ML17116A081
| ML17116A081 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/09/2017 |
| From: | Chuck Zoia Operations Branch III |
| To: | Exelon Generation Co |
| Shared Package | |
| ML16308A463 | List: |
| References | |
| Download: ML17116A081 (478) | |
Text
1 ID: 1265090 Points: 1.00 An event has occurred resulting in lowering Suppression Pool (SP) level and rising SP temperature.
A scram is required before SP temperature exceeds a maximum of _____(1)_____°F.
The lowest SP level requiring a blowdown to be performed is _____(2)_____.
A. (1) 110 (2) 13'1" B. (1) 110 (2) 15'1" C. (1) 185 (2) 13'1" D. (1) 185 (2) 15'1" Answer: B Answer Explanation B is correct:
CPS 4402.01 EOP-6 Primary Containment Control:
- the Suppression Pool Temperature leg directs inserting a scram before Suppression Pool temperature reaches 110°F.
- the Suppression Pool Temperature leg and Suppression Pool Level leg directs performing a blowdown if SP Level cannot be held above 15'1".
A is incorrect but plausible if the examinee correctly recalls the SP temperature requiring a scram to be inserted but incorrectly recalls the SP Level requiring a blowdown to be performed. The SP level leg requires the Mixing Compressors to be secured when SP level drops below 13'1".
C is incorrect but plausible if the examinee incorrectly recalls the SP temperature requiring a scram to be inserted and also incorrectly recalls the SP Level requiring a blowdown to be performed. The containment temperature requiring a blowdown to be performed is 185°F. The SP level leg requires the Mixing Compressors to be secured when SP level drops below 13'1".
D is incorrect but plausible if the examinee incorrectly recalls the SP temperature requiring a scram to be inserted but correctly recalls the SP Level requiring a blowdown to be performed.
The containment temperature requiring a blowdown to be performed is 185°F.
KA justification - this question meets the KA because the examinee has to demonstrate knowledge of the operational impacts of parameters affecting the heat capacity of the suppression pool to during low suppression pool water level conditions to answer the question.
Cog Level justification - this is a low cog question written at the memory level. The examinee has to recall facts in a procedure to answer the question (1-F).
Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1265090 User-Defined ID: CL-ILT-1265090 Cross Reference Number:
An event has occurred resulting in lowering Suppression Pool Topic:
(SP) level and rising SP temperatur...
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Comments: General Data Technical Reference with CPS 4402.01 Fig. P Rev. 30 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New question Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4402.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 295030 Low Suppression Pool Water Level Category / KA Statement: EK1. Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: EK1.03 Heat capacity RO Value: 3.8 SRO Value: 4.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.8 to 41.10 10CFR55-43 (SRO) Data: NA
2 ID: 1268971 Points: 1.00 The plant has been scrammed due to rising Drywell temperature.
RPV level indicates:
- +3" on narrow range level indicators
- -11" on wide range level indicators Under these conditions, CPS 4411.07 RPV Level Instrumentation requires the use of _____(1)_____ to report RPV level even though the _____(2)_____.
A. (1) narrow range (2) indicators read LOWER than actual B. (1) narrow range (2) indicators read HIGHER than actual C. (1) wide range (2) indicators read LOWER than actual D. (1) wide range (2) indicators read HIGHER than actual Answer: D Answer Explanation D is correct:
Per CPS 4411.07 Attachment A: RPV Level Instrumentation response to Off-Calibration /
Changing Plant Conditions, increasing Drywell (DW) temperature will cause indicated level to rise, therefore Wide Range (WR) level indication will be higher than actual. This is caused by lowering density in the instrument reference leg causing level instrument dP to lower resulting in a higher indicated level.
CPS 4411.07 RPV Level Instrumentation step 4.8.3 requires use of the Narrow Range (NR) Level indicators when it is on scale above its minimum usable level. Per Attachment A of 4411.07, the operating range for the NR level instruments is +5" to +60". Therefore, with NR level indicating
+3", use of the WR Level indicators is required.
A is incorrect but plausible if the examinee fails to correctly analyze the effect of rising DW temperature on the narrow range level instruments and also incorrectly believes that the narrow range level indicators should be used when indicating above 0". This choice is incorrect because the minimum usable level indication for the narrow range instruments is +5".
B is incorrect but plausible if the examinee correctly analyzes the effect of rising DW temperature on the narrow range level instruments but incorrectly believes that the narrow range level indicators should be used when indicating above 0". This choice is incorrect because the minimum usable level indication for the narrow range instruments is +5".
C is incorrect but plausible if the examinee fails to correctly analyze the effect of rising DW temperature on the wide range level instruments.
KA justification - this question meets the KA because the examinee is required to determine the effects of rising DW temperature on the RPV level indicators and determine which RPV level instruments should be used to report RPV level (the operational implication).
Cog Level justification - this is a high cog question written at the analysis and comprehension level. The examinee has to analyze the conditions in the stem, determine how rising DW temperature affects the RPV water level instruments, and then choose which instruments to use based on knowledge of instrument ranges and the analysis to answer the question (3-SPK).
Question 2 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268971 User-Defined ID: CL-ILT-1268971 Cross Reference Number:
The plant has been scrammed due to rising Drywell temperature.
Topic: RPV level indicates:
+3" on...
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Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 4411.07 Rev. 6b Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Modified (CL-ILT-N12001)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Modified the stem to make History: (i.e. Modified distractor distracter D the correct b to make plausible based on answer.
OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4411.07 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295028 High Drywell Temperature Category / KA Statement: EK1. Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE : EK1.01 Reactor water level measurement RO Value: 3.5 SRO Value: 3.7 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.8 - 41.10 10CFR55-43 (SRO) Data: NA
3 ID: 1268973 Points: 1.00 A transient has occurred resulting in the following conditions:
Parameter Value Trend DW temperature 205°F rising Containment temperature 190°F rising Reactor pressure 200 psig lowering Suppression pool temperature 122°F rising Suppression pool level 20' stable Under these conditions, a blowdown must be performed because...
A. Drywell failure is imminent.
B. SRV tailpipes may fail in an SRV actuation.
C. the operability of equipment in the containment may be jeopardized.
D. the suppression pool may NOT absorb the energy from a loss of coolant accident.
Answer: C
Answer Explanation C is correct - Per the EOP Tech Bases for EOP-6 Primary Containment Control, containment temperature above 122°F (the Technical Specification LCO limit) is a symptom of events which may jeopardize primary containment integrity and the operability of equipment in the containment.
A blowdown is directed by EOP-6 if containment temperature cannot be maintained below 185°F.
A is incorrect but plausible - with the elevated DW temperature provided in the stem. If drywell temperature cannot be restored and held below 330°F, a blowdown is performed to limit further release of energy into the drywell, thus minimizing the drywell heatup. The specified temperature is the lower of the maximum temperature at which ADS is qualified (340°F) and the drywell design temperature (330°F).
B is incorrect but plausible - The SRV tailpipe limit is based on reactor pressure and suppression pool level. The examinee may select this response based on the elevated temperatures in the containment and the elevated level in the Suppression Pool if the bases for the SRV Tail Pipe Limit are incorrectly recalled.
D is incorrect but plausible - this is the bases for the Heat Capacity Limit, which is based on Suppression Pool Temperature, RPV Pressure, and SP Level. The examinee may select this response based on the elevated temperature and level in the suppression pool or if the bases for the HCTL are incorrectly recalled.
KA justification - this question meets the KA because the examinee has to determine why a blowdown has to be performed based on the parameters provided in the stem.
Cog Level justification - this is a high cog question because the examinee has to evaluate a number of parameters provided in the stem and then determine the bases for the action that is required to be performed.
Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268973 User-Defined ID: CL-ILT-1268973 Cross Reference Number:
A transient has occurred resulting in the following conditions:
Topic:
Parameter Value Trend DW tem...
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Text Field:
Comments: General Data Technical Reference with
- EOP-TB Rev. 7 Revision Number:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-ILT-A14002)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data table History: (i.e. Modified distractor and added figures P and Q to b to make plausible based on the question stem.
OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- EOP-TB ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295027 High Containment Temperature (Mark III Containment Only)
Category / KA Statement: EK1. Knowledge of the operational implications of the following concepts as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) : EK1.03 Containment Integrity: Mark-III RO Value: 3.8 SRO Value: 3.8 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.8 to 41.10 10CFR55-43 (SRO) Data: NA
4 ID: 1269005 Points: 1.00 A transient has occurred requiring the MCR to be abandoned.
The Division 1 DG TRANSFER Switch, C61-HS502 at the Remote Shutdown Panel has been placed in the EMERGENCY position.
Based on these conditions, which case below describes how the operation of Diesel Generator (DG) 1A is impacted?
Case # Bus Undervoltage Auto Start Feature LOCA Auto Start Feature 1 Defeated Defeated 2 Enabled Enabled 3 Enabled Defeated 4 Defeated Enabled Case...
A. 1 B. 2 C. 3 D. 4 Answer: C Answer Explanation C is correct - CPS 4003.01 Remote Shutdown (RS) section 4.3 (note before step 4.3.2) states:
"When TRANSFER SWITCH C61-HS502 is placed in EMERG, DG 1A is prevented from starting on a LOCA signal. DG 1A will only start on Bus 1A1 Undervoltage."
This is represented in Case 3.
A is incorrect but plausible if the examinee incorrectly believes that all auto start functions are defeated (Case 1) when C61-HS502 is placed in Emergency. The candidate may select this response based on knowledge that components will typically not respond to their normal initiation signals IF their control has been transferred to the Remote Shutdown Panel (RSP) but fails to recall that the Div 1 DG will auto start on a bus UV signal initiated from relays located on the 4160V Bus 1A1 switchgear.
B is incorrect but plausible if the examinee fails to recall that the LOCA auto start signals are defeated for Div 1 DG when C61-HS502 is in the Emergency position (Case 2). The candidate may select this response based on knowledge that the Div 1 DG will auto start on undervoltage and incorrectly determines that none of the auto start signals are defeated when operating the DG from the RSP.
D is incorrect but plausible if the examinee fails to recall that only the LOCA auto start signals are defeated for Div 1 DG when C61-HS502 is in the Emergency position and confuses the LOCA auto start function with the bus UV function when operating the DG from the RSP.
KA justification - this question meets the KA because the examinee must use knowledge of how Div 1 DG operation is affected when operating the system from the Remote Shutdown Panel to answer the question.
Cog Level Justification - this is a low cog question written at the memory level. The examinee must recall how a system functions with a given control switch alignment (1-F).
Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269005 User-Defined ID: CL-ILT-1269005 Cross Reference Number:
A transient has occurred requiring the MCR to be abandoned.
Topic:
The Division 1 DG TRANSFER Switch...
Num Field 1:
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Text Field:
Comments: General Data Technical Reference with CPS 4003.01 Rev. 17c Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-0129)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data Table.
History: (i.e. Modified distractor Added KA and cog level b to make plausible based on justification statements.
OTPS review) Revised the question stem for readability.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4003.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 295016 Control Room Abandonment Category / KA Statement: AK2. Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following:
AK2.01 Remote shutdown panel: Plant-Specific RO Value: 4.4 SRO Value: 4.5 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
5 ID: 1269077 Points: 1.00 The plant was operating at rated thermal power when annunciator 5061-5C AUTO TRIP 480V BUS FEEDER BKR was received.
The investigating Equipment Operator (EO) reports that the main feed breaker to AB MCC 1B1 has tripped.
The cause of the trip and restoration time is unknown.
Based on these conditions, which of the following actions (if any), are required?
Reducing loads on DC MCC 1B _____(1)_____ required.
Reducing loads on DC MCC 1D _____(2)_____ required.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Answer: A
Answer Explanation A is correct:
Per CPS 3503.01E001, the AC power supply to 125V Battery Charger 1B and 1D is AB MCC 1B1. Since the stem states that the 480V Bus Feeder to AB MCC 1B1 has tripped, Battery Chargers 1B and 1D have been lost.
Per CPS 3503.01 section 8.2.5 Loss of Battery Charger, step 8.2.5.1.3 states that load should be reduced on the batteries if the situation warrants. Since the stem states that the cause of the trip and restoration time is unknown, loads are required to be reduced on DC MCC 1B and 1D to minimize Battery 1B and 1D discharge rate.
In addition, a NOTE in CPS 4200.01C002 DC Load Shedding During a Station Black Out (SBO) states that the Load Shedding Checklist may be used in part or in whole for events less severe than a full Station Black Out.
B is incorrect but plausible if the examinee correctly determines that Battery Charger 1B has been lost based on conditions in the stem, but incorrectly believes that Battery Charger 1D is unaffected.
C is incorrect but plausible if the examinee correctly determines that Battery Charger 1D has been lost based on conditions in the stem, but incorrectly believes that Battery Charger 1B is unaffected.
D is incorrect but plausible if the examinee incorrectly believes neither Battery Charger is affected by the conditions in the stem, based on incorrect knowledge of the power sources to the 1B and 1D DC Battery Chargers, or by believing that each battery charger has an alternate power supply.
KA justification - this question meets the KA because the examinee has to demonstrate knowledge of a partial loss of DC (loss of 1B and 1D Battery Chargers) and the associated procedural requirements due to those losses to answer this question.
Cog Level justification - this is a high cog question written at the analysis and comprehension level. The examinee has to recognize the interaction between two systems (Auxiliary Power and DC Power), and the implications and consequences of the conditions to answer the question (2-RI).
Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269077 User-Defined ID: CL-ILT-1269077 Cross Reference Number:
The plant was operating at rated thermal power when Topic:
annunciator 5061-5C AUTO TRIP 480V BUS FEEDE...
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Text Field:
Comments: General Data Technical Reference with CPS 5061.05 (5C) Rev. 27 Revision Number: CPS 3503.01E001 Rev. 14a CPS 3503.01 Rev. 18b CPS 4200.01C002 Rev. 5a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 5061.05 (5C)
ON-## not provided) CPS 3503.01E001 CPS 3503.01 CPS 4200.01C002 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level High (2-RI)
KA Data KA Number / System Name: 295004 Partial or Complete Loss of D.C. Power Category / KA Statement: AK2. Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following: AK2.01 Battery Charger RO Value: 3.1 SRO Value: 3.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
6 ID: 1269089 Points: 1.00 The plant was operating at rated thermal power when a plant transient occurred resulting in the following:
Parameter Value Trend Drywell Pressure 2.1 psig rising RPV Level -20" lowering These conditions will cause TB MCC _____(1)_____ to de-energize, resulting in a loss of power to
_____(2)_____.
A. (1) 1L (2) CRD Pump 'A' Aux Oil Pump B. (1) 1M (2) CRD Pump 'A' Aux Oil Pump C. (1) 1L (2) 1FW004 RFP 1C Flow Control Valve Hydraulics D. (1) 1M (2) 1FW004 RFP 1C Flow Control Valve Hydraulics Answer: D Answer Explanation D is correct - per CPS 4001.02 Automatic Isolation, Table 1: Shunt Trips, 1AP71E TB MCC 1M Fdr Bkr on 480V Unit Sub 1B is shunt tripped on a Level 1/High DW pressure or ECCS Manual Initiation signal.
Per CPS 4001.02 step 4.9.2, resetting TB MCC 1M Fdr Bkr (1AP71E) should be given priority when RFP 1C is needed. This circuit feeds the hydraulic control for 1FW004, RFP 1C Flow Control Valve, and RFP 1C Aux Oil Pump.
A is incorrect but plausible if an examinee incorrectly believes TB MCC 1L is shunt tripped during a LOCA resulting in a loss of CRD Pump 'A' Aux Oil Pump. TB MCC 1L is powered from a non-safety related Unit Substation (480V Unit Substation 1I) and is unaffected by a LOCA. CRD Pump 'A' Aux Oil Pump is powered from TB MCC 1A and is also unaffected by the LOCA conditions in the stem. The examinee may select this response by confusing CRD Pump 'A' Aux Oil Pump with 1C11-C300 Reactor Recirc Pumps Aux Seal Injection Pump which is powered from TB MCC 1M and would lose power with the high DW pressure condition present.
B is incorrect but plausible if an examinee correctly determines TB MCC 1M is shunt tripped during a LOCA but incorrectly determines that CRD Pump 'A' Aux Oil Pump is de-energized as a result. CRD Pump 'A' Aux Oil Pump is powered from TB MCC 1A and is unaffected by the LOCA conditions in the stem. The examinee may select this response by confusing CRD Pump
'A' Aux Oil Pump with 1C11-C300 Reactor Recirc Pumps Aux Seal Injection Pump which is powered from TB MCC 1M and would lose power with the high DW pressure condition present.
C is incorrect but plausible if an examinee incorrectly believes TB MCC 1L is shunt tripped during a LOCA resulting in a loss of 1FW004. TB MCC 1L is powered from a non-safety related Unit Substation (480V Unit Substation 1I) and is unaffected by a LOCA. 1FW004 is powered from TB MCC 1M which is de-energized (shunt tripped) by the LOCA conditions in the stem. The examinee may select this response by incorrectly recalling the power supply to 1FW004.
KA justification - this question meets the KA because the examinee has to determine how LOCA parameters will result in a partial loss of AC power and shunt trip of breakers in the AC electrical distribution system and the impact on the plant to answer the question.
Cog Level justification - this is a low cog question written at the memory level. The examinee must recall how a LOCA signal impacts the AC electrical distribution system and the associated loads to answer the question (1-F).
Question 6 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269089 User-Defined ID: CL-ILT-1269089 Cross Reference Number:
The plant was operating at rated thermal power when a plant Topic:
transient occurred resulting in the ...
Num Field 1:
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Text Field:
Comments: General Data Technical Reference with CPS 4001.02 Rev. 17c Revision Number: CPS 3502.01E001 Rev. 16c CPS 3304.01E002 Rev. 4b CPS 3304.01E001 Rev. 7 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4001.02 ON-## not provided) CPS 3502.01E001 CPS 3304.01E002 CPS 3304.01E001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 295003 Partial or Complete Loss of A.C. Power Category / KA Statement: AK2. Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF A.C. POWER and the following: AK2.03 A.C. electrical distribution system RO Value: 3.7 SRO Value: 3.9 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
7 ID: 1269110 Points: 1.00 The plant was operating at rated thermal power when annunciator 5041-4C LOW PRESS CONTROL BLDG IA RING HDR was received.
NO other ring header low pressure annunciators were received or are alarming.
Based on these conditions, automatic actuations have occurred to maintain air supply to which of the following systems/components?
System / Description Component #
1 Spent Fuel Pool Gate Seals 2 Scram Discharge Volume Vent and Drain Valves 3 Main Steam Isolation Valves 4 Continuous Containment Purge Ventilation (CCP) System A. 1 ONLY B. 1 AND 2 ONLY C. 1, 2, AND 3 ONLY D. 1, 2, 3, AND 4 Answer: C Answer Explanation C is correct:
Per CPS 5041.04 (4C) Low Pressure Control Building IA Ring Header, low air pressure of 70 psig to the Control Building IA header will result in automatic closure of 1IA022 and 1IA021, Control Bldg IA Ring Header Isolation Valves, resulting a loss of air to:
- CNMT/Drywell Purge (VR/VQ)
- Fuel Bldg (VF)
- Aux Bldg (VA)
- Turbine Bldg (VT)
- Machine Shop (VJ)
- Laboratory (VL)
- Radwaste Bldg (VW)
- Makeup Air portion of Diesel Generator (VD)
- Plant Chilled Water (WO) Chillers shutdown. The makeup valve to the WO Compression Tank fails open & lifts the WO relief valve.
- CCW Storage Tank Automatic Makeup Water Valve will fail closed.
Per CPS 3214.01 Plant Air (IA & SA), section 8.1.2.13, Figure 1, and M05-1048-9, the Spent Fuel Pool / Transfer Pool and Cask Washdown Gate Seals are supplied by the Aux and Fuel Building Service Air system and is unaffected by closure of IA022 and 1IA021, Control Bldg IA Ring Header.
The Scram Discharge Volume Vent and Drain Valves are supplied from Containment Building IA which is fed from Aux/Fuel Building IA and Turbine Building IA ring headers. Per CPS 3214.01 Figure 1, these ring headers are not equipped with automatic ring header isolation valves, so automatic isolation of 1IA021 and 1IA022 will have no impact on the Containment Building IA supply.
The Main Steam Isolation Valves are supplied from Containment Building IA which is fed from Aux/Fuel Building IA and Turbine Building IA ring headers. Per CPS 3214.01 Plant Air (IA & SA)
Figure 1, these ring headers are not equipped with automatic ring header isolation valves, so automatic isolation of 1IA021 and 1IA022 will have no impact on the Containment Building IA supply.
A is incorrect but plausible if the examinee correctly recognizes that the Spent Fuel Pool Gate Seals are unaffected by the conditions in the stem, but fails to recognize that the Scram Discharge Volume Vent and Drain Valves and the Main Steam Isolation Valves are also unaffected.
B is incorrect but plausible if the examinee correctly recognizes that the Spent Fuel Pool Gate Seals and the Scram Discharge Volume Vent and Drain Valves are unaffected by the conditions in the stem, but fails to recognize that the Main Steam Isolation Valves are also unaffected.
D is incorrect but plausible if the examinee misdiagnoses the indications provided in the stem.
The conditions in the stem will result in a loss of IA to the CCP system resulting in an automatic system shutdown (air supply is not maintained).
KA justification - this question meets the KA because the examinee has to determine the reason for the automatic isolation of the Control Building Instrument Air Header Isolation Valves (maintain air supply to various equipment supplied from the SA/IA system) to answer the question.
Cog level justification - this question is a high cog question written at the analysis and comprehension level because the examinee has to analyze the indications provided in the stem, and then determine impact and consequences of those conditions (2-RI).
Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269110 User-Defined ID: CL-ILT-1269110 Cross Reference Number:
The plant was operating at rated thermal power when Topic:
annunciator 5041-4C LOW PRESS CONTROL BLDG I...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 5041.04 (4C) Rev. 27 Revision Number:
- CPS 3214.01 Rev. 26f
- M05-1048-9 rev. R Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 5041.04 (4C)
ON-## not provided)
- CPS 3214.01
- M05-1048-9 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 295019 Partial or Complete Loss of Instrument Air Category / KA Statement: AK3. Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : AK3.03 Service air isolations: Plant-Specific RO Value: 3.2 SRO Value: 3.2 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
8 ID: 1269173 Points: 1.00 The plant has experienced a Main Turbine & Generator trip from rated thermal power.
Assuming all systems respond as designed, which of the following describes the reason for the response of the following valves?
A. protect the Main Turbine from overspeed.
B. prevent rotor bowing due to uneven heating.
C. prevent exceeding cooldown rate limitations on the Main Turbine.
D. provide a flowpath to allow depressurization of the High Pressure Feedwater Heaters.
Answer: A Answer Explanation A is correct - A Main Turbine trip will cause 1ES001A and 1ES001B to automatically close, and 1ES013A and 1ES013B to automatically open to prevent reverse flow from the feedwater heaters back to the Main Turbine following a turbine trip, thus providing overspeed protection for the Main Turbine.
B is incorrect but plausible if the examinee incorrectly believes that 1ES001A and 1B will remain open, and 1ES013A and 13B will remain closed (the normal alignment with the TG on-line) following a turbine trip to prevent excessive side to side differential temperature that will result in TG rotor bowing during TG coast down.
C is incorrect but plausible if the examinee incorrectly believes that 1ES001A, 1B, 13A, and 13B will close following a turbine trip to limit the depressurization / cooldown rate of the Main Turbine.
D is incorrect but plausible if the examinee incorrectly believes that 1ES001A, 1B, 13A, and 13B will all open following a turbine trip to provide a flowpath from the HP Feedwater Heaters (6A/6B) to the Main Condenser. This is incorrect because the Extraction Steam Non-Return Check Valves (1ES002A and 1ES002B) located between 1ES001A/1B and HP Heater 6A/6B (not shown in the graphics) automatically close on a turbine trip to prevent reverse flow from HP Heater 6A/6B through the Main Turbine.
KA Justification - this question meets the KA because the examinee has to recall the reason for the extraction steam isolations following a Main Turbine Trip event to answer the question.
Cog Level Justification - this is a low cog question written at the memory level - the examinee has to recall the function of several ES system valves to answer the question.
Question 8 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269173 User-Defined ID: CL-ILT-1269173 Cross Reference Number:
The plant has experienced a Main Turbine & Generator trip from rated thermal power.
Topic:
Assuming all Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 5007.01 (1B) Rev.
Revision Number: 30b
- CPS 5016.04 (4F & 4G)
Rev. 24
- N-CL-OPS-239003 Rev 002 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 5007.01 (1B)
ON-## not provided)
- CPS 5016.04 (4F & 4G)
- N-CL-OPS-239003 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 295005 Main Turbine Generator Trip Category / KA Statement: AK3. Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP: AK3.05 Extraction steam/moisture separator isolations RO Value: 2.5 SRO Value: 2.6 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
9 ID: 1269199 Points: 1.00 The plant is operating during peak summer loading at rated conditions.
- Line voltage is being maintained IAW CPS 3105.05 Generator (TG) section 8.5.10 Maintaining Line Voltage Under High Load Conditions.
Current Generator parameters are as follows:
Parameter Value Generator Output 1108 MWe Generator VARS 580 MVAR Field Current 6415 amps Field Voltage 547 volts DC Generator Hydrogen Pressure 72 psig The following table is an excerpt of the Alterrex Excitation (Rectifier) System Limitations contained in CPS 3105.05 Generator (TG):
Condition Limitation (EC 338215, SI 35.01)
Nameplate Rating 3607 KW / 3797 kVA at 0.95 PF Rating of total rectifier output 6408 amps / 545 volts DC Minimum exciter cooler cold air temperature 10°C (50°F) Alarm: 53°C (127°F)
Maximum rectifier heat sink temperature 110°C (230°F) Alarm: 93°C (200°F)
One rectifier bridge out of service 5680 amps One rectifier switch complement OOS 2840 KW / 485 volts Loss of cooling water flow to the rectifiers 6408 amps for 5 minutes, THEN 2922 amps Based on these conditions, which of the following is a required action and the reason for that action?
A. Lower reactor power to reduce generator output.
B. Raise hydrogen pressure to restore margin with the Generator Estimated Capability Curves.
C. Depress the Exciter Volt Control Lower pushbutton on 1H13-P680 to restore compliance with generator limitations.
D. Shift non-safety 4160V and 6900V Busses to their reserve source to ensure they will not lose power if the plant trips.
Answer: C
Answer Explanation C is correct:
The high load conditions have resulted in the generator exciter exceeding its voltage and current limits (rectifier output amperage and voltage limits). The required action is to reduce excitation to within limits specified in CPS 3105.05 Generator (TG) section 8.5.10 Maintaining Line Voltage Under High Load Conditions.
Distractors:
A is incorrect but plausible if the examinee incorrectly determines that the generator output MW is exceeding the limits of 3105.05 App. A Generator Estimated Capability Curve. The examinee may select this response if they incorrectly follow the intersection of 72 psig H2 line and 580 MVAR lines down vertically and determine that generator output is limited to 1080 MWe, and then determines that lowering reactor power is the only way to restore compliance with App A. The correct generator MWe limit with H2 pressure at 72 psig is 1200 MWe. Note - the notes above the spider curve allows the 75 psig VAR curve to be used up to 3 psig below the VAR curve value. Therefore, with H2 pressure at 72 psig, the 75 psig VAR curve can be used.
B is incorrect but plausible if the examinee incorrectly determines that raising generator hydrogen pressure to 75 psig will restore the generator to within the App A Estimated Capability Curve.
Raising hydrogen pressure will not bring the generator operating parameters to within specification. The hydrogen pressure curves are valid for up to a 3 psig range.
D is incorrect but plausible if the examinee incorrectly determines that shifting non-safety busses is directed by OP-CL-108-107-1002 Degraded Grid Actions. OP-CL-108-107-1002 step 4.3.3.4 prohibits manually transferring any bus that could place a transient on the grid. Since transferring the non-safety busses would place them on the Reserve Auxiliary Transformers (powered from the 345 KV North Bus), this action is prohibited. This action would be correct if transferring busses IAW guidance provided in CPS 3501.01 High Voltage Auxiliary Power limitation 6.6, which allows transferring busses if desired during degraded grid conditions that do not meet the threshold of a TSO or RC declared degraded grid status.
KA justification - this question meets the KA because the examinee has to demonstrate knowledge of the reasons for actions contained in CPS procedures for degraded grid conditions and maintaining line voltage under high load conditions to answer the question.
Cog Level justification - this question is a high cog question written at the analysis and application level. The examinee has to analyze multiple indications in the stem, compare them to values in a table and on a graph, and then determine required actions and the reason for those actions to answer the question (3-SPK/SPR).
Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269199 User-Defined ID: CL-ILT-1269199 Cross Reference Number:
The plant is operating during peak summer loading at rated conditions.
Topic:
The Transmission System Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 3105.05 Rev. 21c Revision Number:
- OP-CL-108-107-1002 Rev. 6 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. CPS 3105.05 Appendix A ABN-##) Generator Estimated Capability Curves with the notes above the curve redacted.
Excluded
Reference:
(i.e. Ensure
- CPS 3105.05 (with the ON-## not provided) exception of Appendix A Generator Estimated Capability Curves)
- OP-CL-108-107-1002 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK/SPR)
KA Data KA Number / System Name: 700000 Generator Voltage and Electric Grid Disturbances Category / KA Statement: AK3. Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: AK3.02 Actions contained in abnormal operating procedure for voltage and grid disturbance RO Value: 3.6 SRO Value: 3.9 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.4, 41.5, 41.7, 41.10 10CFR55-43 (SRO) Data: NA
10 ID: 1269203 Points: 1.00 The plant was operating at rated thermal power when annunciators 5066-5B ADS OR SAFETY RELIEF VALVE LEAKING and 5067-8L SRV MONITORING SYSTEM TROUBLE were received.
Main Generator MWe lowered from 1113 MWe to 1031 MWe.
Current indications on 1LR-CM241 Supp Pool Bulk Temp and Level Recorder are shown below.
Given these conditions, an EOP-6 entry condition _____(1)_____ been exceeded. Placing RHR Loops
'A' and 'B' in Suppression Pool (SP) Cooling _____(2)_____ reverse the current SP temperature trend.
A. (1) has (2) will B. (1) has (2) will NOT C. (1) has NOT (2) will D. (1) has NOT (2) will NOT Answer: B
Answer Explanation B is correct:
Per CPS 4402.01 Primary Containment Control, the EOP-6 entry condition for high suppression pool temperature is 95°F.
The 82 MWe reduction listed in the stem is equivalent to a single full open SRV. A single SRV passes approximately 6.5% of total steam flow. The heat removal capacity of both RHR loops in suppression pool cooling is equivalent to approximately 1% of total steam flow. Per ITS B3.6.2.3 and USAR Section 6.2, the suppression pool temperature will continue to increase until the RHR heat exchanger heat removal rate is equal to the decay heat release rate during small size break events. Therefore Suppression Pool temperature will continue to rise even with both SP Cooling loops in service.
A is incorrect but plausible if the examinee incorrectly believes that the heat removal capacity of both loops of SP Cooling is greater than the heat addition caused by a single open SRV with the reactor at power. SP Cooling subsystem is designed to absorb decay and sensible heat but could be heated beyond design limits if the reactor is not shut down.
C is incorrect but plausible if the examinee incorrectly recalls the EOP-6 entry condition for SP temperature and also believes that the heat removal capacity of both loops of SP Cooling is greater than the heat addition caused by a single open SRV with the reactor at power.
D is incorrect but plausible if the examinee incorrectly recalls the EOP-6 entry condition for SP temperature at 110°F. EOP-6 requires the reactor to be scrammed before SP temperature reaches 110°F.
KA Justification - this question meets the KA because the examinee has to demonstrate the ability to monitor Suppression Pool Cooling operations by predicting how Suppression Pool temperature will be affected with a stuck open SRV and two loops of SP Cooling in service to answer the question.
Cog Level Justification - this is a high cog question written at the analysis level. The examinee must evaluate the conditions in the stem and then determine if EOP-6 entry conditions have been exceeded and how placing both loops of Suppression Pool Cooling in service will impact those conditions (3-PEO/SPK).
Question 10 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269203 User-Defined ID: CL-ILT-1269203 Cross Reference Number:
The plant was operating at rated thermal power when Topic:
annunciators 5066-5B ADS OR SAFETY RELIEF VALVE Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 4402.01 Rev. 30 Revision Number:
- B3.6.2.3 (3.6-56) background discussion of the heat removal capability of each RHR subsystem)
Rev. 0 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-ILT-A14018)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated the General Data History: (i.e. Modified distractor Table.
b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 4402.01 ON-## not provided)
- B3.6.2.3 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO/SPK)
KA Data KA Number / System Name: 295026 Suppression Pool High Water Temperature Category / KA Statement: EA1. Ability to operate and/or monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: EA1.01 Suppression pool cooling RO Value: 4.1 SRO Value: 4.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
11 ID: 1269366 Points: 1.00 A plant transient has occurred resulting in the following conditions:
Parameter Value Trend RPV Level -150" Wide Range lowering The CRS has directed you to maximize injection using the Control Rod Drive Hydraulic (RD) system IAW CPS 4411.03 Injection/Flooding Sources.
Based on these conditions:
- 1C11-R600 CRD Hydraulics Flow Controller _____(2)_____ aligned IAW CPS 4411.03 for maximizing RD injection.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Answer: B
Answer Explanation B is correct:
Per CPS 4411.03 Injection/Flooding Sources, section 2.4 CRD, step 2.4.3 directs performing CPS 4410.00C003 Defeating IA Interlocks if CNMT instrument air isolation has occurred. Per CPS 4001.02C001 Auto Isolation Checklist, valves 1IA005, 006, 007, and 008 will automatically close when RPV level reaches Level 1 (-145.5"), resulting in a loss of air to the CRD Flow Control Valves which will fail to the minimum position. 4411.03 directs performing 4410.00C003 to restore air to the CRD FCVs to allow them to be fully opened to maximize RD injection to the RPV.
CPS 4411.03 step 2.4.4 requires placing 1C11-R600 CRD Hydraulics Flow Control in MANUAL.
In the graphic, 1C11-R600 is in Auto, so the controller is NOT aligned per CPS 4411.03.
A is incorrect but plausible if the examinee correctly determines that 4410.00C003 must be performed to maximize RD injection but incorrectly believes that 1C11-R600 is aligned IAW 4411.03. The candidate may select this response because the controller automatic flow setpoint (thumbwheel controller) is dialed up.
C is incorrect but plausible if the examinee incorrectly determines that 441.000C003 does not have to be performed to maximize RD injection flow. The examinee may select this response if they believe that the CRD FCVs fail open on a loss of air to the containment, or fail to recall that the FCVs are affected by a loss of Cnmt IA. C is also incorrect if the examinee believes that 1C11-R600 is aligned IAW 4411.03. The candidate may select this response because the controller automatic flow setpoint (thumbwheel controller) is dialed up.
D is incorrect but plausible if the examinee incorrectly determines that 441.000C003 does not have to be performed to maximize RD injection flow. The examinee may select this response if they believe that the CRD FCVs fail open on a loss of air to the containment, or fail to recall that the FCVs are affected by a loss of Cnmt IA.
KA Justification - this question meets the KA because the examinee has to demonstrate the ability to operate the CRD system during a low reactor water level transient to answer the question.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level - the examinee must evaluate the conditions in the stem and then determine the actions required to operate the CRD Hydraulic system to answer the question.
Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269366 User-Defined ID: CL-ILT-1269366 Cross Reference Number:
A plant transient has occurred resulting in the following conditions:
Topic:
ParameterValueTrendRPV Lev Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 4411.03 Rev. 10c Revision Number: CPS 4001.02C001 Rev. 16 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4411.03 ON-## not provided) CPS 4001.02C001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295031 Reactor Low Water Level Category / KA Statement: EA1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL : EA1.10 Control rod drive RO Value: 3.6 SRO Value: 3.7 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
12 ID: 1269455 Points: 1.00 The plant is in Mode 5.
- The Fuel Building Ventilation (VF) system is operating.
- The Containment Building Ventilation (VR/VQ) system is operating in Containment Vent Mode.
THEN, the following alarms are received:
- 0RIX-PR001 HVAC Exhaust Stack PRM #1 channel 5 (Lo Nbl Gas) indicating tile is RED.
- 1RIX-PR001A, 1B, 1C, and 1D Containment Bldg Exhaust PRM is indicating 105 mr/hr. Channel 1 (Gamma) for all 4 monitors is rising.
Based on these conditions, which of the following scenarios describe the status of the following ventilation systems?
Fuel Building Ventilation Containment Building Standby Gas Treatment (VF) Ventilation (VR/VQ) System (VG)
Scenario 1 Running Running NOT Running Scenario 2 Running NOT Running NOT Running Scenario 3 NOT Running NOT Running Running Scenario 4 NOT Running Running Running Scenario...
A. 1 B. 2 C. 3 D. 4 Answer: C
Answer Explanation C is correct Per CPS 5140.61 and CPS 4001.02C001 Automatic Isolation Checklist, the high alarm setpoint for 1RIX-PR001A, 1B, 1C, and 1D (red tile) is 99 mR/hr, and will cause an automatic isolation of Groups 10 (Containment Ventilation), 16 (Drywell Ventilation) and 19 (Fuel Building / Secondary Containment Isolation), resulting in shutdown and isolation of VR/VQ and VF.
Per CPS 5050.07 (7F), the Standby Gas Treatment System (VG) automatically initiates on Containment Building Exhaust High Radiation (100 mr/hr) on 1RIX-PR001A(C) AND 1RIX-PR001B(D).
A is incorrect but plausible if the examinee fails to recall the trip setpoints for 1RIX-PR001A, 1B, 1C, and 1D and determines that VF and VR/VQ will remain running and VG will remain in standby (normal alignment).
B is incorrect but plausible if the examinee correctly determines that VR/VQ will shutdown based on the conditions in the stem, but incorrectly determines that VF and VG are unaffected by radiation levels in the containment not impacting secondary containment radiation levels.
D is incorrect but plausible if the examinee incorrectly determines that 1RIX-PR001A, 1B, 1C, and 1D are below the isolation setpoint for VR/VQ, but correctly determines that VF will isolate and VG will auto start.
KA justification - this question meets the KA because the examinee has to determine how the conditions in the stem affect the operation of various plant ventilation systems during an off-site release.
Cog Level justification - this question is a low cog question written at the memory level. The examinee has to recall the interlocks between plant radiation monitors and the plant ventilation systems (1-I).
Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1269455 User-Defined ID: CL-ILT-1269455 Cross Reference Number:
The plant is in Mode 5.
Topic:
The Fuel Building Ventilation (VF) system is operating.
The Containmen Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- 5140.61 Rev. 0d Revision Number:
- CPS 5050.07 (7F) Rev. 33
- CPS 4001.02C001 Rev.
16 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- 5140.61 ON-## not provided)
- CPS 5050.07 (7F)
- CPS 4001.02C001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 295038 High Off-Site Release Rate Category / KA Statement: EA1. Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE : EA1.06 Plant ventilation RO Value: 3.5 SRO Value: 3.6 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
13 ID: 1269411 Points: 1.00 Plant conditions are as follows:
- Reactor power is 33%.
- The Feedwater System (FW) is operating with Turbine Driven Reactor Feed Pump (TDRFP) 'A' in automatic control maintaining RPV water level and the Motor Driven Reactor Feed Pump (MDRFP) in standby.
- 1H13-P680-5004 AND 1H13-P680-5005 annunciators shown below are all reset (NOT alarming):
1H13-P680-5004 1H13-P680-5005 Under these conditions, if Reactor Core Isolation Cooling System is manually initiated, how will reactor power be affected?
The reactor will...
A. Scram due to RPV Low Level 3.
B. Scram due to RPV High Level 8.
C. Scram due to Main Turbine Trip.
D. remain at the current power level.
Answer: C
Answer Explanation C is correct:
Per CPS 3310.01 Reactor Core Isolation Cooling (RI) note before step 8.1.2 Automatic Initiation and CPS 5007.01 (1B) Turb Trip EHC Sys, an initiation of RCIC resulting in RCIC injection (F013 not fully shut & flow > 120 gpm) will result in trips of the Main Turbine and Reactor Feed Pump Turbines.
Per 5004.02 (2D) and 5005.02 (2D) a Turbine Trip will result in a reactor scram if annunciator 5004-3D and 5005-3D is NOT lit and any two instrument channels trip on Turbine Control Valve fast closure. With reactor power at 33% and annunciators 5004-3D and 5005-3D reset (NOT lit) the TCV Fst Cl & TSV Trips are not bypassed; the resulting Turbine Trip will result in a reactor scram.
Distractors:
A is incorrect but plausible if the examinee correctly recalls that RCIC initiation will result in a trip of the Reactor Feed Pumps and an automatic start of the MDRFP, but determines that a scram will be initiated due to insufficient capacity of the MDRFP to maintain RPV level above Level 3 resulting in a Level 3 Reactor Scram. Per CPS 3103.01 section 8.1.3 MDRFP Startup, the note before step 8.1.3.1 states that reactor power should be limited to < 25% full rated power when only the MDRFP is in operation feeding the reactor; at > 25% power closely monitor RPV level response. If FW system conditions and the reactor power presented in the stem exceeded the capacity of the MDRFP, RPV level would slowly reach the RPV Level 3 scram setpoint, but not before the reactor would scram due to the Main Turbine Trip.
B is incorrect but plausible if the examinee determines that initiation of RCIC will cause RPV level to rise to the Level 8 scram setpoint resulting in a scram. RCIC initiation will result in a Main Turbine Trip and TDRFP trip causing RPV level to lower, not rise.
D is incorrect but plausible if the examinee incorrectly believes that the TCV/TSV closure trip reactor scram signal is bypassed based on the power level provided in the stem (33%) and that MDRFP capacity is sufficient to maintain RPV water level above the scram setpoint. Per the Note in 5004-2D and 5005-2D, the Turbine 1st stage pressure which activates a turbine trip scram and an RPS trip is set between 29.2 and 31.5% RTP and is indicated in the MCR by the status of annunciators 5004-3D and 5005-3D discussed above. Since these two annunciators are not alarming, a turbine trip will result in a reactor scram. The ITS SR 3.3.1.1.16 value is 33.3% RTP.
KA justification - this question meets the KA because the examinee has to demonstrate the ability to determine the cause of the reactor scram based on conditions provided in the stem of the question.
Cog Level justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to analyze the conditions in the stem, and then determine how those conditions impact the RPS system (2-RI).
Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269411 User-Defined ID: CL-ILT-1269411 Cross Reference Number:
Plant conditions are as follows:
Topic:
Reactor power is 33%.
The Feedwater System (FW) is operatin...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 3310.01 Rev. 29c Revision Number:
- CPS 5007.01 (1B) Rev.
30b
- CPS 5004.02 (2D) Rev.
29d
- CPS 5005.02 (2D) Rev.
29d
- CPS 5004.03 (3D) Rev.
28a
- CPS 5005.03 (3D) Rev.
31b
- CPS 3103.01 Rev. 30a
- CPS 5002.01 (1C, 1G, &
1J) Rev. 33e
- CPS 3305.01 App. A Rev.
11e Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 3310.01 ON-## not provided)
- CPS 5007.01 (1B)
- CPS 5004.02 (2D)
- CPS 5005.02 (2D)
- CPS 5004.03 (3D)
- CPS 5005.03 (3D)
- CPS 3103.01
- CPS 5002.01 (1C, 1G, &
1J)
- CPS 3305.01 App. A LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 295006 SCRAM Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to SCRAM : AA2.06 Cause of reactor SCRAM RO Value: 3.5 SRO Value: 3.8 Tier: 1 RO Group: 1
SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
14 ID: 1269426 Points: 1.00 The plant was operating at rated thermal power when an alarm was received on MCR Panel 1H13-P841 indicating receipt of a fire alarm on XL3 Panel 1FP43J (located Control Building 781').
The Equipment Operator dispatched to investigate the alarm reports that infrared device 11-04 in the Drywell is alarming.
Based on these indications, the cause of the alarm is a fire in the...
A. Standby Liquid Control (SLC) pumps.
B. Reactor Recirculation (RR) Pump motors.
C. Main Steam Isolation Valve (MSIV) inboard actuators.
D. Automatic Depressurization System (ADS) Safety Relief Valve (SRV) actuators.
Answer: B Answer Explanation B is correct - per CPS 1893.04 Fire Fighting Appendix J Drywell Fire - MCR Actions, Note before step 1 states the following:
"The following information can be used to determine if there is a fire in the Drywell and the fires potential location. Device (B) 11-04 is the only device located in the Drywell. It receives an input from two infrared detectors. Each detector looks for flames emanating from the Reactor Recirc Pump Motors. If device (B) 11-04 alarms, MCR personnel will have to determine which RR Pump Motor is the cause for the alarm. This can be done by looking at RR Pump Motor temperatures on DCS. RR Pump A is at AZM 140 (SE Quadrant) and RR Pump B is at AZM 328 (NW Quadrant)."
Distracters:
A is incorrect but plausible if the examinee correctly recalls that an infrared flame detector is used for the SLC Pumps, but fails to determine that the location of the alarm (drywell) precludes the SLC Pumps from being a potential cause of the alarm.
C is incorrect but plausible if the examinee incorrectly determines that the MSIV actuators are monitored by infrared flame detectors in the drywell. As stated above, the only device located in the drywell monitors the RR Pump Motors.
D is incorrect but plausible if the examinee incorrectly determines that the ADS SRV actuators are monitored by infrared flame detectors in the drywell. As stated above, the only device located in the drywell monitors the RR Pump Motors.
KA justification - this question meets the KA because the examinee has to demonstrate the ability to determine the location of a fire affecting the RR Pump Motors based on fire alarm information provided in the question stem.
Cog Level justification - this is a low cog question written at the memory level. The examinee has to recall facts about the Fire Detection and Protection System to answer the question.
Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269426 User-Defined ID: CL-ILT-1269426 Cross Reference Number:
The plant was operating at rated thermal power when an alarm Topic:
was received on MCR Panel 1H13-P841...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 1893.04 Rev. 17e Revision Number:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 1893.04 ON-## not provided)
- CPS 1893.04M230 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 600000 Plant Fire On Site Category / KA Statement: AA2 Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:
AA2.12 Location of vital equipment within fire zone RO Value: 3.1 SRO Value: 3.5 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.4 10CFR55-43 (SRO) Data: NA
15 ID: 1269428 Points: 1.00 The plant was operating at rated thermal power when ALL offsite power was lost.
Ten (10) minutes after the loss of off-site power the following conditions exist:
Parameter Value Trend Reactor Pressure 950 psig Cycling between 926 and 1073 psig SRV F051C Open Cycling open and closed SRV F051D Open Open (NOT cycling)
The above conditions indicate that the Reactor is . . .
A. critical with power above 5%.
B. critical with power below 5%.
C. shutdown with a stuck open SRV.
D. shutdown with SRVs operating normally.
Answer: A
Answer Explanation A is correct:
The indications provided in the stem indicate that an ATWS has occurred. Per N-CL-OPS-239001 Main Steam System, rated steam flow is 15.153x106 lbm/hr. Each SRV is rated at 936,454 lbm/hr at 1205 psig (~ 6.5% of total steam flow). With one SRV remaining open and another SRV cycling 10 minutes after the event initiation, reactor power is between 6 and 12%
(>5% power for EOP-1 entry criteria).
Therefore, with all conditions considered, the reactor is critical with power above 5%.
Distracters:
B is incorrect but plausible if the examinee incorrectly applies the capacity of the Main Turbine Bypass Valves to the SRVs. Per ITS B3.7.6, the bypass capacity of the system is 28.8% of rated steam flow (4.36x106 lbm/hr), with each SRV passing 1/16, or 0.27x106 lbm/hr, or 1.8% of rated steam flow. With one SRV remaining open and another SRV cycling 10 minutes after the event initiation, reactor power would be calculated to be between 1.8 and 3.6%.
C is incorrect but plausible if the examinee misdiagnoses the conditions in the stem and concludes one SRV remains open following a successful scram. For a normal scram response with a Group 1 isolation, one SRV will normally cycle open and closed to maintain RPV pressure between 926-1033 psig (ref. 5066.06 window 6C). This choice is incorrect because ten minutes after a successful scram with a stuck open SRV, RPV pressure would continuously lower.
D is incorrect but plausible if the examinee misdiagnoses the conditions in the stem of one SRV remaining open following the scram. For a normal scram response with a Group 1 isolation, one SRV will cycle open and closed to maintain RPV pressure between 926-1033 psig (ref. 5066.06 window 6C). This choice is incorrect because if the reactor was shutdown, RPV pressure would be lowering and decay heat alone would not keep one SRV open and one cycling ten minutes after a scram.
KA justification - this question meets the KA because the examinee has to demonstrate the ability to determine reactor power from the condition of the SRVs during an ATWS condition above 5%
power to answer the question.
Cog Level justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to analyze the conditions in the stem and then make determinations about the condition of the reactor based on that analysis (3-SPK).
Question 15 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269428 User-Defined ID: CL-ILT-1269428 Cross Reference Number:
The plant was operating at rated thermal power when ALL offsite power was lost.
Topic:
Ten (10) minutes Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- EOP-TB Rev. 007 Revision Number:
- CPS 4404.01 Rev. 30
- N-CL-OPS-239001 Rev. 4
- UFSAR Ch. 5 (5.2-4) Rev.
11
- CPS 3310.01 Rev. 29c
- CPS 5066.06 (6C) Rev.
25d
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-LC-1334)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Revised stem for readability.
History: (i.e. Modified distractor Updated the General Data b to make plausible based on Table. Added answer OTPS review) plausibility statements.
Added KA and cog level justification statements.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- EOP-TB ON-## not provided)
- CPS 4404.01
- N-CL-OPS-239001
- UFSAR Ch. 5 (5.2-4)
- CPS 3310.01
- CPS 5066.06 (6C)
- ITS B3.7.6 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown Category / KA Statement: EA2. Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : EA2.01 Reactor power RO Value: 4.2 SRO Value: 4.3 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
16 ID: 1270330 Points: 1.00 The plant is in Mode 3 with conditions as follows:
- RHR 'B' is operating in Shutdown Cooling Mode
- RR Pumps 'A' and 'B' are secured
Under these conditions, vessel thermal stratification _____(1)_____ expected to occur.
The minimum RPV level on the Upset Range necessary to ensure natural circulation flow is
_____(2)_____.
A. (1) is NOT (2) 44" B. (1) is (2) 61" C. (1) is (2) 97" D. (1) is (2) 108" Answer: B Answer Explanation B is correct - per CPS 4006.01 Loss of Shutdown Cooling section 4.6 Loss of SDC: Starting From Mode 3, step 4.6.5 directs maintaining RPV water level > minimum natural circulation level (44" Shutdown Range or 61" Upset Range) when no forced coolant circulation exists.
Distracters:
A is incorrect but plausible - the Narrow Range and Upset Range level indicators in the stem are reading ~ 48-49 inches which is above the minimum level requirement for the Shutdown Range level indicator but below the 61" requirement for the Upset Range.
C is incorrect but plausible - per EOP-1 RPV Control Figure C Minimum Usable Levels, this is the minimum usable level for Shutdown Range Level Instrumentation with DW temperature above 350°F and is above the natural circulation RPV level, but is higher than the minimum level requested in the question stem.
D is incorrect but plausible - per EOP-1 RPV Control Figure C Minimum Usable Levels, this is the minimum usable level for Upset Range Level Instrumentation with DW temperature above 350°F and is above the natural circulation RPV level, but is higher than the minimum level requested in the question stem.
KA Justification - this question meets the KA because the examinee has to demonstrate knowledge of the minimum natural circulation levels contained in the Loss of Shutdown Cooling off-normal procedure (CPS 4006.01) to answer the question.
Cog Level Justification - this is a memory level question because the examinee has to recall the Upset Range level indication that is required to be maintained to promote natural circulation in the RPV.
Question 16 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1270330 User-Defined ID: CL-ILT-1270330 Cross Reference Number:
The plant is in Mode 3 with conditions as follows:
Topic:
RHR 'B' is operating in Shutdown Cooling Mode Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 4006.01 Rev. 5a Revision Number: CPS 4401.01 Rev. 30 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14015)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data Table.
History: (i.e. Modified distractor Revised question stem for b to make plausible based on readability.
OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4006.01 Rev. 5a ON-## not provided) CPS 4401.01 Rev. 30 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1P)
KA Data KA Number / System Name: 295021 Loss of Shutdown Cooling Category / KA Statement: 2.4.11 Knowledge of abnormal condition procedures.
RO Value: 4.0 SRO Value: 4.2 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
17 ID: 1269311 Points: 1.00 The plant is in Mode 3 with the preferred loop of RHR in Shutdown Cooling Mode and the remaining ECCS systems in a normal standby alignment.
Then, the 'A' RO reports that Drywell pressure and temperature are rising.
Then, two minutes later, multiple DW High Pressure annunciators were received.
Which of the following describes the impact of these conditions on the automatic initiation of RHR 'A' AND
'B' in LPCI mode?
__________ will automatically realign into LPCI mode and inject to the RPV.
A. RHR 'A' ONLY B. RHR 'B' ONLY C. BOTH RHR 'A' AND RHR 'B' D. NEITHER RHR 'A' NOR RHR 'B' Answer: A
Answer Explanation A is correct:
Per CPS 3312.03 RHR - SHUTDOWN COOLING (SDC) & FUEL POOL COOLING AND ASSIST (FPC&A), section 8.1.2, the preferred loop of RHR for Shutdown Cooling is RHR Loop B. In this configuration, the following valve alignments are made:
- 1E12-F006B, RHR B Shutdown Cooling Suct Valve is opened (3312.03 step 8.1.1.9.3)
- 1E12-F004B, RHR B Suppr Pool Suction Valve is closed (3312.03 step 8.1.2.4.4)
- 1E12-F008, Shutdown Cooling Outbd Suct Isol Vlv is opened (3312.03 step 8.1.2.11.2)
- 1E12-F009, Shutdown Cooling Inbd Suct Isol Vlv is opened (3312.03 step 8.1.2.11.3)
- RHR Pump B is started and 1E12-F053B, RHR B To Feedwater S/D Cooling Rtrn Vlv is opened to establish a return path to the FW system (3312.03 step 8.1.2.20.3).
Per CPS 5064.02 (2G) RHR A LPCI OR CNMT SPRAY INITIATED, an automatic LPCI initiation will result in the following RHR system automatic actuations:
- RHR Pump 'A' Auto Starts
- 1E12-F024A RHR A Test Valve to Suppr Pool closes
- 1E12-F028A RHR A CNMT Spray Shutoff Valve closes (only if no CNMT Spray signal is present)
- 1E12-F027A RHR A to CNMT Outbd Isol Valve opens.
If the LPCI mode is initiated with 1E12-F004A/B closed, RHR Pump Auto Start Failure annunciators will be received (5064-2F / 5065-2A) and the respective RHR Pump will not automatically start.
Therefore, with the conditions listed in the stem:
- RHR 'B' will remain in SDC Mode Distracters B is incorrect but plausible if the examinee correctly determines that the RHR loop not in Shutdown Cooling will automatically realign into LPCI mode, but incorrectly recalls that RHR 'A' is the preferred SDC loop. RHR 'B' is the preferred SDC loop because all the valves used to flush and warm the loop are operated from the MCR (no local operations are required) which reduces total radiation exposure to operations personnel.
C is incorrect but plausible if the examinee incorrectly recalls that LPCI initiation logic will cause all the valves in both RHR loops to realign to LPCI mode. Automatic suction valve realignment will occur for the High Pressure Core Spray system, but not for LPCI systems.
D is incorrect but plausible if the examinee incorrectly recalls that both LPCI 'A' and 'B' are impacted with 1E12-F008 and 1E12-F009 open to support Shutdown Cooling operations. 1E12-F008 and F009 are common to both Shutdown Cooling Loops and the examinee may confuse the system interlocks that are applied with these valves open.
KA justification - this question meets the KA because the examinee is required to demonstrate how the mitigating strategy for a Shutdown LOCA (LPCI injection with RHR) is impacted when aligned for Shutdown Cooling operations to answer the question.
Cog Level justification - this is a low cog question written at the memory level. The examinee has to recall facts about the Shutdown Cooling procedure (which loop is preferred for shutdown cooling) and system interlocks to answer the question (1-F/1-I).
Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 2.00 System ID: 1269311 User-Defined ID: CL-ILT-1269311 Cross Reference Number:
The plant is in Mode 3 with the preferred loop of RHR in Topic:
Shutdown Cooling Mode and the remaining EC Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 3312.03 Rev. 10d Revision Number:
- CPS 5064.02 (2G & 2F)
Rev. 32
- CPS 5065.02 (2A) Rev.
30a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usge 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 3312.03 ON-## not provided)
- CPS 5064.02 (2G & 2F)
- CPS 5065.02 (2A)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F/1-I)
KA Data KA Number / System Name: 295024 High Drywell Pressure Category / KA Statement: 2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
RO Value: 3.8 SRO Value: 4.2 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
18 ID: 1268879 Points: 1.00 The Reactor was operating at 28% power when a transient resulted in a peak reactor pressure of 1135 psig.
The expected state of the following RPS / ARI indicators at the moment these conditions were received is described in graphic number...
1
2 3
4 A. 1 B. 2 C. 3 D. 4 Answer: D
Answer Explanation D is correct:
During normal power operations, indications are as follows:
- Lights above the scram switches - illuminated
- 1C11-F401A & B - open (red)
- 1C11-F402A/B, 403A/B, 404A/B, and 405A/B - closed (green)
Per 5004-1C and 5005-1C, an automatic reactor scram will occur if two instrument channels trip on high reactor pressure (1065 psig).
Per 5008-1K and 1L, ARI will automatically initiate on high reactor pressure at 1127 psig, causing 401A/B to close, and 402A/B, 403A/B, 404A/B, and 405A/B to open. These valves will remain in these positions for 2 minutes or until the initiating signal is clear, and then 401A/B will open, 402A/B and 403A/B will remain open, and 404A/B and 405A/B will close.
A, B, and C are incorrect but plausible variations of the RPS and ARI indicating lights.
KA justification - this question meets the KA because the examinee must have knowledge of the function of the RPS system to a high reactor pressure condition to answer the question.
Cog Level justification - this is a high cog question written at the analysis and comprehension level because the examinee has to analyze the data in the stem and then predict how the RPS and ARI indicating lights will indicate the expected response of the system based on that analysis (3-PEO).
Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1268879 User-Defined ID: CL-ILT-1268879 Cross Reference Number:
The Reactor was operating at 28% power when a transient Topic:
resulted in a peak reactor pressure of 1...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- 5008.01 (1K & 1L) Rev. 27 Revision Number:
- 5004.01 (1C) Rev. 28a
- 5005.01 (1C) Rev. 29c Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) usage.
Question Source: (i.e. New, Bank (CL-ILT-A14005)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated the General Data History: (i.e. Modified distractor Table.
b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- 5008.01 (1K & 1L)
ON-## not provided)
- 5004.01 (1C)
- 5005.01 (1C)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 295025 High Reactor Pressure Category / KA Statement: 2.1.28 Knowledge of the purpose and function of major system components and controls.
RO Value: 4.1 SRO Value: 4.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
19 ID: 1269325 Points: 1.00 The Rod Control & Information System (RC&IS) prevents an inadvertent criticality during refueling operations with the Mode Switch in REFUEL by...
A. preventing selection of a rod when a different rod is already withdrawn.
B. inserting a rod withdrawal block if a rod is selected and fuel is loaded in that control cell.
C. inserting a rod withdrawal block if the Refueling Platform is moved over the core to remove a fuel assembly.
D. having the Rod Pattern Controller enforce control rod movements in accordance with a prescribed sequence.
Answer: A
Answer Explanation A is correct - The refueling interlocks are as follows:
- ITS B3.9.2 Refuel Position One-Rod-Out-Interlock and CPS 9090.01 REFUELING INTERLOCKS OPERABILITY TEST/ ONE ROD OUT INTERLOCK OPERABILITY section 8.1 - Refuel Position One-Rod-Out Interlock - restricts the movement of control rods to reinforce unit procedures that prevent the reactor from becoming critical during refueling operations. During refueling operations, no more than one control rod is permitted to be withdrawn by preventing the selection of a second control rod for movement when any other control rod is not fully inserted.
- ITS B3.9.1 Refueling Equipment Interlocks and CPS 9090.01 section 8.2 - Fuel Grapple Position Interlock/Channel 1 - verifies the following:
- a control rod cannot be withdrawn with the fuel grapple loaded and positioned over the reactor vessel, and
- the loaded fuel grapple cannot be lowered or bridge moved with a control rod withdrawn
verifies the following:
- a control rod cannot be withdrawn with the fuel grapple loaded and positioned over the reactor vessel, and
- the loaded fuel grapple cannot be lowered or bridge moved with a control rod withdrawn Distracters B is incorrect but plausible if the examinee fails to recall that a rod block is only inserted if the fuel grapple is loaded and positioned over the reactor vessel. RC&IS does not receive input for the status of fuel loading in a control cell.
C is incorrect but plausible if the examinee fails to recall that a rod block is only inserted if the fuel grapple is loaded and the refueling bridge is over the reactor. A control rod withdrawal block is not enforced by RC&IS until the Refueling Platform is positioned over the core with a loaded hoist. The purpose of this interlock is to prevent loading fuel into a control cell where the control rod may be withdrawn.
D is incorrect but plausible if the examinee confuses the provisions of ITS 3.10.6 Multiple Control Rod Withdrawal - Refueling with the refueling interlocks. ITS 3.10.6 allows the position interlocks for multiple control rods to be bypassed to allow for withdrawal of these control rods and/or removal of associated control rod drives provided the specific requirements of 3.10.6 (including fuel loading in compliance with an approved spiral reload sequence) are followed.
The spiral reload sequence is enforced administratively; no automatic actions or interlocks enforce the loading sequence. This answer would also be correct if the Reactor Mode Switch were in Run or Startup/Hot Standby with reactor power less than or equal to 16.7%.
KA Justification - this question meets the KA because the examinee has to demonstrate knowledge of the RCIS interlocks that are enforced to prevent refueling accidents to answer the question.
Cog Level Justification - this is a low cog question written at the memory level. The examinee has to recall the function of the refueling interlocks to answer the question (1-I).
Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269325 User-Defined ID: CL-ILT-1269325 Cross Reference Number:
The Rod Control & Information System (RC&IS) prevents an Topic:
inadvertent criticality during refuelin...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with ITS B3.9.2 Rev. 0 Revision Number: ITS B3.9.1 Rev. 2-9 ITS 3.10.6 Amendment 95 CPS 9090.01 Rev. 34a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure ITS B3.9.2 ON-## not provided) ITS B3.9.1 ITS 3.10.6 CPS 9090.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1I)
KA Data KA Number / System Name: 295023 Refueling Accidents Category / KA Statement: AK2. Knowledge of the interrelations between REFUELING ACCIDENTS and the following: AK2.04 RMCS/Rod control and information system RO Value: 3.2 SRO Value: 3.4 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
20 ID: 1650250 Points: 1.00 The plant was operating at rated thermal power when the following alarms were received:
- 1RIX-PR037 CCW Hx Process Rad Monitor (PRM) (indicating tile is yellow).
- 5000-1C F-D INLET TEMP HI 140°F NO other alarms were received.
Trend data for 1RIX-PR037 is slowly rising and is NOT due to a spike.
Which of the following graphics show the expected response of the Reactor Water Cleanup (RT) System to these conditions? (Duplicate graphic is attached.)
A B
C D
A. Graphic A B. Graphic B C. Graphic C D. Graphic D Answer: A
Answer Explanation A is correct:
The RWCU Non-Regenerative Heat Exchangers are cooled by the Component Cooling Water System (CCW). A partial loss of CCW caused by a tube leak will cause NRHX effluent temperature and 1RIX-PR037 radiation levels to rise. The effluent of the NRHXs is used to cool the water entering the RWCU system Filter Demineralizers which are filled with resin which are susceptible to damage if overheated. To prevent this, if the Filter Demineralizer inlet temperature reaches 140°F, 1G33-F004 RWCU Suct Outbd Isol valve will automatically close to interrupt flow to the filter demineralizers as described below.
Receipt of annunciator 5000-1C F-D INLET TEMP HI 140°F will cause the following:
- Trip of the running RWCU Pumps
- Filter Demin in service swap to HOLD mode B is incorrect but plausible if the examinee incorrectly recalls that a high F-D inlet temperature will cause the inboard isolation valve 1G33-F001 RWCU Suct Inbd Isol) to close instead of the outboard isolation valve 1G33-F004.
C is incorrect but plausible if the examinee incorrectly believes that both 1G33-F001 & F004 will automatically close when F-D Inlet Temperature reaches 140°F.
D is incorrect but plausible if the examinee incorrectly believes that a high F-D inlet temperature will result in a complete Group 4 RWCU system isolation. The graphic shows all RT primary containment isolation valves closed.
KA justification - this question meets the KA because the examinee has to show the ability to monitor the RT system (affected system) during a partial loss of CCW to the RT NRHx to answer the question.
Cog level justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to analyze the conditions in the stem and then choosing the graphic that represents the predicted outcome (3-PEO).
Question 20 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1650250 User-Defined ID: CL-ILT-1650250 Cross Reference Number:
The plant was operating at rated thermal power when the following alarms were received:
Topic:
1RIX-PR0 Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 5000.01 (1C) Rev. 26 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 5000.01 (1C)
ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 295018 Partial or Complete Loss of Component Cooling Water Category / KA Statement: AA1. Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : AA1.03 Affected systems so as to isolate damaged portions RO Value: 3.3 SRO Value: 3.4 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
21 ID: 1269430 Points: 1.00 The plant was operating at rated thermal power when annunciator 5013-5D HIGH-HIGH LEVEL FLR/EQUIP DRN SUMP - AUX BLDG was received. Upon investigation, the following computer point indications were observed:
Computer Point In Alarm?
CM-BC815: LPCS Pump Rm Sump Yes CM-BC814: RHR A Rm Sump Yes CM-BC816: RHR B Rm Sump No CM-BC812: RHR C Rm Sump No CM-BC813: RCIC Pump Rm Sump No CM-DC802: Aux Bldg Sump No Suppression Pool level is indicating 18' 10" and lowering at 1"/min.
Based on the above conditions, _____(1)_____ is/are required to be entered.
The general mitigating strategies required during this event are performed to _____(2)_____.
A. (1) EOP-6 Primary Containment Control ONLY (2) prevent discharging steam through the horizontal vents in the suppression pool ONLY B. (1) EOP-6 Primary Containment Control ONLY (2) prevent flooding equipment necessary for safe operation of the plant AND to prevent discharging steam through the horizontal vents in the suppression pool.
C. (1) EOP-6 Primary Containment Control AND EOP-8 Secondary Containment Control (2) prevent discharging steam through the horizontal vents in the suppression pool ONLY D. (1) EOP-6 Primary Containment Control AND EOP-8 Secondary Containment Control (2) prevent flooding equipment necessary for safe operation of the plant AND to prevent discharging steam through the horizontal vents in the suppression pool.
Answer: D Answer Explanation
D is correct:
Part 1 Per CPS 4402.01 Primary Containment Control, EOP-6 is required to be entered if Suppression Pool Level is below 18' 11".
Per CPS 4406.01 Secondary Containment Control, EOP-8 is entered whenever floor drain sump level is above max normal (Table V). Table V lists LPCS computer point CM-BC815, RHR A computer point CM-BC814 and annunciator 5013-5D as indications used to determine if the entry condition has been exceeded.
Therefore, for part 1 of the question, EOP-6 and EOP-8 entry conditions have been exceeded.
Part 2 Per CPS 4304.01 Flooding Table 2: Suppression Pool Leak/ECCS Room Equalization Levels, the expected final suppression pool level would be ~ 14' 4" based on the leak in the LPCS pump room.
Per CPS 4402.01 EOP-6 Primary Containment Control, "IF......still cannot hold suppression pool level above 15' 1", THEN......BLOWDOWN".
Per EOP-TB discussion on the Heat Capacity Limit (page 8-21), the lowest curve on the Heat Capacity Limit corresponds to a suppression pool level of 15 ft. 1 in. (15.1 ft), or two feet above the top of the horizontal vents. If a loss of coolant accident occurs with level below this value, steam discharged through the horizontal vents may not be completely condensed and containment pressure could exceed structural limits.
Per EOP-TB discussion on EOP-8 Secondary Containment Control (page 9-5), "high area radiation, high VG exhaust radiation, high fuel building ventilation exhaust radiation, and high sump levels are also indications of a break into the secondary containment.
High radiation levels may limit access to the secondary containment and to the equipment in it. Water collecting in sumps could overflow into secondary containment spaces and ultimately flood equipment necessary for safe operation of the plant (causing electrical grounds/circuit malfunctions)". EOP-8 and CPS 4304.01 contain mitigating actions to isolate discharges into affected areas containing safe shutdown equipment.
Distractors A is incorrect but plausible if the examinee fails to determine that EOP-8 entry conditions have been exceeded and also fails to recall the mitigating actions contained in EOP-8 and CPS 4304.01 to prevent flooding areas containing safe shutdown equipment. The candidate may select this response if he/she believes the suppression pool leak is unisolable, and therefore there are no actions contained in CPS 4304.01 Flooding that will mitigate the event.
B is incorrect but plausible if the examinee fails to determine that EOP-8 entry conditions have been exceeded.
C is incorrect but plausible if the examinee fails to recall the mitigating actions contained in EOP-8 and CPS 4304.01 to prevent flooding areas containing safe shutdown equipment. The candidate may select this response if he/she believes the suppression pool leak is unisolable, and therefore there are no actions contained in CPS 4304.01 Flooding that will mitigate the event.
KA Justification - this question meets the KA because the examinee has to demonstrate knowledge of the mitigation strategies employed during events causing flooding into the Secondary Containment to answer the question.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee has to analyze several parameters in the stem and then determine the mitigating strategies that are required based on that analysis (3-SPK).
Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269430 User-Defined ID: CL-ILT-1269430 Cross Reference Number:
The plant was operating at rated thermal power when Topic:
annunciator 5013-5D HIGH-HIGH LEVEL FLR/EQUIP D Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 5013.05 (5D) Rev.
Revision Number: 27a
- CPS 4402.01 Rev. 30
- CPS 4406.01 Rev. 30
- EOP-TB Rev. 007
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 5013.05 (5D)
ON-## not provided)
- CPS 4402.01
- CPS 4406.01
- CPS 4304.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level High (3-SPK)
KA Data KA Number / System Name: 295036 Secondary Containment High Sump / Area Water Level Category / KA Statement: EK1. Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL : EK1.02 Electrical ground/ circuit malfunction RO Value: 2.6 SRO Value: 2.8 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.8 to 41.10 10CFR55-43 (SRO) Data: NA
22 ID: 1269431 Points: 1.00 The plant is operating at rated thermal power with spent fuel movements in progress in the Fuel Building.
All plant ventilation systems are operating in their normal at power alignments.
Then, a dropped fuel bundle occurred in the Fuel Building. Fuel Building exhaust radiation level is currently 6 mr/hr and rising.
What would be the operational implication if Fuel Building radiation level reached 12 mr/hr?
A. Fuel Building area temperatures would rise.
B. Primary Containment ventilation would be lost.
C. Secondary Containment integrity would be lost.
D. Off-site radiation levels would approach release limits.
Answer: A Answer Explanation A is correct - per CPS 4001.02C001, FB Exhaust Radiation at 10 mr/hr will result in a Group 19 isolation of the VF system. Per 5050/52-7F Hi Rad Initiation SGTS Div 1/2, SGTS Train A and B will automatically initiate when FB Exhaust Radiation reaches 10 mr/hr. Since the VG system does not provide cooling to the Fuel Building, Fuel Building area temperatures will rise, but FB/Secondary Containment differential pressure will be maintained.
Distracters B is incorrect but plausible if the examinee incorrectly determines that high radiation conditions in the Fuel Building will cause the Containment Building Ventilation systems to shutdown. A group 10 and 16 isolation of the containment and drywell ventilation isolation valves only occurs under the following conditions:
- RPV Level Low - Level 2
- Drywell Pressure - High
- CNMT Bldg Exh Rad - High (100 mr/hr)
- CNMT Bldg Fuel Transfer Pool Vent Plenum Radiation - High (100 mr/hr)
Since none of those conditions have been met, containment building ventilation is unaffected.
C is incorrect but plausible if the examinee confuses the loss of secondary containment cooling with secondary containment integrity. Secondary containment integrity is maintained by maintaining secondary containment differential pressure within specifications. Since the VG system will auto start as a result of the conditions in the stem, secondary containment dP will be maintained.
D is incorrect but plausible if the examinee fails to determine that VG will auto start as a result of the conditions in the stem, and determines that without secondary containment a ground level radiation release would occur. Since VG automatically starts, a rise in the off-site release rate will not occur as a result of the conditions in the stem.
KA Justification - this question meets the KA because the examinee has to demonstrate knowledge of the impact of a loss of Fuel Building Ventilation on secondary containment temperatures to answer the question.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee has to determine how the change in rad levels will impact secondary containment parameters (temperature) to answer the question (2-RI/DS).
Question 22 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269431 User-Defined ID: CL-ILT-1269431 Cross Reference Number:
The plant is operating at rated thermal power with spent fuel Topic:
movements in progress in the Fuel Bui Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 4001.02C001 Rev.
Revision Number: 16
- CPS 5050.07 (7F) Rev. 33
- CPS 5052.07 (7F) Rev.
33e Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-LC-0924)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data Table.
History: (i.e. Modified distractor Changed distracter A to b to make plausible based on "Primary Containment OTPS review) Ventilation would be lost".
Added distracter plausibility statements. Added KA and Cog Level justification statements.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 4001.02C001 ON-## not provided)
- CPS 5050.07 (7F)
- CPS 5052.07 (7F)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level High (2-RI/DS)
KA Data KA Number / System Name: 295032 High Secondary Containment Area Temperature Category / KA Statement: EK2. Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA TEMPERATURE and the following: EK2.02 Secondary containment ventilation RO Value: 3.6 SRO Value: 3.7 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
23 ID: 1269435 Points: 1.00 Plant conditions are as follows:
- The Reactor is in Mode 2 at 7% power.
- Motor Drive Reactor Feed Pump (MDRFP) is unavailable.
- Turbine Driven Reactor Feed Pump (TDRFP) 1A is feeding the Reactor vessel.
- Main Turbine Shell and Chest warming is in progress.
THEN, a plant transient occurs:
- Reactor Water Level rises to 56 inches before turning.
- Reactor power rises to 12% before turning.
(1) Which of the following identifies action(s) that will occur as a result of these conditions, AND (2) Why?
A. (1) TDRFP trip ONLY (2) Protect the Main Turbine from damage due to moisture carry-over from the reactor vessel into the Main Steam Lines.
B. (1) TDRFP trip ONLY (2) Ensure the Minimum Critical Power Ratio Safety Limit is not exceeded due to the introduction of a significant amount of relatively cold feedwater.
C. (1) TDRFP trip AND Reactor SCRAM (2) Protect the Main Turbine from damage due to moisture carry-over from the reactor vessel into the Main Steam Lines.
D. (1) TDRFP trip AND Reactor SCRAM (2) Ensure the Minimum Critical Power Ratio Safety Limit is not exceeded due to the introduction of a significant amount of relatively cold feedwater.
Answer: A
Answer Explanation A is correct. Per CPS 5002.01 Alarm Panel 5002 Annunciators - Row 1, 5002-1C TRIPPED REACTOR FEED PUMP TURBINE 1A, one possible cause of TDRFP 1A to trip is high reactor water level (Level 8, 52 in).
Per SER TS Amend 95 ITS, the feedwater pump/turbine trip on level 8 is a BWR/6 design feature that anticipates a scram and protects the main turbine from damage due to moisture carry-over from the reactor vessel into the main steam lines by anticipating a vessel overfill event.
Per CPS 3001.01 Preparation for Startup & Approach to Critical and based on plant conditions (MODE 2 at 7% power), the MODE switch is in STARTUP/STANDBY.
Per CPS 3305.01 Reactor Protective System Appendix A: RPS TRIP SET POINTS, for the RPV High Level 8 trip to be active, the MODE switch must be in RUN. Additionally, the APRM Setdown Flux High trip setpoint is 15%.
Incorrect Responses:
B is incorrect but plausible. The candidate may select this response if he/she recognizes that the TDRFP 1A will trip on level 8 but the potential of "introducing relatively cold feedwater into the vessel" leads the candidate to incorrectly choose exceeding the MCPR safety limit as the reason for the TDRFP level 8 trip.
C is incorrect but plausible. The candidate may select this response if he/she fails to recall that the RPV Level 8 Scram signal is bypassed with the RMS not in Run while also mistakenly believing that the Reactor scram is initiated to protect the Main Turbine. This answer would be correct if the RMS were in Run (Mode 1).
D is incorrect but plausible. The candidate may select this response if he/she fails to recall that the RPV Level 8 Scram signal is bypassed with the RMS not in Run but recognizes the correct reason for the RPV High Level 8 scram.
KA justification - this question meets the KA because the examinee must demonstrate knowledge of the reason for the reactor feed pump trip with regard to high reactor water level.
Cog level justification - this question is a high cog question written at the comprehension level.
The examinee must analyze conditions presented in the stem of the question, determine the correct consequences based on the plant transient and the implications of those consequences.
Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269435 User-Defined ID: CL-ILT-1269435 Cross Reference Number:
Plant conditions are as follows:
Topic:
The Reactor is in Mode 2 at 7% power.
Motor Drive Reactor Feed Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 5002.01 Rev. 33e Revision Number: ITS SER Amend. 95 CPS 3001.01 Rev. 27c CPS 3305.01 Rev. 11e Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 5002.01 ON-## not provided) ITS SER Amend. 95 CPS 3001.01 CPS 3305.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 295008 High Reactor Water Level Category / KA Statement: AK3. Knowledge of the reasons for the following responses as they apply to HIGH REACTOR WATER LEVEL: AK3.04 Reactor feed pump trip: Plant-Specific RO Value: 3.3 SRO Value: 3.5 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
24 ID: 1269869 Points: 1.00 The plant was operating at rated thermal power with Drywell Chiller 'B' operating when multiple High Drywell Pressure annunciators were received in the MCR.
Which of the following describes the impact of these conditions on Drywell Cooling (VP) and Supplemental Drywell Cooling (from the Plant Chilled Water (WO) System)?
Drywell Cooling (VP) will be _____(1)_____.
Supplemental Drywell Cooling (WO) will be _____(2)_____.
A. (1) lost (2) lost B. (1) lost (2) unaffected C. (1) unaffected (2) lost D. (1) unaffected (2) unaffected Answer: A
Answer Explanation A is correct:
Per CPS 4001.02C001 Automatic Isolation Checklist, Drywell Pressure - High conditions will result in Group 11 and 17 isolations.
Group 11 BOP (FROM RHR) and Group 17 BOP Chill Water consists of the following valves:
- Group 11 Valves
- 1VP0015A DW Ch Wtr 1A Rtrn Outbd Isol Vlv
- 1VP004A DW Ch Wtr 1A Outbd Isol Vlv
- 1VP015B DW Ch Wtr 1B Rtrn Outbd Isol Vlv
- 1VP004B DW Ch Wtr 1B Outbd Isol Vlv
- 1WO002A Plant Ch Wtr Outbd Isol Vlv
- 1WO001A Plant Ch Wtr Outbd Isol Vlv
- 1VP014A DW Ch Wtr 1A Rtrn Inbd Isol Vlv
- 1VP005A DW Ch Wtr 1A Inbd Isol Vlv
- 1VP014B DW Ch Wtr 1B Rtrn Inbd Isol Vlv
- 1VP005B DW Ch Wtr 1B Inbd Isol Vlv
- 1WO002B Plant Ch Wtr Inbd Isol Vlv
- 1WO001B Plant Ch Wtr Inbd Isol Vlv
- Group 17
- 1WO551A Plant Ch Wtr Outbd Isol Vlv
- 1WO552A Plant Ch Wtr Outbd Isol Vlv
- 1WO551B Plant Ch Wtr Inbd Isol Vlv
- 1WO552B Plant Ch Wtr Inbd Isol Vlv The chilled water flowpath for the Drywell Cooling (VP) System flows through the Group 11 isolation valves listed above, so a Group 11 isolation will result in a loss of VP cooling to the Drywell.
The Supplemental DW Cooling system uses WO through the Group 17 isolation valves, so a Group 17 isolation will result in a loss of Supplemental Cooling to the Drywell.
B is incorrect but plausible if the examinee correctly determines that Group 11 Isolation Valves will automatically close on High DW Pressure, but incorrectly believes that Group 17 is unaffected. High DW pressure affects 11 of the 20 CRVICS Isolation Groups.
C is incorrect but plausible if the examinee correctly determines that Group 17 Isolation Valves will automatically close on High DW Pressure, but incorrectly believes that Group 11 is unaffected. High DW pressure affects 11 of the 20 CRVICS Isolation Groups.
D is incorrect but plausible if the examinee incorrectly believes that Group 11 and Group 17 is unaffected by High DW Pressure conditions. High DW pressure affects 11 of the 20 CRVICS Isolation Groups.
KA justification - this question meets the KA because the examinee is required to demonstrate the ability to monitor the Drywell Cooling Systems (VP and Supplemental WO) by determining the impact to these systems during high DW pressure conditions.
Cog Level Justification - this question is a low cog question written at the memory level. The examinee has to recall how system interlocks are impacted by conditions to answer the question (1-I).
Question 24 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269869 User-Defined ID: CL-ILT-1269869 Cross Reference Number:
The plant was operating at rated thermal power with Drywell Topic:
Chiller 'B' operating when multiple ...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 4001.02C001 Rev. 16 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New question Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4001.02C001 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 295010 High Drywell Pressure Category / KA Statement: AA1. Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE : AA1.01 Drywell ventilation/cooling RO Value: 3.4 SRO Value: 3.5 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
25 ID: 1269871 Points: 1.00 The plant was operating at power with conditions as follows:
Parameter Value Reactor Power 84%
Core Flow 66.6 Mlbh Reactor Steam Dome Pressure 988 psig THEN, a Steam Bypass Pressure Regulator malfunction occurred resulting in the following conditions:
Parameter Value Reactor Power 88%
Core Flow 66.6 Mlbh Reactor Steam Dome Pressure 1040 psig Based on these conditions:
Entry into ITS 3.2.1 APLHGR, ITS 3.2.2 MCPR, AND ITS 3.2.3 LHGR _____(1)_____ required.
Entry into ITS 3.4.12 Reactor Steam Dome Pressure _____(2)_____ required.
A. 1) is
- 2) is B. 1) is
- 2) is NOT C. 1) is NOT
- 2) is D. 1) is NOT
- 2) is NOT Answer: B
Answer Explanation B is correct:
- Per CPS 3005.01 Unit Power Changes Figure 1: Stability Control & Power/Flow Operating Map, the pressure regulator malfunction has caused reactor power to rise above the MELLLA limit (100.7% FCL).
- Per CPS 3005.01 Unit Power Changes Limitation 6.5 MELLLA Limit Operational Concerns, if the MELLLA Limit is exceeded, enter the following LCO Actions: LCO 3.2.1 APLHGR, LCO 3.2.2. MCPR, and LCO 3.2.3 LHGR.
- Per ITS 3.4.12 Reactor Steam Dome Pressure, the reactor steam dome pressure shall be 1045 psig, so entry into ITS 3.4.12 is NOT required.
A is incorrect but plausible if the examinee fails to recall the ITS 3.4.12 limit for reactor steam dome pressure (1045 psig) and determines that 3.4.12 must be entered.
C is incorrect but plausible if the examinee fails to determine that the MELLLA limit has been violated or that ITS 3.2.1, 3.2.2, and 3.2.3 must be entered when the MELLLA limit has been violated and also fails to recall the ITS 3.4.12 limit for reactor steam dome pressure (1045 psig) and determines that 3.4.12 must be entered.
D is incorrect but plausible if the examinee fails to determine that the MELLLA limit has been violated or that ITS 3.2.1, 3.2.2, and 3.2.3 must be entered when the MELLLA limit has been violated.
KA Justification - this question meets the KA because the examinee has to intepret the parameters in the stem and determine the impact of the high reactor pressure condition on reactor operation with regards to the power to flow map to answer the question.
Cog Level Justification - this is a low cog question written at the memory level. The examinee has to recall limitations in a procedure and in Technical Specifications to answer the question (1-F).
Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269871 User-Defined ID: CL-ILT-1269871 Cross Reference Number:
The plant was operating at power with conditions as follows:
Topic:
Parameter Value Reactor Power 8...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 3005.01 Rev. 42d Revision Number:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. CPS 3005.01 Figure 1 Stability ABN-##) Control & Power/Flow Operating Map Excluded
Reference:
(i.e. Ensure
- CPS 3005.01 (with the ON-## not provided) exception of Figure 1)
- ITS 3.4.12 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 295007 High Reactor Pressure Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE : AA2.02 Reactor power RO Value: 4.1 SRO Value: 4.1 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
26 ID: 1269188 Points: 1.00 The plant is operating at rated thermal power with DW temperature at 105°F.
A reactor coolant leak is causing Drywell (DW) temperature to RISE.
Under these conditions, annunciator 5004-3F SPDS CSF ALARM will be received when DW temperature first reaches _____(1)_____, requiring entry into EOP(s) _____(2)_____.
EOP RPV Control EOP Primary Containment Control A. (1) 122°F (2) EOP-6 ONLY B. (1) 150°F (2) EOP-6 ONLY C. (1) 122°F (2) EOP-1 AND EOP-6 D. (1) 150°F (2) EOP-1 AND EOP-6 Answer: B Answer Explanation B is correct - Per 5004-3F SPDS CSF ALARM, the alarm setpoint for DW temperature is 150°F which corresponds to the EOP-6 Primary Containment Control entry condition on high DW temperature.
A is incorrect but plausible - 122°F is the EOP-6 entry condition and SPDS CSF Alarm setpoint for high containment temperature.
C is incorrect but plausible - 122°F is the EOP-6 entry condition and SPDS CSF Alarm setpoint for high containment temperature. High DW pressure, not temperature, is an entry condition for EOP-1.
D is incorrect but plausible - High DW pressure, not temperature, is an entry condition for EOP-1.
KA Justification - this question meets the KA because the examinee has to determine the value of DW temperature requiring entry into the Emergency Operating Procedures and which EOP-6 to enter to answer the question.
Cog Level Justification - this is a low cog question written at the memory level - requires recall of alarm setpoint and EOP entry conditions.
Question 26 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269188 User-Defined ID: CL-ILT-1269188 Cross Reference Number:
The plant is operating at rated thermal power with DW temperature at 105°F.
Topic:
A reactor coolant le Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- 5004.03 (3F) Rev. 28a Revision Number:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Bank (CL-ILT-A14016)
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- 5004.03 (3F)
ON-## not provided)
- CPS 4402.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1I)
KA Data KA Number / System Name: 295012 High Drywell Temperature Category / KA Statement: 2.4.1 Knowledge of EOP entry conditions and immediate action steps.
RO Value: 4.6 SRO Value: 4.8 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
27 ID: 1269185 Points: 1.00 Suppression pool level is 23 feet.
RPV pressure is 1000 psig.
Opening SRVs under these conditions....
A. may result in missile damage to the Reactor Pressure Vessel.
B. may result in direct pressurization of the Containment.
C. may result in steam entrainment in pump suctions.
D. is the preferred method to depressurize the RPV.
Answer: B
Answer Explanation B is correct. The candidate must apply the initial conditions to Figure Q in order to determine that the plant is operating above the SRV Tail Pipe Limit. Per the EOP Technical Bases, the operation of SRVs while above the SRV Tail Pipe Limit may result in Tail Pipe failure which results in direct pressurization of the containment.
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that the concern is missile damage to the Reactor Pressure Vessel (RPV). The RPV is protected by the reactor shield wall.
C is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that the concern is steam entrainment in pump suctions. NPSH restrictions for the pumps taking suction from the Suppression Pool (RCIC, HPCS, LPCS and RHR Pumps) are listed in CPS 4402.01 Detail Z and are affected by Suppression Pool Level (11') and Suppression Pool temperature (197°F), neither of which are threatened by the conditions presented in the stem.
D is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that the initial conditions, when applied to Figure Q, determine that the plant is operating in the OK region of the SRV Tail Pipe Limit. Based on this determination, opening SRV(s) would be the preferred method to depressurize the RPV.
KA justification - this question meets the KA because the examinee has to demonstrate knowledge of the impact of operating SRVs during a high Suppression Pool Level condition to answer the question.
Cog Level justification - this is a high cog question written at the analysis and comprehension level because the candidate must first apply the initial conditions to Figure Q in order to determine that the plant is operating above the SRV Tail Pipe Limit, and then apply his/her knowledge of the EOP Technical Bases to determine the correct effect (3-SPK).
Question 27 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269185 User-Defined ID: CL-ILT-1269185 Cross Reference Number:
Suppression pool level is 23 feet.
RPV pressure is 1000 psig.
Topic:
Opening SRVs under these...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- EOP-TB Rev. 007 Revision Number:
Question History: (i.e. LGS NRC- ILT 10-1 NRC Exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-N11060)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated the General Data History: (i.e. Modified distractor Table. Revised the cog level b to make plausible based on and KA justification OTPS review) statements.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- EOP-TB ON-## not provided)
- CPS 4402.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level High (3-SPK)
KA Data KA Number / System Name: 295029 High Suppression Pool Water Level Category / KA Statement: EK2. Knowledge of the interrelations between HIGH SUPPRESSION POOL WATER LEVEL and the following: EK2.06 SRV's and discharge piping RO Value: 3.4 SRO Value: 3.5 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
28 ID: 1270009 Points: 1.00 A toxic gas event has occurred which required MCR evacuation.
- A manual Group 1 isolation has been completed IAW CPS 4003.01 Remote Shutdown (RS).
- Remote Shutdown Panel Transfer Switches C61-S10 AND C61-HS527 have been positioned as shown in the graphic below.
Based on these conditions and assuming ONLY AUTOMATIC SRV actuation, the MAXIMUM RPV pressure that would indicate normal RPV pressure response is _____ psig.
SRV Pressure Relief Low-Low Setpoint Spring Setpoint Setpoint (psig) (psig) (psig)
F041A 1123 1165 F047A 1113 1180 F047B 1113 1180 F041B 1123 1165 F051B 1113 1113 1190 F041F 1123 1165 F047F 1113 1113 1180 F041C 1123 1165 F051C 1113 1073 1190 F041G 1123 1165 F047C 1113 1180 F041L 1123 1165 F051G 1113 1113 1190 F041D 1123 1165 F047D 1113 1180 F051D 1103 1033 1190
A. 1073 B. 1103 C. 1113 D. 1190 Answer: C Answer Explanation C is correct:
Per the graphic in the stem, control for SRVs F051C, F051G, and F051D have been transferred to the Remote Shutdown Panel (RSP).
Per N-CL-OPS-200000 Remote Shutdown, these three SRVs will NOT operate in the LLS pressure relief nor ADS modes when controlled from the RSP.
CPS 5066.06 (6C) LOW-LOW SETPOINT DIVISION 2 SEALED IN lists the low-low set setpoints for SRVs F051D, F051C, F047F, F051B, and F051G. N-CL-OPS-239001 Main Steam Attachments F and G list the lift setpoints for all 16 SRVs as stated in the stem.
Since the RSP transfer switches C61-S10 and C61-HS527 only affect SRVs F051C, F051G, and F051D, the remaining SRVs will lift in either pressure relief or low-low set modes. Referring to Attachment F and G, this will result in the lifting of 6 SRVs (F047A, F047B, F051B, F047F, F047C, and F047D) at 1113 psig reactor pressure.
Distracters A is incorrect but plausible if the examinee incorrectly believes that F051C will function in Low-Low Set Mode and lift at 1073 psig. With control switches C61-S10 and C61-HS527 in Emerg, the Low-Low Set function for F051C is not functional.
B is incorrect but plausible if the examinee incorrectly believes that the Relief Function for F051D is functional, resulting in lifting at 1103 psig.
D is incorrect but plausible if the examinee incorrectly believes that only the SRVs controlled by C61-S10 and C61-HS527 (F051C, F051G, and F051D) will open when their lowest Spring Setpoint (Safety Mode) is reached (1190 psig).
KA justification - this question meets the KA because the examinee has to demonstrate knowledge of the pressure control response of the Safety Relief Valves when operating at the Remote Shutdown Panel.
Cog Level justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to determine how Safety Relief Valve function is affected by conditions shown in a graphic, and then predict how reactor pressure response is affected based on that analysis (3-SPK).
Question 28 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1270009 User-Defined ID: CL-ILT-1270009 Cross Reference Number:
A toxic gas event has occurred which required MCR evacuation.
Topic:
A manual Group 1 isolation has bee Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 4003.01 Rev. 17c Revision Number:
- CPS 5066.06 (6C)
- N-CL-OPS-200000 Rev.
003
- N-CL-OPS-239001 Rev.
004 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) usage.
Question Source: (i.e. New, New question Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 4003.01 ON-## not provided)
- N-CL-OPS-200000
- N-CL-OPS-239001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 239002 Relief/Safety Valves Category / KA Statement: K5. Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES : K5.01 Relief function of SRV operation RO Value: 3.4 SRO Value: 3.5 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
29 ID: 1269183 Points: 1.00 The indications in _____(1)_____ show the normal, standby alignment for the Standby Liquid Control (SLC) System. The SLC Manual Shutoff Valve shown in the graphics below isolates the SLC flowpath to the _____(2)_____.
Graphic 1 Graphic 2 A. (1) Graphic 1 (2) HPCS Injection Line B. (1) Graphic 1 (2) Core Plate Differential Pressure Indication Sensing Line C. (1) Graphic 2 (2) HPCS Injection Line D. (1) Graphic 2 (2) Core Plate Differential Pressure Indication Sensing Line Answer: B
Answer Explanation B is correct:
Per M05-1077-1 Standby Liquid System (SC), the SC system has two injection flowpaths, one via the HPCS Injection Line via 1C41-F334, and the other via the Nuclear Boiler System (core plate differential pressure sensing line) via 1C41-F008. The normal injection path is via the HPCS Injection Line via 1C41-F334.
Per CPS 3314.01V001 STANDBY LIQUID CONTROL VALVE LINEUP, 1C41-F008 SLC Injection
- Bottom Head Valve is normally locked closed. 1C41-F334 SLC Injection - HPCS Line is normally locked open.
Per M05-1077-1 at D-2, 1C41-F008 SLC Injection - Bottom Head Valve is shown as normally locked closed and is equipped with position indication lights (1C41A-DS006 & 7) on 1H13-P601.
Per M05-1071-1 at B-8, this line connects to the Core Plate Differential Pressure Sensing Line via line 1SC02DD 3.
Per M05-1077-1 at E-2, 1C41-F334 is shown as a normally locked open valve discharging to the HPCS system (M05-1074 at E-8).
Therefore, the SLC Manual Shutoff Valve indicating light on 1H13-P601 shows the position for 1C41-F008 which is a normally locked closed valve injecting to the Core Plate Differential Pressure Indication Sensing Line (choice B).
A is incorrect but plausible if the examinee incorrectly recalls that the SLC Manual Shutoff Valve light on 1H13-P601 indicates the position of 1C41-F334 and that the HPCS Injection Line is the alternate injection path for SLC.
C is incorrect but plausible if the examinee incorrectly recalls that the SLC Manual Shutoff Valve indicating light on 1H13-P601 indicates the position of 1C41-F334 and correctly recalls that the HPCS Injection Line is the normal injection path for SLC.
D is incorrect but plausible if the examinee correctly recalls that the SLC Manual Shutoff Valve indicating light on 1H13-P601 indicates the position of 1C41-F008 but incorrectly recalls that the Core Plate Differential Pressure Indication Sensing Line is the normal injection path for SLC.
KA justification - this question meets the KA because the examinee must have knowledge of the physical connection between the SLC System and the Core Plate Differential Pressure Indication line to answer the question.
Cog Level justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to analyze two graphics in the stem and apply knowledge of the system alignment and flowpaths to answer the question (3-SPK).
Aux Bldg 781 East DC MCC 1A, 1DC13E (12A) 125 VDC Dist Panel ckt:
Ckt #22 SLC Div 1 Annunciator Optical Isol AB MCC 1A1, 1AP72E 1C41-C001A (3A) Standby Liquid Control Pump 1A (9B) 208/120V Distribution Panel ckt:
Ckt #25 SLC MOV Test (11C) 120V FP Distribution Panel ckt:
Ckt #9 Motor Heater To SLC Pump 1A 1C41-C001A Ckt #12 Standby Liquid Control System Squib Valve 1C41-F004A
Question 29 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269183 User-Defined ID: CL-ILT-1269183 Cross Reference Number:
The indications in _____(1)_____ show the normal, standby Topic:
alignment for the Standby Liquid Control Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- M05-1077-1 Rev. AC Revision Number:
- M05-1071-1 Rev. AE
- CPS 3314.01V001 Rev.
10a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- M05-1077-1 ON-## not provided)
- M05-1071-1
- CPS 3314.01V001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 211000 Standby Liquid Control System Category / KA Statement: K1. Knowledge of the physical connections and/or cause-effect relationships between STANDBY LIQUID CONTROL SYSTEM and the following:
K1.02 Core plate differential pressure indication RO Value: 2.7 SRO Value: 2.7 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.2 to 41.9 10CFR55-43 (SRO) Data: NA
30 ID: 1269178 Points: 1.00 A reactor startup was in progress when multiple annunciators were received in the Main Control Room (MCR).
THEN, the following indications were observed:
A loss of _____ would cause these indications.
C. Div 2 NSPS Bus (1C71-P001B)
D. "B" RPS Solenoid Bus (1C71-P011B)
Answer: C
Answer Explanation C is correct. Per CPS 3509.01C002 Division 2 NSPS Bus (1C71-P001B) Outage, a loss of the Div 2 NSPS Bus (1C71-P001B) will cause SRM 'B' to deenergize and fail in a tripped condition.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she fails to recognize that even though the Div 2 NSPS Inverter is normally powered from DC MCC 1B, the inverter's static switch will transfer the loads without interruption to the alternate AC supply (CB MCC F2).
B is incorrect but plausible. The candidate may select this response if he/she fails to recognize that AB MCC 1B1 is the alternate AC supply to the Div 4 NSPS Inverter and therefore would have no effect on the Div 2 NSPS Inverter.
D is incorrect but plausible. The candidate may select this response if he/she fails to recognize that the "B" RPS Solenoid Bus powers the Div 2 MSIV and RPS solenoids and therefore would have no effect on the Div 2 NSPS Inverter.
KA justification - this question meets the KA because the examinee has to recognize a loss of a SRM channel based on the graphic presented in the stem and have knowledge of the electrical power supply of the SRM 'B' channel to answer the question.
Cog Level Justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to analyze conditions in the stem to determine a failed SRM channel and then determine the failed electrical power source that would have caused it (2-RI).
Question 30 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269178 User-Defined ID: CL-ILT-1269178 Cross Reference Number:
A reactor startup was in progress when multiple annunciators Topic:
were received in the Main Control R...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3509.01C002 Rev. 13a Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- CPS ILT 10-1 exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-N11024)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table and History: (i.e. Modified distractor KA / Cog Level justifications, b to make plausible based on wdk 5/19/2016 OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3509.01C002 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 215004 Source Range Monitor (SRM) System Category / KA Statement: K2. Knowledge of electrical power supplies to the following: K2.01 SRM channels/detectors RO Value: 2.6 SRO Value: 2.8 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: N/A
31 ID: 1270248 Points: 1.00 A transient has occurred resulting in the indications shown in the graphic below.
Based on these indications, the _____ Initiation/Shutdown Hard Card can NOT be successfully performed.
A. Reactor Core Isolation Cooling (RCIC)
B. Low Pressure Core Spray (LPCS)
C. High Pressure Core Spray (HPCS)
D. Low Pressure Coolant Injection (LPCI) 'C' Answer: B Answer Explanation B is correct:
The image in the stem shows a loss of 480V Unit Substations 1A and A1, which provides power to AB MCC 1A3.
Per CPS 3313.01 Appendix A: LPCS Initiation/Shutdown Hard Card, LPCS initiation is accomplished by:
- Arm and Depress LPCS/LPCI FM RHR A MANUAL INITIATION push-button.
Per CPS 3313.01E001, 1E21-F005 is powered from AB MCC 1A3 (1AP74E) which is de-energized by the conditions provided in the stem.
Therefore, LPCS can NOT be successfully initiated using CPS 3313.01 Appendix A: LPCS Initiation/Shutdown Hard Card.
Distracters:
A is incorrect but plausible if the examinee incorrectly recalls the power sources necessary to initiate RCIC.
Per CPS 3310.01 Appendix C: RCIC Initiation/Shutdown Hard Card, RCIC is initiated as follows:
- As needed, Arm, depress and HOLD depressed the RCIC MANUAL INITIATION push-button until 1E51-F045 begins to open (takes ~ 6 secs).
- Verify:
- Main turbine trips.
- Verify both reactor feed pump turbines trip.
- Start/verify running Gland Seal Air Compressor.
- Monitor RPV level.
Per CPS 3310.01E001, 1E51-F013 and 1E51-F045 are powered from DC MCC 1A and are not impacted by a loss of 480V Unit Substations 1A and A1.
C is incorrect but plausible if the examinee incorrectly recalls the power sources necessary to initiate HPCS.
Per CPS 3309.01 Appendix A: HPCS Initiation/Shutdown Hard Card, HPCS is initiated as follows:
- As needed, Arm and Depress HPCS MANUAL INITIATION push-button.
- Restore and maintain level using:
Per CPS 3309.01E001, the HPCS Pump is powered from 4160V Bus 1C1 (HPCS Switchgear) and 1E22-F004 is powered from HPCS Motor Control Center 1C, neither of which are impacted by a loss of 480V Unit Substations 1A and A1.
D is incorrect but plausible if the examinee incorrectly recalls the power sources necessary to initiate LPCI.
Per CPS 3312.01 Appendix C: LPCI Initiation/Shutdown Hard Card, RHR 'C' is initiated as follows:
- As needed, Arm and Depress
- Verify desired RHR Pump 'C', 1E12-C002C started.
- When RPV pressure < 472 psig:
- Open/verify open 1E12-F042C, LPCI Fm RHR C Shutoff Valve.
- Restore and maintain level using 1E12-F042C, LPCI Fm RHR C Shutoff Valve.
Per CPS 3312.01E001, RHR Pump 'C' and 1E12-F042C are powered from 4160V Bus 1B1 and AB MCC 1B4 respectively, neither of which are impacted by a loss of 480V Unit Substations 1A and A1.
KA justification - this question meets the KA because the examinee has to demonstrate knowledge of the electrical power supply to the LPCS injection valve by determining how loss of power indications in the stem impact the ability of the system to be used to inject water into the RPV to answer the question.
Cog Level justification - this is a high cog question written at the analysis and comprehension level - the examinee must recognize the interaction between the tripped breaker provided in the stem and the impact on MCC loads supplied from the 480V Unit Subs that were lost.
Question 31 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1270248 User-Defined ID: CL-ILT-1270248 Cross Reference Number:
A transient has occurred resulting in the indications shown in the graphic below.
Topic:
Based o...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 3313.01 Rev. 16e Revision Number:
- CPS 3313.01E001 Rev.
11a
- CPS 3310.01 Rev. 29c
- CPS 3310.01E001 Rev.
16
- CPS 3309.01 Rev. 17
- CPS 3309.01E001 Rev. 8
- CPS 3312.01 Rev. 45b
- CPS 3312.01E001 Rev.
17 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 3313.01 ON-## not provided)
- CPS 3313.01E001
- CPS 3310.01
- CPS 3310.01E001
- CPS 3309.01
- CPS 3309.01E001
- CPS 3312.01
- CPS 3312.01E001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 209001 Low Pressure Core Spray System Category / KA Statement: K2. Knowledge of electrical power supplies to the following: K2.02 Valve power RO Value: 2.5 SRO Value: 2.7 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
32 ID: 1269097 Points: 1.00 The reactor was at 92% power when the Main Turbine tripped.
The following 1H13-P680-5004/5005 indications are observed:
1H13-P680-5004 1H13-P680-5005 The control rods fully inserted due to the...
A. ARI Scram Pilot Valves energizing.
B. ARI Scram Pilot Valves de-energizing.
C. Scram Solenoid Valves energizing.
D. Scram Solenoid Valves de-energizing.
Answer: A
Answer Explanation Correct Answer: A - Per CPS 5004.03 Alarm Panel 5004 Annunciators - Row 3 and CPS 5006.01 Alarm Panel 5006 Annunciators - Row 1, Annunciators 5004-3J (DIV 4 HALF SCRAM IB, IIB, IIIB, IVA) and 5006-1C (DIV 4 MANUAL SCRAM TRIP) indicate only Div 4 RPS Channel has tripped.
Per CPS 3305.01 Reactor Protective System, both scram solenoid channels must trip in order to deenergize all the scram solenoids in order to cause a scram. Since at least one of the Scram Solenoid Energized lights (blue) are LIT at P-680 for each division, no other RPS Channel has tripped and therefore RPS has not initiated a scram.
Per CPS 3305.01 Reactor Protection System, Alternate Rod Insertion (ARI) serves to dump the air header supplying the scram valves. Scram air header depressurizes resulting in rod insertion when scram valves OPEN. Since all the rods have inserted ARI would be the only possible method to depressurize the scram air header and insert the control rods. ARI solenoids are required to be energized to cause this action to occur.
Incorrect Responses:
B is incorrect but plausible. The candidate may select this response if he/she recognizes that the scram solenoid valves did NOT actuate the SCRAM but incorrectly believes that the ARI Scram Pilot Valves deenergize to depressurize the scram air header to cause rods to insert (like the scram solenoid valves).
C is incorrect but plausible. The candidate may select this response if he/she fails to recognize that the indications provided in the stem do NOT satisfy the logic to initiate a SCRAM (trip signals for scram are processed by the four divisions of instrument logic whenever any two of the four channels of a monitored variable trip). The candidate also incorrectly believes that the scram solenoid valves energize to trip (like the ARI scram pilot valves).
D is incorrect but plausible. The candidate may select this response if he/she fails to recognize that the indications provided in the stem do NOT satisfy the logic to initiate a SCRAM (trip signals for scram are processed by the four divisions of instrument logic whenever any two of the four channels of a monitored variable trip) but, recognizes that the scram solenoid valves deenergize to OPEN.
KA justification - this question meets the KA because the examinee must have knowledge of the effect that a loss or malfunction of the Reactor Protection System (RPS) (Turbine trip with failure of RPS to actuate with the Mode Switch in RUN) will have on the scram air header solenoid valves in order to determine the correct response.
Cog Level justification - this question is a high cog question written at the comprehension level.
Based on the conditions presented in the stem, the examinee has to recognize the interaction between the RPS, scram solenoids and the ARI systems and what conditions initiated the SCRAM.
Question 32 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269097 User-Defined ID: CL-ILT-1269097 Cross Reference Number:
The reactor was at 92% power when the Main Turbine tripped.
Topic:
The following 1H13-P680-5004/5005 in Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3305.01 Rev. 11e Revision Number: CPS 5004.03 (3J) Rev. 28a CPS 5006.01 (1C) Rev. 32e Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-LC-1050)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table, History: (i.e. Modified distractor improved question stem and b to make plausible based on explanation and added OTPS review) justifications, wdk 5/23/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3305.01 ON-## not provided) CPS 5004.03 CPS 5006.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 212000 Reactor Protection System Category / KA Statement: K3. Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on the following: K3.06 Scram air header solenoid operated valves RO Value: 4.0 SRO Value: 4.1 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
33 ID: 1269072 Points: 1.00 Plant is operating at 72% rated thermal power.
The following annunciators were received:
- 5003-3D - RECIRC MOTOR A WINDING COOLING WATER FLOW LOW
- 5003-3K - RECIRC MOTOR B WINDING COOLING WATER FLOW LOW THEN, the "B" Reactor Operator reports ALL Component Cooling Water Pumps have tripped and WILL NOT restart.
A _____(1)_____ is required.
The Main Steam Isolation Valves will _____(2)_____ the plant cooldown.
A. (1) Rapid Plant Shutdown (2) remain OPEN throughout B. (1) Reactor Scram (2) SHUT during C. (1) Rapid Plant Shutdown (2) SHUT during D. (1) Reactor Scram (2) remain OPEN throughout Answer: B
Answer Explanation B is correct. Per CPS 5003.03 Alarm Panel 5003 Annunciators - Row 3 Sections 5003-3D/3K Operator Actions, IF full CCW Cooling flow is lost to both RR Pumps A & B,
- Within one minute, perform Emergency RR Loop A & B shutdown Additionally, the CCW System provides cooling water to the Service Air Compressors high-efficiency internal air coolers and oil coolers. High or low CCW temperatures would result in abnormal component temperatures and possible damage. A loss of CCW would result in a loss of Service Air/Instrument Air (SA/IA) and a shutdown/scram. SA/IA Compressors will trip on high air outlet temperature or high oil temperature and require an entry into the Loss of Air Off-Normal.
Per CPS 3214.01 Plant Air (IA/SA) Section 8.2.2 Containment Isolation and Recovery, the loss of IA will result in MSIVs to fail closed. MSIVs close at < 70 psig air supply pressure to their accumulators.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she fails to recall that the RR pumps must be shutdown within one (1) minute or otherwise incorrectly believes that a Rapid Plant Shutdown is the correct response to the loss of CCW and further believes that the MSIVs will be unaffected by the impending loss of IA.
C is incorrect but plausible. The candidate may select this response if he/she recognizes that the MSIVs will be affected by the impending loss of IA causing them to fail close but fails to recall that the RR pumps must be shutdown within one (1) minute or otherwise incorrectly believes that a Rapid Plant Shutdown is the correct response to the loss of CCW.
D is incorrect but plausible. The candidate may select this response if he/she recognizes that based on the plant conditions a reactor scram is required but incorrectly believes that the MSIVs will be unaffected by the impending loss of IA or fails to recognize the impending loss of IA.
KA justification - this question meets the KA because the examinee must have knowledge of the effect that a loss or malfunction of the Component Cooling Water (CCW) system will have on system loads (Reactor Recirculation (RR) pumps and Service Air Compressors) in order to determine the correct response.
Cog Level justification - this question is a high cog question written at the comprehension level.
The examinee has to recognize the interaction between the CCW, RR and IA systems upon a loss of CCW, including the consequences/implications to the RR and IA systems.
Question 33 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269072 User-Defined ID: CL-ILT-1269072 Cross Reference Number:
Plant is operating at 72% rated thermal power.
Topic: The following annunciators were received:
5...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 5003.03 (3D) Rev. 29 Revision Number: CPS 5003.03 (3K) Rev. 29 CPS 3214.01 Sect. 8.2.2 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- ILT NRC 10-1 exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-N11054)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data table, History: (i.e. Modified distractor improved explanation and b to make plausible based on added justifications, wdk OTPS review) 5/16/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 5003.03 ON-## not provided) CPS 3214.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 400000 Component Cooling Water System (CCWS)
Category / KA Statement: K3. Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:
K3.01 Loads cooled by CCWS RO Value: 2.9 SRO Value: 3.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
34 ID: 1270108 Points: 1.00 Standby Gas Treatment (VG) System 'A' was manually initiated one hour ago per CPS 3319.01 Standby Gas Treatment System (VG).
Referring to the figures below, which of the four figures indicate that VG train 'A' is operating properly?
1 2
3 4
A. 1 B. 2 C. 3 D. 4 Answer: B
Answer Explanation B is correct - per CPS 9067.03 STANDBY GAS TREATMENT SYSTEM OPERABILITY, design Standby Gas Treatment System (VG) flow is 4000 cfm (+ / - 10%). During manual initiation, the heater automatically energizes to remove entrained moisture from the process stream, indicated by train outlet temperature higher than train inlet temperature. Case B is the only case that indicates ~ 4000 cfm and the train outlet temperature is ~ 10 degrees higher than the train inlet temperature.
A is incorrect but plausible if the examinee fails to determine that the heater is not operating in Case A (inlet and outlet temperature are the same). An examinee may select this response if he/she incorrectly believes that the heater only energizes on an automatic initiation signal or misreads the meters.
C is incorrect but plausible if the examinee fails to recall that VG flow should be ~ 4000 cfm and determines that flow should be ~ 50% of the indicator band.
D is incorrect but plausible if the examinee fails to determine that VG flow should be ~ 4000 cfm and that the heater is not operating.
KA justification - this question meets the KA because the examinee has to have knowledge of the VG system design feature that provides for moisture removal (electric heater) to pick the graphic showing proper system operation.
Cog level justification - this is a high cog question written at the analysis and application level.
The examinee has to analyze each of the graphics and then determine which shows the VG system operating normally.
Question 34 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 4.00 System ID: 1270108 User-Defined ID: CL-ILT-1270108 Cross Reference Number:
Standby Gas Treatment (VG) System 'A' was manually initiated Topic:
one hour ago per CPS 3319.01 Standb...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 3319.01 Rev. 17 Revision Number:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14045)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data Table.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 3319.01 ON-## not provided)
- CPS 9067.03 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 261000 Standby Gas Treatment System Category / KA Statement: K4. Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) and/or interlocks which provide for the following: K4.03 Moisture removal RO Value: 2.5 SRO Value: 2.7 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
35 ID: 1269069 Points: 1.00 CPS 9080.03 Diesel Generator 1C Operability - Manual And Quick Start Operability is in progress. The current step is "8.2.15 Load the DG per the following:"
Assuming:
- The DG 1C Output Breaker Sync switch is in the ON position
- Grid frequency is 60 Hz Answer the following:
Based on the indications in the graphic, the Synchroscope is turning in the ____(1)____ direction.
Prior to closing the diesel generator output breaker, _____(2)_____ engine speed using the governor control switch.
A. (1) Clockwise (2) Raise B. (1) Clockwise (2) Lower C. (1) Counter-Clockwise (2) Raise D. (1) Counter-Clockwise (2) Lower Answer: C
Answer Explanation C is correct: Per CPS 9080.03 Diesel Generator 1C Operability - Manual And Quick Start Operability, 8.2.15 Load the DG per the following:
Adjust DG 1C speed with DG 1C Governor control switch such that DG frequency is slightly greater than bus frequency as indicated by the following:
- CLOCKWISE rotation of the synchroscope at a speed of approximately one revolution every 60-120 sec (i.e., 1/2 - 1 RPM) or slower.
- Both synchroscope lights are extinguished at the 12 o'clock position.
- Both synchroscope lights are brightly lit at the 6 o'clock position.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she:
- fails to recognize that the DG is the incoming source
- incorrectly believes that CLOCKWISE rotation of the synchroscope is achieved when DG speed (and therefore frequency) is less than grid frequency but correctly recognizes that DG speed must be raised prior to shutting the DG output breaker.
B is incorrect but plausible. The candidate may select this response if he/she:
- fails to recognize that the DG is the incoming source
- incorrectly believes that CLOCKWISE rotation of the synchroscope is achieved when DG speed (and therefore frequency) is less than grid frequency and incorrectly concludes that DG speed must be lowered (potentially to slow down the synchroscope) prior to shutting the DG output breaker.
D is incorrect but plausible. The candidate may select this response if he/she recognizes that based on the DG speed (and therefore frequency) being less than grid frequency, the synchroscope will rotate in the COUNTER-CLOCKWISE (SLOW) direction, but fails to recognize that lowering DG speed will only cause the synchroscope to rotate faster in the COUNTER-CLOCKWISE (SLOW) direction.
KA justification - this question meets the KA because the examinee must determine information provided by the synchroscope (design feature) which is used to parallel AC sources.
Cog Level Justification - this is a high cog question written at the analysis level. The examinee has to analyze the conditions provided in the question stem, determine what information the synchroscope provides and based on that information, choose appropriate action required to parallel the DG.
Question 35 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269069 User-Defined ID: CL-ILT-1269069 Cross Reference Number:
CPS 9080.03 Diesel Generator 1C Operability - Manual And Topic:
Quick Start Operability is in progress. T Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 9080.03 Rev. 34e Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 9080.03 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 262001 A.C. Electrical Distribution Category / KA Statement: K4. Knowledge of A.C.
ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the following: K4.05 Paralleling of A.C. sources (synchroscope)
RO Value: 3.4 SRO Value: 3.6 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
36 ID: 1269065 Points: 1.00 Given:
- The plant is operating at 80% power with Both Turbine Driven Reactor Feed Pumps (TDRFPs) in service on the Master Level controller (MLC).
- The Motor Driven Reactor Feed Pump (MDRFP) and the MDRFP Discharge valve (1FW004) are presently being controlled per the graphic below.
THEN, a Reactor Scram is received due to a Main Turbine trip.
Within the next 20 seconds, Reactor water level lowers to -10 inches and is automatically recovered by the Digital Feedwater (DFW) System.
After one (1) minute, and assuming NO operator action was taken, which of the following describes the status of the MDRFP and its discharge valve 1FW004? (Assume NO RPV Level 8 is received.)
A. MDRFP is OFF with the 1FW004 valve in Automatic control on the MLC.
B. MDRFP is running with the 1FW004 valve in Automatic control on the MLC.
C. MDRFP is OFF with the 1FW004 valve in Local control on the Small Loop Interface Module (SLIM).
D. MDRFP is running with the 1FW004 valve in Local control on the Small Loop Interface Module (SLIM).
Answer: C
Answer Explanation C is correct. Per CPS 3103.01 Feedwater (FW), the graphic shows the MDRFP Aux Oil Pump in STOP (indicated by the word "STOP" in the green box) and control of 1FW004 valve in local on it's SLIM controller (indicated by the "L" in the yellow box).
Per CPS 3103.01 Feedwater (FW) 8.1.3 MDRFP Startup, the MDRFP Aux Oil Pump must be started prior to starting the MDRFP.
In this case, the MDRFP cannot start without the oil pressure permissive being met (Aux oil pump is OFF).
Per CPS 3103.01 Feedwater (FW) 8.3.18 1FW004 SLIM Module Operations - CAUTION- Placing the SLIM in LOCAL (L) removes control from the Ovation DFW controls. Turbine operations can only be performed from the SLIM up/down arrows. Once SLIM is in local (L) the soft M/A station manual (M) and auto (A) buttons will be deactivated.
Additionally, any DFW control in LOCAL prevents the Auto-Scram logic from functioning; thus MDRFP and 1FW004 will remain as shown - even if MDRFP Aux Oil pump was running initially.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she recognizes that the Aux Oil Pump is OFF and therefore the MDRFP cannot start (no oil pressure permissive) but fails to recognize that the 1FW004 did NOT shift to AUTOMATIC control and will NOT respond to the MLC.
B is incorrect but plausible. The candidate may select this response if he/she fails to recognize that the Aux Oil Pump is OFF and therefore the MDRFP cannot start (no oil pressure permissive) and additionally fails to recognize that the 1FW004 did NOT shift to AUTOMATIC control and will not respond to the MLC.
D is incorrect but plausible. The candidate may select this response if he/she fails to recognize that the Aux Oil Pump is OFF and therefore the MDRFP cannot start (no oil pressure permissive) but recognizes that the 1FW004 SLIM Module is in local (L) control.
KA Justification - this question meets the KA because the candidate must demonstrate knowledge of the operational implications of the Ovation Digital Feedwater Controls as it applies to the Reactor Water Level Control System in order to select the correct response.
Cog Level Justification - this is a high cog question written at the analysis and application level -
the examinee must analyze the graphic presented in the stem to determine the status of the affected equipment and apply system knowledge to determine behavior of the Ovation Digital Feedwater Controls based on those plant conditions.
Question 36 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269065 User-Defined ID: CL-ILT-1269065 Cross Reference Number:
Given:
Topic: The plant is operating at 80% power with Both Turbine Driven Reactor Feed Pumps (TDRFPs) i Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3103.01 Rev. 31 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (909170)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table, History: (i.e. Modified distractor enhanced stem, improved b to make plausible based on explanation and added OTPS review) justifications, wdk 5/20/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3103.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK/SPR)
KA Data KA Number / System Name: 259002 Reactor Water Level Control System Category / KA Statement: K5. Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM: K5.01 GEMAC/Foxboro/Bailey controller operation: Plant-Specific RO Value: 3.1 SRO Value: 3.1 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
37 ID: 1269413 Points: 1.00 The plant was operating at rated thermal power with the High Pressure Core Spray (HPCS) Pump aligned to its normal suction source.
Then, the following indications were observed:
Which of the following graphics represent the expected alignment for the HPCS Pump suction 2 seconds after the indications above were received?
A B C D A. A B. B C. C D. D
Answer: D Answer Explanation D is correct:
Per CPS 3309.01E001 High Pressure Core Spray Electrical Lineup, 1E22-F001 is normally open and 1E22-F015 is normally shut when the system is in standby.
Per CPS 3309.01 High Pressure Core Spray (HPCS), step 2.3, and 5062.03 (3E) Suppression Pool Water Level High, HPCS pump suction automatically shifts to the suppression pool from the RCIC storage tank (1E22-F015 opens and 1E22-F001 closes) upon receiving any of the following:
- Low RCIC Storage Tank Level: 0.3 (3)
- High Suppression Pool Level: 19 11.5 Per N-CL-OPS-209002, When the water level in the RCIC Storage Tank falls below the low level setpoint (0.3 feet or 3), or if the Suppression Pool level increases above the high level setpoint (19' 11 1/2"), the HPCS Pump suction source is shifted to the Suppression Pool by the automatic opening of HPCS Suppression Pool Suction Valve, F015. When F015 is fully open, F001 closes. Water from the Suppression Pool then flows through F015 to the suction side of the HPCS Pump.
Therefore, 2 seconds after receipt of annunciator 5062-3E, 1E22-F015 will be stroking open (red and green indicating lights and 1E22-F001 will be open (red light on, green light off). This is represented in graphic D.
A is incorrect but plausible if the examinee correctly recognizes that HPCS suction is normally aligned to the RCIC Storage Tank but fails to determine that the HPCS Suction will automatically shift to the Suppression Pool on a high suppression pool level condition. The examinee may select this choice if they incorrectly believe that the auto shift to the suppression pool from the RCIC storage tank only occurs on a RCIC Storage Tank low level signal when the HPCS Pump is aligned to the RCIC Storage Tank.
B is incorrect but plausible if the examinee incorrectly recalls that the HPCS Pump Suction is normally aligned to the Suppression Pool and that the suction will remain aligned to the suppression pool when the suppression pool high level alarm is received. The examinee may select this choice based on knowledge that ITS LCO 3.5.1/2 requires HPCS to be capable of taking a suction from the Suppression Pool for HPCS operability.
C is incorrect but plausible if the examinee correctly determines that 1E22-F015 will automatically open on a high suppression pool level condition, but incorrectly believes that 1E22-F001 will begin to stroke closed when 1E22-F015 has left its closed seat.
KA justification - this question meets the KA because the examinee has to determine how the conditions in the stem affect the physical connection between the HPCS system and the HPCS Storage Tank system to answer the question.
Cog Level justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to analyze the conditions in the stem, determine how those conditions affect the HPCS system, and then determine which graphic represents the expected alignment of two HPCS system valves to answer the question (3-SPK).
Question 37 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1269413 User-Defined ID: CL-ILT-1269413 Cross Reference Number:
The plant was operating at rated thermal power with the High Topic:
Pressure Core Spray (HPCS) Pump aligne Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- 5062.03 (3E) Rev. 30a Revision Number:
- CPS 3309.01 Rev. 17
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- 5062.03 (3E)
ON-## not provided)
- CPS 3309.01
- CPS 3309.01E001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 209002 High Pressure Core Spray System (HPCS)
Category / KA Statement: K1. Knowledge of the physical connections and/or cause-effect relationships between HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) and the following: K1.01 Condensate transfer and storage system: BWR-5,6 RO Value: 3.4 SRO Value: 3.4 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.2 to 41.9 10CFR55-43 (SRO) Data: NA
38 ID: 1650234 Points: 1.00 With the reactor operating at 60% power and 70% of rated flow, the APRM Channel 'A' flow signal from the Recirculation System Flow Converter fails DOWNSCALE.
What is the status of the APRM 'A' Thermal rod block and scram trip units?
APRM 'A' Thermal Upscale Rod Block APRM 'A' Thermal Scram Trip Channel Channel Status Status Choice 1 NOT tripped NOT tripped Choice 2 Tripped Tripped Choice 3 Tripped NOT tripped Choice 4 NOT tripped Tripped A. Choice 1 B. Choice 2 C. Choice 3 D. Choice 4 Answer: B
Answer Explanation B is correct - a downscale failure of the APRM 'A' flow reference signal will cause receipt of annunciators 5004-1H APRM A UPSC TRIP OR INOP, 5004-1K APRM UPSC, 5004-3B DIV 1 OR 4 NMS TRIP, and 5006-2H ROD OUT BLOCK.
Per 5004-1H, the thermal upscale trip setpoint is determined using the following formula:
RPS Trip Setpoint = 0.58W + 56% during two RR loop operation, 111% max. Since W (loop flow) is 0 with the flow converter failed downscale, the trip setpoint is 0% which is below the actual power level provided in the stem (60%).
Per ORM 2.2.1 APRM Control Rod Flow Biased Upscale Rod Block is calculated using the following formula:
Rod Block Setpoint = 0.58W + 50% with a maximum of 108.0% of RATED THERMAL POWER. Since W (loop flow) is 0 with the flow converter failed downscale, the rod block trip setpoint is 0% which is below the actual power level provided in the stem (60%).
A is incorrect but plausible if the examinee believes that downscale signal failures do not normally result in the generation of trip signals and fails to recall the function of the APRM flow converter network.
C is incorrect but plausible if the examinee believes that receipt of a single downscale signal failure will result in a rod block but not an RPS signal since RPS trip logic is 2 out of 4 logic.
D is incorrect but plausible if the examinee believes that receipt of a single APRM flow converter downscale signal failure will result in an inop RPS trip signal but does not affect the thermal rod block circuitry.
KA justification - this question meets the KA because the examinee has to determine the impact of an downscale failure of the APRM flow reference signal to the APRM system to answer the question.
Cog Level justification - this is a high cog question written at the analysis and comprehension level. The examinee has to analyze the conditions in the stem, and then determine how a system failure will impact the system (3-PEO).
Question 38 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1650234 User-Defined ID: CL-ILT-1650234 Cross Reference Number:
With the reactor operating at 60% power and 70% of rated flow, Topic:
the APRM Channel 'A' flow signal fro Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with ORM 2.2.1 Rev. 79 Revision Number: CPS 5004.01 (1H) Rev. 28b Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Modified (CL-ILT-A11012)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Modified CL-ILT-A11012 to History: (i.e. Modified distractor make answer B the correct b to make plausible based on answer.
OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure ORM 2.2.1 ON-## not provided) CPS 5004.01 (1H)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 215005 Average Power Range Monitor/Local Power Range Monitor Category / KA Statement: K6 Knowledge of the effect that a loss or malfunction of the following will have on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM: K6.07 Flow converter/comparator network:
Plant-Specific RO Value: 3.2 SRO Value: 3.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
39 ID: 1270112 Points: 1.00 The plant is operating at rated thermal power.
THEN, a Division 2 NSPS circuit malfunction causes the INPUT to the Load Driver that services Group 8
& 15 isolation valves to fail to ZERO.
Which of the following valves CLOSE as a result of this failure?
A. 1VR001A (Containment Building Supply OUTBOARD Isolation Valve)
B. 1RE021 (Equipment Drain Sump Discharge Containment INBOARD Valve)
C. 1VR002B (Containment Building Supply INBOARD Isolation Bypass Valve)
D. 1RE022 (Equipment Drain Sump Discharge Containment OUTBOARD Valve)
Answer: B
Answer Explanation B is correct. Per N-CL-OPS-223002 Containment And Reactor Vessel Isolation Control System (CRVICS), CRVICS utilizes a pair of Low Level 2 - Drywell Pressure NSSS Load Drivers to initiate isolation of valves assigned to Group 8 and 15. These two Load Drivers, one for outboard valves and one for inboard valves, also supply isolation signals to valves in Groups 10, 12, 16, 19, and 20.
When the input level to either Load Driver falls to ZERO the output is energized to initiate an isolation. The outboard Load Driver utilizes Division 1 sensors and the inboard utilizes Division 2.
Therefore, Division 2 NSPS services the Load Driver for the Inboard valves. A ZERO input to the Load Driver produces an energized function to close the Inboard valves.
Per CPS 4001.02C001 Automatic Isolation Checklist, the only INBOARD Group 8 or 15 valve on the list is 1RE021, Equipment Drain Sump Discharge Containment INBOARD Valve (Group #8).
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she recognizes 1VR001A (Containment Building Supply OUTBOARD Isolation Valve) as a Group #10 CRVICS valve that could be affected by Group 8 & 15 load driver but fails to recognize that a failure of Division 2 NSPS will NOT affect an OUTBOARD Isolation Valve.
C is incorrect but plausible. The candidate may select this response if he/she recognizes 1VR002B (Containment Building Supply INBOARD Isolation Bypass Valve) as an INBOARD Isolation Valve that could be affected by a failure of Division 2 NSPS but fails to recognize that this valve belongs to Group #9 and is not among the other Groups (10, 12, 16, 19, and 20) that are serviced by the same Load Drivers as Groups 8 and 15.
D is incorrect but plausible. The candidate may select this response if he/she recognizes RE022 (Equipment Drain Sump Discharge Containment OUTBOARD Valve) as a Group #8 CRVICS valve that could be affected by Group 8 & 15 load driver but fails to recall that OUTBOARD valves would be affected if the malfunction were to occur in Division 1 NSPS.
KA Justification - this question meets the KA because the candidate must demonstrate knowledge of the effect that a loss or malfunction of NSPS will have on CRVICS in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall NSPS power to CRVICS valves and the groups they belong.
Question 39 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1270112 User-Defined ID: CL-ILT-1270112 Cross Reference Number:
The plant is operating at rated thermal power.
Topic:
THEN, a Division 2 NSPS circuit malfunction cau Num Field 1:
Num Field 2:
Text Field:
Comments:
General Data Technical Reference with CPS 4001.02C001 Rev. 16 Revision Number: N-CL-OPS-223002 Rev. 4 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- CPS ILT 9-1 NRC exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-6086)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table, History: (i.e. Modified distractor enhanced stem, explanation b to make plausible based on and added justifications, wdk OTPS review) 5/13/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4001.02C001 ON-## not provided) N-CL-OPS-223002 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off Category / KA Statement: K6. Knowledge of the operational implications of the following concepts as they apply to PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: K6.07 Essential A.C. power RO Value: 3.2 SRO Value: 3.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
40 ID: 1269001 Points: 1.00
- The Reactor Mode Switch is in STARTUP/HOT STANDBY.
- All IRMs are selected to range 5.
- Reactor power is midscale on range 5 of the Intermediate Range Monitors (IRMs).
Which of the following describes an operating condition that will cause the Rod Control and Information System (RC&IS) to generate a rod block?
A. The SRM channel "A" indicates 7 E4 cps and its detector is fully inserted.
B. The SRM channel "C" indicates 150 cps when its detector is partially withdrawn.
C. The IRM channel "B" indicated 30/125 scale and its detector is fully inserted.
D. The IRM channel "F" indicated 8/125 scale when its detector is partially withdrawn.
Answer: D Answer Explanation D is correct. Per CPS 3304.02 Rod Control And Information System (RC&IS) Table 1: Rod Block Troubleshooting Guide, a Rod Withdrawal Block is generated under the following conditions:
- IRM is upscale (108/125) - Bypassed when MODE Switch is in RUN
- IRM inop - Bypassed when MODE Switch is in RUN
- IRM's not fully inserted - Bypassed when MODE Switch is in RUN Based on the given plant conditions, the IRM Detector Not Full In will generate a Rod Withdrawal Block.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that a Rod Withdrawal Block is generated based on the given plant conditions. The condition that the candidate may be considering is SRM Channel Upscale at 1 E5 cps (per CPS 3304.02 Rod Control And Information System (RC&IS) Table 1: Rod Block Troubleshooting Guide). This condition is not met.
B is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that a Rod Withdrawal Block is generated based on the given plant conditions. The condition that the candidate may be considering is SRM Detector Not Full In and < 100 cps (per CPS 3304.02 Rod Control And Information System (RC&IS) Table 1: Rod Block Troubleshooting Guide). This condition is not met.
C is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that a Rod Withdrawal Block is generated based on the given plant conditions. The condition that the candidate may be considering is IRM Channel Downscale at 5/125 full scale (per CPS 3304.02 Rod Control And Information System (RC&IS) Table 1: Rod Block Troubleshooting Guide). This condition is not met.
KA Justification - this question meets the KA because the candidate must demonstrate the ability to predict rod block trips based on changing parameters associated with IRMs in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall rod block trip setpoints.
Question 40 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269001 User-Defined ID: CL-ILT-1269001 Cross Reference Number:
The Reactor Mode Switch is in STARTUP/HOT STANDBY.
Topic: All IRMs are selected to range 5.
Reactor powe Num Field 1:
Num Field 2:
Text Field:
Comments:
General Data Technical Reference with CPS 3304.02 Rev. 22d Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- CPS ILT 10-1 NRC exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-N11009)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data table, History: (i.e. Modified distractor enhanced explanation and b to make plausible based on added justifications, wdk OTPS review) 5/13/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3304.02 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 215003 Intermediate Range Monitor (IRM) System Category / KA Statement: A1. Ability to predict and/or monitor changes in parameters associated with operating the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM controls including: A1.05 SCRAM and rod block trip setpoints RO Value: 3.9 SRO Value: 3.9 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
41 ID: 1270125 Points: 1.00 Plant conditions are as follows:
Parameter/Condition Value Trend Reactor Pressure 450 psig Slowly Lowering Drywell Pressure 1.20 psig Slowly Rising RPV Water Level -100 inches Slowly Lowering Low Pressure Core Spray (LPCS) Pump Out of Service NA Under these conditions, arming AND depressing the LPCS/LPCI Fm RHR A Manual Initiation button on 1H13-P601 will result in the indications for the LPCS/LPCI FM RHR A SEAL-IN RESET pushbutton shown in graphic _____(1)____, AND will result in RPV Level _____(2)_____.
1 2 A. (1) 1 (2) rising B. (1) 2 (2) rising C. (1) 1 (2) continuing to lower D. (1) 2 (2) continuing to lower Answer: D Answer Explanation D is correct:
Per CPS 3312.01 section 8.1.2, LPCI will automatically initiate on High DW Pressure and RPV Level 1 and can be manually initiated by arming and depressing the LPCS/LPCI FM RHR A MANUAL INITIATION push-button (3312.01 step 8.1.3.1).
Per N-CL-OPS-203000 Residual Heat Removal (RHR) System, the Low Pressure Coolant Injection (LPCI) initiation signal seals in upon actuation (indicated by the red INITIATION SEAL-IN light) and must be manually reset when the initiation signal(s) clear. A reset pushbutton for each divisional set of logic clears the seal-in and allows the operator to manually terminate LPCI.
Per Figure 12 of the lesson plan, the ready to reset white light is energized when the automatic initiation signals are clear (RPV Level 1 and High DW Pressure).
Per CPS 3312.01 Residual Heat Removal (RHR) section 8.1.5 LPCI Shutdown, if INITIATION SEAL-IN RESET ready (white) light is ON, reset LPCS/RHR A by depressing LPCS/LPCI FM RHR A SEAL-IN RESET push-button.
Therefore, with RPV Level above Level 1 (-145.5") and DW Pressure < 1.68 psig, the red light will energize when the logic is manually initiated and ready to reset white light will energize with the RPV level and DW pressure parameters provided in the stem.
Per N-CL-OPS-203000, the LPCI subsystem shall pump a total of 5050 gpm of water in each of three separate loops from the suppression pool into the core region of the vessel when vessel pressure is 20 psid over drywell pressure. Injection flow begins at 225-psid vessel pressure over drywell pressure. Per CPS 5064.02 (2G), if RPV pressure is less than 472 psig, 1E12-F042A will open but will not be capable of injecting water into the RPV until pressure is reduced to ~ 225 psig, therefore RPV water level will continue to lower with the conditions provided in the stem.
Distracters:
A is incorrect but plausible if the examinee incorrectly determines that the White Ready to Reset Light will not be illuminated with a manual initiation signal present and that LPCI injection will cause RPV level to rise at 450 psig reactor pressure. The examinee may select this response based on knowledge that the LPCI injection valve will open when RPV pressure lowers to 472 psig and believes that LPCI Pump 'A' has sufficient discharge head to inject water into the RPV when the injection valve permissive is met.
B is incorrect but plausible if the examinee correctly determines that the White Ready to Reset Light will be illuminated with the conditions provided in the stem, but incorrectly determines that that LPCI injection will cause RPV level to rise at 450 psig reactor pressure. The examinee may select this response based on knowledge that the LPCI injection valve will open when RPV pressure lowers to 472 psig and believes that LPCI Pump 'A' has sufficient discharge head to inject water into the RPV when the injection valve permissive is met.
C is incorrect but plausible if the examinee incorrectly determines that the White Ready to Reset Light will not be illuminated with a manual initiation signal present but correctly recognizes that RPV level will continue to lower at 450 psig reactor pressure.
KA justification - this question meets the KA because the examinee has to predict how RPV level will respond during a manual initiation of LPCI to answer the question.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee must analyze the conditions presented in the stem to determine the expected indications and predict how RPV level will respond when operating RHR LPCI controls (3-SPK/PEO).
Question 41 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1270125 User-Defined ID: CL-ILT-1270125 Cross Reference Number:
Plant conditions are as follows:
Topic:
Parameter/ConditionValueTrendReactor Pressure450 psigSlowly Low Num Field 1:
Num Field 2:
Text Field:
Comments:
General Data Technical Reference with
- CPS 3312.01 Rev. 45b Revision Number:
- N-CL-OPS-203000 Rev. 4
- CPS 5064.02 (2G) Rev.
32 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 3312.01 ON-## not provided)
- N-CL-OPS-203000
- CPS 5064.02 (2G)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level High (3-SPK/PEO)
KA Data KA Number / System Name: 203000 RHR/LPCI: Injection Mode (Plant Specific)
Category / KA Statement: A1. Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:
INJECTION MODE (PLANT SPECIFIC) controls including:
A1.01 Reactor water level RO Value: 4.2 SRO Value: 4.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: N/A
42 ID: 1268997 Points: 1.00 Given the following indications on P601:
How are these indications impacted by a loss of Div 1 DC to the ADS valve solenoids followed by arming and depressing the ADS Logic A and Logic E Manual Initiation pushbuttons?
ADS A & E Logic lights B21-F041F B21-F041F (White & Red) (Green) (Red)
Scenario 1 ON OFF ON Scenario 2 ON ON OFF Scenario 3 OFF ON OFF Scenario 4 OFF OFF OFF A. Scenario 1 B. Scenario 2 C. Scenario 3 D. Scenario 4 Answer: B
Answer Explanation B is correct. Per N-CL-OPS-218000 Automatic Depressurization System (ADS), to manually actuate an ADS division, both the ADS logic A(E) or B(F) manual initiation "arm and depress" pushbuttons must be used. Rotating the collar devices of these pushbuttons arms the circuit.
Depressing the pushbutton will then cause an initiation signal to be developed.
Upon a manual or automatic actuation of a ADS division the signal is sealed in as indicated by a RED light above the ADS logic A/E (B/F) reset pushbutton. When any initiation signal or permissive signal clears a WHITE light above the pushbutton illuminates.
Power Supplies (Division 1):
- ADS Logic - Division 1 NSPS Based on the indications in the stem, there is no power to the Division 1 ADS solenoid valves.
Even though Division 1 (ADS Logic A) is actuated as indicated by the ADS A & E Logic lights being ON, with no DC power to the solenoids, ADS valves DO NOT reposition and B21-F041F indicates SHUT (Green light - ON/Red light - OFF).
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that the loss of 125 VDC MCC 1A power has no effect on Division 1 ADS (such as believing that Division 1 solenoids are powered from AB MCC 1A1) allowing the logic to actuate normally and ADS valves to reposition OPEN as indicated by B21-F041F (Green light - OFF/Red light - ON).
C is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that Division 1 ADS logic power is supplied by DC MCC 1A (in addition to Division 1 ADS solenoid valves OR instead of Division 1 ADS solenoid valves). Either way, if Division 1 ADS logic does not actuate, the ADS A & E Logic lights will remain OFF and ADS valves DO NOT reposition and B21-F041F indicates SHUT (Green light - ON/Red light - OFF).
D is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that Division 1 ADS logic power AND Division 1 ADS solenoid valve position indication is supplied by DC MCC 1A (and potentially Division 1 ADS solenoid valves OR instead of Division 1 ADS solenoid valves). Either way, if Division 1 ADS logic does not actuate, the ADS A & E Logic lights will remain OFF and ADS valves DO NOT reposition and B21-F041F indication is lost (Green light - OFF/Red light - OFF).
KA Justification - this question meets the KA because the candidate must select the correct impact of the abnormal condition presented (Loss of DC power to ADS valves) to answer the question. The (b) portion of the KA (use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations) is not included in the question as permitted by ES-401 D.2.a.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee has to compare current conditions to a loss of power and then predict an outcome after performing a manual action to answer the question.
Question 42 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1268997 User-Defined ID: CL-ILT-1268997 Cross Reference Number:
Given the following indications on P601:
Topic:
How are these indications impacted by a loss of Div Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with N-CL-OPS-218000 Rev. 3 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure N-CL-OPS-218000 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level High (3-SPK/PEO)
KA Data KA Number / System Name: 218000 Automatic Depressurization System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.05 Loss of A.C. or D.C. power to ADS valves RO Value: 3.4 SRO Value: 3.6 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
43 ID: 1269011 Points: 1.00 The plant was operating at 80% power.
Then, a malfunction of Division 4 NSPS Inverter caused the inverter output voltage to go to zero (0) volts.
Based on these conditions, the _____(1)_____.
The required action is to _____(2)_____.
A. (1) Inverter Output Breaker will trip (2) declare HPCS inoperable immediately B. (1) Inverter Output Breaker will trip (2) transfer Div 4 NSPS bus to alternate power in one hour C. (1) Inverter Solid State Transfer Switch (SSTS) will transfer to alternate (2) declare HPCS inoperable immediately D. (1) Inverter Solid State Transfer Switch (SSTS) will transfer to alternate (2) de-energize Div 4 NSPS bus in one hour Answer: C Answer Explanation C is correct:
Per CPS 3509.01 Instrument Power (IP) Discussion Item 2.1.3 and CPS 5002.05 (5N) NSPS INV TROUBLE, an inverter failure condition will cause the static switch of affected NSPS inveter to transfer to bypass through inverter output breaker B-2.
Per ITS 3.8.7 Inverters-Operating, Action C.1 requires declaring High Pressure Core Spray System inoperable immediately if the Div 4 NSPS inverter is inoperable.
Incorrect Responses:
A is incorrect but plausible if the examinee confuses the impact of a NSPS Inverter failure with the impact of an NSPS (RPS) Inverter failure. Per CPS 5006.03 (3L) REACTOR PROTECTION SYSTEM SOLENOID POWER SUPPLY INVERTER A TROUBLE ALARM, an RPS inverter failure (Possible Cause 7) will result in a trip of the RPS Solenoid Inverter output breaker CB-3, and de-energization of all 'A' RPS scram and scram pilot solenoids and MSIV solenoids, while correctly recalling that HPCS must be declared inoperable immediately due to inoperability of the Div 4 NSPS Inverter.
B is incorrect but plausible if the examinee confuses the impact of a NSPS Inverter failure with the impact of an NSPS (RPS) Inverter failure. Per CPS 5006.03 (3L), an RPS inverter failure (Possible Cause 7) will result in a trip of the RPS Solenoid Inverter output breaker CB-3, and de-energization of all 'A' RPS scram and scram pilot solenoids and MSIV solenoids, while also incorrectly recalling that ITS 3.8.7 requires transferring the Div 4 NSPS bus to alternate power source. This is the action for ITS 3.8.7 Condition D for an inoperable RPS Inverter.
D is incorrect but plausible if the examinee correctly recalls the impact of the inverter failure in the stem, but incorrectly recalls the ITS 3.8.7 Required Actions for an inoperable Div 3 or 4 NSPS Inverter. ITS 3.8.7 D.2 requires de-energizing the RPS bus in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for an inoperable RPS Inverter.
KA Justification - this question meets the KA because the examinee has to predict the impact and corrective actions for an undervoltage condition of an NSPS Inverter to answer the question.
Cog Level Justification - this is a low cog question written at the memory level. The examinee has to recognize the singular system response to an inverter failure and recall ITS requirements for the resultant inoperability to answer the question (1-I/1-P).
Question 43 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269011 User-Defined ID: CL-ILT-1269011 Cross Reference Number:
The plant was operating at 80% power.
Topic:
Then, a malfunction of Division 4 NSPS Inverter caused the Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 3509.01 Rev. 21 Revision Number:
- CPS 5002.05 (5N) Rev. 31
- ITS 3.8.7 Amendment No.
187
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 3509.01 ON-## not provided)
- CPS 5002.05 (5N)
- ITS 3.8.7
- CPS 5006.03 (3L)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I/1-P)
KA Data KA Number / System Name: 262002 Uninterruptable Power Supply (A.C./D.C.)
Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.01 Under voltage RO Value: 2.6 SRO Value: 2.8 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
44 ID: 1270208 Points: 1.00 The plant was operating at 52% power when a loss of all off-site power occurred coincident with a large recirculation suction line break.
Which of the following describes WHEN the listed pumps sequence onto their respective buses?
Immediately After The Five (5) Seconds After Ten (10) Seconds After Respective Bus is The Respective Bus Is The Respective Bus Is Energized Energized Energized Scenario 1 LPCS RHR A Div 1 SX Scenario 2 RHR C HPCS Div 3 SX Scenario 3 RHR A Div 1 SX RHR C Scenario 4 HPCS Div 3 SX LPCS A. Scenario 1 B. Scenario 2 C. Scenario 3 D. Scenario 4 Answer: A Answer Explanation A is correct. Per N-CL-OPS-264000 Diesel Generator, the vital bus loads have delay timers which allow controlled starting of large ECCS pumps and related support loads following a LOCA or LOOP. This "sequencing" ensures starting and power availability for loads required for safe shutdown of the plant.
- RHR A, B starts after 5-second timer.
Incorrect Responses:
B is incorrect but plausible if the examinee incorrectly recalls the load sequencing logic and believes that the HPCS pump starts after a 5 second delay and the Div 3 SX pump starts after a 10 second delay (they will both start immediately after the bus is energized).
C is incorrect but plausible if the examinee incorrectly recalls the load sequencing logic and believes that the RHR A pump starts immediately (it will start after a 5 second delay), Div 1 SX pump starts after a 5 second delay (it will start after a 10 second delay) and RHR C pump starts after a 10 second delay (it will start immediately after the bus is energized).
D is incorrect but plausible if the examinee incorrectly recalls the load sequencing logic and believes that the Div 3 SX pump starts after a 5 second delay and the LPCS pump starts after a 10 second delay (they will both start immediately after the bus is energized).
KA justification - this question meets the KA because the examinee must be able to recall the automatic sequence of events that occur during bus load sequencing actuations.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall the automatic sequence of events that occur during bus load sequencing actuations.
Question 44 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1270208 User-Defined ID: CL-ILT-1270208 Cross Reference Number:
The plant was operating at 52% power when a loss of all off-site Topic:
power occurred coincident with a l Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with N-CL-OPS-264000 Rev. 4 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure N-CL-OPS-264000 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 262001 A.C. Electrical Distribution Category / KA Statement: A3. Ability to monitor automatic operations of the A.C. ELECTRICAL DISTRIBUTION including:
A3.04 Load sequencing RO Value: 3.4 SRO Value: 3.6 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
45 ID: 1650223 Points: 1.00 The plant is operating at rated conditions.
Given the graphic below, which one of the following statements is correct?
A. Div 1 Battery fused disconnect is open due to overcurrent.
B. An equalizing charge is in progress on Div 1 Battery.
C. The Div 1 Battery is on a float charge.
D. Div 1 Battery Charger is tripped.
Answer: D
Answer Explanation D is correct - Indications provided show the following:
- Negative Battery 1A current indicates that Battery 1A is discharging.
These readings are indicative of a loss of the Div 1 Battery Charger (1A). Per CPS 5060-4E TROUBLE BATT CHARGER 1A, possible causes would be that the battery charger has shunt tripped (or otherwise lost power).
Distractors:
A is incorrect but plausible if the examinee incorrectly believes an overcurrent condition on DC MCC 1A leading to a loss of the Div 1 battery (fused disconnect open) would cause results similar to the battery charger feeder breaker tripping (causing the battery to discharge). Per CPS 5060-1E TRIP 125V DC MCC 1A BREAKER, an overcurrent trip causing a loss of the battery feed will also cause the battery charger feeder breaker to trip, deenergizing the respective DC MCC and cause the DC MCC Voltage and Current meters to read 0 volts.
B is incorrect but plausible if the examinee incorrectly believes that negative amps on the Battery 1A current meter indicates that the Div 1 battery is charging. An equalizing charge would be indicated by positive amps and a higher than normal DC MCC 1A bus voltage.
C is incorrect but plausible if the examinee incorrectly believes that these meter readings are normal (a nominal bus voltage ~ 125V with negative DC amps) for DC MCC 1A.
KA Justification - this question meets the KA because the examinee must demonstrate the ability to recognize an automatic action (i.e. battery charger trip) of the DC Electrical Distribution system using indications (i.e. meters) the candidate normally monitors in the main control room.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level - the examinee has to analyze a graphic in the stem and then determine the correct status of the Div 1 battery system based on knowledge of the equalizing function of the Divisional Battery Chargers to answer the question (3-SPK).
Question 45 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1650223 User-Defined ID: CL-ILT-1650223 Cross Reference Number:
The plant is operating at rated conditions.
Topic:
Given the graphic below, which one of the following Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 5060.04 Rev. 27 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New question Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure None ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 263000 D.C. Electrical Distribution Category / KA Statement: A3. Ability to monitor automatic operations of the D.C. ELECTRICAL DISTRIBUTION including:
A3.01 Meters, dials, recorders, alarms, and indicating lights RO Value: 3.2 SRO Value: 3.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
46 ID: 1270234 Points: 1.00 The plant is operating at 97% rated thermal power.
CPS 3506.01P001 Division 1 Diesel Generator Operations is in progress:
- 4160V Bus 1A1 is currently being supplied from off-site power
- Diesel Generator (DG) 1A is ready for loading
- The DG 1A Output BKR SYNC switch is in the ON position The DG 1A Output BKR is SHUT when the synchroscope's pointer is in the proper position AND the synchronizing lamps are ____(1)____.
Once DG 1A has been loaded as desired, the DG 1A Output BKR SYNC switch ____(2)____.
A. (1) dark (2) remains in the ON position B. (1) dark (2) is taken to the OFF position C. (1) bright (2) remains in the ON position D. (1) bright (2) is taken to the OFF position Answer: A
Answer Explanation A is correct. Per 3506.01P001 Division 1 Diesel Generator Operations:
WHEN the synchroscope's pointer nears the vertical (12 o'clock) position, and the synchronizing lamps go dark, close the DG 1A Output Bkr.
- Both synchroscope lights are extinguished at the 12 o'clock position.
- Both synchroscope lights are brightly lit at the 6 o'clock position.
CAUTION: Placing DG 1A Output BKR SYNC switch to OFF while the DG is in parallel, will trip the DG output breaker.
Incorrect responses:
B is incorrect but plausible if the examinee recognizes that the synchronizing lamps are dark when the DG 1A Output BKR is SHUT but fails to recognize that placing DG 1A Output BKR SYNC switch to OFF while the DG is in parallel will trip the DG output breaker.
C is incorrect but plausible if the examinee fails to recognize that the synchronizing lamps are dark when the DG 1A Output BKR is SHUT but recognizes that placing DG 1A Output BKR SYNC switch to OFF while the DG is in parallel will trip the DG output breaker.
D is incorrect but plausible if the examinee fails to recognize that the synchronizing lamps are dark when the DG 1A Output BKR is SHUT while also failing to recognize that placing DG 1A Output BKR SYNC switch to OFF while the DG is in parallel will trip the DG output breaker.
KA justification - this question meets the KA because the examinee must be able to demonstrate the ability to manually operate and monitor the synchronizing indications for an emergency diesel generator in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall facts concerning the diesel generator synchroscope operation and operation of the output breaker sync switch.
Question 46 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1270234 User-Defined ID: CL-ILT-1270234 Cross Reference Number:
The plant is operating at 97% rated thermal power.
Topic:
CPS 3506.01P001 Division 1 Diesel Generator O Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3506.01P001 Rev. 5 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3506.01P001 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1F)
KA Data KA Number / System Name: 264000 Emergency Generators (Diesel/Jet)
Category / KA Statement: A4. Ability to manually operate and/or monitor in the control room: A4.02 Synchroscope RO Value: 3.4 SRO Value: 3.4 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
47 ID: 1268990 Points: 1.00 Given the following graphic:
Assuming the indicated value is the LOWEST value reached and there has been NO operator action, complete the following:
____(1)____ Service Air (SA) Compressors are currently running.
All SA ring header Automatic isolation valves are ____(2)____.
A. (1) TWO (2) OPEN B. (1) TWO (2) SHUT C. (1) THREE (2) OPEN D. (1) THREE (2) SHUT Answer: A
Answer Explanation A is Correct. Per CPS 3214.01 Plant Air (IA & SA), one Service Air (SA) Compressor is normally in service with another in STANDBY. The third compressor is usually in PULL-TO-LOCK.
Per CPS 4004.01 Instrument Air Loss, the standby SA Compressor will auto-start when SA Header pressure reaches 80 psig. Building ring header auto-isolation valves close when respective building ring header lowers to 70 psig.
Based on the conditions presented in the stem, there would be a total of two (2) SA compressors running and since SA Header pressure never reached 70 psig, all building ring header isolation valves are OPEN.
Incorrect responses:
B is incorrect but plausible. The candidate may select this response if he/she recognizes that ONLY the standby SA Compressor would start when SA Header pressure reached 80 psig (realizing that the third SA Compressor's control switch is in PULL-TO-LOCK) but incorrectly believes that the building ring header auto-isolation setpoint has also been reached (this happens at 70 psig).
C is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that since SA Header pressure REMAINS below 80 psig that the remaining two SA Compressors would auto start (failing to realize that the third SA Compressor's control switch is in PULL-TO-LOCK) but correctly recognizes that the building ring header auto-isolation setpoint has NOT been reached.
D is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that since SA Header pressure REMAINS below 80 psig that the remaining two SA Compressors would auto start (failing to realize that the third SA Compressor's control switch is in PULL-TO-LOCK) while also incorrectly believing that the building ring header auto-isolation setpoint has also been reached (this happens at 70 psig).
KA Justification - this question meets the KA because the candidate must demonstrate the ability to monitor Instrument Air System pressure gauges in the control room in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall setpoints at which the standby SA compressor will auto start and the SA ring header isolations will auto-isolate.
Question 47 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268990 User-Defined ID: CL-ILT-1268990 Cross Reference Number:
Given the following graphic:
Topic:
Assuming the indicated value is the LOWEST value reached and Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3214.01 Rev. 26f Revision Number: CPS 4004.01 Rev. 10 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Modified (CL-ILT-6046)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table, History: (i.e. Modified distractor enhanced stem (changed one b to make plausible based on pertinent condition in the stem OTPS review) and one distractor, improved explanation and added justifications, wdk 5/20/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3214.01 ON-## not provided) CPS 4004.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 300000 Instrument Air System (IAS)
Category / KA Statement: A4. Ability to manually operate and /
or monitor in the control room: A4.01 Pressure gauges RO Value: 2.6 SRO Value: 2.7 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
48 ID: 1270028 Points: 1.00 The plant is currently in Mode 3 with the highest reading reactor coolant temperature indicating 300°F, cooling down at 25°F/hr.
The 'B' Loop of Residual Heat Removal (RHR) is in Shutdown Cooling (SDC) mode.
(1) If present trends continue, how long will it take for Mode 4 Cold Shutdown to be reached?
(2) What is the RHR cut in permissive pressure value contained in CPS 4001.02C001 Automatic Isolation Checklist?
A. (1) 3.52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> (2) 60 psig B. (1) 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (2) 60 psig C. (1) 3.52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> (2) 104 psig D. (1) 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (2) 104 psig Answer: D
Answer Explanation D is correct.
Part 1 Per ITS Table 1.1-1 Modes, Mode 4 is defined as Cold Shutdown with the Reactor Mode Switch in Shutdown and Average Reactor Coolant Temperature 200°F. With reactor coolant temperature at 300°F and cooling down at 25°F/hr, Mode 4 will be reached in 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. (300 - 200) / 25 = 4 Part 2 Per CPS 4001.02C001 Automatic Isolation Checklist, the RHR SDC Cut-In Permissive Pressure/Isolation - High setpoint is 104 psig.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she incorrectly recalls that Mode 4 is reached when reactor coolant temperature reaches 212°F and calculates that it will take 3.52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> to reach 212°F. (300 - 212) / 25 = 3.52. Also incorrect if he/she confuses the Group 3 isolation setpoint with the Group 5, 6, 7 RCIC Steam Supply Pressure - Low isolation setpoint which is 60 psig.
B is incorrect but plausible. The candidate may select this response if he/she correctly recalls that Mode 4 is reached when reactor coolant temperature reaches 200°F but confuses the Group 3 isolation setpoint with the Group 5, 6, 7 RCIC Steam Supply Pressure - Low isolation setpoint which is 60 psig.
C is incorrect but plausible. The candidate may select this response if he/she incorrectly recalls that Mode 4 is reached when reactor coolant temperature reaches 212°F and calculates that it will take 3.52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> to reach 212°F. (300 - 212) / 25 = 3.52.
KA justification - this question meets the KA because the examinee has to recall the value for the RHR Cut-In Permissive Pressure contained in ITS 3.4.9 RHR Shutdown Cooling System - Hot Shutdown and the definition for Mode 4 from ITS section 1.0 Use and Application and ITS Table 1.1-1 Modes.
Cog Level justification - this question is a low cog question written at the memory level. The examinee has to recall facts from Technical Specifications to answer the question (1-F).
Question 48 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1270028 User-Defined ID: CL-ILT-1270028 Cross Reference Number:
The plant is currently in Mode 3 with the highest reading reactor Topic:
coolant temperature indicating 30 Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with ITS 1.0 Use and Application Revision Number: Amend. 128 ITS Table 1.1-1 Amend 95 ITS 3.4.9 Amend. 163 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure ITS 1.0 Use and Application ON-## not provided) ITS Table 1.1-1 ITS 3.4.9 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)
Category / KA Statement: 2.2.38 Knowledge of conditions and limitations in the facility license.
RO Value: 3.6 SRO Value: 4.5 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7, 41.10 10CFR55-43 (SRO) Data: 43.1
49 ID: 1269436 Points: 1.00 A transient has occurred requiring the Main Control Room (MCR) to be evacuated.
All initial MCR actions prior to evacuation have been completed.
The Control Room Supervisor (CRS) has directed you to report to the Remote Shutdown Panel and establish RPV Level Control using Low Pressure Coolant Injection (LPCI) in accordance with CPS 4003.01C006 RSP - DIV 1 LPCI OPERATION.
Upon reporting to the Remote Shutdown Panel, the following indications are observed:
Based on these indications, which of the following is available for LPCI injection?
A. A AND 'B' RHR with automatic minimum flow capability B. A AND 'B' RHR WITHOUT automatic minimum flow capability C. B RHR ONLY with automatic minimum flow capability D. B RHR ONLY WITHOUT automatic minimum flow capability Answer: C
Answer Explanation C is correct:
Per CPS 4003.01C006 Div 1 LPCI Operation requires power to RHR Pump 'A' and 1E12-F042A LPCI From RHR A Shutoff Valve in order to inject to the RPV. This is accomplished by placing 6 transfer switches on the RSP to EMERG. Placing C61-S8 in EMERG transfers control power for 1E12-F042A from its normal power source (AB MCC 1A3) to AB MCC 1A1 Ckt 12 (E02-1RS99-101 and 108). Placing C61-S12 in EMERG shifts the control power source for RHR Pump 'A' from DC MCC 1A Ckt #32 (3312.01E001 sheet 3) to DC MCC 1A Ckt #16 (3312.01E001 sheet 3).
Per CPS 4003.01 step 4.3.3, power availability to 4160V Bus 1A1 is indicated by the following energized blue lights:
- 120 VAC CONTROL POWER CKT #12, AB MCC 1A1 Since both of those lights are de-energized in the question stem, the following conditions are indicated:
- Loss of power to 4160 V Bus 1A1, or
- Loss of power to 480V Unit Sub 1A or A1, or
- Loss of power to AB MCC 1A1 The following table provides the impact matrix for each of these conditions:
Condition Power Available to Power Available to LPCI 'A' RHR Pump 'A'? 1E12-F042A? Available?
4160V Bus 1A1 de-energized No No No 480V Unit Sub 1A or A1 de- Yes No No energized AB MCC 1A1 de-energized Yes No No Since RHR Pump 'B' is unaffected by the conditions in the stem, Div 2 LPCI is available for injection IAW CPS 4003.01C011. In addition, precaution 1.1 of 4003.01C011 states that Div 2 interlocks remain functional as these switches parallel the operation of the MCR control switches.
Therefore, the min flow protection for RHR Pump 'B' is unaffected when operating RHR Pump 'B' IAW CPS 4003.01C011.
Incorrect answers:
A is incorrect but plausible if the examinee if the examinee fails to recall that the loss of power to AB MCC 1A1 Ckt #12 renders RHR 'A' unavailable for LPCI operation and also incorrectly believes that RHR 'A' automatic minimum flow protection is preserved when operating RHR 'A' from the RSP similar to the function of RHR 'B' using Div 2 RSP controls.
B is incorrect but plausible if the examinee fails to recall that the loss of power to AB MCC 1A1 Ckt #12 renders RHR 'A' unavailable for LPCI operation and also incorrectly believes that RHR
'B' automatic minimum flow protection is lost when operating RHR 'B' using Div 2 RSP controls similar to the function of RHR 'A' using Div 1 RSP controls.
D is incorrect but plausible if the examinee correctly determines that RHR 'A' is unavailable for LPCI injection but incorrectly believes that RHR 'B' automatic minimum flow protection is lost when operating RHR 'B' using Div 2 RSP controls similar to the function of RHR 'A' using Div 1 RSP controls.
KA Justification - this question meets the KA because the examinee has to demonstrate the ability to operate local RSP controls for Div 1 and 2 LPCI Pumps by analyzing panel indications and determining the ability to operate each system IAW remote shutdown procedures to answer the question.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee has to analyze indications in a graphic and then make determinations based on that analysis using knowledge of system operation from the Remote Shutdown Panel (3-SPK).
Question 49 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1269436 User-Defined ID: CL-ILT-1269436 Cross Reference Number:
A transient has occurred requiring the Main Control Room (MCR) to be evacuated.
Topic:
All initial MCR Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 4003.01C006 Rev. 0 Revision Number:
- E02-1RS99-108 Rev. G
- E02-1RS99-101 Rev. U
- CPS 3312.01E001 Rev.
17
- CPS 4003.01 Rev. 17c
- CPS 4003.01C011 Rev.
1a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-LC-0941)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data table.
History: (i.e. Modified distractor Added a graphic to the b to make plausible based on question stem. Added OTPS review) distracter plausibility statements. Added KA and cog level justification statements.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 4003.01C006 ON-## not provided)
- E02-1RS99-108
- E02-1RS99-101
- CPS 3312.01E001
- CPS 4003.01
- CPS 4003.01C011 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 203000 Residual Heat Removal
/Low Pressure Coolant Injection: Injection Mode (Plant Specific)
Category / KA Statement: 2.1.30 Ability to locate and operate components, including local controls.
RO Value: 4.4 SRO Value: 4.0 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
50 ID: 1269171 Points: 1.00 The reactor was operating at 96% RTP. Residual Heat Removal (RHR) pump 1A is unavailable due to maintenance.
THEN, a loss of offsite power results in a reactor scram.
The following conditions currently exist:
- Shutdown criteria is met.
- Division 2 Emergency Diesel Generator (EDG) is tripped.
- Reactor Core Isolation Cooling (RCIC) initiated and is currently isolated.
- High Pressure Core Spray (HPCS) initiated then immediately tripped.
- Reactor pressure is being controlled by Safety Relief Valves (SRVs).
Parameter Value Trend RPV water level + 35 inches lowering 10 inches/minute Drywell (DW) pressure 1.50 psig rising 0.25 psig/minute If plant conditions remain as stated and NO operator action is taken, the Automatic Depressurization System (ADS) will automatically initiate in ____(1)_____ using the ____(2)____ pump.
A. (1) 2 minutes 28.2 seconds (2) Residual Heat Removal (RHR) 1C B. (1) 2 minutes 28.2 seconds (2) Low Pressure Core Spray (LPCS)
C. (1) 19 minutes 48 seconds (2) Residual Heat Removal (RHR) 1C D. (1) 19 minutes 48 seconds (2) Low Pressure Core Spray (LPCS)
Answer: D
Answer Explanation D is correct: Per CPS 5063.01 Alarm Panel 5063 Annunciators - Row 1, LPCS Pump Auto Start, LPCS initiation is due to RPV Level Low (-145.5 in.) or High Drywell Pressure (1.68 psig). All other Low Pressure Coolant Injection (LPCI) pumps are unavailable.
Per CPS 5066.05 Alarm Panel 5066 Annunciators - Row 5, ADS LOGIC B 105 SEC TIMER INITIATED (typical), ADS initiation logic can be broken down as follows:
Level 1 (<-145.5" ) -
Level 1 (<-145.5" ) -
1B21-N091A 1B21-N091A And And Confirmatory Level 3 - 1B21-OR Confirmatory Level 3 - 1B21-N095A N095A And And High Drywell Pressure 6 minute time delay.
1B21-N094A AND 105 Second Time Delay AND LPCS RHR A Discharge Pressure OR Discharge Pressure Greater Greater Than 145 psig than 125 psig.
Using this information, the candidate can determine ADS will automatically initiate in 19 minutes 48 seconds by taking the following steps:
- Calculate how long it takes to reach -145.5" Rx Level 1
- Understand that by the time Level 1 is reached, DW Pressure will already be above 1.68 psig and therefore not relevant to this calculation
- Recognize that based on plant conditions that only the LPCS pump is operating
- Take into account the 105 second timer Mathematical breakdown to reach the answer:
Calculating how much time it takes to reduce to the Level one ADS initiation signal:
35.0 inches (originally stated level)
+145.5 inches (level 1 -145.5 inches, made a positive to determine the calculate inches of water) 180.5 inches 180.5 inches / 10 inches/min (level dropping per minute stated)= 18.05 minutes or 18 minutes and 3 seconds 18 minutes and 3 seconds + 105 seconds (time delay) = 19 minutes and 48 seconds Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she fails to recognize that the RHR 1C pump is unavailable (Division 2 power), recognizes that ADS has a 105 second (1 minute 45 second) time delay but incorrectly believes that High Drywell pressure alone will start the 105 second timer.
Mathematical breakdown to reach this distractor:
Calculating how much time it takes to raise Drywell pressure to 1.68 psig:
1.68 psig - High Drywell Pressure
- 1.50 psig - current pressure
.18 psig - pressure until High Drywell Pressure is reached
.18 psig divided by .25 psig = .72 min (to reach 1.68 psig)
.72 x 60 seconds = 43.2 seconds 43.2 seconds + 105 seconds time delay = 148.2 seconds or 2 minutes 28.2 seconds B is incorrect but plausible. The candidate may select this response if he/she recognizes that the LPCS pump will start, recognizes that ADS has a 105 second (1 minute 45 second) time delay but incorrectly believes that High Drywell pressure alone will start the 105 second timer (same mathematical breakdown as answer A).
C is incorrect but plausible. The candidate may select this response if he/she fails to recognize that the RHR 1C pump is unavailable (Division 2 power), but determines the correct time for ADS to actuate (same mathematical breakdown as answer D).
KA justification - this question meets the KA because the examinee must have knowledge of the cause-effect relationship between the Automatic Depressurization System (ADS) and Low Pressure Core Spray (LPCS), specifically how to determine when the requirements are satisfied to initiate ADS using the only available injection sourece (LPCS) in order to determine the correct response.
Cog Level justification - this question is a high cog question written at the comprehension level.
The examinee has to recognize the interaction between the ADS and LPCS systems and the conditions necessary to initiate ADS using LPCS.
Question 50 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 3 Difficulty: 0.00 System ID: 1269171 User-Defined ID: CL-ILT-1269171 Cross Reference Number:
The reactor was operating at 96% RTP. Residual Heat Topic:
Removal (RHR) pump 1A is unavailable due to...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 5042.05 (5D) Rev. 31 Revision Number: CPS 5042.04 (4D) Rev. 31b Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 5042.05 (5D)
ON-## not provided) CPS 5042.04 (4D)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 218000 Automatic Depressurization System Category / KA Statement: K1. Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: K1.02 Low pressure core spray: Plant-Specific RO Value: 4.0 SRO Value: 4.1 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.2 to 41.9 10CFR55-43 (SRO) Data: NA
51 ID: 1269870 Points: 1.00 A malfunction occurred resulting in the generation of a trip signal from CNMT Bldg Refueling Pool Rad Monitors 1RIX-PR008A-D.
Assuming the four systems listed below were operating prior to the event, which system isolations are impacted by this malfunction?
System Designator System Name CCP Continuous Containment Purge System VF Fuel Building Ventilation System VP Drywell Cooling System FC Fuel Pool Cooling and Cleanup System A. CCP ONLY B. CCP and VF ONLY C. CCP, VF and VP ONLY D. CCP, VF, VP and FC Answer: B Answer Explanation B is correct. Per 4001.02C001 Auto Isolation Checklist, the trip of CNMT Bldg Refueling Pool Rad Monitors 1RIX-PR008A-D will cause a Group 10 (Containment Ventilation), 16 (Drywell Ventilation), and 19 (Secondary Containment) isolation which will cause CCP and VF to shutdown and isolate.
Incorrect Responses:
A is incorrect but plausible if the examinee determines that the CNMT Bldg Refueling Pool Rad Monitors 1RIX-PR008B & D trip will NOT cause a Group 19 (Secondary Containment) isolation, incorrectly believing that ONLY the trip of Fuel Building (FB) Exhaust Rad Monitors (1RIX-PR006A-D) will cause a Group 19 isolation.
C is incorrect but plausible if the examinee correctly determines that the CCP and VF systems should isolate based on the conditions provided in the stem, but incorrectly determines that the Drywell Cooling System (VP) should also have isolated. The VP System containment isolation valves are a part of Group 11 which did not receive an isolation signal (RPV Level 1 or Drywell Pressure - High).
D is incorrect but plausible if the examinee correctly determines that the CCP and VF systems should isolate based on the conditions provided in the stem, but incorrectly determines that the VP and FC Systems should also have isolated.
- The VP System containment isolation valves are a part of Group 11 which did not receive an isolation signal (RPV Level 1 or Drywell Pressure - High).
- The FC System valves are a part of Group 8 and Group 20 which did not receive an isolation signal (RPV Level 2 or Drywell Pressure - High).
KA justification - this question meets the KA because the examinee has to have knowledge of how a loss or malfunction of process rad monitors will impact Primary Containment Isolation Systems in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall the interlocks associated with Primary Containment Isolation Systems.
Question 51 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269870 User-Defined ID: CL-ILT-1269870 Cross Reference Number:
A malfunction occurred resulting in the generation of a trip signal Topic:
from CNMT Bldg Refueling Pool R Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 4001.02C001 Rev. 16 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4001.02C001 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-off Category / KA Statement: K3. Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following: K3.11 Plant ventilation RO Value: 2.8 SRO Value: 2.9 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
52 ID: 1269335 Points: 1.00 The plant is operating at 97% rated thermal power. An Equipment Operator has been directed to LOWER Component Cooling Water Heat Exchanger (CCW HX) Outlet temperature.
(1) What CCW cooled component is most sensitive to rapid temperature changes?
(2) What parameter must be monitored to ensure procedural limits are not exceeded during this evolution?
A. (1) Reactor Recirculation (RR) Pumps (2) CCW Header pressure B. (1) Reactor Recirculation (RR) Pumps (2) Plant Service Water (WS) Header pressure C. (1) Service Air (SA) Compressors (2) CCW Header pressure D. (1) Service Air (SA) Compressors (2) Plant Service Water (WS) Header pressure Answer: B Answer Explanation B is correct. Per CPS 3203.01 Component Cooling Water (CC):
- 4.0 Precautions - maintain Plant Service Water (WS) pressure > 100 psig.
- 8.1.3 Temperature Control of CCW System Loads: CAUTION - CCW Supply Header temperature changes should be made slowly in order to avoid thermally stressing the RR Pump Seals.
Incorrect Responses:
A is incorrect but plausible if the examinee recognizes that the RR Pumps are most sensitive to temperature changes but incorrectly believes that adjusting CCW HX Outlet temperature will have an appreciable effect on CCW Header pressure. The possible cause for a lowering CCW Header pressure would be a CCW Pump failure.
C is incorrect but plausible if the examinee incorrectly believes that the SA Compressors are more sensitive to temperature changes than RR Pumps. The SA Compressors do not have components susceptible to thermal stress as do the RR Pumps, although a loss of CCW cooling would eventually lead to a SA Compressor tripping on High Air or Oil temperature. Additionally, the examinee incorrectly believes that adjusting CCW HX Outlet temperature will have an appreciable effect on CCW Header pressure. The possible cause for a lowering CCW Header pressure would be a CCW Pump failure.
D is incorrect but plausible if the examinee recognizes that WS Header pressure must be monitored during the evolution but incorrectly believes that the SA Compressors are more sensitive to temperature changes than RR Pumps. The SA Compressors do not have components susceptible to thermal stress as do the RR Pumps, although a loss of CCW cooling would eventually lead to a SA Compressor tripping on High Air or Oil temperature.
KA Justification - this question meets the KA because the examinee has to predict which component is most significantly affected as well as choosing the parameter that must be monitored during the operation of CCW controls to adjust CCW temperature in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee has to recall information contained in procedure sections.
Question 52 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269335 User-Defined ID: CL-ILT-1269335 Cross Reference Number:
The plant is operating at 97% rated thermal power. An Topic:
Equipment Operator has been directed to LOWE Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3203.01 Rev. 35a Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New question Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3203.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1P)
KA Data KA Number / System Name: 400000 Component Cooling Water System (CCWS)
Category / KA Statement: A.1 Ability to predict and / or monitor changes in parameters associated with operating the CCWS controls including: A1.02 CCW temperature RO Value: 2.8 SRO Value: 2.8 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: N/A
53 ID: 1268878 Points: 1.00 The plant was operating at rated thermal power and 1000 psig when a Main Control Room (MCR) evacuation was required.
10:00 - The reactor is scrammed and the Remote Shutdown Panel (RSP) is manned.
10:20 - Reactor Core Isolation Cooling (RCIC) is placed in operation for RPV pressure control.
10:30 - The following plant conditions exist:
Parameter Value Trend RPV water level 39 inches lowering 0.5 inches/minute RPV pressure 550 psig lowering 10 psig/minute RCIC flow 550 gpm steady RCIC storage tank level 80 inches lowering 1.0 inch/minute Which ONE of the following actions is required NEXT?
A. Align RCIC for injection B. Maintain RCIC flow at 550 gpm C. Reduce RCIC Flow Controller Setpoint D. Shift RCIC suction to the Suppression Pool Answer: C
Answer Explanation C is correct: Per CPS 4003.01F003 RSP - Saturated Temperature/Pressure Correlation, when the Reactor was shutdown at 10:00 the coolant temperature was approximately 546°F (assuming 1000 psig). Per CPS 4003.01C001 RSP - RCIC Operation, cooldown rate must be held below 100°F/hr. Using CPS 4003.01F003, 446°F correlates to 390 psig. At time 10:30 the reactor was at 550 psig and falling at 10 psig/min.
Using: (550psig - 390psig) / 10psig/minute, it will take approximately 16 minutes to exceed cooldown rate if the rate of depressurization is not reduced. Since the RCIC system is controlling reactor pressure it's flowrate should be reduced in an attempt to control cooldown rate.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she recognizes that lowering RPV water level is a concern but, RPV water level will take approximately 30 minutes to reach level 3. Exceeding the 100°F/hr cooldown rate is a more immediate concern.
B is incorrect but plausible. The candidate may select this response if he/she fails to recognize that with RCIC in operation for RPV pressure control, the current RCIC flowrate directly correlates to RPV pressure lowering at 10 psig/minute and maintaining this flow rate will exceed the 100°F/hr cooldown rate.
D is incorrect but plausible. The candidate may select this response if he/she recognizes that lowering RCIC storage tank level is a concern but, RCIC suction automatically shifts to the suppression pool at ~ 3 inches (more than an hour to reach at the current leak rate) and therefore no reason to manually shift RCIC suctions at this time. Exceeding the 100°F/hr cooldown rate is a more immediate concern.
KA Justification - this question meets the KA because the examinee demonstrates an ability to apply plant conditions (presented in the stem) to provided reference material (Saturated Temperature / Pressure table) and interpret the conditions necessary to prevent exceeding an operating limit.
Cog Level Justification - this is a high cog question written at the application level. The examinee must solve a problem using a reference and other plant knowledge by applying plant conditions and interpreting the results.
Question 53 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268878 User-Defined ID: CL-ILT-1268878 Cross Reference Number:
The plant was operating at rated thermal power and 1000 psig Topic:
when a Main Control Room (MCR) evacuat Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 4003.01C001 Rev. 0a Revision Number: CPS 4003.01F003 Rev. 0 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-LC-1040)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table, History: (i.e. Modified distractor enhanced stem and b to make plausible based on distractors, added OTPS review) justifications, wdk 5/11/2016.
ILT Supplied Ref (If appropriate): (i.e. CPS 4003.01F003 ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4003.01C001 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK/SPR)
KA Data KA Number / System Name: 217000 Reactor Core Isolation Cooling Category / KA Statement: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
RO Value: 3.9 SRO Value: 4.2 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
54 ID: 1269116 Points: 1.00 The plant is at 55% rated thermal power.
THEN, the Main Turbine to Main Condenser seal boot ruptures. Main Condenser Vacuum begins to LOWER (degrade).
Given the graph below and assuming NO operator action, at what time will Main Condenser Vacuum lower to the point that the Main Steam Isolation Valves (MSIVs) will automatically close?
A. 4:10 B. 4:15 C. 4:21 D. 4:41 Answer: D
Answer Explanation D is correct: Per CPS 3112.01 Condenser Vacuum (CA), the following events occur when vacuum is broken (i.e. lowering Main Condenser Vacuum):
- Main Turbine Trip - 21.6 " Hg vac
- Rx Feed Pump Turbine Trip - 18.5 " Hg vac
- Group 1 Isolation - 8.5" Hg vac
- Bypass Valve Inhibit - 7.5" Hg vac Per CPS 4001.02C001 Automatic Isolation Checklist, a Group #1 isolation includes Main Steam Line Inboard MSIVs (1B21-F022A-D) and Outboard MSIVs (1B21-F028A-D).
Using the graph provided in the question stem, 8.5" Hg vac corresponds to a time of 4:41.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she incorrectly recalls as Main Condenser Vacuum lowers, 24" Hg vacuum is the point at which a Group #1 isolation occurs. Per CPS 3105.01 Turbine (TG, EHC, TS) the turbine should not be operated above 1200 rpm with a condenser vacuum < 24" Hg vac. Using the graph provided in the question stem, 24" Hg vac corresponds to a time of 4:10.
B is incorrect but plausible. The candidate may select this response if he/she incorrectly recalls as Main Condenser Vacuum lowers, 21.6" Hg vacuum is the point at which a Group #1 isolation occurs. Per CPS 3112.01 Condenser Vacuum (CA) a Main Turbine Trip will occur at 21.6" Hg vac. Using the graph provided in the question stem, 21.6" Hg vac corresponds to a time of 4:15.
C is incorrect but plausible. The candidate may select this response if he/she incorrectly recalls as Main Condenser Vacuum lowers, 18.5" Hg vacuum is the point at which a Group #1 isolation occurs. Per CPS 3112.01 Condenser Vacuum (CA) a Rx Feed Pump Turbine Trip will occur at 18.5" Hg vac. Using the graph provided in the question stem, 18.5" Hg vac corresponds to a time of 4:21.
KA justification - this question meets the KA because the examinee must demonstrate knowledge of the cause-effect relationship between the Reactor Condensate System (specifically the Main Condenser) and the Main Steam System to answer the question.
Cog Level Justification - this is a high cog question written at the comprehension level. The examinee must recognize the relationship between the main condenser (vacuum) and the Main Steam System (MSIVs) and then determine when an event will take place using a graph pertinent to that relationship.
Question 54 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269116 User-Defined ID: CL-ILT-1269116 Cross Reference Number:
The plant is at 55% rated thermal power.
Topic:
THEN, the Main Turbine to Main Condenser seal boot r...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3112.01 Rev. 20d Revision Number: CPS 4001.02C001 Rev. 16 CPS 3105.01 Rev. 41d Justification for Non SRO CFR N/A Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3112.01 ON-## not provided) CPS 4001.02C001 CPS 3105.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-DR)
KA Data KA Number / System Name: 256000 Reactor Condensate System Category / KA Statement: K1. Knowledge of the physical connection and/or the cause-effect relationship between REACTOR CONDENSATE SYSTEM and the following: K1.25 Main steam system: Plant-Specific RO Value: 3.0 SRO Value: 3.1 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.2 to 41.9 10CFR55-43 (SRO) Data: NA
55 ID: 1269615 Points: 1.00 The Fire Protection System is in a normal standby configuration.
THEN, electrical power is lost to the Makeup Water Pump House (MWPH).
Assuming NO operator action, which of the following describes the expected response of the Fire Protection (FP) Water System to these conditions?
Fire Pump ____(1)____ will start due to ____(2)____.
A. (1) 'A' (0FP01PA) ONLY (2) low system pressure B. (1) 'B' (0FP01PB) ONLY (2) low system pressure C. (1) 'A' AND 'B' (0FP01PA/B)
(2) low system pressure D. (1) 'A' AND 'B' (0FP01PA/B)
(2) a loss of AC control power Answer: A
Answer Explanation A is correct. Per CPS 3213.01 Fire Detection and Protection, the Fire Protection (FP) water system is normally pressurized by the Jockey Pump (0FP04P). Per E02-0AP27 Sheet 001 Key Diagram Pump House MCC A & B, 0FP04P is powered from 480V Pump House MCC A (0AP28E). Based on the stem of the question, since power is lost to the MWPH, 0FP04P is de-energized and consequently the FP water system pressure will degrade.
Per CPS 5121 Alarm Panel 5121 Annunciators, the 'A' Diesel Fire Pump (0FP01PA) will automatically start at a FP water system pressure below 140 psig and the 'B' Diesel Fire Pump (0FP01PB) will automatically start at a FP water system pressure below 130 psig.
Since the question stem indicates that the only malfunction is a loss of power to the MWPH MCC
'A', the expected response of the FP system is a loss of the Jockey Pump causing system pressure to decrease. 0FP01PA will automatically start at 140 psig to raise and maintain pressure in the FP water system and precluding the 0FP01PB from starting.
Incorrect Responses:
B is incorrect but plausible. The candidate may select this response of he/she recognizes that 0FP04P is de-energized and the diesel fire pumps start in a staggered sequence based on the setting of the pressure switches but incorrectly believes that 0FP01PB automatically starts BEFORE 0FP01PA.
C is incorrect but plausible. The candidate may select this response of he/she recognizes that 0FP04P is de-energized but fails to recognize that the diesel fire pumps start in a staggered sequence (based on the setting of the pressure switches) and believe that the 0FP01PA and 0FP01PB will automatically start.
D is incorrect but plausible. The candidate may select this response of he/she recognizes that both diesel fire pumps will start on a loss of AC control power but incorrectly believes that 0FP01PA/B are energized from the MWPH when in fact they are powered from Screenhouse MCC 'A' & 'B' respectively.
KA justification - this question meets the KA because the examinee is required to have knowledge of how a loss of AC power to the Fire Protection Jockey Pump affects the Fire Protection System Diesel Driven Fire Pumps.
Cog Level Justification - this is a high cog question written at the analysis level. The examinee has to analyze the parameters provided in the question and predict how the FP water system will respond (loss and subsequent recovery) to select the correct response (3-PEO).
Question 55 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269615 User-Defined ID: CL-ILT-1269615 Cross Reference Number:
The Fire Protection System is in a normal standby configuration.
Topic:
THEN, electrical power is lost Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 5121 Rev. 27b Revision Number: E02-0AP27-001 Rev. W Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC Exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 5121 ON-## not provided) E02-0AP27-001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 286000 Fire Protection System Category / KA Statement: K2. Knowledge of electrical power supplies to the following: K2.02 Pumps RO Value: 2.9 SRO Value: 3.1 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
56 ID: 1268920 Points: 1.00 The plant is operating at 97% rated thermal power. CPS 9054.01C002 RCIC (1E51-C001) High Pressure Operability Checks is in progress.
Plant status is as follows:
- RCIC is running and data collection has begun.
- RHR 'A' Loop is operating in Suppression Pool Cooling Mode (Suppression Pool temperature control).
- RHR 'B' Loop is operating in Pool To Pool Mode (Suppression Pool circulation).
THEN, an inadvertent LPCI 'A' and 'B' initiation signal was received and can NOT be reset.
The earliest suppression Pool temperature control may be reestablished is ____(1)____.
The earliest suppression Pool circulation may be reestablished is ____(2)____.
A. (1) immediately (2) immediately B. (1) immediately (2) in ten minutes C. (1) in ten minutes (2) immediately D. (1) in ten minutes (2) in ten minutes Answer: C
Answer Explanation C is correct. A LPCI initiation signal will result in RHR Loops 'A' and 'B' automatically shifting to Low Pressure Coolant Injection Mode (a loss of SP Cooling).
Per CPS 3312.01 Residual Heat Removal (RHR), section 8.1.2 LPCI Automatic Initiation, if RHR was not in standby when LPCI initiated, verify following valves automatically repositioned as follows:
- 1E12-F048A(B), RHR A(B) Hx Bypass Valve - OPEN
- 1E12-F024A(B), RHR A(B) Test Valve To Suppr Pool - Shut
- 1E12-F028A(B), RHR A(B) To CNMT Spray A(B) Shutoff Vlv - Shut
- 1E12-F027A(B), RHR A(B) To CNMT Outbd Isol Valve - OPEN Per CPS 3312.01 section 8.1.11 Suppression Pool Cooling - Shifting From LPCI, 1E12-F024A(B)
RHR A(B) Test Valve To Suppr Pool is opened immediately (manually overridden). A note above the step for opening 1E12-F048A(B) RHR A(B) Hx Bypass Valve states that 1E12-F048A(B) will open for 10 minutes after receipt of a LPCI signal, and then can be repositioned.
Therefore, 10 minutes must elapse from the time of the LPCI initiation signal before 1E12-F048A can be repositioned and the 'A' RHR HX can be utilized for Suppression Pool temperature control.
Per CPS 3312.01 section 8.2.10 Manual Operation of RHR - Pool To Pool - 1E12-F048A(B) is to be opened or verified open. Since it is open due to the LPCI signal, there is no delay in restoring RHR 'B' in Pool To Pool (Suppression Pool circulation).
Incorrect Responses:
A is incorrect but plausible if the examinee correctly recognizes that Suppression Pool circulation can be reestablished immediately, but fails to recall that there is a 10 minute time delay interlock on 1E12-F048A and Suppression Pool temperature control is unavailable until 1E12-F048A can be repositioned.
B is incorrect but plausible if the examinee incorrectly recalls that the 10 minute time delay interlock applies to 1E12-F048A(B) and not to 1E12-F024A(B).
D is incorrect but plausible if the examinee incorrectly recalls that the 10 minute time delay interlock applies to both the 1E12-F048A(B) and 1E12-F024A(B), or otherwise thinks that repositioning the 1E12-F048A(B) is necessary for Pool To Pool Mode as well as Suppression Pool Cooling Mode.
KA justification - this question meets the KA because the examinee must determine how a LPCI initiation affects the ability of RHR to provide suppression pool temperature control.
Cog Level Justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to interpret the indications provided in the stem, predict how the RHR System will respond to a LPCI signal and then using knowledge determine how to restore the RHR System to pre-event conditions.
Question 56 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268920 User-Defined ID: CL-ILT-1268920 Cross Reference Number:
The plant is operating at 97% rated thermal power. CPS Topic:
9054.01C002 RCIC (1E51-C001) High Pressure Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3312.01 Rev. 45b Revision Number: CPS 9054.01C002 Rev. 8d Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Modified (CL-ILT-N12056)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Changed conditions in the History: (i.e. Modified distractor stem such that one of the b to make plausible based on three distractors in the original OTPS review) question becomes the correct answer, wdk 5/18/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3312.01 ON-## not provided) CPS 9054.01C002 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 219000 RHR/LPCI:
Torus/Suppression Pool Cooling Mode Category / KA Statement: K3. Knowledge of the effect that a loss or malfunction of the RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE will have on following: K3.01 Suppression pool temperature control RO Value: 3.9 SRO Value: 4.1 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
57 ID: 1685276 Points: 1.00 With Narrow Range Reactor Pressure Vessel (RPV) water level at 30.9 inches and the Reactor at rated thermal power, the Motor Driven Reactor Feed Pump (MDRFP) would automatically start . . .
A. IMMEDIATELY if BOTH of the Turbine Driven Reactor Feed Pumps trip.
B. IMMEDIATELY when EITHER one of the two running Turbine Driven Reactor Feed Pumps trip.
C. ONLY if BOTH of the Turbine Driven Reactor Feed Pumps trip WHEN RPV level lowers to Level 4.
D. if EITHER of the two running Turbine Driven Reactor Feed Pumps trip WHEN RPV level lowers to Level 4.
Answer: A Answer Explanation A is correct - IAW CPS 3103.01 Feedwater (FW), step 2.1.2, the Motor Driven Reactor Feed Pump (MDRFP), in STANDBY, has an Auto Start feature:
If Both TDRFPs are out of service as sensed by one or more of the following conditions:
- TDRFP discharge valve not full open.
- Both the High Press and Low Pressure Stop Valves are Closed (not Full Open).
- TDRFP tripped (sensed by low oil pressure on the trip oil header. May also be caused by loss of control hydraulic oil, which supplies the trip oil header.)
Then, the MDRFP will start automatically.
B is incorrect but plausible if the examinee incorrectly recalls that the MDRFP will automatically start on the trip of a single TDRFP to attempt to maintain RPV water level above the Low RPV level scram setpoint. The plant is beyond the capacity of a single single TDRFP at rated thermal power.
C is incorrect but plausible if the examinee confuses the RR Runback logic with the MDRFP auto start logic. Per CPS 3103.01 section 8.1.10, a Level 4 runback will occur at 30.8" if less than 2 TDRFPs are in operation. 30.8" corresponds with Level 4.
D is incorrect but plausible if the examinee confuses the RR Runback logic with the MDRFP auto start logic. Per CPS 3103.01 section 8.1.10, a Level 4 runback will occur at 30.8" if less than 2 TDRFPs are in operation. 30.8" corresponds with Level 4.
KA justification - this question meets the KA because the examinee has to recall the conditions that will result in auto start of the MDRFP to answer the question.
Cog Level justification - this question is a low cog question written at the memory level. The examinee has to recall FW system interlocks to answer the question (1-I).
Question 57 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1685276 User-Defined ID: CL-ILT-1685276 Cross Reference Number:
With Narrow Range Reactor Pressure Vessel (RPV) water level Topic:
at 30.9 inches and the Reactor at rated Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3103.01 Rev. 31 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-ILT-5351)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table, History: (i.e. Modified distractor changed distracter C and D b to make plausible based on level values from Level 3 to OTPS review) Level 4, added KA justification and distracter plausibility statements.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3103.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 259001 Reactor Feedwater System Category / KA Statement: K4. Knowledge of REACTOR FEEDWATER SYSTEM design feature(s) and/or interlocks which provide for the following: K4.01 Auto start of the RFP's:
Plant-Specific RO Value: 3.8 SRO Value: 4.0 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
58 ID: 1271189 Points: 1.00 The Main Control Room (MCR) Ventilation (VC) System is currently aligned in the NORMAL Mode with the 'B' train in operation and the 'A' train in standby. Cont Rm Trn Min OS Air Dmpr 0VC01YA (East)
AND 0VC01YB (West) are OPEN.
THEN, the following annunciators were received:
- 1RIX-PR009A-D MCR Air Intake Rad Monitors indicating tiles are all red on the AR/PR LAN Which of the following graphics identifies the expected condition of CONT RM HVAC MU AIR FAN (0VC05CB) control switch flag AND indicating lights two (2) minutes later?
Graphic 1 Graphic 2 Graphic 3 Graphic 4 A. Graphic 1 B. Graphic 2 C. Graphic 3 D. Graphic 4 Answer: D
Answer Explanation D is correct. Per CPS 3402.01 Control Room HVAC (VC) 8.3.3 High Radiation Isolation, the operator would verify running/start 0VC05CB, Cont Rm HVAC B MU Air Fan. This alignment (red indicating light on and CS in Auto After Stop (green flagged)) is represented in Graphic 4.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she recognizes that when VC is in its Normal Operating Mode, 0VC05CB is NOT operating but fails to recognize that when VC shifts to High Radiation Isolation Mode, the Makeup Air Filter package is placed into service and 0VC05CB auto starts. The candidate may confuse High Radiation Isolation Mode with Smoke Mode where the Makeup Air Filter package is NOT utilized.
B is incorrect but plausible. The candidate may select this response if he/she recognizes that the Makeup Air Filter packages are designed to provide clean, filtered outside air to the Main Control Room (MCR) but incorrectly believes that when VC is in its Normal Operating Mode, the Makeup Air Filter package is in service and 0VC05CB is running. The candidate may therefore incorrectly believe that when VC shifts to High Radiation Isolation Mode, the Makeup Air Filter package remains in service and 0VC05CB REMAINS running.
C is incorrect but plausible. The candidate may select this response if he/she recognizes that the Makeup Air Filter packages are designed to provide clean, filtered outside air to the Main Control Room (MCR) but incorrectly believes that when VC is in its Normal Operating Mode, the Makeup Air Filter package is in service and 0VC05CB is running. If the candidate incorrectly believes that the outside source of air must be isolated based on the event, the candidate may therefore incorrectly believe that when VC shifts to High Radiation Isolation Mode, the Makeup Air Filter package is taken out of service and 0VC05CB trips.
KA justification - this question meets the KA because the examinee must demonstrate knowledge of the operational implications to Control Room Ventilation (VC) based on a VC train realignment due to radiological concerns to select the correct response.
Cog Level justification - this is a high cog question written at the comprehension level. The examinee has to understand the relationship between the VC System and its indications (based on conditions presented in the stem) and how those indications change as the VC system mode changes based on an automatic action.
Question 58 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1271189 User-Defined ID: CL-ILT-1271189 Cross Reference Number:
The Main Control Room (MCR) Ventilation (VC) System is Topic:
currently aligned in the NORMAL Mode with th Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 5050.07 Rev. 33 Revision Number:
- CPS 5052.07 Rev. 33e
Question History: (i.e. LGS NRC- No previous NRC exam use 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 5050.07 ON-## not provided)
- CPS 5052.07
- CPS 3402.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-DR)
KA Data KA Number / System Name: 290003 Control Room HVAC Category / KA Statement: K5. Knowledge of the operational implications of the following concepts as they apply to CONTROL ROOM HVAC: K5.01 Airborne contamination (e.g.,
radiological, toxic gas, smoke) control RO Value: 3.2 SRO Value: 3.5 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
59 ID: 1269803 Points: 1.00 The plant was operating at 97% rated thermal power with the following conditions;
- Control Rod Drive (CRD) Pump 1A (1C11-C001A) is secured and tagged out for maintenance
- 4.16KV Bus 1B Reserve Feed Breaker is in the "Racked Out" position for Post Maintenance Testing (PMT)
THEN, a plant transient occurs. The following conditions currently exist:
- All rods are fully inserted.
- Reactor vessel water level is 30 inches, controlling level with the Motor Driven Feed Pump (MDRFP) running.
From the following, choose the correct action to be taken FIRST:
A. Perform an Emergency Shutdown - RR Loop 'A'.
B. Start the Recirc Pump Auxiliary Seal Injection Pump.
C. SHUT the 'B' Reactor Recirculation Pump Seal Staging Shutoff Valve, 1B33-F075B ONLY.
D. SHUT the 'A & B' Reactor Recirculation Pump Seal Staging Shutoff Valves, 1B33-F075A & B.
Answer: C
Answer Explanation C is correct. Based on plant conditions, an End of Cycle Recirculation Pump Trip (EOC-RPT) occurs, downshifting Reactor Recirculation (RR) pumps 1A and 1B to slow speed. However, with 4.16 KV Bus 1B Reserve Feed Breaker in the "Racked Out" position and the Main Generator off-line due to the scram, the Low Frequency Motor Generator (LFMG) set 1B is unavailable and RR pump 1B is completely deenergized. Additionally, neither CRD pump is available and therefore no RR seal injection flow is available.
Per CPS 3302.01 REACTOR RECIRCULATION (RR) section 8.3.2.1.2:
IF the RR pump trips/is shutdown when no RR seal injection flow is available, THEN IMMEDIATELY shut/verify shut 1B33-F075A/B PMP A(B) Seal Stag Shutoff Vlv.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response based on incorrect knowledge of the actions required by CPS 3302.01 section 8.3.4 Loss of RR Seal Injection and/or CCW which requires and emergency loop shutdown if both RD Seal Injection (provided by RD) and CCW Cooling Flow is lost. Since CCW is not lost, RR Pump operation RR pump operation may continue due to internal seal flow and external cooling provided by Component Cooling Water (CCW).
B is incorrect but plausible. The candidate may select this response if he/she recognizes that since both CRD pumps are unavailable the Recirc Pump Auxiliary Seal Injection Pump should be started but fails to recognize that shutting the 'B' Seal Staging Shutoff Valve (1B33-F075B) has a higher priority. CPS 3302.01 requires the RO to immediately shut the affected RR Pump Seal Staging Shutoff Valve on a loss of RR pump seal injection with the RR Pump tripped.
D is incorrect but plausible. The candidate may select this response if he/she recognizes that RR seal injection is lost but fails to recall that 'A' RR pump operation may continue due to internal seal flow and external cooling provided by Component Cooling Water (CCW). Shutting the 'A' Seal Staging Shutoff Valve (1B33-F075A) is not required based on current plant conditions nor will it enhance continued pump operation.
KA Justification - this question meets the KA because the candidate must use knowledge of how a loss of AC power (4.16KV Bus 1B) will affect the RR System directly and the interaction/consequences between the CRD System and RR System based on the same loss in order to select the correct response.
Cog Level Justification - this is a high cog question written at the comprehension level - the examinee must recall how a loss of AC power affects the RR and CRD Systems and the consequences to the RR System due to the effect on the CRD System.
Question 59 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 0.00 System ID: 1269803 User-Defined ID: CL-ILT-1269803 Cross Reference Number:
The plant was operating at 97% rated thermal power with the Topic: following conditions; Control Rod D...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3302.01 Rev. 35e Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-LC-1275)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table, History: (i.e. Modified distractor enhanced question stem, b to make plausible based on distractors, explanation and OTPS review) added justifications, wdk 5/17/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3302.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 202001 Recirculation System Category / KA Statement: K6. Knowledge of the effect that a loss or malfunction of the following will have on the RECIRCULATION SYSTEM: K6.03 A.C. power: Plant-Specific RO Value: 2.9 SRO Value: 3.0 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
60 ID: 1268916 Points: 1.00 Plant conditions are as follows:
- The unit is at 97% rated thermal power.
- The Fuel Pool Cooling (FC) System is operating normally with the 'A' FC train in service.
- FC Filter Demineralizer (F/D) unit 1B is in service at 700 gpm.
THEN, the 'B' RO directs an Equipment Operator to place the FC F/D unit 1B in HOLD per CPS 3317.02 Operating Fuel Pool Filter/Demineralizers.
While lowering flow on FC F/D 1B:
- FC Surge tank level will ____(2)____.
A. (1) lower (2) remain unchanged B. (1) lower (2) rise C. (1) rise (2) lower D. (1) rise (2) remain unchanged Answer: B
Answer Explanation B is correct: The FD Bypass to HX A Valve (1FC004A) normally modulates to maintain FC FD flowrate. As the FD flowrate is reduced, the 1FC004A will CLOSE to reduce the flowrate bypassing the FC FD and raising the flowrate through the FC FD to compensate for the lowering FC FD flow. Per CPS 3317.01 Fuel Pool Cooling and Cleanup (FC), isolation of a filter demineralizer with flow controllers in AUTO and 1FC004A in AUTO will reduce flow to the pools to a pump minimum flow of 1000 gpm (to prevent pump damage).
Additionally, Per CPS 3317.01 Fuel Pool Cooling and Cleanup (FC), securing FC pump and demineralizer will raise FC surge tank level. This is due to the reduction in system flow (to the pools as described above) with flow into the surge tank dependent on pool level (vs. system flow).
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she recognizes that the 1FC004A valve will CLOSE reducing FD Bypass Flow (raising FD Flow) but failing to recall the role that the pools play and believe that since the system volume has not changed, the surge tank level would remain UNCHANGED.
C is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that in an attempt to maintain system flowrate, 1FC004A valve will move in the OPEN direction thereby increasing its flowrate (due to the lowering FD flowrate) but recalls the role that the pools play and correctly believes that the Surge Tank level will LOWER as flowrate through 1FC004A increases.
D is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that in an attempt to maintain system flowrate, 1FC004A valve will move in the OPEN direction thereby increasing its flowrate (due to the lowering FD flowrate) but failing to recall the role that the pools play and believe that since the system volume has not changed, the surge tank level would remain UNCHANGED.
KA Justification - this question meets the KA because the candidate must be able to predict the changes in FC system flow due to the operation of FC system controls in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall the system response to an operator manipulation.
Question 60 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268916 User-Defined ID: CL-ILT-1268916 Cross Reference Number:
Plant conditions are as follows:
Topic:
The unit is at 97% rated thermal power.
The Fuel Pool Cooling Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3317.01 Rev. 31c Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3317.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I/1-F)
KA Data KA Number / System Name: 233000 Fuel Pool Cooling and Clean-Up Category / KA Statement: A1. Ability to predict and/or monitor changes in parameters associated with operating the FUEL POOL COOLING AND CLEAN-UP controls including: A1.06 System flow RO Value: 2.5 SRO Value: 2.4 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
61 ID: 1268919 Points: 1.00 The plant was operating at rated thermal power with the Reactor Water Cleanup (RWCU) system operating in a normal two (2) pump, two (2) Filter Demineralizer (F/D) alignment.
THEN, a complete loss of Plant Air (IA & SA) system pressure occurred.
Assuming two (2) minutes have elapsed and NO operator intervention, what action is necessary to mitigate the consequences of the expected change in condition to the Reactor Water Cleanup (RWCU) system?
A. Throttle OPEN 1G33-F044 RWCU F/D Bypass Valve to restore original F/D flowrate.
B. Perform a Group #4 RWCU System isolation to prevent excessive F/D flowrate and resin breakthrough.
C. Trip RWCU Pumps A & B (1G33-C001A & B) to prevent operation at maximum shut-off head resulting in pump damage.
D. Throttle OPEN 1G33-F044 RWCU F/D Bypass Valve to prevent undesired cooldown and depressurization of RWCU return piping.
Answer: D
Answer Explanation D is correct. Per CPS 3303.01 Reactor Water Cleanup (RT) step 8.3.2 RWCU Operation with Loss of Instrument Air / Momentary Power Loss / Filter Demin Isolation:
- NOTE - On a loss of instrument air (IA), all the air operated valves (AOVs) in the F/D system will fail closed, causing the RWCU pumps to trip on low flow (provided the low flow trip bypass timer has timed out).
- 8.3.2.2 - IF RWCU pump(s) tripped on low flow, THEN:
- To prevent undesired cooldown and depressurization of return piping, throttle OPEN 1G33-F044.
Response Assumptions Scenario RWCU F/D RWCU Pumps A/B RWCU F/D Actions necessary to mitigate AOVs (1G33-C001A/B) Bypass Vlv (1G33-F044)
A Fail OPEN Unaffected Unaffected Throttle 1G33-F044 OPEN to restore initial F/D flow rate B Fail OPEN Trip Fail OPEN Perform a manual Group #4 Isolation to prevent excessive F/D flowrate and resin breakthrough.
C Fail SHUT Unaffected Fail SHUT TRIP 1G33-C001A/B to prevent "deadhead" pumps.
D Fail SHUT TRIP Unaffected Throttle 1G33-F044 OPEN to prevent undesired cooldown and depressurization.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that all the AOVs in the F/D system will fail OPEN on a loss of IA. Assuming full flow through both F/Ds, opening the RWCU F/D Bypass Valve (1G33-F044) would 'shunt' flow around the F/Ds and lower the flow passing through the F/Ds.
B is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that all the AOVs in the F/D system will fail OPEN on a loss of IA, including RWCU F/D Bypass Valve (1G33-F044) which is a normally CLOSED, motor operated valve (MOV) and unaffected by IA. With RWCU F/D AOVs full OPEN, an excessive flowrate through the F/Ds as the overriding concern may prompt the candidate to perform a manual Group #4 Isolation to prevent excessive F/D flowrate and resin breakthrough.
C is incorrect but plausible. The candidate may select this response if he/she recognizes that the AOVs in the F/D system will fail SHUT on a loss of IA, but incorrectly believes that RWCU F/D Bypass Valve (1G33-F044) fails SHUT as well (and cannot be opened). With no discharge path for the pumps AND failing to recognize the automatic trip of any running RWCU pump due to low flow, the candidate would believe that the only course of action is to manually trip the operating RWCU pumps to prevent operation at maximum shut-off head which could result in pump damage.
KA Justification - this question meets the KA because the candidate must predict the impact of a loss of Service Air on the Reactor Water Cleanup (RWCU) system based on the conditions presented in the stem and recall from the ABNORMAL OPERATION section of the RWCU procedure actions to mitigate the consequences. Specifically, this question meets the (b) portion of the KA to use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations. The (a) portion of the KA to predict the impacts is implied. A specific question on impact would be lower cognitive level. Scope limited IAW ES-401 D.2. Select and Develop Questions.
Cog Level Justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to recognize the interaction between two systems including consequences and implications to answer the question (2-RI).
Question 61 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268919 User-Defined ID: CL-ILT-1268919 Cross Reference Number:
The plant was operating at rated thermal power with the Reactor Topic:
Water Cleanup (RWCU) system operati Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3303.01 Rev. 36a Revision Number: CPS 5000.01 Rev. 26 CPS 5000.02 Rev. 25a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3303.01 ON-## not provided) CPS 5000.01 CPS 5000.02 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 204000 Reactor Water Cleanup System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: A2.07 Loss of plant air systems RO Value: 2.5 SRO Value: 2.6 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA
62 ID: 1269768 Points: 1.00 Reactor power is 36% rated thermal power.
Group 7 Control rod 24-25 is being notch withdrawn from position 12 to position 48.
When control rod 24-25 reached position 20, the operator noted the following:
- digital position indication alternates between "20" and a blank
- DATA FAULT pushbutton on the Operator Control Module (OCM) is LIT.
(1) With respect to control rod 24-25, is rod motion currently inhibited?
(2) What procedural action must be taken?
A. (1) No (2) RCIS data mode must be selected to single channel.
B. (1) No (2) A substitute position must be entered for the failed reed switch.
C. (1) Yes (2) RCIS data mode must be selected to single channel.
D. (1) Yes (2) A substitute position must be entered for the failed reed switch.
Answer: D
Answer Explanation D is correct. Per CPS 3304.02 Rod Control And Information System (RC&IS) Section 8.2.2 Position Data Faults, NOTE: The presence of a defective position probe is indicated by the DATA FAULT light on the Operator Control Module (OCM). To correct the invalid data being received, data from the other channel can be substituted.
- In the normal 2 channel mode, a CHANNEL DISAGREEMENT situation will cause the position indication to alternate between the 2 signals.
- Rod motion inhibit will result except for Group 1 and 2 rods when < Low Power Set Point (LPSP).
- Determine which channel is inaccurate, and enter substitute position data from the other probe.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she fails to recall that a data fault condition will result in a rod block (rod motion inhibit) and also incorrectly believes that procedural requirements exist that requires RCIS data mode to be shifted to single channel to allow monitoring of the good (non-failed) position probe.
B is incorrect but plausible. The candidate may select this response if he/she fails to recall that a data fault condition will result in a rod block (rod motion inhibit), and also incorrectly recalls that substitute position must be entered for the failed reed switch to comply with ITS 3.1.3 CONTROL ROD OPERABILITY (ITS SR 3.1.3.1 requires the position of each control rod to be determined).
C is incorrect but plausible. The candidate may select this response if he/she recognizes that rod motion is inhibited but incorrectly believes that selecting RCIC data to single channel mode is the correct course of action. However, this action will only select channel 1 or 2 data for position indication and will not clear the rod motion inhibit.
KA Justification - this question meets the KA because the candidate must demonstrate the ability to recognize automatic operations of the RC&IS system based on indications (including OCM lights) in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall the interlocks, setpoints and RC&IS system response based on a given problem.
Question 62 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269768 User-Defined ID: CL-ILT-1269768 Cross Reference Number:
Reactor power is 36% rated thermal power.
Topic:
Group 7 Control rod 24-25 is being notch withdrawn fro Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3304.02 Rev. 22d Revision Number: ITS 3.1.3 Amendment 188, 149 and 192 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-LC-1012)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table, History: (i.e. Modified distractor enhanced stem and b to make plausible based on responses, improved OTPS review) explanation and added justifications, wdk 5/17/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3304.02 ON-## not provided) ITS 3.1.3 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 201005 Rod Control and Information System (RCIS)
Category / KA Statement: A3. Ability to monitor automatic operations of the ROD CONTROL AND INFORMATION System (RCIS) including: A3.01 Operator control module lights: BWR-6 RO Value: 3.5 SRO Value: 3.5 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
63 ID: 1268910 Points: 1.00 A Main Turbine start up is in progress. The following indications are observed:
- SPEED SET RPM - 1800 is selected.
- Main Turbine speed is 1315 RPM and rising at 90 RPM/minute.
- The Main Shaft Oil Pump (MSOP) discharge pressure is 95 psig.
- Bearing Oil Header pressure is 14 psig.
Which of the following describes the expected response of the Main Turbine based on these conditions?
The Main Turbine will.....
A. trip immediately due to low MSOP discharge pressure.
B. trip immediately due to low Bearing Oil Header pressure.
C. continue to accelerate, then trip when > 1350 RPM and MSOP discharge pressure is 95 psig but < 100 psig.
D. continue to accelerate, then trip when > 1350 RPM and Bearing Oil Header pressure is 14 psig but < 16 psig.
Answer: C Answer Explanation C is correct. Per CPS 3105.01 Turbine (TG, EHC, TS) section 6.9 Turbine Trips - EHC System, the following items are possible causes for a turbine trip as activated via the turbine trip EHC system:
- Shaft driven oil pump (MSOP) low pressure trip ( 100 psig and > 1350 rpm)
- Bearing oil low pressure trip (12 psig)
Based on the conditions presented in the stem, the Main Turbine will continue to accelerate. If the MSOP pressure is still 100 psig when the Main Turbine speed reaches 1350 RPM, the Main Turbine will trip.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that the Main Turbine will trip immediately on low MSOP discharge pressure and that a low MSOP pressure condition currently exists.
B is incorrect but plausible. The candidate may select this response if he/she recognizes that the Main Turbine will trip immediately on low bearing oil pressure but incorrectly believes that a bearing oil pressure of 14 psig is low enough to cause the Main Turbine to trip.
D is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that the low bearing oil pressure trip is only active at > 1350 RPM and that a bearing oil pressure > 12 psig but < 16 psig is low enough to cause the Main Turbine to trip.
KA Justification - this question meets the KA because the candidate must be able to demonstrate the ability to monitor turbine lube oil pump parameters in the Main Control Room (MCR),
understand the relationship between turbine lube oil pump pressures and turbine speed, and recall the potential consequences with respect to Main Turbine trips in order to select the correct response.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall the MSOP discharge pressure trip how it relates to turbine speed.
Question 63 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 0.00 System ID: 1268910 User-Defined ID: CL-ILT-1268910 Cross Reference Number:
A Main Turbine start up is in progress. The following indications are observed:
Topic:
SPEED SET RPM -
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3105.01 Rev. 41d Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-ILT-4514)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Enhanced stem and History: (i.e. Modified distractor responses, improved b to make plausible based on explanation and added OTPS review) justifications, wdk 5/10/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3105.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 245000 Main Turbine Generator and Auxiliary Systems Category / KA Statement: A4. Ability to manually operate and/or monitor in the control room: A4.01 Turbine lube oil pumps RO Value: 2.7 SRO Value: 2.7 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA
64 ID: 1268914 Points: 1.00 The plant was operating at rated thermal power when a red indicator tile and audible alarm was observed on the MCR AR/PR LAN for 1RIX-PR019 Fuel Building CAM.
Based on these conditions, it is required to enter CPS 4979.01, Abnormal Release of Airborne Activity
_____(1)_____, and _____(2)_____.
A. (1) ONLY (2) verify VG auto starts B. (1) ONLY (2) notify RP of the alarm on 1RIX-PR019 C. (1) AND EOP-8, Secondary Containment Control (2) verify VG auto starts D. (1) AND EOP-8, Secondary Containment Control (2) notify RP of the alarm on 1RIX-PR019 Answer: D Answer Explanation D is correct:
Per section 1.0 SYMPTOMS of CPS 4979.02 ABNORMAL HIGH AREA RADIATION LEVELS, the off-normal is entered whenever any area radiation ALERT or HIGH alarm is received on the MCR AR/PR LAN Terminal. CPS 4979.02 step 3.0 Immediate Operator Actions states, "Verify RP and MCR are aware of the condition."
Per CPS 4406.01 SECONDARY CONTAINMENT CONTROL, EOP-8 is entered whenever any area radiation is above max normal. The "Area radiation above max normal" entry condition of EOP-8 corresponds to the high alarm setpoint for 1RIX-AR016 (EOP-TB Page 9-4 discussion of entry conditions).
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that only entry conditions for CPS 4979.02 are met and that the conditions presented in the stem would cause an auto start of VG. VG auto starts on high rad signals for process rad monitors 1RIX-PR001A-D CNMT Bldg Exh Rad, 1RIX-PR006A-D FB Exhaust Radiation, 1RIX-PR008A-D CNMT Bldg Fuel Transfer Pool Vent Plenum Radiation, and 1RIX-PR042A-D CNMT CCP Exh Radiation, but not 1RIX-AR016 Spent Fuel Storage Area Radiation Monitor.
B is incorrect but plausible. The candidate may select this response if he/she recognizes that per CPS 4979.02 it is required to notify RP of the AR/PR alarm, but incorrectly believes that entry conditions for CPS 4979.02 ONLY are met. The "Area radiation above max normal" entry condition of EOP-8 corresponds to the high alarm setpoint for 1RIX-AR016 (EOP-TB Page 9-4 discussion of entry conditions) and the student may not know this.
C is incorrect but plausible. The candidate may select this response if he/she recognizes that entry conditions for BOTH CPS 4979.02 and EOP-8 are met but incorrectly believes that the conditions presented in the stem would cause an auto start of VG.
KA justification - this question meets the KA because the examinee has to recognize that the conditions provided in the stem are entry conditions for an emergency operating procedure (EOP-
- 8) and an abnormal operating procedure (CPS 4979.02) to answer the question.
Cog Level justification - this question is a high cog question written at the analysis and comprehension level. The examinee has to analyze the indications provided in the stem, determine what the indication represents, and then determine required actions based on that analysis (3-SPK).
Question 64 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268914 User-Defined ID: CL-ILT-1268914 Cross Reference Number:
The plant was operating at rated thermal power when a red Topic:
indicator tile and audible alarm was obse Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 4406.01 Rev. 30 Revision Number: CPS 4979.02 Rev. 9 EOP-TB Rev. 007 CPS 5140.08 Rev. 0a CPS 4001.02C001 Rev. 16 CPS 3315.03 Rev. 9b Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- 10-1 NRC Exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-4928 and CL-Bank, Modified) ILT-N11084)
Low KA Justification (if required): NA Revision History: Revision Updated General Data Table.
History: (i.e. Modified distractor Added KA and cog level b to make plausible based on justification statements.
OTPS review) Revised distracters to convert the question to an RO-level question.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4406.01 ON-## not provided) CPS 4979.02 EOP-TB CPS 5140.08 CPS 4001.02C001 CPS 3315.03 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 272000 Radiation Monitoring Equipment Category / KA Statement: 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
RO Value: 4.5 SRO Value: 4.7 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.2
65 ID: 1268881 Points: 1.00 The plant was operating at rated thermal power when the following annunciators were received:
- 5042-4D TROUBLE VF SYSTEM LOCAL PNL 1PL44J
- 5042-5D HIGH DIFF PRESS FUEL BLDG The following indications shown below were observed:
Given these indications, which of the graphics below depicts the expected status of the Fuel Building Ventilation Supply and Exhaust Fans?
Case A Case B Case C Case D A. Case A B. Case B C. Case C D. Case D Answer: B
Answer Explanation B is correct.
Per 5042-4D TROUBLE VF SYSTEM LOCAL PNL 1PL44J, the running VF Exhaust Fan will trip on low FB differential pressure and the standby Exhaust Fan will auto start on a trip of the running Exhaust Fan.
Per 5042-5D HIGH DIFFERENTIAL PRESSURE FUEL BUILDING, the running Fuel Building Supply Fan will trip at 0.0 in. W.C.
Since Fuel Building and Secondary Containment dP both indicate a high value > 0.0 " H20, the running VF Supply Fan will trip and the running Exhaust Fan will be unaffected. This is depicted in the Case B graphic.
Incorrect Responses:
A is incorrect but plausible if the examinee fails to recall the VF Supply Fan high dP trip setpoint and believes that the system remains running normally with the indications provided in the stem.
C is incorrect but plausible if the examinee incorrectly believes that the standby VF Exhaust Fan will auto start in response to high building differential pressure.
D is incorrect but plausible if the examinee incorrectly believes that the standby VF Exhaust Fan will auto start and the running Supply Fan will trip in response to high building differential pressure.
KA justification - this question meets the KA because the examinee must have knowledge of the cause-effect relationship between secondary containment dP and Fuel Building ventilation (VF),
specifically how the system reacts to abnormal building differential pressure conditions in order to determine the correct response.
Cog Level justification - this question is a high cog question written at the comprehension level.
The examinee has to determine which graphic depicts the expected status of the VF supply and exhaust fans with the dP indication provided in the stem.
Question 65 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 2.00 System ID: 1268881 User-Defined ID: CL-ILT-1268881 Cross Reference Number:
The plant was operating at rated thermal power when the following annunciators were received:
Topic:
50 Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 5042.05 (5D) Rev. 31 Revision Number: CPS 5042.04 (4D) Rev. 31b Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-ILT-A14062)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Enhanced stem and improved History: (i.e. Modified distractor justifications, wdk 5/10/2016.
b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 5042.05 (5D)
ON-## not provided) CPS 5042.04 (4D)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI / 3-PEO)
KA Data KA Number / System Name: 288000 Plant Ventilation Systems Category / KA Statement: K1. Knowledge of the physical connections and/or cause-effect relationships between PLANT VENTILATION SYSTEMS and the following: K1.02 Secondary containment RO Value: 3.4 SRO Value: 3.4 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.2 to 41.9 10CFR55-43 (SRO) Data: NA
66 ID: 1650211 Points: 1.00 Plant conditions:
- Today's date - 6/21/20xx
- The time is 1615.
- You are scheduled to relieve the shift at 1830 this evening.
- You have worked the 1900 - 0700 shift for the past 5 nights.
- You receive a call from the on-shift CRS to provide emergency relief for the 'B' RO, who was transported to the hospital and vacated the watch at 1545 this afternoon.
Which of the following describes:
(1) The latest time that a relief must be on-shift?
(2) Whether you may cover the vacancy and COMPLETE your shift WITHOUT violating overtime limitations?
A. (1) 1645 (2) You may relieve the shift early AND work your entire shift without violating overtime limitations.
B. (1) 1645 (2) You may NOT relieve the shift early AND work your entire shift because doing so will violate overtime limitations.
C. (1) 1745 (2) You may relieve the shift early AND work your entire shift without violating overtime limitations.
D. (1) 1745 (2) You may NOT relieve the shift early AND work your entire shift because doing so will violate overtime limitations.
Answer: D
Answer Explanation D is correct.
Part 1 Per OP-CL-101-102-1001 CPS MINIMUM ON-SHIFT STAFFING FUNCTIONS, step 3.3, shift crew composition may be one less than the minimum requirements for a period of time not to exceed two hours in order to accommodate an unexpected absence of on-duty shift crew members provided immediate action is taken to restore composition to within the minimum requirements stated.
Since the vacancy occurred at 1545, crew composition must be restored by 1745.
Part 2 Per LS-AA-119 Fatigue Management And Work Hour Limits, section 5.1.1 10CFR26 Work Hour Limits:
The following limits apply to covered individuals regardless of unit status:
- No more than 16 work hours in any 24-hour period
- No more than 26 work hours in any 48-hour period
- No more than 72 work hours in any 7-day (168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) period
- At least a 10-hour break between successive work periods, or an 8-hour break when a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is necessary to accommodate a crew's scheduled transition between work schedules or shifts
- A 34-hour break in any 9-day period (this limit may be incorporated into minimum days off requirements).
Since the individual has already worked 5 12-hour shifts (60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />), working an additional 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 15 minutes would cause the individual to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period (73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br /> 15 minutes).
A is incorrect but plausible if the examinee fails to recall the 72 work hour limit and also incorrectly recalls the maximum vacancy time limit believing one hour is a reasonable time to provide shift relief.
B is incorrect but plausible if the examinee incorrectly recalls the maximum vacancy time limit believing one hour is a reasonable time to provide shift relief.
C is incorrect but plausible if the examinee fails to recall the 72 work hour limit.
KA justification - this question meets the KA because the examinee has to use knowledge of the procedure for 10 CFR 26 work hour limits to ensure his/her own overtime limitations are not exceeded.
Cog Level justification - Changed the question to high cog..
Question 66 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1650211 User-Defined ID: CL-ILT-1650211 Cross Reference Number:
Plant conditions:
Topic: Today's date - 6/21/20xx The time is 1615.
You are scheduled to relieve the Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with OP-CL-101-102-1001 Rev. 7 Revision Number: LS-AA-119 Sect. 5.1.1 Rev. 12 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- 2010 Ginna ILT NRC Exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added CPS specific History: (i.e. Modified distractor references to the answer b to make plausible based on explanation section.
OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure OP-CL-101-102-1001 ON-## not provided) LS-AA-119 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level High KA Data KA Number / System Name: 2.1 Conduct of Operations Category / KA Statement: 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
RO Value: 2.9 SRO Value: 3.9 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
67 ID: 1268858 Points: 1.00 Given:
- A new ILT student is performing his familiarization time (prior to starting Generic Fundamentals).
- The new student intends to enter the Main Control Room (MCR) to observe shift operations which will include walking on the contrasting carpeting (Zone of Control) immediately adjacent to the control panels.
The student will obtain A. Shift Manager permission prior to entering the MCR. Once this permission is obtained, the student has unlimited access to the control room as a member of the crew.
B. Shift Manager permission prior to entering the MCR. The Control Room Supervisor OR Reactor Operator may authorize the control board walkdown in the Zone of Control.
C. Work Execution Center (WEC) Supervisor permission prior to entering the MCR.
BOTH the Control Room Supervisor AND Reactor Operator must authorize the control board walkdown in the Zone of Control.
D. Work Execution Center (WEC) Supervisor permission prior to entering the MCR.
ONLY the Reactor Operator may authorize the control board walkdown in the Zone of Control.
Answer: D Answer Explanation D is correct. Per OP-AA-103-101 Control Room Access Control:
- Section 4.1.2 - Permission must be granted by the Reactor Operator (RO) in order to enter the zone of control.
- Section 4.1.4 - Permission is required from the WEC supervisor prior to entering the Control Room.
Additionally, per OP-AA-103-101 only specific operations personnel and others are granted unlimited access to the MCR (within the operations department, those On-Shift personnel assigned to a control room position and On-Shift personnel conducting control room related business).
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she recognizes that the Shift Manager enforces expectations and standards and provide leadership and direction for all On-Shift personnel but incorrectly believes that these responsibilities implicitly include granting unlimited access to the MCR zone of control.
B is incorrect but plausible. The candidate may select this response if he/she confuses the WEC's responsibility for Control Room access and incorrectly believes that it is a responsibility of the Shift Manager while also incorrectly believes that the Control Room Supervisor can grant access to the MCR zone of control in addition to the Reactor Operator.
C is incorrect but plausible. The candidate may select this response if he/she recognizes the WEC's responsibility for Control Room access but incorrectly believes that the Control Room Supervisor AND Reactor Operator must grant access to the MCR zone of control.
KA justification - this question meets the KA because the examinee has to use knowledge of the facility's requirements for Main Control Room access.
Cog Level justification - this question is a low cog question written at the memory level. In order to answer the question, the examinee must demonstrate knowledge of the procedure delineating the process facility personnel follow to access the Main Control Room.
Question 67 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268858 User-Defined ID: CL-ILT-1268858 Cross Reference Number:
Given:
Topic: A new ILT student is performing his familiarization time (prior to starting Generic Fun...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with OP-AA-103-101 Rev. 1 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure OP-AA-103-101 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 2.1 Conduct of Operations Category / KA Statement: 2.1.13 Knowledge of facility requirements for controlling vital/controlled access.
RO Value: 2.5 SRO Value: 3.2 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
68 ID: 1269434 Points: 1.00 The plant is operating at rated thermal power with Div 3 DG out of service.
Evaluate the indications in the graphic below and then determine:
- 1) a fault that could cause the indications shown, and
- 2) if 4160V Bus 1C1 is energized or de-energized A. (1) RAT 'A' Overcurrent Trip (2) energized B. (1) RAT 'A' Overcurrent Trip (2) de-energized C. (1) ERAT Sudden Pressure Fault (2) energized D. (1) ERAT Sudden Pressure Fault (2) de-energized Answer: A
Answer Explanation A is correct:
The graphic shows the 4160V Bus 1C1 Main Breaker in Auto-After-Close position (red flag) with a green and amber light. This indicates that the bus was originally powered from it's main source (RAT 'B'). The Reserve Breaker control switch is shown in Auto after Trip (green flag) indicating that 4160V Bus 1C1 Reserve Feed (ERAT) was originally the reserve feed source.
Per CPS 5062-1B, the green and amber indicating lights above the Main Breaker control switch indicate the breaker has tripped. The red and amber lights above the Reserve Breaker control switch indicate that the breaker has closed and that the breaker position and handswitch positions disagree (breaker closed with handswitch in after-trip).
Per CPS 5010-1A AUTOMATIC TRIP SWITCHER (RAT or ERAT), an overcurrent trip of RAT 'A' will result in a trip of 345KV RAT Circuit Switcher 4538, and a lockout trip of the 4160V Bus 1A1, 1B1, and 1C1 main breakers.
Per CPS 5062-1A AUTO TRIP OF 4160V BUS 1C1 MAIN FEEDER BREAKER, an automatic trip of the 4160V Bus 1C1 Main Feed Breaker will cause an auto closure of the 4160V Bus 1C1 Reserve Breaker to keep the bus energized.
Incorrect answers:
B is incorrect but plausible if the examinee correctly determines that an overcurrent trip of RAT 'A' will result in the indications shown in the graphic, but incorrectly determines that 4160V Bus 1C1 is de-energized based on the incorrect belief that the amber light on the ERAT Feeder Breaker indicates that the breaker has tripped. For 4160V Bus 1C1, the amber light indicates a breaker disagreement with the control switch position (breaker is closed with the control switch in after-trip).
C is incorrect but plausible if the examinee incorrectly analyzes the graphic and based on incorrect knowledge of the breaker disagreement indications, believes that an ERAT fault has occurred resulting in a trip of the ERAT feeder breaker and an auto closure of the RAT feeder breaker to maintain the bus energized.
D is incorrect but plausible if the examinee incorrectly analyzes the graphic and based on incorrect knowledge of the breaker disagreement indications believes that an ERAT fault has occurred resulting in a trip of the ERAT feeder breaker with a failure of the RAT feeder breaker to close resulting in de-energization of the bus.
KA Justification - this question meets the KA because the examinee has to analyze the graphic in the question stem and determine the fault that could result in those indications and the energized status of the bus to answer the question.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee has to analyze indications in a graphic and then make determinations based on that analysis.
Question 68 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269434 User-Defined ID: CL-ILT-1269434 Cross Reference Number:
The plant is operating at rated thermal power with Div 3 DG out of service.
Topic:
Evaluate the indicat Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with
- CPS 5010.01 (1A) Rev. 27 Revision Number:
- CPS 5062.01 (1A) Rev.
30a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 5010.01 (1A)
ON-## not provided)
- CPS 5062.01 (1A)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: Conduct of Operations Category / KA Statement: 2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
RO Value: 4.6 SRO Value: 4.3 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: NA
69 ID: 1269099 Points: 1.00 Plant conditions are as follows:
- A startup is in progress.
- The Reactor Mode Switch is in the STARTUP & HOT STBY position.
- Reactor power is 2%.
- It is then discovered that both Rod Pattern Controller Channels are NOT operable.
Which ONE of the following actions are required to be taken as a result of these conditions?
A. Commence a normal plant shutdown.
B. Suspend rod movement except by scram.
C. Immediately place the reactor mode switch in shutdown.
D. Suspend control rod withdrawal ONLY (rods may be inserted).
Answer: B Answer Explanation B is correct - One hour or less action statement from ITS 3.3.2.1 Condition B. (One or more rod pattern controller channels inoperable.) Required action is B.1 - Suspend control rod movement except by scram. Completion time - Immediately.
Incorrect answers:
A is incorrect but plausible if the examinee incorrectly recalls the requirements for a RPC system inoperability and believes the ITS requirement is to shutdown the plant.
C is incorrect but plausible if the examinee incorrectly recalls the requirements for a RPC system inoperability and believes the ITS requirement is to immediately place the reactor mode switch in shutdown. ITS 3.3.2.1 allows continued plant operation while resolving the inoperability of the RPC.
D is incorrect but plausible - this is the required action for in inoperable rod withdrawal limiter channel(s).
KA Justification - this question meets the KA because the examinee demonstrates an understanding of entry-level conditions for Technical Specifications by correctly selecting the required action based on the conditions presented in the stem. The completion time for the correct Action statement is less than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Cog Level Justification - this is a low cog question written at the simple memory level. The examinee must recall the correct Action statement based on the entry conditions presented in the stem.
Question 69 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269099 User-Defined ID: CL-ILT-1269099 Cross Reference Number:
Plant conditions are as follows:
Topic:
A startup is in progress.
The Reactor Mode Switch is in the ST Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with ITS 3.3.2.1 Amend. 95 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14068)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision NA History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure ITS 3.3.2.1 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1P)
KA Data KA Number / System Name: 2.2 Equipment Control Category / KA Statement: 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
RO Value: 3.9 SRO Value: 4.6 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.7/41.10 10CFR55-43 (SRO) Data: 43.2/43.3
70 ID: 1269103 Points: 1.00 Plant conditions are as follows:
- Mode 4 - cold shutdown
- Both Reactor Recirculation (RR) Pumps are secured.
- Residual Heat Removal (RHR) 'A' is in Shutdown Cooling mode.
- Preparations are in progress to start BOTH RR Pumps to support plant startup.
Parameter Value RHR Heat Exchanger 'A' inlet temperature 130°F Bottom head drain temperature 108°F RR Loop 'A' temperature 120°F RR Loop 'B' temperature 115°F Which of the following describes the operator response to these conditions?
A. Lower RHR Heat Exchanger 'A' outlet temperature.
B. Open the Recirc FCVs to raise flow through the core.
C. Close the Recirc FCVs to lower flow through the core.
D. The temperature differences are within limits; startup of the idle Recirc Loops may proceed.
Answer: D
Answer Explanation D is correct - per 3302.01 Reactor Recirculation (RR) during recirculation pump start, three parameters are verified:
Description Limit Actual Value Difference between bottom head coolant temperature 100°F 22°F*
and RPV coolant temperature Difference between the RPV coolant temperature in 50 °F 'A' - 10°F*
the RR loop to be started and the RPV coolant 'B' - 15°F*
temperature Difference between idle RR loop to be started and the 50°F 5°F other RR loop
- RPV Coolant temperature is monitored using RHR Hx inlet temperature on recorder E12-R601 on 1H13-P601. Steam Dome temperature can NOT be used when coolant temperature is <
214°F because it is derived from reactor pressure and is not valid below 214°F.
Therefore, the temperature differences are within limits and startup of the idle RR loops may proceed.
Incorrect Responses:
A is incorrect but plausible - The candidate may select this response if he/she incorrectly believes that the RPV coolant temperature must be lowered. The temperature differences are within limits of 3302.01 Reactor Recirculation (RR).
B is incorrect but plausible - The candidate may select this response if he/she incorrectly applies the CPS 3302.01 Reactor Recirculation (RR) idle loop restoration requirement to open the idle loop's FCV when the T between an idle and OPERATING loop is > 50 °F. With no recirculation pumps operating, opening the RR FCVs will have no effect on RR loop flow or temperature.
C is incorrect but plausible - The candidate may select this response if he/she incorrectly applies the CPS 3302.01 Reactor Recirculation (RR) idle loop restoration requirement to OPEN the idle loop's FCV when the T between an idle and OPERATING loop is > 50 °F. With no recirculation pumps operating, closing the RR FCVs will have no effect on RR loop flow or temperature.
KA Justification - this question meets the KA because the examinee demonstrates an understanding of pre-startup procedures on plant equipment that could affect reactivity by correctly selecting the action required based on conditions presented in the stem.
Cog Level Justification - this is a low cog question written at the simple memory level. The examinee must recall procedure steps and precautions, selecting the correct response by applying that knowledge to the conditions provided in the stem.
Question 70 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269103 User-Defined ID: CL-ILT-1269103 Cross Reference Number:
Plant conditions are as follows:
Topic:
Mode 4 - cold shutdown Both Reactor Recirculation (RR) Pumps a Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3302.01 Rev 35e Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14074)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision NA History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3302.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1P)
KA Data KA Number / System Name: 2.2 Equipment Control Category / KA Statement: 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
RO Value: 4.5 SRO Value: 4.4 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.5/41.10 10CFR55-43 (SRO) Data: 43.5
71 ID: 1269104 Points: 1.00 An individual has 1800 mR TEDE annual exposure.
This worker is required to perform an evolution with an exposure estimate of 400 mR.
Which of the following describes the appropriate dose controls?
A. No Dose Extension is required B. Admin Dose Extension is required C. Planned Special Exposure is required D. No further exposure is permitted Answer: B Answer Explanation B is correct. Per RP-AA-203 Exposure Control and Authorization, you must use Attachment 1, Dose Control Level Extension Form, or a computerized equivalent, to authorize exposures for adult individuals in excess of 2000 mrem routine TEDE in a year.
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that a dose extension is not required because the candidate believes that no action is required until a different increment such as the 10CFR20 Limit (5000 mr) is reached.
C is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that a Planned Special Exposure is required when exceeding 2000 mrem instead of the 10CFR20 Limit. This evolution does not meet the definition of a PSE contained in RP-AA-203 (an infrequent exposure to radiation, separate from and in addition to the annual exposure limits).
D is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that the individual has reached a limit or will reach a limit that cannot be exceeded if this work evolution is performed.
KA Justification - this question meets the KA because to answer the question the examinee must recognize the appropriate dose controls based on radiation exposure limits under normal conditions.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recall radiation exposure limits and recognize the proceduralized dose controls required during a normal evolution.
Question 71 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269104 User-Defined ID: CL-ILT-1269104 Cross Reference Number:
An individual has 1800 mR TEDE annual exposure.
Topic:
This worker is required to perform an evolution Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with RP-AA-203 Rev. 3 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- ILT 10-1 NRC exam (CL-ILT-05, OYS CERT-04) N11070)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table and History: (i.e. Modified distractor justifications, wdk 5/09/2016.
b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure RP-AA-203 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 2.3 Radiation Control Category / KA Statement: 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
RO Value: 3.2 SRO Value: 3.7 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.12 10CFR55-43 (SRO) Data: 43.4
72 ID: 1268856 Points: 1.00 Operations is required to enter a radiation area to perform several valve manipulations.
Based on ALARA considerations, which of the following approaches should be used to minimize total collective dose?
A. ONE individual performing the job in a 60 mr/hr field for 60 minutes.
B. TWO individuals performing the job in a 60 mr/hr field for 20 minutes.
C. ONE individual installing and removing temporary shielding in a 60 mr/hr field for a total of 30 minutes, AND then performing the job in a 6 mr/hr field for 60 minutes with ONE individual.
D. TWO individuals installing and removing temporary shielding in a 60 mr/hr field for a total time period of 15 minutes, AND then performing the job in a 6 mr/hr field for 40 minutes with TWO individuals.
Answer: C Answer Explanation C is correct - With the data provided in the answer choice, 36 mr total exposure is received by the individual installing temporary shielding and performing the job. (60 mr/hr for 30 minutes = 30 mr) + (6 mr/hr for 60 minutes = 6 mr). 30 + 6 = 36 mr Incorrect Answers:
A is incorrect but plausible - The examinee may determine that ALARA is maintained by performing the job with the least number of individuals in the least amount of time. For this case however, total collective dose is 60 mr.
B is incorrect but plausible - The examinee may determine that ALARA is maintained by performing the task with two individuals in the least amount of time. For this case however, total collective dose is 40 mr (2 x 20 = 40).
D is incorrect but plausible - The examinee may determine that ALARA is maintained by performing the task with two individuals in the lowest dose field. For this case however, total collective dose is 38 mr.
KA justification - this question meets the KA because the examinee has to use knowledge of the radiological safety principle of ALARA (time, distance, and shielding) to determine which case results in the lowest total collective dose to plant operations personnel in the performance of licensed duties.
Cog Level justification - this question is a high cog question written at the analysis level. The examinee must solve a problem using knowledge of the ALARA principle (time, distance and shielding) to answer the question.
Question 72 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268856 User-Defined ID: CL-ILT-A14071 Cross Reference Number:
Operations is required to enter a radiation area to perform several valve manipulations.
Topic:
Based o Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with RP-AA-16 Rev. 0 Revision Number: HU-AA-1081-F-06 Rev. 3 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14071)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Enhanced stem and Cog Level History: (i.e. Modified distractor justification statements, wdk b to make plausible based on 5/09/2016.
OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure RP-AA-16 ON-## not provided) HU-AA-1081-F-06 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 2.3 Radiation Control Category / KA Statement: 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
RO Value: 3.2 SRO Value: 3.7 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.12 10CFR55-43 (SRO) Data: NA
73 ID: 1268855 Points: 1.00 An irradiated fuel bundle being moved from the Reactor Cavity to the Inclined Fuel Transfer System becomes ungrappled and falls into the Reactor vessel downcomer area.
Which of the following people would be at greatest risk of radiation overexposure?
A. Refuel SRO on the Bridge B. Operator in Fuel Building 755' elevation C. Mechanic installing Safety Relief Valves D. Instrument Maintenance Technician at Standby Liquid Control Skid Answer: C Answer Explanation
C is correct. Per CPS 3007.01 Preparation and Recovery from Refueling Operations, RP must be contacted prior to entry into upper elevations of the drywell during spent fuel movement. Per CPS 4979.07 Dropped of Irradiated Fuel Bundle, dropping an irradiated fuel bundle poses a significant radiological problem. The mechanic would have the greatest risk because he could move into an area with very little shielding between him and the dropped fuel bundle.
A, B, and D are all incorrect but plausible. In the case of each distracter, the other personnel have either large quantities of water or concrete as shielding. The candidate may select any of these responses if he/she understands that dropping an irradiated fuel bundle poses a significant radiological problem, but incorrectly believes that any of these personnel are in a closer proximity to the dropped irradiated fuel bundle than the mechanic installing Safety Relief Valves.
KA Justification - this question meets the KA because to answer the question the examinee must recognize the radiation hazard to personnel during an activity (fuel move) resulting in a dropped irradiated fuel bundle and requiring entry into multiple abnormal procedures.
Cog Level Justification - this is a low cog question written at the memory level - the examinee must recognize the radiological risk to personnel based on their location in the plant during a significant radiological problem to answer the question.
Question 73 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268855 User-Defined ID: CL-ILT-1268855 Cross Reference Number:
An irradiated fuel bundle being moved from the Reactor Cavity to Topic:
the Inclined Fuel Transfer Syst...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 3007.01 Sect. 4.10 Rev.
Revision Number: 19e CPS 4979.07 Sect. 6.1 Rev.
8e Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- ILT 10-1 NRC exam (CL-ILT-05, OYS CERT-04) N11071)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Added General Data table and History: (i.e. Modified distractor justifications, wdk 5/09/2016.
b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 3007.01 Sect. 4.10 ON-## not provided) CPS 4979.07 Sect. 6.1 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-S)
KA Data KA Number / System Name: 2.3 Radiation Control Category / KA Statement: 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
RO Value: 3.4 SRO Value: 3.8 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.12 10CFR55-43 (SRO) Data: 43.4
74 ID: 1269214 Points: 1.00 The plant was at 30% RTP when the following occurred:
Time 02:30:00 Rod Out Block and Rod Drift alarms.
Time 02:30:10 RO determines Rod 24-29 is the only rod moving.
Time 02:30:15 RO selects Rod 24-29 and notes rod is at position 34.
Time 02:30:25 RO notes a small rise in Reactor Power to 33% RTP.
Assuming Reactor Recirculation flow has NOT changed, which ONE of the following actions is required?
A. SCRAM the reactor.
B. Depress ROD SELECT CLEAR push-button.
C. Allow the rod to proceed and stop at notch 48.
D. Depress and hold the IN TIMER SKIP pushbutton.
Answer: D Answer Explanation D is correct. Per CPS 4007.02 Inadvertent Rod Movement 3.0 Immediate Actions:
NOTE WITHDRAWALS starting from notch 44 or 46 should be allowed to proceed to and stop at notch 48 3.2 Rod Withdrawing [rod moves starting from notches 00 - 42]
- 1. Select/verify selected the moving rod, and then:
Depress and hold depressed IN TIMER SKIP push-button Therefore, the RO would depress and hold the IN TIMER SKIP push-button in an attempt to stop rod motion.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she fails to recall that the immediate action to SCRAM the reactor is only applicable if more than one rod drift light is energized (signifying multiple rods drifting) and incorrectly believes that a SCRAM is required for a single rod withdrawing.
B is incorrect but plausible. The candidate may select this response if he/she fails to recognize that the most recent change to CPS 4007.02 changed the immediate actions for Rod Inserting to be identical to the immediate actions for Rod Withdrawing and confuses the old immediate action for Rod Inserting (Depress ROD SELECT CLEAR push-button) as the correct response.
C is incorrect but plausible. The candidate may select this response if he/she fails to recognize the significance of the rod position (< notch 44) and incorrectly believes that allowing the rod to proceed to and stop at notch 48 is the correct response.
KA Justification - this question meets the KA because the examinee must be able to select the appropriate actions from memory that require immediate operation of system components and controls based on plant conditions provided in the stem.
Cog Level Justification - this is a high cog question written at the analysis level. The examinee has to analyze the parameters provided in the question stem, identify the event and select the appropriate off-normal immediate actions to mitigate that event.
Question 74 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1269214 User-Defined ID: CL-ILT-1269214 Cross Reference Number:
The plant was at 30% RTP when the following occurred:
Topic:
Time 02:30:00 Rod Out Block and Rod Dri...
Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with CPS 4007.02 Rev. 13C Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4007.02 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 2.4 Emergency Procedures / Plan Category / KA Statement: 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
RO Value: 4.6 SRO Value: 4.4 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.2
75 ID: 1269453 Points: 1.00 A transient has occurred requiring entry into EOP-6 Primary Containment Control.
Given the detail below:
In which of the following scenarios is Containment Spray permitted?
RPV CNMT CNMT Pressure Level Temperature Scenario 1 -92" 140°F 1.5 psig Scenario 2 -92" 150°F 3.0 psig Scenario 3 -102" 140°F 1.5 psig Scenario 4 -102" 150°F 3.0 psig A. Scenario 1 ONLY B. Scenario 2 ONLY C. Scenario 1 AND 3 ONLY D. Scenario 2 AND 4 ONLY Answer: B Answer Explanation B is correct. Per EOP-6 PRIMARY CONTAINMENT CONTROL and the EOP Tech Bases, containment sprays are initiated when containment pressure and temperature is within the "OK TO SPRAY" (unshaded) region of Figure O Containment Spray Initiation Limit. The note states "Do not use RHR pumps you need for core cooling".
Per OP-CL-101-111-1001 Strategies for Successful Transient Mitigation, Alignment of Systems Needed For Adequate Core Cooling (ACC): A trigger point of "-100 inches and lowering" is recommended for evaluating the need to re-align injection systems and/or initiate/maintain containment sprays.
With containment pressure and temperature in the "OK TO SPRAY" region of Figure O and RPV level above the trigger point of -100 inches, the RHR pumps are not needed for core cooling and containment spray IS permitted.
Incorrect Responses.
A is incorrect but plausible. The candidate may select this response if he/she recognizes that RPV level is above the trigger point of -100 inches but misreads Figure O or fails to recall the bases for the graph.
C is incorrect but plausible. The candidate may select this response if he/she fails to recognize that RPV level is below the trigger point of -100 inches and therefore RHR pumps ARE needed for core cooling vice containment spray while also misreading Figure O or failing to recall the bases for the graph.
D is incorrect but plausible. The candidate may select this response if he/she fails to recognize that RPV level is below the trigger point of -100 inches and therefore RHR pumps ARE needed for core cooling vice containment spray but correctly reads Figure O and determines that containment spray is permitted based on Figure O only.
KA Justification - this question meets the KA because the examinee must have knowledge of the note in EOP-6 regarding the use of RHR pumps for containment spray that may be needed for core cooling. Additionally, the examinee must apply the operational stategies of OP-CL-101-111-1001 with regard to RPV level to determine the correct response.
Cog Level Justification - this is a high cog question written at the analysis level. The examinee has to analyze the parameters provided in the question table, compare them to EOP-6 Figure O, OP-CL-101-1001, and then determine impact on the use of containment sprays.
Question 75 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1269453 User-Defined ID: CL-ILT-1269453 Cross Reference Number:
A transient has occurred requiring entry into EOP-6 Primary Containment Control.
Topic:
Given the detai Num Field 1:
Num Field 2:
Text Field:
Comments: General Data Technical Reference with EOP-TB Rev. 6 Revision Number: CPS 4402.01 Rev. 30 OP-CL-101-111-1001 Rev. 12 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure EOP-TB ON-## not provided) CPS 4402.01 OP-CL-101-111-1001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK / SPR)
KA Data KA Number / System Name: 2.4 Emergency Procedures / Plan Category / KA Statement: 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.
RO Value: 3.8 SRO Value: 4.3 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 1 ID: 1268849 Points: 1.00 The plant was operating in Mode 1 when a transient occurred resulting in the sequence of events shown below:
Time Event 10:00 Station experiences a loss of ALL AC power.
10:00 MCR begins performing actions per EOP-1 RPV Control and CPS 4200.01 Loss of AC Power.
11:00 Shift Manager declares an Extended Loss of AC Power (ELAP) condition exists.
11:00 MCR enters CPS 4306.01 Extended Loss of AC Power / Loss of Ultimate Heat Sink.
14:00 RPV level is being maintained using the preferred injection source.
15:30 Upper Containment Pools are dumped IAW CPS 4306.01.
Current plant conditions are as follows:
Parameter Value Trend Suppression Pool Level 21" 0" steady Suppression Pool Temperature 163°F rising RPV Pressure 900 psig cycling between 800-1000 psig Based on these conditions, which of the following RPV pressure control actions is required?
A. Maintain RPV pressure 800 - 1065 psig.
B. Commence cooldown to 150 - 250 psig using SRVs at < 100°F/hr.
C. Enter EOP-3 Emergency RPV Depressurization (Blowdown) and depressurize the reactor to 150 - 250 psig.
D. Enter EOP-3 Emergency RPV Depressurization (Blowdown) and perform emergency depressurization to < 52 psig RPV pressure.
Answer: C CPS OPS ILT EXAM Page: 1 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation C is correct:
Per CPS 4402.01 Primary Containment Control Figure P Heat Capacity Limit, the HCTL is being exceeded with Suppression Pool Temperature at 163°F, Suppression Pool Level at 21" 0", and RPV pressure cycling between 800-1000 psig. The SP temperature leg of EOP-6 directs performing a blowdown if suppression pool temperature cannot be held below the HCTL limit.
Per the override at the top of EOP-3 Emergency RPV Depressurization (Blowdown), if RPV depressurization will result in loss of injection needed for core cooling, then control RPV pressure as low as possible using Alternate Depressurization Systems (Detail L) while maintaining adequate core cooling (150-250 psig).
The EOP Technical Bases discussion for EOP-3 states the following:
Under circumstances requiring emergency RPV depressurization, it is generally desirable to fully depressurize the RPV and cool down the plant to cold shutdown conditions. However, while RPV pressure reductions will tend to increase flow from motor-driven injection sources and mitigate containment challenges, full depressurization may result in loss of steam-driven injection systems. RPV depressurization and cooldown must therefore be coordinated with core cooling strategies. Full depressurization and cooldown is appropriate only if adequate core cooling will not be sacrificed as a result. Loss of adequate core cooling would compound the plant challenges requiring emergency depressurization and increase any resulting radioactivity release. Core cooling is thus prioritized over other EOP objectives. If, at any time during RPV depressurization, it is anticipated that continued pressure reduction will result in loss of injection flow required for adequate core cooling, the depressurization is terminated. Pressure is then controlled as low as practicable but above the minimum value at which the required injection flow can be sustained.
With RCIC as the only available injection source during a complete loss of AC event, the RPV should not be fully depressurized to avoid loss of injection flow required for adequate core cooling, and should be maintained between 150 to 250 psig as described above.
A is incorrect but plausible - The RPV Pressure Control Block of CPS 4306.01 Extended Loss of AC Power / Loss of Ultimate Heat Sink directs controlling RPV pressure per EOP-1 RPV Control.
The pressure leg of EOP-1 directs stabilizing RPV pressure below 1065 psig. OP-CL-101-111-1001 Strategies For Successful Transient Mitigation section 4.1.3.6.B EOP 1 Pressure Leg directs providing an initial RPV pressure band of 800-1065 psig. Plausible if the examinee incorrectly believes that the pressure stabilization actions prescribed in CPS 4306.01 overrides the actions required by EOP-6 Suppression Pool Temperature Leg.
B is incorrect but plausible - The RPV Pressure Control Block of CPS 4306.01 Extended Loss of AC Power / Loss of Ultimate Heat Sink RPV Pressure Control Actions directs performing a cooldown to 150-250 psig using SRVs at < 100°F/hr after pressure is stabilized below 1065 psig and is being controlled per EOP-1 (answer choice A). This choice is plausible if the examinee incorrectly believes that the cooldown actions prescribed in CPS 4306.01 overrides the actions required by EOP-6 Suppression Pool Temperature Leg.
CPS OPS ILT EXAM Page: 2 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam D is incorrect but plausible - EOP-6 Primary Containment Control Suppression Pool Temperature leg requires a blowdown if SP temp cannot be maintained below HCTL. In EOP-3, a blowdown is performed by initiating ADS and allowing the RPV to depressurize to < than 52 psig. This choice is plausible if the examinee fails to recall that EOP-3 does not permit full depressurization if fully depressurizing will result in a loss of adequate core cooling which would occur if RCIC is lost in this scenario before AC power is restored to an AC driven ECCS system.
KA justification - this question meets the KA because the examinee must determine the pressure control actions required to be taken to maintain RPV water level during an extended loss of AC power to answer the question.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee must analyze the data provided in the stem and then determine required actions based on knowledge of several procedures (solve a problem using knowledge).
SRO only justification - this question is linked to SRO Only task 440201.02 Enter and Execute EOP-6 when required, and to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
CPS OPS ILT EXAM Page: 3 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 5 Difficulty: 4.00 System ID: 1268849 User-Defined ID: CL-ILT-1268849 Cross Reference Number:
The plant was operating in Mode 1 when a transient occurred Topic:
resulting in the sequence of events sho Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 4 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with
- CPS 4401.01 Rev. 30 Revision Number:
- CPS 4407.01 Rev. 30
- CPS 4402.01 Rev. 30
- CPS 4200.01 Rev. 24
- CPS 4306.01 Rev. 0
- EOP-TB Rev. 7
- OP-CL-101-111-1001 Rev. 12 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 4401.01 ON-## not provided)
- CPS 4407.01
- CPS 4402.01
- CPS 4200.01
- CPS 4306.01
- OP-CL-101-111-1001 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295003 Partial or Complete Loss of A.C. Power Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER : AA2.02 Reactor power /
pressure / and level RO Value: 4.2 SRO Value: 4.3 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 CPS OPS ILT EXAM Page: 5 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 6 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 7 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 2 ID: 1268343 Points: 1.00 The plant is operating at 90% rated thermal power with the 'A' VC train in service.
THEN, a fire alarm is received on 1H13-P661 Div 1 NSPS Cabinet.
The 'B' RO reports a red flashing strobe light at 1H13-P661 and a small fire in the upper section of 1H13-P661.
Under these conditions, which of the following describes the required operator action?
A. Start a second fire pump.
B. Place ALL of the SRV control switches in OFF on 1H13-P601.
C. Manually initiate Halon for 1H13-P661 at Fire Control Cabinet 1H13-U706.
D. Place VC 'A' Supply Air Filter Damper (0VC09YA/10YA/11YA) control switches in FILTER.
Answer: B CPS OPS ILT EXAM Page: 8 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation B is correct - per CPS 1893.04 Fire Fighting step 8.1.2, if a fire alarm occurs (red flashing strobe light) in MCR panel H13-P661, H13-P662 or the associated subfloor areas, and it cannot be immediately confirmed that a fire does not exist, then for 1H13-P661 or associated subfloor area, place the 16 Div 1 SRV handswitches in the OFF position.
This is performed to prevent a hot short from simultaneously opening all 16 SRVs.
A is incorrect but plausible - CPS 1893.04 step 8.1.6 requires starting a fire pump (if one is not running). There is no requirement to start both fire pumps.
C is incorrect but plausible - CPS 1893.04M364 CPS Pre-Fire Plan states that the MCR Halon suppression system is for sub-floor sections only. Discharging Halon into 1H13-P661 will not impact fires in the upper section of the panel.
D is incorrect but plausible - CPS 3402.01 step 8.3.4 Smoke Isolation requires placing the VC 'A' Supply Air Filter Damper control switches in FILTER ONLY if the supply air train fails to unisolate on detection of smoke or combustion products in the MCR as indicated by annunciator 5050-1J SMOKE VC SYS. Based on the question stem, the annunciator 5050-1J has NOT met it's setpoint to actuate and there is no reason for the candidate to believe that the system will not operate as designed.
KA justification - this question meets the KA because the examinee must determine the actions required to be taken for a fire in MCR Panel 1H13-P661 that has the potential to open all 16 SRVs from a hot short condition.
Cog Level Justification - this is a low cog question written at the memory level. The examinee must recall steps from a procedure to answer the question.
SRO only justification - this question is linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. The actions contained in this question are not immediate actions in an off-normal procedure and require knowledge of specific procedure content not required of the RO license.
Specifically, the question involves the assessment of plant conditions as presented and then selecting the section of a procedure (CPS 1893.04) with which to proceed.
CPS OPS ILT EXAM Page: 9 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 2 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268343 User-Defined ID: CL-ILT-1268343 Cross Reference Number:
The plant is operating at 90% rated thermal power with the 'A' VC train in service.
Topic:
THEN, a f...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 10 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with
- CPS 1893.04 Rev. 17d Revision Number:
- CPS 1893.04M364 Rev. 3
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 1893.04 ON-## not provided)
- CPS 1893.04M364
- CPS 3402.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 600000 Plant Fire On Site Category / KA Statement: AA2 Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:
AA2.04 The fire's extent of potential operational damage to plant equipment RO Value: 2.8 SRO Value: 3.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: NA 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 11 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 12 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 3 ID: 1268848 Points: 1.00 The plant was operating at 92% rated thermal power.
The Containment Instrument Air (IA) Inboard Isolation Valve (1IA006) failed CLOSED.
A manual reactor scram was initiated; however reactor power remained at 33% of rated thermal power.
At 1300, Standby Liquid Control (SLC) was initiated. The following indications were observed:
- SLC Suction Valve 1C41-F001A opened.
- SLC Suction Valve 1C41-F001B failed to open.
- SLC Discharge pressure is 1100 psig.
At 1320, SLC Storage Tank Level indicates zero (0) gallons.
At 1400, Reactor power is < IRM Range 7 and lowering.
Based on these conditions, what is the EARLIEST time that RPV depressurization can be commenced?
A. 1320 B. 1340 C. 1400 D. 1420 Answer: D CPS OPS ILT EXAM Page: 13 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation D is correct. Per CPS 4411.10 SLC Operations Section 2.1.3 NOTE: SLC Strg Tank Level, 1C41-R601 indication is not available on a CNMT IA isolation. Based on the plant conditions presented in the stem, the loss of IA to containment caused the SLC Tank Level indication to fail (0 gallons) at 1320. This is NOT indicative of actual tank level and cannot be used as criteria to commence depressurizing the RPV.
Per EOP-1A ATWS RPV Control RPV Pressure leg, the SRO must wait to depressurize the reactor until:
- Cold shutdown boron injected (Detail X)
Based on the plant conditions presented in the stem, reactor power is < Range 7 and lowering at 1400. However, since the crew commenced boron injection at 1300, this criteria cannot be used to commence depressurizing the RPV.
Per Detail X Cold Shutdown Boron, cold shutdown boron has been injected when:
- Alternate boron injection completed (4411.10)
Since the 'B' SLC pump suction valve (1C41-F001B) failed to open, only one (1) pump is injecting. Therefore, the 80 minutes run time for one (1) pump to inject cold shutdown boron is complete at 1420, allowing the SRO to commence depressurizing the RPV.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that level indication is available/accurate and depressurizing the RPV may commence when SLC tank level drops to 0 gal.
B is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that cold shutdown boron has been injected at 1340, allowing the SRO to commence depressurizing the RPV. The candidates confusion would be based on failing to recognize that one pump is not injecting or simply recalling the injection time for two (2) pumps vs. one (1).
C is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that reactor power being < Range 7 and lowering meets the criteria to commence depressurizing the RPV while failing to recognize that since the crew commenced boron injection at 1300, this criteria cannot be used.
KA justification - this question meets the KA because the examinee must analyze the plant conditions provided in the stem and determine how SLC tank level affects the mitigating actions of an ATWS (EOP-1A) based on that analysis.
Cog level justification - this is a high cog question written at the analysis/comprehension level.
The examinee has to analyze the plant conditions provided in the stem and determine when it is appropriate to commence depressurization/cooldown of RPV per EOP-1A based on that analysis.
SRO justification - this question is linked to SRO only task 440401.07 Determine when to commence RPV cooldown when executing EOP-1A and 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
CPS OPS ILT EXAM Page: 14 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 15 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268848 User-Defined ID: CL-ILT-1268848 Cross Reference Number:
The plant was operating at 92% rated thermal power.
Topic:
The Containment Instrument Air (IA) Inboard Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 16 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4404.01 (EOP-1A) Rev.
Revision Number: 30 CPS 4411.10 Rev. 6a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4404.01 (EOP-1A)
ON-## not provided) CPS 4411.10 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown Category / KA Statement: EA.2 Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: EA2.03 SBLC tank level RO Value: 4.3 SRO Value: 4.4 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 17 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 18 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 4 ID: 1268687 Points: 1.00 A LOCA has occurred causing the trends shown below.
Time Reactor WR RPV Containment Containment DW DW Temp Pressure (psig) Water Pressure Temperature Pressure (°F)
Level (psig) (°F) (psig))
(inches) 0 1021 21 0.33 82 0.1 105 0+5 767 (trending -105 2.2 146 4.5 197 minutes down) (trending down)
Appropriate EOPs have been entered and immediate actions performed.
Under these conditions, which of the following actions is required to be performed? Why?
A. Perform 4410.00C006 Defeating VP/WO Interlocks to prevent loss of RPV level instrumentation.
B. Prevent LPCS and LPCI injection to facilitate RPV water level control.
C. Initiate Containment Sprays to prevent exceeding Figure N Pressure Suppression Pressure.
D. Enter EOP-3 Emergency RPV Depressurization and perform an emergency depressurization to prevent further release of energy into the drywell or containment.
CPS OPS ILT EXAM Page: 19 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer: A Answer Explanation A is correct - performance of 4410.00C006 is required by EOP-6 if DW temperature cannot be maintained below 150°F.
B is incorrect but plausible - This action is performed before RPV pressure reaches 472 psig but not if RHR Pumps are needed for core cooling. With RPV level at -105 inches, RHR pumps are needed for core cooling. Per the guidelines of OP-CL-101-111-1001 Strategies for Successful Transient Mitigation, RPV injection sources (i.e., Residual Heat Removal (RHR), Low Pressure Core Spray (LPCS), etc.) are required to be maximized (aligned and capable of injection) when RPV level is below TAF, regardless of RPV pressure.
C is incorrect but plausible - Initiation of containment sprays is performed only if in the "OK to Spray" region of Figure O Containment Spray Initiation Limit and RHR Pumps are not needed for core cooling. With RPV level at -105 inches, RHR pumps are needed for core cooling per the guidelines of OP-CL-101-111-1001 Strategies for Successful Transient Mitigation.
D is incorrect but plausible - blowdown is required if DW temperature cannot be lowered and maintained below 330°F or containment temperature cannot be held below 185°F.
KA Justification - this question meets the KA because the examinee has to analyze the LOCA parameters (including DW pressure) provided in the stem, and then determine what actions are required to be performed to mitigate those conditions to answer the question.
Cog Level Justification - this is a high cog question because the examinee has to analyze the data provided in the question stem, and then determine required actions based on knowledge.
SRO Justification - this question is linked to SRO only task 100509.05 Determine when an EOP Support Procedure is to be performed.
Also linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
CPS OPS ILT EXAM Page: 20 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268687 User-Defined ID: CL-ILT-1268687 Cross Reference Number:
A LOCA has occurred causing the trends shown below.
Topic:
TimeReactor Pressure (psig)WR RPV Water Level Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 21 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4402.01 Rev. 30 Revision Number: OP-CL-101-111-1001 Rev. 12 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) usage.
Question Source: (i.e. New, Bank (CL-ILT-A14079)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data table.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure None ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295024 High Drywell Pressure Category / KA Statement: 2.4.6 Knowledge of EOP mitigation strategies.
RO Value: 3.7 SRO Value: 4.7 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 22 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 23 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 5 ID: 1268369 Points: 1.00 A plant transient occurred resulting in a reactor scram.
The Shift Manager has directed you to analyze plant performance associated with the scram IAW OP-AA-108-114 Post Transient Review to identify any performance deficiencies which would impact plant restart.
The following is an excerpt of all the RPS system alarms received during the transient.
Time Computer Pt Description State 19:42:12.158 C71NC013 TSV CLOSURE CH A TRUE 19:42:12.158 C71NC016 TSV CLOSURE CH D TRUE 19:42:12.158 C71NC014 TSV CLOSURE CH B TRUE 19:42:12.158 C71NC015 TSV CLOSURE CH C TRUE 19:42:12.158 C71NC032 1/2 SCRM IVA, IB, IIB, IIIA TRUE 19:42:12.158 C71NC030 1/2 SCRM IIA, IIIB, IVB, 1A TRUE 19:42:12.158 C71NC018 TCV FAST CLOSURE CH B TRUE 19:42:12.158 C71NC019 TCV FAST CLOSURE CH C TRUE 19:42:12.158 C71NC031 1/2 SCRM IIIA, IVB, 1B, IIA TRUE 19:42:12.158 C71NC029 1/2 SCRM 1A, IIB, IIIB, IVA TRUE
- 1) Based on these indications, which of the following ITS LCOs should be entered in the Potential LCO/Mode Restraint log in ESOMs?
- 2) If the required actions of ITS 3.3.1.1 are taken, does ITS 3.0.4 allow entry into Mode 2 without repair of the failed channel(s)?
3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each function in Table 3.3.1.1-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.1.1-1 Actions CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Place one channel in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> one channel inoperable. affected Function in trip.
B. One or more Functions with B.1 Place one channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> two channels inoperable. affected Function in trip.
A. 1) 3.3.1.1 A.1 ONLY
- 2) YES B. 1) 3.3.1.1 A.1 ONLY
- 2) NO C. 1) 3.3.1.1 A.1 AND B.1
- 2) YES D. 1) 3.3.1.1 A.1 AND B.1
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer: C Answer Explanation C is correct:
The alarm log indicates that the scram was caused by a Turbine trip, but two channels of the TCV Fast Closure RPS instruments failed to trip ('A' and 'D'). Per ITS Table 3.3.1.1-1 Function 9, 4 channels per function are required to be OPERABLE when Reactor Power is 33.3% of RTP (rated thermal power) and are tracked using the Potential LCO/Mode Restraint Log in ESOMs.
Per ITS 3.0.4, When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Since ITS 3.3.1.1 allows unlimited operation with one of the two inoperable RPS channels tripped, the plant can be transitioned to Mode 2 and a startup commenced.
A is incorrect but plausible if the examinee determines that a single TCV Fast Closure channel tripped requiring entry into ITS 3.3.1.1 A.1 only based on that analysis.
B is incorrect but plausible if the examinee determines that only a single TCV Fast Closure channel tripped and enters 3.3.1.1 A.1 only based on that analysis and also fails to recognize that ITS 3.0.4 permits transition to Mode 2 once one of the two inoperable channels are placed in trip.
D is incorrect but plausible if the examinee fails to recognize that ITS 3.0.4 permits transition to Mode 2 once one of the two inoperable channels are placed in trip.
KA Justification - this question meets the KA because the examinee has to review an alarm log showing plant response during a scram transient, and then determine what Technical Specifications apply.
Cog Level Justification - this is a high cog question written at the analysis/comprehension level.
The examinee has to analyze data from a log, compare the actual response of the plant to the expected response based on the examinee's knowledge, and then determine required actions based on that analysis.
SRO Justification - This question is linked to 10CFR55.43(b)(2), Facility operating limitations in the technical specifications and their bases. SROs are also responsible for applying generic LCO's (section 3.0 of ITS).
CPS OPS ILT EXAM Page: 25 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268369 User-Defined ID: CL-ILT-1268369 Cross Reference Number:
A plant transient occurred resulting in a reactor scram.
Topic:
The Shift Manager has directed you t...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 26 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with ITS 3.0 (3.0.4) Amendment Revision Number: No. 163 ITS 3.3.1.1 Amendment No.
95 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- CPS ILT 14-1 NRC exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-N14081)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data Table.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure ITS 3.3.1.1 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK / 3-SPR)
KA Data KA Number / System Name: 295006 SCRAM Category / KA Statement: 2.2.40 Ability to apply Technical Specifications for a system.
RO Value: 3.4 SRO Value: 4.7 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.2, 43.5 CPS OPS ILT EXAM Page: 27 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 28 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 6 ID: 1268493 Points: 1.00 The plant is in Mode 5 with core alterations in progress. Spent fuel is being temporarily stored in the upper containment pool racks. Continuous Containment Purge (CCP) is operating in Unfiltered mode and Fuel Building Ventilation (VF) is operating normally.
At 0100, the following annunciators were received:
- 5067-3L Hi-Hi Level Drywell Sump Equip/Flr Drn
- 5067-4L High Flow Drywell Equip Drn
- 5068-7A Refuel Bellows Leakage At 0107, MCR AR/PR LAN alarms (YELLOW tiles) with values slowly trending up for:
- CCP Exhaust Radiation Monitors 1RIX-PR042A, B, C, D
- Fuel Building Exhaust Radiation Monitors 1RIX-PR006A, B, C, D At 0110, the Refuel SRO reports Upper Containment Pool level is at the top of the Reactor Vessel/Steam Dryer Pools Weir Wall and lowering.
(1) Which listed action is required to be performed?
(2) Given the following excerpt from EP-AA-1003 Addendum 3 Emergency Action Levels for Clinton Station, what is the correct emergency classification for this event?
RA2 Significant lowering of RU2 Unplanned loss of water water level above, or level above irradiated fuel damage to, irradiated Emergency Action Level (EAL):
fuel. 1. a. UNPLANNED water level Emergency Action Level (EAL): drop in the reactor Refueling
- 1. Uncovery of irradiated fuel in Cavity. Spent Fuel Pool or Fuel the REFUELING PATHWAY. Transfer Canal as indicated by:
- Refueling Cavity water
- 2. Damage to irradiated fuel level <22 ft. 8 in. above the Table R1 resulting in a release of Reactor Vessel Flange Fuel Handling Incident radioactivity from the fuel as OR Radiation Monitors indicated by ANY Table R1
- Spent Fuel Pool or Upper
- Fuel Building Exhaust Radiation Monitoring reading Containment Fuel Storage (1PR006A-D) >1000 mRem/hr. Pool water level < 23 ft.
- Containment Exhaust 3. Lowering of spent fuel pool
- Indication or report of a (1PR001A-D) level to 11.00 ft as indicated on drop in water level in the
- Containment Fuel xfer 1LI-FC221A(B). REFUELING Pathway Plenum (1PR008A-D) AND
- b. UNPLANNED Area Radiation Monitor reading rise on one or more radiation monitor in Table R1.
A. (1) Establish secondary containment.
(2) RU2 B. (1) Establish secondary containment.
(2) RA2 CPS OPS ILT EXAM Page: 29 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam C. (1) Secure the operating Shutdown Cooling loop.
(2) RU2 D. (1) Secure the operating Shutdown Cooling loop.
(2) RA2 Answer: A Answer Explanation A is correct.
Part 1 Explanation:
Failure of the refueling bellows will result in draining the upper containment pools to the Drywell Equipment Drain system and reducing the level of water/shielding above the fuel stored in the upper containment pool racks and the RPV.
Receipt of annunciators 5067-3L and 5068-7A are symptoms of reactor cavity leakage during refueling requiring entry into CPS 4011.01 Reactor Cavity Leakage During Refueling.
If level approaches the top of any irradiated fuel, level cannot be restored, or high radiation levels exist, CPS 4011.01 Reactor Cavity Leakage During Refueling, subsequent action step 4.4 directs the following actions:
- Prohibit access to CNMT Refueling Floor
- Establish Secondary CNMT integrity Part 2 Explanation:
Based on plant conditions presented in the stem:
- Normal Upper Containment Pool level is 827' 3" and was reported at the top of the Reactor Vessel/Steam Dryer Pools Weir Wall (~ 827' 1"), signifying an UNPLANNED drop in water level in the REFUELING PATHWAY
- CCP Exhaust Rad Monitors (1RIX-PR042A-D) and FB Exhaust Rad Monitors (1RIX-PR06A-D) alarming at the ALERT level (Yellow tiles imply that PR042A-D read ~ 5 mRem/hr and PR006A-D read ~ 2 mRem/hr)) and slowly trending up, signifying an UNPLANNED Area Radiation Monitor reading rise on one or more radiation monitor (in Table R1)
Per EP-AA-1003 Addendum 3 Radiological Emergency Plan Annex for Clinton Station Cold Shutdown/Refueling Matrix for Abnormal Rad Levels / Radiological Effluents, the conditions for UNUSUAL EVENT RU2 Unplanned loss of water level above irradiated fuel has been met.
Incorrect Responses:
B is incorrect but plausible. The candidate may select this response if he/she determines that establishing secondary containment is required, but incorrectly determines that irradiated fuel in the REFUELING PATHWAY has been UNCOVERED (NOT reported by Refuel SRO) or alarming Rad Monitors (in Table R1) would be reading >1000 mRem/hr (based on the Yellow tiles) indicating damage to irradiated fuel, causing the candidate to believe the conditions for ALERT RA2 Significant lowering of water level above, or damage to, irradiated fuel has been met.
CPS OPS ILT EXAM Page: 30 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam C is incorrect but plausible. The candidate may select this response if he/she correctly determines the appropriate emergency classification but incorrectly determines that the proper course of action is CPS 4011.01 step 4.2 which directs securing the operating shutdown cooling RHR pump(s) if the leakage source has not been identified. The annunciators provided in the stem identify the leakage source making this step NA.
D is incorrect but plausible. the candidate may select this response if he/she incorrectly determines that:
- the proper course of action is CPS 4011.01 step 4.2 which directs securing the operating shutdown cooling RHR pump(s) if the leakage source has not been identified. The annunciators provided in the stem identify the leakage source making this step NA.
- irradiated fuel in the REFUELING PATHWAY has been UNCOVERED (NOT reported by Refuel SRO) or alarming Rad Monitors (in Table R1) would be reading >1000 mRem/hr (based on the Yellow tiles) indicating damage to irradiated fuel, causing the candidate to believe the conditions for ALERT RA2 Significant lowering of water level above, or damage to, irradiated fuel has been met.
KA Justification: This question meets the KA because given a refuel accident, the examinee must be able to evaluate/interpret the conditions presented in the stem and make operational judgements leading to an emergency classification.
Cog level justification - this is a high cog question written at the analysis/comprehension level.
The examinee has to analyze the plant conditions provided in the stem, determine the appropriate subsequent actions to be taken as well as an emergency classification based on that analysis.
SRO Justification - linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during emergency situations and 10CFR55.43(b)(7) for SRO Fuel handling facilities and procedures. Also linked to SRO only task 999999.12 Direct refueling activities as refueling supervisor.
CPS OPS ILT EXAM Page: 31 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 6 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1268493 User-Defined ID: CL-ILT-1268493 Cross Reference Number:
The plant is in Mode 5 with core alterations in progress. Spent Topic:
fuel is being temporarily store...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 32 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with EP-AA-1003 Addendum 3 Revision Number: Rev. 1 CPS 5067.03 (3L) Rev. 32c CPS 5067.04 (4L) Rev. 31 CPS 5068.07 (7A) Rev. 24 CPS 5140.63 Rev. 1b CPS 5140.65 Rev. 0c CPS 4011.01 Rev. 5 CPS 9000.02D001 Rev. 37a M05-1037-1 M05-1046-4 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam use.
05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure EP-AA-1003 Addendum 3 ON-## not provided) CPS 5067.03 (3L)
CPS 5067.04 (4L)
CPS 5068.07 (7A)
CPS 5140.63 CPS 5140.65 CPS 4011.01 CPS 9000.02D001 M05-1037-1 M05-1046-4 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK/SPR)
KA Data KA Number / System Name: 295023 Refueling Accidents Category / KA Statement: 2.1.7 Ability to evaluated plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.
RO Value: 4.4 SRO Value: 4.7 CPS OPS ILT EXAM Page: 33 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 34 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 7 ID: 1268411 Points: 1.00 Plant conditions:
- MODE Switch is in SHUTDOWN
- Multiple rods failed to insert
- 7 ADS SRVs are opened In accordance with ____(1)____, the CRS should direct the 'A' RO to commence injection into the RPV once reactor pressure first drops below the ____(2)____.
A. (1) EOP-1A (2) Decay Heat Removal Pressure B. (1) EOP-1A (2) Minimum Steam Cooling Pressure C. (1) EOP-3 (2) Decay Heat Removal Pressure D. (1) EOP-3 (2) Minimum Steam Cooling Pressure Answer: B Answer Explanation B is correct. Per CPS 4100.01 Reactor Scram, Shutdown Criteria is met when:
- All rods are full in at 00, OR
- No more than 1 rod out at position 02 or beyond, with all other rods in at 00 OR
- A qualified RE has determined that the reactor will remain shutdown under all conditions without boron Based on the conditions presented in the stem (multiple rods beyond position 02), shutdown criteria is NOT met. Per EOP-1 RPV Control, the CRS would have transitioned from EOP-1 to EOP-1A ATWS RPV Control.
Again, based on conditions presented in the stem, the CRS transitioned from EOP-1A to EOP-3 Emergency RPV Depressurization (Blow Down) and has initiated a Blow Down (as evidenced by the 7 open SRVs)
Per EOP-3, once the 7 SRVs are open, the CRS should re-enter EOP-1A and wait until RPV pressure lowers below the value in Table J. Per the EOP Technical Bases, as pressure lowers Adequate Core Cooling (ACC) is maintained as long as reactor pressure remains above the Minimum Steam Cooling Pressure (MSCP). At pressures above this value, the steam flow provides sufficient cooling to maintain ACC. Once reactor pressure drops below this value, injection must be restored.
Incorrect Responses:
CPS OPS ILT EXAM Page: 35 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam A is incorrect but plausible. The candidate may select this response if he/she correctly recognizes that based on plant conditions once the SRVs are open the CRS must transition back to EOP-1A but confuses Minimum Steam Cooling Pressure and Decay Heat Removal Pressure. This would lead the candidate to incorrectly believe that the RPV must be depressurized below the Decay Heat Removal Pressure (52 psig). Per the EOP Technical Bases (pg 7-16), when continuing in EOP-3 (non-ATWS condition) AND less than 5 SRVs open, "Depressurized" is defined to be an RPV pressure less than 52 psig, the Decay Heat Removal Pressure.
C is incorrect but plausible. The candidate may select this response if he/she fails to recognize that based on plant conditions once the SRVs are open the CRS must transition back to EOP-1A and therefore following EOP-3, also incorrectly believes that RPV must be depressurized below the Decay Heat Removal Pressure (52 psig). Per the EOP Technical Bases (pg 7-16), when continuing in EOP-3 (non-ATWS condition) AND less than 5 SRVs open, "Depressurized" is defined to be an RPV pressure less than 52 psig, the Decay Heat Removal Pressure.
D is incorrect but plausible. The candidate may select this response if he/she fails to recognize that based on plant conditions once the SRVs are open the CRS must transition back to EOP-1A but recognizes that as pressure lowers Adequate Core Cooling (ACC) is maintained as long as reactor pressure remains above the Minimum Steam Cooling Pressure (MSCP).
KA justification - This question meets the KA because the examinee must recognize that based on plant conditions RPV water level is below -162 inches (TAF) and therefore Adequate Core Cooling can no longer be maintained by RPV water level. Therefore, the candidate must understand how Adequate Core Cooling is determined based on RPV pressure.
Cog Level Justification - this is a low cog question written at the memory level. The examinee must recall facts and apply them to the specific situation.
SRO only justification - linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency conditions.
Requires knowledge of specific procedure content to perform Emergency RPV Depressurization and Recovery during ATWS conditions. Also linked to SRO only task 440701.04 (Direct actions to Emergency Depressurize per EOP-3 during ATWS).
CPS OPS ILT EXAM Page: 36 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1268411 User-Defined ID: CL-ILT-1268411 Cross Reference Number:
Plant conditions:
- MODE Switch is in SHUTDOWN Topic:
Multiple rods failed to insert
- All injection sy Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 37 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4407.01 Rev 30 Revision Number: CPS 4404.01 Rev 30 EOP Tech Bases Rev 6 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) usage.
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4407.01 ON-## not provided) CPS 4404.01 EOP Tech Bases LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1-B/1-P)
KA Data KA Number / System Name: 295031 Reactor Low Water Level Category / KA Statement: EA2. Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: EA2.03 Reactor Pressure RO Value: 4.2 SRO Value: 4.2 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 38 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 8 ID: 1649861 Points: 1.00
- The Unit was at 90% power when Main Condenser Vacuum began to degrade.
- Air in leakage from an unidentified source to the Main Condenser was approximately 200 scfm, and is slowly rising.
- Main Condenser Vacuum continues to degrade and is currently 25.0 Hg.
Which of the following actions is required to be performed next?
A. Initiate a Rapid Plant Shutdown.
B. Place both SJAE Trains in service.
C. Start an additional Circulating Water Pump.
D. Perform an Emergency Power Reduction to 80%.
Answer: D Answer Explanation D is correct - Per CPS 4004.02 Loss of Vacuum, Section 4.1 Low / Deteriorating Vacuum, subsequent action step 4.1.1 requires rapidly lowering reactor power to ~ 80% per CPS 3005.01, Unit Power Changes Section 8.2.3 (Emergency Power Reduction).
A is incorrect but plausible if the examinee incorrectly determines a Rapid Plant Shutdown is required based on knowledge that CPS 4004.02 step 4.1.2 requires performing a Rapid Plant Shutdown if condenser vacuum cannot be maintained above 24" Hg vac after performing the Emergency Power Reduction to 80%.
B is incorrect but plausible if the examinee incorrectly believes that placing both SJAE Trains in service is an appropriate mitigating actions for a deteriorating vacuum condition. Operating two SJAE Trains is not an acceptable resolution to excessive air in leakage. If a SJAE is not operating properly, procedures direct transferring to the standby SJAE train.
C is incorrect but plausible if the examinee incorrectly recalls the mitigating actions prescribed in CPS 4004.02 Loss of Vacuum. This answer would be correct if the loss/deteriorating vacuum was caused by inadequate Circulating Water flow through the Main Condenser. Since the loss of vacuum is being caused by high air inleakage, starting an additional CW Pump will not correct the low vacuum condition.
KA justification - this question meets the KA because the examinee has to interpret the deteriorating vacuum conditions in the stem and determine corrective actions to answer the question.
Cog Level Justification - this is a low cog question written at the memory level. The examinee has to recall actions contained in a procedure for low/deteriorating Main Condenser Vacuum.
SRO only justification - linked to 10CFR55.43(b)(5) - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Specifically, the question involves the assessment of plant conditions as presented and then selecting the section of a procedure (CPS 4004.02 Section 4.1) with which to proceed.
CPS OPS ILT EXAM Page: 39 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 8 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1649861 User-Defined ID: CL-ILT-1649861 Cross Reference Number:
The Unit was at 90% power when Main Condenser Vacuum Topic: began to degrade.
Air in leakage from an un Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 40 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4004.02 Rev. 6 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) usage.
Question Source: (i.e. New, Bank (duplicate of CL-ILT-Bank, Modified) 658253)
Low KA Justification (if required): NA Revision History: Revision Revised distracter A to make it History: (i.e. Modified distractor plausible. Added General b to make plausible based on Data Table. Revised the OTPS review) answer / distracter explanations. Added KA, cog level, and SRO only justification statements.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4004.02 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1-B/1-P)
KA Data KA Number / System Name: 295002 Loss of Main Condenser Vacuum Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM: EA2.01 Condenser vacuum/absolute pressure RO Value: 2.9 SRO Value: 3.1 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 41 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 42 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 9 ID: 1268788 Points: 1.00 The plant is operating at rated thermal power. The following conditions exist:
Parameter Value Containment Pressure -0.09 psig Secondary Containment Pressure -0.03 psig Drywell Pressure 0.10 psig Containment Temperature 123°F Drywell Temperature 140°F Suppression Pool Temperature 93°F Based on these conditions...
A. a DBA LOCA would cause DW temperature to exceed the DW design temperature limit.
B. an upper pool dump would result in an overflow of suppression pool water into the DW basement.
C. a DBA LOCA would cause Containment temperature to exceed the Containment design temperature limit.
D. containment spray must be initiated to prevent containment temperature from exceeding the containment design temperature limit.
Answer: C CPS OPS ILT EXAM Page: 43 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation C is correct - Per ITS B3.6.1.5, maintaining containment temperature below the LCO limit (115°F) ensures peak containment temperature during a design basis LOCA does not exceed the containment design temperature of 185°F.
A is incorrect but plausible - Per ITS B3.6.5.5, maintaining DW Temp below the LCO limit (146.53°F) ensures peak DW temperature during a design basis LOCA does not exceed the DW design temperature of 330°F. Plausible with DW temperature above normal values, but incorrect since value provided in the stem is below the LCO limit.
B is incorrect but plausible - Per ITS B3.6.5.4 DW Pressure, maintaining the DW to Cnmt dP within specification ( -0.02 psid and 1.0 psid) will prevent weir wall overflow after an inadvertent upper pool dump. Plausible since containment pressure is negative in the stem, however the DW to Containment dP is 0.19 psid which is within the tech spec limitation.
D is incorrect but plausible - EOP-6 Primary Containment Control requires containment spray to be initiated before containment temperature reaches 185 degrees if in the "OK to Spray" region of Figure O Containment Spray Initiation Limit. Since this is not the case with containment temperature at 123 degrees and containment pressure at -0.09 psig, containment sprays cannot be initiated.
KA Justification - this question meets the KA because the examinee has to determine the LCO bases that are impacted by the parameters and values provided in the stem.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee has to analyze the parameters in the table and Figure O, and then determine how the plant is impacted by that analysis to answer the question (3-SPK/R).
SRO Justification - this question is linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases. Additionally, while the LCO limit is RO level knowledge, knowing the bases that are required to analyze TS required actions and terminology is SRO only knowledge.
CPS OPS ILT EXAM Page: 44 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268788 User-Defined ID: CL-ILT-1268788 Cross Reference Number:
The plant is operating at rated thermal power. The following conditions exist:
Topic:
Parameter Val...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 45 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with
- ITS B3.6.1.5 Rev. 0 Revision Number:
- ITS B3.6.5.5 Rev. 0
- ITS B3.6.5.4 Rev. 0
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14092)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated General Data Table.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- ITS B3.6.1.5 ON-## not provided)
- ITS B3.6.5.5
- ITS B3.6.5.4
- CPS 4402.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK/R)
KA Data KA Number / System Name: 295011 High Containment Temperature (Mark III Containment Only)
Category / KA Statement: 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
RO Value: 3.2 SRO Value: 4.2 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5, 41.7 10CFR55-43 (SRO) Data: 43.2 CPS OPS ILT EXAM Page: 46 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 47 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 10 ID: 1268817 Points: 1.00 A plant heatup and pressurization is in progress, with the following conditions:
- Reactor Pressure is 80 psig
- Condenser Vacuum (CA) Pump 'A' is maintaining Main Condenser vacuum.
- A HIGH level alarm occurs on 0RIX-PR001, HVAC EXHAUST PRM #1.
- The alarm is NOT due to a spike.
- NO other PRMs are in alarm.
Based on these conditions, which of the following actions is required?
Securing CA Pump 'A' _____(1)_____ required, and placing Main Control Room Ventilation (VC) Train 'A' in Hi Rad Mode _____(2)_____ required.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Answer: B CPS OPS ILT EXAM Page: 48 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation B is correct - Per CPS 4979.01 Abnormal Release of Airborne Radioactivity, AR/PR Action Table 2 requires that any running Vacuum Pump(s) be stopped if 0RIX-PR001/2 reaches the high alarm setpoint, and requires verification that the in-service VC train shifts to High Rad Mode if 1RIX-PR009A-D reaches their high alarm setpoints. Since there is no indication that 1RIX-PR009A have reached the high alarm setpoint, placing VC in the High Rad Mode is not required.
A is incorrect but plausible if the examinee incorrectly believes that securing the CA Pump and shifting VC into High Rad Mode are required by CPS 4979.01 at the High value. Per CPS 4979.01 AR/PR Action Table 2, these actions are required if high alarms are reached on 0RIX-PR001/2, HVAC STACK EFF MONITOR #1/#2, and 1RIX-PR009A-D, MCR AIR INTAKE DUCTS. Since there is no indication that 1RIX-PR009A-D have reached the high alarm value, shifting VC into the High Rad Mode is not required.
C is incorrect but plausible if the examinee incorrectly believes that securing the CA Pump is not required by CPS 4979.01 at the High value. This would be the correct answer if 0RIX-PR001 was at the Alert value. Also incorrect because shifting VC into the High Rad Mode is not required because 1RIX-PR009A-D are not in alarm.
D is incorrect but plausible if the examinee misapplies the requirements for Alert Level actions instead of High Level actions for 0RIX-PR001 to CA Pump 'A'.
KA Justification - this question meets the KA because the examinee has to recall the procedural actions required in the event that a high alarm is received on a HVAC Exhaust PRM to answer the question.
Cog Level Justification - this is a low cog question written at the memory level. The examinee has to recall procedural actions to answer the question (1-F).
SRO Justification - this question is linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
The information needed to answer this question is contained in the subsequent actions of an off-normal procedure (not an immediate action step) and requires knowledge of specific procedure content.
CPS OPS ILT EXAM Page: 49 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 10 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268817 User-Defined ID: CL-ILT-1268817 Cross Reference Number:
A plant heatup and pressurization is in progress, with the following conditions:
Topic:
Reactor Pressur Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 50 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4979.01 Rev. 10b Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4979.01 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 295017 High Off-Site Release Rate Category / KA Statement: 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
RO Value: 4.3 SRO Value: 4.4 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 51 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 52 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 11 ID: 1268808 Points: 1.00 The plant is operating at 100% rated thermal power.
A reactor coolant chemistry excursion resulted in numerous LPRMs that failed downscale (marked with an asterisk and shaded).
Div 1 APRM Channel A LPRM Detectors06-23A
- 06-31B 14-31C
- 14-23D 22-07A
- 22-15B
- 14-47C 14-39D 22-23A
- 38-15B
- 30-47C 30-39D
- 38-23A
- 38-31B 46-15C
- 46-23D 38-39A
- 47-47C
- 06-23B
- 06-15C 14-15D
- 14-23A
- 06-39B 06-31C
- 14-47D
- 30-07A 22-23B
- 22-31C 30-15D 30-23A
- 30-39A 38-07B
- 38-15C
- 30-47D 46-23A
- 38-23B
- 46-31D
- 14-07B
- 06-23C 06-15D
- 14-31A
- 14-23B 06-39C
- 22-31D
- 30-31A 30-23B
- 22-39C 22-47D 30-47A
- 30-39B
- 38-07C
- 46-31A
- 46-39B
- 38-39C
- 38-47D
- 46-47A
- 14-15B
- 14-07C
- 06-23D 06-31A
- 14-31B
- 22-07D 22-31A
- 22-47A
- 30-39C 38-07D 38-31A
- 46-31B
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam NO LPRMs are bypassed.
The 'A' RO reports that channel checks performed on APRM A, B, C, and D are all satisfactory, and that APRM Gain Adjustment Factor (AGAF) values are as follows:
APRM AGAF Channel Value A 1.000 B 0.985 C 0.980 D 1.025 Given these conditions, which of the following actions are required in accordance with CPS Technical Specification 3.3.1.1 Reactor Protection System (RPS) Instrumentation?
Required actions are to declare _____ of the 4 APRM channels inoperable.
A. 1 B. 2 C. 3 D. 4 Answer: C CPS OPS ILT EXAM Page: 54 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation C is correct. Per ITS 3.3.1.1 RPS Instrumentation Surveillance SR 3.3.1.1.2 Verify the absolute difference between the average power range monitor (APRM) channels and the calculated power 2% RTP while operating at 21.6% RTP. At 100% RTP, the allowable AGAF is 0.980 - 1.020.
Per ITS B3.3.1.1, to consider an APRM channel OPERABLE, at least 16 LPRM inputs are required for each APRM channel, with at least two LPRM inputs from each of the four axial levels at which the LPRMs are located.
Based on the above information, the SRO will make the following APRM operability call:
- APRM 'A' is inoperable due to having less than two operable LPRM inputs on axial level 'A'.
- APRM 'C' is inoperable due to having less than 16 operable LPRM inputs.
- APRM 'D' is inoperable due to having an AGAF outside the acceptance criteria (> 1.020).
A is incorrect but plausible if the examinee identifies one inoperable APRM channel but fails to recognize the inoperable status of the other two APRM channels. The examinee may select this response if they fail to recall that each APRM requires at least two operable LPRM inputs on each axial level, a total of at least 16 LPRM inputs total or an AGAF outside the acceptance criteria base on the operating power level.
B is incorrect but plausible if the examinee identifies two inoperable APRM channel but fails to recognize the inoperable status of the third APRM channel. The examinee may select this response if they fail to recall that each APRM requires at least two operable LPRM inputs on each axial level, a total of at least 16 LPRM inputs total or an AGAF outside the acceptance criteria base on the operating power level.
D is incorrect but plausible if the examinee believes that all the APRMs are inoperable based on the conditions provided in the stem. The examinee may select this response if they incorrectly recall a total of at least 18 LPRM inputs required in addition to each APRM requiring at least two operable LPRM inputs on each axial level and the AGAF being outside the acceptance criteria base on the operating power level.
KA justification - this question meets the KA because the examinee must analyze the plant conditions provided in the stem and predict the effect on the APRM channels then, based on those predictions and using tech spec knowledge, mitigate the consequences by determining the operability of APRM channels based on that analysis.
Cog level justification - this is a high cog question written at the analysis/comprehension level.
The examinee has to analyze the plant conditions provided in the stem, determine the effect on the APRM channels and the operability of those APRM channels based on that analysis.
SRO justification - this question is linked to SRO only task 140109.23 Apply The Administrative Requirements For Execution Of Technical Specifications Or Off-Site Dose Calculation Manual Requirements and 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases. This question also requires knowledge of TS bases (2 LPRMs inputs on each axial level) to analyze TS required actions and terminology.
CPS OPS ILT EXAM Page: 55 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1268808 User-Defined ID: CL-ILT-1268808 Cross Reference Number:
The plant is operating at 100% rated thermal power.
Topic:
A reactor coolant chemistry excursion result Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 56 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with ITS 3.3.1.1 Amend. 192 Revision Number: ITS B3.3.1.1 Rev. 7-5 Justification for Non SRO CFR Linked to SRO only task Link: 140109.23 Apply The Administrative Requirements For Execution Of Technical Specifications Or Off-Site Dose Calculation Manual Requirements and 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Modified (CL-ILT-A12089)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Changed the condition in the History: (i.e. Modified distractor stem such that one of the b to make plausible based on distractors becomes the OTPS review) correct answer. Revised General Data table, answer explanation and justifications, wdk 4/19/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure ITS 3.3.1.1 ON-## not provided) ITS B3.3.1.1 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 215005 Average Power Range Monitor/Local Power Range Monitor Category / KA Statement: A.2 Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.08 Faulty or erratic operation of detectors/systems RO Value: 3.2 SRO Value: 3.4 Tier: 2 CPS OPS ILT EXAM Page: 57 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA (see justification above)
CPS OPS ILT EXAM Page: 58 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 59 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 12 ID: 1268686 Points: 1.00 The plant is operating at 92% power. Div 3 Diesel Generator is out of service (OOS) for preventive maintenance. All applicable technical specifications have been entered.
THEN, the MCR receives the following:
- Annunciator 5063-8H LPCS OUT OF SERVICE
- Status Light LPCS LINE BREAK DETECTED A Low Pressure Core Spray (LPCS) piping break between the ____(1)____ is the cause of these indications, AND ITS 3.8.1 AC Sources - Operating Required Action B.2 ____(2)____ required to be taken.
ITS 3.8.1 AC Sources - Operating CONDITION REQUIRED ACTION COMPLETION TIME B. One required DG B.2 Declare required 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery inoperable. feature(s), supported by of Condition B the inoperable DG, concurrent with inoperable when the inoperability of redundant required redundant required feature(s) are inoperable. feature(s)
A. (1) RPV wall and the Core Shroud (2) is B. (1) RPV wall and the Core Shroud (2) is NOT C. (1) core shroud and the LPCS sparger (2) is D. (1) core shroud and the LPCS sparger (2) is NOT Answer: A CPS OPS ILT EXAM Page: 60 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation Answer A is correct. Should a break occur in an injection line outside the core shroud, dP between the intact line and the broken line would increase. Per CPS 3315.02 Leak Detection (LD), If the HPCS, LPCS, or LPCI line breaks, a pressure transmitter will sense a high dP in one direction. If the dP is over the alarm setpoint, the respective transmitter will actuate an alarm and a "Line Break" Status Light. A line break in the LPCS injection line outside the core shroud would prevent LPCS from performing its safety function, rendering the system INOPERABLE.
Per ITS B3.8.1 AC Sources - Operating, Required Action B.2 is intended to provide assurance that a loss of offsite power, during the period that a DG is inoperable, does not result in a complete loss of safety function of critical systems. These features are designed with redundant safety related divisions (i.e., single division systems are not included, although, for this Required Action, Division 3 is considered redundant to Division 1 and 2 Emergency Core Cooling System (ECCS). Redundant required features failures consist of inoperable features associated with a division redundant to the division that has an inoperable DG.
Based on the conditions provided in the stem (LPCS and Div 3 DG/HPCS inoperable), Required Action B.2 must be taken.
Incorrect Responses:
B is incorrect but plausible. The candidate may select this response if he/she recognizes that a piping break between the RPV wall and the core shroud is required to cause the indications provided in the stem but fails to recognize that Div 3 is considered redundant to Div 1 and Div 2 ECCS systems, requiring ITS 3.8.1 Required Action B.2 to be taken.
C is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that a piping break inside the core shroud is required to cause the indications provided in the stem but recognizes that Div 3 is considered redundant to Div 1 and Div 2 ECCS systems, requiring ITS 3.8.1 Required Action B.2 to be taken.
D is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that a piping break inside the core shroud is required to cause the indications provided in the stem while also failing to recognize that Div 3 is considered redundant to Div 1 and Div 2 ECCS systems, requiring ITS 3.8.1 Required Action B.2 to be taken.
KA justification - this question meets the KA because the examinee is required to know the impact of a LPCS core spray line break and the required tech spec actions to mitigate that break in order to answer the question.
Cog level justification - this is a high cog question written at the analysis/comprehension level.
The examinee has to analyze the plant conditions provided in the stem and determine applicability of required actions based on that analysis.
SRO only justification - the first part of the question can be answered using RO level knowledge.
The second part of the question is linked to SRO only task 140109.23 Apply The Administrative Requirements For Execution Of Technical Specifications Or Off-Site Dose Calculation Manual Requirements and 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.
CPS OPS ILT EXAM Page: 61 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 4 Difficulty: 0.00 System ID: 1268686 User-Defined ID: CL-ILT-1268686 Cross Reference Number:
The plant is operating at 92% power. Div 3 Diesel Generator is Topic:
out of service (OOS) for preventive Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 62 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 5063.08 Rev. 35 Revision Number: CPS 3315.02 Rev. 14e ITS 3.8.1 Amend. 141 ITS B3.8.1 Rev. 3-5 Justification for Non SRO CFR Linked to SRO only task Link: 140109.23 Apply The Administrative Requirements For Execution Of Technical Specifications Or Off-Site Dose Calculation Manual Requirements Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 5063.08 ON-## not provided) CPS 3315.02 ITS 3.8.1 ITS B3.8.1 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK / SPR)
KA Data KA Number / System Name: 209001 Low Pressure Core Spray System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.05 Core spray line break RO Value: 3.3 SRO Value: 3.6 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA (See justification above)
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EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 64 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 65 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 13 ID: 1268772 Points: 1.00 The plant is operating at 92% rated thermal power.
- High Pressure Core Spray (HPCS) is in a normal standby lineup.
Complete the following with regard to the 1E22-F001 HPCS Storage Tank Suction Valve and 1E22-F015 HPCS Suppression Pool Suction Valve.
Once the "HPCS MOV Test Prep" handswitch is placed in the "TEST" position, thermal overload protection for 1E22-F001 and 1E22-F015 is bypassed inserted in the ____(1)____.
The HPCS system will be INOPERABLE when shifting HPCS suction from ____(2)____.
A. (1) CLOSED direction ONLY (2) RCIC Storage Tank to the Suppression Pool B. (1) CLOSED direction ONLY (2) Suppression Pool to the RCIC Storage Tank C. (1) OPEN and CLOSE direction (2) RCIC Storage Tank to the Suppression Pool D. (1) OPEN and CLOSE direction (2) Suppression Pool to the RCIC Storage Tank Answer: D CPS OPS ILT EXAM Page: 66 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation D is correct - Per CPS Operational Requirements Manual (ORM) Attachment 3 CPS Operational Requirements Manual (ORM) Motor Operated Valves Thermal Overload Protection, 1E22-F001 HPCS Storage Tank Suction Valve and 1E22-F015 HPCS Suppression Pool Suction Valve are protected in BOTH the OPEN and CLOSE direction.
Per CPS 9051.02 HPCS Valve Operability Test, step 8.1 and CPS 3309.01 section 8.1.7.2, the HPCS system will be INOPERABLE during the suction shift from the Suppression Pool to the RCIC Storage Tank until 1E22-F001 is open to re-establish pump suction path.
Per CPS 3309.01 High Pressure Core Spray (HPCS), section 8.1.7.1 Shifting HPCS Suction to Suppression Pool, 1E22-F015 HPCS Suppr Pool Suction Valve is opened, then 1E22-F001 HPCS Storage Tank Suction Valve is verified to automatically close.
Per CPS 3309.01 High Pressure Core Spray (HPCS), section 8.1.7.2 Shifting HPCS Suction to RCIC Storage Tank, 1E22-F015 HPCS Suppr Pool Suction Valve is closed, then 1E22-F001 HPCS Storage Tank Suction Valve is opened.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that bypassing thermal overload protection is only required in the CLOSED direction of 1E22-F001 and 1E22-F015 since it is necessary for one of the valves to CLOSED in order to obtain a proper suction path. This may be concluded due to the misconception that the safety function of 1E22-F001 and 1E22-F015 is in the CLOSED direction ONLY. Additionally, the candidate may also confuse the operation of the 1E22-F001/15 valves, believing that the 1E22-F001 must be SHUT prior to OPENING the 1E22-F015 during the suction shift from the RCIC Storage Tank to the Suppression Pool.
B is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that bypassing thermal overload protection is only required in the CLOSED direction of 1E22-F001 and 1E22-F015 since it is necessary for one of the valves to CLOSED in order to obtain a proper suction path. This may be concluded due to the misconception that the safety function of 1E22-F001 and 1E22-F015 is in the CLOSED direction ONLY. However, the candidate correctly identifies that the HPCS system will be INOPERABLE while shifting HPCS suction from the Suppression Pool to the RCIC Storage Tank until 1E22-F001 is open to re-establish pump suction path.
C is incorrect but plausible. The candidate may select this response if he/she correctly believes that bypassing thermal overload protection is required in BOTH the OPEN and CLOSE directions of 1E22-F001 and 1E22-F015 but confuses the operation of the 1E22-F001/15 valves, believing that the 1E22-F001 must be SHUT prior to OPENING the 1E22-F015 during the suction shift from the RCIC Storage Tank to the Suppression Pool.
KA justification - this question meets the KA because the examinee is required to have knowledge of surveillance procedures and recognize how certain equipment manipulations during that surveillance will affect the HPCS system.
Cog level justification - this is a high cog question written at the analysis/comprehension level.
The examinee has to analyze the HPCS system conditions during a surveillance and using knowledge, determine operability of the HPCS system.
SRO only justification - the first part of the question can be answered using RO level knowledge.
The second part of the question is linked to SRO only task 140109.23 Apply The Administrative Requirements For Execution Of Technical Specifications Or Off-Site Dose Calculation Manual Requirements and 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases. Correction made 2/9/17 and communicated to SRO applicants.
CPS OPS ILT EXAM Page: 67 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268772 User-Defined ID: CL-ILT-1268772 Cross Reference Number:
The plant is operating at 92% rated thermal power.
Topic:
High Pressure Core Spray (HPCS) is in a no...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 68 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 9051.02 Rev. 41c Revision Number: CPS ORM Att. 3 Rev. 69 CPS 3309.01 Rev. 17 Justification for Non SRO CFR Linked to SRO only task Link: 140109.23 Apply The Administrative Requirements For Execution Of Technical Specifications Or Off-Site Dose Calculation Manual Requirements Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 9051.02 ON-## not provided) CPS ORM Att. 3 CPS 3309.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 209002 High Pressure Core Spray System Category / KA Statement: 2.2.12 Knowledge of surveillance procedures.
RO Value: 3.7 SRO Value: 4.1 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: NA (See justification above)
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EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 70 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 14 ID: 1268631 Points: 1.00 The plant was operating at rated thermal power for a prolonged period until adverse weather conditions resulted in the following:
- Complete loss of all 138 KV and 345 KV power
- Generator trip and reactor scram
- Div 1 & 2 DGs failed to start Current conditions:
Parameter Value Trend Reactor power 0% steady Reactor pressure 936 psig rising Reactor water level -31.3 inches slowly lowering Suppression Pool Temperature 92°F slowly rising EOP-1 RPV control has been entered.
Based on the above conditions:
(1) What is the PREFERRED injection source?
(2) Which of the listed SRVs is required to be used FIRST for controlling reactor pressure?
A. (1) HPCS (2) F041D B. (1) RCIC (2) F041D CPS OPS ILT EXAM Page: 71 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam C. (1) HPCS (2) F041G D. (1) RCIC (2) F041G Answer: C Answer Explanation C is correct. Although the SRO is already in EOP-1 RPV Control, he/she will also enter CPS 4200.01 Loss Of AC Power based on the conditions presented in the stem - Station Blackout (SBO). CPS 4200.01 provides the direction for maintaining RPV water level and pressure consistent with EOP parameters.
Per CPS 4200.01 RPV water level is controlled Level 3 (8.9 in.) to Level 8 (52 in.) using High Pressure Core Spray (HPCS) or Reactor Core Isolation Cooling (RCIC). HPCS (with suction aligned to the suppression pool) is the preferred injection system.
Pressure control strategies in CPS 4200.01 directs the use of non-ADS SRVs first, followed by ADS SRVs in a sequence that minimizes uneven suppression pool heating and avoids the running HPCS or RCIC pump suction to preserve these systems for RPV level control.
Per CPS 3101.01 Main Steam (MS), Figure 1 SRV Discharge Locations, the SRV meeting these requirements is 41G (non-ADS SRV located at 122°).
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she recognizes that HPCS is the preferred injection system but fails to recognize that F041D is an ADS valve or that CPS 4200.01 directs the use of non-ADS SRVs first.
B is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that RCIC is the preferred injection system and also fails to recognize that F041D is an ADS valve or that CPS 4200.01 directs the use of non-ADS SRVs first.
D is incorrect but plausible. The candidate may select this response if he/she incorrectly believes that RCIC is the preferred injection system while correctly recalling that pressure control strategies in CPS 4200.01 directs the use of non-ADS SRVs first and that F041G meet that requirement.
KA justification - this question meets the KA because the examinee has to determine the correct method of RPV water level and pressure control by using an abnormal procedure in conjunction with an EOP.
Cog Level Justification - this is a high cog question because the examinee has to analyze conditions provided in the stem, use knowledge and a reference to determine the correct method of RPV water level and pressure control by using an abnormal procedure in conjunction with EOP-1.
SRO Justification - this question is linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Specifically, the question involves the assessment of plant conditions as presented and then selecting the section of a procedure (CPS 4200.01 Section 4.4) with which to proceed.
CPS OPS ILT EXAM Page: 72 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 73 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1268631 User-Defined ID: CL-ILT-1268631 Cross Reference Number:
The plant was operating at rated thermal power for a prolonged Topic:
period until adverse weather cond...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 74 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4200.01 Rev. 24 Revision Number: CPS 3101.01 Rev. 23c Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC Exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4200.01 Rev. 24 ON-## not provided) CPS 3101.01 Rev. 23c LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPR/SPK)
KA Data KA Number / System Name: 239002 Safety Relief Valves Category / KA Statement: 2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
RO Value: 3.8 SRO Value: 4.5 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 75 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 76 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 15 ID: 1268285 Points: 1.00 The plant was operating at rated thermal power when a loss of DC MCC 1A occurred.
Which one of the following identifies the effect this will have on the RCIC system and what action is required to be taken per Tech Spec 3.5.3 RCIC System?
Under these conditions, the RCIC system is INOPERABLE _____(1)_____.
(2) In addition to restoring the RCIC System to OPERABLE status, what are the MINIMUM actions REQUIRED in accordance with Tech Spec 3.5.3.RCIC System?
A. (1) AND unavailable (2) Perform CPS 9051.01 HPCS Pump & HPCS Water Leg Pump Operability.
B. (1) BUT available (2) Perform CPS 9051.01 HPCS Pump & HPCS Water Leg Pump Operability.
C. (1) AND unavailable (2) Examine logs or other information to determine HPCS system operability.
D. (1) BUT available (2) Examine logs or other information to determine HPCS system operability.
Answer: C CPS OPS ILT EXAM Page: 77 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation C is correct:
Per WC-AA-101 On-Line Work Control Process and ER-AA-310 Implementation of the Maintenance Rule, the terms AVAILABLE and UNAVAILABLE are defined as follows:
- Available - An SSC that is capable of performing its intended function(s). An SSC that can be restored to functional status within the timeframe associated with realistic conditions using proceduralized operator actions.
- Unavailability - The condition where equipment is out-of-service (e.g. tagged out) for corrective or preventive maintenance, or can not perform its Maintenance Rule function.
A loss of DC MCC 1A renders the RCIC System unavailable because RCIC cannot perform its intended function within the timeframe associated with realistic conditions using proceduralized operator actions.
Per ITS B3.5.3, OPERABILITY of HPCS is therefore verified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> when the RCIC System is inoperable. This may be performed as an administrative check, by examining logs or other information, to determine if the HPCS is out of service for maintenance or other reasons.
Verification does not require performing the Surveillances needed to demonstrate the OPERABILITY of the HPCS System.
Incorrect Responses:
A is incorrect but plausible if the examinee recognizes that due to a loss of Div 1 DC power, RCIC is in a position in which it is unable to to perform its intended function but incorrectly determines that the HPCS system operability test is required to be performed to satisfy ITS 3.5.3 required action A.1.
B is incorrect but plausible if the examinee fails to recognize that RCIC is rendered unavailable by a loss of Div 1 DC power and incorrectly determines that the HPCS system operability test is required to be performed to satisfy ITS 3.5.3 required action A.1.
D is incorrect but plausible if the examinee fails to recognize that RCIC is rendered unavailable by a loss of Div 1 DC power but correctly determines that the HPCS system must be verified OPERABLE by the administrative methods outlines in ITS B3.5.3, OPERABILITY of HPCS.
KA justification - this question meets the KA because the examinee is required to predict the impact of a loss of DC power to the RCIC system in order to answer the question, and to determine what actions are required to be performed as a result of the condition.
Cog level justification - this is a low cog question written at the memory level. The examinee must recall facts and apply them to a specific situation.
SRO only justification - the determination of SSC availability/unavailability is an SRO function at CPS and is supported by SRO only task 115112.01 Apply the administrative requirements of ON-LINE RISK ASSESSMENT. In addition the administrative actions required to verify HPCS system operability is contained in the Tech Spec Bases, which is SRO only knowledge. Linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.
CPS OPS ILT EXAM Page: 78 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 15 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268285 User-Defined ID: CL-ILT-1268285 Cross Reference Number:
The plant was operating at rated thermal power when a loss of DC MCC 1A occurred.
Topic:
Which one o...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 79 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with
- ITS 3.5.3 Amend. 163 Revision Number:
- ITS B3.5.3 Rev 10-3
- CPS 4201.01C001 Rev. 1
- WC-AA-101 Rev. 26
- ER-AA-310 Rev. 9 Justification for Non SRO CFR Linked to SRO only tasks Link: 115112.01 Apply the administrative requirements of ON-LINE RISK ASSESSMENT and 140109.23 Apply The Administrative Requirements For Execution Of Technical Specifications Or Off-Site Dose Calculation Manual Requirements.
Question History: (i.e. LGS NRC- ILT 12-1 NRC Exam 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-N12090)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Revised General Data table History: (i.e. Modified distractor and justification statements, b to make plausible based on wdk 4/11/2016 OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- ITS 3.5.3 ON-## not provided)
- ITS B3.5.3
- CPS 4201.01C001
- ER-AA-310 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1-P/1-I)
KA Data KA Number / System Name: 217000 Reactor Core Isolation Cooling System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.05 D.C. power loss RO Value: 3.3 SRO Value: 3.3 CPS OPS ILT EXAM Page: 80 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA (see justification above)
CPS OPS ILT EXAM Page: 81 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 82 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 16 ID: 1268275 Points: 1.00 A transient has occurred resulting in a loss of coolant accident requiring a blowdown per EOP-3 Emergency RPV Depressurization, which is complete.
Plant conditions have stabilized.
Given the detail below:
If both Fuel Zone instruments were inoperable, which, if any, of the following scenarios will require entry into EOP-2 RPV Flooding? (Assume the instruments are NOT indicating erratically.)
Wide Range RPV RPV Pressure DW Temp Cnmt Temp Level Scenario 1 -147" 55 psig 325°F 140°F Scenario 2 -131" 114 psig 275°F 205°F Scenario 3 -136" 45 psig 305°F 209°F A. Scenario 2 ONLY B. Scenario 3 ONLY C. Scenarios 1 & 3 ONLY D. Scenarios 1 & 2 ONLY Answer: B CPS OPS ILT EXAM Page: 83 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation B is correct. Per the level leg overrides in EOP-1 RPV Control and 1A ATWS RPV Control, RPV Flooding is required if RPV water level is unknown.
Per the instructions in Detail A (not provided in the stem) and CPS 4411.07 RPV Level Instrumentation:
- RPV water level instruments may be unreliable due to boiling in the instrument legs if drywell or containment temperature is above Fig. B, RPV Saturation Temperature.
- Do not use an RPV water level instrument if level is at or below Fig. C, Minimum Usable Levels.
> Fig. B? < Min Usable Level? Flooding Required?
Scenario 1 DW No (WR) No Scenario 2 No No (WR) No Scenario 3 DW Yes Yes Therefore, RPV Flooding is required for scenario 3.
Incorrect Responses:
A is incorrect but plausible if the examinee incorrectly determines that RPV flooding is required based solely on drywell or containment temperature being > the saturation curve of Fig. B.
C is incorrect but plausible if the examinee incorrectly determines that RPV flooding is NOT required based solely on drywell and containment temperature being < the saturation curve of Fig. B.
D is incorrect but plausible if the examinee incorrectly determines that the WR RPV Level indications in Scenarios 1 & 2 are below the minimum usable level values of Fig. C, requiring RPV flooding to be performed. In scenario 1, the minimum usable level for WR with containment temperature at 140°F is -149 inches. In scenario 2, the minimum usable level for WR with containment temperture at 205°F is -134 inches. With indicated level at -147" and -131" in scenarios 1 and 2 respectively, WR level can be utilized for RPV level indication and flooding is not required.
KA Justification: This question meets the KA because the examinee must be able to predict the impact of elevated containment temperature on RPV water level indication and use procedures to control the consequences of that abnormal condition.
Cog Level Justification - this is a high cog question because the examinee has to analyze conditions provided in the stem, use knowledge and a reference to determine available RPV water level indication and if entry into EOP-2 RPV Flooding is warranted.
SRO Justification - linked to SRO only task 440301.02 (Enter and Execute EOP-2 Flooding during NON-ATWS conditions) and 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. The question is also SRO ONLY level because the evaluation of plant parameters requires knowledge of the usage instructions of details in EOP-1. The interpretation of the data in the table and determining level is unknown to determine an entry condition into EOP-2 is the SRO's job at Clinton. Knowledge of EOP-2 RPV Flooding direct entry conditions is NOT RO level knowledge per the SRO Only clarification guidance.
CPS OPS ILT EXAM Page: 84 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 16 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1268275 User-Defined ID: CL-ILT-1268275 Cross Reference Number:
A transient has occurred resulting in a loss of coolant accident Topic:
requiring a blowdown per EOP-3 Eme Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 85 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4411.07 Rev. 6b Revision Number: 4401.01 RPV Control Detail A RPV Water Level Instruments Rev. 30 Justification for Non SRO CFR Linked to SRO only task Link: 440301.02 (Enter and Execute EOP-2 Flooding during NON-ATWS conditions) and 10CFR55.43(b)(5)
Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. The question is also SRO ONLY level because the evaluation of plant parameters requires knowledge of the usage instructions of details in EOP-
- 1. The interpretation of the data in the table and determining level is unknown to determine an entry condition into EOP-2 is the SRO's job at Clinton.
Knowledge of EOP-2 RPV Flooding direct entry conditions is NOT RO level knowledge per the SRO Only clarification guidance.
Question History: (i.e. LGS NRC- No previous NRC Exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Modified (CL-ILT-N12082)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Changed pertinent conditions History: (i.e. Modified distractor in the stem and at least one b to make plausible based on distractor. Updated General OTPS review) Data table, answer explanation and justifications, wdk 4/13/2016.
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4411.07 ON-## not provided) Detail A in EOP-1, 1A, 3, 6 and SAG-1 LORT PRA: (i.e. Yes or No or #) Yes LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO CPS OPS ILT EXAM Page: 86 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Station Clinton Cognitive Level Higher (3-SPR/SPK)
KA Data KA Number / System Name: 216000 Nuclear Boiler Instrumentation Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.08 Elevated containment temperature RO Value: 3.2 SRO Value: 3.4 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA (see justification above)
CPS OPS ILT EXAM Page: 87 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 17 ID: 1268533 Points: 1.00 The plant is in Mode 5 performing core alterations.
During the performance of a scheduled fuel move, the following sequence of events occurred:
- Refueling grapple was lowered over the bail handle for the fuel bundle and engaged (engagement with the fuel bundle bail handle was verified).
- Upon lifting the fuel bundle, the SLACK CABLE light cleared, but the HOIST LOADED light remained out.
Under these conditions:
- The Refueling Equipment Interlocks required by ITS 3.9.1 are ______(1)_____.
- The Refuel Position One-Rod-Out Interlock required by ITS 3.9.2 is _____(2)_____.
A. (1) OPERABLE (2) OPERABLE B. (1) OPERABLE (2) INOPERABLE C. (1) INOPERABLE (2) OPERABLE D. (1) INOPERABLE (2) INOPERABLE Answer: C Answer Explanation C is correct -
Per ITS B3.9.1 Refueling Equipment Interlocks, two channels of instrumentation are provided.
The following provide input to one or both channels: the position of the refueling platform, the loading of the refueling platform main hoist, and the full insertion of all control rods. With the reactor mode switch in the shutdown or refueling position, the indicated conditions are combined in logic circuits to determine if all restrictions on refueling equipment operations and control rod insertion are satisfied.
A control rod not at its full-in position interrupts power to the refueling equipment and prevents operating the equipment over the reactor core when loaded with a fuel assembly. Conversely, the refueling equipment located over the core and loaded with fuel inserts a control rod withdrawal block to prevent withdrawing a control rod.
Per CPS 9090.01 Refueling Interlocks Operability Test / One Rod Out Interlock Operability, the hoist loaded functions are tested in section 8.2 Fuel Grapple Position Interlock/Channel 1 and section 8.3 Fuel Grapple Position Interlock/Channel 2. These sections are used to satisfy ITS SR 3.9.1.1 Refueling Equipment Interlocks.
CPS OPS ILT EXAM Page: 88 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Per CPS 9090.01 Refueling Interlocks Operability Test / One Rod Out Interlock Operability, the Refuel Position One-Rod-Out Interlock is tested in section 8.1 and is used to satisfy ITS SR 3.9.2.1 Refuel Position One-Rod-Out Interlock. The hoist loaded functions are only tested in sections 8.2 and 8.3, not in section 8.1.
Therefore, failure of the "hoist loaded" function of the Refueling Platform will require declaring the Refueling Equipment Interlocks INOPERABLE, but do not affect the operability of the Refuel Position One-Rod-Out Interlock.
A is incorrect but plausible if the examinee fails to correctly recall the function of the Hoist Loaded interlock, and determines that the surveillance requirements for ITS 3.9.1 and 3.9.2 are met with the conditions provided in the stem. The examinee may select this choice if he/she incorrectly believes that the hoist loaded functions are satisfied when the slack cable light de-energizes while correctly recalling that the hoist loaded function does not impact the Refuel Position One-Rod-Out Interlock.
B is incorrect but plausible if the examinee fails to correctly recall the function of the Hoist Loaded interlock, and determines that the surveillance requirements for ITS 3.9.1 are met with the conditions provided in the stem. The examinee may select this choice if he/she incorrectly believes that the hoist loaded functions are satisfied when the slack cable light de-energizes while also incorrectly recalling that the hoist loaded function impacts the Refuel Position One-Rod-Out Interlock.
D is incorrect but plausible if the examinee fails to correctly recall the function of the Hoist Loaded interlock, and determines that the surveillance requirements for ITS 3.9.1 and 3.9.2 are NOT met with the conditions provided in the stem. As explained above, ITS 3.9.2 Refuel Position One-Rod-Out Interlock is not impacted by the hoist loaded function.
KA justification - this question meets the KA because the examinee has to determine how the conditions provided in the stem impact the operability of the fuel handling equipment to answer the question.
Cog Level Justification - this is a high cog question written and analysis and comprehension level.
The examinee has to analyze the conditions in the stem, and then determine how ITS requirements are impacted by the conclusions of the analysis.
SRO justification - since the refueling SRO performs surveillance procedure CPS 9090.01 and makes the determination that the surveillance has passed or failed, this question is linked to SRO only task 999999.12 (Direct Refueling Activities as the Refueling Supervisor) and 10CFR55.43(b)(7) Fuel handling facilities and procedures and is thus SRO only.
CPS OPS ILT EXAM Page: 89 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 3.00 System ID: 1268533 User-Defined ID: CL-ILT-1268533 Cross Reference Number:
The plant is in Mode 5 performing core alterations.
Topic:
During the performance of a scheduled f...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 90 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 9090.01 Rev. 34a Revision Number: ITS B3.9.1 Rev. 2-9 ITS B3.9.2 Rev. 0 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 9090.01 ON-## not provided) ITS B3.9.1 ITS B3.9.2 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 234000 Fuel Handling Category / KA Statement: 2.2.37 Ability to determine operability and/or availability of safety related equipment.
RO Value: 3.6 SRO Value: 4.6 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 91 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 92 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 18 ID: 1268668 Points: 1.00 The plant is operating at rated thermal power.
While reviewing CPS 9030.01C003 NS4 MAIN CONDENSER VACUUM B21-N675A(B, C, D)
CHECKLIST, the following data was recorded:
75A 75B 75C 75D Acceptable Allowable (In Hg Vac) (In Hg Vac) (In Hg Vac) (In Hg Vac) Limit Limit (In Hg Vac) (In Hg Vac)
Trip #1 7.58 8.30 7.56 8.31 8.42 to 8.58 7.6 Reset #1 9.35 9.38 9.33 9.41 9.32 to 9.48 N/A Based on these conditions, which of the following describes the status of Main Steam Line Primary Containment Isolation Instrumentation and required ITS 3.3.6.1 action(s)?
Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 CONDITION REQUIRED ACTION COMPLETION TIME
NOTE------------------- A.1 Place one channel in affected 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Only applicable to Main Steam Function in trip.
Line (MSL) isolation functions.
A. One or more Functions with one channel inoperable.
NOTE------------------- B.1 Place one channel in affected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Only applicable to Main Steam Function in trip.
Line (MSL) isolation functions.
B. One or more Functions with two channels inoperable.
The Isolation Function for Divisions _____(1)_____ are INOPERABLE.
ITS 3.3.6.1 Required Action(s) _____(2)_____ are required to be taken.
A. (1) 1 AND 3 ONLY (2) A.1 ONLY B. (1) 1 AND 3 ONLY (2) A.1 AND B.1 C. (1) 1, 2, 3 AND 4 (2) A.1 ONLY D. (1) 1, 2, 3 AND 4 (2) A.1 AND B.1 CPS OPS ILT EXAM Page: 93 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer: B Answer Explanation B is correct -
Per CPS 9030.01 ATM CHANNEL FUNCTIONAL AND CALIBRATION CHECK, Limitation 6.2 and note before step 8.1.28, if ATM AS FOUND data is within the Acceptable limit, but NOT within the AS LEFT limit, then the ATM is still operable, however an ATM calibration per section 8.2 is required within specified surveillance interval.
Since N675A and N675C are outside the Allowable Limit, these channels are inoperable and actions of ITS 3.3.6.1 must be taken.
Per ITS B3.3.6.1 discussion item #1 Main Steam Line Isolation:
Most Main Steam Line Isolation Functions (RPV Level 1, MSL Low Pressure, MSL High Flow, Condenser Low Vacuum, MS Tunnel High Temperature, MSL Turbine Building High Temperature, and Manual Initiation) receive inputs from four channels. The four channels input to four separate two-out-of-four logic divisions.
The exception to this arrangement is the Main Steam Line Flow-High Function. This Function uses 16 flow channels, four for each steam line. The four flow channels associated with a steam line are combined in a two-out-of-four logic configuration.
Instruments B21N675A, B, C, and D each provide input into the Div 1, 2, 3 and 4 NS4 MSL Isolation Logic.
Per ITS 3.3.6.1 Table 3.3.6.1-1, Function 1.d is Main Steam Line Isolation - Condenser Vacuum -
Low. In Modes 1, 2, and 3, four (4) channels are required per function. With 2 of the 4 channels (B21-N675A and C inoperable), ITS 3.3.6.1 Condition A and B must be entered and required actions A.1 and B.1 taken.
A is incorrect but plausible if the examinee incorrectly believes that each MSL is a function (instead of Condenser Vacuum - Low) and therefore only A.1 actions are required to be taken.
C is incorrect but plausible if the examinee incorrectly believes that B21N675A, B, C, and D are INOPERABLE with their trips outside the acceptable limit, while also incorrectly believing that each MSL is a function (instead of Condenser Vacuum - Low) and therefore only A.1 actions are required to be taken.
D is incorrect but plausible if the examinee incorrectly believes that B21N675A, B, C, and D are INOPERABLE with their trips outside the acceptable limit.
KA justification - this question meets the KA because the examinee has to determine how a loss of two the Main Condenser Vacuum Instruments affect the MSL isolation logic (in effect predicting how an actual low vacuum condition would affect the Group 1 Isolation Logic) to answer the question.
Cog Level Justification - this is a high cog question written at the analysis and comprehension level. The examinee has to analyze the conditions in the stem, and then determine how ITS requirements are impacted by the conclusions of the analysis.
CPS OPS ILT EXAM Page: 94 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam SRO justification - this question is linked to SRO Only task 140109.23 (Apply the administrative requirements fro execution of Technical Specifications and Off-Site Dose Calculation Manual Requirements). Also linked to 10CFR55.43(b)(2) Facility operating limitations in the Technical Specifications and their bases.
CPS OPS ILT EXAM Page: 95 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 3.00 System ID: 1268668 User-Defined ID: CL-ILT-1268668 Cross Reference Number:
The plant is operating at rated thermal power.
Topic:
While reviewing CPS 9030.01C003 NS4 MAIN CONDEN Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 96 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with ITS 3.3.6.1 (3.3-48)
Revision Number: Amendment No. 95 ITS 3.3.6.1 (3.3-55)
Amendment No. 169 ITS B3.3.6.1 Rev. 7-6 CPS 9030.01 Rev. 33a CPS 9030.01C003 Rev. 26b Justification for Non SRO CFR Linked to 10CFR55.43(b)(2)
Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure ITS 3.3.6.1 (3.3-48)
ON-## not provided) ITS 3.3.6.1 (3.3-55)
ITS B3.3.6.1 CPS 9030.01 Rev. 33a CPS 9030.01C003 Rev. 26b LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 239001 Main and Reheat Steam System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM ;
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.08 Low condenser vacuum RO Value: 3.6 SRO Value: 3.6 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA (see justification above)
CPS OPS ILT EXAM Page: 97 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 98 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 99 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 19 ID: 1268555 Points: 1.00 A fuel shuffle is in progress. The fuel movement sheet indicates that a fuel assembly will be inserted into core location 15-38.
Before lowering the fuel bundle into its new core location, which direction should the channel fastener be pointing?
X-AXIS Y-AXIS A. SW B. NW C. NE D. SE Answer: D CPS OPS ILT EXAM Page: 100 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation D is correct - per N-CL-OPS-290004, proper orientation of fuel assemblies is assured by verification procedures during core loading. Five separate visual indications of proper fuel assembly orientation exist:
- The channel fastener assemblies are to the center of the control rod blade.
- The handle orientation boss points toward the control blade (toward the center of the cell).
- The channel spacer buttons are toward the control rod blade.
- The alphanumeric serial numbers on the handles can be read from the center of the cell.
- There is cell-to-cell symmetry.
Since the fuel assembly is in the bottom right of the fuel cell (NW), the channel fastener should point toward the center of the cell (SE).
A is incorrect but plausible if the examinee fails to recall the location of the channel fastener on the fuel bundle or makes an error determining the correct core location, etc.
B is incorrect but plausible if the examinee fails to recall the location of the channel fastener on the fuel bundle or makes an error determining the correct core location, etc.
B is incorrect but plausible if the examinee fails to recall the location of the channel fastener on the fuel bundle or makes an error determining the correct core location, etc.
KA justification - this question meets the KA because the examinee has to determine how correct fuel bundle orientation is performed during the administration of core alterations.
Cog level justification - this question is a high cog question because the examinee has to solve a problem (correct fuel bundle orientation) using knowledge (fuel bundle construction, relationship of the fuel bundle to the fuel cell, etc.).
SRO justification - this question is an SRO-only question because the refueling SRO is responsible for ensuring correct orientation of the fuel bundle before releasing the grapple (CPS 3703.01 step 4.22). Also linked to 10CFR55.43(b)(7) Fuel handling facilities and procedures.
CPS OPS ILT EXAM Page: 101 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268555 User-Defined ID: CL-ILT-1268555 Cross Reference Number:
A fuel shuffle is in progress. The fuel movement sheet indicates Topic:
that a fuel assembly will be ins Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 102 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with
- CPS 3703.01 Rev. 27e Revision Number:
- N-CL-OPS-290004 Rev. 3 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14094)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Updated the General Data History: (i.e. Modified distractor table.
b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure
- CPS 3703.01 ON-## not provided)
- N-CL-OPS-290004 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 2.1 Conduct of Operations Category / KA Statement: 2.1.40 Knowledge of refueling administrative requirements.
RO Value: 2.8 SRO Value: 3.9 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 103 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 104 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 20 ID: 1268609 Points: 1.00 The plant was scrammed 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ago due to a LOCA which resulted in the following conditions:
- RPV level is unknown
- RPV has been flooded to the MSLs for last 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />
- DW temperature is 131°F and stable
- Containment temperature is 95°F and stable
- RPV injection has just been terminated Level indications of ____(1)_____ in _____(2)_____ minutes will allow return to EOP-1.
A. (1) 180" Upset (steady) and 105" Shutdown (steady)
(2) 8 B. (1)110" Upset (lowering) and 100" Shutdown (lowering)
(2) 8 C. (1)110" Upset (steady) and 95" Shutdown (steady)
(2) 10 D. (1)110" Upset (lowering) and 95" Shutdown (lowering)
(2) 10 CPS OPS ILT EXAM Page: 105 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer: B Answer Explanation B is correct. Per CPS 4411.07 RPV Level Instrumentation and CPS EOP-2 RPV Flooding override, when RPV water level indication is available per 4411.07, leave EOP-2 RPV flooding and return to EOP-1.
Per CPS 4411.07 Section 2.5 Recovering RPV Water Level Instrumentation from Saturation Failures (Instrument Line Boiling):
- 1. Wait until all three conditions are satisfied:
- RPV Water Level instrumentation is available, and
- Drywell and Containment temperatures are below 212°F, and
- 2. Find Core Uncovery Limit from graph.
- 3. Terminate all injection into the RPV, and reduce RPV water level until any RPV water level indication is restored (on-scale and trending).
- IF RPV water level indication is restored before the Core Uncovery Limit time expires, THEN return to EOP-1 RPV Control.
- IF RPV water level indication is not restored within the Core Uncovery Limit time, THEN return to EOP-2 RPV Flooding.
Per 4411.07 Attachment A: RPV Level Instrumentation Use and Applicability, the Upset Range level instrument has a +0" to +180" range, and the Shutdown Range instrument has a +8" to
+400" range.
Since both the Upset and Shutdown instruments are on-scale and trending (down) and time is <
the Core Uncovery Time Limit (CUTL), exit to EOP-1 is permitted. At 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> since reactor shutdown CUTL ~9 minutes.
Incorrect Responses:
A is incorrect but plausible if the examinee fails to recall that RPV water level indication must be on-scale and trending to be considered restored and determines that these indications are correct since the RPV is filled to the Main Steam Lines, but correctly determines the CUTL as read on the graph.
C is incorrect but plausible if the examinee fails to recall that RPV water level indication must be on-scale and trending to be considered restored and determines that these indications are correct since the RPV is filled to the Main Steam Lines, and additionally the examinee incorrectly reads the logarithmic scale on the CUTL graph.
D is incorrect but plausible if the examinee correctly identifies the RPV water level indication as restored (on-scale and trending) but incorrectly reads the logarithmic scale on the CUTL graph.
KA Justification - this question meets the KA because the examinee must interpret/execute procedure steps in order to determine recovery of RPV water level instrumentation which in turn the examinee will utilize to select the correct response.
CPS OPS ILT EXAM Page: 106 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Cog Level Justification - this is a high cog question because the examinee has to analyze conditions provided in the stem, use knowledge and a reference to determine recovery of RPV water level instrumentation and subsequently when return to EOP-1 is allowed.
SRO Justification - this question is linked to SRO only task 100509.19D (Demonstrate knowledge of EOP implementation hierarchy and coordination with other support procedures). Also linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
CPS OPS ILT EXAM Page: 107 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 20 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268609 User-Defined ID: CL-ILT-1268609 Cross Reference Number:
The plant was scrammed 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ago due to a LOCA which resulted in the following conditions:
Topic:
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 108 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4411.07 rev. 6b Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14081)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Revised General Data table, History: (i.e. Modified distractor answer explanation and b to make plausible based on justification statements, wdk OTPS review) 4/13/2016 ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4411.07 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK / SPR)
KA Data KA Number / System Name: 2.1 Conduct of Operations Category / KA Statement: 2.1.20 Ability to interpret and execute procedure steps.
RO Value: 4.6 SRO Value: 4.6 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 109 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 21 ID: 1268272 Points: 1.00 Plant conditions occurred as follows:
- The Reactor is operating at 92% power.
- The "A" APRM has failed downscale due to internal circuitry problems.
- The Control Room operators have placed the channel in TRIP.
What effect will this condition have on the continued ability to operate the plant in Mode 1?
A. Unless the failed APRMs is returned to normal service prior to the next scheduled Channel Functional Test of one of the remaining APRMs, the plant will have to be shutdown.
B. Continued operation in this condition is NOT permitted. Due to operation outside the accident analysis, LCO 3.0.3 must be entered and the plant must be placed in HOT SHUTDOWN within the next 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
C. Continued operation is permitted indefinitely. In this condition, Tech Specs allows removing the trip inserted on APRM 'A' in order to perform testing required to demonstrate the operability of the remaining APRMs.
D. While in this condition, the remaining operable APRMs must be channel checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND channel functional tests must be performed every 7 days, with the exception that their trip units need NOT be tripped as long as there are no abnormal responses observed in the performance of either test.
Answer: C Answer Explanation C is correct - per ITS 3.0.5, Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
A & B are incorrect but plausible if the examinee fails to recall that ITS 3.0.5 allows equipment removed from service or declared inoperable to comply with ACTIONS to be returned to service to support testing of other equipment. Long term operation with an inoperable and tripped APRM is defined in ITS, so ITS 3.0.3 actions are not required.
D is incorrect but plausible if the examinee determines that the compensatory actions listed in the distracter are contained in the ITS bases document. These actions are not required by ITS.
The channel functional tests of the remaining operable APRMs are still required.
KA justification - this question meets the KA because the examinee has to have knowledge of ITS 3.0.5 to answer the question.
Cog Level justification - this is a memory level question - recall of a definition in ITS.
SRO justification - this question is linked to SRO only task 140109.23 (Apply the administrative requirements for Execution of Technical Specifications or Off-Site Dose Calculation Manual Requirements). Also linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.
CPS OPS ILT EXAM Page: 110 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268272 User-Defined ID: CL-ILT-1268272 Cross Reference Number:
Plant conditions occurred as follows: The Reactor is operating Topic:
at 92% power. The "A" APRM has fai Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 111 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with ITS 3.0.5 Amend. 163 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam 05, OYS CERT-04) history Question Source: (i.e. New, Bank (CL-ILT-A14095)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Revised general data table, History: (i.e. Modified distractor wdk 4/12/2016 b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. ITS 3.0 ABN-##)
Excluded
Reference:
(i.e. Ensure None ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1B)
KA Data KA Number / System Name: 2.2 Equipment Control Category / KA Statement: 2.2.22 Knowledge of limiting conditions for operations and safety limits.
RO Value: 4.0 SRO Value: 4.7 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: 43.2 CPS OPS ILT EXAM Page: 112 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 22 ID: 1268277 Points: 1.00 Which ONE of the following is subject to control under CC-AA-112 Temporary Configuration Changes?
A. A catch basin is installed under an FC valve with a packing leak.
B. A hose is installed to drain a heat exchanger under a clearance order.
C. An electrical lead is lifted in accordance with a surveillance procedure.
D. A supplemental mixing fan is place in the Turbine Building Heater Bay.
Answer: D Answer Explanation D is correct. Per CC-AA-112 Temporary Configuration Changes section 4.2.12, Temp Heat/Cooling for supplemental equipment heating or cooling requirements is typically NOT considered a Controlled Exclusion from this procedure (i.e. controlled in an alternate approved manner per Section 4.2 of CC-AA-112) and IS therefore controlled under CC-AA-112 Temporary Configuration Changes.
Incorrect Responses; A is incorrect but plausible. The candidate may select this response if he/she fails to recognize that this response is considered a controlled exclusion per CC-AA-112. Catch Basins controlled under procedure RP-AA-502 are Controlled Exclusions from this procedure.
B is incorrect but plausible. The candidate may select this response if he/she fails to recognize that this response is considered a controlled exclusion per CC-AA-112. Operations clearances (tagouts) established for the protection of personnel and equipment, including isolation of equipment using system or component design features such as removing fuses, spectacle flanges, and permanently installed bypass/defeat mechanisms in accordance with the applicable clearance and tagging procedure are Controlled Exclusions from this procedure.
C is incorrect but plausible. The candidate may select this response if he/she fails to recognize that this response is considered a controlled exclusion per CC-AA-112. Surveillance and Inservice tests are repetitive in nature and typically controlled through specific station procedures that call for Temporary Configuration Change (e.g.,installation of a jumper to conduct a trip and cal test). Surveillance and Inservice tests procedures are Controlled Exclusions from this procedure.
KA Justification - this question meets the KA because the examinee has to demonstrate knowledge of the process for controlling temporary design changes by determining which activity is controlled under CC-AA-112 Temporary Configuration Changes.
Cog Level Justification - this is a low cog question written at the memory level. The examinee must recall facts and apply them to the specific situation.
SRO Justification - this question is linked to SRO only task 999999.10 (Authorize installatoin of a Temporary Modification). Also linked to 10CFR55.43(b)(3) Facility licensee procedures required to obtain authority for design and operating changes in the facility.
CPS OPS ILT EXAM Page: 113 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 22 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268277 User-Defined ID: CL-ILT-1268277 Cross Reference Number:
Which ONE of the following is subject to control under CC-AA-Topic:
112 Temporary Configuration Changes?
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 114 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CC-AA-112 Rev. 23 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CC-AA-112 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 2.2 Equipment Control Category / KA Statement: 2.2.11 Knowledge of the process for controlling temporary design changes.
RO Value: 2.3 SRO Value: 3.3 Tier: 3 RO Group: NA SRO Group: N/A 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.3 CPS OPS ILT EXAM Page: 115 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 116 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 23 ID: 1268557 Points: 1.00 Current plant conditions require venting the Primary Containment in accordance with CPS 4411.06 Emergency Containment Venting, Purging, and Vacuum Relief.
The Station Emergency Director (SED) has authorized exceeding release rate limits.
(1) Given the two containment vent/purge paths below, which is PREFERRED?
If containment pressure continues to rise following the successful initiation of the PREFERRED method, additional vent/purge pathways may be initiated as long as ____(2)____.
A. (1) Hydrogen Purge Supply Path (2) core cooling is not adversely affected B. (1) Hydrogen Purge Supply Path (2) venting interlocks are not defeated C. (1) CCP Supply Path Modification (2) core cooling is not adversely affected D. (1) CCP Supply Path Modification (2) venting interlocks are not defeated Answer: A CPS OPS ILT EXAM Page: 117 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation A is correct. Per 4411.06 Table A Vent and Purge Paths, the "Vent Using CCP Supply Path Modification" is used only as a last resort because the release path is not monitored or filtered.
Per 4411.06 section 2.1, IF CNMT pressure OR Hydrogen continues to increase, THEN Initiate vent/purge using additional paths.
- Do not use vent paths needed for core cooling
- Do not exceed release rates.
- Do not defeat isolation interlocks Per EOP-6 Primary Containment Control:
- Do not use vent paths needed for core cooling
- OK to defeat venting interlocks Incorrect Responses:
B is incorrect but plausible. The candidate may select this response if he/she correctly identifies the PREFERRED vent/purge path but incorrectly believes that containment ventilation interlocks must remain intact to allow containment venting or confuses the statements concerning isolation interlocks and venting interlocks discussed above.
C is incorrect but plausible. The candidate may select this response if he/she incorrectly recalls the advantages/disadvantages for the selected vent/purge paths and fails to recognize that using the CCP Supply Path Modification should be the LAST POSSIBLE PATH, but correctly recognizes that core cooling must be preserved.
D is incorrect but plausible. The candidate may select this response if he/she incorrectly recalls the advantages/disadvantages for the selected vent/purge paths and fails to recognize that using the CCP Supply Path Modification should be the LAST POSSIBLE PATH, while also incorrectly believing that containment ventilation interlocks must remain intact to allow containment venting or confuses the statements concerning isolation interlocks and venting interlocks discussed above.
KA justification - this question meets the KA because the examinee is required to recall containment venting strategies that are employed to control radiation releases.
Cog Level Justification - this is a low cog question written at the memory level. The examinee must recall facts and apply them to the specific situation.
SRO only justification - linked to SRO Only task 440201.15 (Determine when to exceed release limits when executing EOPs) and 10CFR55.43(b)(4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.
CPS OPS ILT EXAM Page: 118 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 1268557 User-Defined ID: CL-ILT-N12097 Cross Reference Number:
Current plant conditions require venting the Primary Topic:
Containment in accordance with CPS 4411.06 ...
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 119 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with CPS 4411.06 Rev. 6 Revision Number: CPS 4402.01 Rev. 30 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC Exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. None ABN-##)
Excluded
Reference:
(i.e. Ensure CPS 4411.06 ON-## not provided) CPS 4402.01 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: NA Category / KA Statement: 2.3.11 Ability to control radiation releases.
RO Value: 3.8 SRO Value: 4.3 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.11 10CFR55-43 (SRO) Data: 43.4 CPS OPS ILT EXAM Page: 120 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 121 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 24 ID: 1268268 Points: 1.00 The plant was operated at rated thermal power until adverse weather conditions resulted in a plant transient and activation of the Emergency Plan.
The Clinton Station Emergency Response Organization is unable to report to the on-site facility.
Command and control has been transferred to the Corporate Emergency Director.
The Shift Emergency Director (Shift Manager) is still responsible to perform which of the following duties?
- 1. Notifying Offsite authorities
- 2. Identifying applicable Emergency Action Levels and emergency classifications
- 3. Determining and issuing Protective Action Recommendations
- 4. Authorization of Emergency Exposures A. 4 ONLY B. 2 AND 3 ONLY C. 2 AND 4 ONLY D. 1, 2 AND 3 ONLY Answer: C CPS OPS ILT EXAM Page: 122 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation CPS OPS ILT EXAM Page: 123 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam C is correct. Per EP-AA-112 Emergency Response Organization (ERO) / Emergency Response Facility (ERF) Activation and Operation, the non-delegable responsibilities will normally move with the transfer of Command and Control as indicated below for MA/MW stations:
Control Room TSC EOF (Shift Emergency Director) (Station Emergency Director) (Corporate Emergency Director)
Classification Classification PARs PARs PARs Notifications Notifications Notifications Emergency Exposure Controls Emergency Exposure Controls If the Technical Support Center (TSC) is not functional and the Emergency Operations Facility (EOF) is adequately staffed and briefed, then Command and Control of overall emergency response and the nondelegable responsibility for Protective Action Recommendation (PAR) determination and the notification of offsite authorities can be transferred directly from the Shift Emergency Director to the Corporate Emergency Director. The Control Room will retain responsibility for event classification and emergency exposure controls until the Station Emergency Director is ready to accept.
Incorrect Responses:
A is incorrect but plausible. The candidate may select this response if he/she recognizes Emergency Exposure Controls as a responsibility that the Shift Emergency Director MUST retain but fails to recognize Classifications as an additional responsibility that the Shift Emergency Director MUST also retain.
B is incorrect but plausible. The candidate may select this response if he/she recognizes Classifications as a responsibility that the Shift Emergency Director MUST retain but incorrectly believes that since determining and issuing PARs normally follows the Classification declaration, the Shift Emergency Director retains this responsibility as well.
D is incorrect but plausible. The candidate may select this response if he/she recognizes Classifications as a responsibility that the Shift Emergency Director MUST be retained but, incorrectly believes:
- that since determining and issuing PARs normally follows the Classification declaration AND
- the notification of off-site authorities is usually made via the Nuclear Accident Reporting System (NARS) following the determination of Classification and PARs (as applicable),
the Shift Emergency Director retains both these responsibilities as well.
KA Justification - this question meets the KA because the examinee has to demonstrate knowledge of SRO Responsibilities in Emergency Plan implementation by determining duties retained by the Control Room when transferring Command and Control of an event directly to the EOF.
Cog Level Justification - this is a low cog question written at the memory level. The examinee must recall facts and apply them to the specific situation.
CPS OPS ILT EXAM Page: 124 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam SRO Justification - this question is linked to SRO Only task 997777.03 (Emergency Plan Activities performed by an SRO). Also linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
CPS OPS ILT EXAM Page: 125 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 24 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 0 Difficulty: 0.00 System ID: 1268268 User-Defined ID: CL-ILT-1268268 Cross Reference Number:
The plant was operated at rated thermal power until adverse Topic:
weather conditions resulted in a plant Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 126 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with EP-AA-112 Rev. 18 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision New question.
History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): (i.e. EP-AA-112-F-01 ABN-##)
Excluded
Reference:
(i.e. Ensure EP-AA-112 Rev. 18 ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 2.4 Emergency Procedures / Plan Category / KA Statement: 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.
RO Value: 2.7 SRO Value: 4.5 Tier: 3 RO Group: NA SRO Group: N/A 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 127 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam CPS OPS ILT EXAM Page: 128 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam 25 ID: 1268288 Points: 1.00 The plant was in Mode 1 at RTP when a severe plant transient occurred resulting in the following:
- An UNISOLABLE primary system is leaking into the Turbine Building.
- Drywell and Containment radiation levels are trending up per the data table below.
Time DW Radiation Monitor Reading (R/hr) Cnmt Radiation Monitor Reading (R/hr) 08:00:00 101 34 08:02:00 101 42 08:05:00 261 98 08:15:00 591 98 Under these conditions, the earliest time that an Emergency Action Level (EAL) threshold is met requiring a Protective Action Recommendation (PAR) to be made by the station is __________.
A. 08:00:00 B. 08:02:00 C. 08:05:00 D. 08:15:00 Answer: B CPS OPS ILT EXAM Page: 129 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Answer Explanation B is correct - PARS are made at the GE level. FG1 is defined as the Loss of ANY two barriers AND loss or potential loss of third barrier. The values at 08:02:00 represent a loss of fuel clad, reactor coolant system, and the primary containment (three barriers) - meets the FG1 criteria requiring PARS to be issued.
A is incorrect but plausible - the values at 08:00:00 represent a loss of the reactor coolant system and the containment (two barriers) - does not meet the FG1 criteria. Does meet the criteria for FS1 (loss or potential loss of any two barriers). The examinee may select this choice if he/she incorrectly determines the classification that requires PARS to be issued or misreads the barrier matrix.
C is incorrect but plausible - The values at 08:05:00 represent a loss of all three barriers - meets the FG1 criteria but occurs later than 08:02:00 which is the first time that FG1 is exceeded.
D is incorrect but plausible - The values at 08:15:00 represent a loss of all three barriers - meets the FG1 criteria but occurs later than 08:02:00 which is the first time that FG1 is exceeded.
KA Justification - this question meets the KA because the examinee has to demonstrate knowledge of Emergency Plan Protective Action Recommendations by determining when PARS must be issued based on the parameters provided in the question stem.
Cog Level Justification - this is a high cog question because the examinee has to analyze the conditions provided in the stem and then determine when actions are required based on that analysis.
SRO Justification - this question is linked to SRO only task 997777.02 (Given a postulated E-Plan condition, determine and recommend Offsite Protective actions (PARs), IAW corporate EP, and station specific EP procedures). Also linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
CPS OPS ILT EXAM Page: 130 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 1268288 User-Defined ID: CL-ILT-1268288 Cross Reference Number:
The plant was in Mode 1 at RTP when a severe plant transient Topic: occurred resulting in the following:
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 131 of 132 10 January 2017
EXAMINATION ANSWER KEY ILT 15-1 NRC SRO Written Exam Comments: General Data Technical Reference with EP-AA-1003 Rev. 25 Revision Number: EP-AA-111 Rev. 19 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS NRC- No previous NRC exam usage 05, OYS CERT-04)
Question Source: (i.e. New, Bank (CL-ILT-A14077)
Bank, Modified)
Low KA Justification (if required): NA Revision History: Revision Revised General Data table History: (i.e. Modified distractor and justifications, wdk b to make plausible based on 4/11/2016.
OTPS review)
ILT Supplied Ref (If appropriate): (i.e. EP-AA-1003 Barrier Matrix ABN-##) Page CL 2-3 Excluded
Reference:
(i.e. Ensure EP-AA-1003 Rev. 25 (other ON-## not provided) than Barrier Matrix Page CL 2-3)
EP-AA-111 Rev. 19 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, A- NA Systems or B-Procedures)
General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK/SPR)
KA Data KA Number / System Name: 2.4 Emergency Procedures / Plan Category / KA Statement: 2.4.44 Knowledge of emergency plan protective action recommendations.
RO Value: 2.4 SRO Value: 4.4 Tier: 3 RO Group: NA SRO Group: N/A 10CFR55-41 (RO) Data: 41.10 & 41.12 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 132 of 132 10 January 2017