ML023240348
| ML023240348 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/20/2002 |
| From: | Pisano L Constellation Energy Group, Constellation Nuclear |
| To: | Caruso J, Miller H NRC Region 1 |
| Conte R | |
| References | |
| 50-220/02-303, NMP-97938, NUREG-1021, Rev 8 50-220/02-303 | |
| Download: ML023240348 (125) | |
Text
P.O. Box 63 Lycoming, New York 13093 Constellation NMP-97938 Nuclear Nine Mile Point August 20, 2002 Nuclear Station A Member of the Constellation Energy Groupz 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 1 INITIAL OPERATOR WRITTEN EXAMINATION SUBMITTAL Mr. Miller:
In response to the NRC Corporate Notification Letter dated June 4, 2002, arrangements were made for the administration of licensing examinations at Nine Mile Point, Unit 1 during the week of September 30, 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 for review and approval.
Enclosed are the examination outline and quality checklists.
Please withhold these examination materials from public disclosure until after the examinations have been completed.
If you have any questions regarding the examination outline submittal, please contact Mr. Jerry Bobka (Facility Contact) at 315-349-2569 or Mr. Ron Thurow (General Supervisor of Operations Training) at 315-349-1182.
Sincerely, Louis t Pisanoula T Manager Nuclear Training LEP/crr
U.S. Nuclear Regulatory Commission Site-Specific Written Examination Applicant Information Name:
Region I
Date:
September 30, 2002 Facility/Unit:
Nine Mile Point Unit 1 License Level RO Reactor Type:
GE BWR-2 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 paper will be collected six hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither nor received nor received aid.
Applicant's Signature Results Examination Value:
100 Points Applicant's Score Points Applicant's Grade Percent NUREG-1021, Revision 8, Supplement 1
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A#
295007 295007 Importance Rating 2.9 3.1 Proposed Question: RO 001, SRO 002 The plant is shutdown, with the following:
Reactor Pressure is 130 psig Shutdown Cooling (SDC) is being lined-u Which one of the following describes the SDC isolation valves that can be opened?
A.
INSIDE or OUTSIDE but not both A
B.
Only the INSIDE C.
Only the OUTSIDE D.
Neither the INSIDE nor OUTSIDE Proposed Answer: A Justification:
A correct - high pressure (120 psig and above) will prevent both valves from valves from opening BIC incorrect - high pressure will prevent both valves from opening but is not specific to which valve D is incorrect-one valve can be opened with high pressure but not both Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-4, D.3 K/A:
295007 AK2.05. Knowledge of the interrelations between HIGH REACTOR REACTOR PRESSURE and the following: Shutdown cooling: Plant-Specific PRESSURE 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
X12721 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A #
295009 295009 Importance Rating 3.3 3.4 Proposed Question: RO 002, SRO 003 The plant is operating at 100% power, with the following:
A Feedwater malfunction causes RPV water level to drop to -80" before being stabilized by the operator All rods fail to insert on the scram Reactor power is 25%
Bypass valves are controlling pressure Which one of the following describes where the plant is operating on the Power to Flow Map?
The plant is operating with...
A.
adequate forced circulation B.
inadequate forced circulation C.
adequate natural circulation D.
inadequate circulation Proposed Answer: D Justification:
D is correct - Recirc pumps tripped at +5 inches; no forced flow exists. Level is -80 inches; no natural circulation exists at this low level; natural circ line is valid only at normal operating level. AIB are incorrect - Recirc pumps tripped at +5 inches; no forced flow exists.
C is incorrect - Reasons as described for D.
Proposed references to be provided to applicants during examination: Power to Flow Map, Five Loop Operation Technical Reference(s):
DDC IE00135 Power to Flow Map, Five Loop Operation Ni -ODP-PRO-0305 K/A:
295009 LOW AKI.05. Knowledge of the operational implications of the following REACTOR concepts as they apply to LOW REACTOR WATER LEVEL: Natural WATER LEVEL circulation 10 CFR Part 55 Content:
55.41(5)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A #
295009 295009 Importance Rating 3.9 3.9 Proposed Question: RO 003, SRO 004 The plant is operating at 100% power, with the following:
L 12 FW pump is running and 11 FW pump s in standby A turbine trip occurs A,
Reactor Water level drops to 35 inches Two minutes later, Reactor Water level is stable at 72 inches With no operator action, which one of the following describes the Feedwater pumps that are running to control Reactor Water level?
A.
11 and 12 running with 12 FCV closed B.
11 and 13 are both injecting to control level C.
11 and 12 running with 11 FCV closed D.
12 and 13 are both injecting to control level Proposed Answer: C Justification:
C is correct-Turbine trip and reactor level of 53" both initiate HPCI, 12 FW will control at 72" while 11 FW controls at 65" BID are incorrect 13 FW is not available two minutes after a turbine trip A is incorrect 12 FW will raise level to 72" driving 11 FW FCV closed Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-16, sect B.2, page 10 K/A:
295009 LOW AA1.01 Ability to operate and/or monitor the following as they apply to REACTOR LOW REACTOR WATER LEVEL: Reactor feedwater WATER LEVEL 10 CFR Part 55 Content:
55.41(3)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A#
295010 295010 Importance Rating 2.6 2.6 Proposed Question:
RO 004, SRO 005 The plant is at 40% power, with the following conditions:
Makeup to the drywell is in progress from the 11 nitrogen makeup line A small steam leak develops within containment It Drywell pressure rises to 3.7 psig Which one of the following identifies the additional condition required to cause automatic closure of the Drywell Nitrogen Makeup and Bleed Isolation Valves?
A.
The CAD bypass switches in NORMAL.
B.
The CAD bypass switches in BYPASS.
C.
RPV level below 5 inches and the CAD bypass switches in NORMAL.
D.
RPV level below 5 inches and the CAD bypass switches in BYPASS.
Proposed Answer: A Justification:
A is correct-pressure above isolation with isolation circuit in enabled.
C incorrect-level input not required. D incorrect-level input not required and isolation is bypassed. B incorrect-isolation is bypassed Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-223-1-04 K/A:
295010 HIGH AA1.03 Ability to operate and/or monitor the following as they apply to DRYWELL HIGH DRYWELL PRESSURE: Nitrogen makeup: Plant-Specific PRESSURE 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
X Modified Bank #
New History Susquehanna NRC '99 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A #
295014 295014 Importance Rating 4.0 4.1 Proposed Question:
RO 005, SRO 008 The plant is operating at 100% power, with the following:
A failure to scram occurs All rods fail to insert Liquid Poison is initiated RPV water level is -94 inches and stable RPV pressure is 1000 psig and stable Reactor power is 10%
Which one of the following, by itself, will cause reactor power to rise?
A.
Raising RPV water level to -41" with Feedwater B.
Terminating and preventing all RPV injection, allowing RPV level to drop' C.
Terminating all injection, initiating ADS, and allowing RPV pressure to drop D.
Starting a second CRD pump while holding RPV water level constant with Feedwater Proposed Answer: A Justification:
A correct - level is lowered below -41" to lower power. B incorrect this has already happened and yielded the opposite effect.
C incorrect - lowering pressure voids the core further, lowering power (void coeff still predominant at this power level). D incorrect Injection is below core plate, FW heating is gone, thus this source provides essentially no change in subcooling or reactivity insertion.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-ODP-PRO-0305 K/A:
- 295014, AA1.07, Ability to operate and/or monitor the following as they apply INADVERTENT to INADVERTENT REACTIVITY ADDITION: Cold water injection REACTIVITY ADDITION 10 CFR Part 55 Content:
55.41(5)
X 55.43 55.45 Question Source:
Bank #
X Modified Bank #
New History LaSalle 1, 1996
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A #
295015 295015 Importance Rating 4.0 4.1 Proposed Question: RO 006, SRO 009 The plant is operating at 100% power, when a scram occurs, with the following:
RPS remains energized All rods fail to insert Scram fuses are now pulled Scram Pilot Solenoid Valve lights are deenergized Scram air header pressure is 0 psig All rods remain at their same positions Without re-installing the RPS fuses, which one of the following methods may insert the rods?
A.
Repeated manual scrams B.
Manually driving rods C.
Venting the over-piston areas D.
Individual rod scram switches Proposed Answer: C Justification:
C correct - this is the only available method to insert the hydraulically locked rods with re-pressurizing the scram air header. AIBID incorrect - all require that fuses be reinstalled to re-pressurize Proposed references to be provided to applicants during examination:None Technical Reference(s):
01-OPS-006-344-1-11, Ni-EOP-3.1 K/A:
295015 AK2.04, Knowledge of the interrelations between INCOMPLETE Incomplete SCRAM and the following: RPS Scram 10 CFR Part 55 Content:
55.41(10)
X 55.43 Question Source:
Bank #
Modified Bank #
New X
History
Examination Outline Cross-reference:
Level Ru
ýrKu Tier #
1 1
Group #
1 1
K/A#
295015 295015 Importance Rating 3.4 3.7 Propoised Question: RO 007, SRO 010
/
thepln operating at 80% power when a manual scram is inserted:
15 control rods remain at position 24 RPV level dropped to 35 inches and is recovering EOP-3 has been entered Which one of the following identifies why rod blocks need to be bypassed to execute N1 -EOP 3.1, Alternate Control Rod Insertion, Section 3, Driving Control Rods Using The Reactor Manual Control System?
To bypass the....
IRM upscale rod block APRM upscale rod block RWM out of sequence rod block SRM downscale rod block Proposed Answer: C Justification:
C correct - section 3 directs RWM bypassing if enforcing a rod block.
A incorrect - IRM is a W/D block only. B incorrect - is a W/D block only. D incorrect - is a W/D block only.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
K/A:
- 295015, INCOMPLETE SCRAM 10 CFR Part 55 Content:
I Question Source:
AK3.01, Knowledge of the reasons for the following responses as they apply to INCOMPLETE SCRAM: Bypassing rod insertion blocks 55.41(10)
X 55.43 55.45 1Bank #
N1I-EOP-3 NiI-EOP-3. 1 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None A.
B.
C.
D.
N 1 EOP 3 N1-EOP-3*I
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A #
295006 295006 Importance Rating 4.3 4.4 Proposed Question: RO 008, SRO 017 The plant has just scrammed from rated power.
Which one of the following identifies the control rod position indications on the F Panel before the scram is reset?
A.
XX B.
Blank C.
-99 D.
Red bars Proposed Answer: B Justification:
B is correct - Both digit positions are blank. AIC are incorrect related to Process Computer RPIS, but not F Panel. D is incorrect Two red bars are present at position 48 (full-out); two green bars are present at the full-in position.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-201-1-02 K/A:
295006 SCRAM AA2.02, Ability to determine and/or interpret the following as they apply to SCRAM: Control rod position 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
1 Group #
1 K/A #
295025 Importance Rating 4.3 Proposed Question: RO 010 The plant is operating at 100% power, with the following:
Generator load reject occurs Reactor automatically scrams All Turbine Bypass Valves fail 100% closed Which one of the following describes the impact on the Reactor Coolant System Safety Limit and its associated RPS scram setpoint?
SAFETY LIMIT A.
Exceeded B.
Exceeded C.
Not exceeded D.
Not exceeded Proposed Answer: D SCRAM SETPOINT Not exceeded Exceeded Not exceeded Exceeded Justification:
D is correct - Candidate must know that the RCS S.L. is 1375 psig and that the associated LSSS/SCRAM setpoint is </= 1080 psig. The generator load reject analysis is not concerned with the RCS S.L.; rather its concern is with the MCPR S.L. for Fuel Clad Integrity. MCPR is preserved by way of the high pressure and/or high flux scram that results from the TSV closure with failed TBVs. 1375 psig is not exceeded, but the LSSS (scram setpoint) for RPV pressure is exceeded. A/BIC are incorrect - different combinations that do not conform to the correct answer.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
TS 2.2.1, TS 2.1.2 (inc. bases)
K/A:
295025 HIGH EA2.01, Ability to determine and/or interpret the following as they apply to REACTOR HIGH REACTOR PRESSURE: Reactor pressure PRESSURE 10 CFR Part 55 Content:
55.41 (5)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New X
History
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A #
295037 295037 Importance Rating 3.4 4.1 Proposed Question: RO 011, SRO 022 The plant has experienced a seismic event, with the following:
Reactor Power is 40%
MSIVs are closed ERVs are controlling pressure RPV level is being controlled with Feedwater Liquid Poison Tank drain valve has broken off, causing the tank to drain Which one of the following alternate boron injection methods m sed per N1-EOP-3.2?
A.
Liquid Poison Hydro Pump B.
Liquid Poison Pump from test tank C.
RWCU system from cleanup filters D.
Condensate system from demineralizers Proposed Answer: C Justification:
C correct - per EOP-3.2. A incorrect - Connects to LP tank, which is drained. B incorrect - Not allowed by EOP-3.2, and no boron in that tank anyway. D incorrect - No connection to LP system.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-EOP-3.2 K/A:
295037 Scram EK2.13. Knowledge of the interrelations between SCRAM CONDITION Condition PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR Present and UNKNOWN and the following: Alternate boron injection methods: Plant Reactor Power Specific Above APRM Downscale or Unknown 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
X Modified Bank #
New History Dresden 1996 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A #
295037 295037 Importance Rating 4.6*
4.6*
Proposed Question: RO 012, SRO 023 A failure to scram has occurred, with the following:
Mode Switch is in SHUTDOWN All RPS Rod Group Solenoid lights are OFF Scram Valve indicator lights (BLUE) are OFF Which one of the following is required to insert the control rods per N1-EOP-3.1?
A.
Depress both RPS pushbuttons B.
Repeated manual scrams C.
Remove rod group fuses D.
Vent the Scram Air Header Proposed Answer: D Justification:
D is correct-SCRAM valves are not open, the SCRAM header is still pressurized. A/B/C incorrect-RPS has already been tried and failed.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-EOP-3 K/A:
295037 SCRAM EA1.01. Ability to operate and/or monitor the following as they apply CONDITION to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE PRESENT AND APRM DOWNSCALE OR UNKNOWN: Reactor Protection System REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
X12817 New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
1 1
K/A #
500000 500000 Importance Rating 3.3 3.9 Proposed Question: RO 013, SRO 026 Which one of the following identifies the post-LOCA H 2 and 02 concentrations at which a loss of containment integrity may result from a deflagration event?
DRYWELL H2 A.
6%
B.
5%
C.
0%
D.
7%
DRYWELL 02 5%
6%
6%
4%
Proposed Answer: A Justification:
A correct - >= 6% H2 and >= 5% 02 in same, or either, space. BICID incorrect - combination of concentrations < deflagration Proposed references to be provided to applicants during examination: N1-EOP-4.2, HYDROGEN CONTROL Technical Reference(s):
01-OPS-006-344-1-19 N1-EOP-4.2, HYDROGEN CONTROL K/A:
500000, High EK1.01, Knowledge of the operational implications of the following Containment concepts as they apply to HIGH CONTAINMENT HYDROGEN Hydrogen CONCENTRATIONS: Containment integrity Concentrations 10 CFR Part 55 Content:
55.41(10)
X 55.43 55.45 Question Source:
Bank #
X 12849 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis lo LOD:
3 Comments:
None TORUS H2 0%
5%
5%
0%
TORUS 02 4%
5%
6%
4%
Examination Outline Cross-reference:
1 1
Group #
1 2
K/A #
295001 295001 Importance Rating 3.3 3.3 Proposed Question: RO 014, SRO 028 The plant is operating at 55% power with the following:
4 Reactor Recirculation loops are operating Reactor Recirculation Pump 11 is ready for restart The following events then occur:
An individual controller malfunction results in a speed decrease for Recirc Pump 14 Operation is now in the Restricted Zone APRM power has stabilized Reactor Period is infinite and steady No LPRMs are in alarm Which one of the following describes the required operator action?
A.
Start Recirc Pump 11.
B.
Manually scram the reactor and enter SOP-1.
C.
Use the RECIRC MASTER controller to raise recirc flow to exit the Restricted Zone.
D.
Take manual control of Recirc Pump 14 to raise recirc flow to exit the Restricted Zone.
Proposed Answer: C Justification:
C is correct-This is the precise action specified by SOP-2. A is incorrect Specifically prohibited by SOP-2. B is incorrect - There are no indications of thermal hydraulic instability requiring this action.
D is incorrect - This action will probably work; however, SOP-2 specifically requires use of the RECIRC MASTER controller and provides the alternative of CRAM rod insertion.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-SOP-2 K/A:
295001 Partial or AA1.05, Ability to operate and/or monitor the following as they apply to Complete Loss of PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW Forced Core CIRCULATION: Recirculation Flow Control system Flow Circulation 10 CFR Part 55 Content:
55.41(10)
X 55.43 (5)
X 55.45 Question Source:
-Bank #
Modified Bank #
X457 New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
1 Group #
1 K/A #
295001 Importance Rating 3.1 Proposed Question: RO 015 The plant is operating at 100% power, with the following:
A malfunction results in a lowering speed on all five running Recirculation Pumps Operator action has been taken to stop the lowering flow Operation remains outside the Restricted Zone on the Power to Flow Map Which one of the following describes the effect of this flow reduction on the APRM margins to rod blocks and scrams?
A.
The same margins exist now as before and the margins will remain constant.
B.
Lesser margins exist now than before and these margins will remain constant.
C.
Lesser margins exist now than before and these margins will become even less.
D.
Greater margins exist now than before but these margins will return to the original margins.
Proposed Answer: C Justification:
C is correct - FCTR curves the setpoints downward to avert the scram zone and the lowering FW temperature will continue to raise power.
A/B/D are incorrect - wrong direction Proposed references to be provided to applicants during examination: None Technical Reference(s):
DDC1E00135, Five Loop Power Flow Map K/A:
295001 Partial or AA2.02, Ability to determine and/or interpret the following as they Complete Loss of apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW Forced Core CIRCULATION: neutron monitoring Flow Circulation 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
2 2
K/A #
295002 295002 Importance Rating 3.4 3.4 Proposed Question: RO 016, SRO 029 Which one of the following describes the reason for manually tripping the main turbine if exhaust pressure is above 5 inches HgA with generator load less than 190 MWe?
Protects the...
A.
main turbine from blading damage.
B.
main turbine exhaust hoods from excessive temperatures.
C.
main condenser from over-pressurization.
D.
main condenser shells from excessive stress due to unbalanced steam loads.
Proposed Answer: A Justification:
A is correct-per OP-31, D.1.0. BIC/D are incorrect - not the basis for this operator action.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-31, D.1.0 K/A:
295002 Loss of AK3.02, Knowledge of the reasons for the following responses as Main Condenser they apply to LOSS OF MAIN CONDENSER VACUUM: Turbine Trip Vacuum 10 CFR Part 55 Content:
55.41(10)
X 55.43 (5)
X 55.45 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:
1 1
Group #
2 2
K/A #
295004 295004 Importance Rating 2.8 2.9 Proposed Question: RO 017, SRO 030 The plant is operating, with the following:
A loss of Battery Charger capability to Battery Board 11 occurs Battery Board 11 amperage is 580 amps If Battery 11 amperage remains constant, which one of the following states the expected time in hours that the battery will continue to supply loads?
A.
2 B.
3 C.
4 D.
5 Proposed Answer: C Justification:
C is correct - Battery 11 rating is 2320 amp-hrs, 2320/580 amps=4 hours AIB/D are incorrect - values close to correct and conceivably arrived at if actual battery rating digits are re-arranged into incorrect ratings (eg 3230)
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-47A, B.2, pg 3 K/A:
295004 PARTIAL AK1.04: Knowledge of the operational implications of the following OR COMPLETE concepts as they apply to PARTIAL OR COMPLETE LOSS OF LOSS OF D.C.POWER: Effect of battery discharge rate on capacity D.C.POWER 10 CFR Part 55 Content:
55.41(7)
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:
2 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
2 2
K/A #
295004 295004 Importance Rating 3.1 3.1 Proposed Question: RO 018, SRO 031 N1-SOP-1 8, Station Blackout, directs the stripping of certain non-vital 125 VDC loads.
Which one of the following describes the reason for this requirement?
Without AC power...
A.
the battery boards will not automatically transfer to the standby static battery chargers; stripping loads is necessary for a manual dead-bus transfer.
B.
loads will not automatically transfer between Battery Boards 11 and 12; stripping loads is necessary for a manual dead-bus transfer.
C.
the static battery chargers will not carry the battery boards; stripping loads preserves DC battery power for vital functions.
D.
MG Set 167 is unavailable; stripping loads preserves battery board power for the process computer.
Proposed Answer: C Justification:
C correct - SBC's are lost; preserving DC power for Rx Instrumentation, EC controls, and starting EDGs is critical in a blackout. A/B incorrect - there are no auto-transfer features for either BB1 1/12 loads, or in-service/standby SBCs. D incorrect - although MG set 167 is unavailable, DC power is preserved for vital functions (described above), not for the PPC (an AC-powered system).
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-47A, Ni-SOP-18 K/A:
295004 Partial or AK2.01 - Knowledge of the interrelations between Partial or Total Total Loss of DC Loss of DC Pwr and the following: Battery charger Pwr 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2
Examination Outline Cross-reference:
1 1
Group #
2 2
K/A #
295028 295028 Importance Rating 3.5 3.7 Proposed Question: RO 019, SRO 032
)
With Drywell Temperature and React rdressure on the "BAD" side of Figur the EOP's, "RPV SATURATION TEMPERATURE hich one of the following describes the elationship between INDICATED RPV water level and ACTUAL RPV water level?
All instruments...
A.
will read higher than ACTUAL B.
will read less than ACTUAL C.
except Fuel Zone will read higher than ACTUAL D.
except Fuel Zone will read less than ACTUAL Proposed Answer: C Justification:
C is correct-With the instrument reference legs in saturation, flashing could occur resulting in less dense reference legs so the variable legs would appear heavier (more water) making the instrument read higher than actual for all instruments except Fuel Zone as the Fuel Zone is density compensated and can be used when in the "Bad" zone as long as it is NOT flashing BID are incorrect-INDICATED level will be higher than ACTUAL A is incorrect - right response but does not effect Fuel Zone directly Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-EOP-4 K/A:
295028 HIGH EK1.01 Knowledge of the operational implications of the following DRYWELL concepts as they apply to HIGH DRYWELL TEMPERATURE:
TEMPERATURE Reactnr Water I~"e! measu'*-ent 10 CFR Part 55 Content:
55.41(10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 1
K/A#
295013 295013 Importance Rating 2.9 3.2 Proposed Question: RO 020, SRO 006 A loss of coolant accident has occurred, with the following:
Torus Water temperature is 99F Torus Water level is 11 feet Torus pressure is 15 psig Containment Sprays cannot be established Which one of the following components may faill as direct result of these conditions?
A.
Downcomers B.
ERV tailpieces C.
Drywell closure bolts D.
Drywell vent valves Proposed Answer: A Justification:
A is correct-Torus pressure is above the Suppression Chamber Spray Initiation Limit which requires containment sprays to prevent cyclic condensation and fatigue failure of the downcomers. BICID are incorrect-not the component referenced in EOP bases as likely to fail due to chugging.
Proposed references to be provided to applicants during examination: EOP Flowcharts Technical Reference(s):
Ni-ODP-PRO-0305, pg 467 K/A:
295013 HIGH AK1.04. Knowledge of the operational implications of the following SUPPRESSION concepts as they apply to HIGH SUPPRESSION POOL POOL TEMPERATURE: Complete condensation TEMPERATURE 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 (5)
X Question Source:
Bank#
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
2 1
K/A#
295013 295013 Importance Rating 3.6 3.7 Proposed Question: RO 021, SRO 007 The EOP's have been entered due to high Torus Temperature, with the following:
At 11:01, Torus Temperature is 85F At 11:05, Torus Temperature is 86F All four Containment Spray loops are available A.
11:16 B.
11:20 C.
11:31 D.
11:35 Proposed Answer:
ir1)
A Justification:
A is correct-per N1-EOP-1, Att. 16, step 2.1, Torus cooling shall be in service within 15 minutes of Torus temperature equal to or greater than 85F B/C/D incorrect-uses greater than 85F and/or subsitutes 30 min for 15 min Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-EOP-1, Att 16, step 2.1 K/A:
295013 HIGH AK2.01. Knowledge of the interrelations between HIGH SUPPRESSION SUPPRESSION POOL TEMPERATURE and the following:
POOL Suppression pool cooling TEMPERATURE 10 CFR Part 55 Content:
55.41(5,10)
X 55.43 (l)
X 55.45 Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None 0
0 0
Examination Outline Cross-reference:
1 1
Group #
2 1
K/A#
295016 295016 Importance Rating 3.0*
3.1 Proposed Question: RO 022, SRO 012 The plant was initially at 100% power when the following occurred:
The Control Room has been evacuated Ahe reactor has just been scrammed from outside the Control Room Which one of the following describes how the reactor is to be confirmed shutdowf A.
Locally verify that both MG 131 and MG 141 are coasting down.
B.
Observe that all control rods are fully inserted on the process computer at the TSC.
C.
Observe the CONTROL RODS IN lights are energized on the Remote Shutdown Panels.
D.
Locally verify the scram air header is depressurized and confirm all scram valves are open.
Proposed Answer: C Justification:
C is correct - per SOP-9.1. A is incorrect - Not per SOP-9.1, and confirms status of RPS bus power but not actual rod position. B is incorrect - Not per SOP-9.1. D is incorrect - Not per SOP-9.1, and does not account for a 'hydraulic' ATWS.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
O1-OPS-001-212-1-01, Ni-SOP-9.1 K/A:
295016 AA1.03, Ability to operate and/or monitor the following as they apply Control Room to CONTROL ROOM ABANDONMENT: RPIS Abandonment 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
X12755 Modified Bank#
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 #
295018 295018 Importance Rating 3.3 3.4 Proposed Question: RO 023, SRO 034 A loss of Service Water has occurred, with the following:
N1-SOP-7 has been entered H11-4-2, R BUILDING SW PRESS/SERV W PUMP HDR PRESS LOW is in alarm Neither Emergency Service Water Pump can be started Which one of the following sources should be used to supply cooling to the RBCLC heat exchangers?
A.
Domestic Water B.
Fire Water C.
Circulating Water D.
TBCLC Water Proposed Answer: B Justification:
B is correct-per N1-SOP-7 Fire Water is to be used AICID are incorrect-not referenced by SOP-7.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1 -SOP-7, A K/A:
295018 PARTIAL AA1.01. Ability to operate and/or monitor the following as they apply OR COMPLETE to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING LOSS OF WATER: Backup Systems COMPONENT COOLING WATER 10 CFR Part 55 Content:
55.41(5,7)
X 55.43 55.45 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:
1 1
Group #
2 2
K/A #
295022 295022 Importance Rating 3.4 3.6 Proposed Question: RO 024, SRO 035 A plant heatup is in progress, with the following:
RPV pressure is 850 psig The only available Control Rod Drive (CRD) pump has just tripped Three withdrawn control rods have accumulator pressures reading 940 psig Which one of the following describes the required operator action?
A.
Place the Reactor Mode Switch in SHUTDOWN.
B.
Attempt to insert at least one withdrawn control rod one notch.
C.
If a CRD pump cannot be started within 20 minutes, scram the reactor.
D.
Commence a normal orderly shutdown in accordance with N1-OP-43C within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
Proposed Answer: A Justification:
A is correct - action specified in ARP F3-1-2. B is incorrect - only done if attempting to confirm that at least CRD pump is running. C is incorrect - An option only when RPV pressure > 900 psig. D is incorrect - not per any related procedure.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-ARP-F3-1-2 K/A:
295022 Loss of AK2.07, Knowledge of the interrelations between LOSS OF CRD CRD Pumps PUMPS and the following: Reactor pressure (SCRAM assist): Plant Specific 10 CFR Part 55 Content:
55.41(7,10)
X
[E5.43 55.45 Question Source:
Bank #
X Modified Bank#
New History Lasalle 2000 NRC Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
1 1
Group #
2 1
K/A #
295026 295026 Importance Rating 3.2 3.6 Proposed Question: RO 025, SRO 018 A loss of coolant accident and loss of Powerboard 102 have occurred, with the following:
Containment Sprays have been utilized to lower Torus pressure The RPV has been depressurized using EC's and ERV's Torus Water temperature is 200F Torus Level is 9.5 feet Torus pressure is 6 psig Drywell pressure 7 psig Which one of the following states the maximum Core Spray flow (Ibm/hr x 1 0E4) that may be used for RPV injection?
A.
175 B.
240 C.
350 D.
480 Proposed Answer: C Justification:
B is correct - 9.5 feet - 4.5 feet = 5 feet x.433=2 psig + 6 psig=8psig, so 5 psig curve is used. With two sub-systems available the max flow is 240 A/C/D are incorrect different combinations of one subsystem values and/or using the 10 psig curve which would be chosen if candidate forgets to subtract 4.5 feet from 9.5 feet.
Proposed references to be provided to applicants during examination: N1-EOP-4 Technical Reference(s):
N1-ODP-PRO-0305, pg 48 and N1-EOP-4, Detail N1 K/A:
295026 EK2.03: Knowledge of the interrelations between SUPPRESSION SUPPRESSION POOL HIGH WATER TEMPERATURE and the following:
POOL HIGH Suppression chamber pressure: Mark-I&lI WATER TEMPERATURE 10 CFR Part 55 Content:
55.41(5)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: Needs SRO Tech Verify number of subsystems/which curve to use
Examination Outline Cross-reference:
1 1
Group #
2 1
K/A #
295003 295003 Importance Rating 3.7 3.8 Proposed Question: RO 026, SRO 019 The plant is in a Station Blackout. The 115kV line from the South Oswego Substation has just been restored Which one of the following describes the response of breaker R10 and Powerboards 11 and 12, given the above conditions?
Breaker R10 Will automatically close Will automatically close Must be manually closed Must be manually closed PB 11 and 12 Will re-energize automatically Must be re-energized manually Will re-energize automatically Must be re-energized manually Proposed Answer: A Justification:
A correct - auto re-closure feature and bus re-energizes B incorrect bus re-energizes C incorrect - auto re-closure feature D incorrect auto re-closure feature and bus re-energizes Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-262-1-01 N1-OP-30 H.3.1 K/A:
295003 Partial or AA1.01 - ability to operate and/or monitor thew following as they Complete Loss of apply to PARTIAL OR COMPLETE LOSS OF AC POWER: A.C.
AC Power electrical distribution system 10 CFR Part 55 Content:
55.41(7)
X 55.43 55-45 Question Source:
Bank #
X Modified Bank#
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None A.
B.
C.
D.
Examination Outline Cross-reference:
1 1
Group #
2 2
K/A #
295028 295028 Importance Rating 3.6
-3.8 Proposed Question: RO 027, SRO 037 The plant is operating at 100%, with the following:
Drywell Cooler 16 is tagged out The normal feeder breaker to Powerboard 17A malfunctions and trips open Powerboard 17A has been checked by Electrical Maintenance and is fault free Drywell temperature is rising Which one of the following states the maximum number of Drywell Coolers that can be placed in service?
A.
2 B.
3 C.
4 D.
5 Proposed Answer: D Justification:
D is correct-Powerboard 17A can be cross tied and the 3 drywell coolers lost restarted for a total of 5 A is incorrect -would be the number if 17A could not be reeenergized B incorrect - would be the number if 17A could not be energized and if drywell cooler 16 was believed powered from 17A C incorrect - powerboard 17A can be reenergized and drywell coolers restarted Proposed references to be provided to applicants during examination: None Technical Reference(s):
K/A:
295028 HIGH EK3.04: Knowledge of the reasons for the following responses as 7
DRYWELL they apply to HIGH DRYWELL TEMPERATURE: Increased drywell TEMPERATURE cooling 10 CFR Part 55 Content:
55.41(5,7,10)
X 55.43 (5) 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments:
None Ni -AR P-A5-3-6
Examination Outline Cross-reference:
.Tier#
1 1
Group #
2 1
K/A#
295016 295016 Importance Rating 4.2 4.3*
Proposed Question: RO 028, SRO 011 The plant is operating at 100%, with the following:
A fire occurs filling the control room with heavy smoke Control Room Abandonment is directed All control room actions were completed While transiting to RSP 12 to establish control of Reactor Water Level, which one of the following describes the initial Reactor Water Level response?
Reactor Water Level will initially...
A.
Rise to the Main Steam Lines and higher B.
Rise to >95 inches and then stabilize C.
Lower to <53 inches then recover on HPCI D.
Lower to triple low and reflood on ADS/Core Spray Proposed Answer: C Justification:
C correct-before exiting the control room a scram and trip of the 13 FW pump will occur, this will lower water level to the HPCI initiation point A/B incorrect - on the scram from 100% power reactor water level will drop D incorrect - Feedwater is available from FW pumps 11 and 12, but if assumed not available would occur Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-SOP-9.1 K/A:
295016 Control AA2.02 - Ability to determine and interpret the following as they apply Room to Control Room Abandonment: Reactor water level Abandonment 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
2 2
K/A #
295033 295033 Importance Rating 3.9 4.2*
Proposed Question: RO 029, SRO 038 The plant is operating at 100%, with the following:
H1-4-8, AREA RADIATION MONITORS, alarms REFUEL BRIDGE (HIGH RANGE) is in alarm RX BLDG-EAST WALL, EL. 340 is in alarm Affected areas have radiation levels between 8500 and 10,000 mr/hr NO area temperature or sump level alarms exist in the Reactor Building Which one of the following states the action required and the areas that should be evacuated?
ACTION A.
B.
Shutdown the Reactor (OP-43A &B)
C.
D.
Shutdown the Reactor (OP-43A &B)
Proposed Answer: B Justification:
EVACUATION AREA Refuel Floor (RB 340)
Refuel Floor (RB 340)
Reactor Building (All)
Reactor Building (All)
B is correct - No indication of primary system discharging and the only affected area is the refuel floor A/C are incorrect-no primary system discharging D is incorrect-only the refuel floor is affected Proposed references to be provided to applicants during examination: EOP Flowcharts Technical Reference(s):
N1-EOP-5, H1-4-8 K/A:
295033 High EK1.02 - Knowledge of the operational applications of the following Secondary concepts as they apply to the High Secondary Containment Area Containment Radiation Levels: Personnel protection Area Radiation Levels 10 CFR Part 55 Content:
55.41(12)
X 55.43 (4)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
1 Group #
2 K/A #
295029 Importance Rating 3.9 Proposed Question: RO 030 EOP-4 has been entered due to high Torus water level, with the following:
Torus water level is 11.3 feet 80-40 CONT SPRAY BYPASS BV 111 is stuck OPEN Which one of the following loops of Containment Spray should be used to lower Torus Level?
A.
111 B.
112 C.
121 D.
122 Proposed Answer: A Justification:
A correct - per EOP-1 attachment 15 only loop 111 can be used if BV 80-40 cannot be closed BICID incorrect-all these loops require BV 80-40 be closed Proposed references to be provided to applicants during examination: N1-EOP-1, Attachment 15 Technical Reference(s):
N1-EOP-1, Attachment 15, step 2.2 K/A:
295029 High Generic 2.1.30 Ability to locate and operate components/including Suppression Pool local controls Water Level 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 1
K/A #
295038 295038 Importance Rating 1 2.5 3.4 Proposed Question: RO 031, SRO 025 A loss of coolant accident has occurred, with the following:
Primary containment water level is 30 feet Torus pressure is 38 psig and rising H2 and 02 concentrations are below their thresholds for PC venting Estimates indicate that any PC venting would exceed General Emergency level dose rates Which one of the following identifiep the required action and the proper vent path?
A.
Vent the Drywelleowt.u the vent and p furge fn B.
Do NOT ven until directed by EOP-4.2;usetie vent and purge fan.
C.
Vent the Torus now; use the Post-LOCAVt ath D.
Do NOT ventuntil directed by EOP-4., use The Post-LOCA Vent path.
Proposed Answer: A Justification:
A correct - Per EOP-4, step PCP-8 and Figure D. Ok to exceed release rates; PC level too high to vent from torus. PC pressure too high to use Post-LOCA path thru RBEVS. BID incorrect -With the PCPL about to be reached, PC gas concentration is irrelevant; EOP-4 directs us to vent now. C incorrect - PC water level too high (>27') to use torus.
Proposed references to be provided to applicants during examination: EOP flowcharts Technical Reference(s):
Ni-EOP-4, Ni-EOP-4.1 K/A:
295038 High Off-2.3.9 - Knowledge of the process for performing a containment purge site Release Rate 10 CFR Part 55 Content:
55.41(10,12 X
55.43 (4,5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
1 1
Group #
2 2
K/A #
600000 600000 Importance Rating 3.0 3.1 Proposed Question: RO 032, SRO 043 The plant is at power, with the following:
A fire develops in Remote Shutdown Panel 11 The Fire Brigade leader reports the fire appears out but there is heavy smoke Which one of the following Smoke Removal Zones should be purged?
A.
Zone 1 B.
Zone 2 C.
Zone 3 D.
Zone 4 Proposed Answer: B Proposed references to be provided to applicants during examination: N1-OP-21 F, Technical Reference(s):
N1-OP-21F K/A:
600000 Plant Fire AA1.05 - Ability to operate and/or monitor the following as they apjf'y On Site to Plant Fire On Site: Plant and control room ventilation systems 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
1 Group #
3 K/A #
295021 Importance Rating 3.3 Proposed Question: RO 033 The plant is in Mode 4, with the following$
Shutdown Cooling (SDC) is in service No Recirc pumps are available Which one of the following describes how high RPV level should be raised and the reason for raising level?
RAISE LEVEL TO ABOVE THE...
REASON A.
Recirc pump return nozzles Promote Natural Circulation B.
Main Steam Line nozzles Promote Natural Circulation C.
Recirc pump return nozzles Prevent SDC flow short cycling D.
Main Steam Line nozzles Prevent SDC flow short cycling Proposed Answer: B Justification:
B is correct - Prescribed by N1-OP-4 for the condition of no forced circulation. A/C incorrect - wrong RPV nozzle used as reference height in OP D incorrect - right nozzle but reason is for maintaining SDC min flow valves closed with no recirc pumps Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-04, D.8 K/A:
295021 LOSS AK3.01: Knowledge of the reasons for the following responses as OF SHUTDOWN they apply to LOSS OF SHUTDOWN COOLING: Raising reactor COOLING water level 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Examination Outline Cross-reference:
1 1
Group#
3 1
K/A #
295023 295023 Importance Rating 3.3 3.4 Proposed Question: R0034, SRO 016 Fuel movements are in progress, with the following:
SRM Channel 14 fails downscale and is declared inoperable Only SRM Channels 11 and 13 are operable The next fuel movement is the removal of a bundle from core quadrant 12 Which one of the following describes the impact of these conditions on the next fuel movement, and the reason for that impact?
The next fuel movement.....
A.
must NOT proceed because there is no operable SRM in quadrant 12.
B.
must NOT proceed because the minimum number of operable SRMs requirement is not satisfied.
C.
may proceed because the minimum number of operable SRMs requirement is satisfied.
D.
may proceed because there is still an operable SRM in the quadrant adjacent to quadrant
- 12.
Proposed Answer: A Justification:
A is correct-There is no operable SRM in this quadrant. B is incorrect - The minimum required SRMs are operable, but SRM 12 is not. C is incorrect - Although the minimum SRMs operable requirement is met, there is no operable SRM in this quadrant. D is incorrect - SRM 12 must be operable to proceed.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-34 Precaution 14, O1-OPS-001-234-1-01 K/A:
295023 Refueling AA1.06, Ability to operate and/or monitor the following as they apply Accidents to REFUELING ACCIDENTS: Neutron monitoring 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 (2,7)
X 55.45 Question Source:
Bank #
Modified Bank#
X12776 New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2
Examination Outline Cross-reference:
1 1
Group #
3 2
K/A #
295032 295032 Importance Rating 3.5 3.8 Proposed Question: R0035, SRO 041 An unisolable steam leak has developed in the Reactor Building, with the following:
"* Reactor Building Ventilation Exhaust Radiation is 7 mr/hr
"* K3-3-4, CLEAN-U
,q---
AREA T HI, alarms
"* RW CU Pump Area sinae r 00 isinar SRWCU Heat exchanger oor is in alar Local temperatures are consisent with alarms Which one of the following describes the required action and the reason for that action?
ACTION REASON A.
Commence a normal plant shutdown Minimize effects of Level instrument errors B.
Perform an RPV Blowdown Allow RPV Flooding with Core Spray C.
Commence a normal plant shutdown Minimize the threat to Secondary Containment D.
Perform an RPV Blowdown Reduce driving head of steam leak Proposed Answer: D Justification:
D correct - With two areas above max safe'Blowdown is required to reduce the leakrate A/C incorrect - action if only one area above max safe B incorrect - right action but wrong reason Proposed references to be provided to applicants during examination: N1-EOP-5 Technical Reference(s):
N1-EOP-5, N1-ODP-PRO-0305 K/A:
295034 HIGH EK3.01: Knowledge of the reasons for the following responses as SECONDARY they apply to HIGH SECONDARY CONTAINMENT AREA CONTAINMENT TEMPERATURE: Emergency/normal depressurization AREA TEMPERATURE 10 CFR Part 55 Content:
55.41(10)
X 55.43 (5)
X 55-45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
1 Group #
2 K/A #
295036 Importance Rating 3.3 Proposed Question: RO 036 The plant is operating at 100% power, with the following:
H2-2-1, R BLDG FL DR SUMPS 11-16 AREA WTR LVL LEVEL HIGH, alarms Computer printout confirms the alarm Which one of the following describes the required operator action?
A.
Verify affected sump pump is running and direct Radwaste to determine cause of high level.
B.
If affected sump rate of rise exceeds 4.2 gpm, manually scram and enter N 1-SOP-1.
C.
Direct Radwaste to pump down affected sump with temporary pump per Ni-OP-10.
D.
Enter N1-EOP-5, Secondary Containment Control, and determine cause of high level.
Proposed Answer: D Justification:
D correct - per ARP-H2-2-1 actions. A/BIC incorrect - various actions from similar ARPs involving RB Eqpt Drains and Drywell sumps.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
ARP-H2-2-1 K/A:
295036 2.4.50 - Ability to verify system alarm setpoints and operate controls Secondary identified in the alarm response manual Containment High Sump/Area Water Level 10 CFR Part 55 Content:
55.41(10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 2
K/A#
201001 201001 Importance Rating 3.0 2.9 Proposed Question:
RO 037, SRO 067 The plant is operating at 100% power, with the following:
F3-3-2, CRD CONTROL AIR PRESSURE HI-LO, alarms CRD air header pressure is reading 85 psig on the F Panel Which one of th following describes the effect on the Control Rod Drive System?
A.
Rods may begin to drift in~1 jI B.
CRD high temperatures m*y result.
C.
The scram air header relief valve will soon lift causing all rods to scram.
D.
Opening of the Scram Inlet and Outlet valves will be delayed on a scram.
Proposed Answer: D Justification:
D correct - high pressure may result in excessive scram times. A is incorrect - No connection exists between high air pressure and the conditions that may result in rod drift. B is incorrect-The scram pilot regulator does not supply the CRD FCV, which supplies cooling flow.
C is incorrect -There is no such relief valve.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-5, P&L 2.0, Ni-ARP-F3-3-2 K/A:
201001 K6.03. Knowledge of the effect that a loss or malfunction of the CONTROL ROD following will have on the CONTROL ROD DRIVE HYDRAULIC DRIVE System: Plant Air Systems HYDRAULIC 10 CFR Part 55 Content:
55.41(7)
X 55.43 55-45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
202002 Importance Rating 2.6 Proposed Question:
RO 038 The plant is operating at 100% power, with the following:
5 Recirc Loops are in service The OPEN limit switch for Recirc Pump 14 discharge valve fails (contact no longer closed)
Which one of the following describes the Recirc Pump 14 response?
Recirc Pump 14...
A.
will trip.
B.
speed will lower to 20%.
C.
scoop tube will lock up.
D.
will remain running at its current speed.
Proposed Answer: D Justification:
D correct - The speed interlock is off of full-close valve position.
A incorrect - Suction valve closure is a pump trip, not discharge valve. B incorrect-Speed is limited only when the valve is fully closed. C incorrect -
Discharge valve position has no relationship to scoop tube lock up.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
O1-OPS-001-202-1-01, Nl-OP-01 K/A:
202002 K5.02. Knowledge of the operational implications of the following RECIRCULA-concepts as they apply to RECIRCULATION FLOW CONTROL TION FLOW SYSTEM: Feedback signals CONTROL SYSTEM 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank#
Modified Bank #
New 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
K/A #
206000 206000 Importance Rating 3.5 3.8*
Proposed Question:
RO 039, SRO 044 A reactor scram from rated power has occurred, with the following:
Feedwater Pump 12 is injecting to the RPV A fault causes the loss of Battery Board 12.
Which one of the following describes the effect of this power loss on RPV injection, and the operator action necessary to compensate?
Feedwater Pump 12 will...
A.
trip immediately and must be restarted.
B.
trip immediately and will auto-start after manually transferring control power to BB 11.
C.
not trip and must be manually tripped if RPV level rises to the high level trip setpoint.
D.
not trip, but FCV 12 will lock up, Feedwater Pump 11 must be started to control RPV level.
Proposed Answer: C Justification:
C is correct - Pump tripping power is lost. RPS control power remains available from the AC inverter source. A is incorrect - Pump tripping power is lost. B is incorrect - Pump tripping power is lost.
D is incorrect-FCV 12 does not lock up on this power loss.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-259-1-01 K/A:
206000 High A2.05, Ability to (a) predict the impacts of the following on the HIGH Pressure Coolant PRESSURE COOLANT INJECTION SYSTEM; and (b) based on Injection System those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: D.C.
failures: BWR-2,3,4 10 CFR Part 55 Content:
55.41(7)
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:
2 Comments:
None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
206000 206000 Importance Rating 3.9 3.8 Proposed Question: RO 040, SRO 045 The plant is operating at 100% power with Feedwater Pumps 12 and 13 in service, with the following:
° HPCI CH 12 light on the 'E' Panel energizes Plant remains at 100% power All systems operate as designed Which one of the following identifies the status of HPCI and identifies the additional alarms and indications that should be present?
HPCI has...
A.
initiated and the HPCI CH 11 light on the 'E' Panel should also be energized.
B.
initiated and annunciator F4-4-1, HPCI MODE AUTO INITIATE, should be energized.
C.
NOT initiated and both Bypass Flow Control Valves 11 and 12 should indicate closed.
D.
NOT initiated and Feedwater Pump 12 flow should be reading greater than 1.9 x 106 Ibm/hr.
Proposed Answer: D Justification:
D is correct-This indicates a shift of the FCV to HPCI Mode due to high pump flow. However, HPCI has not initiated. A/B are incorrect
- The plant is at 100% power and HPCI initiation signals are scram signals. Since HPCI has not initiated, no reason for HPCI CH 11 light to be energized. No reason for F4-4-1 to be alarming. C is incorrect Since HPCI has not initiated, no reason for either Bypass Flow Control Valve to indicate closed.
Proposed references to be provided to applicants during examination: None
/
Technical Reference(s):
ARP-F4-4-1, 01-OPS-001-259-1-01 K/A:
206000 A3.07, Ability to monitor automatic operations of the HIGH /
High Pressure PRESSURE COOLANT INJECTION SYSTEM including: L1its and Coolant Injection alarms: BWR-2,3,4 System 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
209001 209001 Importance Rating 3.8 3.9 Proposed Question: RO 041,SRO 046 A loss of coolant and impaired injection has occurred, with the following:
RPV level drops and stabilizes at -20 inches RPV pressure drops and stabilizes at 750 psig Drywell pressure rises and stabilizes at 11 psig ONE minute later, with no operator action, which one of the following describes the Core Spray 111 pump flowrate and status of Spray' u p min flow relief valve?
CORE SPRAY 111 PUMP FLOW PU IN FLOW RELIEF A.
500 GPM B.
500 GPM C.
3400 GPM D.
3400 GPM Proposed Answer: B CLOSED OPEN CLOSED OPEN Justification:
B correct - 111 CS pump would be running but ADS would not yet initiated so the pump would be running on min flow AICID are incorrect - various configurations of incorrect BV position (CLOSED) and/or flowrate (3400=full flow)
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-2, section B, page 4 K/A:
209001 LOW A1.03. Ability to predict and/or monitor changes in parameters PRESSURE associated with operating the LOW PRESSURE CORE SPRAY CORE SPRAY SYSTEM controls including: Reactor water level SYSTEM 10 CFR Part 55 Content:
55.41(7)
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:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
209001 209001 Importance Rating 3.5 3.6 Proposed Question:
RO 042, SRO 047 The plant is Cold Shutdown, with the following:
Torus water level is low Core Spray pump 111 is inoperable due to clearance on Core Spray pump 111 motor breaker Core Spray pumps 112 121 and 122 are operable and in standby Which one of the following describes the ability to add water to the Torus using Core Spray?
A.
Either Core Spray System may be used B.
Only Core Spray System 11 may be used C.
Only Core Spray System 12 may be usedl, D.
Water cannot be added using Core Spray Proposed Answer: B Justification:
B is correct - Core Spray 11 keep-fill is available for Torus fill as both 121 and 122 are operable A/C are incorrect - Core Spray 12 is not available for Torus fill due to Core Spray 111 being INOP D is incorrect - Core Spray 11 is available (uses Keep-Fill not main pump)
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni1-OP-02, H.1 K/A:
209001 LOW A4.09. Ability to manually operate and/or monitor in the control room:
PRESSURE Suppression pool level CORE SPRAY SYSTEM 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
212000 Importance Rating 2.7 Proposed Question: RO 043 A failure to scram has occurred, with the following:
Reactor Water level is being controlled -41 inches to -84 inches N1-EOP-3.1, Alternate Rod Insertions is in progress RPS logic jumper 6, RELAY 11 K8 TO RELAY 11 K52B fails to work Which one of the following describes the Reactor Protection System (RPS) response when RPS reset is attempted?
A.
A full scram remains in effect B.
Only a half scram on 11 RPS remains in effect C.
Only a half scram on 12 RPS remains in effect D.
A full scram reset occurs Proposed Answer: B Justification:
B is correct - an RPV level low scram signal would still be detected by RPS 11 AICID are incorrect-RPS 12 will reset Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-EOP-3.1, Print C-19859-C, Sheet 4 K/A:
212000 A1.09: Ability to predict and/or monitor changes in parameters REACTOR associated with operating the REACTOR PROTECTION SYSTEM PROTECTION controls including: Individual relay status: Plant-Specific SYSTEM 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
-Bank #
Modified Bank #
New X
History Question Cognitive Level: I Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments:
None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
215004 215004 Importance Rating 3.2 3.2 Proposed Question: RO 044, SRO 049 A plant heatup is in progress with the following:
All IRMs are reading mid-scale on Range 8 SRM 12 detector is being withdrawn to maintain 10a 5 CP Then, the following occurs:
A short circuit causes the SRM 12 detector to fully retract from the core SRM 12 counts stabilize at 40 CPS Which one of the following describes the impact of this malfunction on the ability to continue the plant heatup?
A.
SRM 12 must first be bypassed to clear the rod block.
B.
SRM 12 must first be repaired and declared operable.
C.
Control rod withdrawals may continue provided SRM 12 remains above its downscale.
D.
Control rod withdrawals may continue provided all IRMs remain above the downscales on Range 8.
Prnnrwlzc AnqwAJr" n Justification:
D is correct - the rod block from SRM not full in below 100 CPS is bypassed with IRMs on range 8 or above. A is incorrect - a rod block does not exist with IRMs on range 8. SRM bypass will be necessary only if power is allowed to lower below range 8.
B is incorret--,S only requires 3 SRM channels for the heatup. C is incorrect-*Allough S-RM 12-is _<__0
_CPS, the rod block does not exist with IRMs on Range 8.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-215-1-02 K/A:
215004 Source K4.06, Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design Range Monitor feature(s) and/or interlocks which provide for the following: IRM/SRM interlock (SRM) System 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 x//,,LA
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
215004 215004 Importance Rating 2.8 2.8 Proposed Question: RO 045, SRO 050 A reactor startup is in progress, with the following:
Reactor power is 5.5 x 104 cps on all SRMs SRM 11 detector becomes stuck and will not withdraw Which one of the following describes when SRM 11 must be bypassed in order for control rod withdrawals to continue?
To continue rod withdra 11 must be bypassed when...
A.
SRM 11 reaches B.
any SRM reache<
1ý10 3 c§/
C.
IRM 11, 12, 13, or 14 is on Range 7 D.
all IRMs are on Range 7 Proposed Answer: A Proposed references to be provided to applicants during examination: None Technical Reference(s):
01 -OPS-001-215-1-02 K/A:
215004 SOURCE K5.03. Knowledge of the operational implications of the following RANGE concepts as they apply to SOURCE RANGE MONITOR (SRM)
MONITOR (SRM)
SYSTEM: Changing detector position SYSTEM 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New X
History Justification:
A is correct - any single SRM reaching 1 E5 cps will impose a rod withdrawal block, but bypassing SRM 11, specifically, will remove the rod block if only SRM 11 is at 1 E5 cps. B is incorrect Although any of the other SRMs at 1 E5 cps will cause a rod block, bypassing SRM 11 will affect only the SRM 11 upscale signal to RMCS. CID are incorrect - plausible only if candidate is confused about the feature that auto-bypasses the SRM upscale rod block when IRMs are on Range 7.
oyl__
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A#
215005 215005 Importance Rating 2.6 2.8 Proposed Question: RO 046, SRO 051 The plant is operating at 100% power, with the following:
The power supply leads to an LPRM detector associated with APRM 15 requires repair You have been assigned to work on the clearance Which of the following states the electrical bus you would expect to apply clearance tags for this work?
A.
24 VDC Bus 11 B.
24 VDC Bus 12 C.
120 VAC RPS Bus 11 D.
120 VAC RPS Bus 12 Proposed Answer: D Justification:
D correct - The LPRM detectors are powered from RPS 120 VAC, APRM 15 is associated with channel 12 A/B are incorrect - LPRM detectors are powered from RPS 120 VAC C is incorrect - APRM 15 is associated with channel 12 Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1 -OP-38C/sect C, 01 -OPS-001 -215-1-02/Table 25 K/A:
215005 K2.02. Knowledge of electrical power supplies to the following:
AVERAGE APRM channels POWER RANGE MONITOR/LOCA L POWER RANGE MONITOR
_ SYSTEM 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2
Examination Outline Cross-reference:
2 2
Group#
1 K/A #
215005 215005 Importance Rating 3.6 3.6 Proposed Question: RO 047, SRO 052 A plant startup is in progress, with the following:
The Mode Switch is in RUN Reactor Power lowers due to steam load changes and feedwater input APRM's 11, 12 and 16 have Downscale alarms Which one of the following describes the ability to individually drive control rods?
Control rods may be individually driven...
A.
In both directions B.
Inward direction only C.
Outward direction only D.
In neither direction.
Proposed Answer: B Justification:
B is correct - with APRM downscale and Mode switch not in STARTUP/REFUEL a withdraw block is applied AICID are incorrect
-other possible effects but withdraw block will occur for given conditions Proposed references to be provided to applicants during examination: None Technical Reference(s):
01 -OPS-001 -215-1-02/Table 29 K/A:
215005 A1.03: Ability to predict and/or monitor changes in parameters AVERAGE associated with operating the AVERAGE POWER RANGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls MONITOR/LOCA including: Control rod block status.
L POWER RANGE MONITOR SYSTEM 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
216000 Importance Rating 3.2 Proposed Question: RO 048 The plant is operating in Four-loop mode, with the following:
Recirc pumps 11, 12, 13 and 15 are operating One Channel 11 RPV level instrument is OOS for testing and inputting a LOW signal One Channel 11 RPV pressure instrument fails high Which one of the following describes the effect on the Reactor Recirculation System pumps?
All Recirc pumps...
A.
will remain running at current flowrates B.
will runback to minimum flow C.
except 12 will trip D.
will trip Proposed Answer: A Justification:
A is correct - Two pressure or two level inputs are required on either channel 11 or 12 to trip all recirc pumps B is incorrect - runback would not occur, but is a recirc response to other conditions C incorrect - if trip is initiated all pumps would trip. D incorrect - two signal of one parameter required to initiate a trip Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-40, section B, page 9 K/A:
216000 K3.30: Knowledge of the effect that a loss or malfunction of the NUCLEAR NUCLEAR BOILER Instrumentation will have on following:
BOILER Recirculation system Instrumentation 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
216000 Importance Rating 2.4.10 Proposed Question: RO 049 A Failure to Scram has occurred, with the following:
Reactor Power is 4Yo Reactor Water Level is being controlled -202o-30 inches F4-2-1, CORE LEVEL TORUS TEMP. MONITOR SYS. 12 TROUBLE alarms H482, FZWL12 DRYWL TEMP is in alarm Drywell Temperature is -220F A disp~arity exists between F one instruments A similar disparity exists between Lo-Lo-Lo instruments Which one of the following RPV Level instruments should be used to control RPV Le el?
A.
Lo-Lo-Lo Ch 11 B.
Lo-Lo-Lo Ch 12 C.
Fuel Zone Ch 11 D.
FuelZoneChl2 12(
Proposed Answer: C Justification:
C correct-Fuel Zone range -240 to +110, 11 Density Compensation is working A/B incorrect -
gh Drywell te rature makes the minimum usable indication is 10 inches ncorrect - Fuel Zone Ch 12 is inoperable due to loss o density mpensation Proposed references to be provided to ap ts during examinat n:
RP F4-2-1, N1-EOP-3 Technical Reference(s):
ARP-F4-
-EOP-3 K/A:
216000 Nuclear
- 2.
wledge of annunciator response procedures Boiler Instrumentation 10 CFR Part 55 Content:
55.41(7)
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:
2 Comments:
None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
218000 218000 Importance Rating 3.7 3.8 Proposed Question: RO 050, SRO 053 The plant is operating at 100% power, with the following:
PRESS SAFETY / RELIEF VALVES FLOW is alarming ERV 121 Acoustic Monitor reads high VY't Downstream tailpiece temperature for ERV 121 reads 138 OF N'
Torus water temperature is 74 OF and steady Which one of the following identifies the appropriate operator response to these conditions?
A.
Repair the ERV 121 acoustic monitor during the next cold shutdown.
B.
Commence an emergency power reduction per N1-OP-43B.
C.
Cycle the control switch for Emergency Relief Valve 121.
D.
Pull the control power fuses for ERV 121 in "F Panel.
Proposed Answer: A Justification:
A correct-The remaining indicators confirm an acoustic monitor failure B incorrect - SRV is not open C incorrect - SRV is not open D incorrect - SRV is not open Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-218-1-01 K/A:
218000 A3.03: Ability to monitor automatic operations of the AUTOMATIC AUTOMATIC DEPRESSURIZATION SYSTEM including: ADS valve acoustical DEPRESSURIZA monitor noise: Plant-Specific.
TION SYSTEM 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
X1 2450 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
218000 Importance Rating 3.8 Proposed Questi 01 A loss of coolantand electrical power has occurred, with the following:
the Powerboard 102 supply to ADS Channel 11 is lost.
valid and sustained ADS initiation signals are received.
Which one of the following identifies the status of the Primary and Backup ADS valves at 116 seconds after the initiation of the ADS signals?
PRIMARY VALVES BACKUP VALVES A.
Closed Closed B.
Closed Open C.
Open Closed D.
Open Open Proposed Answer: C Justification:
C is correct - ADS Channel 12 is unaffected by the PB 102 loss; all of the ADS logic necessary to actuate ERVs will function normally; i.e.,
primary valves will open at Time = 111 sec and prevent the opening of the secondary valves. AIB/D are incorrect - plausible if examinee confuses relationship between PB 102 120 VAC power and the RPS ADS logic and is distracted by our choice of 116 sec in the stem.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-218-1-01 K/A:
218000 K5.01, Knowledge of the operational implications of the following Automatic concepts as they apply to the AUTOMATIC DEPRESSURIZATION Depressurization SYSTEM: ADS logic operation.
System 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
X New History 2000 NMP1 ROISRO Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group#
1 1
K/A #
223001 223001 Importance Rating 3.0 3.1 Proposed Question: RO 052, SRO 054 A loss of Instrument Air to the CAM and H2-0 2 Monitors has occurred.
Which one of the following describes the response of the sample stream isolation valves, and the required alternate method for monitoring the primary containment atmosphere?
RESPONSE OF SAMPLE STREAM IVs A.
B.
Fail open C.
Fail closed D.
Fail closed Proposed Answer: A LTERNATE MONITORING METH D Channel 27 2local indication Channel 12 H2-0 2 Control Room indication Drywell PASS sample Torus PASS sample Justification:
A is correct - Per SOP-6. B is incorrect - cal gas IVs fail closed; therefore no control room indication is valid. CID are incorrect sample IVs fail open, and although SOP-6 suggests a PASS (if desired), it still requires monitoring Ch. 12 locally.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
NI-SOP-6 K/A:
223001 Primary K1.10, Knowledge of the physical connections and/or cause-effect Containment relationships between PRIMARY CONTAINMENT SYSTEM AND System and AUXILIARIES and the following: Plant air systems Auxiliaries 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
X1 2473 Modified Bank #
New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
223001 Importance Rating Proposed Question: RO 053 The plant is operating at 100% power, with the following:
RBCLC pump 12 is operating RBCLC Temperature Controller 70-23B is operating in automatic Controller 70-23B's output signal rapidly fqils high (maximum output signal Without operator action, which one of the following control room annunciators
- result?
A.
K3-4-4, CLEANUP SYSTEM ISOLATION B.
F2-1-1, REACT RECIRC PUMP - MOTOR 11 C.
K1-4-6, TORUS - DWVAC RELIEF CHECK VALVE OPEN D.
H1-2-1, REACTOR BLDG COOL PUMP 12 TRIP-V-SUCT Proposed Answer: C Justification:
C is correct - Controller's max output signal acts to fully close RBCLC HX bypass valve and fully open the RBCLC HX Service Water outlet valve; results in maximum RBCLC cooling (minimum supply temperature). Sudden significant drop in DW cooler RBCLC temperature may cause rapid DW atmosphere cooldown, DW pressure drop and create the d/p (DW-Torus) necessary to momentarily open the Torus-DW Vacuum Breakers. A/B are incorrect - plausible if examinee believes that the max output signal results in minimum cooling (higher RBCLC supply temp). D is incorrect - RBCLC pump suction pressure would not lower if system temp lowered.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-223-1-02, N1-ARP-K1-4-6, HI-4-1 K/A:
223001 Primary K4.05, Knowledge of Primary CTMT and Auxiliaries design feature(s) and or CTMT and interlock(s) which provide for the following: Maintains proper suppression Auxiliaries pool to drywell differential pressure 10 CFR Part 55 Content:
55.41(7)
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
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
223002 Importance Rating 3.6 Proposed Question: RO 054 The plant is operating at 100% power with the following:
Battery Board 11 is clearance tagged Transferrable loads have been transferred to Battery Board 12 Then, the following occurs:
Loss of Powerboard 161 B Failure to Scram Liquid Poison is initiated RPV water level has been intentionally lowered to -41 inches Which one of the following describes the current status of the Reactor Water Cleanup System (RWCU) and Reactor Sample Return Vs (63-04 and 63-05)?
RWCU A.
Isolated B.
Isolated C.
Not isolated D.
Not isolated REACTOR SAMPLE RETURNS Closed Open Closed Open Proposed Answer: B Justification:
B is correct - Although loss of PB 161 B prevents closure of RWCU Inboard IV (33-02R), the Outboard IV is a DC valve powered from Battery Board 12. The RWCU Return IV (33-01R) still has power from PB 171B. When Liquid Poison is initiated, RWCU will successfully isolate. The Reactor Sample Return IVs are DC valves powered from Battery Board 11 and are not transferrable loads. When an RPV Lo-Lo level occurs (+5 inches) for the failure to scram actions (lowering level), these valves will not auto-close. A/C/D are incorrect - for the reasons described above.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-SOP-17, Ni-OP-47A, 01-OPS-001-204-1-01 K/A:
223002 Primary A4.01, Ability to manually operate and/or monitor in the control room: Valve closures.
Containment Isolation/Nuclear Steam Supply Shutoff 10 CFR Part 55 Content:
55.41(7)
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
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
239002 239002 Importance Rating, 3.7 3.8 Proposed Question: RO 055, SRO 059 The plant is operating at 100%, with the following:
"An ERV inadvertently opens C-Reactor Water level is 72 inches With no operator action, which one of the following describes Reactor Water level response?
Reactor Water level will...
A.
Rise and remain above 72 inches B.
Rise and then return to 72 inches C.
Lower and remain below 72 inches D.
Lower and then return to 72 inches Proposed Answer: B Justification:
B correct - the ERV opening will result in a level swell which will be corrected for by FWLC A incorrect - correct initial response but ERV steam flow is measured as part of the steam flow signal used by FWLC C/D incorrect - Reactor Water level will not lower Proposed references to be provided to applicants during examination: None Technical Reference(s):
Nl-OP-01 section B K/A:
239002 SRVs A1.05 - Ability to predict and/or monitor changes in parameters associated with operating the SRVs controls including: Reactor Water Level 10 CFR Part 55 Content:
55.41(5,14)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
239002 239002 Importance Rating, 3.9 4.0 Proposed Question: RO 056, SRO 060 The plant is operating at 100% power, with the following:
Battery Board 12 is lost A sustained loss of Turbine Building ventilation has occurred No operator action is taken Which one of the following describes the plant response per Technical Specification bases?
A.
Reactor Coolant Safety Valves may lift.
B.
Reactor Coolant Pressure Safety Limit may be violated.
C.
Peak cladding temperatures greater than 15000 F may occur.
D.
Loss of RPV inventory due to steam flow may exceed the Core Spray capacity.
Proposed Answer: A Proposed references to be provided to aeo Technical Reference(s):
1l-S 2.2.2 Bases z
K/A:
C239002o K3.01, Knowledge of the effect that a loss or malfunction of the Relief/Safe RELIEF/SAFETY VALVES will have on following: Reactor pressure Valves control--
10 CFR Part 55 Conten.t*-55_7)
X 55.43 55.45 Question Source:
-Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None Justification:
A is correct - Per T.S. 2.2.2, all 9 Safety Valves may lift to prevent exceeding the 1375 psig Safety Limit in the event of an MSIV closure from rated power followed by a high flux scram. BB 12 loss leaves the plant with only 3 ERVs, with insufficient relief capacity to keep pressure below the Safety Valve setpoints. Sustained loss of TB Ventilation will ultimately (no operator action) allow Main Steam Pipe Tunnel temperature to reach 200 F.
MSIV's will auto-close as a result. B is incorrect - Purpose of the Safeties lifting is to prevent exceeding the Pressure Safety Limit. C is incorrect - Plausible only if examinee is distracted to think that the "Minimum Number of ERVs Required for ED" is something greater than 3. D is incorrect - Plausible only if examinee is distracted to believe that the 3 available ERVs, combined with the lifting Safeties, let down inventory at a rate that is greater than Core Spray's capacity to replace.
Y'jf I
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
241000 241000 Importance Rating 3.8 3.9 Proposed Question: RO 057, SRO 061 The plant is operating at 90% with the following:
Power ascension is in progress Turbine Load Limiter is set at 95%
As reactor power is raised, which one of the following effects will be seen when the Turbine Load Limiter setpoint is reached?
A.
The intercept valves will throttle closed and the bypass valves will open.
B.
The control valves will stop opening, causing a high pressure reactor scram.
C.
The control valves will stop opening and the bypass valves will open to maintain pressure.
D.
There will be no effect because the Governor and Speed Load Changer are in control of the turbine.
Proposed Answer: C Justification:
C is correct - Pressure is controlled by control, then bypass valves.
Load is controlled by control valves. The Load Limiter may be employed to limit control valve opening (Load). A is incorrect - IV's are not affected by the Load controls. B is incorrect - Ignores operation of Bypass valves. D is incorrect - The Load Limiter can limit the oil available to the control system, limiting CV opening.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni1-OP-31, 01-OPS-001-248-1-01 K/A:
241000 K1.01, Knowledge of the physical connections and/or cause-effect Reactor/Turbine relationships between REACTOR/TURBINE PRESSURE Pressure REGULATING SYSTEM and the following: Reactor power Regulating System 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
X12523 New History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
2 Group#
1 K/A #
241000 Importance Rating 1 3.1 Proposed Question: RO 058 The plant is operating at 40% power when the turbine Speed Control Unit output linkage to one Combined Intercept Reheat Stop Valve for Low Pressure Turbine 'A' (LP 'A') becomes disconnected from the valve.
Without operator action, which one of the following describes an effect of this malfunction?
A.
Turbine trip and reactor scram B.
Increased vibrations on the LP 'A' journal bearings C.
Potential turbine overspeed on a loss of generator load D.
10% closure on at least one Turbine Control Valve (TCV)
Proposed Answer:
B Justification:
B is correct - SCU linkage holds open the IV portion of the CRV. A disconnected linkage results in that IV going closed, stopping steam flow into one of the two inlets to LP 'A'.
Unbalanced steam flow into LP 'A' (thru the unaffected CRV) results in increased vibrations. A is incorrect - TSV/TCV closure scram signals, yes; CRV closure scram signals, no. C is incorrect - Stem suggests the opposite; this LP 'A' steam inlet is already closed. D is incorrect - Plausible only if examinee confuses the relationship between the CRVs (IV portion) reaching fully open at about the same time when TCVs are approximately 10% open, on a turbine startup.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
NI-OP-31, 01-OPS-001-248-1-01 K/A:
241000 K1.09, Knowledge of the physical connections and/or cause-effect Reactor/Turbine relationships between REACTOR/TURBINE PRESSURE REGULATING Pressure SYSTEM and the following: Combined intermediate valves: Plant-Specific Regulating System 10 CFR Part 55 Content:
55.41(7)
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:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
259002 259002 Importance Rating 3.6 3.6 Proposed Question: R0060, SRO 063 The plant is at 100% power, with the following:
12 and 13 FW pumps are in service FWLC is in a normal configuration The selected RPV Level input to FWLC fails low Which one of the following describes the expected RPV level response and the action that should be taken?
RPV LEVEL RESPONSE A.
Rise B.
Rise C.
Lower D.
Lower ACTION Take 13 FCV to MANUAL Select the standby level input Take 13 FCV to MANUAL Select the standby level input Proposed Answer: A Justification:
A is correct - Level input low will cause a level error that will act to open 13 FCV and raise RPV level, taking 13 FCV to manual will correct the problem in a controlled fashion B is incorrect - not the right action per OP-16, F. 10- all input swapping should be done with FCV's in MANUAL CID are incorrect -water level will rise not lower Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-OP-16, Sec B/pg 6 & F.10 K/A:
259002 A2.03: Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Loss of level inputs.
10 CFR Part 55 Content:
55.41(7,10)
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:
2 46
Examination Outline Cross-reference:
2 2
Group #
1 1
K/A #
261000 261000 Importance Rating 3.2 3.4 Proposed Question: RO 061, SRO 064 A small drywell steam leak has occurred, with the following:
Torus venting via RBEVS train #11 has been established using the POST-LOCA vent line Drywell pressure is 3.1 psig and steady Which one of the following describes the effect on the containment venting evolution if RBEVS Exhaust Fan 11 were to trip?
Venting flow will...
A.
stop and Drywell pressure will rise B.
continue at a much lower rate, allowing Drywell pressure to rise slightly C.
stop until RBEVS train #12 auto starts; Drywell pressure may rise slightly D.
continue at the same rate, but will be untreated before reaching the main stack Proposed Answer: A Justification:
A is correct - The fan trip isolates the train and the flowpath. B is incorrect - dampers close on fan trip. C is incorrect - There is no such auto start feature. D is incorrect - BV-202-36 is closed; no such path thru normal RBVS is available.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-09; N1-EOP-1, Aft 10 K/A:
261000 Standby K3.03, Knowledge of the effect that a loss or malfunction of the Gas Treatment STANDBY GAS TREATMENT SYSTEM will have on following:
System Primary containment pressure: Mark-I&lI 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 2
LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
261000 Importance Rating 2.7 Proposed Question: RO 062 The plant is operating, with the following:
Reactor Building Emergency Ventilation (RBEVS) is in a normal line-up Power is lost to Channel 11 Reactor Building Exhaust Radiation monitor Which one of the following identifies the status of the Reactor Building Emergency Ventilation System (RBEVS) Inlet Dampers?
RBEVS 11 INLET RBEVS 12 INLET A.
Closed Closed B.
Open Closed C.
Closed Open D.
Open Open Proposed Answer: D Justification:
D is correct - RBEVS inlet dampers are normally closed and open upon initiation, both trains will initiate on loss of power to a rad monitor A/BIC are incorrect - combinations of incorrect responses should examinee not recognize the expected response Proposed references to be provided to applicants during examination: None Technical Reference(s):
NI-OP-10 K/A:
261000 Standby A4.09, Ability to manually operate and/or monitor in the control room:
Gas Treatment Ventilation valves/dampers System 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
2 2
Group#
1 1
K/A #
264000 264000 Importance Rating 3.4 3.5 Z-,
eUstiý :
63 SUR$ 966 Core Sl y Topping Pump 1i1 is clearance tagged, wIt~he-fdng:
0 0
0 0
A Loss of coolant accident occurs Containment Sprays are running RPV water level is -90 inches and steady Drywell pressure is 21 psig and slowly lowering Then, the following occur:
A loss of offsite power Both emergency diesel generators simultaneously start and load.
With Containment Spray initiation signals still present, which one of the following identifies the number of Containment Spray Pumps running 50 seconds after the emergency diesel generators energize their powerboards?
A.
0 B.
2 C.
3 D.
4 Proposed Answer: B Justification:
B is correct - Powerboard 103 pumps are unaffected by the tagged CSTP 111; so both Cont Spray Pumps 121 and 122 are running within 30 seconds of the EDG 103 re energizing PB 103. Due to CSTP 111 be OOS, a 3r Cont Spray Pump won't be running until 55 seconds after PB 102 is re-energized (50 sec b/up timer + 5 sec normal sequencing). AICID are incorrect - Not by design. All are plausible if examinee does not understand this starting sequence logic.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Nl-OP-14, drawing C-19410-C, Sh. 8 K/A:
264000 A3.05, Ability to monitor automatic operations of the EMERGENCY Emergency GENERATORS (DIESEL/JET) including: Load shedding and C1 Generators sequencing (Diesel/Jet) 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
1 K/A #
264000 Importance Rating 3.4 Proposed Question: RO 064 The plant is operating at 100% power, with the following:
Loss of 115KV Line 4 and T-101S EDG 103 starts and successfully loads on PB 103 A fire is then confirmed in the EDG 103 room Which one of the following describes how the RO would remove EDG 103 from service per NI-OP-45, Emergency Diesel Generators?
Place...
A.
u B.
out ut breaker in PTL, then place EDG 103 control switch in EMERGENCY STOP.
B.ýýoutl ut breaker in PTL, then place EDG 103 control switch in STOP.
C.
PB 103 normal supply breaker in PTL, then place EDG 103 control switch in EMERGENCY STOP.
D.
PB 103 normal supply breaker in PTL, then place EDG 103 control switch in STOP.
Proposed Answer: C Justification:
C correct - Must first lock out normal supply power to the bus, then satisfy the remaining engine control logic by indicating there is no need for the EDG to re-power the bus, by positioning the engine control sw in EMERG STOP. A/B incorrect normal supply power is not locked out. D incorrect - normal supply power is locked out, but EDG will re-start on bus undervoltage using the normal STOP switch.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni1-OP-45, 01-OPS-001-264-1-01 K/A:
264000 A2.06: Ability to (a) predict the impacts of the following on the EMERGENCY EMERGENCY GENERATORS (DIESEL/JET) ; and (b) based on those predictions, GENERATORS use procedures to correct, control, or mitigate the consequences of those abnormal (DIESEL/JET) conditions or operations: Opening normal and/or alternate power to emergency bus 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 3
K/A#
201003 201003 Importance Rating 3.6 3.7 Proposed Question: RO 065,SRO080 The plant is operating at 100% power, with the following:
A Reactor scram occurs 10 scram inlet valves on withdrawn control rods fail to open All scram outlet valves open per design Which one of the following describes the response of the 10 malfunctioning control rods?
The 10 control rods will...
A.
scram at normal scram speed, with reactor pressure alone.
B.
scram at normal scram speed, with accumulator pressure alone.
C.
scram more slowly than the others, with reactor pressure alone.
D.
scram more slowly than the others, with accumulator pressure alone.
Proposed Answer: C Justification:
C is correct - With the reactor at rated pressure, the accumulator provides the motive force to achieve proper scram time, but reactor pressure will fully insert the rods. A is incorrect - The rods scram due to reactor pressure but slower with accumulator/charging header isolated. B is incorrect - Accumulator is isolated from mech. D is incorrect - Accumulator is isolated from mech.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-201-1-,J04O' K/A:
201003 Control K4.04: Knowledge of CONTROL ROD AND DRIVE MECHANISM Rod and Drive design feature(s) and/or interlocks which provide for the following:
Mechanism The use of either accumulator or reactor water to SCRAM the control rod 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 #
201006 201006 Importance Rating 3.0 3.0 Proposed Question: RO 066, SRO 068 A reactor startup is in progress, with the following:
The tenth rod of RWM Group 01 has just been withdrawn to position 48 RWM Group 01 contains 12 rods Which one of the following identifies the number of RWM errors displayed when the next rod in sequence is selected?
INSERT ERRORS A.
0 rods displayed B.
2 rods displayed C.
0 rods displayed D.
2 rods displayed WITHDRAW ERRORS 0 rods displayed 0 rods displayed 2 rods displayed 2 rods displayed Proposed Answer: B Justification:
B is correct - The RWM latches the next group when the last 2 rods in a group withdraw sequence remain inserted past the insert limits.
AICID are incorrect -
Plausible combinations to discriminate against an examinee who lacks an understanding of what generates RWM errors.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-201-1-03 K/A:
201006 RWM A4.03, Ability to manually operate and/or monitor in the control room:
I Latched group indication: PSpec(Not-BWR6) 10 CFR Part 55 Content:
55.41(7)
X 55.43_
55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Y~o ( ý Examination Outline Cross-reference:
2 2
Group #
2 2
K/A #
202001 202001 Importance Rating 2.8 2.9 Proposed Question: RO 067, SRO 070 The plant is planning for an upcoming refueling outage, with the following:
Work on Recirc Loop 14 will require plugging both the suction and discharge nozzles All other Recirc Loops will be available For the upcoming outage, which one of the following describes Shutdown Cooling (SDC) availability and the reason?
Shutdown Cooling would be...
A.
unaffected due to ecirc Loop 15 being available B.
unavailable due t4 oss of only the suction path C.
unavailable due tr" jUss of only the discharge path D.
unavailable due to oss of both suction and discharge paths Proposed Answer: B Justification:
B is correct - The SDC system takes a suction on Recirc Loop 14 and returns via Recirc Loop 15 AIC/D are incorrect - the suction path and only the suction path will be lost Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-04, B.1, page 3 K/A:
202001 K3.08: Knowledge of the effect that a loss or malfunction of the RECIRCULATIO RECIRCULATION SYSTEM will have on following: Shutdown N SYSTEM cooling system 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 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 #
204000 204000 Importance Rating 3.4 3.8 Proposed Question: RO 068,SRO 071 The plant is operating at 100% power, with the following:
RWCU Filter 12 is in service RWCU Filter 11 is clearance tagged for repairs UPS 172 Protective Relaying has just tripped on a spurious Overvoltage Which one of the following describes the status of the RWCU Filter 12 isolation and the need to perform filter backwash?
RWCU Filter 12 A.
Isolated B.
NOT Isolated C.
Isolated D.
NOT Isolated Backwash filter before next use?
Yes Yes-No No*
Proposed Answer: A Justification:
A is correct-UPS loss results in filter 12 isolation and RWCU isolation on low flow.
OP-3, D.20 warns that system isolation without Filter 12 in recycle (it wasn't) does not guarantee that media will be fully retained on the element. Requires backwash and precoat prior to being placed back in service. B is incorrect - system isolates. C is incorrect - system isolates. D is incorrect - Filter 12 isolates.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-40, N1-OP-3 K/A:
204000 Reactor 2.1.32, Ability to explain and apply system limits and precautions.
Water Cleanup System 10 CFR Part 55 Content:
55.41(10)
X 55.43 (5) 55.45 Question Source:
Bank #
Modified Bank #
New 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 1
KIA #
219000 219000 Importance Rating 2.5 2.9 Proposed Question: R0069, SRO 072 The plant is operating, with the following:
Torus Cooling is desired Powerboard 167 is not available Which one of the following states the Containment Spray loop(s) that can be placed in Torus Cooling from the Control Room?
A.
121 only B.
122 only C.
121 or 122 D.
None Proposed Answer: D Justification:
D correct - Without PB 167 (600 VAC), can't open BV-80-118, which is necessary to place any of the 4 loops in torus cooling. AIBIC incorrect - BV-80-118 is the only valve (common to placing any of the 4 loops in service) that restricts the ability to place at least one of the loops in service. All other valves to be operated in aligning for torus cooling are DC-solenoid operated, AOVs.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-14, PID C-18012-C, Sh.2 K/A:
219000 K2.01: Knowledge of electrical power supplies to the following:
RHR/LPCI:
Valves Torus/Suppressio n Pool Cooling Mode 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History
Examination Outline Cross-reference:
2 2
Group #
2 2
K/A #
219000 219000 Importance Rating 2.8 2.9 Proposed Question: R0070, SRO 073 Containment Spray Loop 121 is cooling the Torus when a tube ruptures in its heat exchanger.
Which one of the following describes the initial response of Containment Spray Pump 121 discharge pressure and Raw Water Pump 121 flow?
SPRAY PUMP DISCHARGE PRESSURE RAW WATER PUMP FLOW A.
Lowers Rises B.
Lowers Lowers C.
Rises Rises D.
Rises Lowers Proposed Answer: C Justification:
C correct - RW pressure is > Cont Spray pressure. Ruture results in a higher Cont Spray pressure and increased RW flow (additional flow path made available). Both of these parameters are monitored in the control room. AIBID incorrect - for reasons as already described for A.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-14, B.0, D.3.0 K/A:
219000 A1.03: Ability to predict and/or monitor changes in parameters RHR/LPCI:
associated with operating the RHR/LPCI: TORUS/SUPPRESSION TORUS/SUPPRE POOL COOLING MODE controls including: System pressure SSION POOL COOLING MODE 10 CFR Part 55 Content:
55.41(7,14)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 #
226001 226001 Importance Rating 2.6 2.8 Proposed Question: RO 071, SRO 058 The plant is determined to be above the upper-most limit of Figure K, Containment Spray Initiation Limit.
Per the EOP Bases, which one of the following identifies the potential consequence of spraying the containment at this time, and why that consequence might occur?
POTENTIAL CONSEQUENCE A.
Vacuum Breakers operate B.
Vacuum Breakers operate C.
Containment fails D.
Containment fails WHY IT MIGHT OCCUR Thermal transient Rapid pressure reduction Thermal transient Rapid pressure reduction Proposed Answer: D Justification:
D correct - Per EOP bases evaporative cooling could result in excessive negative pressure in the conatinment either before the vacuum breakers can respond or in excess of the relief capability/non-condensible content of the Torus AIBIC incorrect combination of response for being left of the curve and/or wrong reason.
Proposed references to be provided to applicants during examination: EOP flowcharts Technical Reference(s):
Ni-ODP-PRO-0305 K/A:
226001 K5.06 - Knowledge of the operational implications of the following RHR/LPCI:
concepts as they apply to the RHR/LPCI: CTMT Spray Mode:
CTMT Spray Vacuum breaker operation Mode 10 CFR Part 55 Content:
55.41(5)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New 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
KJA #
245000 245000 Importance Rating 2.8 3.1 Proposed Question: R0072, SRO 074 Which one of the following describes a turbine vibration condition that would require the operator to immediately trip the turbine per NI-OP-31, "Tandem Compound Reheat Turbine"?
A.
7 mils for 2 minutes while at 400 rpm B.
9 mils for 1 minute while at 700 rpm C.
7 mils for 2 minutes while at 1000 rpm D.
9 mils for 1 minute while at 1300 rpm Proposed Answer: B Justification:
B is correct - turbine trip is required @ 8 mils below 800 rpm.
A is incorrect - 7 mils is the limit for continued operation between 800-1400 rpm. C is incorrect-above the 800 rpm limitation. D is incorrect - vibration 14 mils would require immediate trip at this rpm.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
NI-OP-31 K/A:
245000 Main K5.02 - Knowledge of the operational implications of the following Turbine Gen. and concepts as they apply to the Main Turbine Gen. and Auxiliaries:
Auxiliaries Turbine operations and limitations 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
X12529 New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None I.--
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
2 K/A #
256000 Importance Rating 2.8 Proposed Question: RO 073 The plant is operating at 90% power, with the following:
Condensate Pumps 11 and 12 are running FW Booster Pumps 12 and 13 are running FW Pumps 12 and 13 are running Condensate Pump 13 is tagged out Condensate Pump 11 now trips Which one of the following describes the plant response and the required operator action?
A.
FW Booster pumps trip on low suction pressure; immediately scram the reactor.
B.
FW Booster pump suction pressure slowly lowers; perform Emergency Power Reduction.
C.
Feedwater pumps trip on low suction or discharge pressure; immediately scram the reactor.
D.
Feedwater pump suction pressure slowly lowers; perform Emergency Power Reduction.
Proposed Answer: C Justification:
C is correct - FWP 12 trips on low suction pressure; FWP 13 trips on low discharge pressure; RPV water level rapidly lowers; scram the plant before +53". A is incorrect - There are no low suction pressure trips for the FWBPs. BID are incorrect - FWBP suction pressures rapidly lower with only I running Cond Pump @ 90%. No time-for EPR to make a difference before RPV water level drops to +53".
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-OP-15A K/A:
256000 A1.03: Ability to predict and/or monitor changes in parameters REACTOR associated with operating the REACTOR CONDENSATE SYSTEM CONDENSATE controls including: System Pressure SYSTEM 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 1
K/A #
262001 262001 Importance Rating 3.5 3.7 Proposed Question: RO 074,SRO 065 The plant is operating at 100% power, with the following:
Main generator output voltage is normal when the amplidyne begins to fail (Time 0 seconds)
The following main generator output voltages result:
TIME OUTPUT VOLTS 20 seconds 26,000 30 seconds 27,000 40 seconds 28,000 50 seconds 29,000 60 seconds 30,000 Without operator action, which one of the following identifies the earliest time by which the house loads should have fast transferred to reserve power?
A.
30 seconds B.
40 seconds C.
50 seconds D.
60 seconds Proposed Answer: C Justification:
C correct - Generator over-voltage trips are: 110% x normal (24,000) for 30 seconds, and 118% x normal for 2 seconds. Given time-line indicates output volts will reach the first trip point (26,400) @ Time = 24 seconds, and will reach the 2 nd trip point (28,320) @ Time = 43 seconds. The 1st trip's timer will trip the generator at Time = 54 seconds (i.e., 24 + 30).
The 2 nd trip's timer will trip the generator at Time = 45 seconds (43 + 2). By Time = 50 seconds, house loads will have auto-transferred to reserve transformers. The turbine will have tripped, and the reactor will have scrammed, as well, but are incidental to this question. AIBID incorrect - See explanation above.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
O1-OPS-001-262-1-01 A//- O K/A:
262001 A.C.
K6.03 Knowledge of the effect that a loss or malfunction ofrte following will Electrical have on the A.C. Electrical Distribution; Generator trip.
Distribution 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 #
263000 Importance Rating 3.3 Proposed Question: RO 075 The plant is operating at 100% power, with the following:
Static Battery Chargers (SBC) 161A and 171A are in service Powerboard 16A is inadvertently deenergized then re-energized TWO minutes after Powerboard 16A is re-energized, and with no additional operator action, which one of the following identifies the Battery Board 11 and 12 voltages?
Battery Board 11 Battery Board 12 A.
125 VDC 125 VDC B.
125 VDC 135 VDC C.
135 VDC 125 VDC D.
135 VDC 135 VDC Proposed Answer: D Justification:
D is correct - 100 seconds after AC power is restored to SBC161 A (from powerboard 16A) the SBC will align itself to the Battery 11-and return voltage to the normal float voltage of 135VDC AIB are incorrect
- Battery 11 voltage will return to 135 VDC. C is incorrect - Battery 12 is unaffected as it's SBC is powered from PB-17A(B).
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-47A, B.4 K/A:
263000 D.C.
K1.01, Knowledge of the physical connections and/or cause-effect Electrical relationships between D.C. ELECTRICAL DISTRIBUTION and the Distribution following: A.C. electrical distribution 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW 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 #
271000 271000 Importance Rating 3.6 3.3 Proposed Question: RO 076, SRO 075 The plant is operating at 100%, with the following:
H1-2-6, AIR EJECTOR OFF GAS FLOW-PRESS TEMP HIGH alarms C145 OFFGAS TEMP HIGH is in alarm C135 OFFGAS PRESSURE HIGH is in alarm H1-1-6, AIR EJECTOR HI-LO STM PR V CLOSED alarms Which one of the following is required?
A.
Verify Offgas Stack BV closes B.
Place a second Offgas vacuum pump in service C.
Perform an Emergency Power Reduction D.
Place the Mode Switch in Shutdown Proposed Answer: C Justification:
C correct - Offgas conditions would result in closure of SJAE BV's, per N1-OP-25, H.4.1.1 Emer Power Red required A incorrect-Stack BV closes on high rad only B incorrect - OP-25 action, but not required for conditions D incorrect - SCRAM not immediately required on Offgas isolation Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-ARP-H1-2-6, NI-OP-25, H.4 K/A:
271000 Offgas K4.08 - Knowledge of Offgas ;esign feature(s) and or -ftteiock(s)
I which provide for the followin : Automatic system isolation 10 CFR Part 55 Content:
55.41(7)
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:
2 Comments:
None
(1J'r7 Examination Outline Cross-reference:
2 2
Group #
2 2
K/A #
272000 272000 Importance Rating 3.6 3.5 Proposed Question: RO 077, SRO 076 Containment inerting is in progress, with the following:
Annunciator H1-1-8, STACK GAS MONITORS HIGH RADIATION, alarms RN10A is above the HIGH-HIGH alarm setpoint RN10B has just reached the HIGH alarm setpoint and is rising Which one of the following describes the required operator action?
Verify...
A.
isolation of the inerting lineup has occurred B.
Reactor Building Emergency Ventilation has started C.
isolation of the inerting lineup when RN101B reaches the HIGH-HIGH setpoint D.
Reactor Building Emergency Ventilation starts when RN 10B reaches the HIGH-HIGH setpoint Proposed Answer: C Justification:
C is correct-2-out-of-2 logic (both RN10's > HIGH-HIGH) required to initiate isolation of PC vent/purge valves. A is incorrect - for the reasons described above. BID are incorrect-RN10A/B have no relationship with Secondary Containment/RBEVS.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-OP-50B, NI-ARP-HI-1-8 K/A:
272000 Radiation A3.09, Ability to monitor automatic operations of the RADIATION V
Monitoring MONITORING SYSTEM including: Containment Isolation Indications.
System 10 CFR Part 55 Content:
55.41(7,11)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank#
X New History 2000 NMPI SRO audit, modified Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
2 K/A #
286000 Importance Rating 2.9 Proposed Question: RO 078 Which one of the following describes how the fire protection system responds to a loss of Powerboard 176 when Fire Jockey Pump 12 is running?
Concerning the Fire Jockey pumps...
A.
both lose power; the Motor Driven Fire Pump starts at 110 psig to restore header pressure.
B.
both lose power; the Diesel Driven Fire Pump starts at 110 psig to restore header pressure.
C.
11 loses power; Fire Jockey Pump 12 maintains header pressure.
D.
12 loses power; Fire Jockey Pump 11 starts to maintain header pressure.
Proposed Answer: A Justification:
A correct - Both jockey pumps are powered from PB 176. MDFP starts at 110 psig. B incorrect-DDFP starts at 100 psig. CID incorrect - Both jockey pumps are powered from the same source.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-286-1-01 K/A:
286000 Fire K2.02 - Knowledge of electrical power supplies to the followind.
I Protection Pumps 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45_
Question Source:
Bank #
Modified Bank #
X12651 New History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
2 Group#
2 K/A #
290001 Importance Rating, 3.3 Proposed Question: RO 079 The plant is at 100% power, with the following:
Light can be seen from outside, along the train rails coming under the Reactor Building Outer Swing Door.
Inner Lift Door is closed and sealed 0
The SSS has been informed Which one of the following identifies the status of Secondary Containment Integrity and the required actions?
Secondary Containment Integrity is...
A.
intact and an ACR is required.
B.
intact and RBEVS must be started.
C.
not met and an ACR is required.
D.
not met and RBEVS must be started.
Proposed Answer: A Justification:
A correct - If the inner lift door is properly sealed, Secondary Containment is intact, however, the loss of the rail seals constitutes a degradation requiring the SSS to be notified such that compensatory actions can be taken. B incorrect - RBEVS is not required to be operated. CID incorrect - Secondary Containment Integrity is maintained by the inner lift door seals.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-OP-52; 01-OPS-001-223-1-03 K/A:
290001 A2.01: Ability to (a) predict the impacts of the following on the SECONDARY SECONDARY CONTAINMENT; and (b) based on those predictions, CONTAINMENT use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: f-Personnel airlock failure 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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 #
290003 290003 Importance Rating 3.4 3.5 Proposed Question: RO 080, SRO 077 The plant is operating at 100% power, with the following:
Control Room Vent Rad Monitor Channel 11 fails The radiation monitor is bypassed With no operator action, which one of the following describes the status of the Control Room Emergency Ventilation System 11 and 12 should a high radiation condition actually occur?
CREVS11 CREVS12 A.
Standby Standby B.
Running Standby C.
Standby Running D.
Running Running Proposed Answer: D Justification:
D correct - Only one radiation monitor input is required for CREVS initiation A/BIC are incorrect-only one signal is required so both trains of CREVS will be running Proposed references to be provided to applicants during examination: None Technical Reference(s):
Nl-OP-49 section B K/A:
290003 K1.01 Knowledge of the physical connections and/or cause-effect CONTROL relationships between CONTROL ROOM HVAC and the following:
ROOM HVAC Radiation monitors 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 (2)
X 55.45 Question Source:
Bank #
Modified Bank #
New 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 #
290003 290003 Importance Rating, 2.7 2.9 Proposed Question: RO 081, SRO 078 The plant is operating at 100% power, with the following:
An after-cooler tube leak has developed in the LEAD Instrument Air Compressor #11 The BACKUP Instrument Air Compressor (IAC) #12 is unaffected and is maintaining air header pressure Assuming no loss of instrument air, which one of the following describes the potential effect of this condition on the Control Room Ventilation (CRV) System?
A.
Chiller compressors may trip on RBCLC high temperature.
B.
Chiller compressors may cycle off and on as RBCLC flow fluctuates.
C.
CRV normal supply dampers may drift open and closed as IAC #12 loads and unloads.
D.
CRV emergency supply dampers may drift open and closed as IAC #12 loads and unloads.
Proposed Answer: B Justification:
B is correct - RBCLC supplies the IAC inter-after-coolers. A tube leak can cause RBCLC flow fluctuations. The CRV chiller compressors will cycle on/off (automatically) as RBCLC supply flow moves above and below 51 gpm at the compressors. A is incorrect - compressors are unaffected by RBCLC temps; no such high temp trip exists. CID are incorrect - Plausible distractors for the examinee who believes there is a relationship between lower than normal IAS pressures (while on the BACKUP IAC) and the potential for CRV dampers to operate abnormally.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-SOP-8; Ni-OP-011; Nl-OP-49 K/A:
290003 Control K6.02, Knowledge of the effect that a loss or malfunction of the following will I Room HVAC have on the CONTROL ROOM HVAC: Component cooling water systems 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
2 K/A #
300000 Importance Rating 3.3 Proposed Question: RO 082 An operator reports that the air supply line to BV 16-08, FW Heater 123 Extraction Steam bypass valve, broke off when he attempted to tighten a lea
- fittinkg, Which one of the following identifies the a7 1 valve and FW temperature response?
BV 16-08 FW Temnlerature A.
Opens B.
Opens C.
Closes D.
Closes Lowers Rises Lowers Rises Proposed Answer: A Justification:
A correct - The BV fails open on loss of air bypassing extraction steam to the main condenser effectively removing FW heating from the 123 heater and FWtemperature lowers. B incorrect-BV fails open but FW temperature will lower not rise COD incorrect - BV fails open Proposed references to be provided to applicants during examination: None Technical Reference(s):
C-1 8002-C sheet 3 K/A:
300000 K3.02: Knowledge of the effect that a loss or malfunction of the INSTRUMENT (INSTRUMENT AIR SYSTEM) will have on the following: Systems AIR SYSTEM having pneumatic valves and controls 10 CFR Part 55 Content:
55.41(7,)
X 55.43 55.45 Question Source:
-Bank #
Modified Bank #
New 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 #
400000 400000 Importance Rating 2.8 3.0 Proposed Question: RO 083, SRO 079 The plant is operating, with the following:
Annunciator H1-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW, alarms Instrument Air to TBCLC LCV 71-127 is lost Which one of the following describes the expected TBCLC MU TANK level response and the action that should be taken?
MU TANK LEVEL ACTION A.
Rising Isolate the MU Tank LCV by shutting its BV B.
Rising Verify auto-start of the standby Condensate Transfer pump C.
Lowering Take manual control of the MU Tank LCV D.
Lowering Verify auto-start of the standby Condensate Transfer pump Proposed Answer: A Justification:
A is correct -The LCV fails open on a loss of air and the ARP requires isolating the LCV B is incorrect - There is no auto-start feature for the standby Condensate Transfer pump. CID is incorrect With the LCV failed open the tank level will rise not lower Proposed references to be provided to applicants during examination: None Technical Reference(s):
NI-ARP-H 1-3-4, 4-4 K/A:
400000 CCWS A2.02: Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
I/
High/low surge tank level 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
-Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None i
Examination Outline Cross-reference:
2 2
Group #
2 2
K/A#
215001 215001 Importance Rating Proposed Question: RO 084, SRO 082 The plant is operating at 100% power, with the following:
A TIP detector is stationary at the top of the core for a trace Loss of coolant accident occurs RPV water level is +25 inches and slowly lowering Drywell pressure is 3.6 psig and slowly rising Which one of the following identifies the status of the TIP detector and describes the radiation level in the TIP Room?
TIP DETECTOR A.
Stationary at top of core B.
Stationary at top of core C.
Retracting D.
Retracting RADIATION LEVEL Elevated Normal background Elevated Normal background Proposed Answer: C Justification:
C is correct - High DW pressure, alone, initiates a TIP isolation. TIP room rad levels *Were already higher than normal and will rise even higher as the detector automatically retracts, until it is in shield. NB are incorrect - Plausible only if examinee believes it takes both High DW pressure and RPV Lo-Lo water level to initiate TIP isolation (level is still above +5 inches). D is incorrect - while the detector was out-of-shield and the TIP tube un-isolated from the core, rad levels were already elevated, not normal.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-39 K/A:
215001 A1.01, Ability to predict and/or monitor changes in parameters associated Traversing In-with operating the Traversing In-core Probe controls includingý Radiation core Probe levels 10 CFR Part 55 Content:
55.41(7,12)
X 55.43 (4)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
2 Group #
3 K/A #
215001 Importance Rating 3.1 Proposed Question: RO 085 A full core c
System is in progress, with the following:
The detector from machine number 3 is inserting \\
The inserting TIP has reached the core bottom limit Loss of RPS bus 11 occurs Which one of the following describes the effect on the TIP system?
The TIP will...
A.
Withdraw at slow speed B.
Withdraw at fast speed C.
Insert at slow speed D.
Insert at fast speed Proposed Answer: C Justification:
C correct - The half isolation signal generated from the RPS power loss has no affect on TIP operation and at the core limit the TIP will shift to slow speed. AIB incorrect - Half isolation will not cause TIP to retract D incorrect - At the core limit the TIP will shift to slow speed.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-40;N1-OP-39 K/A:
215001 K6.04: Knowledge of the effect that a loss or malfunction of the TRAVERSING following will have on the TRAVERSING IN-CORE PROBE: Primary IN-CORE containment isolation system: Mark-I&ll(Not-BWRI)
PROBE 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
2 2
Group #
3 3
K/A #
233000 233000 Importance Rating 2.5 2.5 Proposed Question: RO 086, SRO 083 The plant is operating at power, with the following:
Fuel Pool filter #11 is scheduled to be backwashed and precoated Valve 54-105, ROOT - LT 54 FP FLTR SLUDGE TANK, on RB 237N has been inadvertently closed rendering the level transmitter inoperative The tank indicates empty with actual level at 4.0 feet Which one of the following describes the consequences if this condition is not corrected before the backwash evolution is conducted?
A.
The Reactor Building Ventilation System will be contaminated.
B.
The sludge tank will overflow to Radwaste with no additional consequences.
C.
This is the normal level for conducting a backwash and there will be no consequences.
D.
A Sludge Tank High Level alarm will alert the operator to the problem prior to other adverse consequences.
Proposed Answer: A Justification:
A is correct - level will exceed 4.5' during the backwash flooding the RB vent system. B is incorrect - overflow will occur, but not before RB Vent is flooded. C is incorrect - Tank level should be low at start
-1.3'.
D is incorrect-This transmitter is the only one on the tank AND the high level alarm is at 5.2' which is above the level where RB ventilation floods.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
ARP-SFP-1-6; N1-OP-6;P&ID C-18008-C K/A:
233000 Fuel Pool K1.14, Knowledge of the physical connections and/or cause-effect Cooling and relationships between FUEL POOL COOLING AND CLEAN-UP and Cleanup the following: Reactor building ventilation 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank#
Modified Bank#
New 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 #
3 K/A #
233000 Importance Rating 2.8 Proposed Question: RO 087 The plant is in an outage, with the following:
The core is offloaded and the cavity is drained A loss of Instrument Air to the Spent Fuel Pool Cooling (SFP) system occurs Which one of the following identifies the effect on Spent Fuel Pool Temperature and identifies an action to mitigate?
Effect on temperature A.
Lowers B.
Lowers C.
Rises D.
Rises Action to miti ate Remove a SFP rom service Reduce Shutdown Cooling (SDC) flow Feed and Bleed using fire hoses and the main Place an additional SDC loop in service Proposed Answer: C Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-ODP-OPS-0108, N1-SOP-6 K/A:
233000 FUEL A2.15: Ability to (a) predict the impacts of the following on the FUEL POOL COOLING POOL COOLING AND CLEAN-UP; and (b) based on those AND CLEAN-UP predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High system temperature 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Justification:
C correct - fuel pool cooling pumps trip on a loss of air which will cause pool temperature to rise, feed and bleed is available A incorrect - pool temperature will rise, if air system effect on the RBCLC supply to SFP heat exchanger is not understood (fails as is) and pump trip is not recognized could be selected B incorrect - pool temp will rise, shutdown cooling flow has no impact with cavity drained D incorrect - temp will rise but SDC has no effect with the gates installed.
Examination Outline Cross-reference:
3 3
Group #
K/A#
2.1.18 2.1.18 Importance Rating 2.9 3.0 Proposed Question: RO 088 SRO 086 Which one of the following describes the CSO/RO response to an expected control room annunciator alarm received for the second time?
Scan panels to identify...
A.
associated plant parameter, acknowledge with pushbutton, report annunciator name to the CRS.
B.
associated plant parameter, acknowledge with pushbutton, perform associated ARP actions.
C.
as the only alarm, acknowledge with pushbutton, perform associated ARP actions, if required.
D.
as the only alarm, acknowledge with pushbutton, report "Expected alarm" to the CRS.
Proposed Answer: C Justification:
C correct - per Ops Manual, section 3.3.5.B. A incorrect - this is the response to a plant transient alarm, per section 3.3.5.D. B incorrect a hybrid from various sections of this OM part. D incorrect - correct response for the first time an expected alarm is received.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Operations Manual, Section 3.3.5 K/A:
Generic 2.1.18 2.1.18: Ability to make accurate, clear, and concise logs, records, I
status boards, and reports 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New 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#
2.1.9 2.1.9 Importance Rating 2.5 4.0 Proposed Question: RO 089, SRO 087 The plant is operating at power, with the following:
A rod sequence exchange is in progress An RO candidate is present to perform a control rod reactivity manipulation for qualification The candidate has just selected a rod to be moved The ATC RO notices the wrong rod is displayed as selected on the F Panel, but has not yet been moved Which one of the following describes the ATC RO's required action?
Direct the candidate to...
A.
stop and back away from the E Panel.
B.
stop, self-check again, and re-select the correct rod.
C.
verify the selected rod against the RMR form for the sequence exchange.
D.
verify the rod selected display on the F Panel against the same display on the E Panel.
Proposed Answer: A Justification:
A correct - per Ops Manual, Section 3.3.8.j.4. BICID incorrect - each of these lack the 'positive trainee control' expected anytime an evolution goes wrong.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ops Manual 3.3.8.j.4 K/A: I Generic 2.1.9 2.1.9: Ability to direct personnel activities inside the Control Room 10 CFR Part 55 Content:
55.41(10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
3 Group #
K/A#
2.1.31 Importance Rating 4.2 Proposed Question: RO 090 The plant is operating at 100% power, with the following:
13 FW FCV is in AUTO RPV Level is 73 inches and stable Power is reduced to 90%, and the following is observed:
The deviation meter on thel 3 FW FCV indicates to the right of center RPV Level is 73 inches and stable Which one of the following explains the 13 FW FCV indications?
FCV INDICATIONS A.
Unexpected B.
Unexpected C.
Expected D.
Expected REASON The AUTO signal to 13 FCV has lowered The AUTO signal to 13 FCV has risen The AUTO signal to 13 FCV has lowered The AUTO signal to 13 FCV has risen Proposed Answer: C Justification:
C is correct-the power reduction would cause the 13 FCV to close to control water level thereby generating a difference between the auto and manual FCV signals AIB are incorrect as the unbalancing isan expected response D is incorrect since the AUTO signal would have risen not lowered in response to the power change Proposed references to be provided to applicants during examination: None Te I
e K/A:
Generic 2.1.31 2.1.31:,Ak6ility to locate control room switches, control and indication4 do deterr i`e ta
ý or~y.4'_plant lineup 10 CFR Part 55 Content:
55.41()-
X 55.43 55.45 t
Question Source:
Bank #
Modified Bank #
New X
History
\\
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2
Examination Outline Cross-reference:
3 3
Group #
K/A#
2.2.2 2.2.2 Importance Rating 4.0 3.5 Proposed Question: RO 091, SRO 090 A normal plant heatup is in progress, with the following:
Reactor pressure is 800 psig FW Pump 12 is feeding the RPV when its FqCjgisopen RPV water level rises to +105" before the operator trips the pump 15 minutes later, level lowers to +75" and continues to slowly lower Which of the following describes the only actiksrecessary to restore feed to the RPV with FW Pump 11?
A.
Position the FW Pump 11 control switch to START.
B.
Position the FW Pump 11 control switch to STOP, then to START.
C.
Bypass/ then Normal the High Level Trip, then position the FW Pump 11 control switch to START.
D.
Bypass/ then Normal the High Level Trip, position the FW Pump 11 control switch to STOP, then to START.
Proposed Answer: C Justification:
C is correct-The hi level trip logic actuated and must be reset. A is incorrect - The hi level trip logic must first be reset. BID are incorrect The STOP manipulation resets HPCI auto start logic under certain conditions and is not a function of resetting the high level trip.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
01-OPS-001-259-1-01 K/A:
Generic 2.2.2 2.2.2. Ability to manipulate the console controls as required to I
operate the facility between shutdown and designated power levels 10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group #
K/A #
Generic Generic 2.2.24 2.2.24 Importance Rating 2.6 3.8 Proposed Question: RO 092, SRO 091 The plant is operating at 100% power, with the following:
TIME CONDITION 0100 Containment vent and purge valve High Drywell Pressure isolation logic Channel 1 passes its surveillance test and is returned to normal 0100 Channel 2 is placed in test 0200 Channel 2 fails its surveillance when its trip setpoint is found out of spec high 0300 Channels 3 and 4 have passed their surveillance and have been returned to normal Which one of the following identifies the time at which the Technical Specification LCO clock should be started for the inoperable channel?
A.
0100 B.
0200 C.
0700 D.
0800 Proposed Answer: A Justification:
A is correct-Channel goes to inop status at the time it's placed in test. Since it failed its test, it remains in test, and therefore remains inoperable. Direction is provided at the beginning of STs to declare equipment inop when it is rendered inop by the ST (e.g., channel is placed in test). B is incorrect - By this time, the channel has already been inop for an hour. C is incorrect - This is plausible only if examinee believes the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AOT extends the operability status of the channel. D is incorrect - This plausible if the examinee believes the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AOT extends operability status beyond time where failed surveillance is discovered; presumably because the channel is still in test.
I Proposed references to be provided to applicants during examinatior(-T.S. 3.6.2
'*A.-C' Technical Reference(s):
TS 3.6.2//
V KA:
I Generic 2.2.24 2.2.24, Ability to analyze the effect of maintenance activities on LCO status 10 CFR Part 55 Content:
55.41(10)
X 55.43 (3)
X 55.45 Question Source:
Bank #
Modified Bank #
X New History NMPI 1998 NRC EXAM, modified Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
Level RO Tier #
3 Group #
K/A #
2.2.33 Importance Rating 2.5 Proposed Question: RO 093 A control rod sequence exchange is in progress, with the following:
Reactor Power is 75%
Control Rod 26-27 is at position 14 Which one of the following Control Rods would be permissible to move from position 12 to position 18?
A.
Control Rod 22-27 Proposed Answer: B Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group #
K/A #
Generic Generic 1 2.4.47 2.4.47
__Importance Rating 3.4 3.7 Proposed Question: RO 094,SRO 096 The plant is operating at 100% power, with the following:
1-H1-4-3, SCREEN WASH PUMP-SCREEN TRIP-LO VOLT DIFF PRESS, alarms due to high screen differential A massive collection of weeds is at the intakes Local operator actions are complete Forebay level is about 1 foot low and is lowering Screen differential continues to rise Which one of the following describes the required operator action?
A.
If H1-4-2, R BUILDING SW PRESS SERV W PUMP HDR PRESS alarms, scram the reactor and initiate ECs.
B.
If H2-1-3, CIRCULATING WATER PUMP INTAKE LEVEL LOW alarms, scram the reactor and initiate ECs.
C.
Start ESW pumps, scram the reactor, initiate ECs, close MSIVs, attempt to restore normal Service Water flow and pressure.
D.
Secure one Circulating Water pump, reduce power for one Circulating Water pump operation, attempt to restore forebay level.
Proposed Answer: D Justification:
D is correct-This is the SOP-7 set of actions to reduce flow as much as practicable to; restore forebay level. ARP directs entry into SOP-7 if unable to clear the high diff alarm and there is a sustained lowering of forebay level. Stem conditions make it very clear this is the case. A/B are incorrect - there is nothing in either of these ARPs that shuts down the plant. Each directsthe
.operators to enter SOP-7. C is incorrect - these are the SOP-7 actions for loss of both SW pumps, or inability to restore normal SW header pressure.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-SOP-7; ARP H1-4-2, H2-1-3, Hl-4-3 K/A:
Generic 2.4.47 2.4.47. Ability to diagnose and recognize trends in an accurate and timely I
manner utilizing the appropriate control room reference material.
10 CFR Part 55 Content:
55.41(7)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History L_
-/
i Question Cognitive Level:
Memory or F-undamental K-,nowleoge CopeesoIrAayi r
Comprehension or Analysis X
Examination Outline Cross-reference:
3 3
Group#
K/A #
Generic Generic 1 2.3.2 2.3.2 Importance Rating 2.5 2.9 Proposed Question: RO 095, SRO 095 Ac rd-iigtbGAP-RPP-0 High Radiation/Locked High RadiationNery High Radiation Ar as, which one of the following describ the minimum controls requirements for rooms with p
or very high radiation levels?
Con rols shall be posted at the entrance, the room...
A.
locked at all times (except for entry/exit), fenced off (up to the overhead) when open and unguarded, and a conspicuous flashing light near the entrance B.
locked at all times (except for entry/exit), guarded when left open, and a conspicuous flashing light near the entrance C.
locked when practicable, and fenced off (up to the overhead) when open and unguarded D.
locked when practicable, and roped off when open and unguarded Proposed Answer: B Justification:
B is correct - per the GAP; these are the minimum requirements.
A/C/D - not per the GAP.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
GAP-RPP-08 K/A: I Generic 2.3.2 2.3.2, Knowledge of facility radiation ALARA requirements.
10 CFR Part 55 Content:
55.41(12)
X 55.43 55.45 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:
Level RO Tier #
3 Group#
K/A #
2.3.4 Importance Rating 2.5 Proposed Question: RO 096 You are assigned to conduct inspections of each FW Booster pump followed by completion of Turbine Building rounds, with the following:
A contaminated area is established around each FW Booster pump An inspection of the FW Booster pumps is required early in the shift The entry requirement for tours in each area is shoe covers and booties No active leaks exist in any of the areas Which one of the following describes the frisking requirements for your rounds?
Your first frisking is required upon exiting...
A.
each area B.
the second area C.
the last area D.
the Turbine Building Proposed Answer: C Justification:
C correct -frisking allowed to be done after last area on multiple area entries but upon exit from last area AIBID incorrect - in excess or not meeting GAP-RPP requirements Proposed references to be provided to applicants during examination: None Technical Reference(s):
GAP-RPP-01 K/A:
Generic 2.3.4 2.3.4: Knowledge of radiation exposure limits and contamination control/including permissible levels in excess of those authorized 10 CFR Part 55 Content:
55.41(12)
X 55.43 55.45 Question Source:
-Bank #
Modified Bank#
X New History NMPI,2000 audit Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Examination Outline Cross-reference:
3 3
Group #
K/A #
Generic Generic 2.4.24 2.4.24 Importance Rating 3.3 3.7 Proposed Question: RO 097, SRO 097 The plant is operating at 70% power with the following:
RBCLC Pump #11 is clearance tagged for repairs Powerboard 17B is clearance tagged for repairs A fire de-energizes Powerboard 16B Which one of the following describes the required operator action?
A.
Immediately scram the reactor and enter SOP-I.
B.
Enter N1-SOP-7, Service Water Failure/Low Intake Level C.
Reduce reactor power as low as possible without entering the R cted Zone.
/"D.
When one or more CaID accumulators a a e-*ri reactor and enter SOP-I.
Proposed Answer: C Justification:
C is correct -With RBCLC #11 0OS, and PB 17B OOS, only RBCLC pump #13 is runnrng at the time the fire takes away PB 16B. No RBCLC pumps running is a direct entry into SOR-8. An SOP-8 "required" action is to reduce power as low as possible without entering the IRZ. A is incorrect - PlaU-ible when the examinee recalls Xl that the PB 16B loss has just taken away his last CRD pump, aspwell. However, with reactor pressure > 900 psig, there is no need to scram until after 20 minutes without-CRD pressure, and~only witli an accumulator for a withdrawn rod in alarm. B is incorrect - Plausible to the examinee who recalls that the loss of PB 16B has also taken away his last Emergency Service Water Pump, and he believes this to be an ehtrynto SOP-7. D is incorrect - Similar to justification for A, above. In this case, however, the 20-minute clock has not yet expired.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-SOP-8 K/A: I Generic 2.4.24 2.4.24. Knowledge of the loss of cooling water propedure.
10 CFR Part 55 Content:
55.41(7)
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:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group#
K/A #
2.4.5 2.4.5 Importance Rating 2.9 3.6 Proposed Question: RO 098, SRO 098 The plant is operating at 100% power, with the following:
ERV 113 sticks open Efforts to close the ERV have failed Reactor is manually scrammed EOP-2 is entered on RPV low level ERV 113 closes and is confirmed closed Torus temperature is 80° E-and rising slowly CRS directs the Control Room 'E' to place torus cooling in service Which one of the following identifies the procedure used for placing a loop of torus cooling in service?
A.
N1-EOP-4, Primary Containment Control B.
N1-EOP-1, Attachment 16, Torus Cooling C.
N1-ARP-L1-4-4, Drywell - Torus Temp High D.
N1-OP-1 4, Containment Spray Proposed Answer: D Justification:
D correct - Off-Normal Section H.0 must be used when EOP-4 has not been entered. Given these conditions, only EOP-2 has reason to be entered. No EOP-4 entry conditions exist. With ERV closed, and torus temp rising slowly thru 80 F, temp will turn before 85 F. If torus cooling is to begin, now, it must be aligned IAW the OP. N/B incorrect - EOP-4 not yet entered;can't get to EOP-1, Att.16 except thru EOP-4. C incorrect - This ARP monitors DW/Torus air space temps, not Itorus water temp.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ops Manual NMP1 EOP User's Guide K/A:
Generic 2.4.5 2.4.5. Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions 10 CFR Part 55 Content:
55.41(10)
X 55.43 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group #
K/A #
2.4.27 2.4.27 Importance Rating 3.0 3.5 Proposed Question: RO 099, SRO 099 A plant SCRAM has occurred, with the following:
An electrical fire is burning in Battery Room 12 Reactor Pressure is being controlled 700 to 800 psig on the5EC' Which one of the following identifies the preferred instruments to monitor Reactor Pressure and EC Water Level?
REACTOR PRESSURE A.36-31A B.36-31A C.36-32A D.36-32A EC WATER LEVEL 121/122 111/112 121/122 111/112 Proposed Answer: B Justification:
B is correct-per table 9.3. AIC/D are incorrect-different combinations of either non-preferred reactor press instrument or EC water level instruments or both.
Proposed references to be provided to applicants during examination: SOP-9, FIRE IN P T,
Flowchart Technical Reference(s):
N1-SOP-9 K/A: I Generic 2.4.27 2.4.27 Knowledge of fire in the plant procedure.
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:
2 Comments: None
Examination Outline Cross-reference:
3 3
Group #
K/A #
2.4.22 2.4.22 Importance Rating 3.0 4.0 Proposed Question: RO 100, SRO 100 An override in the level control leg of EOP-3 provides direction to terminate and prevent injection to the RPV except CRD and Boron.
Which one of the following is the basis for this action?
A.
Reduce power to within bypass valve capacity B.
Achieve faster reactor shutdown by concentrating the liquid poison C.
Prevent instabilities and to reduce reactor power D.
Ensure that HCTL will not be exceeded before liquid poison can be initiated Proposed Answer: C Justification:
C correct - per the EOP bases A incorrect - Not a consideration (bypass valves may be unavailable) B incorrect - Not a consideration D incorrect - Not an assured response Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-ODP-PRO-0305 K/A:
Generic 2.4.22 2.4.22: Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations 10 CFR Part 55 Content:
55.41(5)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
U.S. Nuclear Regulatory Commission Site-Specific Written Examination Aoolicant Information Name:
Region I
Date:
September 30, 2002 Facility/Unit:
Nine Mile Point Unit 1 License Level SRO Reactor Type:
GE BWR-2 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 paper will be collected six hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither nor received nor received aid.
Applicant's Signature Results Examination Value:
100 Points Applicant's Score Points Applicant's Grade Percent NUREG-1021, Revision 8, Supplement 1
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
1 K/A #
295017 Importance Rating 4.2*
Proposed Question: SRO 013 The plant is operating at 100% power, with the following:
1 H1-1-8, STACK GAS MONITORS HIGH RADIATION, alarms C062 OGESMS RADIATION LEVEL HIGH is in alarm The OGESMS monitor on J panel is reading just above the alarm setpoint.
Which one of the following describes the action required based on the Offsite Release?
A.
E-plan entry is required B.
Offsite Release LCO entry is required C.
Have Chemistry calculate the actual Offsite Release D.
Place RBEVS in service Proposed Answer: C Justification:
C correct - LCO release rate may be being exceeded. Chemistry sample and calculation is required to make such determination A incorrect - Not a confirmed alarm AND not near E-plan level B incorrect - alarm is not confirmed D incorrect - referenced action in ARP but only if an initiating condition is met Proposed references to be provided to applicants during examination: None Technical Reference(s):
ARP-Hl-1-8 K/A:
295017 High Off-AA2.01 - Ability to determine and interpret the followi g as they apply I site Release Rate to High Off-site Release Rate: Off-site release rate 10 CFR Part 55 Content:
55.41(7,12)
X 55.43 (4) 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
Level SRO Tier #
1 Group#
1 K/A #
295017 Importance Rating 3.7 Proposed Question: SRO 014 /
The plant is operating at 100% 1ith the following:
Og becomes unavailable
- Power operation is to continuec With no erator action, of the following describes the potential problem pe Tech S p e c b a s e s ?
p A.
Gross fuel failure detection and MSIV closure capability will be impaired B.
Child thyroid doses at the site boundary could exceed 1 OCFR limits during normaI operations C.
Buildup of fission product activity in station systems could go undetected D.
Child thyroid doses at the site boundary could exceed 10CFR limits on a steam line brea Proposed Answer: C Justification:
C correct-Main purpose specified on page 312 of tech specs. A incorrect - Done based on MSL Rad monitor reading 3.75 X NFPBB incorrect - monitored by stack monitor, not Offgas rates would be, exceeded if offgas were bypassed. D incorrect - Basis for MSIV; closure at 3.75 X NFPB on MSL RAD Monitor Proposed references to be provided to applicants during examination: TS 3.6.14 and 3.6.15 Technical Reference(s):
Tech spec bases page 312, TS Table 3.6.14-2 K/A:
295017 High Off-2.2.25 - Knowledge of bases in technical specifications for limiting I site Release Rate conditions for operations and safety limits 10 CFR Part 55 Content:
55.41(7,12)
X 55.43 (2,4) 55.45 Question Source:
-Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
1 K/A #
295023 Importance Rating 4.6 Proposed Question: SRO 015 Core alterations are in progress, with the following:
A control rod blade has been pulled above the hoist up-limit stop and is stuck there Refuel floor has been evacuated Fuel Pool High Range Rad Monitor is reading 7 x 103 mr/hr RBEVS has automatically initiated
/
Which one of the following describes the required EAL declaration?
A.
1.4.1 B.
1.4.2 C.
1.4.3 D.
1.4.4 Proposed Answer: A Justification:
A is correct-With the high range monitor at 7 r/hr then the low range monitor (table 1) would be offscale BIC/D lack one or more conditions to be applicable Proposed references to be provided to applicants during examination: EAL Flowchart Technical Reference(s):
EPIP-EPP-01 K/A:
295023 Refueliný AA2.05 - Ability to determine and interpret the following as they apply Accidents to Refueling Accidents: Entry conditions of emergency plan 10 CFR Part 55 Content:
55.41 55.43 (4,7)
X 55.45 (11)
X Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
\\
Examination Outline Cross-reference:
Level SRO Tier# *1 Group #
1 K/A #
295030 Importance Rating 3.8 Proposed Question: SRO 020 Technical Specifications requires a normal plant shutdown when all 3 of the following conditions exist for more than 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Torus downcomer submergence is below the minimum allowable Torus water temperature is above 850F-Reactor coolant temperature is above 2150 F Which one of the following identifies the minimum allowable downcomer submergence and describes the basis for the 2150 F value?
MINIMUM SUBMERGENCE A.
3.5 feet B.
4.25 feet C.
3.5 feet D.
4.25 feet Proposed Answer: C BASIS FOR 2150 F An ERV discharge will not result in a damaged tailpiece An ERV discharge will not result in a damaged tailpiece A blowdown will not challenge the torus design pressure limit A blowdown will not challenge the torus design pressure limit Justification:
C is correct - TS 3.3.2 LCO specifies the LCO and 24 action when > 215 F. Min allowable submergence is 3.5', max allowable is 4.25'. Basis for LCO justifies the 215 F value. BID are incorrect - 4.25 is max allowable submergence. A is incorrect - plausible if candidate confuses the min torus level required for ensuring adequate downcomer submergence with a high torus level that challenges the ERV Tailpipe Level Limit of the EOP Bases.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ts 3.3.2, with Bases; N1-OP-1 4, D.2.0 P/L K/A:
295030 Low 2.1.32 -Ability to explain and apply system limits and precautions Suppression Pool Water Level 10 CFR Part 55 Content:
55.41(5,10)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
I K/A #
295003 Importance Rating 4.1 Proposed Question: SRO 0211*
The plant is operating at 100% with the following:
K PB-i 03 is deenergized for bus repairs A transformer fault on reserve transformer 101 N occurs After 15 minutes, which one of the following describes the EAL that should be declared?
A.
6.1.1 B.
6.1.2 C.
6.1.3 D.
6.1.4 Proposed Answer: C Justification:
C correct-power is lost to T101N and T101S is not available with PB 103 0OS. No backfeed alignment has been made, only DG 102 is available B incorrect - plant is in Mode 1 A incorrect - conditions are met but higher classification (6.1.3) should be declared D incorrect DG 102 is available and PB 102 should be energized Proposed references to be provided to applicants during examination: EAL Flowchart Technical Reference(s):
EPIP-EPP-01 K/A:
295003 Partial or Generic 2.4.41 - Knowledge of the emergency action level threshold Complete Loss of and classification AC Pwr 10 CFR Part 55 Content:
55.41()
55.43 (5)
X 55.45()
Question Source:
-Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Examination Outline Cross-reference:
1 Group#
1 K/A #
295024 Importance Rating 4.0 Proposed QUes SRO 0 The plant ia
- ower, h n a steam leak in the drywell occurs, with the following:
RPV pressur 00 psig A-
- RPV level 26" Drywell pressure 7 psig L)/*j NE*v Torus pressure p 'g
- Torus temperature i
- Torus level Which one of the following is required?
A.
Vent the Drywell via RBEVS per EOP-1 Attachment 10.
B.
Emergency Depressurize per EOP-8 C.
Start all Drywell Cooling Fans D.
Initiate Containment Sprays per EOP-1, Attachment 17 Proposed Answer:
D Justification:
D is correct-Torus pressure is above 13 psig requiring sprays A incorrect-Not possible because drywell pressure is above 3.5 psig B incorrect-PSP is not exceeded C incorrect-EOP-4 directs tripping the fans to spray containment.
Proposed references to be provided to applicants during examination: EOP Flowcharts Technical Reference(s):
N1-EOP-4 K/A:
295024 HIGH 2.1.23. HIGH DRYWELL PRESSURE: Ability to perform specific DRYWELL system and integrated plant procedures during different modes of PRESSURE plant operation cooling: Plant-Specific 10 CFR Part 55 Content:
55.41 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank#
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
2 K/A #
295001 Importance Rating 3.3 Proposed Question: SRO 027 The plant is operating at 90% power, with the following:
5 Recirc Loops are operating Recirc Pump 14 trips Recirc Pump 14 discharge valve cannot be closed Which one of the following describes the initial action the CRS shall direct the RO to perform, and the impact of that action on Technical Specifications?
DIRECT THE RO TO...
A.
Close the suction valve B.
Close the suction valve C.
Close the suction and bypass valves D.
Close the suction and bypass valves TECH SPEC IMPACT Flow-Biased Scram/Rod Blocks are now operable Suction valve is inoperable Flow-Biased Scram/Rod Blocks are now operable Discharge valve is inoperable Proposed Answer: A Justification:
A correct - OP-1 directs suction valve be closed to stop all flow thru pump. Once closed, the APRM Flow-biased trip setpoints are no longer INOP (i.e., no longer have reverse flow thru pump causing non-conservative flow-biasing of the APRM scram and rod block setpoint. B incorrect - Suction valve being closed has no bearing on T.S. CID incorrect - Only when if it is later decided to completely isolated loop 14 and return the plant to rated power will OP-1 require that the pump bypass valve be closed as well.
Proposed references to be provided to applicants during examination: None K/A:
295001 Partial or AAr3 to d etermine and/or interpret the following as they~ply to PARTIAL Complete Loss of Foce Core Flw
- E LOSS OF FORCED CORE FLOW CIRCUý90:Ncerbie Circulation A
10 CFR Part 55 Content:
--6-5.-41 (7)
X 55.45 Question Source:
Bank #
Modified Bank#
New X
History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None 2
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
2 K/A #
295018 Importance Rating 3.9 Proposed Question: SRO 033 The plant is Refuel, with the following:
A loss of all RBCLC pumps has occurred Reactor Coolant temperature is 139F and rising Core offload is in progress Which of the following describes actions that should be taken for decay heat removal and the need to determine Time to Boil?
Feed and Bleed...
A.
SFP B.
SFP C.
RPV D.
RPV Prnnnt1 Anwr:
D
. - f.,---...-
Determine Time to Boil No Yes No Yes Justification:
D is correct - per N1-SOP-20, with no SDC/SFP cooling (No RBCLC) and coolant temperature likely to exceed 140 F then time -to boil calc required AND with offload in progress communication exists between the RPV and SFP so only the RPV is directed to be Feed and Bled AIC are incorrect - Time to boil calc is required (exceed 140F likely)
B is incorrect - communication between RPV/SFP exists (offload in progress) so per SOP only RPV feed and bleed Proposed references to be provided to applicants during examination: N1-SOP-20 Technical Reference(s):
N1-SOP-20 K/A:
295018 Partial or Generic 2.4.9 - Knowledge of low power/shutdown implications in Total Loss of accident (eg. LOCA or loss of RHR) mitigation strategies CCW 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3
- L
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
2 K/A #
295028 Importance Rating 4.2 Proposed QLng, Trips of/owerboards results in a loss of Drywell Cooling, w h the following:
Drywell Humidity is 40%/*
- Drywell Temperature i 299 0F Torus Pressure is 2 p 'g---_
Drywell Pressure is 2.5 sig Torus level is 1)'
Powerboard recovery is imminent Which one of the following is required per EOP-4?
A.
Lockout Containment Spray B.
Initiate Containment Spray C.
Perform an RPV Blowdown D.
Initiate Containment Venting Proposed Answer: A Justification:
A correct -Containment spray is not allowed since DW pressure and temperature are on the bad side of Figure K B incorrect - Containment spray is not allowed since DW pressure and temperature are on the bad side of Figure K C incorrect-RPV Blowdown is not required until powerboard/drywell cooling recovery will not be possible D incorrect-conditions do not warrant venting (pressure is low)
Proposed references to be provided to applicants during examination: EOP Flowcharts Technical Reference(s):
N1-EOP-4 K/A:
295028 High EA2.04 - Ability to determine and interpret the following as they apply Drywell to High Drywell Temperature: Drywell pressure Temperature 10 CFR Part 55 Content:
55.41(7)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments:
None
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
2 K/A #
295034 Importance Rating 4.2 Proposed Question: SRO 039 The plant is stable following a scram, with the following:
Several Fire alarms initiate in the Reactor Building RBEVS initiates on high ventilation radiation Both Reactor Building vent rad monitors are reading similar Reactor pressure begins to lower Which one of the following describes the event, as it would be applied to emergency procedures?
A.
A fire has occurred involving radioactive materials B.
A fire has occurred along with radiation detector failures C.
A non-primary system is discharging D.
A primary system is discharging Proposed Answer: D Justification:
D correct -high temp/humidity from steam will cause fire alarms, elevated vent rad caused by gaseous and particulate from reactor coolant AND only a primary system would cause a corresponding reduction in RPV pressure A/BIC are incorrect -none of these events would account for the lowering reactor pressure Proposed references to be provided to applicants during examination: None Technical Reference(s):
NI-ODP-PRO-0305, page 221 K/A:
5034 EA2.02 - Ability to determine and interpret the following as they apply econdary to Secondary Containment Ventilation High Radiation: Cause of high ontainment f
oels entilation Hig adiation
)
10 CFR r
t 55 C ent:
55.41(7,10)
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:
2 Comments:
None
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
2 K/A #
295034 Importance Rating 3.6 Proposed Question: SRO 040 A plant transient has occurred, with the following:
"* Reactor Building (RB) Vent radiation rose to 8 mr/hr
"* Multiple temperature and fire alarms were received in the RB Initial actions are taken to stabilize the plant and limit leakage into the RB, resulting in:
"* Reactor Building Vent radiation lowers to 3 mr/hr
"* Further access into the RB is required to isolate the leaking components Which one of the following describes the required action and bases for that action?
ACTION BASES A.
Verify RB isolated/EVS running Provide for filtered release B.
Verify RB isolated/EVS running Maximize RB air flow C.
Restart RB Ventilation/Shutdown EVS Provide for filtered release D.
Restart RB Ventilation/Shutdown EVS Maximize RB air flow Proposed Answer: D Justification:
D correct -with RB vent rad <5 mr/hr step SC-2 requires restart of RB vent to maximize RB air flow A incorrect - this is the action/reason for RB vent rad > 5 mr/hr BIC are incorrect -combinations of actions/reasons that one or both are not appropriate for the conditions Proposed references to be provided to applicants during examination: N1-EOP-5 Technical Reference(s):
NI -ODP-PRO-0305/ page 224, N1 -EOP-5/step SC-2 K/A:
295034 Generic 2.4.18 - Knowledge of the specific bases for EOPs Secondary Containment Ventilation High Radiation 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level: I Memory or Fundamental Knowledge I
5 slý'
Examination Outline Cross-reference:
Level SRO Tier #
1 Group #
2 K/A #
600000 Importance Rating 3.6 Proposed Question: SRO 042 The plant is at 100% power, with the following:
DG 102 is running for monthly testing A loud bang is heard and heavy smoke fills the DG room The DG trips and the smoke dissipates 10 minutes after the loud noise the room is entered and the DG is observed to be damaged but no fire is observed
/
Which one of the foflowing identifies when NRC is required to be notified of this event?
Notify the NRC within...
A.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D.
30 Days Proposed Answer: A Justification:
A correct - EAL 8.2.2 is met as DG 102 is unavailable as a result of a fire/explosion B/ICD are incorrect-any emergency declaration requires NRC notification within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Pro osed references to0 e provided to applicants during examination: EAL Flowchart, I l*FR50.72 and 73
/
- _P_*
)
,/**.
Fch nical ReferenceW:
I K/A:
lant Fire 2.4.30 - Knowledge of which events related to system On Site operations/status should be reported to outside agencies 10 CFR Part 55 Content:
55.410 55.43 (5)
X 55.45()
Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments: None
Examination Outline Cross-reference:
Level SRO Tier #
2 Group #
1 K/A #
212000 Importance Rating 2.4.21 Proposed Question: SRO 048 The plant is operating at 100% power, with the following:
Required surveillances for MSIV 112 position input to RPS are determined as due All other MISV position indication surveillances are up to date The surveillances will take 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to complete Which one of the following is required?
A.
Complete the required surveillances B.
Close MSIV 112 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C.
Trip RPS 11 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D.
Trip RPS 12 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Proposed Answer: A Justification:
A correct - per TS table 3.6.2.a, note (o), required channels can be taken o t of service for surveillances for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if redundant parameter monitoring is pro ided in the trip system. With MSIV 111 position indication operable and only one inp is required to trip RPS 11 the requirement is met. B incorrect - required action if M V inoperable combined with time allowed to conduct surveillance CID are incorrect -
ctions required if redundant trip capability in RPS trip system not functional jad/or wrong trip system Proposed references to be provided to applicants during examin n:
able 3.6.2.
Technical Reference(s):
'Jable 3.6.0.
O1-OPS 1-212-1-01/p ge 16 K/A:
212000 RPS 2.4.21: Knowledge of the parameters and logic use-dto assess the status of safety functions including:
- 1. Reactivity control
- 2. Core cooling and heat removal
- 3. Reactor coolant system integrity
- 4. Containment conditions
- 5. Radioactivity release control.
10 CFR Part 55 Content:
55.41(7)'
55.43 55.45 Question Source:
-Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 0
I
Examination Outline Cross-reference:
Level SRO Tier #
2 Group #
1 K/A #
216000 Importance Rating 4.0 Proposed Question:
055 An MSIV closure sults in a failure of control rods to i sert, with the following:
Reactor power is 14% and owering due to liquid poison injection An RPV level band between -106" to -131" has been directed Power lowers to 8%, which one of the following level bands should be directed?
A.
-53" to -96" B.
-63" to -106" C.
-94" to -119" D.
-96" to -121" Proposed Answer: D Justification:
D correct-Per Detail X of EOP-3, 8% with goal of-84 to -109 A/BIC incorrect - different combinations of incorrect goals and power levels Proposed references to be provided to applicants during examination: EOP Flowcharts Technical Reference(s):
EOP-3 K/A:
216000 G2.4.6 Knowledge symptom based EOP mitigation strategies.
NUCLEAR BOILER INSTRUMENTAT ION 10 CFR Part 55 Content:
55.41 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: None
Examination Outline Cross-reference:
Level SRO Tier #
2 Group #
1 K/A #
223002 Importance Rating 4.0 Proposed Question: SRO 056 A plant transient results in simultaneous entry into both EOP-2 and EOP-4, with the following:
E/eactor water level drops rapidly then recovers
(
s auto-initiate and control RPV pressure along with MSIV closure Reactor water level is then maintained using Feedwater onme F-uel Zone instruments Which one of the following describes the isolations that should be verified per the EOP's (VESSEL/CONTAINMENT)?
VESSEL ISOLATIONS A.
Required B.
Not Required C.
Required D.
Not Required Proposed Answer: A CONTAINMENT ISOLATIONS Required Required Not Required Not Required Proposed references to be provided to applicants during examination: EOP Flowcharts, N1-SOP 17 Technical Reference(s):
N1-EOP-2/step L-l, N1-SOP-1 7/page 2 K/A:
223002 Generic 2.4.6 - Knowledge of symptom based EOP strategies PCIS/Nuclear Steam Supply Shutoff 10 CFR Part 55 Content:
55.41(10)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 0
0
0 Justification:
A is correct - per SOP-1 7( which is used by EOP-2 to verify isolation) if level drops below 5 inches (indicated by MSIV/EC response and choice of level instrument) then both vessel and containment isolation verifications are required B is incorrect -both are required but could be chosen if only high drywell pressure is diagnosed (both EOP-2 and 4 entered together). CID are incorrect - both isolation verifications are required for situation
Examination Outline Cross-reference:
Level SRO Tier #
2 Group #
1 K/A #
226001 Importance Rating 4.0 Proposed Question: SRO 057 A LOCA has occurred, with the following:
ADS has initiated and Core Spray is controlling RPV level Only Containment Spray pump 111 is available Drywell pressure is 14 psig and rising Drywell temperature is 260F and rising Torus Pressure is 13.8 psig and rising Torus water temperature is 95F and rising Torus water level is 11.5 feet and stable Which one of the following actions should be taken with Containment Spray pump 111 ?
A.
No actions are warranted B.
Initiate Containment Sprays C.
Initiate Torus Cooling D.
Pump Torus Water to Waste Collector Proposed Answer: B Justification:
B is correct - with the RPV already depressurized and Torus level <13.5 feet AND only one contain spray available, initiating containment spray to reduce containment pressure should be accomplished A incorrect - multiple possible actions could be taken with the one available CT Spray pump C is incorrect - Containment spray is an alternate torus cooling path and is more desirable than just torus cooling D is incorrect
- not as high a priority as CT spray since next action point is 13.5 feet Proposed references to be provided to applicants during examination: EOP Flowcharts Technical Reference(s):
NI-EOP-4 K/A:
226001 Generic 2.4.22 - Knowledge of the bases for prioritizing safety RHR/LPCI:
functions during abnormal/emergency operations CTMT Spray Mode 10 CFR Part 55 Content:
55.41(7,10)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank#
New NEW History
Examination Outline Cross-reference:
Level SRO Tier #
2 Group #
2 K/A #
202001 Importance Rating 3.7 Proposed Question: SRO 069 The plant is operating, with the following:
Three Recirc loops are operating, with two isolated
° Reactor power is 91%
Which one of the following describes the bases for not continuing operation at this power level?
A.
LOCA analyses*wW yield higher peak clad temperatures in this configuration.
B.
The margin between the MCPR Safety Limit and the Limiting Safety System Setting is reduced in this configuration.
C.
MCPR analyses,i~k&show higher peaking due to flow unbalance in this configuration.
D.
Cold start of a loop 7 exceedi4the MCPR limit.
Proposed Answer: A Justification:
A correct - TS 3.1.7 bases identifies smaller coastdown inventory as reducing LOCA cooling and raising peak clad temperature B incorrect
- nonsense unless candidate doesn't understand interrelations C incorrect - nonsense unless candidate doesn't understand flow baffle configuration D incorrect - This is 4 loop unisolated basis.
Proposed references to be provided to applicants during examination: None Technical Reference(s):
TS 3.1.7 bases (pg 73)
K/A:
202001 Generic 2.2.25 - Knowledge of the bases in technical specifications Recirculation for limiting conditions for operations and safety limits 10 CFR Part 55 Content:
55.41(7)
X 55.43 (2)
X 55.45 Question Source:
-Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
3 Comments: None
Examination Outline Cross-reference:
Level SRO Tier #
2 Group #
3 K/A #
201003 Importance Rating 3.3 Proposed Question: SRO 081 Control rod movements are in progress, with the following:
The third of ten rods on a control rod movement sheet is being repositioned The target position for the control rod is 14 from 18 The control rod is inserted to position 12 Which one of the following describes the EARLIEST discovery of this control rod positioning that would require notification of both Reactor Engineering and the General Supervisor Operations per N1-OP-5?
Would require notification if found by the...
A.
Independent Verifier at the end of the mc B.
Independent Reviewer at the end of the move shE 7
C.
STA on turnover at the end of shift D.
Reactor Engineering the following day Proposed Answer: C Justification:
C is correct - this is a mispositioned control rod requiring GSO notification and RE notification. AIB are incorrect - per OP-5, H.4.1, control rod misposition not reportable if caught during use of control rod move sheet D incorrect - would require notification but is not the EARLIEST Proposed references to be provided to applicants during examination: None Technical Reference(s):
N1-OP-5, H.4 K/A:
201003 Control Generic 2.1.14 - Knowledge of system status criteria which require Rod and Drive the notification of plant personnel Mechanism 10 CFR Part 55 Content:
55.41(10)
X 55.43 (5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History
Examination Outline Cross-reference:
Level SRO Tier #
3 Group #
K/A #
Generic 2.1.11 Importance Rating 3.8 Proposed Question: SRO 084 A plant startup is in progress, with the following:
Reactor power is 85%
Core Flow is 77%
Recirc Flow control is in automatic MCPR is determined to be 1.50 Which one of the following describes when the first action is required?
A.
15 Minutes B.
30 Minutes C.
2 Hours D.
No action is required Proposed Answer: A Justification:
A is correct-per the COLR the required value of MCPR at 77%
flow/AUTO is 1.45 x 1.1=1.59, with MCPR not in compliance action is required to be initiated within 15 minutes B is incorrect-not a referenced time limit of MCPR spec C is incorrect-is the second action time of MCPR spec D incorrect-action is required but if Kf is not applied would be the chosen answer Proposed references to be provided to applicants during examination: TS 3.1.7, COLR Technical Reference(s):
TS 3.1.7.c, COLR 2.1/Fig 25 K/A:
Generic 2.1.11 2.1.11: Knowledge of less than one hour te hnical specification action I
statements for systems 10 CFR Part 55 Content:
55.41 55.43 (2)
X 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 vi
q
Examination Outline Cross-reference:
Level SRO Tier #
3 Group #
K/A #
Generic 2.1.12 Importance Rating 4.0 Proposed Question: SRO 085 0)'
The plant is operating at 1 000/ý-l0ower followin refueling outage, with the following:
A review of sta valve ine-ups and logs is being conducted Position of val 05-10 V-EC VENT TO TORUS MANUAL AFT4(05-0 questioned Investigation revl hat valve 05-10 is stuck closed Which one of the following describes the action required to support continued power operations?
Valve 05-10 must be opened within...
A.
1 Hour B.
7 Days C.
14 Days D.
30 Days Proposed Answer: C Justification:
C is correct - the vent path to the Torus for both EC's is isolated requiring restoration of at least one within 14 days B incorrect - This would be chosen if one EC loop was believed INOP A is incorrect This would be required if both EC's were INOP or the valve could not be opened within 14 days D is incorrect-Tobiswuld be the time allowed if only one EC were affected
/'
V Proposed references to be provided to applicants during examinati n: TS 3.1.3\\
V Technical Reference(s):
TS 3.1.3, DWG C-1 8017-C K/A: I Generic 2.1.12 2.1.6: Ability to apply technical specifications for a system 10 CFR Part 55 Content:
55.41 55.43 (2,5)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
3 Comments:
None
(
Proposed Question: SRO 088 A core shuffle is in progress, with the following:
A Fuel Bundle is inserted into the correct core location The fuel bundle is misoriented Which one of the following describes the category of fuel movement event and the action that should be taken concerning continuing with fuel movements?
EVENT CATEGORY STOP FUEL MOVES?
A.
Fuel Loading error (FLE)
Yes B.
Fuel Movement Discrepancy Yes C.
Fuel Loading error (FLE)
No D.
Fuel Movement Discrepancy No Proposed Answer: B Justification:
B is correct - misorientation is NOT a FLE per FHP-25 but is a movement discrepancy AND either would require stopping fuel moves A incorrect - Not a Fuel Loading Error CID are incorrect - either event would require stopping of fuel moves Proposed references to be provided to applicants during examination: None Technical Reference(s):
Ni-FHP-25/page 4/Att.4 K/A: I Generic 2.2.28 2.2.28 - Knowledge of new and spent fuel movement procedures 10 CFR Part 55 Content:
55.41 55.43 (7)
X 55.45 Question Source:
Bank #
Modified Bank #
New NEW History Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None
Proposed Question: SRO 089 W The plant is operating at 100%, with the following:
An extremely cold weather system has settled in the area Engineering has determined that a safety related valve)operability is threatened by cold environment
-/
Engineering recommends, via an Engineering Reply (ER) installation of portable hea ting to maintain the required environmental conditions Which one of the following describes the appropriate controls to maintain the valve operable?
A.
The ER provides the necessary approvals and the heater may be installed B.
A Work Order/Job Traveler is all that is needed to approve heater installation C.
A Temporary Change Package needs to be issued to install the heater D.
A Design change must be made to increase the available heating in the room Proposed Answer: C Justification:
C is correct-This is the process specified for making temporary changes to plant design A incorrect-Ref 3.2.2.a prohibits use of an ER in this manner B incorrect-This activity constitutes a necessary change to plant design to maintain equipment operability. While an ACR may be needed to accomplish installation, the ACR is not acceptable to document a design change which installs support equipment essential to maintaining operability of safety related plant equipment. D incorrect-Ultimately, a permanent design change may be appropriate, however a temporary change has been evaluated in the ER as acceptable Proposed references to be provided to applicants during examination: None Technical Reference(s):
NIP-CON-01 K/A:
Generic 2.2.5 2.2.5: Knowledge of the process for making changes in the-facility as described in the safety analysis report 10 CFR Part 55 Content:
55.41 55.43 (3)
X 55.45 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments: None
Proposed Question: SRO 092 Per S-RAP-RPP-0703, Authorization to Exceed Administrative Dose Limits, which one of the following describes the final authorization required to extend an individual annual Nine Mile dose limit to 1600 mrem?
A.
Vice President-Nuclear B.
Plant Manager C.
Unit RP Manager D.
RP Supervisor Proposed Answer: B Justification:
B is correct-The Plant Manager is designated as the final authority A/I/D incorrect-not the referenced final approver for dose above 1500 but below 2000 Proposed references to be provided to applicants during examination: None I ecnnical Rererence(s):
K/A: I Generic 2.3.1 10 CFR Part 55 Content:
S-RAP-RPP-0703 2.3.1. Knowledge of 10 CFR 20 and related facility radiation control requirements 55.41(7)
X 55.43 55.45 Question Cognitive Level:
Memory or Fundamental Knowledge X
Comprehension or Analysis LOD:
2 Comments:
None SJ
Examination Outline Cross-reference:
Level SRO Tier #
3 Group#
K/A #
Generic 2.3.11 Importance Rating 3.2 Proposed Question: SRO 094 One hour ago, a reactor scram occurred, with the following:
RPV Level dropped to 35 inches and is now 70 inches and stable RPV Pressure dropped to 700 and is now 770 psig and stable Torus water level is 11 feet and stable EC 11 CANNOT be isolated EC 11 Vent radiation monitor is in alarm Chemistry reports that the off-site dose projection is 1080 mRem/hr TEDE.
Which one of the following describes the required actions?
A.
Perform an RPV blowdown.
B.
Bypass ADS C.
Lower RPV pressure to 450 to 550 psig D.
Lower RPV pressure to 350 to 450 psig Proposed Answer: A Justification:
A is correct-Rad Release EOP for GE and primary system discharging outside containment. B incorrect-The vents are on the main steam line to the EC. Opening the vents will be ineffective in reducing the release. C incorrect-This is an appropriate action before the General Emergency level is reached. Once the General Emergency level is reached, the required action is to-open 3 ERVs (RPV blowdown). D incorrect-Only evacuate areas 2 miles around and 5 miles downwind and shelter all remaining areas.
Proposed references to be provided to applicants during examination: EOP Flowcharts Technical Reference(s):
N1-EOP-6, Radioactivity Release Control K/A:
Generic 2.3.11 2.3.11. Ability to control radiation releases.
10 CFR Part 55 Content:
55.41(10,12)
X 55.43 (5)
X 55.45 Question Source:
Bank #
X Modified Bank #
New History 2000 NMPI SRO*
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis X
LOD:
2 Comments: