ML022400066
| ML022400066 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/10/2002 |
| From: | Pisano L Constellation Nuclear |
| To: | Caruso J, Miller H NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-410/02301, NMP-97925 50-410/02301 | |
| Download: ML022400066 (130) | |
Text
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PO. Box 63 P Z CE I VE D Lycoming, New York 13093 RUE li ION I Constellation fl?7 fJ,% f I AM f
NMP-97925 Nuclear UJune 10, 2002 Nine Mile Point Nuclear Station A Member of the Constellation Energy Group Mr. Hubert J. Miller Regional Administrator USNRC Region I 475 Allendale Road King of Prussia, PA 19406 ATTENTION: Mr. John Caruso
SUBJECT:
NINE MILE POINT UNIT 2 INITIAL OPERATOR WRITTEN EXAMINATION SUBMITTAL Mr. Miller:
In response to the NRC Corporate Notification Letter dated April 1, 2002, arrangements were made for the administration of licensing examinations at Nine Mile Point, Unit 2 during the week of July 29, 2002.
The examinations are being prepared based on the guidelines in Revision 8, Supplement 1, of NUREG 1021, "Operator Licensing Examination Standards for Power Reactors." To meet the examination schedule, Nine Mile Point Nuclear Station is required to furnish the examinations by June 11, 2002.
Please withhold these examination materials from public disclosure until after the examinations have been completed.
If you have any questions regarding the submittal, please contact me at (315) 349-2073 or Mr. Jerry Bobka at (315) 349-2569.
Since
, Louis E. Pisano Manager Nuclear Training LEP/crr
ES-401 Site-Specific Written Examination Form ES-401-8 Cover Sheet S. -I tc t-aI j Ilili alion starts.
icant Certification own. I have neither given nor received aid.
Applicant's Signature Results
__JkQL__
Points
__________ Points
________Percent 43 of 46 NUREG-1021, Revision 8, Supplement I
Proposed Question: RO 1, SRO 32 With the plant at 28% power, a Generator armature fault occurs.
Which one of the following identifies the effect this would have on the Main Turbine?
A.
Main Turbine trips B.
Turbine Load Reject occurs C.
Turbine Load is runback to 25%
D.
Main Turbine remains on-line at previous load Proposed Answer: A Justification:
A correct - Main Turbine trips/armature protected.
B incorrect - 40% imbalance cannot actuate at the power level.
C incorrect - Loss of stator water response D incorrect-reverse of RPS interlock knowledge Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-245-2-02 (Page.39), EO-1.5 KA:
295005, Main AK 2.04, Main Generator Protection Turbine Generator Trip 10 CFR Part 55 Content:
55.41(4 X
Question Source:
Bank #
Modified Bank #
New X
History uestion Cognitive Level:
Memory or Fundamental Knowledge Questo Cg Comprehension or Analysis l
LOD:
2 Comments: None
Examination Outline Cross-reference:
1 1
Group#
1 1
KIA#
295006 295006 Importance Rating 4.2 4.3 Proposed Question: RO 2, SRO 2 The plant is in Mode 2 at 11 % power when the MSIV's close due to a spurious isolation signal. A reactor scram also occurs.
After the scram, the following plant data is obtained to determine the RPS signal that initiated the SCRAM.
Reactor pressure spiked to 1050 psig Reactor power spiked to 16%
Which one of the following RPS signals initiated the scram?
6
/$
A.
High Reactor Power B.
High Reactor Pressure C.
MSIV position switches D.
Turbine Stop Valve position switches Proposed Answer: A Justification:
A correct - in STARTUP position SCRAM occurs at 15% power. B incorrect - scram on pressure occurs at 1057 psig. C incorrect -
MSIV position scram bypassed in STARTUP. D incorrect - TSV/TCV scram bypassed when less than 30% power.
Proposed references to be provided to applicants during examination-None Technical Reference(s):
02-OPS-212-02-00 KA:
295006 AK2.06, Knowledge of the interrelations between SCRAM and the SCRAM following: 'Reactor power' 10 CFR Part 55 Content:
55.41 l (71 X Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Proposed Question: RO 3, SRO 5 The plant is operating at 100% power, with the following:
One of the two operating Reactor Feedwater (FWS) Pumps trips.
Annunciator 603139, "REACTOR WATER LEVEL HIGH/LOW' alarms.
Narrow Range RPV water level is 175 inches and slowly lowering.
The Feedwater Level Control Valves (LV1 Os) are observed to be opening Reactor Recirculation flow has remained constant.
Which one of the following actions is required by N2-SOP-06, Feedwater Failures, to stabilize RPV water level above the scram setpoint?
A.
Place LV10 controller for the tripped FWS Pump in "MANUAL" B.
Place the Feedwater Master Level Controller in "MANUAL" C.
Reduce power per N2-SOP-101 D, Rapid Power Reduction D.
Reduce power per N2-OP-101D, Power Changes Proposed Answer: C Justification:
C is correct - Immediate Action per N2-SOP-06. A&B incorrect -
placing any controller in "MANUAL" will not stabilize level as FWLCS is responding properly. D incorrect not N2-SOP-06 Immediate Action and would not stabilize level before automatic scram Proposed references to be provided to applicants during examination - None Technical Reference(s):
N2-SOP-06 KA:
295009: Low AA1.01: Ability to operate/monitor the following as they apply to LOW Reactor Water REACTOR WATER LEVEL: 'Reactor feedwater' Level 10 CFR Part 55 Content:
55.41.10 X
55.43 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LODC 2
Comments:
None
Proposed Question: RO 4, SRO 8 The plant is operating at 100% power, with the following:
Annunciator 603443, Control Rod Drift, alarms Rod 34-23, originally at notch 14, indicates at 18, then 20 and continuing Which one of the following describes the reactivity control actions required to minimize the potential for a Thermal Limit violation?
A.
Insert rod 34-23 to position 00, only B.
Lower Recirculation (RCS) flow until power drops by 40 MWe, only C.
Lower Recirculation (RCS) flow until power drops to 89%, only D.
Lower power to 89% and insert rod 34-23 to 00 Proposed Answer: D
/
Justification:
i is correct - Both power reduction below 90% and rod insertion are required.
V fAIB are incorrect - Outward rod drift will raise power so power must be reduced to below 90%. C is incorrect-In addition to power reduction below 90% the rod must be inserted.
Proposed references to be provided to applicants during examination - None Technical Reference(s):
N2-SOP-08, 3.4/4.3 KA:
- 295014, AKI.05, Knowledge of the operational implications of the following concepts as Inadvertent they apply to INADVERTANT REACTIVITY ADDITION: 'Fuel Thermal limits' Reactivity Addition 10 ClR Part 55 Content:
55.41.5 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Proposed Question: RO 5, SRO 10 The plant is operating at 95% power, with the following:
"B" 6th Point Feedwater Heater extraction steam isolation valve closes Steady state Feedwater temperature drops to #06ff,'t Reactor power level rises to 99%.
Which one of the following is the required operator action?
A.
B.
C.
D.
Perform a reactor scram.
Reduce reactor power to 89%.
Reduce reactor power to 95%.
Maintain reactor power at 99%0 Proposed Answer: B Justification:
B is correct - Step 3.4 of N2-SOP-08 requires an initial power reduction to less than 90%. A incorrect - reactor scram is not required per N2-SOP-08. C&D incorrect - reactor power level is too high per N2-SOP-08.
Proposed references to be provided to applicants during examination - None Technical Reference(s):
N2-SOP-08 KA:
295014:
Inadvertent Reactivity Addition AA1.07: Ability to operate and/or monitor the following as they apply to INADVERTENT REACTIVITY ADDITION: 'Cold water injection' 55.41.10 X
55.43 10 CFR Part 55 Content:
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Proposed Question: RO 6, SRO 11 A reactor scram has occurred, with the following:
Reactor power is 10% on all APRMs The MODE SELECT indicated on SPDS screen is RUN mode Which one of the following indicates the color that the APRM POWER will be displayed in on the SPDS screen?
A.
Green B.
Yellow C.
Red D.
Magenta Proposed Answer: A Justification:
A is correct-As long as the SPDS mode is RUN, power above 4% will be displayed as Green. B incorrect-Yellow would be correct if MODE SELECT was Shutdown. C incorrect-Red displayed if above high value limit.
D incorrect. Magenta is displayed for invalid data.
Proposed references to be provided to applicants during examination - None Technical Reference(s):
02-OPS-00 1-226-2-01 KA:
295015:
AK2.10 Knowledge of interrelationship between INCOMPLETE Incomplete SCRAM and the following: 'SPDS/ERIS/CRIDS/GDS' SCRAM 10 ClFR Part 55 Content:
55.41 X
Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:3 Comments: None
Proposed Question: RO 7, SRO 16 A large break LOCA is in progress, with the following:
Suppression Pool level is 215 feet Primary Containment venting is required Which one of the following identifies the appropriate path to vent the Primary Containment?
A.
Only the Drywell vent flow path should be aligned.
B.
Only the Suppression Chamber vent flow path should be aligned.
C.
BOTH the Drywell AND Suppression Chamber vent flow paths should be aligned.
D.
NEITHER the Drywell NOR the Suppression Chamber vent flow path should be aligned.
Proposed Answer: B Justification:
B is correct - Venting is capable from both but is desired from SC for scrubbing with SPL below 217ft. A&D incorrect - The venting should occur from the SC. C is incorrect - The DW should not be vented since SPL is low enough to take advantage of scrubbing.
Proposed references to be provided to applicants during examination-N2-EOP-PC Technical Reference(s):
N2-EOP-PC & N2-EOP 6 Att 21 K/A:
295024: High EA1.19, Ability to operate and/or monitor the following as they apply D/W pressure.
to HIGH DRYWELL PRESSURE: Containment atmosphere control 10 CFR Part 55 Content:
55.41 x
Question Source:
Bank #
X Modified Bank #
New History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis x
ILOD 3
Comments: Question from INPO bank Oyster Creek 13071 -1996 exam
Proposed Question: RO 8, SRO 17 With the plant at 100% power a Group 1 Primary Containment Isolation and reactor scram occurs, with the following:
All rods are "FULL IN" except for one rod which is stuck at position "12" 2 SRVs are automatically controlling RPV pressure Which one of the following describes the expected status of the Alternate Rod Insertion (ARI) valves AND the status of the Redundant Reactivity Control system (RRCS) Reactor Feedwater Runback logic?
ARI VALVE STATUS RRCS RUNBACK STATUS A.
Open Runback occurred B.
Open Runback did not occur C.
Closed Runback occurred D.
Closed Runback did not occur Proposed Answer: B Justification:
B correct - SRV opening in Relief Mode indicates RPV pressure >1065 psig which opens ARI valves. RFPs remain available since power < 4% after 25 sec. A incorrect - RFPs will not runback. C&D incorrect - RRCS ARI initiation setpiont (high RPV pressure) exceeded.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-294-2-08 (RRCS), EO-1.5 KA:
295025, Reactor EK2.04, Knowledge of interrelationships between HIGH REACTOR Pressure PRESSURE and the following: 'ARI, RPT, ATWS' 10 CFR Part 55 Content:
55.41.7 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension orAnalysis X
LOC0:
2 Comments: None
Proposed Question: RO 9, SRO 18 The plant has scrammed due to an MSIV closure, with the following:
A large number of control rods have failed to fully insert Reactor power is 6% and steady 6 SRVs initially lifted Pressure is being maintained with SRVs Which one of the following describes the expected status of the Reactor Recirculation Pumps (RCS) and Standby Liquid Control Pumps (SLS) two minutes following the initial event?
RCS Pumps A.
Running B.
Running SLS Pumps Running Not running C.
Not running Running D.
Not running Not running Proposed Answer: C Justification:
C is correct-SLC pumps start with the APRM's >4% and RCS pumps trip on a RRCS reactor high press signal& pwr >4% after 25 sec.
A is incorrect-RCS pumps initially downshift but then trip if pwr >4%.
B is incorrect-this would be with power <4%. D is incorrect-NP Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-294-2-08-Rev 3 (RRCS), EO-1.5 KA:
295025, High EA1.08, Ability to operate and/or monitor RRCS as it applies to Reactor Reactor Pressure Pressure 10 CFR Part 55 Content:
55.41.7 55.43 Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
ILOD:
4 Comments: None
Proposed Question: RO 10, SRO 23 Which one of the following system lineups must be terminated and prevented in accordance with N2-EOP-C5~
ailure To Scram, when level is required to be lowered to reduce reactor power?
A.
Daligned to maximize injection B.
aligned to inject boron solution C.
RCIC with suction aligned to the Suppression Pool D.
RHS aligned to inject through the Shutdown Cooling line Proposed Answer: D Justification:
D correct - injects outside shroud and will cause power excursion. A incorrect - used to S/D reactor. B incorrect - a boron injection system.
C incorrect - RCIC excluded per EOP bases Proposed references to be provided to applicants during examination: N2-EOP-C5 Technical Reference(s):
N2-EOP-C5 step L-7 KA:
295031, Reactor EK1.03, Knowledge of the operational implications of the following concepts Low Water Level as they apply to REACTOR LOW WATER LEVEL: 'Water level effects on reactor power' 10 CFR Part 55 Content:
55.41 (10) X 55.43 I
Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis C eLOD:
3 Comments: None
Proposed Question: RO 11, SRO 25 A spurious reactor scram has occurred, with the following:
22 Control Rods failed to automatically insert Reactor Power is unknown Reactor Pressure is 940 psig and steady A steam leak, which cannot be isolated, has developed in the Reactor Water Cleanup (WCS) pump room WCS pump room temperature is 1450F and rising.
Which one of the following actions should be taken to lower the leak rate?
A.
Manually insert control rods and then initiate a normal cooldown.
B.
Immediately commence a cooldown at less then 100OF per hour.
C.
Terminate and prevent injection into the RPV and blowdown the reactor.
D.
Depressurize with Turbine Bypass valves regardless of cooldown rate.
Proposed Answer: A Justification:
A is correct - EOP-C5 step P-6 only allows a cooldown if the reactor is shutdown with no boron injected. B is incorrect - With reactor power unknown, a cooldown is not permitted. C is incorrect - A blowdown per EOP-SC/RR is only warranted if two or more areas exceed their Max Safe values. D is incorrect - not permitted during ATWS.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-C5; N2-EOP-SC/RR KA:
295037, Scram EK1.06, Knowledge of the operational implications of 'cooldown effects on Condition Present reactor power' and Reactor Power Above 4%
or Unknown 10 CFR Part 55 Content:
55.41 X
Question Source:
Bank #
Modified Bank #
X SSES - 2001 Q RO-8 New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
C LOD: N Comments: None
Proposed Question: RO 12 A LOCA is in progress, with the following:
Hydrogen (H2) has been released into the Primary Containment.
Suppression Chamber sprays have been directed in accordance with N2-EOP-PCH, Hydrogen Control.
Which one of the following identifies the bases for initiating Suppression Chamber sprays under these conditions?
To reduce.
A.
H2 concentration prior to purging.
B.
radioactive particulate prior to purging.
C.
H2 concentration to prevent deflagration.
D.
radioactive particulate to prevent deflagration.
Proposed Answer:
B Justification:
B is correct - per N2-EOP-PCH Bases. BIC/D incorrect - not correct per N2-EOP-PCH.
Proposed references to be provided to applicants during examination-N2-EOP-PCH Technical Reference(s):
N2-EOP-PCH K/A:
500000, High EK3.05: Knowledge of the reasons for the following responses as Containment they apply to HIGH PRIMARY CONTAINMENT HYDROGEN Hydrogen CONCENTRATIONS: Operation of wetwell (suppression pool)
Concentration sprays' 10 CFR Part 55 Content:
55.41.10 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD 2
Comments: Question from INPO bank# 905 Grand Gulf 1998
Proposed Question: RO 13, SRO 27 Which one of the following identifies the reason for securing the H2 Recombiners when H2 concentration rises to 5% per N2-EOP-PCH, Hydrogen Control?
H2 Recombiners are required to be shutdown to prevent damage from.....
A.
excessive recombiner chamber temperatures.
B.
excessive recombiner chamber moisture.
C.
insufficient hydrogen and oxygen recombination.
D.
insufficient hydrogen and oxygen flow.
Proposed Answer: A Justification:
A is correct - per step 32 of N2-EOP-PCH, shutdown H2 Recombiners if 02 and H2 concentrations > 5% because recombiner damage can result from excessive temperatures at the higher recombination rate.
BICID incorrect - wrong reason.
Proposed references to be provided to applicants during examination - N2-EOP-PCH Technical Reference(s):
N2-EOP-PCH & Bases, N2-OP-62, D.7.0 K/A:
500000, High 2.1.32, Ability to explain and apply system limits and precautions.
Containment Hydrogen Conc.
10 CFR Part 55 Content:
55.41()
X 55.43 Question Source:
Bank #
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis2 Comments: None
Proposed Question: RO 14 The plant is at 100% power when a jet pump rams head failure occurs.
Which one of the following describes the expected response of reactor power AND drive flow in the Recirculation loop containing the defective jet pump?
REACTOR POWER RECIRC LOOP DRIVE FLOW A.
Rises Rises B.
Rises Lowers C.
Lowers Rises D.
Lowers Lowers Proposed Answer: C Justification:
C is correct - less core flow results in lower reactor power. Drive flow in recirc loop with defective pump rises due to less flow resistance.
D incorrect - drive flow does not lower. A&B incorrect - reactor power does not rise.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
K/A:
- 295001, Partial/corn plete loss of forced core I circulation 10 CFR Part 55 Content:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
LOD:
2 Comments: None
Examination Outline Cross-reference:
1 1
Group #
2 2
K/A #
295002 295002 Importance Rating
- 3.4 3.4 Proposed Question: RO 15, SRO 28 While operating at 100% power, a loss of main condenser vacuum occurs.
Which one of the following identifies the automatic action and the reason for that action should main condenser vacuum drop to 8.5" Hg VAC?
A.
B.
C.
D.
MSIVs close due to indication of a loss of the primary heat sink.
MSIVs close due to indication of excessive reactor vessel inventory Turbine Bypass Valves close due to indication of a loss of the primary heat sink.
Turbine Bypass Valves close due to indication of excessive reactor vessel inventory loss.
Proposed Answer: A Justification:
A correct - Setpoint for MSIV closure is 8.5" Hg. vac basis per Op.
Tech. B incorrect - wrong basis. C&D incorrect - Turb. BPVs close at 7.0" hg. vac.
Proposed references to be provided to applicants during examination-none Technical Reference(s):
02-OPS-001-223-2-02, N2 OP-83 K/A:
295002, Loss of AK3.05, Knowledge of the reasons for the following responses as Main Condenser they apply to Loss of Main Condenser Vacuum: Main steam Vacuum isolation valve 10 CFR Part 55 Content:
55.41(7)
Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD 3
Comments: None
Proposed Question: RO 16, SRO 29 The plant is operating at 100% power, with the following:
Annunciator 851306, "OFF GAS SYSTEM TROUBLE", alarms Main condenser vacuum is 28 inches Hg and degrading slowly Which one of the following identifies the required procedural entry for this condition?
A.
N2-OP-101C, Plant Shutdown B.
N2-OP-101 D, Power Changes C.
N2-SOP-101 C, Reactor Scram D.
N2-SOP-101 D, Rapid Power Reduction Proposed Answer: D Justification:
D is correct. Immediate action for loss of condenser vacuum is to reduce power per SOP-101D. A & B - incorrect. SOP-09 requires rapid power reduction or scram. C incorrect. Slow vac drop does not immediately threaten trip.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-09 KA:
295002, Loss of Main G2.4.4 Ability to recognize abnormal indications for system Condenser Vacuum operating parameters which are entry level conditions for emergency and abnormal operating procedures.
10 CFR Part 55 Content:
55.41.10 X
55.43 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
No2 Comments: None
Examination Outline Cross-reference:
1 1
Group#
2 1
KIA #
295003 295003 Importance Rating 2.9 3.2 Proposed Question: RO 17, SRO 01 The plant is operating at 100% power, with the following:
A complete loss of off -site power has occurred.
All three divisional diesels (EDGs) running and powering their respective switchgears.
Which one of the following describes the action required to be taken per N2-SOP-03, Loss of AC Power, when ready to start an additional Service Water Pump in Division I?
A.
Re-open non-essential Service Water MOVs.
B.
Verify Service Water crosstie MOVs are closed.
C.
Start RHS Pump "A" and CSL Pump.
D.
Verify RHS "A" and CSL Pumps are secured.
Proposed Answer C Justification:
Cis correct - RHS and CSL pumps need to be already running due to-starting current considerations. A incorrect - if non-essentials opened prior to pump start, pump runout will occur. B incorrect - Service Water crosstie MOVs are required to be open when the additional pump is started. D incorrect - wrong sequence.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-03 KA:
295003: Partial/
AK1.03: Knowledge of operational implications of the following Complete Loss of concepts as they apply to PARTIAL OR COMPLETE LOSS OF AC AC Power POWER:" Under voltage/degraded voltage effects on electrical loads' 10 CFR Part 55 Content:
55.41.5 X
55.43 Question Source:
Bank #
X Question from NM2 bank - Group 3, Question #2 Modified Bank #
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Proposed Question: RO 18, SRO 18 The plant is operating at 75% power when a fault in the Division 11 125 VDC Battery, 2BYS*BAT2B, causes the following:
Battery Breaker to Division II DC Switchgear, 2BYS*SWG002B, trips OPEN.
Charger 2BYS*CHGR2B1, Output Breaker to Division II DC Switchgear, 2BYS*SWG002B, trips OPEN.
Which one of the following describes the effect on plant operation and conditions needed to restore power to the Division 11 125 VDC Bus or loads?
A.
Stop all activity that could result in a plant trip, DC power can NOT be restored until the battery is available.
B.
Orderly plant shutdown is required, DC power can NOT be restored until the battery is available.
C.
Orderly plant shutdown is required until DC power can be restored using the standby charger.
D.
Immediate scram is required, DC power can be restored using the standby charger.
Proposed Answer:
D Justification:
D is correct. Plant must be scrammed because both recirculation pumps tripped. Power can be restored by placing the alternate charger in service. C is incorrect. Plant must immediately be scrammed due to the trip of both recirc pumps. B is incorrect. Plant must be scrammed because both recirculation pumps tripped. Power can be restored by placing the alternate charger in service. A is incorrect. Plant must be scrammed because both recirculation pumps tripped. Power can be restored by placing the alternate charger in service.
Proposed references to be provided to applicants during examination - None Technical Reference(s):
N2-SOP-04 and N2-SOP-29 KA:
295004 Partial or AK1.02: Knowledge of the operational implications of the following Complete Loss of concepts as they apply to Partial or Complete Loss of D.C. Power:
D.C. Power Redundant D.C. power supplies: Plant-Specific 10 CFR Part 55 Content:
55.41(7)
X Question Source:
Bank #
X Modified Bank #
New History Last NRC Exam 2000 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Proposed Question: RO 19, SRO 33 The plant is operating at 100% power when an EHC malfunction causes all open, with the following:
RPV pressure is at 900 psig and decreasing rapidly The mode switch is placed in "SHUTDOWN" RPV pressure continues to decrease.
Which one of the following actions is required?
A.
Trip the operating EHC pump.
B.
Trip the main turbine before reaching 175 MWe.
C.
Close the Outboard MSIVs before dropping below 500 psig.
D.
Verify the backup EHC pressure regulator is in service.
Proposed Answer: C Justification:
C is correct - SOP-23 has immediate action step to close MSIVs before pressure drops below 500 psig.
A incorrect - may stop press drop but not per procedure. B incorrect-turbine already tripped either on high IvI or reverse power.
D incorrect - Not per procedure.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-23 KA:
295005: Main AA1.05 Ability to operate and or monitor the following as they apply to Turbine Generator MAIN TURBINE GENERATOR TRIP: 'Reactor/turbine pressure Trip regulating system.
10 CFR Part 55 Content:
55.41.10 X
55.43 Question Source:
Bank#
X Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Proposed Question: RO 20, SRO 34 A manual reactor scram is inserted due to rising Drywell Pressure, with the following:
A Feedwater Level Control (FWLC) malfunction causes RPV level to rise.
RPV water level rises to 212 inches then slowly lowers When RPV level drops to 210 inches Drywell pressure reaches 1.68 psig Which one of the following identifies the RPV water level at which High Pressure Core Spray (CSH) System injection will begin? (Assume no operator action)
A.
210 inches oP B.
202 inches A
1 C.
159 inches D.
108 inches Proposed Answer: D Justification:
D correct. Injection Valve re-opens automatically, but not until level lowers to 108 inches. AIBIC are incorrect. Injection Valve doesn't reopen until 108 inches. The High Pressure Core Spray Pump will start when DWP reaches 1.68 psig.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001 -206-2-00 KA: l295008: Reactor AA1.06 Ability to operate and/or monitor the following as they apply to I High Level HIGH REACTOR WATER LEVEL: 'HPCS' 10 CFR Part 55 Content:
55.41.7 X
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Proposed Question: RO 21 The plant is operating at 50% power, with the following:
A Feedwater Level Control (FWLC) malfunction causes RPV level to rise.
Level continuing to rise after the controller is taken to manual.
Level is rising on P601 indications.
Which one of the following describes the response of the Main Turbine if the current level trend continues?
The Main Turbine will trip when the following indicator(s) reach Level 8.....
A.
both P601 PAM level indicators.
B.
either P601 PAM level indicator.
C.
any two P603 NR level indicators.
D.
the selected P603 NR level indicator.
Proposed Answer:
C Justification:
C is correct - Main turbine trip on high level comes from narrow range detectors indicated on P603, 2 of 3 needed to produce trip. A&B incorrect - PAM indicates wide range and does not input to trip logic.
D incorrect - not correct logic Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-216-2-01 KA:
295008: High High Reactor Water Level K/A Topic: AA 1.07 Ability to Reactor Water operate/monitor the following as they apply to HIGH REACTOR Level WATER LEVEL: Main turbine 10 CFR Part 55 Content:
55.41.7 X
Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Proposed Question: RO 22, SRO 22 A steam line break has occurred in the Primary Containment, several control rods failed to fully insert, with the following.
RPV Level is 167 inches RPV Pressure is 420 psig Drywell Pressure is 7.0 psig Drywell Temperature is 1800F Suppression Chamber Pressure is 2 psig Suppression Pool Temperature is 1060F Which one of the following Residual Heat Removal System lineups is required?
A.
System "A" and "B" in suppression pool cooling.
B.
System "A" in suppression pool cooling with "B" in LPCI.
C.
System "A" and "B" in drywell and suppression chamber spray.
D.
System "A" in suppression pool cooling and "B" in drywell spray.
Proposed Answer: A Justification:
A is correct - N2-EOP-PC directs starting all available suppression pool cooling. B incorrect - B loop should also be started in SP cooling, RPV makeup is NOT needed. C is incorrect - because both loops should be in suppression pool cooling. D is incorrect - because both loops should be in suppression pool cooling.
Proposed references to be provided to applicants during examination: N2-EOP-PC Question Source:
Bank #
X Modified Bank #
New History Last NRC Exam 2000 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
No3 Comments: None
Examination Outline Cross-reference:
11 Group #
2 K/A #
295016
_ Importance Rating 3.7 3.8 Proposed Question: RO 23, SRO 12 The plant is operating at 100% power, with the following:
A fire forces an evacuation of the Control Room.
Dense smoke prevented any Control Room actions from being taken.
Which one of the following describes the method employed per N2-SOP-78, Control Room Evacuation, for tripping the Main Turbine?
A.
Locally scram the Reactor and then confirm the Main Turbine trips on reverse power.
B.
Locally scram the Reactor and then manually trip the Main Turbine from the front standard.
C.
Manually trip the Main Turbine from the front standard and confirm automatic reactor scram.
c7 fA D.
Locally initiate a Group I isolation and confirm automatic reactor scram and Main Turbine tripon reverse power.
Figs XA Proposed Answer: B Justification:
B is correct, SOP-78 directs the Operator to trip the Main Turbine from the front standard after the Reactor is scrammed locally. AICID incorrect - do not comply with procedural direction of SOP-78.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-78 KA:
295016, Control AK 3.02, Knowledge of the reasons for the following responses as they to Room CONTROL ROOM ABANDONMENT: 'turbine trip' Abandonment 10 CFR Part 55 Content:
55.41.10 X
55.43 Question Source:
Bank#
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Proposed Question: RO 24, SRO 13 N2-EOP-RR, Radioactive Release Control, is being executed with the following:
a Radioactive release rates approach the General Emergency level.
A reactor scram AND RPV blowdown are required.
Which one of the following describes the basis for ordering the reactor scram prior to the RPV blowdown in accordance with N2-EOP-RR?
A.
B.
C.
D.
Prevents fuel damage from a reactor power excursion 4 9 A
Ensures that the Reactor Protection System is not challenged Y
Ensures isolation of the leak by closing the Main Steam Isolation Valves Reduces the rate of energy production and thus the rate of radioactivity release sed Answer D Propo Justification:
0D is correct - per N2-EOP-RR basis. AIB/C incorrect - not per N2-EOP-RR basis Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-RR basis KA:
295017: High Off-AK3.04: Knowledge of the reasons for the following responses as Site release Rate they apply to HIGH OFF-SITE RELEASE RATE: 'Power reduction' 10 CFR Part 55 Content:
55.41.10 55.43 Question Source:
Bank #
X NM-2 bank. Question 58/Group 6 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Proposed Question: RO 25, SRO 36 An Instrument Air System transient occurs, with the following:
The Instrument Air system is aligned with the Compressor Selector Switch on P851 selected to the "BCA" position.
Instrument Air header pressure drops to 98 psig.
Which one of the following identifies the compressor that will automatically start and load AND the pressure at which this compressor will then unload?
COMPRESSOR THAT STARTS UNLOAD PRESSURE A.
A 115 psig B.
A 125 psig.
C.
C 115 psig D.
C 125 psig Proposed Answer:
D Justification:
D correct - Lag compressor "C" will start and load at 100 psig and unload at 125 psig. A&B incorrect - "A" will not start until 85 psig.
C incorrect - unloading pressure is always 125 psig.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-279-2-00 pgs. 9, 27 & 29 K/A:
295019, Partial or AK3.02, Knowledge of the reasons for the following as they apply to Total Loss of PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Standby Instrument Air compressor operation 10 CF R Part 55 Content:
55.41(5) 55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:2 Comments: None
Proposed Question: RO 26, SRO 37 An inadvertent Division 1 Group level isolation signal causes the Outboard CCP Containment Isolation valves to to isolate, with the following:
The isolation signal can not be reset.
The CRS has directed performance of N2-SOP-60, Loss of Drywell Cooling.
Which one of the following is required per the N2-SOP-60?
A.
Place DRYWELL UNIT COOLER WTR DIV I LOCA OVERRIDE in the "OVERRIDE" position only.
B.
Place both DRYWELL UNIT COOLER WTR DIV I (II) LOCA OVERRIDE in the "OVERRIDE" position only.
C.
Place DRYWELL UNIT COOLER WTR DIV I LOCA OVERRIDE and UNIT COOLER FANS GR 1 LOCA OVERRIDE switches in the "OVERRIDE" position only.
D.
Place both UNIT COOLER FANS GR 1(2) LOCA OVERRIDE switches in the "OVERRIDE" position only.
Proposed Answer: B Justification:
B is correct - required for restoration per SOP.
A/C incorrect - not required per SOP steps.
D incorrect - this is action if CCP cannot be restored Proposed references to be provided to applicants during examination: N2-SOP-60 KA:
295020:
2.1.23 Ability to perform specific system and integrated plant Technical Reference(s):
N2-SOP 60 Step 4.4.a KA:
295020:-
2.1.23 Ability to perform specific system and integrated plant Inadvertent procedures during different modes of plant operation.
Containment isolation 10 C-R Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank#
Modified Bank#
X Question from NM-2 Bank. #
8 I110/G ro up 6/Q61 New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
r _
Examination Outline Cross-reference:
1 1
Group #
2 12 K/A#
295022 295022 Importance Rating 3.3 3.4 Proposed Question: RO 27, SRO 39 A plant startup is in progress, with the following:
Reactor Pressure is 500 psig The operating Control Rod Drive (RDS) Pump trips No RDS Pump can be started A Control Rod at position 12 has an accumulator pressure of 900 psig Which one of the following describes when a manual scram is required to be initiated per N2-SOP-30, Control Rod Failures?
A.
Immediately B.
In 20 minutes C.
If one control rod drifts in D.
If any other control rod accumulator becomes inoperable Proposed Answer: A Justification:
A is correct-SOP-30 calls for immediate scram if reactor pressure is <900#
and CRD charging water pressure is <940# and any accumulator is inop with its associated rod withdrawn. B/C/D incorrect-All conditions not met per SOP-30.
Proposed references to be provided to applicants during examination: N2-SOP-30 Attachments 1 & 2 Technical Reference(s):
N2 SOP-30, 02 OPS-001-201-2-01, EO-1.8 KA:
295022, Loss of AK1.01, 'Reactor pressure versus rod insertion capabilities'.
CRD Pumps 10 CFR Part 55 Content:
55.41.10 X
55.43 Question Source:
Bank#
X Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension orAnalysis X
LCD:
3 Comments: None
Proposed Question: RO 28, SRO 19 Which one of the following events would bring a running Residual Heat Removal System (RHS) pump closer to cavitation while injecting during the Low Pressure Coolant Injection (LPCI) mode of operation?
A.
A stuck open Suppression Chamber to Drywell vacuum breaker AS B.
Broken tailpipe on an open SRV in the Suppression Chambe C.
Inadvertently opened Safety Relief Valve 1iyfl D.
CST leaking into the Suppression Pool Proposed Answer: C I Justification:
C is correct - warmer water will lower pump NPSH. A incorrect - no effect on NPSH, BID incorrect - improve NPSH Proposed references to be provided to applicants during examination: None Technical Reference(s):
EOP Basis Document, Calculations KA:
295026 High EK1.01: Knowledge of the operational implications of the following Suppression Pool concepts as they apply to HIGH SUPPRESSION POOL TEMP:
Temperature Pump NPSH 10 CFR Part 55 Content:
55.41.5 X
55.43 Question Source:
Bank#
Modified Bank #
X Question from NM2 bank #15925, Grp 5
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
1 1
Group #
2 2
K/A #
295029 295029 Importance Rating 2.9 3.0 Proposed Question: RO 29, SRO 41 The plant has experienced a LOCA, with the following:
Reactor pressure is 200 psig and slowly lowering Reactor level is 102 inches and steady Suppression Pool level is 210 feet and rising Which one of the following injection systems is allowed to be used to maintain reactor level per the Emergency Operating Procedures?
A.
RDS B.
Condensate D.
RCIC with suction aligned to the CST Proposed Answer: B Justification:
B is correct. With S/P level high (above 209.5 feet @ 200 psig), N2-EOP-PC, SPL-2 calls for injection sources that do not add to containment inventory. AICID incorrect - all inject from outside sources.
Proposed references to be provided to applicants during examination: N2-EOP-RPV, N2-EOP-PC Technical Reference(s):
N2-EOP-PC KA:
295029: High EA1.03, Ability to operate and/or monitor the following as they apply Suppression Pool to HIGH SUPPRESSION POOL LEVEL:
"RHR/LPCI" Level 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Proposed Question: RO 30, SRO 21 Procedure N2-EOP-PC, Primary Containment Control, contains a caution concerning the operation of RCIC with low suppression pool water level.
Which one of the following describes the potential hazard of not complying with this caution?
A.
RCIC exhaust line pressure oscillations could potentially cause system damage.
B.
Reduced cooling water flow to the RCIC turbine bearings may cause system damage.
C.
With RCIC suction aligned from its alternate source, NPSH and vortex limits may be exceeded.
D.
RCIC steam will discharge into the Suppression Chamber air space and overpressurize containment.
Proposed Answer: C Justification:
C is correct - per EOP basis. A is incorrect - concern at low RPM. B is incorrect - low cooling water flow is not reason for caution. D is incorrect -
isolation prevents this if exhaust uncovers Technical Reference(s):
EOP-PC Basis, 02-OPS-006-344-2, EO-1.4 KA:
2g5030, Low EK3.03, Knowledge for the reasons for the following responses as they Suppression Pool apply to LOW SUPPRESSION POOL WATER LEVEL: 'RCIC operation' Water Level 10 CFR Part 55 Content:
55.41 X
55.43 Proposed references to be provided to applicants during examination: None Question Source:
Bank#
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Proposed Question:
RO 31, SRO 6 The plant has experienced a LOCA, with the followin Reactor level -10 inches and slowly rising i/
Suppression Pool level 196.5 inches and steady "A" RHS injecting (LPCI mode) with Service Water aligned to heat exchanger "B" RHS running (Suppression Pool Cooling mode) with Service Water aligned to heat exchanger Which one of the following describes the method per N2-EOP-PC, Primary Containment Control, that should be used for determining a valid reading for Suppression Pool temperature with the above conditions?
A.
Heat exchanger inlet temperature on "B" RHS.
B.
Heat exchanger outlet temperature on "A" RHS.
C.
Suppression Pool temperature indication on SPDS.
D.
Post Accident Monitor Suppression Pool temperature indicators.
Proposed Answer: A Justification:
A is correct-with S/P level <197 ft, one method given for determining temperature is the HTX inlet temp. for a RHS pump running in S/P cooling. B incorrect-LPCI flow not thru HTX. C/D incorrect-S/P level
< 197'.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-PC Basis K/A:
295030, Low S/P EA2.02, Knowledge of the interrelationships between LOW Water Level SUPPRESSION POOL WATER LEVEL and the following:
'Suppression pool temperature' 10 CFR Part 55 Content:
55.41(10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments:
None
Proposed Question: RO 32 A primary system is found to be discharging into the Reactor Building and attempts to isolate it have failed, with the following:
Area temperature on Elevation 215' is 1800F and rising Radiation levels on Elevation 353' are 1.2 x E4 mRem/hr and rising Radiation levels on Elevations 261' and 240' are 1.5 x E4 mRem/hr and rising Reactor Building ventilation exhaust radiation levels are above the alarm setpoint Which one of the following actions is required?
A.
Reactor scram only B.
Reactor scram and RPV blowdown C.
Reactor scram and RPV depressurization not to exceed 1 000F/hr D.
Reactor scram and rapid RPV depressurization with turbine bypass valves Proposed Answer: B Justification:
B is correct - reactor scram and RPV blowdown required if 2 or more areas exceed maximum safe operating radiation levels. A incorrect -
RPV blowdown is also required. C&D incorrect - not actions per N2-EOP-SC.
Proposed references to be provided to applicants during examination: N2-EOP-SC Technical Reference(s):
N2-EOP-SCC KA:
295033: High EK2.01: Knowledge of interrelationships between HIGH Secondary SECONDARY CONTAINMENT RADIATION LEVELS and the Containment Area following: 'Area radiation monitoring system' Radiation Levels 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
X From NM-2 bank # 8340 162/Grp 6 Modified Bank#
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
K/A #
259021 Importance Rating 3.3 Proposed Question: RO 33 During a loss of shutdown cooling direction is given in N2-SOP-31, Loss of Shutdown Cooling, to raise level if no RHR pump or Recirculation Pump can be started.
Which one of the following identifies the reason for raising RPV water level to 227 to 243 inches?
To flood the.....
A.
dryer assembly to promote natural circulation.
B.
steam separators to promote natural circulation.
C.
dryer assembly to provide long term decay heat removal.
D.
steam separators to provide long term decay heat removal.
Proposed Answer:
B Justification:
B correct, separators are flooded to connect flow from inside to outside the shroud. A&C incorrect, separator not dryer. D incorrect, does not remove heat.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-31 K/A:
295021, Loss of AK3.01, Knowledge of the reasons for the following as they apply to Shutdown Loss of Shutdown Cooling: Raising reactor water level Cooling 10 CFR Part 55 Content:
55.41(5)
X Question Source:
Bank#
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
Comments: None
Proposed Question: RO 34 The plant is in a Refueling Outage, with the following:
Fuel loading is in progress RPS shorting links are installed Following the insertion of a fuel assembly into the core, the Reactor Operator reports that SRM count rates are steadily rising The "SRM SHORT PERIOD" annunciator alarms and does not clear Which one of the following identifies automatic actions that will occur AND operator actions that must be taken in accordance with N2-SOP-39, Refuel Floor Events?
AUTOMATIC ACTION A.
SRM scram OPERATOR ACTIONS Evacuate Refuel Floor and Drywell Evacuate Refuel Floor and Drywell Manually start both Standby Gas Treatment trains Manually start both Standby Gas Treatment trains Proposed Answer: A Justification:
A is correct - IRM scram will occur and evacuation is required per N2-SOP-39. B&D incorrect - SRM scram will not occur with shorting links installed. C incorrect - manual GTS start not required per N2-SOP-39.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
KA:
10 CFR Part 55 Content:
Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 3
LO D:
13 Comments: None
Examination Outline Cross-reference:
1 1
Group#
3 2
K/A #
295035 295035 Importance Rating 3.3 3.5 Proposed Question: RO 35, SRO 44 While the plant is operating at 100% power, with the following:
A swap of the operating Reactor Building ventilation (HVR) exhaust fans is performed Reactor Building differential pressure changes from -0.6" to -0.4" WG.
Which one of the following identifies the ventilation system response to this transient?
GTS RESPONSE HVR MOD17A/B RESPONSE A.
Starts Open B.
Remains in standby Close C.
Remains in standby Open D.
Starts Close Proposed Answer:
C Justification:
C correct - MODs will modulate open to reduce intake air flow to RB and GTS will not start on building dp. A&D incorrect - GTS will not start on building dp. B incorrect - MODs will modulate open to reduce intake air flow to RB.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-52 and N2-OP-61 B KA:
295035:
EK3.02 Knowledge of the reasons for the following as they apply to Secondary SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:
Containment High Secondary containment ventilation response Differential Pressure 10 ClR Part 55 Content:
55.41(5)
X 55.4 3 Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
ILOD:
3 Comments: None
Examination Outline Cross-reference:
1 Group #
3 K/A #
295036 Importance Rating 2.8 Proposed Question: RO 36 The plant is at 50% power when the Radwaste Operator calls reporting that he has received the following alarms and conditions:
RX. BLDG. FL DR. SUMP TK2B LEAK RATE HIGH RX. BLDG. FL.DR. SUMP TK2B LEVEL HIGH HIGH The associated standby sump pump has auto started Another call is received from a non-licensed operator reporting a service water leak in the "A" RHR pump room and the floor drain is handling the leak.
Which one of the following describes entry requirements to N2-EOP-SC, Secondary Containment Control AND plant shutdown requirements?
N2-EOP-SC ENTRY A.
Yes B.
No C.
No D.
Yes PLANT SHUTDOWN Yes Yes No No Proposed Answer: D Justification:
D is correct-Rx Bldg. Sump level Hi Hi alarm is entry to EOP-SC only one area is above Max Safe. A is incorrect-S/D directed if more than one area. B/C is incorrect-Rx Bldg. Sump level Hi Hi alarm is entry to EOP-SCC Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-SC & R/W ARC 2CES-PNL513 KA:
295036 High EA1.03 Ability to operate/monitor the following as they apply to Secondary SECONDARY CONTAINMENT HIGH SUMP /AREA WATER LEVEL:
Containment
'Radwaste' Sump/Area Water level 10 CFR Part 55 Content:
55.41.10 X
55.43.[
Question Source:
Bank#
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Proposed Question: RO 37 The plant is operating at 100% power, with the following:
Annunciator 603441, "ROD DRIVE ACCUMULATOR TROUBLE", alarms.
Local accumulator pressure for control rod 30-35 is indicating 1015 psig.
Which one of the following identifies the effect this will have on normal movement of control rod 30-35 AND the action that should be directed to clear the annunciator?
EFFECT ON MOVEMENT A.
Slower rod speeds B.
Slower rod speeds C.
No effect on movement D.
No effect on movement REQUIRED ACTION Blow water out of the instrument block Charge Nitrogen side of accumulator Charge Nitrogen side of accumulator Blow water out of the instrument block Proposed Answer: C Justification C is correct - the rod speed of control rod 30-35 will not be effected. N2-OP-30 indicates that a local accumulator pressure indication of less than 1025 psig is indicative of a nitrogen leak and the required action for this condition is to recharge the Nitrogen side of the accumulator to 1100 psig. A&B are incorrect - control rod 30-35 rod speeds are not effected. D is incorrect - wrong action per N2-OP-30 Proposed references to be provided to applicants during examination: None Technical Reference(s):
02 OPS-001-201-2-01, N2-OP-30 (F.7.0), N2-ARP-01 Window 603441 KA:
201001, Control A2.10, Ability to (a) predict the impacts of the following on the CONTROL ROD Rod Drive DRIVE HYDRAULIC SYSTEM; and (b) based on those predictions, use procedures to Hydraulic System correct, control, or mitigate the consequences of those abnormal conditions or operations: Low HCU accumulator pressure/high level 10 CFR Part 55 Content:
55.41.6 X
55.43 Question Source:
Bank#
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-
Reference:
2 Group #
1 K/A #
201002 201002 Importance Rating 3.4 3.1 Proposed Question: RO 38, SRO 69 A reactor startup is in progress when power to the Reactor Manual Control (RMC) system is lost.
Which one of the following describes the effect on reactor power and why?
A.
Unchanged because control rods cannot be moved.
B.
Rises because control rods will drift out.
C.
Lowers because all control rods will scram.
fi64/A D.
Lowers because some rods will drift in.
Proposed Answer: A Justification A is correct - a loss of power results in the inability to move rods because the Directional Control Valves cannot be energized, no rod motion means power does not change B is incorrect - because control rods will not drift out and power will not rise.
C is incorrect - because a scram will not occur if RMC power is lost. D is incorrect -
because control rods will not drift in and power will not lower.
Proposed references to be provided to applicants during examination: None Technical Reference 02-OPS-001-201-2-02,Section V.B.6.b KA:
201002, Reactor K3.01, Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL Manual Control CONTROL SYSTEM will have on the following: Ability to move control rods.
System 10 CFR Part 55 Content:
55.41.6 X
Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Proposed Question: RO 39 A reactor startup is in progress, with the following:
0 0
Reactor power is currently on Range 3 of the Intermediate Range Monitoring system Control rod 30-31 is the next control rod to be moved AND it is currently at notch position 12 Following the selection of control rod 30-31, the "ACTIVITY CONTROLS DISAGREE" light on the Rod Select Module illuminates, and remains illuminated Based on the above condition, which one of the following describes the ability to move the control rod?
Using Reactor Manual Control System, control rod 30-31 can be.....
A.
inserted or withdrawn B.
withdrawn only C.
inserted only D.
neither inserted nor withdrawn Proposed Answer: D Justification D is correct - the RMC system inserts control rod motion inhibit signals in response to an Activity Controls Disagree condition. A/B/C incorrect - due to both insert and withdraw blocks being applied Proposed references to be provided to applicants during examination: None Technical Reference(s):
02 OPS-001-201-2-02 KA:
201002, Reactor A3.01, Ability to monitor automatic operations of the REACTOR MANUAL CONTROL Manual Control SYSTEM including: Control rod block actuation System 10 CFR Part 55 Content: l 55.41.7 X
55.43 Comments: None
Proposed Question: RO 40, SRO 45 The plant is operating at 100% power, with the following:
The "A" hydraulic power unit (HPU) subloop for Reactor Recirculation (RCS) pump PlA is in-service The "B" HPU subloop for RCS pump PlA is in the READY (standby) mode The "A" HPU subloop trips on motor overload Which one of the following identifies the status of the "B" HPU subloop AND Reactor Recirculation flow control valve (FCV) "A" one minute after the motor overload condition occurs?
"B" HPU SUBLOOP STATUS A.
Running B.
Running C.
Not running D.
Not running FCV "A" STATUS Motion inhibited Motion not inhibited Motion inhibited Motion not inhibited Proposed Answer: B Justification B is correct - standby HPU subloop ("B") will start and no motion inhibit signal will be generated. A is incorrect - FCV "A" motion will not be inhibited. B&D are incorrect -
standby HPU subloop ("B") will automatically start.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-00 1-202-2-02, EO-1.7e KA:
- 202002, K3.06, Knowledge of the effect that a loss or malfunction of the RECIRCULATION Recirculation FLOW CONTROL SYSTEM will have on the following: Recirculation flow control valve Flow Control position: Plant-Specific System 10 CFR Part 55 Content:
55.41.6 55.43 Question Source:
Bank #
X NMP2 exam bank: Group 7 Question 8 Modified Bank #
New History Comments: None
Proposed Question: RO 41, SRO 46 The plant is shutdown, with the following:
Startup preparations are in progress.
Recirc Pump "A" is about to be started Recirc Pump "A" Flow Control Valve is at 25% open position.
An operator gives 'A' pump a start signal.
Which one of the following describes the response of the Recirc Pump?
A.
Does not start.
B.
Starts, immediately trips off.
C.
Starts then shifts to slow speed.
D.
Starts, remains running on high speed.
Proposed Answer: A Justification:
A is correct based on the FCV position starting interlock of 17 - 19 %. B is incorrect, pump does not start, since FCV is not at the minimum interlock position.C incorrect, would be correct at present power level if FCV were in correct position. D incorrect, would be correct for high power.
Proposed references to be provided to applicants during examination: None Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 2
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
11 K/A #
203000 203000 Importance Rating 4.2 4.3 Proposed Question: RO 42, SRO 47 The plant has experienced a LOCA, with the following:
Division I Switchgear Bus 2ENS*SWG1O1 is de-energized due to a bus fault An automatic ADS blowdown has occurred RPV water level is -30 " and steady RHS pump "B" is the only running ECCS pump Which one of the following identifies the effect on the ADS valves if RHS pump "B" were to ip?
A.
All ADS valves will remain open.
B.
All ADS valves will close immediately.
C.
3 ADS valves will close AND 4 ADS valves will remain open.
C/
D.
4 ADS valves will close AND 3 ADS valves will remain open.
Proposed Answer:
A Justification:
A is correct - valves remain open due to seal-in contact.
B incorrect - reset PB must be depressed.
C&D incorrect - only a loss of nitrogen and accumulator will cause partial ADS valve closure.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-218-2-01 K/A:
- 203000, K3.03: Knowledge of the effect that a loss or malfunction of the RHR/LPCI RHR/LPCI INJECTION MODE will have on the following: 'Automatic Injection Mode depressurization logic' 10 CFR Part 55 Content:
55.41.7 Question Source:
Bank#
Modified Bank #
X New History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
C LOD:
2 Comments: modified from INPO bank-LGS 1998
Proposed Question: RO 43 Residual Heat Removal (RHS) loop "A" is being placed in the Shutdown Cooling mode, with the following:
RHS pump PlA is started.
2RHS*MOV40A, SDC A RETURN THROTTLE, is being throttled open when it sticks in the partially open position.
RHS loop "A" flow is 900 gpm.
Which one of the following is the correct response to this condition?
A.
Open the "A" RHS full flow test return valve.
B.
Open the "A" Shutdown Cooling Test Check Bypass Valve.
C.
Trip RHS pump PlA within 40 seconds D.
Trip RHS pump PIA if heat exchanger outlet temperature >130OF Proposed Answer: C A
Justification:
A is incorrect because N2-OP-31 does NOT direct the opening of the full flow test valve to raise loop flow. B is incorrect because N2-OP-31 directs actions to throttle open RHS*MOV40A, SDC B(A) RETURN THROTTLE, to raise loop flow, NOT 2RHS*MOV67A, SDC A TEST CHECK VLV BYPASS.
C is correct because it indicates that RHS pump PlA should be tripped if a loop flow of > 1,000 gpm is NOT established within 40 seconds. D is incorrect because N2-OP-31 does NOT direct the tripping of RHS pump PlA if heat exchanger outlet temperature exceeds 1300F. It directs actions to throttle open RHS*MOV40A, SDC B(A) RETURN THROTTLE, to raise loop flow.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-31, 02-OPS-001-205-2-00 KA:
203000 RHR/LPCI 2.1.32 Ability to explain and apply system limits and precautions Inection Mode 10 CFR P ontent:
55.41.10 X
55.43 Question Source:
Bank*#
Group 6 Question 124 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Proposed Question: RO 44, SRO 48 A small break loss of coolant accident (LOCA) has just occurred, with the following:
The reactor has been manually scrammed RPV pressure is 938 psig AND depressurizing at a rate of 50 psig/minute Drywell pressure is 0.69 psig AND rising at a rate of 0.5 psig/minute Assuming all systems function as designed, which one of the following identifies the approximate earliest elapsed time at which the Low Pressure Core Spray Injection Valve will begin to open? (Assume a CSL shutoff head pressure of 450 psig)
A.
2 minutes B.
8 minutes C.
11 minutes D.
15 minutes Proposed Answer: B Justification:
For the conditions given (small break LOCA, RPV pressure 930 psig AND depressurizing at 50 psi per minute, Drywell pressure 0.7 psi AND rising at 0.5 psi per minute), the CSL system will receive an automatic initiation signal (high drywell pressure 1.68 psig) in approximately 2 minutes (0.7+0.5
= 1.2; 1.2+0.5 =1.7), but the CSL injection valve will NOT receive an open signal until the differential pressure across the valve is less than 88 psid. Assuming CSL pump shutoff head pressure is 450 psig, it will take approximately 8 minutes for the differential pressure permissive for the CSL injection valve to be met (450+88=538, 938-538= 400; 8x50=40). Therefore:
"A" is incorrect because the earliest time at which the CSL injection valve will begin to open is approximately 8 minutes. The CSL system will receive an automatic initiation signal in approximately 2 minutes.
"B" is correct because the earliest time at which the CSL injection valve will begin to open is approximately 8 minutes.
"C" is incorrect because it indicates that the earliest time at which the CSL injection valve will begin to open is approximately 8 minutes.
"D" is incorrect because the earliest time at which the CSL injection valve will begin to open is approximately 8 minutes.
I Proposed references to be provided to applicants during examination: None Question Source:
Bank #
Modified Bank#
X New History Question Cognitive Level:
Memory or Fundamental Knowledge l
Comprehension or Analysis l
LOD:
4 Comments: None
Proposed Question: RO 45, SRO 49 N2-EOP-PC, Primary Containment Control, has been entered due to high Suppression Pool level.
Which one of the following describes the current suction source for the RCIC and High Pressure Core Spray (CSH) systems?
RCIC SUCTION A.
CST B.
CST C.
Suppression Pool D.
Suppression Pool CSH SUCTION Suppression Pool CST Suppression Pool CST Proposed Answer: A Justification:
A is correct - SP high level entry to N2-EOP-PC is > HPCS swap setpoint from CST to SP. C&D incorrect - RCIC swap occurs only on low CST level. B incorrect - CSH swaps to SP Proposed references to be provided to applicants during examination: None Question Cognitive Level:
Memory or Fundamental Knowledge
=
Comprehension or Analysis X
LOD:
2 I
Comments: None
Proposed Question: RO 46, SRO 50 The plant is operating at 100% power, with the following:
The High Pressure Core Spray (CSH) system is in standby Condensate Storage Tank (CST) 1 B level is 35 feet The CSH water leg pump (WTR LEG PMP 2) trips Which one of the following identifies the operational status AND availability of the CSH system?
CSH OPERATIONAL STATUS A.
OPERABLE B.
OPERABLE C.
INOPERABLE D.
INOPERABLE CSH AVAILABILITY Available for injection Unavailable for injection Unavailable for injection Available for injection Proposed Answer: C Justification C is correct - per N2-OP-33 (H10.0), with the CSH water leg pump out of service, CSH is inoperable, but will be unavailable since CST level is less than 47 feet.
A&B are incorrect - CSH is not operable. C is incorrect - CSH is not available for injection, CST 1 B level is less than 47 feet.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-33 KA:
209002, High A4.07, Ability to manually operate and/or monitor in the control room: Line fill pump:
Pressure Core BWR-5, 6 Spray System (HPCS) 10 CFR Part 55 Content:
55.41.7 X
55.43 1
Question Source:
Bank#
Modified Bank#
New X
History Comments: None
Proposed Question: RO 47, SRO 51 The plant has experienced a transient, with the following:
The Reactor Water Cleanup (WCS) system is operating normally The switch for Standby Liquid Control (SLS) pump P1 B is placed in the "PUMP B RUN" position The SLS pump P1 B suction valve fails to open SLS pump P1 B fails to start Which one of the following identifies the response of the WCS isolation valves to the above event?
WCS Inboard Isolation WCS Outboard Isolation Valve (2WCS*MOV102)
Valve (2WCS*MOV112)
A.
Closes Remains open B.
Remains open Remains open C.
Remains open Closes D.
Closes Closes Proposed Answer: A Justification:
A is correct - it indicates that inboard WCS isolation valve 2WCS*MOV102 will close AND outboard WCS isolation valve 2WCS*MOV1 12 will remain open. B is incorrect - inboard WCS isolation valve 2WCS*MOV102 will close. C is incorrect - inboard WCS isolation valve 2WCS*MOV102 will close AND outboard WCS isolation valve 2WCS*MOV1 12 will remain open.
D is incorrect - 2WCS*MOV1 12 will remain open.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-36A, 02-OPS-001-204-2-01, 02-OPS-001-211-2-00 K/A:
211000, SLC K1.05, Knowledge of the physical connections and/or cause-effect relationships between SLC and the following: RWCU 10 CFR Part 55 Content:
55.41 Question Source:
Bank #
Modified Bank #
X, NM-2 Group 5 Question 130 New History:
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
2#
Group 1
KIA #
212000 Importance Rating 3.9 Proposed Question: RO 48 The plant is at 90% power when an automatic scram occurred as a result of a Main Generator lockout, with the following:
All control rods fully inserted RPV pressure is 960 psig and steady RPV water level dropped to 120 inches and is slowly rising Which one of the following describes the position of the EOC-RPT Breakers AND Reactor Recirculation (RCS) pump status 30 seconds later?
EOC-RPT BREAKERS RCS PUMP STATUS A.
Closed Off B.
Closed Slow speed C.
Open Off D.
Open Slow speed Proposed Answer: D Justification:
D is correct - EOC-RPT bkrs open on Main Turbine trip & pumps shift to slow. A incorrect - NP. B incorrect - EOC RPT bkrs do not stay closed. C incorrect - Pump remains running Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001 -202-2-01 KA:
212000: Reactor A4.15: Ability to manually operate and/or monitor in the control room:
Protection System
'Recirculation pump/EOC RPT' 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level: I Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group 1
2 K/A #
215003 215003 Importance Rating 4.0 4.0 Proposed Question: RO 49, SRO 72 The plant is in Mode 2 with a reactor startup in progress, with the following:
All APRMs are reading 2% power "B" IRM is reading 122 on Range 6 Which one of the following describes the expected Reactor Protection System (RPS) and Reactor Manual Control System (RMCS) response?
A.
Half scram only.
B.
Full reactor scram.
C.
Rod withdraw block only.
D.
Rod withdraw block and half scram.
Proposed Answer: D Justification:
D correct - IRM upscale trip and RB would be in with mode switch in STARTUP. A - incorrect with units above trip 120/125 it is also above RB 108/125. B incorrect - this would occur if shorting links were removed. C incorrect - this would be true if units were above 108 and below 120.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-212-2-00 (RPS)
KA:
- 215003, K4.02, Knowledge of IRM system design features and/or interlocks which Intermediate Provide for the following: 'Reactor SCRAM signals' Range Monitors 10 CFR Part 55 Content:
55.41(7)
X 55.43 Question Source:
Bank #
X LGS Bank Modified Bank #
New History from LGS 2001 Audit Exam Question Cognitive Level: l Memory or Fundamental Knowledge l X Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
2 Group #
1 K/A #
215004 Importance Rating 3.2 Proposed Question: RO 50 The plant is in Mode 2 with a reactor start-up in progress, with the following:
The IRM's are all on Range 4 reading between 40 and 60.
The SRM's B and C are being withdrawn with the following readings:
SRM:
A B
C D
CPS:
120 80 120 110 Which one of the following describes the status of the SRM withdrawal and the Rod Out Block?
SRM Withdrawal Rod Out Block Applied A.
Continues Yes B.
Continues No C.
Terminates Yes D.
Terminates No Proposed Answer: B Justification:
B correct - SRM retract has no stop interlock & no rod block if IRM's on or above range 3. A incorrect-RB is bypassed on B SRM with IRM on R4. C incorrect - Retract permit inputs to RB circuit not drive circuit and RB is bypassed >IRM R3. D incorrect - Retract permit inputs to RB circuit not drive circuit.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-00 -215-2-03, EO-1.5 KA: l 215004, Source A4.04, Ability to manually operate and/or monitor in the control room: 'SRM l
I History I on LGS 2000 NR Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
215005 215005 Importance Rating 2.7 3.1 Proposed Question: RO 51, SRO 53 Which one of the following identifies the Local Power Range Monitor (LPRM) input signals to Average Power Range Monitoring channel #2 (includes the LPRM AND APRM Chassis)?
APRM #2 receives a total number of....
A.
22 inputs from A", "B", "C", AND "D" level LPRM detectors B.
22 inputs from "B" AND "D" level LPRM detectors only C.
43 inputs from "A", "B", "C", AND "D" level LPRM detectors D.
43 inputs from "B" AND "D" level LPRM detectors only Proposed Answer: C
.9)h Justification:
A is incorrect because APRM #2 receives a total number of 43 inputs from "A", "B", "C" AND "D" level detectors. B is incorrect because APRM #2 receives a total number of 43 inputs from "A", "B", "C" AND "D" level detectors. C is correct because APRM #2 receives a total number of 43 inputs from "A", "B", "C" AND "D" level detectors. D is incorrect because APRM #2 receives a total number of 43 inputs from "A", "B", "C" AND "D" level detectors Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-215-2-05 KA:
215005 K4.08, Knowledge of APRM/LPRM design feature(s) and/or interlocks which APRM/LPRM provide for the following: Sampling of overall core power in each APRM (accomplished through LPRM assignments and symmetrical rod patterns 10 CFR Part 55 Content:
55.41.7 55.43 Question Source:
Bank#
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
217000 217000 Importance Rating 2.6 2.6 Proposed Question: RO 52, SRO 55 The plant is operating at 100% power, investigating a loss of Normal 125 VDC Distribution, 2BYS-SWG001 B, with the following:
A Loss of Feedwater occurs The reactor is scrammed RCIC automatic initiation conditions are met Which one of the following describes the status of the Reactor Core Isolation Cooling Syst (RCIC)?
A.
Failed to initiate, the logic is not actuated.
B.
Running with the Injection Valve closed C.
Running and injecting with no minimum flow protection D.
Running and injecting with no turbine seals Proposed Answer: D Justification:
D is correct - Gland Seal Compressor is powered from Normal DC distribution (2BYS-SWG001B) and is not running. A is incorrect -
Logic power is from Division I Safety Related DC. B/C are incorrect -
Minimum Flow and Injection Valves are not powered from Normal 125VDC.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-217-2-00, EO-1.5 N2-SOP-04 KA:
217000, Reactor K2.04, Knowledge of electrical power supply to the Gland Seal Core Isolation Compressor Cooling 10 CFR Part 55 Content:
55.41.8 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 2
Group#
1 1
K/A #
218000 218000 Importance Rating 3.8 3.8 Proposed Question: RO 53, SRO 56 A plant transient has occurred requiring entry into the EOPs, with the following:
"B" and "C" RHR pumps are the only ECCS pumps running RPV Blowdown is required Just prior to the blowdown, the following events/actions occur:
A loss of Division 11 125 VDC Then, all four ADS Logic Manual Initiation pushbuttons are armed and depressed Which one of the following applies to the ADS valves?
A.
Open only after the ADS timer has timed out.
B.
Open immediately without further operator action.
C.
Still closed and should be opened using their "B" solenoids.
D.
Still closed and should be opened using their "A" solenoids.
Proposed Answer: D Justification:
D is correct - Remain closed because ADS logic Div I does not have ECCS pump run permissive since RHR A nor CSL Pumps are running AND "A" solenoid is Div I DC (2BYS*PNL201A). A is incorrect - this would be auto initiation with Div I ECCS Pumps running. B is incorrect - this would be if Div I ECCS Pumps were running. C is incorrect - "B" ADS solenoids are powered from Div II DC (2BYS*PNL201B).
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-218-2-01, EO-1.5 K/A:
- 218000, K4.01, Knowledge of the operational implications of the following concepts Automatic as they apply to THE AUTOMATIC DEPRESSURIZATION SYSTEM: 'ADS Depressurization logic operation' System 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank#
X NM-2 Q157 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 2
Group#
1 1
K/A #
218000 218000 Importance Rating 3.7 3.8 Proposed Question: RO 54, SRO 57 A Loss of High Pressure injection occurs, with the following:
Automatic initiation of ADS RPV Pressure lowers to 80 psig RPV level is 180 inches Which one of the following identifies the expected status of the Control Room P601 and P628/P631 red indicating lights for SRV 137 at this time?
P601 P628/P631 A.
On On B.
On Off C.
Off On D.
Off Off Proposed Answer: C Justification:
C correct - the solenoid red lights on P628/631 light and Acoustic Monitoring actuates the red P601 light but will be off because pressure is too low (330 psig) to drive acoustic mon. A incorrect - this is expected with pressure
>330 psig. B incorrect this would be if valve opened above 330 psig by relief or safety modes. D incorrect - this would be normal indication without open or ADS initiation.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-218-02-01, EO-1.5 KA:
218000, Automatic A3.03, Ability to monitor automatic operations of the ADS including: ADS Depressurization valve acoustical monitor noise System 10 CFR Part 55 Content:
55.41(7)
X Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 2
Group #
I 1
K/A #
223001 223001 IImportance Rating 2.7 2.9 Proposed Question: RO 55, SRO 58 The plant is operating at 100% power when electrical power is lost to 2NNS-SWG014.
Which one of the following identifies the Drywell Unit Cooler Fans that will lose power?
A.
None B.
Only a quarter C.
Only a half D.
All Proposed Answer: C Justification:
C is correct. NNS-SWG014 supplies power to MCCO 1I through NJS-US5.
MCCOI 1 supplies 5 of the 10 Drywell Unit Cooler Fan Motors.
AIB/D are incorrect.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-60, Attachment 2 KA:
223001, Primary K2.09, Knowledge of electrical power supplies to Drywell Cooling Fans Containment System and Auxiliaries 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank#
Modified Bank#
X New History Question Cognitive Level:
Memory or Fundamental Knowledge l X Comprehension or Analysis LOD:
l2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
223001 223001
-Importance Rating 3.1 3.3 Proposed Question: RO 56, SRO 59 A LOCA is in progress, with the following:
All Drywell Vacuum Breakers fail to open, when required.
Which one of the following identifies the containment failure mechanism that can result from the vacuum breaker failure?
A.
Excessive inward pressure on Drywell wall.
B.
Excessive inward pressure on Suppression Pool wall.
C.
Excessive upward pressure on Drywell floor.
D.
Excessive downward pressure on Drywell floor.
Proposed Answer: C Justification:
C is correct - Vac breakers relieve from SC to DW to limit upward stress on DWfloor. A&B incorrect -These would result from excessive negative (to outside) pressure in the Drywell. D incorrect -
Under LOCA conditions, a downward force exist on the floor.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-221-2-01 KA:
223001 Primary K5.01 Knowledge of the operational implications of the following Containment and concepts as they apply to the PRIMARY CONTAINMENT AND Auxiliaries AUXILIARIES: 'Vacuum breaker/relief operation' 10 CFR Part 55 Content:
55.41(5)
X 55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
[ILOD:
12 Comments: None
Examination Outline Cross-
Reference:
2 2
Group 1
1 K/A #
223002 223002 Importance Rating 3.7 3.7 Proposed Question: RO 57, SRO 60 The plant is in an outage, with the following:
System testing is in progress Division 1 HYDROGEN RECOMBINER Manual isolation switch on P602 is taken to PUSH TO ISOLATE and depressed Which one of the following describes the status of the HYDROGEN RECOMBINER Train "A" Isolation Valves?
Inboard Valves A.
Open B.
Closed C.
Open D.
Closed Outboard Valves Open Open Closed Closed Proposed Answer: D Justification:
D is correct - For the HCS system "A" Train (all valves) are isolated by Division 1 AIBIC are incorrect - Both Inboard and Outboard valves will close Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001 -223-2-02, N2-SOP-83 KA:
223002, Primary A1.02, Ability to predict and/or monitor changes in parameters associated with Containment operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM Isolation SUPPLY SHUTOFF SYSTEM (PCIS/NSSSS) controls including: Valve closures System/Nuclear Steam Supply Shutoff System (PCIS/NSSSS) 10 CFR Part 55 Content:
55.41.5 X
55.43 1
Question Source:
Bank #
Modified Bank #
X New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
KIA #
239002 239002 Importance Rating 4.1 4.2 Proposed Question: RO 58, SRO 61 The plant is operating at 100% power, with the following:
Safety Relief Valve (SRV) 2MSS*PSV120 inadvertently opens AND remains open All fuses for the SRV have been removed in accordance with N2-SOP-34, Stuck Open Safety Relief Valve Which one of the following identifies an acceptable method for confirming, by observation, that the SRV is closed following the removal of its associated fuses in accordance with N2-SOP-34?
A.
Immediate clearing of the ADS/SRV Leaking alarm B.
Closed indication on Control Room panel P601 C.
Closed indication on the ERF computer D.
Reduction in Main Generator megawatts Proposed Answer: C Justification:
A is incorrect because N2-SOP-34 does NOT specify that the clearing of this annunciator is an indication of valve closure following the removal of the fuses for the associated SRV. B is incorrect because N2-SOP-34 does NOT specify that observing a closed position indication on Main Control Room panel P601 is an indication of valve closure following the removal of the fuses for the associated SRV. C is correct because N2-SOP-34 specifies that SRV indications on the ERF computer can be used to confirm SRV closure following the removal of the fuses for the associated SRV. D is incorrect because Turbine Generator output would rise (more steam would be available to the Turbine Generator).
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-ARP-01 Window 601537, N2-SOP-34.
KA:
239002 SRVs A2.03, Ability to (a) predict the impacts of the following on the SRVs and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open SRV 10 CFR Part 55 Content:
55.41.10 X
55.43 Question Source:
Bank #
Group 1 Question 45 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
ILOD:
3 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
241000 241000
____I Importance Rating 2.7 2.7 Proposed Question: RO 59, SRO 63 Main Turbine speed rises from 100% to 107% of rated.
Which one of the following describes the response of the Main Turbine Control Valves (CVs) AND Intercept Valves (lVs)?
A.
The CVs AND [Vs start to throttle closed together B.
CVs throttle closed first followed by the IVs C.
IVs throttle closed first followed by the CVs D.
lVs throttle closed AND the CVs remain open Proposed Answer: B Justification:
A is incorrect because the CVs AND IVs will NOT throttle together. The CVs will throttle closed first AND will be fully closed at 105% of rated speed.
Then the master IVs will throttle closed AND all IVs will be fully closed at 107% of rated speed. B is correct because it indicates that the CVs will throttle closed first followed by the IVs. C is incorrect because the IVs will NOT throttle closed first. The CVs will throttle closed first AND will be fully closed at 105% of rated speed. Then the master IVs will throttle closed AND all IVs will be fully closed at 107% of rated speed. D is incorrect because the CVs will NOT remain open. The CVs will throttle closed first AND will be fully closed at 105% of rated speed. Then the master IVs will throttle closed AND all IVs will be fully closed at 107% of rated speed Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001 -248-2-00 KA:
241000 A1.13 Ability to predict and/or monitor changes in parameters associated Reactor/Turbine with operating the Reactor/Turbine Pressure Regulating System controls Pressure including: Main turbine speed Regulating System 10 CFR Part 55 Content:
55.41.4 55.43 Question Source:
Bank #
X Group 1 Question 56 Modified Bank #
New History Question Cognitive Level: l Memory or Fundamental Knowledge l X Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 2
KIA #
259001 259001 Importance Rating 3.3 3.3 Proposed Question: RO 60, SRO 75 A plant startup is in progress with RPV pressure at 500 psig, with the following:
The first Reactor Feedwater Pump (FWS-PlA) has just been placed in-service on minimum flow RPV water level is being controlled by the Startup Level Control Valve (LV1 37) in automatic An electrical malfunction fails open the Feedwater Pump Bypass Valve (MOV122)
Which one of the following will terminate the RPV water level transient?
A.
Reactor Feedwater Pump (FWS-PlA) trip on Level 8.
B.
Startup Level Control Valve (LV1 37) automatic closure.
C.
RO closes the Feedwater Blocking Valves (MOV21s).
D.
RO closes the 6th Point Heater A Inlet Valve (MOV1 7A).
Proposed Answer: C Justification:
C is correct - because the MOV122 bypasses the FWS pumps and LV137 allowing uncontrolled injection by Condensate Booster Pumps.
The RPV water level rise can be terminated only by closing the Feedwater Blocking Valves (MOV21s).
AlB/D are incorrect - none will stop RPV water level rise.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-08, N2-SOP-101 C (Steps 4.2.5, 4.2.6, 4.2.7, 4.2.8, 4.2.9)
K/A:
259001, Reactor A1.01: Ability to predict and/or monitor changes to parameters Feedwater associated with operating the REACTOR FEEDWATER SYSTEM System controls including: Feedwater flow/pressure 10 CFIR Part 55 Content:
55.41.5 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-
Reference:
2 2
Group#
1 2
K/A #
259001 259001' Importance Rating 2.7 2.7 Proposed Question: RO 61, SRO 74
.7 The plant is operating at 100% power, with the following:
A loss of Turbine Building Closed Loop Cooling Water (CCS) has occurred The reactor has scrammed The main turbine has tripped Which one of the following identifies the effect this loss will have on plant shutdown AND cooldown?
A.
Failure of Condensate pump seals B.
Loss of Turbine Building area cooling C.
Trip of operating Instrument Air compressors D.
Overheating of operating Reactor Feedwater pumps Proposed Answer: D X
Justification D is correct - RFP pump bearing and lube oil coolers receive cooling water fromn theX CCS system. A/IBC are incorrect - receive cooling water from other cooling water l
systems.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-208-2-00, 02-OPS-001-274-2-00, N2-SOP-14 KA:
259001, Reactor K6.05, Knowledge of the effect that a loss or malfunction of the following will have on lFeedwater System the REACTOR FEEDWATER SYSTEM: Component cooling water systems 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group I
1 K/A #
259002 259002 Importance Rating 3.1 3.1 Proposed Question: RO 62, SRO 64 The plant is operating at 100% power, with the following:
Feedwater Level Control (FWLC) is in Automatic - 3 element control Level setpoint is 183 inches Then the total steam flow signal to FWLC fails downscale to zero flow Which one of the following identifies the effect of this signal failure on reactor water level?
A.
Lowers resulting in a reactor scram at Level 3.
B.
Lowers and automatically maintains 170 to 175 inches.
C.
Rises and automatically maintains 190 to 195 inches.
D.
Rises resulting in main turbine and reactor feed pump trips at Level 8.
Proposed Answer: A Justification:
A is correct - Based on 12 inch drop for one steam flow transmitter downscale failure, a total loss of steam flow input from all four, will result in a level 3 (159.8 inches) scram. B is incorrect - this is single steam flow downscale failure. C is incorrect - single steam flow upscale failure. D is incorrect -single feed flow downscale failure Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-259-2-02 KA:
- 259002, K6.03, Knowledge of the effect that a loss or malfunction of the following Reactor Water will have on the Reactor Water Level Control: Main steam flow input.
Level Control 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
X Modified Bank #
New History Question taken from SSES, 2001 LOT Exam, RO 59, SRO 61 Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 Group#
1 K/A #
259002 295002 Importance Rating 3.3 3.4 Proposed Question: RO 63, SRO 65 The plant is operating at 100% power, with the following:
Only Reactor Feedwater (FWS) Pump "A" is in-service Both Reactor Recirc (RCS) Pumps are in Fast Speed Power is lost to 2FWS-PNL1 OA, the panel for 2FWS-LV1 OA Reactor Recirc (RCS) Pump "A" inadvertently trips Which one of the following identifies the response of RPV water level AND the operator response necessary to stabilize RPV water level in accordance with N2-SOP-6, Feedwater Failures?
LEVEL RESPONSE A.
Rises B.
Rises C.
Lowers D.
Lowers OPERATOR ACTION Throttle Feedwater Blocking Valves (MOV21 s)
Take manual control of Master Level Controller Throttle Feedwater Blocking Valves (MOV21s)
Take manual control of Master Level Controller Proposed Answer: A Justification:
A is correct - per 4.4.1.a of N2-SOP-06, loss of power to 2FWS-PNLlOA will cause LV-10A lockout circuits to trip. RPV water level rise following RCS pump trip due to swell and reactor power reduction. Operator response per N2-SOP-6 is to throttle Feedwater Blocking Valves (MOV-21s). B incorrect - with valve locked up, Master Level Controller will not move valve. C/D incorrect - RPV water level rises, not lowers.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-06 KA:
259002: Reactor A2.06: Ability to predict the impacts of the following on the REACTOR Water Level WATER LEVEL CONTROL and based on those predictions, use Control procedures to correct, control or mitigate the consequences of these abnormal conditions or operations: 'Loss of controller signal output' 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
4 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
264000 264000 Importance Rating 3.3 3.5 Proposed Question: RO 64, SRO 67 The plant is operating at 100% power, with the following:
Emergency Diesel Generator, 2EGS*EG2 is running and loaded.
Both Battery AND Battery Charger power to Division IlIl 125 VDC are lost.
Which one of the following describes the effect on Emergency Diesel Generator, 2EGS*EG2?
A.
Continues to operate but engine and output breaker protection are lost.
B.
Continues to operate but output breaker controls are lost.
C.
Trips and output breaker remains closed.
D.
Trips and output breaker opens.
Proposed Answer: C Justification:
C is correct - Emergency Diesel Generator trip without DC power and output breaker will remain as is. A/B incorrect - Emergency Diesel Generator will not continue to run. D incorrect - Output breaker cannot open without control power Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-04 K/A:
264000:
K6.09, Knowledge of the effect that a loss or malfunction of the Emergency following will have on the EMERGENCY GENERATORS; DC Power Generators (Diesel) 10 CFR Part 55 Content:
55.41(7) x Question Source:
Bank#
X NM2 bank # 15974 GRP 5 Modified Bank #
New History:
Question Cognitive Level: l Memory or Fundamental Knowledge l X Comprehension or Analysis LOD 3
Comments: None
Examination Outline Cross-
Reference:
2 2
Group #
2 3
K/A #
201003 201003 Importance Rating 3.3 3.A Proposed Question: RO 65, SRO 81 The plant is operating at 100% power, the scram inlet valve for a control rod at position 24 opens.
Which one of the following identifies the response of reactor power AND scram discharge volume (SDV) level to this event?
REACTOR POWER A.
Rises B.
Rises C.
Lowers D.
Lowers Proposed Answer: C SDV LEVEL Stays the same Rises Stays the same Rises Justification C is correct - opening of the scram inlet valve will cause the control rod to drift in, resulting in a drop in reactor power. Because the scram outlet valve did not open, SDV level remains the same. A&B are incorrect - reactor power lowers, not rises.
D is incorrect - SDV level remains the same, it does not rise.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-O PS-001-201-2-01 KA:
201003, Control K5.03, Knowledge of the operational implications of the following concepts as they Rod And Drive apply to CONTROL ROD AND DRIVE MECHANISM: Reactor power control Mechanism 10 CFR Part 55 Content:
55.41.6 55.43 Question Source:
Bank#
X NMP2 exam bank: Group 5 Question 148 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
2 Group#
2 K/A #
201003 Importance Rating 3.7 Proposed Question: RO 66 The plant is operating at power, with the following:
Control rod 22-19 is fully withdrawn A coupling integrity check is performed on control rod 22-19 Annunciator 603444, "CONTROL ROD OVERTRAVEL", alarms Which one of the following identifies the position indication displayed on the Four Rod Display window for control rod 22-19 after movement has been completed for the coupling check?
A.
Blank B.
XX C.
48 D.
50 Proposed Answer: A Justification:
A. correct because it indicates the position indication for control rod 22-19 on the Four Rod Display will be blank.
B. incorrect this is failed RPIS.
C. incorrect this is full out indication coupled.
D. incorrect this is not indicated on display.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-ARP-01 603444 KA:
201003 Control A3.01 Ability to monitor automatic operations of the CONTROL ROD AND Rod and Drive DRIVE MECHANISM including: Control rod position Mechanism 10 CFR Part 55 Content:
55.41.6 55.43 Question Source:
Bank #
Group 3 Question 185 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 Group #
2 K/A #
202001 Importance Rating 2.6 Proposed Question: RO 67 A reactor startup is in progress with power at 15%, with the following indications for Recirculation Pump (RCS) Pl B:
0 0
Seal Purge Flow No. 1 Seal Cavity Temperature No. 2 Seal Cavity Temperature 0 gpm 150OF and steady 153 0F and steady Which one of the following describes the impact on continued operation of RCS P1 B per N2-OP-29, Reactor Recirculation System?
A.
Is allowed without any restrictions.
B.
Is allowed provided CCP is available.
C.
Is not allowed and the pump must be tripped within 90 seconds.
D.
Is not allowed and the pump should be shutdown using the normal shutdown procedure.
Proposed Answer: B Justification:
B is correct - With no CRD seal purge, continued pump operation allowed per N2-OP-29 as long as CCP is available. AICID incorrect -
not correct per N2-OP-29.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-29 KA:
202001 A1.10 Ability to predict and/or monitor changes in parameters Recirculation associated with operating the RECIRCULATION SYSTEM controls system including: 'Seal purge flow' 10 CFR Part 55 Content:
55.41(10)
X 55.431 Question Source:
Bank#
X Question from NM2 bank #17778 Grp 7
Modified Bank #
New History Question Cognitive Level: l Memory or Fundamental Knowledge l Comprehension or Analysis X
ILOD:
13 Comments: None
Examination Outline Cross-reference:
2 Group#
2 K/A #
204000 I Importance Rating 3.0 Proposed Question: RO 68 The plant is operating at 100% power, with the following:
A catastrophic tube rupture occurs in the Reactor Water Cleanup (WCS) System Non-Regenerative Heat Exchanger tube bundle.
The resultant leak rate is 300 gpm.
Which one of the following identifies the WCS system AND the CCP Surge Tank level responses to the tube rupture?
A.
WCS continues to operate and the CCP Surge Tank empties.
B.
WCS continues to operate and the CCP Surge Tank overflows.
C.
WCS isolates and the CCP Surge Tank empties.
D.
WCS isolates and the CCP Surge Tank overflows.
Proposed Answer: D Justification:
D is correct. For the conditions given (WCS NRHX tube leak), WCS flow will enter the CCP system because WCS system pressure is higher than CCP system pressure. As a result, the WCS system will isolate on high differential flow (after a 45 second time delay) AND CCP Surge Tank level will rise until it reaches the atmospheric vent, at which time it will overflow into the Reactor Building. A is incorrect because the WCS system will isolate AND the CCP Surge Tank level rises. B is incorrect because the WCS system will isolate. C is incorrect because the CCP Surge Tank level rises.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-204-2-00 KA:
204000, Reactor A4.06, Ability to manually operate and/or monitor in the control room:
Water Cleanup System flow System 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
Modified Bank #
X New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 Group #
2 K/A #
205000 Importance Rating 3.6 N-Proposed Question: RO 69 The plant is in Mode 3 at 272 0F with 'A' RHS Pump operating in Shutdown Cooling, with the following:
'A' RHS Pump trips on a motor electrical fault The reactor coolant begins to heat up at a constant 40F per minute At a constant heat up rate, which one of the following identifies the maximum time before Shutdown Cooling isolates?
A.
15 minutes B.
17 minutes C.
20 minutes D.
24 minutes Proposed Answer: C Justification:
C correct - From steam tables: The isolation setpoint of 128 psig/142.7 psia is equal to 354.5 degrees F. A maximum time of 20 minutes (correct ans.)
would take you to 352 degrees. A incorrect- (60 degree rise) this is subtracting 14.7 instead of adding it to 128 for psia. B incorrect - (68 degree rise) this is using 128 without converting to psia. D incorrect - (96 degree rise) NP Proposed references to be provided to applicants during examination: Steam Tables Technical Reference(s):
02 OPS-001-205-2-00, EO-1.7 KA:
205000, Shutdown K1.01, Knowledge of the physical connections and/or cause effect Cooling System relationships between SHUTDOWN COOLING SYSTEM and the following:
'reactor pressure' 10 CFR Part 55 Content:
55.41.5 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge l Comprehension or Analysis X
LOD:
13 Comments: None
Examination Outline Cross-
Reference:
Group 2
K/A #
214000 Importance Rating 3.0 Proposed Question: RO 70 A reactor scram has occurred, with the following:
All rods fully insert RPS has NOT been reset Which one of the following identifies the position indicated in the Four Rod Display and the status of the "Green Full In" light on the Full Core Display, for the control rods?
Indicated Rod Position A.
00 B.
00 C.
Blank "Green Full In" light Status OFF ON OFF D.
Blank Proposed Answer: D ON Justification:
D is correct -With RPS tripped, the rod is driven past the 00 position switch. The full in overtravel position will light the Green Full In light, but the Four Rod display will be blank. A/C are incorrect - The full in overtravel position will light the Green Full In light B is incorrect - With RPS tripped, the rod is driven past the 00 position switch.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-00 1-201-2-03 KA:
214000, Rod K4.01, Knowledge of ROD POSITION INFORMATION SYSTEM design feature(s)
Position and/or interlocks which provide for the following: Reed switch locations Information System 10 CFR Part 55 Content:
55.41.7 55.43 Question Source:
Bank#
Modified Bank #
X NMP2 exam bank: Group 7 Question 73 New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group#
2 2
K/A #
214000 214000 Importance Rating 2.8 2.7 Proposed Question: RO 71, SRO 7 The plant is operatin" 100% power whe the InstrumentAirsupply line to the in-service Control Rod Drive (RDS) systep fl w n
ve (2 S*
actuator breaks.
Which one of the following identifies the response of the Control Rods/Drive Mechanisms (CRDMs) to this Instrument Air line break?
A.
CRDM temperatures will rise B.
CRDM temperatures will lower C.
Control rods will drift in D.
Control rods will drift out Proposed Answer: A Justification:
A is correct because it indicates that CRDM temperatures will rise as a result of the Instrument Air line break. B is incorrect because CRDM temperatures will NOT lower as a result of the Instrument Air line break. CRDM temperatures will rise due to closure of the in-service RDS flow control valve.
C is incorrect because control rods will NOT drift in as a result of the Instrument Air line break. CRDM temperatures will rise due to closure of the in-service RDS flow control valve. D is incorrect because control rods will NOT drift out as a result of the Instrument Air line break. CRDM temperatures will rise due to closure of the in-service RDS flow control valve.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001 -201-2-01 KA:
214000 RPIS A4.03 Ability to manually operate and/or monitor in the control room: Control I
rod drive temperature 10 CFR Part 55 Content:
55.41.10 55.43 Question Source:
Bank#
Group 6 Question 152 Modified Bank#
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-
Reference:
2 Group 2
2 K/A #
215002 215002 Importance Rating 3.3 3.5 Proposed Question: RO 72, SRO 71 A reactor startup is in progress, with the following:
- Reactor power is 40%
Control rod 22-31 is selected and being withdrawn from positionn Annunciator 603204, "RBM UPSCALE/INOPERABLE", alarms then clears Control rod 22-31 settles at position>2-Both Rod Block Monitor (RBM) channel "A" AND "B" "ALARM SET INTM" lights are now illuminated Which one of the following identifies the procedural action required to continue control rod withdrawal?
A.
Bypass one RBM channel to continue rod withdrawal and notify the System Engineer B.
Depress the PUSH TO SET UP pushbuttons then continue control rod withdrawal C.
Stop all control rod movement and contact the Reactor Engineerf6r ass-isfance D.
Place one RBM channel keylock switch to INOP Proposed Answer: B Justification B is correct - Step 2.0 of 603204, `RBM UPSCALE/ INOPERABLE", states "IF the ALM SET LO OR ALARM SET INTM light is lit, THEN depress the PUSH TO SET UP pushbutton". An-nunciator clears because alarm setpoint changes. A/ICD are incorrect - wrong action per procedure.
Technical Reference(s):
02-OPS-001-215-2-06, EO-1.7e, N2-ARP-01 Window 603204 KA:
215002, Rod A2.01, Ability to predict and/or monitor the impacts of the following on the ROD Block Monitor BLOCK MONITOR SYSTEM and based on those predictions, use procedures to System correct, control or mitigate the consequences of those abnormal conditions or operations: Withdrawal of control rod in a high power region of the core.
10 C FR Part 55 Content:
55.41.7 X
55.43 Proposed references to be provided to applicants during examination: None Question Source:
Bank #
X NMP2 exam bank: Group 7 Question 92 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD 2
Comments:
None
Examination Outline Cross-
Reference:
2 Group#
2 K/A #
215002 Importance Rating 3.3 Proposed Question: RO 73 A reactor startup is in progress, with the following:
Reactor power is 25%X/"
Total Re rculation Flow ignals received by the Rod Block Monitors (RBMs) are as follows:
32%
K30%
41%
38%
Which one of the following describes the capability to drive individual control rods?
A.
Can INSERT or WITHDRAW B.
Can INSERT Only C.
Can WITHDRAW Only D.
Can neither INSERT nor WITHDRAW Proposed Answer: B Justification:
B is correct - Alarm setpoint is 10%, initiates a withdraw block only and is active at any power level. AICID are incorrect - a WITHDRAW block is initiated.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-215-2-06, EO-1.7e, N2-ARP-01 Window 603217 KA:
215002, Rod 2.4.50, Ability to verify system alarm setpoints and operate controls identified in the Block Monitor alarm response manual System 10 ClR Part 55 Content:
55.41.7 55.43 Question Source:
Bank #
X NMP2 exam bank: Group 7 Question 92 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 Group #
2 K/A #
256000
- Importance Rating 2.8 Proposed Question: RO 74 The plant is operating at 85% power, with the following:
7 Condensate Demins are in service and 2 in standby Fourth Point Heater drain pump 'A' trips on electrical fault.
Which one of the following describes the effect on the Condensate Demineralizer differential pressure (D/P) and the required actions?
A.
D/P lowers, remove Demineralizers as necessary.
B.
D/P rises, open Condensate Demineralizer Bypass Valve.
C.
D/P lowers, verify closed Condensate Demineralizer Bypass Valve.
D.
D/P rises, place in service standby Demineralizers as necessary.
Proposed Answer: D Justification:
D is correct based on the loss of the pumping forward by one heater drain pump. Condensate System Flow rises and causes a higher demineralizer D/P and a drop in Booster Pump Suction pressure. Placing additional demineralizers in service will restore system dp. A is the inverse of the correct answer, C adds the normal power to be lowered to in N2-SOP-8 for unplanned power changes. B Condensate Demineralizer Bypass Valve is not opened under theses conditions.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-ARP-01 (page 1327 - 851403), N2-SOP-8 K/A:
256000, Reactor A2.16, Ability to (a) predict the impacts of the following on the reactor Condensate condensate system and (b) based on those predictions, use procedures to System correct, control, or mitigate the consequences of those abnormal conditions or operations: High demineralizer differential pressure.
10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 2
Group #
2 1
K/A #
262001 262001
_ Importance Rating 3.5 3.7 Proposed Question: RO 75, SRO 66 The plant is operating at 100% power, with the following:
A loss of Line 6 occurs 15 seconds later, a loss of Line 5 occurs Which one of the following identifies the Control Building Special Filter Train(s), if any, that will be running after power is restored by the Emergency Diesel Generators?
A.
Neither Special Filter Train B.
Only Special Filter Train "A" C.
Only Special Filter Train "B" D.
Both Special Filter Trains "A and "B" Proposed Answer: C Justification:
C is correct - If loss of second Division occurs > 8 seconds after the first Division then the start of the second fan will be blocked. A is incorrect - this would occur if EDGs did not re-energize buses. B is incorrect - this would be if line 5 were lost followed by line 6 > 8 seconds later. D is incorrect - this is if loss occurred < 8 seconds apart Proposed references to be provided to applicants during examination: None Technical Reference(s):
02 OPS-001-288-2-02, EO-1.5, N2-SOP-03 KA:
262001, Electrical K3.01, Knowledge of the effect that a loss or malfunction of the A.C.
l Distribution ELECTRICAL DISTRIBUTION will have on: 'major system loads' 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
X NM-2 system final Q-57 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 Group #
2 KIA #
262002 Importance Rating 2.8 Proposed Question: RO 76 Due to an overcurrent condition, plant AC Bus NJS-US3 is lost, de-energizing the Normal AC input to 2VBB-UPS1A.
Which one of the following describes the 2VBB-UPSIA load response?
A.
Transfers to the maintenance AC source.
B.
Lost due to a loss of "synch" with the maintenance AC supply.
C.
Continuously supplied by the DC input until Bus NJS-US3 is restored.
D.
Momentarily supplied by DC and then supplied by the alternate Normal AC source.
Proposed Answer: D Justification:
D correct - on a loss of normal AC input, UPS will be supplied from DC input for about 30 seconds while VBB-TRS1 transfers the normal AC input to US-4. AIBIC incorrect - do not function as above.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-262-2-03 KA:
262002:
A3.01: Ability to monitor automatic operations of the Uninterruptable Power UNINTERRUPTABLE POWER SUPPLY SYTEM including:
Supply
'Transfer from preferred to alternate source' 10 CFR Part 55 Content:
55.41 X
(7 )
55.43 Question Source:
Bank#
X Question from NM2 bank #8100 Grp 6, ques 58 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Examination Outline Cross-reference:
2 2
Group #
2 2
K/A #
263000 263000 Importance Rating 3.1 3.4 Proposed Question: RO 77, SRO 76 The plant is operating at 100% power, when a loss of 125VDC Bus 2BYS-SWG001C occurs.
Which one of the following identifies the Uninterruptible Power Supplies (UPS's) that will lose DC power?
A.
2A and 2B B.
ID and 3B C.
1A, IC and 1G D.
1B, 1Gand3A Proposed Answer: D Justification:
D is correct. UPS 1 B, 1 G AND 3A receive backup dc power from 2BYS-SWG001C A incorrect-dc power from *SWG002B. B incorrect-dc power from SWG001 B C incorrect-dc power from SWG001A, except IG Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-262-2-03 KA:
263000, D.C K2.01: Knowledge of the electrical power supplies to the following:
Electrical Major D.C. loads Distribution 10 CFR Part 55 Content:
55.41.7 X
55.43.
Question Source:
Bank #
Modified Bank #
New X
History.
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis
. LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group#
2 2
K/A #
263000 263000 Importance Rating 2.5 2.8 Proposed Question: RO 78, SRO 77 During a period of heavy loading on the Division 1 125 VDC Bus, bus current rises to 375 amps.
Which one of the following describes the resultant condition of the Division I battery charger AND battery?
A.
The battery charger will supply the entire current load B.
The battery will supply the entire current load C.
The battery charger will supply 345 amps AND the battery will supply the remaining current load D.
The battery will supply 345 amps AND the battery charger will supply the remaining current load Proposed Answer: C Justification:
A is incorrect because the battery charger will NOT supply the entire current load. The battery charger will supply 345 amps AND the battery will supply the remaining current. B is incorrect because the battery will NOT supply the entire current load. The battery charger will supply 345 amps AND the battery will supply the remaining current. C is correct because it indicates that the battery charger will supply 345 amps AND the battery will supply the remaining current load. D is incorrect because the battery will NOT supply 345 amps. The battery charger will supply 345 amps AND the battery will supply the remaining current load Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-74A, 02-OPS-001-263-2-01 KA:
263000 DC A1.01 Ability to predict and/or monitor changes in parameters associated Electrical with operating the DC Electrical Distribution controls including: Battery Distribution charging/discharging rate 10 CFR Part 55 Content:
55.41.10 55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-
Reference:
2 Group #
2 K/A #
271000 Importance Rating 3.4 Proposed Question: RO 79 The plant is operating at 100% power when a control rod drop accident and fuel element failure occurs.
Offgas radiation levels go into alarm as follows:
At 0618, 2OFG-RE13A goes to ALERT (Yellow)
At 0621, 2OFG-RE1 3B goes to ALERT (Yellow)
At 0630, 2OFG-RE13B goes to HIGH (Red)
At 0635, 2OFG-RE13A goes to HIGH (Red)
Which one of the following describes the earliest time when the Offgas System Discharge Valve (20FG-AOV1 03) will automatically close?
A.
0618 B.
0621 C.
0630 D.
0635 Proposed Answer: D Justification:
D is correct-Both RE13's have to be Red. AIB/C are incorrect - Both RE13's are not yet Red Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-ARP-01, 851253 KA: l 271000, Offgas K6.09, Knowledge of the effect that a loss or malfunction of the following will have on I System the OFFGAS SYSTEM: Fuel cladding integrity 10 CFR Part 55 Content:
55.41.10 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group#
2 2
K/A #
286000 286000 Importance Rating 3.2 3.4 Proposed Question: RO 80, SRO 78 One zone of Computer Room Underfloor Area fire detection is inoperable and has been placed in Alarm Only. This area is protected by cross zone detection.
Which one of the following identifies the impact of this failure if an actual fire occurs in the room?
The remaining zone will.....
A.
actuate local/control room alarms, but fire suppression must be manually actuated.
B.
actuate local/control room alarms and fire suppression will be automatically actuated.
C.
not actuate local/control room alarms, but fire suppression will be automatically actuated.
D.
not actuate local/control room alarms and fire suppression must be manually actuated.
Proposed Answer: A Justification:
A correct - alarms occur off either zone, suppression requires both. B incorrect - requires one detector in both zones. C incorrect - alarms are from either zone, suppression requires both. D incorrect - alarms will still occur from the remaining zone.
Proposed references to be provided to applicants during examination: N2-OP-47 (without attachments)
Technical Reference(s):
N2-OP-47, 02-OPS-001 -286-02-01 KA:
286000, Fire K3.01, Knowledge of the effect that a loss or malfunction of the FIRE I Protection System PROTECTION SYSTEM will have on the following: 'Ability to detect fires.
10 CFR Part 55 Content:
55.41(4)
X 55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level: l Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-
Reference:
2 Group#
2 K/A #
290003 Importance Rating 3.2 Proposed Question: RO 81 The plant has experienced a large break LOCA inside the Drywell, with the following:
Drywell pressure is 5 psig Both Control Building Special Filter Train Booster Fans start at 1200 Which one of the following identifies the latest time that both Control Building Special Filter Train Booster Fans can remain running and why, per N2-OP-53A, Control Building Ventilation System?
A.
1220 to prevent excessive positive Control Room pressure.
B.
1220 to prevent excessive radiation exposure to personnel.
C.
2000 to prevent excessive positive Control Room pressure.
D.
2000 to prevent excessive radiation exposure to personnel.
Proposed Answer: B Justification B is correct - CAUTION in Step H 1.0 of N2-OP-53A states "BOTH Special Filter Trains start simultaneously on a valid LOCA/Hi Rad signal. Failure to shutdown one of the operating fans 2HVC*FN2A(B) within 20 minutes of Actuation CAN result in the Control Room personnel receiving Excessive Radiation Exposure". AICID are incorrect - not an action directed in either N2-EOP-6 Attachment 1 or N2-OP-53A. There is an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> requirement to close one of the Building intake dampers under LOCA conditions.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-6 Attachment 1 (Step 3.2.2.1), N2-OP-53A (CAUTION H 1.0)
K/A 290003, K5.01 Knowledge of the operational implications of the following concepts as they apply to CONTROL ROOM HVAC: Airborne contamination (example: radiological, toxic gas, smoke) control KA:
290003, Control K5.01, Knowledge of the operational implications of the following concepts as they Room HVAC apply to CONTROL ROOM HVAC: Airborne contamination (example: radiological, toxic gas, smoke) control 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments:
None
Examination Outline Cross-reference:
2 Group #
2 K/A #
300000 Importance Rating 2.8 Proposed Question: RO 82 Exces r
S ccurs, w ollowing:
Instrument Air pressure as read at P851 is 80 psig.
The Lead and Lag compressors are running Which one of the following identifies the expected status of the Back-Up Compressor and Service Air Header isolation (21AS-AOV171) at this pressure?
BACK-UP COMPRESSOR 21AS-AOV171 A.
On Closed B.
On Open C.
Off Closed D.
Off Open Proposed Answer: A Justification:
A correct - Backup compressor starts and 21AS-AOVI71 closes at 85 psig.
B incorrect - SA isolates at same setpoint. C incorrect - B/U Comp starts at same pressure as SA iso. D incorrect - normal conditions prior to low air pressure Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-279-2, EO-1.4, SOP-19 KA:
- 300000, K4.01, Knowledge of design features and/or interlocks which provide for the Instrument Air following: 'Manual/automatic transfers of controllers' System 10 CFR Part 55 Content:
55.41.4 X
55.43 Question Source:
Bank #
X NM-2 Q8403 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group#
2 2
K/A #
400000 400000 Importance Rating 3.2 3.4 Proposed Question: RO 83, SRO 80 Piping failures resulted in a loss of Reactor Building Clo ed Loop Cooling (CCP) flow. Which one of the following components can still be cooled following
/loss? b 4,f j i
A.
Drywell Unit Coolers 1Fl' B.
RHS Pump Seal Coolers C.
RDS Pump Seal Coolers D.
Drywell Equipment Drain Coolers Proposed Answer: B Justification:
B correct - RHS Pump seal coolers can also be supplied with Service Water. A/C/D incorrect - loads cooled by CCP only.
Technical Reference(s):
N2-SOP-1 3 K/A:
- 400000, K1.02, Knowledge of the physical connections and/or cause-effect Component relationships between COMPONENT COOLING WATER SYSTEM cooling water and the following: Loads cooled by CCWS system 10 CFR Part 55 Content:
55.41.4 X
55.43 Proposed references to be provided to applicants during examination: None Question Source:
Bank #
Modified Bank#
X New History Last NRC Exam.
Question # 12338 modified from INPO bank (LGS - 1998 Exam).
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD 2
Comments: None
Examination Outline Cross-reference:
12 Group #
3 K/A #
233000
_Importance Rating 2.9 Proposed Question: RO 84 The plant is operating at 100% power, with the following:
Spent Fuel Cooling Pump (SFC) "A" is in service Fuel pool gates installed.
Then, SFC Pump "A" trips Which one of the following describes fuel pool and SFC Surge Tank "A" level response?
Fuel Pool Level SFC Surge Tank "A" Level A.
Remains the same Remains the same B.
Remains the same Rises C.
Lowers to bottom of weir Remains the same D.
Lowers to bottom of weir Rises Proposed Answer: D Justification:
D is correct - Overflow from weirs to SFC Surge Tank lowers pool level and raises Surge Tank level. A/BIC incorrect - Surge tank Level rises as Pool drains to Surge Tank Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-233-2-00 Spent Fuel Pool Cooling & Cleanup K/A:
233000, Fuel K4.06, Knowledge of Fuel Pool Cooling and Cleanup design feature(s) and Pool Cooling and or interlocks which provide for the following: 'Maintenance of adequate pool Clean-up level'.
10 CFR Part 55 Content:
-55.41 (7)
X 55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge l
Comprehension or Analysis X
LOD 3
Comments: None
Examination Outline Cross-reference:
2 2
Group#
3 2
KIA #
234000 234000 Importance Rating 3.0 3.7 Proposed Question: RO 85, SRO 73 Which one of the following describes an indication of a fuel assembly that has been improperly oriented in the core?
A.
The channel fastener is adjacent to the center of the fuel cell.
B.
The identification boss on the bail handle points toward the top guide.
C.
The channel spacing buttons are adjacent to the control rod passage area.
D.
The fuel assembly identification number on the bail handle is readable from the direction of the center of the fuel cell.
Proposed Answer: B Justification:
B correct -.D boss should point toward the center of the cell to be correctly oriented. A incorrect - number (1) per OPTECH. C incorrect - number (3) per OPTECH. D incorrect - number (4) per OPTECH.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-101-2-02, EO-1.5 KA:
234000, Fuel K5.05, Knowledge of the operational implications of the following as they Handling apply to FUEL HANDLING EQUIPMENT: 'Fuel orientation' Equipment 10 ClR Part 55 Content:
55.41(2)
X Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Examination Outline Cross-reference:
2 2
Group 3
3 K/A #
288000 288000 Importance Rating 2.8 2.9 Proposed Question: RO 86, SRO 83 The plant is in Mode 4 and startup preparations in progress, with the following:
A Reactor Building Ventilation system startup is in progress per N2-OP-52, Reactor Building Ventilation Division 1 and 2 Low Flow Isolation switches are in "OVERRIDE".
All running Reactor Building Exhaust fans trip.
Which one of the following Reactor Building Ventilation System actions will occur?
A.
Supply fans auto trip immediately.
B.
Supply fans auto trip after a time delay.
C.
"B" Emergency Recirc fan auto starts immediately.
D.
"B" Emergency Recirc fan auto starts after a time delay.
Proposed Answer: B Justification:
B correct - 1 0 second TD on high dp. A incorrect - this would occur on isolation damper closure. CID incorrect - occur only if flow isolation is not bypassed.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
02-OPS-001-288-2-03 K/A:
288000, Plant K4.03, Knowledge of PLANT VENTILATION SYSTEMS design feature(s)
Ventilation and/or interlocks which provide for the following: Automatic starting and systems stopping of fans 10 CFR Part 55 Content:
55.41(7)
X 55.43 Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD 3
Comments: None
Examination Outline Cross-reference:
2 2
Group #
3 3
K/A #
290002 290002 Importance Rating 3.6 3.9 Proposed Question: RO 87, SRO 84 The plant is operating at 100% power, with the following:
A Drywell Instrument Nitrogen line break occurs inside the Drywell resulting in a rapid loss of Nitrogen pressure AND rapid closure of the inboard MSIVs 14 Safety Relief Valves opened AND then immediately re-closed Which one of the following identifies the effect of this transient on the RPV Pressure Safety Limit AND RPV pressure control actions specified in N2-EOP-RPV, RPV Control?
SAFETY LIMIT A.
Will not be exceeded B.
Will not be exceeded C.
Will be exceeded D.
Will be exceeded RPV PRESSURE CONTROL METHOD Use sustained SRV opening using the 'C' solenoid only Use ADS SRVs using the 'A/B' solenoids only Use sustained SRV opening using the 'C' solenoid only Use ADS SRVs using the 'A/B' solenoids only Proposed Answer: A Justification:
[A correct - per USAR, Safety Limit will not be exceeded following MSIV closure at rated power. Sustained SRV opening is directed.
B incorrect - operation of ADS solenoids is prohibited.
C&D incorrect - per USAR, Safety Limit will not be exceeded following MSIV closure at rated power.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-RPV K/A:
290002, Reactor A2.02, ability to (a) predict the impacts of the following on the Vessel Internals RECQB.V2G&EL-lNIERNALS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
overpressurization transient.
10 CFR Part 55 Content:
55.41.5 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge l Comprehension or Analysis X
LOD 2
Comments: None
Examination Outline Cross-reference:
3 Group#
K/A#
2.1.10 Importance Rating 2.7 Proposed Question: RO 88 While performing a tour on the Refuel Floor, you note that the New Fuel Storage Vault is partially open AND 15 new fuel bundles are uncovered.
Which one of the following identifies the station document that contains the requirement that is being violated?
A.
Core Operating Limits Report B.
Core Reactivity Control Book C.
Facility ALARA Program D.
Facility Operating License Proposed Answer: D Justification:
D is correct-Tech Spec Operating License Condition C.3.d A/BIC are incorrect. No such requirement exists in these documents Proposed references to be provided to applicants during examination: None Technical Reference(s):
KA:
Generic 2.1:
2.1.10: Knowledge of conditions and limitations in the facility license.
Conduct of Operations 10 C FR Part 55 Content:
55.41.10 X
55.43.l Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
3 3
[Group#
KIA #
2.1.14 2.1.14 Importance Rating 2.5 3.3 Proposed Question: RO 89, SRO 87 The plant is in an outage, with the following:
RHS pump PIA was started for Shutdown Cooling (Event 1)
RHS pump PlA is being removed from Shutdown Cooling (Event 2)
Which one of the following identifies the event(s), if any, that require a Plant Page announcement?
EVENT 1 EVENT 2 A.
Yes Yes B.
Yes.
No C.
No No D.
No Yes Proposed Answer: A Justification:
A is correct - starting or securing a large pump or fan requires station announcement. IB/C/D incorrect - not denoted as evolutions that require Gai-Tronics announcement.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Operations Manual 3.4 KA Generic 2.1:
2.1.14: Knowledge of system status criteria which require the Conduct of notification of plant personnel.
Operations 10 CFR Part 55 Content:
55.41.10 X
Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group #
K/A #
2.1.31 2.1.31 Importance Rating I 4.2 3.9 Proposed Question: RO 90, SRO 88 A loss of coolant has occurred, with the following:
A High Drywell Pressure LOCA signal is present and cannot be reset.
RCIC is injecting into the RPV.
A spurious RCIC Turbine trip occurs.
Which one of the following identifies the status of the ICS*MOV150 "red" position indicating light on the horizontal section of P601 AND the ability to operate ICS*MOV150 from P601?
P601 RED POSITION INDICATING LIGHT (HORIZONTAL SECTION)
A.
On B.
On C.
Off D.
Off P601 OPERATION CAPABILITY Yes No No Yes Proposed Answer: B Justification:
B is correct - horizontal indication is for motor operator, not the Trip And Throttle Valve itself. The red light is normally on when the turbine is reset and remains on following a turbine trip. A LOCA signal removes power from the ICS*MOV1 50 valve operator preventing operation from P601. Power remains available to the indicating lights. A&D incorrect - P601 operation not available with LOCA signal present. C incorrect - red light remains on because control power remains available.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-35 KA:
Generic 2.1:
2.1.31: Ability to locate control room switches, controls and Conduct of indications and determine they are correctly reflecting the desired Operations plant lineup.
10 CFR Part 55 Content:
55.41.7 X
55.43.
Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
4 Comments: None
Examination Outline Cross-reference:
3 3
Group #
K/A #
2.2.12 2.2.12 Importance Rating 3.0 3.4 Proposed Question: RO 91, SRO 89 While performing a step in an Operation's Surveillance Procedure, it has been determined that a normally open, motor operated Primary Containment Isolation Valve will not stroke in the closed direction, as required by the procedure.
Which one of the following identifies when the Technical Specification LCO action time is started per GAP-SAT-01, Surveillance Test Program?
The LCO time would start.....
A.
when the surveillance was logged as started.
B.
as soon as the valve failure is recognized.
C.
when the surveillance is logged as complete.
D.
at the time the surveillance was last satisfactorily completed.
Proposed Answer: B Justification:
lB correct - per step 3.6.3. A/C/D incorrect - not allowed by GAP-SAT.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
GAP-SAT-01 K/A:
Equipment 2.2.12, Knowledge of Surveillance Procedures Control 10 CFR Part 55 Content:
55.41(10)
X 55.43 Question Source:
Bank #
X NM-2 Exam Bank - ID # 13086 Modified Bank#
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis Comments: None
Examination Outline Cross-reference:
3 Group #
K/A #
2.2.28 I Importance Rating I 2.6 Proposed Question: RO 92 The plant is in MODE 5 with the following conditions:
A Core Reload is in progress All SRM's are OPERABLE All control rods are in the core Which one of the following conditions requires the Reactor Operator to notify the Fuel Handling SRO to stop fuel movement in accordance with N2-FHP-13.2, Complete Core Reload?
A.
Only radio communication between control room and refuel floor is available.
B.
High radiation level alarm on either 2HVR*CAB32A or 2HVR*CAB32B.
C.
Control rod 22-31 full-in position indication is lost in the control room.
D.
SRM Channel 'A' high voltage power supply fails.
Proposed Answer: C Justification:
C is correct - FHP-13.2 requires fuel movement be stopped if any control rod (not removed from the core) full-in position indication is lost. A is incorrect -
TRM 3.9.3 Bases allows any mode of direct communication between the control room and refuel floor, including radio. B is incorrect - ARP for 851254 (Process Airborne Radiation Monitor Activated) requires entry into N2-SOP-39, Refuel Floor Events, if either HVR Above Refuel Floor monitor (2HVR*CAB14A/B) alarms. The CAB32's are the Below Refuel Floor monitors. D is incorrect - Stem conditions specify that all 4 SRM's are OPERABLE; an INOP condition (i.e, the HV power supply failure) on the 'A' SRM channel still leaves 3 SRM's operable. Tech Spec 3.3.1.2 (Table 3.3.1.2-1) requires only 2 operable SRMs for the stem conditions.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-FHP-13.2 (Att.4); TS 3.3.1.2, TRM 3.9.3, N2-ARP-01 (Att. 21 for window 851254)
KA: IGENERIC 2.2 2.2.28, Knowledge of new and spent fuel movement procedures 10 CFR Part 55 Content:
55.41 55.43.7 7 x Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
3 3
Group 2211 K/A#
2.2.11 2.2.11
_ Importance Rating 2.5 3.4 Proposed Question: RO 93, SRO 92 Assuming any necessary approval or direction is obtained, which one of the following types of procedure changes may be prepared AND processed as a Type 1 (14 day) Procedure Change Evaluation (PCE) in accordance with NIP-PRO-04, Procedure Change Evaluations And uture Procedure Enhancements?
A change that.....
8 A.
adds a new operator action to a Special Operating Procedure.
B.
revises the acceptance criteria of a Surveillance Test procedure.
C.
adds a new motor-operated valve to the scope of an In-Service Test Procedure.
D.
affects the References And Commitments section of an Administrative Procedure Proposed Answer: A Justification:
A is correct - such a change is not a 'Change of Intent' as defined by NIP-PRO-04, Attachment 3; therefore, a Type 1 PCE would be allowed, provided that the EOP/SOP Coordinator has directed that the SOP be changed using the PCE process (Section 3.1.1). BIC are incorrect-specifically violate NIP-PRO-04, 'Change of Intent' criteria. D is incorrect - Type 1 PCE process is not allowed for changing Administrative Procedures (NIP-PRO-04, Section 3.1.2).
Proposed references to be provided to applicants during examination: None Technical Reference(s):
NIP-PRO-04 KA: l2.2, Equipment Control 2.2.11, Knowledge of the process for controlling temporary changes.
10 CFR Part 55 Content:
55.41.10 X
55.43 Question Source:
Bank #
Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge l X Comprehension or Analysis LOD:
l2 Comments: None
Examination Outline Cross-reference:
3 Group #
K/A #
2.3.2 Importance Rating 2.5 Proposed Question: RO 94 A plant transient is in progress, with the following:
An emergency at the ALERT level has been declared You are a radiation worker who has been authorized to receive an emergency radiation exposure for the purpose of protecting valuable plant equipment Which one of the following identifies the highest (TEDE dose) emergency exposure that you may receive without exceeding the limits specified in EPIP-EPP-15, Emergency Health Physics Procedure?
A.
5rem B.
10 rem C.
25 rem D.
50 rem Proposed Answer: B Justification:
B is correct - For protecting valuable plant equipment/property, emergency exposure limit is 10 rem (TEDE). A is incorrect - 5 rem emergency exposure is within the 10 rem limit, but is not the highest dose before exceeding the 10 rem limit. C is incorrect - 25 rem far exceeds the limit for protecting valuable plant property. 25 rem is the limit for saving lives or protecting large populations. D is incorrect -
50 rem far exceeds the limit for protecting valuable plant property. 50 rem could be authorized only for individuals who volunteer to save lives or protect large populations.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
EPIP-EPP-15, Attachmentl, Section 1.0 KA:
Generic 2.3.2: Knowledge of facility ALARA program 2.3:Radiation Control 10 CFR Part 55 Content:
55.41.12 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group#
Rtn 239 KIA #
2.3.9 2.3.9 Importance Rating 2.5 3.4 Proposed Question: RO 95, SRO 94 Which one of the following identifies the reason for maintaining the following pressure limits during suppression chamber purge operation?
Less than 0.41 psig suppression chamber pressure Not be more negative than -1.0" Water Reactor Building differential pressure2 (a
To prevent cross flow from the...
A.
suppression chamber to the drywell.
e<
B.
drywell to the suppression chamber.
C.
suppression chamber to the reactor building.
D.
reactor building to the suppression chamber.
9 An%.
Proposed Answer: C Justification:
C is correct-Supp. Chamber reverse flow could occur if limits are exceeded. A&B incorrect-limits on SC to DW DP. D incorrect-wrong direction Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-61A, pg.24 KA:
Generic 2.3:
2.3.9: Knowledge of the process for performing a containment purge.
Radiation Control 10 CFR Part 55 Content:
55.41.13 X
-55.43.
Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis
. LOD:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group#
K/A#
2.3.11 2.3.11 Importance Rating 2.7 3.2 Proposed Question: RO 96, SRO 96 Which one of the following describes the reason that N2-EOP-RR, Radiation Release Control, directs the operation of the Turbine Building Ventilation System?
To ensure that.....
A.
any release is elevated and monitored.
B.
any release is treated prior to discharge.
C.
ground level releases are maximized.
D.
the Turbine Building is at negative pressure.
Proposed Answer: A Justification:
A is correct. Turbine Building Ventilation System provides for an elevated and monitored release via the Stack. B is incorrect. TB Ventilation System does not treat the process flow. C is incorrect.
Non-plausible. D is incorrect. Not stated by bases.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-RR Bases KA: l 2.3.11 2.3.11 Ability to control radiation releases.
10 CFR Part 55 Content:
5543 X
Question Source:
Bank #
X Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group K/A#
2.4.18 2.4.18 Importance Rating 2.7 3.6 Proposed Question: RO 97, SRO 97 A Failure To Scram (ATWS) has occurred, with the following:
Suppression Pool temperature is 112OF and steady Reactor water level is being intentionally lowered to reduce power Which one of the following is prevented by specifying a minimum level limit per N2-EOP-C5, Failure to Scram, while lowering RPV level?
A.
Thermal hydraulic instabilities B.
Inadvertent ECCS pump starts C.
Peak cladding temperatures above 1500OF D.
Uncovering Fuel Zone instrument variable leg taps Proposed Answer: C Justification:
C is correct - this is the reason for the Minimum Steam Cooling Water Level (MSCWL) limit. A is incorrect - a maximum level of 100 inches is specified in EOP-C5 step L-7 for this concern. B is incorrect - ECCS Pumps will start as level is lowered to the MSCWL, since their initiation setpoint is above MSCWL. D is incorrect - Fuel Zone Instruments are used when level is at MSCWL.
Proposed references to be provided to applicants during examination: None Question Source:
Bank#
X INPO Bank# 12276 Modified Bank #
New History ILGS 1998 NRC exam Question Cognitive Level: I Memory or Fundamental Knowledge X
Comprehension or Analysis LOD 3
Comments: None
Examination Outline Cross-reference:
Tier #
3 3
Group #
K/A #
2.4.27 2.4.27 Importance Rating 3.0 3.5 Proposed Question: RO 98, SRO 99 The plant is operating at 100%, when a Main Turbine Lube Oil fire starts, with the following:
Automatic fire suppression is in service Multiple fire alarms are illuminated on P849 Which one of the following describes the Chief Shift Operator's actions in accordance with E Fire Fighting?
A.
Sound the Fire Alarm and direct the Fire Brigade to the scene B.
Sound the Station Alarm and direct the Fire Brigade to the scene C.
Call the Fire Brigade leader and direct them to the alarming fire panels D.
Call the OSC and direct the Fire Brigade leader to the alarming fire panels Proposed Answer: A Justification:
A is correct - automatic fire suppression has initiated so Fire Alarm/Announcement is appropriate. B is incorrect - the Fire Alarm is the appropriate alarm. C is incorrect - automatic fire suppression initiation requires use of Alarm/Announce verses phone call and investigation. D is incorrect - the OSC would not be manned and Alarm/Announce would be required verses phone call and investigate..
Proposed references to be provided to applicants during examination: None Technical Reference(s):
EPIP-EPP-28, Sec 3.1, Attachment 1 KA:
2.4, Emergency 2.4.27, Knowledge of fire in plant procedure Procedures/Plan 10 CFR Part 55 Content:
55.41.10 X
55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-
Reference:
3 3
Group #
K/A #
2.4.32 2.4.32 Importance Rating 3.3 3.5 Proposed Question: RO 99, SRO 100 The plant is operating at 100%, when electrical faults on various Foxboro cabinets result in a loss of all annunciator capability.
Which one of the following identifies the required actions per N2-SOP-91, Loss of Control Room Annunciators?
Assign.....
A.
a licensed operator to monitor all control room panels B.
any operator to monitor all control room panels C.
a licensed operator to perform rounds twice per shift in all buildings D.
any operator to perform rounds twice per shift in all buildings Proposed Answer: A Justification:
A is correct - N2-SOP-91 requires a licensed operator to monitor all affected panels B is incorrect - requires a licensed operator C/D are incorrect - building rounds must be performed continuously Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-91 KA: lGENERIC 2.4.32, Knowledge of operator response to loss of all annunciators 10 CFR Part 55 Content:
55.41.7 X
55.43 Question Source:
Bank#
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-
Reference:
3 3
Group #
K/A #
2.4.35 2.4.35 Importance Rating 3.3 3.5 Proposed Question: RO 100, SRO 99 The plant is at 100% power when a SCRAM occurs, with the following:
An RPS is tripped All of the blue lights are illuminated on the full-core display Rods are not all in SLS fails to initiate Radiation levels make Reactor Building elevation 328' inaccessible Which one of the following methods should be used to shut down the reactor?
A.
Individually scram the control rods C.
Inject boron using the SLS hydro pump Proposed Answer: D Justification D is correct-RB elevation 289' is accessible, and hydro pump boron injection would be effective. AIB are incorrect - with scram valves already open, neither would be effective. C is incorrect -
RB elevation 328' is inaccessible Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-6 KA:
GENERIC 2.4.35, Knowledge of local auxiliary operator tasks during emergency operations including system geography and system implications.
10 CFR Part 55 55.41.7 X
Content:
55.43 Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
ES-401 Site-Specific Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific Written Examination Applicant Information Name:
Region:
n1 1111/ IV Date:
(A 21 2_O D Facility/Unit: tlt.L4114 Pot;lt L(*L 2-License Level: RO l~g)
Reactor Type: W / CE I BW /E Start Time:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent.
Examination papers will be collected six hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value
__t OC __ Points Applicant's Score Points Applicant's Grade Percent 43 of 46 NUREG-1021, Revision 8, Supplement 1
Examination Outline Cross-reference:
1 Group #
1 K/A #
295006 Importance Rating 4.1 Proposed Question: SRO 3 The plant is at 100% power when surveillance testing finds that RPS Reactor Pressure trip unit (622-N078B) trip setpoint is 1075 psig and cannot be adjusted.
Which one of the following describes the minimum required Technical Specification action?
A.
Place the Unit in Mode 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B.
Place the Unit in mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
C.
Initiate a 'B' channel half scram within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D.
Initiate a 'B' channel half scram within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Proposed Answer: D Justification:
D is correct. Tech Spec 3.3.1.1 Condition A Required Action A.2.
A is incorrect This is Required Action G.1, which is not entered. B is incorrect but plausible if Condition H is entered directly from Table 3.3.1.1-1 Function 3. C is incorrect. This is Required Action B.2 Proposed references to be provided to applicants during examination: Technical Specification Section 3.3.1.1 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level: l Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
Group#
1 K/A #
295007 Importance Rating 3.7 Proposed Question: SRO 4 A transient has occurred resulting in entry into N2-EOP-C3, Steam Cooling, with no RPV injection sources available and the following conditions:
RPV pressure is 600 psig Fuel Zone RPV water level indicates -60 inches At which one of the following identifies the highest indicated RPV water level that requires RPV Blowdown with RPV pressure now stabilized at 800 psig?
A.
-70 inches B.
-73 inches C.
-80 inches D.
-83 inches Proposed Answer D Justification:
D is correct - -55 at 800 psig.
B incorrect --55 at 600 psig A incorrect - -42 at 600 psig C incorrect - -42 at 800 psig.
Proposed references to be provided to applicants during examination: N2-EOP-C3.
Technical Reference(s):
N2-EOP-C3 - Ref graph Z KA:
295007, High AA2.03: Ability to determine and interpret the following as they apply Reactor Pressure to HIGH REACTOR PRESSURE: 'Reactor water level' 10 CFR Part 55 Content:
55.41.
55.43.5 1X Question Source:
Bank #
Modified Bank#
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
ILOD 13 Comments: None
Examination Outline Cross-reference:
1I Group#
1 KIA #
295013 Importance Rating 4.0 Proposed Question: SRO 7 The plant is in MODE 1 when the following events occur:
A Safety Relief Valve (SRV) inadvertently opens.
Five minutes later the valve re-closes and stays closed.
Suppression Pool Cooling is placed in service as required by plant procedures.
Suppression Pool temperature values AND times are as follows:
Time Suppression Pool Temperature 08:00 85OF (initial opening of SRV) 08:03 900F 08:05 920F (SRV closes) 08:10 940F 09:00 91OF Which one of the following identifies the latest time that the next Technical Specification requirement will need to be completed? (assume one hour readings are being taken for Suppression Pool temperature AND normal channel check readings are being taken)
A.
Same day by 20:03 B.
Same day by 20:05 C.
Next day by 08:03 D.
Next day by 08:05 Proposed Answer: B Justification:
B is correct - TS.3.6.1.7 requires vacuum breakers to be tested within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of an SRV opening.
A incorrect - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> applied when above 900F.
D incorrect - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> applied to vacuum breaker test.
C incorrect - correct, but not next action.
Proposed references to be provided to applicants during examination: Technical Specification 3.6.1.7.
Technical Reference(s):
Technical Specifications 3.6.1.7 (SR 3.6.1.7.2)
KA:
295013, High 2.1.12: Ability to apply technical specifications for a system Suppression Pool Temperature 10 CFR Part 55 Content:
55.41 55.43.2 Question Source:
Bank #
Modified Bank#
New X
History:
Question Cognitive Level: l Memory or Fundamental Knowledge l Comprehension or Analysis X
LOD 3
Comments: From INPO bank - Duane Arnold # 7174
Examination Outline Cross-reference:
1 Group #
1 K/A #
295023 Importance Rating 4.6 Proposed Question: SRO 14 The plant is in a Refueling Outage when the following events occur:
An irradiated spent fuel bundle is dropped in the Spent Fuel Pool 2HVR*RE14A-1 AND 2HVR*RE14B-1 gaseous radiation monitors indicate "red" on DRMS Reactor building ventilation systems respond as designed Refuel Floor ARMs 43-RMS1 11 AND 43-RMS1 12 indicate 5.3 R/hr Which one of the following Emergency Classifications should be declared given these conditions?
A.
Unusual Event B.
Alert C.
Site Area Emergency D.
General Emergency Proposed Answer: B Justification:
B is correct - EAL Category 1.4 (Alert classification). AIC/D incorrect - not per EAL Category 1.4.
Proposed references to be provided to applicants during examination: EAL flowchart Technical Reference(s):
EAL Action Level Matrix KA:
295023, Refueling AA2.05, Ability to determine and/or interpret the following as they apply to Accidents REFUELING ACCIDENTS: "Entry conditions of emergency plan 10 CFR Part 55 Content:
55.41 55.43.5 1 X Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
1 Group #
1 K/A #
295023 Importance Rating 3.6 Proposed Question: SRO 15 The plant is in a Refueling Outage with fuel movements in progress when the following events occur:
Time Event 0830 An Unusual Event is declared due to lowering Spent Fuel Pool level 0900 Refuel Floor SRO reports irradiated spent fuel bundles in the Spent Fuel Pool have uncovered Which one of the following meets the declaration AND reporting time requirements specified in the Emergency Plan for the 'Alert' condition?
A.
Declare an Alert at 0902 AND commence State/County notifications by 0920 B.
Declare an Alert at 0900 AND commence State/County notifications by 0918 C.
Declare an Alert at 0918 AND commence State/County notifications by 0925 D.
Declare an Alert at 0914 AND commence State/County notifications by 0929 Proposed Answer: D Justification:
D is correct - Per EAL flowchart, declare within 15 minutes of discovery (EPIP-EPP-02). AND notify within 15 minutes of declaration (EPIP-EPP-20). A&B incorrect - exceed 15 minute notification. C incorrect - exceeds 15 minute declaration time.
Technical Reference(s):
EPI P-EPP-02, EPI P-EPP-20 KA:
295023 Refueling 2.4.30 Knowledge of which events related to system I Accidents operations/status should be reported to outside agencies.
10 CFR Part 55 Content:
55.41 55.43.5 X
Proposed references to be provided to applicants during examination: None Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge l Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
Group#
1 K/A #
295026 Importance Rating 4.1 Proposed Question: SRO 20 The plant is in Mode 2 at 6% power with extended RCIC testing in progress, and the following conditions:
Suppression Pool temperature 920F Suppression Pool level 200.7 ft.
Which one of the following describes the required actions per plant procedures?
A.
Enter N2-EOP-PC only.
B.
Suspend RCIC testing only.
C.
Enter N2-EOP-PC AND 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action D.
Enter 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action AND suspend RCIC testing.
Proposed Answer: A Justification:
A is correct. Ž900F is entry into EOP-PC. B&D incorrect. RCIC testing can continue until 1050F. C incorrect. LCO not entered with testing in progress.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-EOP-PC and T.S. 3.6.2.1 KA:
295026, High 2.2.22, Knowledge of limiting conditions for operations and safety Suppression Pool limits.
Temperature 10 CFR Part 55 Content:
55.41.
55.43.5 X
Question Source:
Bank #
Modified Bank#
New X
. History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
Level -RO SRO Tier #
II Group#
_1 KIA #
295031 Importance Rating 4.0 Proposed Question: SRO 24 The plant is at 100% power when Fuel Zone level indicator (21SC*LT1 3A) fails downscale.
Which one of the following actions is required by plant Technical Specifications?
A.
Initiate action within I hour to place the unit in Mode 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
B.
Restore to operable within 7 days or be in Mode 3 within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
C.
Restore to operable within 30 days or be in Mode 3 within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D.
Restore to operable within 30 days or file a written report within the following 14 days.
Proposed Answer: D Justification:
D is correct, A &B actions required per TS 3.3.3.1. A incorrect, This would be for TS 3.0.3. B incorrect, This would be for 2 channels INOP. C incorrect, S/D only called for if 2 channels INOP.
Proposed references to be provided to applicants during examination: Tech Spec 3.3.3.1 and 5.6.6 Technical Reference(s):
Tech Spec 3.3.3.1 actions Al & B1 (PAM) and 5.6.6 KA:
295031, Reactor G2.1.33 Ability to recognize indications for system operating Low water level parameters which are entry-level conditions for technical specifications.
10 CFR Part 55 Content:
55.41 55.43.2 X
Question Source:
Bank #
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
1 Group#
1 KIA #
500000 Importance Rating 3.3 Proposed Question: SRO 26 A LOCA is in progress AND Hydrogen (H2) has been released into the Primary Containment.
The following conditions exist:
Drywell H2 6.5%
Drywell 02 5%
Suppression Chamber H2 2.0%
Suppression Chamber 02 5%
Suppression pool level is 205 feet The Drywell Spray Initiation Limit is satisfied Which one of the following identifies the requirement for Drywell AND Suppression Chamber Spray operation for the given Containment H2 AND 02 concentrations?
DRYWELL SPRAY OPERATION SUPPRESSION CHAMBER SPRAY OPERATION A.
Not required Required B.
Not required Not required C.
Required Required D.
Required Not required Proposed Answer: C Justification:
C is correct - DW is at deflagration and SC is deinerted and deflagration Hydrogen exists in DW. A/B incorrect - meet conditions to spray DW per N2-EOP-PCH. D incorrect - meet conditions to spray SC Proposed references to be provided to applicants during examination: N2-EOP-PCH Technical Reference(s):
N2-EOP-PCH KA:
500000 High EA1.05, Ability to operate and/or monitor the following as they apply Containment to HIGH CONTAINMENT HYDROGEN CONC.: 'Wetwell sprays' Hydrogen Concentration 10 CFR Part 55 Content:
55.41 55.43.5 X
Question Source:
Bank #
Modified Bank X INPO bank # 905 Grand Gulf 1998 New History
\\
Question Cognitive Level:
Memory or Fundamental Knowle Comprehension or Analysis X
Comments: None
Examination Outline Cross-reference:
Level R0 SRO Tier #
1 Group #2 K/A #
295004 Importance Rating 3.6 Proposed Question: SRO 31 The plant is in MODE 1, with the following conditions:
The in-service Division I Battery Charger trips off due to an electrical protective device actuation The standby charger is unavailable Neither charger will be available for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Which one of the following identifies the cause of the trip and the time required to be in MODE 3?
Cause of TRIP TIME TO BE IN MODE 3 A.
Low DC output voltage 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B.
Low DC output voltage 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> C.
High DC output voltage 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D.
High DC output voltage 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> Proposed Answer: D Justification:
lHigh DC output voltage is the only device that will auto trip the charger. Tech Jutfcan Specs allows 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore Div 1 and then 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to be in Mode 3.
Proposed references to be provided to applicants during examination: Technical Specification 3.8.4 Technical Reference(s):
02-OPS-001-263-2-1, EO-1.4 KA:
295004, Complete A2.01, Ability to operate/and or interpret the following as they apply to or partial loss of PARTIAL OR COMPLETE LOSS OF DC POWER: 'cause of partial loss of DC DC Power power' 10 CFR Part 55 Content:
55.41 55.43.2 X
Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
1 Group#
2 K/A #
295012 Importance Rating 3.7 Proposed Question: SRO 35 The plant is in MODE 1 when all Drywell Cooling is lost due to an inadvertent Division I containment isolation signal, with the following:
Drywell pressure is 0.77 psig and rising slowly Drywell absolute pressure is 15.4 psia Drywell temperature is 151OF and rising slowly Which one of the following is the maximum time allowed by Technical Specifications before the plant is required to be in MODE 3?
A.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.
13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> C.
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> D.
20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Proposed Answer: D Justification:
D correct, Required Action A.1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore, then 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to be in Mode 3. B is incorrect, 15.4 psia is within the allowable range of 14.2 to 15.45 psia of TS 3.6.1.4 A&C incorrect, actions associated with bypassing PCIV, which has not been done.
Proposed references to be provided to applicants during examination: Tech Spec 3.6.1.4 &
3.6.1.5 Technical Reference(s):
295012, High D/W AK2.02, Knowledge of the interrelations between high Drywell Temperature temperature and the following: Drywell cooling 10 CFR Part 55 Content:
55.41.
55.43.2 1 X Question Source:
Bank #
Modified Bank#
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
Comments: None
Examination Outline Cross-reference:
I Group #
2 KIA #
295021 Importance Rating 3.4 Proposed Question: SRO 38 The plant is in MODE 5 with fuel movements in progress, when an inadvertent Shutdown Cooling isolation occurs.
Which one of the following initial actions is required by plant Technical Specifications?-
A.
Suspend Core Alterations immediately.
B.
Restore Secondary Containment Integrity immediately.,<
C.
Start the Standby Gas Treatment system within one hour)
D.
Verify an alternate method of decay heat removal available within one hour.
Proposed Answer: D Justification:
D is correct - TS 3.9.8 action A (high level.). A incorrect - this is follow up action if an alternate method of decay heat removal is determined to be not available within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. B&C incorrect - actions would be for TS 3.9.9 (low level).
Proposed references to be provided to applicants during examination:Tech Specs 3.9.8 & 3.9.9 Question Source:
Bank #
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge l Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 KA #
295029 Importance Rating 3.7 Proposed Question: SRO 40 The plant is in MODE 1 when the following events occur:
A transient results in a rising suppression pool level.
The crew is executing N2-EOP-PC, Primary Containment Control.
All efforts to reduce pool level below the SRV Tail Pipe Level Limit have been unsuccessful.
Which one of the following describes the implication of delaying RPV Blowdown?
A.
SRV tailpipe submergence could result in exceeding the Primary Containment design pressure.
B.
Containment downcomer submergence could result in exceeding the Primary Containment design pressure.
C.
SRV tailpipe vacuum breaker submergence could result in exceeding the Primary Containment design pressure.
D.
Suppression chamber to drywell vacuum breaker submergence could result in exceeding the Primary Containment design pressure.
Proposed Answer: A Justification:
A correct - per EOP-PC SPL-2 bases. B incorrect - downcomer submergence is not a concern in EOP-PC high level this is low level concern. C incorrect - vac. bkrs are in the drywell not a concern on high pool level. D incorrect - this is concern for spraying the chamber.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
EOP-PC Bases KA:
295029, High EK 1.01, Knowledge of the operational implications of the following concepts Suppression Pool as they apply to the HIGH SUPPRESSION POOL WATER LEVEL:
Water Level Containment integrity 10 CFR Part 55 Content:
55.41 X
55.43.5 Question Source:
Bank #
X Q6684 from INPO bank Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
1 Group#
2 K/A #
295032 Importance Rating 4.0 Proposed Question: SRO 42 The plant is operating at 100% power with the following conditions:
RCIC Pump Room temperature is 2360F and rising Reactor Building General Area Elevation 206 temperature is 2150F and rising.
Several fire alarms are actuated in the Reactor Building DRMS indicates radiation levels in all areas of the Reactor Building are NOT rising There are no indications of system piping breaches anywhere Which one of the following action(s) are required by the EOPs?
Reactor Shutdown Blowdown A.
Yes Yes B.
Yes No C.
No Yes D.
No No Proposed Answer: B Justification:
B is correct. 2 or more areas exceeding max safe temp. requires scram. Blowdown is not required since leak is not from a primary system (based on steady radiation levels and the presence of fire alarms). The indications provided are that the cause of the high temperature is the fire. A&C incorrect. Blowdown is not required. D incorrect. Scram is required Proposed references to be provided to applicants during examination: N2-EOP-SC, EOP 6-att.28 Technical Reference(s):
N2-EOP-SC and Bases KA:
295032, High EA2.03: Ability to determine and/or interpret the following as they Secondary apply to HIGH SECONDARYCONTAINMENT AREA Containment Area TEMPERATURE: 'cause of high area temperature' temperature 10 C FR Part 55 Content:
55.41 55.43.5 lX Question Source:
Bank #
Modified Bank #
X New History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: Question modified from INPO bank - Oyster Creek 13076
Examination Outline Cross-reference:
I Group #
2 K/A #
295032 Importance Rating 3.7 Proposed Question: SRO 43 The Plant is at 100% power when surveillance testing finds that one of the two Reactor Building Pipe Chase Area temperature detectors for elevation 292 feet has a trip setpoint of 1490F.
Which one of the following describes the Technical Specification basis for the temperature setpoint and any Technical Specification action associated with the above instrument?
TS Basis TS Action A.
Will detect leak of
Ž25 GPM B.
Will detect leak of
Ž25 GPM C.
Set to isolate to prevent equipment damage D.
Set to isolate to prevent equipment damage None required 24 hr. Action is required None required 24 hr. Action is required Proposed Answer: A Justification:
A is correct-Basis for setpoint is to detect leaks Ž25 gpm. No action req'd since only one detector required for this area.
B incorrect-right basis wrong to enter LCO C&D incorrect-wrong basis Proposed references to be provided to applicants during examination: Tech Specs Technical Reference(s):
Tech Spec 3.3.6.1 and Basis KA:
295032: High 2.2.25: knowledge of basis in technical specifications for limiting Secondary conditions for operation and safety limits.
Containment Area Temperature 10 CFR Part 55 Content:
55.41.
55.43.2 X
Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
4 Comments: None
Examination Outline Cross-reference:
2 Group #1 K/A#
211000 Importance Rating 3.8 Proposed Question: SRO 52 With the plant in Mode 2, which one of the following sets of parameters are needed to satisfy Standby Liquid Control System Technical Specification requirements?
Tank Volume(Gallons)
Sodium Pentaborate Concentration A.
4400 14%
B.
4500 14%
C.
4600 13.5%
D.
4700 13.5%
Proposed Answer: B Justification:
B is correct, parameters fall within Tech Spec 3.1.7 Figure 3.1.7-1.
AIC/D incorrect, parameters fall outside of the figure.
Proposed references to be provided to applicants during examination: Technical Specification 3.1.7 Technical Reference(s):
Tech Specs 3.1.7 KA:
211000, Standby 2.1.32, Ability to explain and apply system limits and precautions.
liquid Control System 10 CFR Part 55 Content:
55.41.
55.43.2 lX Question Source:
Bank #
X INPO bank; Quad Cities #1 6648 Modified Bank #
New History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 Group #
1 K/A #
215005 Importance Rating 3.8 Proposed Question: SRO 54 The plant is operating at 60% power with the OPRMs enabled. The following alarms are received:
"OPRM INOP/TRIP" received from APRM 1 "APRM TRIP SYSTEM UPSCALE/INOP" received from APRM 4 Which one of the following describes the automatic plant response?
A.
Reactor Scram B.
Rod Out Block only C.
Reactor Half Scram only D.
Reactor Half Scram and Rod Out Block Proposed Answer: B Justification B is correct - per N2-OP-92, need two OPRM and APRM trips.
A/CID are incorrect - wrong response. D would be correct if two trips from same function.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-OP-92 KA:
215005:
2.1.32: Ability to explain and apply system limits and precautions.
APRM/LPRMs 10 CFR Part 55 Content:
55.41.6l X E55.43 Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
f l Comprehension or Analysis Comments: This question is on the SRO exam only, but is NOT one of the required 25 SRO ONLY questions.
Examination Outline Cross-reference:
2 Group #
1 K/A #
239002 IImportance Rating I 4.0 Proposed Question: SRO 62 A major plant transient has occurred and an RPV Blowdown is required, due to exceeding the limit for Pressure Suppression Pressure. The following conditions exists:
Reactor Pressure is 650 psig Drywell Pressure is 14 psig Suppression Chamber pressure is 11 psig Suppression Pool level is 192 feet Primary Containment Sprays are unavailable Which one of the following describes the required method of depressurizing the RPV and the maximum allowable reactor pressure following the depressurization?
DEPRESSURIZATION METHOD MAXIMUM ALLOWABLE REACTOR PRESSURE A.
SRVs below 38 psig B.
SRVs below 49 psig C.
Turbine BPVs D.
Turbine BPVs below 38 psig below 49 psig Proposed Answer: D Justification:
D is correct. Proc calls for turbine BPVs since SP level is too low to use SRVs. Rx. Pressure needs to remain within 38# of SP pressure.
A&B incorrect. SP level too low for SRV use. C incorrect. This would be if SP pressure were 0.
Proposed references to be provided to applicants during examination: N2-EOP-C2 Technical Reference(s):
N2-EOP-PC, N2-EOP-C2 KA:
239002:
Topic: G 2.4.6: Knowledge of symptom bases EOP mitigation Relief/Safety strategies.
valves 10 CF R Part 55 Content:
55.41 55.43.5 X
Question Source:
Bank #
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 Group #
2 K/A#
201001
_ Importance Rating 4.3 Proposed Question: SRO 68 During a plant refueling outage and with core alterations in progress, ANN 603441, ROD DRIVE ACCUMULATOR TROUBLE alarms. The following conditions exist:
Accumulator Alarm is for rod 30-35 Rod 30-35 is fully withdrawn Accumulator pressure for rod 30-35, is 900 psig All fuel bundles around rod 30-35 are present Which one of the following identifies the actions required?
A.
Suspend Core Alterations.
B.
Insert rod 30-35 immediately.
C.
Declare rod 30-35 inoperable and disarm hydraulically.
D.
Verify Technical Specification control rod separation criteria are met.
Proposed Answer: B Justification:
B is correct, action directed from SOP-30. A&D incorrect, not correct per procedure. C incorrect, This is an action for Mode 1 or 2 only.
Proposed references to be provided to applicants during examination: N2-SOP-30 Attachment 1 and 2 Technical Reference(s):
N2-SOP-30, Tech. Spec. 3.9.5 KA:
201001, Control 2.4.4, Ability to recognize abnormal indications for system operating Rod Drive parameters which are entry-level conditions for emergency and Hydraulic System abnormal operating procedures.
10 CFR Part 55 Content:
55.41.
55.43.6 X
Question Source:
Bank#
Modified Bank #
New X
History:
Question Cognitive Level: l Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
12 Group#
2 K/A #
286000 Importance Rating 3.6 Proposed Question: SRO 79 A fire has started in the Control Building HVAC room. Thick smoke pours into the Control Room requiring a Control Room Evacuation.
Event timeline is as follows:
09:03 Fire is reported to the Control Room.
09:06 Main Control Room evacuation ordered.
a 09:08 Reactor is manually scrammed.
09:23 Control at Remote Shutdown Panel is established.
09:30 Fire is reported extinguished.
Which one of the following Emergency Event Classifications is required per the EALs?
A.
Unusual Event B.
Alert C.
Site Area Emergency D.
General Emergency Proposed Answer: C Justification:
C is correct-fire w/ control not established at RSP within 15 min is
.Site Area Emergency 7.2.4. A incorrect-this would be for fire not extinguished within 1 0 min.
B incorrect-would be for fire in vital area. D incorrect-NP Proposed references to be provided to applicants during examination: EAL Matrix Technical Reference(s):
EAL Site Area Emergency 7.2.4 KA:
286000, Fire 2.4.30: Knowledge of which events related to system Protection System operation/status should be reported to outside agencies.
10 CFR Part 55 Content:
55.41.
55.43.5
[X Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
2 Group #
3 K/A #
233000 Importance Rating 4.3 Proposed Question: SRO 82 The plant is in MODE 5 with the Spent Fuel Pool/Cavity Gates installed. Preparations are underway to flood the reactor cavity. The following annunciators alarm in the Main Control Room:
875111, "SPENT FUEL POOL LEVEL HIGH/LOW' 873317, "DIVISION I SPENT FUEL POOL LEVEL LOW' 875117, "DIVISION II SPENT FUEL POOL LEVEL LOW' Which one of the following should be utilized to keep the fuel bundles covered?
A. High Pressure Core Spray (CSH) and Low Pressure Coolant Injection (LPCI)
B. Low Pressure Core Spray (CSL) and Low Pressure Coolant Injection (LPCI)
C. Feedwater (FWS) and Condensate (CNM)
D. Makeup Water (MWS) and Condensate Transfer (CNS)
Proposed Answer: D Justification D is correct-cavity level is not threatened and injecting to the cavity will not add water to the pool. AIBIC are incorrect-injection to the cavity will not add water to the pool.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-39, Section 4.2 KA:
233000: Fuel Pool 2.4.4: Ability to recognize abnormal indications for system operating Cooling and Clean parameters which are entry level conditions for emergency and Up abnormal operating procedures.
10 CFR Part 55 Content:
55.41.
55.43.4 1X Question Source:
Bank #
Modified Bank #
New X
History I
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Examination Outline Cross-reference:
3 Group#
K/A #
2.1.6 Importance Rating 4.3 Proposed Question: SRO 85 During plant transient conditions, which one of the following describes a situation where the Reactor Operator must obtain SSS or CRS approval before taking action?
A.
Initiate a manual scram when the reactor is in jeopardy.
B.
Take an immediate operator action as specified in a Special Operating Procedure.
C.
Executing an approved procedure step that directs overriding an automatic safety feature.
D.
Overriding an automatic safety feature when continued operation will produce an unsafe condition.
Proposed Answer: D Justification:
D is correct-per OM section 3.8.8(operation of control room equipment)
A/BIC incorrect-these actions specified as not requiring prior SRO approval Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ops Manual Section 3.3.8 KA:
Generic 2.1, 2.1.6, Ability to supervise and assume a management role during Conduct of plant transients and upset conditions.
Operations 10 CFR Part 55 Content:
55.41.
55.43.5
]X Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: This question is on the SRO exam only, but is NOT one of the required 25 SRO ONLY questions.
Proposed Question: SRO 86 At 0200 a Station Blackout occurs concurrently with a failure of the Division I AND Division II Emergency Diesel Generators (EDGs). On-shift personnel are unable to start the EDGs and request the troubleshooting support of an EDG vendor who is NOT badged at the site.
Which one of the following identifies the position that through meeting minimum position requirements may authorize the On-site Security Supervisor to grant this individual temporary unescorted access to the facility in accordance with NIP-SEC-01, ProtectedNital Area Access?
A.
Shift Supervisor it G r
B.
Chief Shift Operator
(
G C.
Operations Manager D.
Technical Support Center Manager Proposed Answer: A IJustification:
A is correct. 10CFR50.54(x), (y) required Senior Licensed Opel to implement changes to plant licensing basis in an emergency.
B/C/D incorrect, Not licensed SRO positions per position requirements.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
NIP-SEC-01, Step 3.4.5, Page 8, 10CFR50.54(x), (y)
KA:
G2.1.13, Conduct 2.1.13, Knowledge of facility requirements for controlling of Operations vital/controlled access.
10 CFR Part 55 Content:
55.41.10 55.43.5 Question Source:
Bank#
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Examination Outline Cross-reference:
3 Group #
K/A #
G2.2.17 Importance Rating 3.5 Proposed Question: SRO 90 With the plant at power, which one of the following maintenance activities can the CRS approve to be performed under GAP-PSH-09, Minor Maintenance?
go A.
Meggar of a Chemistry Lab HVAC fan motor.
B.
Welding on an RHR system piping support bracket.
C.
A scheduled recurring preventive maintenance activity.
D.
Work on a plant lighting fixture located in an 'airborne' radiation area.
Proposed Answer: A Justification:
A is correct-activity allowed under GAP-PSH-09. B/CID incorrect-examples cited in GAP-PSH as not covered under Minor Maintenance.
Proposed references to be provided to applicants during examination: None Technical Reference(s): I GAP-PSH -09 Question Source:
Bank #
Modified Bank#
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
4 Comments: None
Examination Outline Cross-reference:
3 Group#
K/A #
G 2.2.23 Importance Rating 3.8 Proposed Question: SRO 91 The plant is operating at 100% power when the following events occur:
February 1 at 2400 "A" RHS pump is declared inoperable February 3 at 1200 "C" RHS pump is declared inoperable February 6 at 0600 "A" RHS pump is restored to operable status February 6 at 0800 CSH system is declared inoperable.
Which one of the following describes the time and date when the plant shall be in Mode 3 as required by plant Technical Specifications?
A.
February 8 at 2400.
B.
February 9 at 1200 C.
February 9 at 2000 D.
February 9 at 2400 Proposed Answer: B Justification:
B is correct. T.Spec 3.5.1, Required Action A - 7 day for one L.P ECCS sys. Inop plus 12 hrs to reach Mode 3. A incorrect-this would be if 12 hrs to be in Mode 3 was not added. C incorrect-this would be for 72 hr action plus 12 with C RHS and CHS INOP D-incorrect NP Proposed references to be provided to applicants during examination: Tech Spec 3.5.1 Technical Reference(s):
Tech Specs KA:
Generic 2.2, 2.2.23, Ability to track Limiting conditions for operations.
Equipment control 10 CFR Part 55 Content:
55.41.
55.43.2 X
Question Source:
Bank #
X Modified Bank #
New History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD 3
Comments: None
Proposed Question: SRO 93 The plant is at 100% Power, when a loss of Drywell Cooling occurs. The following conditions exist:
Drywell Pressure is at 0.8 psig and slowly rising.
Drywell Temperature is at 140 0 and slowly rising.
The decision has been made to vent the Primary Containment.
Which one of the following identifies chemistry sampling requirement AND vent location requirement to perform this evolution?
SAMPLE REQUIRED A.
YES B.
YES C.
NO D.
NO VENT LOCATION Drywell Suppression Chamber Drywell Suppression Chamber Proposed Answer: A Justification:
A is correct, sample required (not directed by EOPs) & DWshould be vented since only DW pressure should rise on loss of cooling.
B incorrect, venting SC would not correct problem. C&D incorrect, sampling is not required only if in EOPs.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N2-SOP-60, N2-OP-61A, H.1.0 KA:
Generic 2.3, 2.3.8, Knowledge of the process for performing a planned gaseous Radiation Control radioactive release.
10 CFR Part 55 Content:
55.41.
55.43.4 X
Question Source:
Bank #
Modified Bank #
New X
History:
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Proposed Question: SRO 95 A stuck TIP cable requires Maintenance personnel to enter the TIP room, which is posted as a Very High Radiation area.
Which one of the following identifies the plant personnel responsible for approving entry into the TIP room per GAP-RPP-08, Control Of Locked High, And Very High Radiation Areas?
A.
I, B.
RP Supervisor and Plant Manager C
OU C.
Maintenance Supervisor and SSS D.
Maintenance Supervisor and Plant Manager Proposed Answer: A ustification:correct.
RP Supervisor & SSS approval needed per GAP-RRP-
- 08. BID incorrect - not per GAP-RRP-08.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
GAP-RPP-08, Section 3.4 KA: l Generic 2.3.
2.3.10, Ability to perform procedures to reduce excessive levels of Radiation Control radiation and guard against personnel exposure.
10 CFR Part 55 Content:
55.41.
55.43.4 X
Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis 2
LOD 2
Comments: None
Examination Outline Cross-reference:
3 Group #
K/A #
2.4.22 Importance Rating 4.0 Proposed Question: SRO 98 A LOCA is in progress with the following conditions:
RPV water level is being maintained at 30 inches with Feedwater Suppression Chamber Spray is in service Drywell Sprays are available AND not in service Pressure Suppression Pressure is being exceeded by 0.5 psig Which one of the following describes the actions that are to be taken to control Primary Containment Pressure, per the EOPs?
A.
Immediately Spray the Drywell. Immediately Blowdown regardless of containment pressure response.
B.
Immediately Spray the Drywell. Blowdown only if sprays do not reduce containment pressure.
C.
Don't Spray the Drywell. Immediately Blowdown regardless of containment pressure response.
D.
Don't Spray the Drywell. Blowdown only if containment pressure cannot be maintained below design pressure limit.
Proposed Answer: B Justification:
B is correct. N2-EOP-PC directs spraying the drywell with the current conditions.
Blowdown is not warranted, since all applicable actions have not yet been taken to reduce pressure. A is incorrect. An immediate blowdown is not required since DW Sprays have not yet been placed in service and are required to be in service.
C/D is incorrect. DW Sprays have not yet been placed in service and are required to be in service.
EOP Bases for PCP-10 requires actions to be taken to lower pressure. PCP-11 to perform a blowdown assumes containment sprays have been ineffective in controlling DW pressure. Blowdown is not warranted unless DW Spray is in service AND pressure cannot be maintained below Pressure Suppression Limit Proposed references to be provided to applicants during examination: None Question Source:
Bank #
Modified Bank #
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge l X Comprehension or Analysis LOD:
3 Comments: None