises from 35 to 150 cps
- d.
"D" SRM rises from 50 to 170 cps
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 1
N N
Question #
38 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - since two doublings not reached Incorrect - since two doublings not reached 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-I20 must be entered.
Incorrect - since two doublings not reached Required Attachments or Reference I Psychometrics L
Source Documentation Source:
New Exam Item Learning LLOTI 550.1 Objective:
Knowledge/Ability: 295023 AA1.06 I Importance: 3.3/3.4 (Description of K&A, from catalog)
Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS:
Neutron monitoring Reference( s):
ON-I20
~~
Prepared by: Craig Fritz L--
Limerick Generatina Station 2005 NRC Initial Licensina 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 + I 2 3 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:
Answer Key and Question Data New Exam Item S0.6.1.D U/1 LLOR0401 B.6 259002 A3.06 I Importance: 3.0/3.0 Question#
39 Choice Basis or Justification
- a.
Incorrect - See "c"
- b.
Incorrect - See "c" C.
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.
- d.
Incorrect - See "c" Required Attachments or Reference 1 Source Documentation Prepared by: Lee Stanford
Limerick Generatina Station 2005 NRC Initial Licensing Examination Question: 40 40 of 100 Unit 2 plant conditions are as follows:
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 I REAC ENCL REFUEL FLR VENT EXHAUST HI RADIATION Refuel Floor ventilation exhaust radiation indicates 2.5 mr/hr Reactor Enclosure ventilation exhaust radiation indicates 0.8 mr/hr N B HI-HI/DOWNSCALE 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 No Fans running
- b.
Both Fans running One Fan running
- c.
One Fan running One Fan running
- d.
Both Fans running No Fans running
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference( s):
Learning Objective:
Knowledge/Ability:
Answer Key and Question Data New Exam item Annun 209 E-I, E-3 LLOT0200.6 261 000 K I.08 I Importance: 2.8/3.1 Question #
40 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see d justification Incorrect - see d justification Incorrect - see d 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 I Source Documentation Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination L, Question: 41 41 of 100 ATTACHMENT Q41 IS PROVIDED Unit 2 plant conditions are as follows:
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 115%
EHC pressure setpoint is set at 960 psig 3 psi bias is applied to the "B" 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 expected total control valve position (in % open) after the plant is stabilized?
- a.
45%
L
- b.
55%
- c.
80%
- d.
103%
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 2
N N
Question#
41 Reference (s ) :
Lea rni ng 0 bjective:
Knowledge/Ability:
Choice LLOT0590.05 241 000 A I.08 I Importance: 3.3/3.2
- a.
- b.
C.
- d.
Basis or Justification 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.
Incorrect - See justification for b.
Required Attachments or Reference EHC logic diagram I Psychometrics I Source Documentation I Source:
I New Exam Item Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination
- - Question: 42 42 of 100 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.
c-'
- d.
Reactor Level drops and stabilizes at a level above the scram setpoint. Place Feedwater Level 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 Choice
- a.
- b.
C.
- d.
Question#
42 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" 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 I O directs manually controlling RFP if FWLCS malfunction occurs.
Incorrect - See "c" Cognitive (H, L)
Unit (I,
- 2)
Required Attachments or Reference
~
~~
H PRA (Y/N)
SRO 2
N N
I Psychometrics Source:
Learning Reference (s):
New Exam Item LLOT0550.7 OT-I IO, REACTOR HIGH LEVEL I Source Documentation 0 bjective:
Knowledge/Ability: 259001 A2.07 I Importance: 3.7/3.8 Prepared by: Lee Stanford
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 43 L,
43 of 100 Unit 1 plant conditions are as follows:
Reactor power is 100%
Annunciator 109 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 1 O4 mr/hr and the reason for lowering Air Ejector discharge radiation levels?
Actions Required to Reduce Air Ejector Radiation Levels Reason for Lowering Air Ejector Discharge Radiation Levels
- a.
Reduce Reactor Power
- b.
Reduce Reactor Power Limit Off Site release through the North Stack Limit Off Site release through the South Stack
- c.
Isolate Steam Jet Air Ejectors Limit Off Site release through the North Stack L
- d.
Isolate Steam Jet Air Ejectors Limit Off Site release through the South Stack
Limerick Generating Station 2005 NRC Initial Licensing Examination
- a.
- b.
Answer Key and Question Data 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 Question#
43 Choice I Basis or Justification Cognitive (H, L)
Unit (1, 2)
H PRA (Y/N)
SRO I
N N
C.
Source:
Learning 0 bjective:
Knowledge/Ability:
Reference(s) :
- d.
New Exam Item LLOTI 550.2 G2.3.11 I Importance: 2.7/3.2 ON-I 02 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 L I Psychometrics I Source Documentation Prepared by: Tim Kan
Limerick Generatina Station 2005 NRC Initial Licensing Examination I
Question: 44 44 of 100 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 Basis for Priority
- a.
Drywell Spray
- b.
Drywell Spray L
- c.
Maximize RPV injection
- d.
Maximize RPV injection Containment cooling is a higher priority than RPV integrity with the given conditions 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
L Source:
Reference( s):
Learning 0 bjective:
Knowledge/Ability:
Limerick Generatina Station 2005 NRC Initial Licensing Examination New Exam Item T-I 02 Bases, T-I 1 I Bases LLOTI 560.05 Generic 2.4.22 I Importance: 3.0/4.0 Answer Key and Question Data Question ##
44 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for c.
Incorrect - See justification for c.
Correct Answer - At -175" reactor level, fuel is uncovered. T-I 1 I directs maximizing RPV injection with all available systems when level drops below -161" and T-I 12 has been performed. This is a higher priority than drywell spray because T-102 only directs drywell sprays if adequate core cooling is assured.
Incorrect - See justification for c.
Required Attachments or Reference T-102, T-I I 1 I Source Documentation Prepared by: Lee Stanford
Limerick Generatina Station 2005 NRC Initial Licensing Examination Question: 45 u
45 of IO0 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
- b. Drywell pressure will equalize with Suppression Pool pressure; containment integrity is threatened
- c.
Drywell pressure will rise to about 5 psig greater than Suppression Pool pressure; containment integrity is NOT threatened
- d.
Drywell pressure will rise to about 5 psig greater than Suppression Pool pressure; containment integrity is threatened L
I
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference (s):
Learning Objective:
Knowledge/Ability:
Answer Key and Question Data
~~
New Exam Item UFSAR section 3A. 16.1 LLOTOI 30.04 295024 EKI.01 I Importance: 4.1/4.2 Question #
45 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for b.
Correct Answer - With both vacuum reliefs on one LOCA downcomer stuck open, the suppression pool will be directly pressurized, which will cause pressures to equalize between the drywell and suppression pool. Also, the direct pressurization of the suppression pool removes the pressure suppression capability of the suppression pool, and with no containment sprays available, can result in drywell and/or suppression pool pressures exceeding design limits.
Incorrect - See justification for b.
Incorrect - See justification for b.
Required Attachments or Reference I Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination
\\,
Question: 46 46 of 100 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 To prevent exceeding RPV design pressure
- c.
Backup Scram valves will open To initiate rod insertion
- d.
Backup Scram valves will open To prevent exceeding RPV design pressure
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1, 2)
\\. i Answer Key and Question Data H
PRA (Y/N)
SRO 2
Y N
I Question #
46 Source :
Reference (s):
Learning Objective:
Knowledge/Ability:
I a-New Exam Item UFSAR section 7.6.1.8.3.1 LLOT0315.04 295025 EK3.06 I Importance: 4.2/4.4 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.
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.
Required Attachments or Reference b
1 Psychometrics Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 47 Unit 1 plant conditions are as follows:
47 of I00 100% reactor power Normal reactor enclosure ventilation in service Both Standby Gas Treatment (SGTS) fans are in "AUTO" A Drywell leak results in Drywell pressure rising to 3 psig. 5 minutes later, a lockout occurs on D12 4KV Bus.
WHICH ONE of the following identifies the status of the SGTS fans following the Bus Lockout?
- a.
Both Fans off
- b.
Both Fans running
- c.
"A" Fan running, "B" Fan tripped
- d.
"A" Fan tripped, "B" Fan running
Limerick Generating Station 2005 NRC Initial Licensing Examination
- b.
Answer Key and Question Data Incorrect - See justification for "c" Question#
47 Choice I Basis or Justification C.
- d.
- a.
Correct Answer - Both SBGT Fans will start on Drywell pressure greater than I
.68 psig. The "B" SBGT Fan will trip on loss of power to D12.
Incorrect - See justification for "c" Incorrect - See justification for "c" Cognitive (H, L)
H PRA (Y/N)
Unit (1. 2) 1 N
SRO N
Source:
Learning Objective:
Knowledge/Ability:
Reference(s):
Required Attachments or Reference New Exam Item LLOT0200.10 261 000 k6.01 I Importance: 2.9/3.0 E-483 Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination L Question: 48 48 of 100 Unit 2 plant conditions are as follows:
OPCON 5 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?
- a.
D214-R-C 480 VAC MCC
- b.
D224-R-G 480 VAC MCC
- c.
20Y101 120 VAC Distribution Panel
- d. 20Y163 120 VAC Distribution Panel
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Refere n ce(s):
Learning Objective:
Knowledge/Ability:
Answer Key and Question Data New Exam Item Tech Spec LCO 3.8.3.2 LLOT0660.9 262001 G 1.10 I Importance: 2.7/3.9 Question #
48 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 - Division 2 is already INOPERABLE due to loss of 20Y102.
SYSTEMS DISTRIBUTION - SHUTDOWN Incorrect - 20Y101 is a Division 1 panel. See 'la" Incorrect - 20Y163 is a Division 3 panel. See "a" Tech Specs Required Attachments or Reference I
L-'
1 Source Documentation
~
Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination MSL Monitor 1A
'W Question: 49 49 of 100 Background with HWC Factor HWC in-service 1.S(x)HWC Factor of l(x) Background =
894 MR/hr 1.o 1341 MR/hr Unit I is at 100% reactor power when the following annunciator alarms:
1 MAIN STEAM LINE DIVISION I RAD MONITOR HVDOWNSCALE The following readings are taken from the Main Steam Line Rad Monitors on panel 1OC600:
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 lOC600:
Unit I Main Steam Line RAD Monitors I
1B I 870MR/hr I 1.0 I
1305 MR/hr I
I I C I 970MR/hr I 1.0 I
1455 MR/hr I
I I D I 900MR/hr I 1.0 I
1350 MR/hr I
WHICH ONE of the following identifies the Rad Monitor(s) responsible for the alarm?
- a. A
- b. B
- c. c
- d.
D
Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data I Question#
49 Source:
Reference(s):
Learning Objective:
Knowledge/Ability:
Choice F New Exam Item ARC-MCR-109 F-I, Main Steam Line Rad Monitor Op Aid 01-014 LLOT0720.02 272000 A4.01 I Importance: 2.9/2.9 Basis or Justification Incorrect - Setpoint for A Rad Monitor is 1341 mr/hr.
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.
Req u ired Attachments or Reference 1 Source Documentation Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 50 50 of 100 L-Unit 1 is at 100% reactor power when the following sequence of event occur:
"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 MSlV 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 WHICH ONE of the following identifies the exhaust path(s) from the MSlV room?
- a. Standby Gas Treatment System to North Stack
- b. Reactor Enclosure Equipment Compartment Exhaust to South Stack
- c.
Outboard MSlV room Blowout Panels to Reactor Building Roof and Condenser Area
- d.
Reactor Enclosure Recirculation System to Standby Gas Treatment System to North Stack b
c
L-Source:
Learning Objective:
Knowledge/Ability:
Reference( s) :
Limerick Generatina Station 2005 NRC Initial Licensina Examination New Exam Item LLOTOI 90.06 290001 K I.02 I Importance: 3.4/3.6 M-76 Answer Key and Question Data Question #
50 Choice
- a.
- b.
C.
- d.
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 Anser - A Main Steam Line break in the Outboard MSlV 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.
Required Attachments or Reference I Source Documentation Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination L/
Question: 51 51 of 100 ATTACHMENT Q51 IS PROVIDED Unit I initial plant conditions are as follows:
Reactor power is 100%
Steam Seal Evaporator (SSE) level as indicated by LI-07-157 on 106653 is 0 inches 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.
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 Action Required to Mitigate Level Change
- a.
- b.
C.
- d.
Rise Close HV-007-157, SSE Cond M/U Shutoff Valve (SUP)
Lower Close HV-007-158, SSE Steam Outlet Valve (OUTLET)
Rise Close HV-007-156, SSE Cond M/U Bypass Valve (BYPASS)
Lower Close 007-1 053 and 007-1 075, SSE Drain Valves
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Knowledge/Ability:
Reference (s):
Answer Key and Question Data New Exam Item LLOT0495.07, LLOT2002.02 Generic 2.4.47 I Importance: 3 ~ 3. 7 M-02, M-05, M-07, ARC-MCR-106 A-4 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 L I Psychometrics I
I Cognitive (H, L)
I H 1 PRA(Y/N)
I SRO I Unit (I, 2) 11 I N I N I Source Documentation Prepared by: Lee Stanford
Limerick Generatina Station 2005 NRC Initial Licensina Examination
\\.
Question: 52 52 of 100 With Unit 1 at 93% power, the "1 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 following annunciators will be alarmed?
- a.
REACTOR HI PRESS (107 REACTOR G-2)
- b. REACTOR HVLO LEVEL (107 REACTOR H-2)
C.
APRM UPSCALE 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 f l. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 1
N N
Question#
52 Source:
Reference( s):
Learning Choice New Exam Item ARCS for annunciators listed LLOT0050.08
- a.
Objective:
K n ow I ed g e/A b i I it y :
- b.
G 2.4.46 I Importance: 333.6 C.
- d.
Basis or Justification Correct Answer - Reactor pressure above 1053 psig will cause this annunciator to alarm.
Incorrect - RPV level must go below +30 inches for this annunciator to alarm.
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.
Required Attachments or Reference
- I Psychometrics 1 Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 53 53 of 100 Unit 2 plant conditions are as follows:
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 10 degrees F?
- a.
"2A" RHR pump suction temperature
- b. "2A" Core Spray pump suction temperature
- c.
"2A" RHR Heat exchanger outlet temperature
- d.
Suppression Pool Temperature Monitoring System (SPOTMOS)
Limerick Generating Station 2005 NRC Initial Licensing Examination Reference (s) :
Learning Answer Key and Question Data T-I02 Note 2 LLOTI 560.5
~
Question#
53 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - per T-I 02, 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 I Source Documentation I Source:
I New Exam Item I Objective:
Knowledge/Ability: I 295026 A I.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 W ATE R TE M P E RAT U RE : Temp era t u re mo n it o ri n g Prepared by: Tim Kan
Limerick Generatina Station 2005 NRC Initial Licensing Examination Question: 54 54 of I00 ATTACHMENT Q54 IS PROVIDED Unit 2 plant conditions are as follows:
Drywell cooling has been lost due to an inadvertent isolation that cannot be bypassed Drywell temperature is 135 deg. F Drywell pressure is 0.8 psig Suppression pool airspace temperature is 123 deg. F Suppression pool pressure is 0.4 psig 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. NOT permitted until drywell pressure is greater than 0.9 psig
- c.
Permitted until drywell temperature is less than 134 deg. F u
- d. NOT permitted until drywell temperature is greater than 137 deg. F
i-Cognitive (H, L)
Unit (1. 2)
Limerick Generatina Station 2005 NRC Initial Licensina Examination H
PRA (YIN)
SRO 2
N N
Answer Key and Question Data Source:
Learning Objective:
Knowledge/Ability:
Reference( s):
Question #
54 New Exam Item None found 295028 EA2.04 I Importance: 4.1/4.2 OT-I01 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for b.
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 I); 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.
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.
OT-101 Required Attachments or Reference 1 Psychometrics 1
Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination i, Question: 55 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 Bypass Capability
- a.
PClG NO
- b.
RWCU YES
- c.
MSlV NO
- d.
DWCW YES
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning I Objective:
Knowledge/Ability:
Reference( s):
Answer Key and Question Data New Exam Item LLOTOI 80.8 262002 K3.10 I Importance: 2.7/2.8 E-2BY 1 60
~
Question #
55 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 - Drywell Chilled Water will isolate on a loss of 2B RPS UPS Static Inverter and the isolation can be bypassed.
Required Attachments or Reference Prepared by: Lee Stanford
Limerick Generatina Station 2005 NRC Initial Licensina Examination v
Question: 56 56 of 100 Unit 1 plant conditions are as follows:
100% reactor power Normal electrical lineup An overtemperature condition occurs on the "1 A RPS/UPS Static Inverter.
WHICH ONE of the following identifies the status of RPS and the power source for the 1 AYI 60 panel following the overtemperature condition?
RPS Status 1 AY 160 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 Answer Key and Question Data Question#
56 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See "d" Incorrect - See "d" Incorrect - See "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
f Source Documentation Source:
I New Exam Item Refe rence(s):
I ARC-MCR-I 20. A-5 Learning LLOT0300.02 Objective:
Knowledge/Ability: 262002 K4.01 I Importance: 3.1/3.4 (Description of K&A, from catalog)
Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design feature(s) and/or 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 Unit I plant conditions are as follows:
A failure to Scram has occurred "1 B" RPS channel has failed to de-energize T-216, "Manual Isolation and Vent of Scram Air Header" has successfully inserted all control rods WHICH ONE of the following describes the indications shown by the SPDS "Scram Event Indicator" during the ATWS event and 6 seconds after the control rods are inserted?
During ATWS 6 Seconds After Control Rods Inserted
- a.
BLUE Border Box /
BLUE Border Box /
- b.
RED Border Box /
RED Border Box /
SCRAMRODSOUT SCRAM RODS OUT
- c.
BLUE Border Box /
GREEN Border Box /
No SCRAM SCRAM RODS IN W
- d.
RED Border Box /
YELLOW Border Box /
SCRAMRODSOUT SCRAM CMD
Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data I Question #
57 Reference(s):
Learning 0 bjective:
Knowledge/Ability:
Choice
- a.
- b.
C.
- d.
None LLOT0768.4 295037A1.09 I Importance: 2.8 / 3.0 Basis or Justification Correct Answer - SPDS Scram Event Indicator will remain Blue with the text NO SCRAM if both channels of RPS do not de-energize and all rods full in reed switches are closed Incorrect - SPDS Scram Event Indicator will turn Red with the text SCRAM RODS OUT only if both channels of RPS fail to de-energize and all control rods are not fully inserted within 7 seconds of the SCRAM Incorrect - SPDS Scram Event Indicator will turn Green only if both channels of RPS drop out.
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 I Source Documentation 1
I Source:
I New Exam Item Prepared by: Corey Goff
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 58
.v 58 of I00 Unit 2 plant conditions are as follows:
A LOCA has occurred resulting RPV level dropping below the top of active fuel and subsequent major fuel damage Drywell pressure is 18 psig 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 c-
Limerick Generatina Station 2005 NRC Initial Licensina Examination I Source:
Reference( s):
Learning Objective:
Answer Key and Question Data New Exam Item LLOTOI 80.2 GP-8, M-0076 P&ID Question #
58 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - RPV level below -129 will result in a Group 1 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 1.68 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 c
I Source Documentation Knowledge/Ability: I 295038 A I.01 (Description of K&A, from catalog)
I Importance: 3.9 /4.2 Ability to operate and/or monitorthe following as they apply to HIGH OFF-SITE RELEASE RATE: Stack-gas monitoring system Prepared by: Corey Goff
Limerick Generatina Station 2005 NRC Initial Licensina Examination
--I Question: 59 59 of 100 ATTACHMENT Q59 IS PROVIDED Unit 1 is at 100% Reactor power.
I UNIT DIV 1 SFGD BATTERY CHARGERS TROUBLE alarms. An Equipment Operator reports that the 480 VAC MCC supply breaker for the 1Al D103 Battery Charger has tripped.
WHICH ONE of the following identifies the power supply for Division I DC loads following the trip of the 1Al D103 Battery Charger?
- a.
1Al Battery only
- b.
1A2D103 Battery Charger only
- c.
I A I and 1A2 Batteries
- d.
1Al Battery and 1A2D103 Battery Charger
Limerick Generating Station 2005 NRC initial Licensing Examination
- a.
Answer Key and Question Data Incorrect - See "d"
- b.
Incorrect - See "d" Question #
59 Choice I Basis or Justification C.
- 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 Source:
Learning I Obiective:
Reference( s):
I Unit (1,2)
New Exam Item LLOT0690.2 ARC-MCR-I 20 G-I, E-33 sh. I, E-92 sh. I I Source Documentation Knowledge/Ability: I 263000 K I.02 I Importance: 3.2/3.3 (Description of K&A, from catalog)
Knowledge of the physical connections and/or cause effect relationships between D.C.
ELECTRICAL DISTRIBUTION and the following: Battery charger and battery Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination x
Question: 60 60 of 100 Unit 2 plant conditions are as follows:
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 Auto trips enabled engine only
- b.
Emergency Stop on Auto trips disabled engine only L
- c.
Emergency Stop on local Auto trips enabled panel only
- d.
Emergency Stop on local Auto trips disabled panel only
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference (s):
Learning 0 b i ect ive:
'\\_.
Answer Key and Question Data New Exam Item E-33, Load Analysis LLOT0670.10 I Question #
60 I
Choice 6 C.
- d.
Basis or Justification Incorrect - Auto trips require DC control power.
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.
Incorrect - See "c" Required Attachments or Reference I Source Documentation Knowledge/Ability: I 263000 K3.01 I Importance: 3.4/3.8 (Description of K&A, from catalog)
Knowledge of the effect that a loss or malfunction of the D.C. ELECTRICAL DISTRIBUTION will have on the following: Emergency generators Prepared by: Lee Stanford
Limerick Generatina Station 2005 NRC Initial Licensina Examination L.
Question: 61 61 of 100 A Recirculation piping break occurs on Unit I inside primary containment resulting in RPV level lowering to -140 inches.
WHICH ONE of the following describes the status of the 'YA" Instrument Air Compressor and Service Air Compressor?
- a.
Both compressors are available without SE-10-1 breaker reset required
- b.
Both compressors are NOT available until breakers are reset per SE-I 0-1
- c.
"IA" Instrument Air Compressor is available; Service Air Compressor is NOT available until breaker is reset per SE-I 0-1
- d.
Service Air Compressor is available; "IA" Instrument Air Compressor is NOT available until breaker is reset per SE-10-1
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference( s):
Learning 0 bjective:
Knowledge/Ability:
Answer Key and Question Data New Exam Item LLOT0730.15 300000 K2.01 I Importance: 2.8/2.8 Question#
61 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 - " I A instrument air compressor is powered from D134-R-H, and Service air compressor is powered from non-safeguard power. Only "I A" 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 " I A 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 Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 62 62 of 100 v
Unit 1 initial plant conditions are as follows:
OPCON 4 DI 3 Bus is out of service for bus repairs A fire causes a loss of the D22 bus.
WHICH ONE of the following describes equipment available to support Unit 1 Shutdown Cooling?
- a.
1A OC
- b.
IB OD
- c.
IC OC
- d.
1 D OD
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data I
L PRA (Y/N)
SRO 1
N N
Question #
62 Choice I Basis or Justification
- a.
Correct Answer - Y A RHR pump is powered from D I 1 OC RHRSW pump is powered from D21. Both have power.
Incorrect - OD RHRSW pump is powered from D22 which does not have power.
Incorrect - IC RHR pump is powered from D13 which does not have power.
- b.
C.
I
- d.
Incorrect - OD RHRSW pump is powered from D22 which does not have power.
Required Attachments or Reference L.
- I Psychometrics I
Source Documentation Source:
New Exam Item Learning LLOT0660.3 Reference(s):
E-D13, E-D22 Objective:
Knowledge/Ability: 600000 AA2.17 I Importance: 3.1/3.6 (Description of K&A, from catalog)
Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:
Svstems that mav be affected bv the fire.
Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 63 Unit 1 initial plant conditions are as follows:
-L-63 of I00 Reactor power is 80%
RPV pressure is 1027 psig "1 B" Outboard MSlV has failed closed. Current conditions are:
Reactor power is 81 %
One bypass valve is 40% open RPV Pressure is 1060 and stable WHICH ONE of the following describes the required immediate operator action per OT-I 02, 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 L
c
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Knowledge/Ability:
Refe re n ce(s):
Answer Key and Question Data New Exam item LLOTI 540.02 295025 G2.4.49 I Importance: 4.0/4.0 OT-I 02 Question #
63 Choice
- a.
- 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-I 02 does not direct the operator to close the BPVs. They are open to help control pressure.
Correct Answer - OT-I 02, 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.
Required Attachments or Reference I Source Documentation Prepared by: Craig Fritz
Limerick Generatinu Station 2005 NRC Initial Licensinu Examination v
Question: 64 64 of 100 Unit 1 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.
Only "A" RPS de-energized (half-scram)
- b.
- c.
Only "B" RPS de-energized (half-scram)
Both "A" and "B" RPS de-energized (full scram)
'-J
- d.
Neither "A" nor "B" RPS de-energized (no half or full scram)
Cognitive (H, L)
Unit (1. 2)
Limerick Generating Station 2005 NRC Initial Licensing Examination H
PRA (Y/N)
SRO I
N N
Answer Key and Question Data Source:
Reference( s):
Learning Question#
64 New Exam Item C71-1020 GE elementary drawings LLOT0240.8 Choice Objective:
Knowledge/Ability:
- a.
21 5004 K3.01 I Importance: 3.4/3.4
- b.
C.
- d.
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 2x105will cause the SRM to be be upscale, and cause a full scram.
Incorrect - see c justification Required Attachments or Reference I Psychometrics
~
I I Source Documentation Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 65
'v 65 of I00 Unit 1 plant conditions are as follows:
RPV level is -150 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-112, "Emergency Blowdown" and the reason for not performing an Emergency Blowdown until that point?
- a. -1 86 inches; Adequate core cooling is maintained
- b. -201 inches; Delays the emergency depressurization as long as possible
- c.
-1 86 inches; Fuel cladding temperature is maintained below 1800 deg. F
- d. -201 inches; The actual fueled region of the fuel bundles is not uncovered
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference( s):
Learning Objective:
Knowledge/Ability:
Answer Key and Question Data New Exam Item T-I 11 and T-I 1 I Bases LLOTI 560.05 295031 EK3.04 I Importance: 4.014.3 Question#
65 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for b.
Correct Answer - With no RPV injection, when RPV level lowers to below -1 61 inches, the steam cooling section of T-I 11 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-16 directs leaving Steam Cooling and performance of an emergency depressurization.
The bases for T-I 1 I states: "The steam cooling strategy thus delays emergency RPV depressurization for as long as possible.
Incorrect - See justification for b.
Incorrect - See justification for b.
Required Attachments or Reference I Source Documentation Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL: Steam Cooling Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination X
d Question: 66 66 of 100 Unit I plant conditions are as follows:
" I A 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 "1A RHR pump trips and the reason for this action?
- a.
- b.
C.
- d.
Raise RPV level to +65 inches on SHUTDOWN range; ensures water level above steam separator turnaround point Raise RPV level to +75 inches on UPSET range; ensures water level above steam separator turnaround point Raise RPV level to +65 inches on SHUTDOWN range; ensures water level above top of jet pump ram's head Raise RPV level to +75 inches on UPSET range; ensures water level above top of jet pump ram's head
Limerick Generating Station 2005 NRC Initial Licensing Examination
- b.
Answer Key and Question Data 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.
Question#
66 Choice I Basis or Justification
- d.
- a.
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.
Correct Answer - S51.8.B, precaution 3.3 states that 'I Maintaining vessel level above 60 inches on LI-42-*R605 at "OC602 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 78 inches on LR-42-*R608 at OC603 will ensure proper natural circulation."
v Required Attachments or Reference C.
Source :
Reference( s):
Learning Obiective:
Incorrect - 65 inches on SHUTDOWN is okay, but the top of the jet pump ram's h e a r is not the reason, and would not promote natural circulation.
New Exam Item S51.8.B, precautions 3.3, 3.4 LLOT0370.09 I Source Documentation Knowledge/Ability: I 295001 AK2.03 I Importance: 3.6/3.7 (Description of K&A, from catalog)
Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the followina: Reactor water level Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 67 67 of 100 Unit 2 plant conditions are as follows:
An ATWS is in progress Reactor power is 3%
All three SLC pump control switches have just been taken to "START" at 20C603.
WHICH ONE of the following describes the expected response of the Standby Liquid Control System ?
- a.
All three SLC pumps start immediately
- b.
- c.
- d.
All three SLC pumps starts after a 1 I 8 second time delay All three SLC pumps will start immediately IF reactor power rises to 4%
All three SLC pumps will start 118 seconds IF reactor power rises to 4%
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference ( s ) :
Learning Objective:
Knowledge/Ability:
Answer Key and Question Data New Exam Item S48.1.B LLOT0310.05 21 I000 K4.08 I Importance: 4.2/4.2 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 I 1 8 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 I Unit (1, 2)
Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 68 68 of 100 L,
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 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 U
Will not open
L-Cognitive (H, L)
Unit (1, 2)
Limerick Generating Station 2005 NRC Initial Licensing Examination L
PRA (Y/N)
SRO 2
Y N
Answer Key and Question Data Question#
68 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 - 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.
Required Attachments or Reference I Psychometrics L-I I Source Documentation Source:
New Exam Item Learning LLOT0350.07 Objective:
Knowledge/Ability: 209001 A3.02 I Importance: 3.8/3.7 (Description of K&A, from catalog)
Ability to monitor automatic operations of the LOW PRESSURE CORE SPRAY SYSTEM including: Pump start Reference( s):
T-270 Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination
-+,
Question: 69 L-Unit I plant conditions are as follows:
69of I00 A Group I isolation occurred 10 minutes ago The reactor is shutdown and RPV pressure is 950 psig and lo\\ rering 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 controlled and the effect on RPV level over the next thirty minutes?
HPCl Parameter Controlled RPV Level Response
- a.
flow remains steady
- b.
flow rises
- c.
speed remains steady
- d.
speed rises
Limerick Generatina Station 2005 NRC Initial Licensina Examination
- a.
Answer Key and Question Data Incorrect - See justification for d.
Question#
69 Choice I Basis or Justification
- b.
C.
Incorrect - See justification for d.
Incorrect - See justification for d.
- d.
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 discharge pressure) remain constant, flow into the RPV will rise, causing RPV level to rise.
Required Attachments or Reference Cognitive (H, L)
Unit (1, 2)
I I
v H
PRA (Y/N)
SRO I
N N
1 Psychometrics Source:
Reference (s):
Learning Objective:
Knowledge/Ability:
New Exam Item UFSAR section 6.3.2.2.1 LLOT0340.12 206000 K3.01 I Importance: 4.0/4.0 I Source Documentation I
Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 70 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
- a.
Indicated RPV level rises Pressure drop in the reactor causes more void production in the core
- b.
Indicated RPV level rises Lower pressure felt in the level instrument reference legs
- c.
Indicated RPV level lowers Valve opening causes more inventory loss from the RPV
'V
- d.
Indicated RPV level lowers Lower pressure felt in the level instrument variable legs
Limerick Generatina Station 2005 NRC Initial Licensina Examination Cognitive (H, L)
Unit f l. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO I
N N
Question#
70 Source:
Reference(s):
Learning Choice New Exam Item T-I 12 Bases LLOT0330.03
- a.
Objective:
Knowledge/Ability:
- b.
21 8000 AI.05 I Importance: 4.1/4.1 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 L. I Psychometrics I Source Documentation Prepared by: Craig Fritz
Limerick Generatinu Station 2005 NRC Initial Licensing Examination
- Question: 71 71 of 100 Unit I plant conditions are as follows:
Rx power 100%
IAY160 has de-energized due to a fault 5 minutes ago Drywell temperature has risen 8 O F since the loss of 1AY160.
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 Generatina Station 2005 NRC Initial Licensina Examination Source:
Learning 0 bjective:
Knowledge/Ability:
Reference( s) :
Answer Key and Question Data New Exam Item LLOTI 566.02 295020.K3.03 1 Importance: 3.2/3.2 E-lAY160 Question#
71 Choice
- a.
- b.
C.
- d.
Basis or Justification 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 1AY160.
Correct Answer - Loss of lAY160 will cause DWCW isolation which will cause DW temp increase.
Required Attachments or Reference I Source Documentation Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination
-u-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 12 and is the selected rod Control Rod 26-1 5 has as an Insert Limit of 12 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 L
Yes
Limerick Generatina Station 2005 NRC Initial Licensina Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO 1
N N
Question#
72 Source:
Learning 0 bj ect ive :
Knowledge/Ability:
Reference(s):
Choice New Exam Item LLOT0095.03 201 006 K4.01 I Importance: 3 ~ 3. 5 RE-73, L-S-37
- 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.
provide an insert error, since the rod is not inserted Incorrect - See justification for b.
Required Attachments or Reference
~ - - I Psychometrics I
Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination b
Question: 73 73 of 100 Unit 1 plant conditions are as follows:
End of cycle coastdown with reactor power at 97%
Both Reactor Recirculation Pumps are operating at approximately 110% speed While attempting to slightly raise the speed of the "IA" Reactor Recirculation Pump, the I A RECIRC M-G FLUID DRIVE SCOOP TUBE LOCK annunciator (1 I 1 RECIRC, B-3) alarms.
The Reactor Operator depresses the "LOWER" speed demand pushbutton for the I'IA Reactor Recirculation Pump.
WHICH ONE of the following describes the reason for the alarm and the expected response of the "1A Reactor Recirculation Pump?
Reason for the alarm Response to a lower speed demand signal
- a.
High electrical stop Speed lowers
- b.
High electrical stop Speed does not change
- c.
High mechanical stop Speed lowers L
- d.
High mechanical stop Speed does not change
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1, 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 1
N N
Question #
73 Source:
Reference(s):
Learning 0 bjective:
Knowledge/Ability:
Choice New Exam Item LLOT0040.14 202002 K3.05 I Importance: 3.2/3.3
- a.
- b.
C.
- d.
Basis or Justification Incorrect - speed will not change, since the scoop tube lock prevents the scoop tube positioner motor from being energized in either direction.
Correct Answer - the scoop tube lock alarm is indicative of being on the high electrical stop, which will de-energize the scoop tube motor is both directions. A lower speed signal will not result in a change is recirc pump speed.
Incorrect - The mechanical stop will not be reached until about 2% speed past the electrical stop, and speed will not change.
Incorrect - The mechanical stop will not be reached until about 2% speed past the electrical stop.
Required Attachments or Reference I Psychometrics I
I Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination L' Question: 74 74 of I00 ATTACHMENT Q74 IS PROVIDED Unit 2 plant conditions are as follows:
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
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1, 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 2
N N
Question #
74 Source:
Reference( s) :
Learning 0 bjective:
Knowledge/Ability:
Choice New Exam Item GP-5, Attachment 5 LLOT0600.10 Generic 2.1.25 I Importance: 2.8/3.1
- a.
- b.
C.
- d.
Basis or Justification Incorrect - 250 could be believed to be correct if the candidate believes the 0.98 power factor must be maintained.
Incorrect - 395 would be correct if the candidate misread the graph by using 1200 MWe instead of 1175 MWe.
Correct Answer - Using GP-5 Attachment 5, Estimated Generator Capability Curve at Various Hydrogen Gas Pressures, with MW at 1175, the MVAR limit at the 75 psig hydrogen gas pressure line is approximately 470 MVARs.
Incorrect - 560 would be correct if the candidate misread the graph by using 1 150 MWe instead of 1 175 MWe Required Attachments or Refere n ce GP-5, Attachment 5 (Estimated Generator Capability Curve at Various Hydrogen Gas Pressures)
I Psychometrics I
I Source Documentation Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 75
.L 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 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 R1 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 Generatina Station 2005 NRC Initial Licensina Examination Cognitive (H, L)
Unit (1, 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 2
N N
Question#
75 Reference( s):
Learning Choice GP-8 (U/2)
LLOTOI 80.02
- a.
Objective:
Knowledge/Ability:
- b.
223002 A4.03 I Importance: 3.6/3.5 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 "B". 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.
GP-8 (U/2) (Do not give GP-8.1,8.2, 8.3,8.4, or 8.5)
Required Attachments or Reference I
I I
I Psychometrics I
I Source Documentation I Source:
I New Exam Item Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination u Question: 76 76 of I00 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 Flow test Suppression Pool Temperature is 97°F and rising slowly WHICH ONE of the following describes required actions per Tech Specs for the conditions above?
- a.
No action until average Suppression Pool temp exceeds 105°F
- b. 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 />
- c.
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 />
- d. Secure HPCl and lower 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 />
- i.
L-,
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference (s ) :
Learning Answer Key and Question Data New Exam Item Tech Spec 3.6.2.1 LLOTOI 30.1 1 Question #
76 Objective:
Knowledge/Ability:
Choice 295026 Generic 2.23 I Importance: 3.8
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Per TS 3.4.6.2 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 a1 justification Incorrect - see a justification Required Attachments or Reference Tech Specs I Source Documentation Ability to track limiting conditions-for operations: Suppression Pool High Water Temperature Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 77
-+-
77 of IO0 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:
108 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.
- b.
'5-C.
- d.
Raise CST level to above 33 feet per S08.0.C, Transferring Water Between the RWST and the CST Place alternate CRD Drive Water Filter in service per S46.6.C, Placing Alternate Control Rod Drive Water Filter in Service Open 46-1 F045, "Pump Suction Filter Bypass Valve" per ON-107,Control Rod Drive System Problems Place FV-46-1 F002A, "A CRD Flow Control Valve" in service per S46.6.B, Placing Alternate CRD Hydraulic System Flow Control Valve in Service
Limerick Generating Station 2005 NRC Initial Licensing Examination I Learning I LLOT0070.05,09 Answer Key and Question Data Objective:
Knowledge/Ability:
Question #
77 Choice I Basis or Justification 295022 G2.1.20 I Importance: 4.2
- a.
- b.
C.
- d.
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-I 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 I
I I
I Source Documentation Source:
I New Exam Item Refe re n ce(s I:
I ON-I07 Loss of CRD Pumps: Ability to execute procedure steps Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination u Question: 78 78 of I00 Unit 2 plant conditions are as follows:
OPCON 4 "2B" RHR is in Shutdown Cooling per S51.8.B, 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 following describes the effect on "2B" RHR Shutdown Cooling and the required action to restore cooling?
Effect on "2B" RHR Shutdown Cooling Required Action
- a.
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 L
- b.
Remains in service without Start " O A RHRSW Pump per S12.1.A, RHR heat exchanger cooling water Service Water System Startup
- c.
RHR Pump trips and can not be restarted 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)
- d.
Remains in service without Start "OD" RHRSW Pump per S12.1.A, RHR Service Water System Startup heat exchanger cooling water
Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data I Question #
78 Source:
Reference( s):
Learning Objective:
KnowledgelAbility:
1 Choice I Basis or Justification New Exam Item S51.8.B, S12.1.A LLOT0400.06 205000 A2.08 1 Importance: 3.5
- a.
- b.
C.
- d.
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 "OR' 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 "28" RHR Heat Exchanger.
Required Attachments or
- I Reference Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination
-~ Question: 79 79 of 100 Unit 1 plant conditions are as follows:
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?
Ability to continue lowering the bundle into the core Procedure Guidance In
- a.
Continued lowering of the bundle ON-I 20, "Fuel Handling is permitted Problems
- b.
Continued lowering of the bundle FH-105, Core Component
- c.
Bundle lowering may not continue ON-I 20, "Fuel Handling is permitted until countrate stabilizes Problems Movement - Core Transfers L.'
- d.
Bundle lowering may not continue FH-I 05, Core Component until countrate stabilizes Movement - Core Transfers
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (I.
- 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 1
N 1 OCFR55.43. b.6 Question #
79 Source:
Learning Objective:
Knowledge/Ability:
Reference(s):
Choice New Exam Item LLOT0760.10 Generic 2.2.32 I Importance: 3.3 FH-105, ON-I 20
- 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-105 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 L
1 Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 80 i-
~
80 of 100 ATTACHMENT Q80/Q91 IS PROVIDED Unit I 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-I 12, Emergency Required Blowdown Required L-
- a.
T-103, Secondary Containment Control AND T-I 04, Radioactivity Release Control
- b.
T-103, Secondary Containment Control, only
- c.
T-103, Secondary Containment Control AND T-104, Radioactivity Release Control
- d.
T-103, Secondary Containment Control, only Yes Yes No No
i-Required Attachments or Reference Limerick Generating Station 2005 NRC Initial Licensing Examination LGS 3-1 : Emergency Action Level (EAL) Matrix T-I 04 T-I 03 Answer Key and Question Data Question #
80 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - see justification for c Incorrect - see justification for c 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 reauired.
T-I04 is required per LGS EAL annex Table 3-1. Release level is not at or Incorrect - see justification for c I
I I
I Source Documentation Source:
I New Exam Item Reference(s1:
I EP-AA-I 008. T-I 03. T-I 04 Learning LLOTl560.02,6 Objective:
Knowledge/Ability: Generic 2.4.1 I Importance: 4.6 (Description of K&A, from catalog)
Knowledge of EOP entry conditions and immediate action steps.
~~
~~
Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination L-Question: 81 81 of 100 Unit I plant conditions are as follows:
100% reactor power Normal electrical lineup A 220 KV Substation fault results in a Main Generator Lockout and loss of the I O 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?
Change in Reactor Pressure and Level 10 seconds after Lockout Procedural Action Required to Mitigate Effect
- a.
Reactor pressure and level will both be lower Restore and maintain RPV level between
+ I 2.5 to 54 inches per T-101, RPV Control
- b.
Reactor pressure will remain the same and reactor level will be lower Restore and maintain RPV level between
+ I 2 5 to 54 inches per T-101, RPV Control L
- c.
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
- d.
Reactor pressure will remain the same and reactor level will be lower Restore reactor level to +35 inches by manually controlling Reactor Feedwater Pumps per OT-I 00, Reactor Low Level
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 1
Y 1 OCFR55.43.b.5 Question#
81 Reference( s):
Learning Choice E-Dl 1, E-IO LLOT0640.06
- 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-101.
Incorrect - Reactor pressure will drop following the scram and level control must be directed from T-I 01 following the scram.
Required Attachments or I Reference L-I Psychometrics Source Documentation Source:
I New Exam Item Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination
- c. Question: 82 82 of 100 ATTACHMENT Q82 IS PROVIDED 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 "2B" 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-51-2FOO8 occurs.
WHICH ONE of the following describes required operator action, and the estimated minimum time before RPV temperature rises to 212 O F ?
Required Action Time to 21 2°F
- a.
Restore Shutdown Cooling per ON-121, 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> Loss of Shutdown Cooling L
- b.
Place "2C" RHR in Shutdown Cooling 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> per S51.8.H, Use of Dedicated LPCl Pumps for Shutdown Cooling/Reactor Coolant Circulation Operation
- c.
Restore Shutdown Cooling per ON-121, 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> Loss of Shutdown Cooling
- d.
Place "2C" RHR in Shutdown Cooling 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> per S51.8.H, Use of Dedicated LPCl Pumps for Shutdown Cooling/Reactor Coolant Circulation Operation
Cognitive (H, L)
Unit (1. 2)
Limerick Generating Station 2005 NRC Initial Licensing Examination H
PRA (Y/N)
SRo-2 N
1 OCFR55.43.b.5 Answer Key and Question Data 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-I 21, 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 />.
S51.8.H is not appropriate, since it will not defeat the isolation of HV-51-2F008.
Incorrect - See justification for b.
ON-121, S51.8.H Required Attachments or Reference I Psychometrics Source Documentation Source:
New Exam Item Learning LLOTI 550.03 Reference( s):
ON-I 21 Objective:
Knowledge/Ability: 295021 AA2.01 I Importance: 3.6 (Description of K&A, from catalog)
Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOL1 NG: Reactor water heatudcooldown rate Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 83
.u 83 of I00 Unit 2 initial plant conditions are as follows:
2H SRV is stuck open Reactor Power is 50% with an ATWS 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 1100 psig.
WHICH ONE of the following describes required actions for the conditions above?
- a.
- b.
C.
L
- d.
Rapidly depressurize using Turbine Bypass Valves per T-101 RPV Control, due to reactor pressure above 1096 psig Enter T-I 12, Emergency Blowdown, due to unsafe on PC/P-3 PRESS SUPP PRESS curve in T-I 02, Primary Containment Control Enter T-I 12, Emergency Blowdown, due to unsafe on SP/T-I HEAT CAPACITY TEMP LIMIT curve in T-102, Primary Containment Control Reduce reactor pressure per T-I 01, RPV Control to maintain on the safe side of SP/T-I HEAT CAPACITY TEMP LIMIT curve in T-102, Primary Containment Control, due to reactor pressure above 1096 Psig
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 2
Y 1 OCFR55.43. b.5 Question #
83 Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - T-I 12, Emergency Blowdown is required due to exceeding SP/T-l curve in T-I 02. 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-102 has not been exceeded.
Correct Answer - T-112, Emergency Blowdown is required due to exceeding SP/T-1 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 'IC".
T-101, T-I02 Required Attachments or Reference L
I Psychometrics I
Source Documentation Source:
I New Exam Item Reference(s):
T-I 02, T-I 01 Learning LLOTI 560.04 Objective:
Knowledge/Ability: 295030 Generic 2.4.16 I Importance: 4.0 (Description of K&A, from catalog)
Knowledge of EOP implementation hierarchy and coordination with other support procedures:
Low Surmression Pool Water Level Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination L
Question: 84 84 of I00 The following has occurred on Unit 1 :
A feedwater level control malfunction has caused RPV level to rise to +I30 inches YA" RFP has tripped "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 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?
L
- a.
Immediately reduce RPV pressure below 1053 psig using the Jack to open Bypass Valves per OT-102, "Reactor High Pressure"
- b.
Immediately reduce RPV pressure below 1053 psig using Pressure Set to open Bypass Valves per OT-402, "Reactor High Pressure"
- c.
When RPV pressure reaches 1096 psig, then reduce pressure using "1 J" SRV per OT-I I O, "Reactor High Level"
- d.
When RPV pressure reaches 1096 psig, then reduce pressure using "I
K" SRV per OT-I 10, "Reactor High Level"
Choice
- a.
- b.
Limerick G e n e rating Stat ion 2005 NRC Initial Licensing Examination Basis or Justification Incorrect - While OT-I02 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.
Incorrect -While OT-I02 does direct reducing pressure to below 1053 psig, since the Answer Key and Question Data
- d.
reduce/maintain RPV pressure below 700 psig.
Incorrect - This is incorrect, because if By 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 likely to be broken in that area.
C.
Source:
Reference(s):
reactor is scrammed, OT-I02 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-I 10 step 3.1 7 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 B, C, OR J SRV to New Exam Item OT-I 02. OT-I I O Learning 0 bjective:
Knowledge/Ability:
Required Attachments or Reference LLOTI 540.05 295008 AA2.01 I Importance: 3.9 I Source Documentation 1
Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination L
Question: 85 85 of 100 Unit I 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?
Cause of the Isolation Effect on Drywell Pressure
- a.
- b.
C.
- d.
Valid Inadvertent Valid Inadvertent 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 performed Will remain constant until GP-8.3, Isolation Reset is performed
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (I,
- 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 1
N I
OCFR55.43.b.5 Question#
85 Source:
Learning Reference (s):
Choice New Exam Item LLOTOI 80.6 GP-8, 8.3, 8.5
- a.
Objective:
Knowledae/Abilitv:
- b.
295020 AA2.01 I ImDortance: 3.7 C.
- d.
Basis or Justification Incorrect - See b justification Correct Answer - Isolation is inadvertent DWCW isolates on Drywell pressure of 1.68 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.
Required Attachments or Reference I Psychometrics L.
I 1 Source Documentation (Description of K&A, from catalog)
Ability to determine and/or interpret the following as they apply to INADVERTENT CONTAINMENT ISOLATION: Drywell/containment pressure Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 86 v
ATTACHMENT Q86 IS PROVIDED 86 of I00 Unit 1 is at 100% reactor power.
A loss of power de-energizes solenoid valves SV-59-150A, 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 Action Required to Mitigate the Effect
- a.
Partial loss of N2 Supply Ensure Instrument Gas Bottle 1AS252 aligned to supply SRVs per S59.8.A, Placing Automatic Depressurization System Backup Nitrogen Supply System In Operation
- b.
Total loss of N2 Supply
- c.
Partial loss of N2 Supply
- d.
Total loss of N2 Supply Ensure Instrument Gas Bottle lAS252 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 I T558 to supply SRVs per SE-1-1, Protected Depressurization Control (Long Term Operation)
Align Diesel Generator Starting Air Receiver 1 A I 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 [I.
- 2)
Answer Key and Question Data H
PRA (Y/N)
SRO 1
N 1 OCFR55.43.b.5 Question#
86 Choice
- a.
- b.
C.
Basis or Justification Correct Answer - SV-59-150A failing closed will only affect one source of NP 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.
- d.
M-59 Sheet 1 Required Attachments or Reference I Psychometrics Source Documentation Source :
I New Exam Item Reference(s):
M-59, S59.8.A, SE-1-1 Learning LLOT0730.13,14 Objective:
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) based on those predictions, use procedures to correct, control, or mitigate the consequences of these abnormal conditions or operations: Loss of air supply to ADS valves Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 87 87 of 100
\\--
Unit 2 plant conditions are as follows:
100% reactor power RClC 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.
u
- b.
C.
- d.
Outboard only Inboard and Outboard Outboard only Inboard and Outboard Isolation can be bypassed with Reactor Level c -1 61" per T-242, Defeat of H PC VRC I C I solation Logic Isolation can be bypassed with Reactor Level < -161" per T-242, Defeat of HPCVRCIC Isolation Logic Isolation can be bypassed with Reactor Level 42.5 " per T-249, HPCI/RCIC High Area Temperature Isolation Bypass Isolation can be bypassed with Reactor Level ~ 1 2. 5
'I per T-249, HPCI/RCIC High Area Temperature Isolation Bypass
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Knowledge/Ability:
Reference( s):
L I Answer Key and Question Data New Exam Item LLOT0340.07, LLOT1561.04 206000 A2.10 I Importance: 4.1 T-101, T-1 I I
, T-242, T-249 I Question #
87
- b.
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 1 I, 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.
T-242.
Incorrect - Although T-101 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.
Required Attachments or Reference T-I 01 T-I 11 Source Documentation Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 88 88 of 100 v
Unit I 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-I.
WHICH ONE of the following will permit removal of D13 Diesel Generator Air Start Receiver I
C1 T558 from service?
- a. Restore D12 Diesel Generator to operable
- b. Add 1,800 gallons to D14 Diesel Generator Storage Tank
- c.
Transfer 60 gallons to the D14 Diesel Generator Day Tank
- d. Ensure D13 Diesel Generator Air Start Receiver 1 C2T558 pressure is greater than 225 psig L
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Reference(s1:
I Answer Key and Question Data New Exam Item T.S. 3.8.1.2.a I Question#
88 Learning 0 bject ive:
Knowledge/Ability:
Basis or Justification 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 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.
LLOT0670.13 264000 G2.2.24 I Importance: 3.8 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.
Tech Spec 3.8.1.2 Required Attachments or Reference
\\
I Source Documentation Prepared by: Tim Kan
Limerick Generatina Station 2005 NRC Initial Licensina Examination u
Question: 89 89 of 100 Unit 2 plant conditions are as follows:
OPCON 5 Reactor cavity flooded up to +496 inches 2B 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 Spray Pump Discharge Both spent fuel pools are connected through the cask pit per S53.0.C, Connecting Fuel Storage Pools to Cask Storage Pit Including Cross Connecting Fuel Storage Pools Unit 1 Fuel Pool Cooling is in service with 2 pumps and 1 demineralizer Unit 2 Fuel Pool Cooling is not in service A crud burst has caused Spent Fuel Pool radiation monitor alarms, with an indicated reading of 40 mr/hr.
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 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 2B RHR from Shutdown Cooling mode per S51.8.B, 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 Choice
- a.
. I Answer Key and Question Data 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.
I Question #
89
- d.
Incorrect - Installing Fuel Pool gates will not lower Refuel Floor radiation levels.
- b.
Source:
Reference (s) :
Learning Objective:
Knowledge/Ability:
C.
New Exam Item S53.1.A LLOT0750.7 233000 G2.3.10 I Importance: 3.3 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.
Required Attachments or Reference I Source Documentation Prepared by: Tim Kan
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 90 L.
90 of 100 Unit 2 plant startup is in progress with the following two activities scheduled for the next two hours:
Main Generator purging with hydrogen Traversing In-core Pro be (TIP) operations WHICH ONE of the following describes the plant personnel notifications that are required during this two hour period?
Notification for Generator Purae Notification for TIP Operations
- a.
- b.
C.
- d.
No cutting, smoking, welding, or open flames permitted in the Turbine Enclosure per S28.5.D, Generator Purging - C02 to H2 No cutting, smoking, welding, or open flames permitted in the Turbine Enclosure per S28.5.D, Generator Purging - C02 to H2 Access restricted to the Unit 1 and Unit 2 Turbine Enclosure until Generator purging is complete per SE-24, lnplant Evacuations Access restricted 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 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 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
L-
- a.
Limerick Generatina Station 2005 NRC Initial Licensina Examination Incorrect - See justification for b.
Answer Key and Question Data
- d.
Question#
90 Choice I Basis or Justification Incorrect - See justification for b.
Source:
Reference (s ):
Learning Obiective:
- b.
New Exam Item S28.5.D, S74.0.A LLOTI 563.01 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.
Required Attachments or Reference I Source Documentation I
Knowledge/Ability: I Generic 2.1.I4 I Importance: 3.3 (Description of K&A, from catalog)
Knowledge of system status criteria which requires the notification of plant personnel Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination L--
Question: 91 91 of 100 ATTACHMENT Q80/Q91 IS PROVIDED Unit I 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, UnexpectedlUnexplained 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 Shift Manager Role
- a.
- b.
U' C.
- d.
MS4 MA4 MS4 MA4 Direct Shift Communicator to initiate required State/Local notifications per EP-MA-114-100, Mid-Atlantic State/Local Notifications Direct Shift Communicator to initiate NRC Notification per EP-AA-114, Notifications Direct Shift Communicator to initiate NRC Notification per EP-AA-114, Notifications Direct Shift Communicator to initiate required State/Local notifications per EP-MA-114-100, Mid-Atlantic State/Local Notifications
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (1. 2)
Answer Key and Question Data H
PRA (Y/N)
SRO I
Y 1 OCFR55.43.b.5 Question#
91 Source:
Learning Objective:
Knowledge/Ability:
Reference(s):
Choice New Exam Item Exelon Generic lesson plan G5.08 Generic 2.1.06 I Importance: 4.3 EP-AA-1008, EP-AA-112-100
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for "d" Incorrect - See justification for '%I1' 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 per EP-MA-114-100.
LGS 3-1 : Emergency Action Level (EAL) Matrix Required Attachments or Reference
+_. I Psychometrics I Source Documentation Prepared by: Lee Stanford
Limerick Generating Station 2005 NRC Initial Licensing Examination V
Question: 92 92 of 100 Unit 1 plant conditions are as follows:
100% reactor power IA lsophase Bus Cooling Fan tripped 1 B lsophase Bus Cooling Fan started automatically FIN team members removed the 1A lsophase Bus Cooling Fan breaker per S34.2.C, Removing/lnstalling an lsophase Fan MCC Breaker When lsophase Cooling is Required to be in Service with the following conditions:
1A 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?
Status of 1 B lsophase Bus Cooling Fan after 1A Fan Breaker Removed Procedure to use to remove the IA lsophase Bus Cooling Fan Breaker L
- a.
- b.
C.
- d.
Running Running MA-MA-7 1 6-004-1 000, Troubles hooting, Rework, and Testing (TRT) Control Manual for Peach Bottom and Limerick S93.O.B, 480 VAC Non-Safeguard MCC Compartment Removal Not running MA-MA-71 6-004-1 000, Troubleshooting, Rework, and Testing (TRT) Control Manual for Peach Bottom and Limerick Not running S93.O.B, 480 VAC Non-Safeguard MCC Compartment Removal
Limerick Generating Station 2005 NRC Initial Licensing Examination Question#
92 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 1
I I
Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensing Examination Question: 93 93 of IO0 Unit 2 plant conditions are as follows:
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 and required authorization for release of key?
Type of Locked High Radiation Area for 4B Feedwater Heater Room Required Authorization for Release of Key
- a. Level I RP Supervision
- b. Level 1 Operations Shift Manager
- c.
Level 2 RP Supervision
- d.
Level 2 Operations Shift Manager L
c Cognitive (H, L)
Unit (1, 2)
Limerick Generating Station 2005 NRC Initial Licensing Examination L
PRA (Y/N)
SRO 2
N 1 OCFR55.43. b.4 Answer Key and Question Data Objective:
Knowledge/Ability:
Question #
93 I
Generic 2.3.1 I Importance: 2.6/3.0 Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Greater that 1000 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 I OCFR20. RP supervision must maintain oversight of the keys to all Locked High Radiation Areas per RP-LG-460-1016 Incorrect - see a justification Incorrect - see a justification Incorrect - see a justification Required Attachments or Reference I Source Documentation Source:
I New Exam Item ReferenceW:
I RP-LG-460-1016. RP-LG-460-1010. 1 OCRF20 Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination v
Question: 94 94 of 100 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.
Raise reactor pressure to greater than 900 psig per GP-2, Normal Plant Startup
- b. Place the reactor mode switch in the "SHUTDOWN " position per Technical Specifications
- c.
Manually scram the reactor if a CRD pump cannot be started within 20 minutes per ON-I 07, Control Rod System Problems
\\-a
- d.
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 Cognitive (H, L)
Unit (1, 2)
Answer Key and Question Data L
PRA (Y/N)
SRO I
N 1 OCFR55.43.b.5 Question #
94 Source:
Reference(s):
Learning Objective:
Knowledge/Ability:
Choice New Exam Item T.S. LCO 3.1.3.5 LLOT0060.12 295006 G2.1.I 2
I Importance: 4.0
- a.
- b.
C.
- d.
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)
Incorrect - This would be correct if only one accumulator was inop. (Action a.1.a)
Required Attachments or Reference I Psychometrics I Source Documentation Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination v
Question: 95 95 of 100 Unit 1 plant conditions are as follows:
OPCON 5 Reactor Disassembly is progress per M-041-200, Reactor Pressure Vessel Unit 1 Reactor Cavity is flooded and connected to the Unit 1 Spent Fuel Pool Seal #4 (Reactor Well Bottom Seal) is deflated and removed from service Unit 1 Dryer / Separator Equipment Pit is flooded and connected to the Unit 1 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 1 Spent Fuel Pool Action Required to terminate Unit 1 Spent Fuel Pool Level Loss
- a.
Will lower until level is below top of irradiated fuel seated in Install Fuel Pool Gates Between Fuel Storage Pool and Reactor Well per the Spent Fuel Pool M-097-009
- b.
Will lower until level is below top of irradiated fuel seated in the Spent Fuel Pool Install Dryer / Separator Storage Pool Stop Logs per M-041-023
- c.
Will lower until level is I O inches above top of Spent Install Fuel Pool Gates Between Fuel Storage Pool and Reactor Well per Fuel Rack M-097-009
- d.
Will lower until level is 10 inches above top of Spent Fuel Rack Install Dryer / Separator Storage Pool Stop Logs per M-041-023
c Limerick Generating Station 2005 NRC Initial Licensing Examination Answer Key and Question Data Question #
95 Choice
- 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 #4 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 S53.0.A for lowering Fuel Pool Level. Direction is provided in S53.O.A to install the Fuel Pool Gates. This action will isolate the Fuel Pool from the leaking seals in the Reactor Well. Replacing the stoplogs in the Dryer / Separator will have no effect on minimizing fuel pool level loss.
Incorrect - See c justification Required Attachments or Reference I LL0T0750.1 I
I Knowledge/AbiIity: I 295023 AA2.02 I Importance: 3.7 (Description of K&A, from catalog)
Ability to determine and/or interpret the following a they apply to Refueling Accidents: Fuel Pool Level Prepared by: Tim Kan
Limerick Generating Station 2005 NRC Initial Licensing Examination i, Question: 96 96 of 100 The following actions have be taken on Unit 2:
A manual reactor scram was initiated from 100% power I O 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 Standby Liquid Control (SLC) has not injected 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 I
.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 L.
- a.
Perform T-214 and T-215 per steps RC/Q-5 and RC/Q-13 Manually inject SLC per step RC/Q-16
- b.
Perform T-214 and T-215 per steps RC/Q-5 and RC/Q-I3 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-I 6 RC/Q-I 3
- d.
Perform T-217 and T-218 per step Do not inject SLC per step RC/Q-4 RC/Q-13
Limerick Generatina Station Source:
Learning Reference(s):
2005 NRC Initial Licensina Examination New Exam Item LLOTI 560.06 T-I 01 Answer Key and Question Data Question#
96 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-13, 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 # I 6) is not met per RWQ-4 and continuing at step RC/Q-I2 only is not appropriate and does not preclude the injection of SBLC.
Incorrect - See justification for c.
T-I 01 Required Attachments or Reference I Source Documentation I Obiective:
I Knowledge/Ability: I 21 1000 G2.4.06 I Importance: 4.0 (Description of K&A, from catalog)
Stand bv Liauid Control Svstem: Knowledae of svmDtom based EOP mitiaation strateaies Prepared by: Craig Fritz
Limerick Generatina Station 2005 NRC Initial Licensina Examination Question: 97 97 of I00 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 "2B" RHR Basis for Decision
- a.
Inject into the RPV with both loops of RHR per T-I16 Adequate Core Cooling is not assured
- b.
Place both loops of RHR in T-I02 and S51.8.A L
Suppression Pool Cooling per Primary Containment is threatened by exceeding heat capacity temperature limit of the Suppression Pool
- c.
Spray the Drywell with one loop of RHR and spray the Suppression Pool with the other loop of RHR per T-102 and T-225 Primary Containment is threatened by direct pressurization of the Suppression Pool
- d.
Inject into the RPV with one loop of RHR per T-I16 and spray the Drywell with the other loop of RHR per T-I02 and T-225 Adequate Core Cooling is not assured AND Primary Containment is threatened by direct pressurization of the Suppression Pool
L-L Cognitive (HI L)
Unit (1, 2)
- I..-
H PRA (Y/N)
SRO 2
Y I
OCFR55.43.b.5 Limerick Generating Station 2005 NRC Initial Licensing Examination Choice
- a.
- b.
C.
- d.
Basis or Justification Correct Answer - Conditions given are on the unsafe side of the Reference Leg Saturation Limit Curve (DW/T-I) in T-I 02. 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-I 02 steps PUP-5 and PUP-9 for spraying the suppression pool and drywell provide the direction to initiate sprays "unless required for core cooling". T-I 02 step SP/T-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-I 02, T-I 16 Required Attachments or Reference I Psychometrics I
Source Documentation Source:
New Exam Item Learning LLOTI 560.06 Objective:
Knowledge/Ability: 21 6000 G2.4.22 I Importance: 4.0 (Description of K&A, from catalog)
Nuclear Boiler Instrumentation: Knowledge of the bases for prioritizing safety functions during a bnormaVemeraencv oeerations Reference( s) :
T-102, T-I 16 Prepared by: Craig Fritz
Limerick Generating Station 2005 NRC Initial Licensing Examination Question: 98 Unit 1 plant conditions are as follows:
\\.
98 of 100 100% reactor power YA" 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 required procedural action?
RWCU System Status One Minute Later Required P rocedu ra I Act ion c-
- a.
RWCU isolated and "IA" RWCU Pump tripped on low 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 YA" RWCU Pump tripped on low RECW pressure and RWCU is not isolated
- b.
- c.
- d.
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
Limerick Generating Station 2005 NRC Initial Licensing Examination Source:
Learning Objective:
Knowledge/Ability:
Reference(s):
Answer Key and Question Data New Exam Item LLOTI 55003 204000 A2.01 I Importance: 3.4 ON-I 13, ARC-MCR-112 G-2 Question #
98 I
Choice
- a.
- b.
C.
- d.
Basis or Justification Incorrect - See justification for "b".
Correct Answer - "1A RWCU Pump will trip on low RECW pressure after I O 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 Unit (I, 2)
Source Documentation Prepared by: Tim Kan c
Limerick Generating Station 2005 NRC Initial Licensina Examination v
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 VENT E-I, "HIGH TOXIC CHEMICAL CONC."
WHICH ONE of the following describes the action that is the highest priority?
- a.
Don Self-contained Breathing Apparatus per SE-2, Toxic Gadchlorine
- b.
Reduce generator reactive load to zero (0 MVAR) to minimize Generator Stator amps per ON-I 01, Loss of Isolated Phase Bus Cooling
- c.
Initiate Control Room chlorine /toxic chemical isolation per S78.8.A, Manual Initiation Of Control Room Radiation Or Chlorine / Toxic Chemical Isolation.
- d.
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 (1. 2)
Answer Key and Question Data L
PRA (Y/N)
SRO I
N I
OCFR55.43.b.5 Question#
99 I
Source:
Reference( s):
Learning Obiective:
Choice
- a.
New Exam Item SE-2, ON-I 01, Arc 002 VENT E-I, Arc 11 8 SERVICE 1-2 LLOT1563.2
- b.
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 lsophase bus cooling, and it is not an immediate operator action Required Attachments or Reference I Psychometrics L
1 Source Documentation Knowledge/Ability: I Generic 2.4.45 I Importance: 3.6 (Description of K&A, from catalog)
I Abilitv to prioritize and interpret the sianificance of each annunciator or alarm.
I Prepared by: Craig Fritz
Limerick Generating Stat ion 2005 NRC Initial Licensing Examination v Question: I00 100 of 100 Unit I 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 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 I
oc201 PI-42-1 R011 (PI-C61-1 R011) on panel
- b.
ADS SRVs per SE-6, Alternate PIS-42-1N690B, on panel lOC618 Remote Shutdown
- c.
C, A, N SRVs per SE-1, Remote Shutdown PIS-42-1 N690B, on panel I OC618
- d.
ADS SRVs per SE-6, Alternate Remote Shutdown 1 oc201 PI-42-1 R011 (PI-C61-1 ROI 1) on panel
Limerick Generating Station 2005 NRC Initial Licensing Examination Cognitive (H, L)
Unit (I, 2)
Question # 100 H
PRA (Y/N)
SRO 1
N I
OCFR55.43.b.5 Choice Source:
Learning Objective:
Knowledge/Ability:
Reference(s):
- a.
New Exam Item LLOT0735.05 29501 6 AA2.03 SE-1, SE-6, E-33, E-102, C61-I 050-E-003 I Importance: 4.4
- b.
C.
- d.
Basis or Justification Incorrect - See justification for "b".
Correct Answer - SE-1 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 R01 I Pressure Indicator is powered from Division 1 DC and is not available.
Required Attachments or Reference I Psychometrics I
I Source Documentation Prepared by: Lee Stanford