ML13276A133
| ML13276A133 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/27/2013 |
| From: | David Reeser Operations Branch III |
| To: | Jennings T Exelon Generation Co |
| David Reeser | |
| Shared Package | |
| ML11354A434 | List: |
| References | |
| Download: ML13276A133 (351) | |
Text
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 1 ID: 896292 Points: 1.00 The plant has been scrammed due to rising Drywell temperature.
RPV level indicates:
- +10" on narrow range level indicators
- 0" 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: B Answer Explanation B is correct:
Per CPS 4411.07 Attachment A: RPV Level Instrumentation response to Off-Calibration / Changing Plant Conditions, increasing DW temperature will cause indicated level to rise, therefore NR 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 Level indicators when it is on scale above its minimum usable level. Per Attachment A of 4411.07, the operating range for the narrow range level instruments is +5" to +60".
A is incorrect but plausible if the examinee fails to correctly analyze the affect of rising DW temperature on the narrow range level instruments.
C is incorrect but plausible if the examinee fails to correctly analyze the affect of rising DW temperature on the wide range level instruments and also believes that the lowest reading level instruments should be used to report RPV level.
D is incorrect but plausible if the examinee believes that the lowest reading level instruments should be used to report RPV level.
KA justification - this question meets the KA because the examinee is required to determine the affects 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).
CPS OPS ILT EXAM Page: 1 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896292 User-Defined ID: CL-ILT-887843 Cross Reference Number:
The plant has been scrammed due to rising Drywell Topic:
temperature. RPV level indicates: +10" on narr Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 2 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 4411.07 Rev. 6 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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 (CFR: 41.8 to 41.10)
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 CPS OPS ILT EXAM Page: 3 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 1 216000.16 EVALUATE the following Nuclear Boiler indications/responses and DETERMINE if the indication/
response is expected and normal.
.1 Rapid Reactor Vessel depressurization
.2 Reactor Vessel heatup
.3 Reactor Vessel cooldown
.4 Increasing Containment temperature
.5 Increasing Drywell temperature
.6 Reactor Recirc Jet Pump flow
.7 Rapid Changes in Void Fraction
.8 Steam flow changes
.9 Shutting 1B21-F454A/B, RPV Pressure / Level Transmitter Reference Line Isolation Valve.
.10 Valving in or out a level transmitter CPS OPS ILT EXAM Page: 4 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 2 ID: 896293 Points: 1.00 The plant is at rated power.
A Fire is reported in 778' Containment.
The Fire Brigade has been dispatched but has NOT arrived at the scene of the fire.
Given these conditions, the MCR operating crew is required to...
A. place the Control Room Ventilation System (VC) in Smoke Mode.
B. energize and open the Containment/Drywell Fire Protection isolation valves.
C. shift from Continuous Containment Purge (CCP) Unfiltered to Containment Purge Mode.
D. close the Containment Floor Drain Sump Disch Containment Inboard and/or Outboard Valves 1RF021/22 before using foam.
Answer: B Answer Explanation B is correct - per CPS 1893.04 Fire Fighting, section 8.1 MCR Actions, step 8.1.7:
For a fire in CONTAINMENT and/or DRYWELL, close the following breakers:
Then Open the following Fire Protection CNMT/Drywell Isol. Valves from the MCR.(Refer to Tech Spec 3.6.1.3)
- 1. 1FP051
- 2. 1FP054
- 3. 1FP078
- 4. 1FP079 This is required because the above listed valves are normally deenergized and closed.
A is incorrect but plausible - there is no requirement to place VC in smoke mode for a fire in the containment. Combustion products in the containment will be exhausted to the plant ventilation stack and outside.
C is incorrect but plausible:
CPS OPS ILT EXAM Page: 5 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version
- The VR/VQ system has several different operating modes that are used for either ventilation or purging of the containment atmosphere. The ventilation modes (CCP unfiltered and Containment Vent) exhaust air directly from the containment atmosphere to the common station ventilation stack.
The purge modes (CCP filtered and Containment Purge) exhaust air from the containment to the common station ventilation stack via charcoal filters and are only used when a radioactive release is in progress inside the containment to filter radionuclides from the exhaust air before discharge to the environment.
- The pre-fire plan for the containment (CPS 1893.04M210) allows use of the Containment Ventilation or the Continuous Containment Purge (CCP) systems for smoke removal. CPS 3408.01 limitation 6.3 states that Containment Purge Mode may only be used in Modes 4 and 5, and Limitation 6.7 states that the CCP Unfiltered Mode or Containment Vent Mode should be used to eliminate smoke to prevent damage to the VR/VQ charcoal beds.
D is incorrect but plausible - CPS 1893.04 precaution 4.7 states that firefighting foam should not be used in the containment building to prevent contamination of the suppression pool with AFFF. Closing 1RF021/22 has face validity because they are required to be closed before resetting a scram with fuel failure to prevent discharging highly radioactive water to radwaste.
KA justification - this question meets the KA because the examinee must know that the FP Containment Isolation Valves (1FP051, 54, 78, and 79) have to be energized and then opened from the MCR (the operational implication) in order to fight fires in the containment.
CPS OPS ILT EXAM Page: 6 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896293 User-Defined ID: CL-ILT-887857A Cross Reference Number:
The plant is at rated power. A Fire is reported in 778' Topic:
Containment. The Fire Brigade has been Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 7 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 1893.04 Rev. 15 Revision Number:
- 1893.04M210 Rev. 6
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - Duplicate of CL-ILT-Bank, Modified) 7019 Low KA Justification (if NA required):
Revision History: Revision Revised question History: (i.e. Modified distractors. Provided distractor b to make plausibility and KA plausible based on OTPS justification statements.
review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. 1893.04 Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 600000 Plant Fire On Site Category / KA Statement: AK1 Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: AK1.02 Fire Fighting RO Value: 2.9 SRO Value: 3.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 8 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 2 LP85804.2.4.25 Knowledge of fire protection procedures.
CPS OPS ILT EXAM Page: 9 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 3 ID: 896294 Points: 1.00 A transient has occurred resulting in lowering Suppression Pool water level.
If the trend in lowering Suppression Pool level can NOT be reversed, which of the following describes why a blowdown is required when suppression pool level reaches 15'1"?
A blowdown is required...
A. because the ability to monitor suppression pool temperature will be lost.
B. to prevent direct pressurization of the containment from the SRV spargers.
C. to prevent direct pressurization of the containment from the Hydrogen Mixing Compressor discharge piping.
D. because steam discharged through the horizontal vents during a LOCA may not be completely condensed and containment design pressure could be exceeded.
Answer: D Answer Explanation D is correct - per the EOP Tech Bases, the lowest curve on the Heat Capacity Limit corresponds to a suppression pool water 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. Since the RPV may not be kept at pressure under these conditions, a blowdown must be performed, irrespective of suppression pool temperature.
A is incorrect but plausible - Lowering suppression pool water level does affect the availability of some of the suppression pool temperature indicators. EOP-6 states that if suppression pool level drops below 18'6", use the suppression pool temperature indicators on 1H13-P678 or on SPDS.
B is incorrect but plausible if the examinee believes that a blowdown is required with pool level at 15'1" to prevent direct pressurization of the containment from the SRV spargers. The spargers are located below 8 feet. ADS can be initiated with suppression pool level above this value.
C is incorrect but plausible - per the EOP Tech Bases, Mixer (HG) operation is permitted in the Drywell/Containment Pressure and Drywell/Containment Hydrogen branches (Parts L and Q) only if suppression pool water level is above 13 ft. 1 in. If suppression pool water level were below 13 ft. 1 in.
(13.1 ft.), the mixer discharge would be uncovered and mixer operation would open a path from the drywell directly into the containment. A break in the drywell could then overpressurize the containment.
KA justification - this question meets the KA because the examinee must be knowledgeable of the operational implications of a LOCA during low suppression pool levelconditions in order to answer the question.
CPS OPS ILT EXAM Page: 10 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 3 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: 896294 User-Defined ID: CL-ILT-887888 Cross Reference Number:
A transient has occurred resulting in lowering Suppression Pool Topic:
water level. If the trend in lowe Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 11 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments:
General Data Technical Reference with EOP Tech Bases Rev. 6 Revision Number: (pages 8-19 and 8-20)
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS 2008 LaSalle NRC Exam NRC-05, OYS CERT-04) Q16 and 2008 Cooper NRC Exam Q16 Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised for applicability at History: (i.e. Modified CPS distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
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:
EK1.01 Steam condensation (CFR: 41.8 to 41.10)
RO Value: 3.8 SRO Value: 4.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.8 - 41.10 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 12 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 3 LP87558.01.02 Given a diagram of EOP-6:
.01 State the conditions to exit/transfer from EOP-6
.02 State the bases for each individual step/action of EOP-6
.03 State the systems that are available for Containment Purge
.04 State the systems and flow paths that can be used to cool and control pressure in the containment.
CPS OPS ILT EXAM Page: 13 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 4 ID: 896295 Points: 1.00 A reactor coolant leak in the containment has driven containment temperature to 105°F and rising.
Drywell temperature is 100°F and stable.
Which ONE of the following RPV water level instrument ranges is affected MOST by these conditions?
A. Upset Range B. Wide Range C. Narrow Range D. Shutdown Range Answer: B Answer Explanation B is correct - per the EOP Tech Bases:
Minimum Usable Levels have been calculated for each RPV water level instrument for drywell temperatures between 100°F and 558.4°F (saturation temperature for 1103 psig, the lowest SRV lift setpoint) and containment temperatures between 70°F and 350°F. Figure C of Detail A lists the levels in terms of whichever temperature has the greater effect upon indicated level; the temperature having the smaller effect is assumed to be at its most limiting value. Upset Range level, for example, increases as both drywell and containment temperatures rise, but is most sensitive to drywell temperature changes.
The Upset Range Minimum Usable Levels are therefore expressed in terms of drywell temperature assuming a containment temperature of 350°F. (The highest containment temperature is most limiting for this instrument since higher containment temperatures produce higher indicated levels.) For drywell temperatures between 100°F and 200°F, the Upset Range instrument cannot be used below an indicated level of 4 in.
Wide Range indicated levels increase as containment temperature rises, decrease as drywell temperature rises, and are most sensitive to containment temperature. The Wide Range levels are therefore expressed in terms of containment temperature assuming a drywell temperature of 100°F. (The lowest drywell temperature is most limiting for the Wide Range instrument since lower drywell temperatures produce higher indicated levels.) For containment temperatures between 100°F and 200°F, the Wide Range instruments cannot be used below an indicated level of -150 in.
A is incorrect but plausible since the upset range is affected by rising containment temperature but is most sensitive to changes in drywell temperature.
C is incorrect but plausible since the narrow range is affected by rising containment temperature but is most sensitive to changes in drywell temperature.
D is incorrect but plausible since the shutdown range is affected by rising containment temperature but is most sensitive to changes in drywell temperature.
KA justification - This question meets the KA because the examinee must have knowledge of the affect of rising containment temperature on the RPV water level instruments in order to answer this question.
CPS OPS ILT EXAM Page: 14 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896295 User-Defined ID: CL-ILT-812577 Cross Reference Number:
Which ONE of the following RPV water level instrument ranges Topic:
is MOST sensitive to rising containme Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 15 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- EOP Tech Bases Rev.
Revision Number: 6
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. Detail A of EOP-1, 1A, 3, 6, Ensure ON-## not provided) and SAG-1 LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 295027 High Containment Temperature (Mark III Containment Only)
Category / KA Statement: EK2. Knowledge of the interrelations between HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the following: (CFR: 41.7 / 45.8) EK2.02 Components internal to the containment: Mark-III RO Value: 3.2 SRO Value: 3.3 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 16 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 4 216000.16 EVALUATE the following Nuclear Boiler indications/responses and DETERMINE if the indication/
response is expected and normal.
.1 Rapid Reactor Vessel depressurization
.2 Reactor Vessel heatup
.3 Reactor Vessel cooldown
.4 Increasing Containment temperature
.5 Increasing Drywell temperature
.6 Reactor Recirc Jet Pump flow
.7 Rapid Changes in Void Fraction
.8 Steam flow changes
.9 Shutting 1B21-F454A/B, RPV Pressure / Level Transmitter Reference Line Isolation Valve.
.10 Valving in or out a level transmitter CPS OPS ILT EXAM Page: 17 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 5 ID: 896296 Points: 1.00 The plant was at 93% power with 4.16 KV Buses 1A AND 1B supplied from Unit Auxiliary Transformers 1A and 1B.
Then, annunciator 5008-5L 4KV Bus Low Voltage Alarm on 1H13-P680 was received.
Per CPS 5008.05 (5L) 4KV Bus Low Voltage, 4.16KV Bus 1A1, 1B1, and 1C1 voltage indications were checked and verified to be just below the alarm setpoint and stable.
Assuming all systems operate as designed, annunciator 5012-1D AC Undervoltage 4160V Bus on 1H13-P870 _____(1)_____ expected to be alarming.
4.16 KV Buses 1A and 1B are expected to be _____(2)_____.
A. (1) is (2) deenergized B. (1) is (2) energized from the reserve source C. (1) is NOT (2) energized from the reserve source D. (1) is NOT (2) energized from the main source Answer: D Answer Explanation D is correct -
Annunciator 5008.05 (5L) 4KV Bus Low Voltage is received when any safety related 4KV Bus (1A1, 1B1, or 1C1) voltage degrades to 4136 VAC.
- If safety related bus voltage continues to degrade to 4072 VAC for 15 seconds, the Bus Main and Reserve Feed Breakers will trip open and lockout; the bus will be stripped of its loads; and the associated DG will auto start and tie onto the bus.
- If the safety related bus 1st level undervoltage (loss of voltage) relays trip, the main(reserve) feed breaker will trip and the reserve(main) feed breaker will close in if sufficient voltage exists on the standby bus.
Annunciator 5012-1D AC Undervoltage 4160V bus will alarm when either 4160V Bus 1A or 1B is deenergized.
There are no undervoltage transfers from main to reserve feed source for the non-safety 4160V Buses, so 4160V Bus 1A and 1B are expected to remain energized from their respective UAT (main source).
A is incorrect but plausible if the examinee incorrectly recalls the setpoint for annunciator 5012-1D, and also believes that the non-safety related 4.16 KV Bus responds to bus undervoltage conditions like the safety related busses do.
CPS OPS ILT EXAM Page: 18 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version A is incorrect but plausible if the examinee incorrectly recalls the setpoint for annunciator 5012-1D, and also believes that the non-safety related 4.16 KV Bus responds to bus undervoltage conditions like the safety related busses do.
C is incorrect but plausible if the examinee incorrectly believes that the non-safety related 4.16 KV Bus responds to bus undervoltage conditions like the safety related busses do.
KA justification - this question meets the KA because the examinee is required to know how the non-safety related 4160V Buses respond to degraded voltage conditions on the grid to answer the question.
CPS OPS ILT EXAM Page: 19 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 5 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: 896296 User-Defined ID: CL-ILT-887914A Cross Reference Number:
The plant was at 93% power with 4.16 KV Buses 1A AND 1B Topic:
supplied from Unit Auxiliary Transformers Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 20 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 5008.05 (5L) Rev. 32a Revision Number:
- 5012.01 (1D) Rev. 24 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 700000 Generator Voltage and Electric Grid Disturbances Category / KA Statement: AK2. Knowledge of the interrelations between GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following:
AK2.02 Breakers, relays (CFR: 41.4, 41.5, 41.7, 41.10 /
45.8)
RO Value: 3.1 SRO Value: 3.3 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 CPS OPS ILT EXAM Page: 21 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 5 262001.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following Auxiliary Power System components.
.1 Unit Auxiliary Transformer &
Cooling Systems
.2 Reserve Auxiliary Transformer
& Cooling Systems
.3 Emergency Reserve Auxiliary Transformer
.4 Non-segregated Phase Bus Ducts
.5 High Voltage Breakers
.6 Non-Divisional High Voltage Distribution System
.7 Divisional High Voltage Distribution System
.8 480 V Substations
.9 480 V Motor Control Centers CPS OPS ILT EXAM Page: 22 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 6 ID: 896297 Points: 1.00 The Reactor was operating at 42% power.
Then, the following annunciators were received:
- 5004-1D Div 1 or 4 TSV CL TRIP
- 5005-1D Div 2 or 3 TSV CL TRIP A malfunction in the Reactor Pressure Regulating System resulted in Reactor pressure peaking at 1120 psig.
The expected state of the following RPS / ARI indicators after these conditions were received is described in choice...
A.
B.
CPS OPS ILT EXAM Page: 23 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version C.
CPS OPS ILT EXAM Page: 24 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version D.
CPS OPS ILT EXAM Page: 25 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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 5004-1D and 5005-1D, an automatic reactor scram will occur if two instrument channels trip on Turbine Stop Valve Closure with Reactor power > 33.3%.
CPS OPS ILT EXAM Page: 26 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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.
With the conditions presented in the stem, an RPS scram signal was received, but RPV pressure did not reach the ARI initiation setpoint.
A is incorrect but plausible if the examinee incorrectly determines that either a scram signal was not received, or that the lights above the scram switches are normally off and illuminate when a scram signal is received, and that RPV pressure exceeded the ARI initiation setpoint resulting in an automatic ARI initiation.
B is incorrect but plausible if the examinee incorrectly determines that either a scram signal was not received, or that the lights above the scram switches are normally off and illuminate when a scram signal is received.
C is incorrect but plausible if the examinee incorrectly determines that RPV pressure exceeded the ARI initiation setpoint resulting in an automatic ARI initiation.
KA justification - this question meets the KA because the examinee must have knowledge of the interrelations between the TSV closure signals and the RPS system in order to answer this question.
CPS OPS ILT EXAM Page: 27 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896297 User-Defined ID: CL-ILT-812579 Cross Reference Number:
The Reactor was operating at 42% power. Then, the following Topic:
annunciators were received: 5004-1D Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 28 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 5008.01 (1K & 1L) Rev.
Revision Number: 27
- 5004.01 (1D) Rev. 28
- 5005.01 (1D) Rev. 29c Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 295006 SCRAM Category / KA Statement: AK2. Knowledge of the interrelations between SCRAM and the following: (CFR: 41.7 / 45.8) AK2.01 RPS RO Value: 4.3 SRO Value: 4.4 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 29 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 6 212000.03 DESCRIBE the function, operation, interlocks, trips, physical location, and power supplies of the following Reactor Protection System (RPS) and Alternate Rod Insertion (ARI) System components.
.1 Backup Scram Valves
.2 Scram Pilot Valve Valves
.3 RPS 10-Second Delay (Function)
.4 ARI 2-Minute Delay (Function)
.5 Shorting Links
.6 Scram Discharge Volume High Level Scram Bypass (Mode Switch Permissive) Interlock
.7 NS4 Sensor Bypass Switches CPS OPS ILT EXAM Page: 30 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 7 ID: 896298 Points: 1.00 A trip of Continuous Containment Purge (CCP) Exhaust Radiation Monitors 1RIX-PR042A, B, C, AND D will initiate automatic actions to _____.
A. prevent liquid radioactivity releases.
B. prevent contamination of the MCR envelope.
C. ensure any release from the containment is filtered.
D. ensure any potential leakage path from the Containment Monitoring System is isolated.
Answer: C Answer Explanation C is correct:
The CCP Exhaust Rad Monitors provide trip signals to CRVICS Groups 10, 16, and 19. A Group 19 isolation results in automatic closure of the Fuel Building Supply and Exhaust Inboard and Outboard Isolation Dampers (SCIDs) and initiates an automatic initiation of the Standby Gas Treatment System.
Per N-CL-OPS-261000 Standby Gas Treatment System, VG will maintain the Secondary Containment at a negative pressure of -0.25 in. WC to assure that there is no unfiltered release of contaminated air to the environment. SGTS ensures that any radioactive materials that leak from the Primary Containment into the Secondary Containment following an accident are filtered by SGTS prior to release.
A is incorrect but plausible - there are numerous Process Radiation Monitors in the AR/PR system designed to detect liquid radioactivity releases (FC Heat Exchanger WS Effluent Monitors 1RIXPR004 &
5, WS Effluent Monitor 1RIXPR036, CC HX Monitor 1RIXPR037, SX Effluent Monitors 1RIXPR038 & 39, and Liquid Radwaste Discharge Monitor 0RIXPR040.
B is incorrect but plausible - this is the function of the MCR Air Intake Monitors 1RIX-PR009A - D.
D is incorrect but plausible - A Group 12 Isolation of the Containment Monitoring Isolation Valves is initiated at RPV Level 2, High Drywell Pressure, and Containment Building Exhaust Radiation Monitors 1RIX-PR001A - D, not by 1RIX-PR042A-D.
KA justification - meets the KA because the examinee must know why the CCP Exhaust Radiation monitors initiate automatic closure of the SCIDs in order to answer this question.
CPS OPS ILT EXAM Page: 31 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896298 User-Defined ID: CL-ILT-812580A Cross Reference Number:
A trip of Continuous Containment Purge (CCP) Exhaust Topic:
Radiation Monitors 1RIX-PR042A, B, C, AND D w Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 32 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- ITS B 3.3.6.1 Primary Revision Number: Containment and Drywell Isolation Instrumentation
- ITS B 3.3.6.2 Secondary Containment Isolation Instrumentation
- CPS 4001.02C001 Auto Isolation Checklist Rev. 15d
- N-CL-OPS-272000 Area and Process Radiation Monitoring Systems (AR/PR)
- N-CL-OPS-261000 Standby Gas Treatment System Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1B / 1I)
KA Data KA Number / System Name: 295038 High Off-Site Release Rate Category / KA Statement: EK3. Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: EK3.02 System isolations (CFR: 41.5 / 45.6)
RO Value: 3.9 SRO Value: 4.2 CPS OPS ILT EXAM Page: 33 of 351 27 August 2013 Tier: 1 RO Group: 1 SRO Group: 1
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 7 223002.08 Given the CRVICS system, DESCRIBE the systems supported and the nature of the support CPS OPS ILT EXAM Page: 34 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 8 ID: 896299 Points: 1.00 A Loss of Coolant Accident is in progress.
The CRS has established containment pressure as a critical parameter, and has directed you to inform him/her when containment pressure reaches 3.2 psig.
A few minutes later, you report the following plant conditions to the CRS:
- Containment pressure at 3.2 psig, trending up.
- Containment temperature at 150°F, trending up.
- Saturation conditions have been reached in the Drywell.
The CRS then announces entry into EOP-3 Emergency RPV Depressurization.
Which of the following states the bases for performing a blowdown under these circumstances?
A blowdown is performed...
A. because containment design pressure has been exceeded.
B. to prevent exceeding the containment design temperature limit.
C. to ensure continued operability of RPV water level instrumentation.
D. because the pressure suppression function of the containment is being challenged.
Answer: D Answer Explanation D is correct:
A blowdown is performed per EOP-6 if Containment pressure cannot be maintained within Fig. N, Pressure Suppression Pressure. At 20' in the suppression pool, the Fig. N limit for containment pressure is 3.2 psig.
A is incorrect but plausible - the Primary Containment Pressure Limit (Fig. D) is affected by Primary Containment Water Level. With Primary Containment Water Level at 70 ft, PCPL is 38 psig. With Primary Containment Water Level at 54 ft, the PCPL is 45 psig.
B is incorrect but plausible - this is the bases for performing a blowdown on containment temperature, not for exceeding PSP.
C is incorrect but plausible - RPV level indications are affected by high DW and Cnmt temperatures, but this is not the bases for performing a blowdown when PSP has been exceeded.
KA justification - this question meets the KA because the examinee is required to know why a blowdown is performed when Containment Pressure has exceeded PSP.
CPS OPS ILT EXAM Page: 35 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896299 User-Defined ID: CL-ILT-812581A Cross Reference Number:
A Loss of Coolant Accident is in progress. The CRS has Topic:
established containment pressure as a crit Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 36 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- EOP Tech Bases Rev.
Revision Number: 6 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS 2005 DAEC NRC Exam NRC-05, OYS CERT-04) Q11 Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised question for History: (i.e. Modified applicability at CPS distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1F)
KA Data KA Number / System Name: 295024 High Drywell Pressure Category / KA Statement: EK3. Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE: EK3.04 Emergency depressurization (CFR: 41.5 / 45.6)
RO Value: 3.7 SRO Value: 4.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 37 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 8 LP87558.01.02 Given a diagram of EOP-6:
.01 State the conditions to exit/transfer from EOP-6
.02 State the bases for each individual step/action of EOP-6
.03 State the systems that are available for Containment Purge
.04 State the systems and flow paths that can be used to cool and control pressure in the containment.
CPS OPS ILT EXAM Page: 38 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 9 ID: 896300 Points: 1.00 A plant transient resulted in a scram. Current conditions are as follows:
- Reactor power is 8%.
- Main Steam Isolation Valves (MSIVs) are open.
- RPV water level is -20 inches and lowering.
- Off-site power is available.
The CRS has directed you to perform CPS 4410.00C004 Defeating MSL/OG Interlocks. The reason for this direction is to...
A. facilitate an immediate reactor plant cooldown to 200°F.
B. prevent the need for injecting Standby Liquid Control (SLC).
C. keep the Turbine Bypass Valves available in the event a blowdown is anticipated.
D. keep the main condenser available to reduce the probability of exceeding the Heat Capacity Temperature Limit (HCTL).
Answer: D Answer Explanation D is correct:
Per 4404.01 (EOP-1A) ATWS, the level leg contains instructions to defeat MSL/OG and IA interlocks to maintain main condenser as heat sink (4410.00C004).
CPS 4410.00C004 defeats the Group 1 Isolation signal on RPV Level 1 and the IA Isolation signals to keep the Main Steam Lines and Main Condenser available as a heat sink. This reduces the heat input to the containment and minimizes the probability of exceeding the HCTL.
A is incorrect but plausible - maintaining the condenser as a heat sink to facilitate plant cooldown is appropriate in EOP-1 RPV Control but inappropriate in EOP-1A until cold shutdown boron is injected or if shutdown criteria is met, otherwise RPV pressure is stabilized below 1065 psig.
CPS OPS ILT EXAM Page: 39 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version B is incorrect but plausible - EOP-1A directs starting SLC whenever power is above 5% or unknown regardless of Suppression Pool temperature. The examinee may select this choice if he/she incorrectly believes that SLC is only initiated when above Fig. G Boron Injection Temperature (Suppression Pool Temperature vs. Reactor Power).
C is incorrect but plausible - EOP-1A directs stabilizing reactor pressure below 1065 psig to prevent adding positive reactivity to the reactor. Rapid depressurization is accomplished using the ADS system.
4410.00C004 is performed to maintain the condenser as a heat sink to prevent unnecessarily adding heat to the containment.
KA justification - this question meets the KA because the examinee is required to know why 4410.00C004 is performed during an ATWS condition.
CPS OPS ILT EXAM Page: 40 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896300 User-Defined ID: CL-ILT-812582 Cross Reference Number:
A plant transient resulted in a scram. Current conditions are as Topic:
follows: Reactor power is 8%. M Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 41 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 4404.01 (EOP-1A) Rev.
Revision Number: 29
- 4410.00C004 Rev. 5a Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS 2005 Grand Gulf NRC NRC-05, OYS CERT-04) Exam Q18 Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised Q18 on the 2005 History: (i.e. Modified Grand Gulf NRC Exam for distractor b to make use at CPS.
plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. Level Leg of 4404.01 Ensure ON-## not provided) ATWS RPV CONTROL LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or unknown Category / KA Statement: EK3. Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : EK3.06 Maintaining heat sinks external to the containment (CFR: 41.5 / 45.6)
RO Value: 3.8 SRO Value: 4.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 42 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 9 LP87553.01.03 Given a diagram of EOP-1A:
.01 Describe the conditions to exit/transfer from EOP-1A
.02 State the bases for each individual step/action of EOP-1A
.03 Discuss the importance of verifying that the appropriate automatic actions of EOP-1A occur as required
.04 List the available methods to be used to stabilize/control RPV pressure in EOP-1A
.05 List the Preferred ATWS level control systems.
CPS OPS ILT EXAM Page: 43 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 10 ID: 896301 Points: 1.00 A MCR evacuation was conducted and the appropriate actions of CPS 4003.01 Remote Shutdown (RS) were performed.
ALL 4.16 KV electrical buses remained energized during the evacuation.
One hour later, a loss of ALL off-site power (LOOP) occurred.
Assuming NO operator actions and ALL equipment functioned as designed, which of the following describes the status of 4160V Buses 1A1 and 1B1?
A. NEITHER Bus energized.
B. BOTH buses energized from their respective DG.
C. ONLY 4160V Bus 1A1 energized from its respective DG.
D. ONLY 4160V Bus 1B1 energized from its respective DG.
Answer: B Answer Explanation B is correct:
CPS 4003.01 Remote Shutdown Hard Card 'A' directs placing C61-HS502 in EMERGENCY. Performing this action prevents the Div 1 DG from starting on a LOCA signal, but does not override auto initiation on 4160V Bus 1A1 undervoltage.
Per 5060.03 (3C), 5061.03 (3C) and CPS 3506.01 section 8.4.1 DG 1A(1B)(1C) Auto Start, a loss of all off-site power will result in an undervoltage initiation of the Div 1 and Div 2 DGs and output breaker closure/bus reenergization.
A is incorrect but plausible - the examinee may select this choice based on the knowledge that when RSP transfer switches are placed in "Emergency", many components will typically not respond to their normal initiation signals (i.e: LOCA signal). This does not, however, apply to Div 1 or Div 2 DG initiation on bus undervoltage.
C is incorrect but plausible - the examinee may select this choice based on the knowledge that when RSP transfer switches are placed in "Emergency", many components will typically not respond to their normal initiation signals (i.e: LOCA signal). This does not, however, apply to Div 1 or Div 2 DG initiation on bus undervoltage.
D is incorrect but plausible - the examinee may select this choice based on the knowledge that when RSP transfer switches are placed in "Emergency", many components will typically not respond to their normal initiation signals (i.e: LOCA signal). This does not, however, apply to Div 1 or Div 2 DG initiation on bus undervoltage.
KA justification - this question meets the KA because the examinee is required to determine the status of the 4160V Bus 1A1 and 1B1 buses on a loss of off-site power while operating from the Remote Shutdown Panel.
CPS OPS ILT EXAM Page: 44 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896301 User-Defined ID: CL-ILT-812583 Cross Reference Number:
A MCR evacuation was conducted and the appropriate actions Topic:
of CPS 4003.01 Remote Shutdown (RS) wer Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 45 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3506.01 Rev. 35 Revision Number:
- CPS 5060.03 (3C) Rev.
30a
- CPS 5061.03 (3C) Rev.
30a
Question History: (i.e. LGS 2009 MNGP Audit Exam NRC-05, OYS CERT-04) Q6 Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised Q6 on the 2009 History: (i.e. Modified MNGP Audit Exam for use distractor b to make at CPS.
plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 295016 Control Room Abandonment Category / KA Statement: AA1. Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: AA1.04 A.C. electrical distribution (CFR:
41.7 / 45.6)
RO Value: 3.1 SRO Value: 3.2 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 46 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 10 200000.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following REMOTE SHUTDOWN System components.
.1 Residual Heat Removal (RHR)
Pump Minimum Flow Control Valve Logic
.2 Safety Relief Valves (SRVs)
Relief Mode when Transfer Switch 1C61-S10 is in the Emergency position
.3 Remote Shutdown Panel Transfer Switches CPS OPS ILT EXAM Page: 47 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 11 ID: 896302 Points: 1.00 The plant is performing a shutdown in preparation for a maintenance outage.
RHR Pump 'B' is operating in Shutdown Cooling Mode.
THEN, RPV level LOWERED to +5.0 inches.
Given these conditions, which of the following describes the impact to the RHR System?
NOTE - Valve descriptions are as follows:
- 1E12-F008 Shutdown Cooling Outbd Suct Isol Vlv
- 1E12-F009 Shutdown Cooling Inbd Suct Isol Vlv A. 1E12-F008 ONLY closes; RHR Pump 'B' trips B. RHR Pump 'B' continues to operate at 5000 gpm.
C. RHR Pump 'B' continues to operate at reduced flow.
D. 1E12-F008 AND 1E12-F009 close; RHR Pump 'B' trips Answer: D Answer Explanation D is correct - per CPS 4001.02C001 Automatic Isolation Checklist, a Group 3 isolation will occur when RPV level reaches 8.9 inches (Level 3). This will result in automatic closure of the following valves:
- 1E12-F053A RHR A To Feedwater S/D Cooling Rtrn Vlv
- 1E12-F053B RHR B To Feedwater S/D Cooling Rtrn Vlv
- 1E12-F008 Shutdown Cooling Outbd Suct Isol Vlv
- 1E12-F009 Shutdown Cooling Inbd Suct Isol Vlv
- 1E12-F023 RHR B Supp To Rx Head Spray Valve Per 5065.03 (3A) RHR Pump B Auto Trip, RHR Pump 'B' will trip if either 1E12-F008 or F009 is not fully open.
A is incorrect but plausible if the examinee incorrectly believes that F009 (Div 1 valve) does not receive an auto closure signal with RHR Pump 'B' (Div 2 Pump) running.
B is incorrect but plausible if the examinee incorrectly believes that the low RPV water level isolation setpoint has not been exceeded and that RHR Pump 'B' is therefore unaffected by the conditions listed in the stem.
C is incorrect but plausible - 1B21-F032B Feedwater Line B Containment Isolation Check Valve receives an isolation signal at Level 2 or High DW pressure. When actuated, flow through the 'B' FW line is restricted, causing RHR B SDC flow to decrease.
KA justification - this question meets the KA because the examinee is required to predict the impact of lowering RPV water level on the RHR Shutdown Cooling system.
CPS OPS ILT EXAM Page: 48 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896302 User-Defined ID: CL-ILT-812584A Cross Reference Number:
The plant is performing a shutdown in preparation for a Topic:
maintenance outage. RHR Pump 'B' is ope Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 49 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 5065.03 (3A) Rev. 28 Revision Number:
- 4001.02C001 Rev. 15d
- N-CL-OPS-259001 Rev. 1 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. 4001.02C001 Auto Isolation Ensure ON-## not provided) Checklist LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 295021 Loss of Shutdown Cooling Category / KA Statement: AA1. Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING : AA1.02 RHR/shutdown cooling (CFR: 41.7 / 45.6)
RO Value: 3.5 SRO Value: 3.5 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 50 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 11 203000.03 DESCRIBE the function, operation, interlocks, trips, physical locations, and power supplies of the following RESIDUAL HEAT REMOVAL System components.
.1 Suppression Pool Suction Strainer
.2 RHR Pumps
.3 RHR Heat Exchangers
.4 B/C Water Leg Pump
.5 Containment Spray Header and Nozzles
.6 Suppression Pool Suction Valves F004A, F004B.
.7 RH Shutdown Cooling Suction Valves F006A and F006B
.8 Shutdown Cooling Inboard and Outboard Isolation Valves F009 and F008
.9 RH B Supply to Reactor Head Spray Valve F023
.10 RH C Full Flow Test Valve F021
.11 RH A (B) Full Flow Test Valves F024A and F024B
.12 RH A (B) Containment Outboard Isolation Valves F027A and F027B
.13 RH A(B) Containment Spray A(B) Shutoff Valves F028A and F028B
.14 RH A(B) to Containment Pool Cooling Shutoff Valves F037A and F037B
.15 LPCI From RH Shutoff Valves F042A, F042B, and F042C
.16 LPCI From RH Testable Check Valves F041A, F041B, and F041C
.17 RH Heat Exchanger Inlet Valves F047A and F047B
.18 RH Heat Exchanger Outlet CPS OPS ILT EXAM Page: 51 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Valves F003A and F003B
.19 RH B Radwaste First and Second Isolation Valves F049 and F040
.20 RH Heat Exchanger Bypass Valves F048A and F048B
.21 RH to Feedwater Shutdown Cooling Return Valves F053A and F053B
.22 RH Heat Exchanger First and Second Sample Valves F060A, F060B, F075A and F075B
.23 RH Pump Minimum Flow Recirc Valves F064A, F064B and F064C
.24 RH Heat Exchanger SSW Inlet and Outlet Valves F014A, F014B, F068A and F068B
.25 RH Fuel Pool Cooling Assist Suction Valve F066 CPS OPS ILT EXAM Page: 52 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 12 ID: 896303 Points: 1.00 The plant was operating at rated thermal power when annunciator 5041-4C Low Press Control Bldg IA Ring Hdr was received.
Service Air system parameters are currently as shown and steady:
Given these conditions, which of the following describes the expected positions of 1IA005, 006, 007, and 008?
CPS OPS ILT EXAM Page: 53 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version A. Alignment 1 B. Alignment 2 C. Alignment 3 D. Alignment 4 Answer: A Answer Explanation A is correct:
Per CPS 5041.04 (4C) Low Pressure Control Building IA Ring Header, low pressure of 70 psig will cause automatic closure of 1IA022 and 1IA021 Control Building IA Ring Header Isolation Valves, resulting in a loss of air to Instrument Air system loads supplied from the Control Building.
With Service Air Header pressure and Service Air Compressor amperage operating in the normal range per the graphic, 1IA021 and 22 have automatically responded correctly to the low pressure condition and the remainder of the IA system is unaffected.
CPS OPS ILT EXAM Page: 54 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Per CPS 3214.01 Plant Air (IA & SA) Figure 1 (page 30), instrument air is supplied to the containment from the Aux/Fuel Building IA Ring Header and/or the Control Building IA Ring Header. Thus, if only the CB IA Ring Header is lost, air is maintained to the Containment via the Aux/Fuel Building IA ring header.
1IA005, 6, 7, and 8 will remain open.
B is incorrect but plausible if the examinee incorrectly believes that air pressure has been lost only to 1IA005 and 1IA008 causing them to fail closed.
C is incorrect but plausible if the examinee incorrectly believes that air pressure has been lost only to 1IA006 and 1IA007 causing them to fail closed.
D is incorrect but plausible if the examinee incorrectly believes that air pressure has been lost to 1IA005, 006, 007, and 008 causing each of the valves to fail closed.
KA justification - this question meets the KA because the examinee must be able to determine the expected response of valves 1IA005, 006, 007, and 008 to a loss of the Control Building Instrument Air Header.
CPS OPS ILT EXAM Page: 55 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 12 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: 896303 User-Defined ID: CL-ILT-812585A Cross Reference Number:
The plant was operating at rated thermal power when Topic:
annunciator 5041-4C Low Press Control Bldg IA Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 56 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 4001.02 Rev. 17a Revision Number:
- 4001.02C001 Rev. 15d
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. 4001.02C001 Auto Isolation Ensure ON-## not provided) Checklist LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2RI)
KA Data KA Number / System Name: 295019 Partial or Complete Loss of Instrument Air Category / KA Statement: AA1. Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : AA1.02 Instrument air system valves: Plant-Specific (CFR: 41.7 /
45.6)
RO Value: 3.3 SRO Value: 3.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 57 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 12 300000.03 DESCRIBE the function, operation, interlocks, trips, physical locations and power supplies of the following Service and Instrument Air System components.
.1 Service Air Compressors
.2 Lube Oil System
.3 Vibration Monitor
.4 Main Service Air Receivers
.5 Service Air Dryers
.6 Makeup Water Pump House Air Receivers
.7 Circulating Water Screen House Air Receivers
.8 Ring Headers
.9 Ring Header Isolation Valves
.10 Containment Service Air Header Isolation Valves
.11 Containment Instrument Air Header Isolation Valves
.12 ADS Air Amplifiers
.13 Compressed Gas Inboard Isolation Valves
.14 Compressed Gas Outboard Isolation Valves
.15 ADS Backup Air Bottles
.16 Fuel Pool Gate Seal Backup Bottles CPS OPS ILT EXAM Page: 58 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 13 ID: 896304 Points: 1.00 For the question below, assume the following:
- The plant was operating at rated thermal power for the previous 300 days when the transient occurred.
- All automatic actions responded as designed.
- All appropriate EOP-1 pressure control strategies are being utilized at the same time to maintain RPV pressure 800-1065 psig.
Analyze the 4 scenarios listed below and determine which scenario would result in the EARLIEST entry into EOP-6 Primary Containment Control on HIGH Suppression Pool temperature.
Scenario Transient RCIC Utilized?
1 Main Turbine Trip without Bypass Valves Yes 2 Main Turbine Trip without Bypass Valves No 3 Group 1 Isolation due to high MSL flow Yes 4 Group 1 Isolation due to high MSL flow No A. Scenario 1 B. Scenario 2 C. Scenario 3 D. Scenario 4 Answer: D Answer Explanation D is correct -
Each of the listed scenarios will result in a reactor pressure transient / reactor scram requiring entry into EOP-1 RPV Control.
Per EOP-1 RPV Control, directions are provided to stabilize RPV pressure below 1065 psig using the following methods:
- MSL Drains
- RWCU (recirculation mode)
- RWCU (reject mode)
The conditions in Scenario 4 will result in the highest heat up rate of the suppression pool and the earliest entry into EOP-6 Primary Containment Control on high suppression pool temperature because the only methods for rejecting decay heat are by using the SRVs and RWCU systems. The remaining pressure control methods are not available due to the Group 1 isolation and RCIC unavailability.
CPS OPS ILT EXAM Page: 59 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version A is incorrect but plausible because RCIC, RFPTs, MSL Drains, and RWCU are available pressure control methods which can be used to delay entry into EOP-6 on high suppression pool temperature. The examinee may select this choice because the Main Turbine Trip without BPVs transient is the limiting pressure transient on the plant (will result in the highest RPV pressure).
B is incorrect but plausible because RCIC, RFPTs, MSL Drains, and RWCU are available pressure control methods which can be used to delay entry into EOP-6 on high suppression pool temperature. The examinee may select this choice if he/she incorrectly believes that utilizing SRVs alone will add less overall heat to the suppression pool than using SRVs and RCIC together.
C is incorrect but plausible if the examinee incorrectly believes that using SRVs and RCIC together add more heat to the suppression pool than using SRVs alone.
KA justification - this question meets the KA because the examinee is required to evaluate 4 scenarios and determine which scenario would affect suppression pool temperature the greatest/fastest.
CPS OPS ILT EXAM Page: 60 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 13 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: 896304 User-Defined ID: CL-ILT-812587 Cross Reference Number:
For the question below, assume the following: The plant was Topic:
operating at rated thermal power for Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 61 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with 4401.01 EOP-1 RPV Revision Number: Control Rev. 29 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. 4401.01 EOP-1 Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295025 High Reactor Pressure Category / KA Statement: EA2. Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: EA2.03 Suppression pool temperature (CFR:
41.10 / 43.5 / 45.13)
RO Value: 3.9 SRO Value: 4.1 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: 62 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 13 LP87552.01.02
.01 Given a diagram of EOP-1, describe the conditions for exiting/transferring from EOP-1 per CPS 1005.09 without error.
.02 Given a diagram of EOP-1, recall the bases for each individual step/action of EOP-1 per CPS EOP Technical Bases without error
.03 Given a diagram of EOP-1, state the minimum suppression pool water level required for the operation of SRVs per EOP-1 without error.
.04 From memory, recall the preferred and alternate methods that can be used to stabilize RPV pressure below 1065 psig as listed on EOP-1 without error.
.05 Given plant conditions involving elevated Drywell/Containment temperatures and a diagram of EOP-1, determine RPV level instrument availability per Detail A, RPV Water Level Instruments, without error.
.06 Given plant conditions and a copy of 4411.09, identify which methods of pressure control are available for use per EOP-1 without error.
CPS OPS ILT EXAM Page: 63 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 14 ID: 896392 Points: 1.00 A major plant transient has occurred with a loss of high pressure injection resulting in the following indications at different times (the first at 0100 and the second at 0115) during the transient.
0100
- Low Pressure Core Spray Flow - 0 gpm
- Low Pressure Coolant Injection Flow - 0 gpm
- High Pressure Core Spray Flow - 0 gpm CPS OPS ILT EXAM Page: 64 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 0115
- Low Pressure Core Spray Flow - 5500 gpm
- A - 4800 gpm
- B - 4800 gpm
- C - 4800 gpm
- High Pressure Core Spray Flow - 0 gpm Under these conditions, adequate core cooling...
A. exists at 0100 ONLY.
B. exists at 0115 ONLY.
C. exists at 0100 AND 0115.
D. does NOT exist at time 0100 NOR 0115.
Answer: A Answer Explanation A is correct:
CPS OPS ILT EXAM Page: 65 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Per the EOP Tech Bases, adequate core cooling is defined as heat removal from the reactor sufficient to prevent rupturing the fuel clad. Two viable mechanisms of adequate core cooling are defined at Clinton core submergence and steam cooling.
Submergence is the preferred method of core cooling. The core is adequately cooled by submergence if RPV water level is above the top of the active fuel. All fuel nodes are then assumed to be covered with water and heat is removed by boiling heat transfer.
Steam cooling is relied upon at Clinton only if:
- RPV water level cannot be restored and maintained above the top of the active fuel following a blowdown in EOP-1 or EOP-1A.
The core is adequately cooled by steam under these conditions if the steam flow through the uncovered part of each fuel bundle is sufficient to maintain the temperature of the hottest fuel rod below 1500°F, the threshold for fuel rod perforation. The covered portion of the core remains cooled by boiling heat transfer and generates the steam that cools the uncovered portion.
When RPV water level cannot be restored and maintained above the top of the active fuel following a blowdown in EOP-1 or EOP-1A, adequate steam flow is established by maintaining RPV water level above the Minimum Steam Cooling RPV Water Level (-187 inches).
Therefore, at time 0100, with Wide Range Level indication reading -113", adequate core cooling is provided by core submergence. At 0115, with Fuel Zone level reading -200" and rising, the Minimum Steam Cooling RPV Water Level of -187 inches has NOT been reached and adequate core cooling does not exist from submergence or from steam cooling.
B is incorrect but plausible if the examinee incorrectly determines that adequate core cooling exists at 0115. The examinee may select this choice based on the idea that adequate core cooling exists under these conditions with RPV level above 2/3 core height (~211 inches) and low pressure ECCS Pumps injecting at 19,900 gpm. The examinee may also select this response if he/she incorrectly believes that submergence core cooling does not exist at 0100 with RPV level indicating below TAF by the fuel zone level indicator with no injection flow.
C is incorrect but plausible if the examinee incorrectly determines that adequate core cooling exists at 0100 and 0115. The examinee may select this choice based on the idea that adequate core cooling exists under these conditions with RPV level above TAF (in the 0100 graphic) and with 2/3 core height
(~211 inches) and low pressure ECCS Pumps injecting at 19,900 gpm (in the 0115 graphic).
D is incorrect but plausible if the examinee incorrectly determines that adequate core cooling does not exist at 0100 or 0115 for the reasons cited above.
KA justification - this question meets the KA because the examinee has to intepret Wide Range and Fuel Zone level indications and then determine if adequate core cooling exists based on those indications.
CPS OPS ILT EXAM Page: 66 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896392 User-Defined ID: CL-ILT-812598 Cross Reference Number:
A major plant transient has occurred with a loss of high Topic:
pressure injection resulting in the follo Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 67 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- EOP Tech Bases Rev.
Revision Number: 6
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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: EA2. Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL : EA2.04 Adequate core cooling (CFR: 41.10
/ 43.5 / 45.13)
RO Value: 4.6 SRO Value: 4.8 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: 68 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
LP87551.01.08 State the definitions of the following words and/or phrases associated with the Emergency Operating Procedures:
.01 Adequate Core Cooling
.02 Available
.03 Before
.04 Blowdown
.05 Control
.06 Enter
.07 Hold
.08 Inhibit ADS
.09 Leave
.10 Line up
.11 Monitor
.12 Prevent
.13 Purge
.14 Stay
.15 Terminate and Prevent
.16 Unknown
.17 Vent
.18 Verify Question 14 CPS OPS ILT EXAM Page: 69 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 15 ID: 896306 Points: 1.00 The plant was operating at rated thermal power when the following annunciator was received:
- 5003-3E Recirc Pmp A Seal Clg Wtr Flow Lo This alarm means that...
A. seal cooling flow from the Control Rod Drive system is low.
B. Component Cooling Water (CCW) system flow to the seal cooler is low.
C. there is a loss of flow in the seal staging line to the Drywell Equipment Drain Sump.
D. the internal RCS seal flow generated by the auxiliary impeller has reached a low flow setpoint.
Answer: B Answer Explanation B is correct:
Per 5003.03 (3E), the Recirculation Pump A Seal Cooling Water Flow Low alarm is caused by a loss of CCW flow to the cooler at 16 gpm.
A is incorrect but plausible - the CRD system provides purge flow to the RR Pump Seals but the flow is not monitored by an alarm circuit.
C is incorrect but plausible - low flow in the seal staging line is annunciated by 5003-5E Recirc Pump A Seal Staging Flow Lo.
D is incorrect but plausible - the RCS does provide seal flow using an auxiliary impeller, but the flow is not monitored by an alarm circuit.
KA justification - this question meets the KA because the RR Pump Seal Cooling Water Flow Low alarm is the primary indicator of a partial or total loss of CCW system flow. The examinee must intepret the conditions listed in the stem and determine that the alarm is an indication of a partial or complete loss of CCW.
CPS OPS ILT EXAM Page: 70 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896306 User-Defined ID: CL-ILT-812588 Cross Reference Number:
The plant was operating at rated thermal power when the Topic:
following annunciator was received: 5003-Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 71 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 5003.03 (3E) Rev. 29 Revision Number:
- 5003.05 (5E) Rev. 30c Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 295018 Partial or Complete Loss of Component Cooling Water Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :
AA2.04 System flow (CFR: 41.10 / 43.5 / 45.13)
RO Value: 2.9 SRO Value: 2.9 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: 72 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 15 202001.06 Given a Reactor Recirculation System Annunciator, DESCRIBE:
.1 The condition causing the annunciator
.2 Any automatic actions
.3 Any operational implications CPS OPS ILT EXAM Page: 73 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 16 ID: 896307 Points: 1.00 The plant was operating at 22% power performing a power ascension when annunciator 5007-1B Turb Trip EHC Sys was received.
While verifying Main Turbine status on the Plant Process Computer (PPC) Display #8, the following indications were observed (also see attached duplicate graphic):
Evaluate these indications and select the answer that describes the status of the Main Turbine.
A. All turbine valves responded as expected for being at 22% power.
B. NOT all turbine valves responded as expected. The turbine is at risk of sustaining damage.
C. The turbine trip was due to mechanical overspeed and the valves responded as expected for this condition.
D. NOT all turbine valves responded as expected, but the Backup Overspeed Trip device will protect the turbine from damage.
Answer: B Answer Explanation B is correct:
The Plant Process Computer displays green for valves that are closed and red for valves that are open.
In this question, the Main Turbine Stop and Control Valves have repositioned to the closed position, and the Intermediate Stop Valves are still open.
CPS OPS ILT EXAM Page: 74 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Per N-CL-OPS-241000 Electrohydraulic Control, any turbine trip signal will cause the Turbine Emergency Trip system to depressurize the ETS header and cause the turbine stop valves, control valves and combined intermediate valves to close.
Per N-CL-OPS-245000, the function of the IVs/ISVs is to protect the turbine against overspeed from stored steam in the crossaround piping.
A is incorrect but plausible - the ISVs will close on a turbine trip regardless of power level. The examinee my select this response confusing this with the Turbine Trip input to RPS which is bypassed at low power
(<33.3%).
C is incorrect but plausible - a mechanical overspeed will cause all SVs, CVs, and ISVs to close. The examinee may select this response based in incorrect recall of the function of the ISVs to protect the Main Turbine from overspeed conditions.
D is incorrect but plausible - the Backup Overspeed Trip will cause all SVs, CVs, and ISVs to close. Since a turbine trip signal is present, the BOST will not protect the turbine from damage.
KA justification - this question meets the KA because the examinee has to determine turbine status based on Plant Process Computer displays.
CPS OPS ILT EXAM Page: 75 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896307 User-Defined ID: CL-ILT-812589A Cross Reference Number:
The plant was operating at 22% power performing a power Topic:
ascension when annunciator 5007-1B Turb Tr Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 76 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- N-CL-OPS-245000 Revision Number: Rev. 1
- N-CL-OPS-241000 Rev. 5 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 295005 Main Turbine Trip Category / KA Statement: 2.1.19 Ability to use plant computers to evaluate system or component status. (CFR:
41.10 / 45.12)
RO Value: 3.9 SRO Value: 3.8 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 77 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 16 241000.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following ELECTROHYDRAULIC CONTROL System components.
.1 Emergency Trip System
.2 Steam Bypass Valves
.3 Pressure Reducers
.4 Bypass HPU Pumps
.5 Hydraulic Power Unit Transfer Pump
.6 Main EHC Fluid Pumps
.7 EHC Transfer and Filter Pump
.8 HPU Heaters and Fans
.9 Coolers
.10 Main Stop Valves
.11 Control Valves
.12 Combined Intermediate Valves
.13 Fullers Earth Filters
.14 Permanent Magnet Generator (PMG)
CPS OPS ILT EXAM Page: 78 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 17 ID: 896308 Points: 1.00 Plant conditions are as follows:
- Plant is in mode 5 for a refueling outage.
- 4160V Bus 1A1 is deenergized for scheduled outage activities.
- RHR 'B' is operating in Shutdown Cooling Mode.
Then, 4160V Bus 1B1 deenergizes and locks out (cause unknown).
The CRS has entered CPS 4006.01 Loss of Shutdown Cooling.
Based on these conditions and power availability, which of the following Shutdown Cooling Methods listed in 4006.01 Table 2: Shutdown Cooling Methods is/are available for decay heat removal 10 minutes later?
Method 1 ECCS Feed and Bleed Through SRVs Method 2 Reactor Water Cleanup Method 3 Fuel Pool Cooling and Cleanup Using Natural Circulation A. Method 1 ONLY B. Method 2 ONLY C. Methods 1 and 2 ONLY D. Methods 1, 2, and 3 Answer: C Answer Explanation C is correct:
With a loss of 4160V Bus 1A1 and 1B1, the only methods listed that are not affected by the loss of power are Methods 1 and 2.
- ECCS Feed and Bleed Through SRVs can be accomplished by operating the HPCS Pump (which is powered from 4160V Bus 1C1) and flowing water through the SRVs.
- RWCU can be aligned for alternate shutdown cooling IAW CPS 3303.01 Reactor Water Cleanup (RT) section 8.2.6 by bypassing the Regenerative Heat Exchangers and using the NRHXs for a heat sink.
CCW and RT must be in operation; neither system requires power from 4160V Bus 1A1 or 1B1 to support alternate decay heat removal operations. The system can also be operated without instrument air by bypassing the RWCU Filter Demineralizers.
A is incorrect but plausible if the examinee fails to recall that RWCU system is available as an alternate shutdown cooling system.
B is incorrect but plausible if the examinee fails to recall that Method 1 (ECCS Feed and Bleed Through SRVs) is available as an alternate shutdown cooling system using HPCS (which is powered from 4160V Bus 1C1).
D is incorrect but plausible if the examinee fails to recall that Method 3 (Fuel Pool Cooling and Cleanup Using Natural Circulation) is not available as an alternate shutdown cooling method with 4160V Bus 1A1 and 1B1 deenergized.
CPS OPS ILT EXAM Page: 79 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version KA justification - this question meets the KA because the examinee is required to determine which alternate shutdown cooling methods are available during a loss of 2 class-1E 4160V busses.
CPS OPS ILT EXAM Page: 80 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896308 User-Defined ID: CL-ILT-887713A Cross Reference Number:
Plant conditions are as follows: Plant is in mode 5 for a Topic:
refueling outage. 4160V Bus 1A1 is deen Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 81 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 4006.01 Rev. 5 Revision Number:
- CPS 3303.01 Rev. 34c
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO 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: 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. (CFR: 41.10 / 43.5 / 45.13)
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 CPS OPS ILT EXAM Page: 82 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 17 DB400601.01.04 Recall the different methods to remove decay heat from the reactor core.
CPS OPS ILT EXAM Page: 83 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 18 ID: 896309 Points: 1.00 (1) The plant is operating at rated thermal power. Which design feature REDUCES forced coolant flow in order to prevent exceeding the MCPR SL?
(2) The plant is operating at rated thermal power. Which design feature functions to prevent exceeding the MCPR SL after an ACTUAL loss of forced coolant flow has occurred?
A. (1) RR FCV runback on TDRFP trip (2) OPRM trip B. (1) RR FCV runback on TDRFP trip (2) APRM Neutron Flux-High, Setdown C. (1) RR Pump downshift on turbine trip (2) OPRM trip D. (1) RR Pump downshift on turbine trip (2) APRM Neutron Flux-High, Setdown Answer: C Answer Explanation C is correct:
- Per ITS B 3.3.4.1, the EOC-RPT instrumentation initiates a recirculation pump trip (RPT) to reduce the peak reactor pressure and power resulting from turbine trip or generator load rejection transients to provide additional margin to core thermal MCPR Safety Limits (SLs).
- Per ITS B 3.3.1.3, the OPRM System provides compliance with GDC 10 and GDC 12, thereby providing protection from exceeding the fuel Minimum Critical Power Ratio (MCPR) safety limit.
A is incorrect but plausible. The RR Flow Control Valve Automatic Runback is provided to reduce reactor power to within the capacity of one reactor feed pump to prevent a scram on low level in the vessel due to the tripping of one of the reactor feed pumps.
B is incorrect but plausible. The RR Flow Control Valve Automatic Runback is provided to reduce reactor power to within the capacity of one reactor feed pump to prevent a scram on low level in the vessel due to the tripping of one of the reactor feed pumps. The APRM Neutron Flux-High Setdown function indirectly ensures that, before the reactor mode switch is placed in the run position, reactor power does not exceed 21.6% RTP (SL 2.1.1.1) when operating at low reactor pressure and low core flow. With the conditions provided in the stem, this trip is not in effect and therefore does not provide protection from exceeding the MCPR SL.
D is incorrect but plausible. The APRM Neutron Flux-High Setdown function indirectly ensures that, before the reactor mode switch is placed in the run position, reactor power does not exceed 21.6% RTP (SL 2.1.1.1) when operating at low reactor pressure and low core flow. With the conditions provided in the stem, this trip is not in effect and therefore does not provide protection from exceeding the MCPR SL.
KA justification - this question meets the KA because the examinee must have knowledge of the design features (EOC-RPT & OPRMs) in protecting the reactor from exceeding the MCPR SL before and after a partial loss of forced core flow circulation to answer this question.
CPS OPS ILT EXAM Page: 84 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 18 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: 896309 User-Defined ID: CL-ILT-812591 Cross Reference Number:
(1) The plant is operating at rated thermal power. Which Topic:
design feature REDUCES forced coolant fl Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 85 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- ITS B 3.3.1.3 Revision Number:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-B)
KA Data KA Number / System Name: 295001 Partial or Complete Loss of Forced Core Flow Circulation Category / KA Statement: 2.1.27 Knowledge of system purpose and/or function. (CFR: 41.7)
RO Value: 3.9 SRO Value: 4.0 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 86 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 18 215006.01 STATE the purpose(s) of the OSCILLATION POWER RANGE MONITOR System including applicable design bases.
212000.14 Given Reactor Protection System (RPS) and Alternate Rod Insertion (ARI)
System operability status and a copy of Tech Specs, DISCUSS the bases for the Reactor Protection System (RPS) and Alternate Rod Insertion (ARI) System Tech Spec LCO, related safety limits and Limiting Safety System Settings.
CPS OPS ILT EXAM Page: 87 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 19 ID: 896310 Points: 1.00 Spent fuel movements were in progress in the Fuel Building when the following indications were observed for the CCP Exhaust Radiation Monitors 1RIX-PR042A, B, C, AND D, and the Spent Fuel Storage ARM 1RIX-AR016 on the MCR AR/PR LAN:
- 1RIX-PR042A RED
- 1RIX-PR0042B YELLOW
- 1RIX-PR0042C RED
- 1RIX-PR0042D YELLOW
- 1RIX-AR016 RED NO additional operator action has yet been taken.
Which ONE of the following identifies the status of:
(1) The Fuel Building Supply and Exhaust Isolation Dampers?
AND (2) The SGTS Accident Range (AXM) Monitor 0RIX-PR008?
A. (1) Open (2) Standby Mode B. (1) Open (2) Operating Mode C. (1) Closed (2) Standby Mode D. (1) Closed (2) Operating Mode Answer: D Answer Explanation D is correct:
Per the conditions provided in the stem, radiation levels are elevated FB 755 as indicated by alert and high alarms on 1RIX-PR042A-D and 1RIX-AR016.
Per 5140.65, a trip of 1RIX-PR042A or B coincident with a trip of 1RIX-PR042C or D will cause automatic isolations of Groups 10, 16, and 19 (VR, VQ, VF) and automatic start of VG A and B.
Per CPS 3319.01 Standby Gas Treatment (VG), section 8.3.1 Automatic Initiation, the SGTS AXM 0RIX-PR008 is verified in operation when VG auto initiates.
Per CPS 4001.02C001 Automatic Isolation Checklist, a Group 19 isolation closes 1VF09Y, 4Y, 7Y, and 6Y (VF Supply and Exhaust Inboard and Outboard Isolation Valves).
A is incorrect but plausible if the examinee incorrectly believes that a Group 19 isolation condition doesn't exist based on the conditions provided in the stem.
CPS OPS ILT EXAM Page: 88 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version B is incorrect but plausible if the examinee incorrectly determines that the Fuel Building Supply and Exhaust Isolation Dampers should be open given the conditions provided in the stem.
C is incorrect but plausible if the examinee fails to recall that 0RIX-PR008 auto initiates on a Group 19 isolation / SGTS initiation.
KA justification - this question meets the KA because the examinee is required to interpret the radiation monitor readings in the stem to determine the impact on the plant.
CPS OPS ILT EXAM Page: 89 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896310 User-Defined ID: CL-ILT-887741A Cross Reference Number:
Spent fuel movements were in progress in the Fuel Building Topic:
when the following indications were obs Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 90 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3315.03 Rev. 9 Revision Number:
- CPS 5140.65 Rev. 0b
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295023 Refueling Accidents Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS : AA2.01 Area radiation levels (CFR: 41.10 /
43.5 / 45.13)
RO Value: 3.6 SRO Value: 4.0 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: 91 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 19 272000.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following AR/PR System components.
.1 Area Radiation Monitors (ARMs)
.2 Continuous Air Monitors (CAMs)
.3 Main Steam Line Radiation Monitors (MSLRMs)
.4 Containment Building Continuous Containment Purge (CCP) Duct Monitors
.5 Containment Building Fuel Transfer Pool Vent Plenum Monitors
.6 Containment Building Exhaust Duct Monitors
.7 Fuel Building (FB) Exhaust Vent Plenum Monitors
.8 Main Control Room Air Intake Monitors
.9 HVAC Exhaust Stack Monitors
.10 SGTS Exhaust Stack Monitors
.11 Pre-Treatment Offgas Monitor
.12 Post Treatment Offgas Monitors
.13 HVAC Accident Range (AXM)
Monitor
.14 SGTS Accident Range (AXM)
Monitor
.15 Fuel Pool Cooling & Cleanup (FC)
Heat Exchanger (HX) 1A (1B) WS Effluent Monitors
.16 Plant Service Water (WS) Effluent Monitor
.17 Component Cooling Water (CC)
HX Monitor
.18 Shutdown Service Water (SX)
Effluent Monitors
.19 Liquid Radwaste Discharge Monitor CPS OPS ILT EXAM Page: 92 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 20 ID: 896311 Points: 1.00 The plant is at Rated Thermal Power with all 3 Circulating Water (CW) Pumps in service.
A hard ground occurs causing a complete loss of 125VDC MCC 1E.
Of the following, what would be the expected response, if any, due to a loss of 125VDC MCC 1E?
A. ONLY CW pump 1A trips B. ONLY CW pump 1C trips C. CW pump 1A and 1C trips D. All CW Pumps remain running Answer: C Answer Explanation C is correct:
Per 4201.01 Loss of DC Power, step 1.4.1 states that in the event of a loss of DC MCC 1E or 1F Non-Divisional DC Buses, the CW pump(s) will trip for motors powered by the affected 6900V bus via alternate tripping circuit.
Per 4201.01C005 Loss of 125VDC MCC 1E Load Impact List, the CW Pump motors affected by a loss of DC MCC 1E are CW Pumps A and C.
Per N-CL-OPS-400006 Circulating Water (CW), upon loss of 125 VDC control power, a power supply for each pump that gets its AC power from the 120 VAC circuit used to feed the exciter heater, will provide a 125 VDC control signal to trip the associated CW pump and close the pump discharge valve. If these DC sources were de-energized, the CW motor would lose excitation power, breaker control power and tripping power. The CW motor would draw a large amount of current acting as an induction motor running at slip speed, (a speed less than synchronous speed) resulting in high motor heating and overcurrent conditions on the respective 6.9 kV Bus.
A is incorrect but plausible if the examinee fails to recall that CW Pump C will also trip on a loss of DC MCC 1E.
B is incorrect but plausible if the examinee fails to recall that CW Pump A will also trip on a loss of DC MCC 1E.
D is incorrect but plausible if the examinee fails to recall that the CW Pumps have an alternate tripping power source in the event of a loss of normal control power to 6900 V Busses 1A and 1B.
KA justification - this question meets the KA because the examinee is required to know the interrelationship between DC MCC 1E and the Circulating Water System.
CPS OPS ILT EXAM Page: 93 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 20 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: 896311 User-Defined ID: CL-ILT-890053 Cross Reference Number:
The plant is at Rated Thermal Power with all 3 Circulating Topic:
Water (CW) Pumps in service. A hard Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 94 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 4201.01 Rev. 7 Revision Number:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - duplicate of CL-LC-Bank, Modified) 0033 Low KA Justification (if NA required):
Revision History: Revision Added distractor plausibility History: (i.e. Modified and KA justification distractor b to make statements.
plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
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: AK2.03 D.C. bus loads (CFR: 41.7 / 45.8)
RO Value: 3.3 SRO Value: 3.3 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 95 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 20 DB420101.01.02 Describe the consequences of the following:
2.1 Loss of DC MCC 1E/1F on Circulating Water Pump operation.
2.2 Loss of DC MCC 1E/1F on Feedwater Level Control.
CPS OPS ILT EXAM Page: 96 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 21 ID: 896312 Points: 1.00 The plant was operating at rated thermal power with Drywell Chiller 'B' operating.
THEN, an inadvertent initiation of the Division 1 Group 11 isolation of the Drywell Cooling (VP) system containment isolation valves occurred.
Drywell Cooling (VP) system valve positions are as follows:
1H13-P801-5050 1H13-P801-5052 CPS OPS ILT EXAM Page: 97 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version What actions, if any, are required to mitigate these conditions?
A. No actions are required.
B. Operate Mixing Compressors as needed.
C. Shift to 'A' train of supplemental drywell cooling.
D. Perform emergency startup of the 'A' DW Chiller.
Answer: B Answer Explanation B is correct Isolation of the Div 1 VP & WO Containment Isolation Valves will result in:
- loss of the WO cooling to the Supplemental DW Cooling Coils When DW cooling is lost, DW pressure and temperature will rise, requiring the Mixing Compressors to be run to maintain DW pressure.
A is incorrect but plausible if the examinee incorrectly believes that a Group 11 isolation will not affect operation of the 'B' Drywell Chiller.
C is incorrect but plausible if the examinee incorrectly recalls that supplemental drywell cooling is available following a Div 1 ESF actuation.
D is incorrect but plausible if the examinee incorrectly believes that the 'A' VP Chiller is available with the Group 11 isolation valves closed. As described above, a Group 11 isolation will result in a trip of the A and B VP Chillers due to loss of the chilled water flow path for each chiller.
KA justification - this question meets the KA because the examinee is required to know the operational implications of an inadvertent Div 1 ESF actuation on the DW cooling system.
CPS OPS ILT EXAM Page: 98 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896312 User-Defined ID: CL-ILT-812594A Cross Reference Number:
The plant was operating at rated thermal power with Drywell Topic:
Chiller 'B' operating. THEN, an inadv Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 99 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 4001.02 Rev. 17a Revision Number:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295020 Inadvertent Containment Isolation Category / KA Statement: AK1. Knowledge of the operational implications of the following concepts as they apply to INADVERTENT CONTAINMENT ISOLATION : AK1.05 Loss of drywell/containment cooling (CFR: 41.8 to 41.10)
RO Value: 3.3 SRO Value: 3.6 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.8 - 41.10 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 100 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 21 223002.08 Given the CRVICS system, DESCRIBE the systems supported and the nature of the support CPS OPS ILT EXAM Page: 101 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 22 ID: 896313 Points: 1.00 A radioactive release is in progress in the Fuel Building.
Fuel Building differential pressure indicates as follows:
Which of the following describes the relationship between the Fuel Building dP indicator and the offsite release?
A. An unfiltered ground level release is in progress.
B. A filtered release is in progress via Standby Gas Treatment System (SGTS).
C. An unfiltered release is in progress. The Fuel Building Ventilation (VF) system is operating normally.
D. An unfiltered release is in progress. The Fuel Building Ventilation (VF) system is in operation, but the VF Exhaust Fans have tripped.
Answer: A Answer Explanation A is correct:
Per N-CL-OPS-290001 Fuel Building HVAC and Secondary Containment (VF), to prevent ground level exfiltration while allowing the Secondary Containment to be designed as a conventional structure, the Secondary Containment requires support systems to maintain the control volume pressure at less than the external pressure during normal and accident conditions. These support systems include:
CPS OPS ILT EXAM Page: 102 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version
- Fuel Building Ventilation
- Secondary Containment Isolation Dampers
- Standby Gas Treatment (SGT) System With Fuel Building differential pressure indicating positive on the meter in the question stem and a radioactive release in progress, an unfiltered ground level release is in progress.
B is incorrect but plausible if the examinee determines that the meter indication is normal with SGTS operating. If SGTS were operating, the meter would indicate a negative pressure.
C is incorrect but plausible if the examinee fails to recall that the Fuel Building Supply Fans trip at 0.0 inches water and that the exhaust fans will trip on low flow or low building differential pressure. If the exhaust fans were running, fuel building differential pressure would be negative.
D is incorrect but plausible if the examinee determines that a Fuel Building Exhaust Fan is operating based on the indications provided in the stem. If the exhaust fans were running, fuel building differential pressure would be negative.
KA justification - this question meets the KA because the examinee is required to determine how the conditions listed in the stem affect off-site release rate during a radioactive release in the Fuel Building.
CPS OPS ILT EXAM Page: 103 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896313 User-Defined ID: CL-ILT-812595A Cross Reference Number:
A radioactive release is in progress in the Fuel Building. Fuel Topic:
Building differential pressure Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 104 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- N-CL-OPS-290001 Revision Number: Rev. 1
- 5042.04 (4D) Rev. 31b
- 5042.05 (5D) Rev. 31
- 3404.01 Rev. 11b Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPR)
KA Data KA Number / System Name: 295035 Secondary Containment High Differential Pressure Category / KA Statement: EK2. Knowledge of the interrelations between SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE and the following: EK2.03 Off-site release rate (CFR: 41.7 / 45.8)
RO Value: 3.3 SRO Value: 4.1 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 105 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 22 290001.16 EVALUATE the following FUEL BUILDING HVAC AND SECONDARY CONTAINMENT indications/responses and DETERMINE if the indication/
response is expected and normal.
.1 VF System Isolation and VG Actuation.
.2 Secondary Containment Diff Press Control.
CPS OPS ILT EXAM Page: 106 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 23 ID: 896314 Points: 1.00 The plant has responded as designed to a Group 1 isolation on high MSL flow.
Complete the following statement.
Under these conditions, the purpose of the Low-Low Set function of the Safety Relief Valves (SRVs) is to...
A. minimize SRV cycles.
B. preserve the accumulator air supply.
C. maintain Reactor pressure within a narrower band.
D. prevent multiple Reactor Protection System (RPS) high level scrams.
Answer: A Answer Explanation A is correct:
Per N-CL-OPS-239001 Main Steam (MS) System, the Low-Low Set (LLS) function reduces the number of SRVs cycling for a given condition.
B is incorrect but plausible - SRV control switches are taken to off if instrument air is lost to the containment to preserve the air accumulators, but this is not the purpose of the low-low set function of the SRVs.
C is incorrect but plausible - the low-low set function maintains RPV pressure in a broader band to minimize SRV cycles. The normal SRV opening and closing setpoints maintain RPV pressure within a ~
100 psig band. The low-low set band is ~ 150 psig.
D is incorrect but plausible - opening an SRV causes RPV water level to swell. CPS 4001.01 Reactor Scram permits expanding the RPV level band to assist in pressure/level coordination efforts if RPV level cannot be maintained between Level 3 and Level 8. This is not, however the purpose of the low-low set function of the SRVs.
KA justification - this question meets the KA because the examinee must have knowledge of the reason for the Low-Low Set (LLS) function of the Safety Relief Valves.
CPS OPS ILT EXAM Page: 107 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 23 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: 896314 User-Defined ID: CL-ILT-812597 Cross Reference Number:
The plant has responded as designed to a Group 1 isolation on Topic:
high MSL flow. Complete the followi Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 108 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- N-CL-OPS-239001 Revision Number: Rev. 3
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1F / 1I)
KA Data KA Number / System Name: 295007 High Reactor Pressure Category / KA Statement: AK3. Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE : AK3.04 Safety/relief valve operation: Plant-Specific (CFR: 41.5 / 45.6)
RO Value: 4.0 SRO Value: 4.1 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 109 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 23 239001.05 Discuss the MAIN STEAM system automatic functions/interlocks including purpose, signals, set points, sensing points, when bypassed, how/when they are.
CPS OPS ILT EXAM Page: 110 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 24 ID: 896315 Points: 1.00 A reactor startup is in progress following a refueling outage.
- Per the Estimated Critical Position, criticality is estimated to occur between steps 4 and 9.
- Operators are withdrawing control rods in step 3.
- The Reactor Engineers have annotated the following control rods in step 3 as "High Notch Worth" control rods: 24-37, 24-21, 40-29, 32-37, 32-21, and 16-29. These rods have been withdrawn to position 24, which completes the move for these two gangs.
Then, when withdrawing the next in-sequence control rod (16-45) in step 3 from position 12 to 14, annunciator 5005-2K SRM Period was received.
SRM A, B, C, AND D Period indicates 25 seconds and is steady.
Which of the following actions is required?
A. Insert control rod 16-45 until the period alarm clears, then continue the startup.
B. Continue with rod withdrawal. Indications are normal at this point in the startup.
C. Initiate an IR to document being outside the expected range of criticality and continue the startup.
D. Insert control rod 16-45 by depressing the IN TIMER SKIP pushbutton until the reactor is subcritical.
Answer: D Answer Explanation D is correct - CPS 3001.01 Preparation For Startup & Approach To Critical, precaution 4.1 and caution before step 8.2.6 states that if excessive rod worths and/or inadvertent criticality occur during rod withdrawal or anytime, immediate conservative operator action is required. This action should include rod insertion using the IN TIMER SKIP button or reactor scram without hesitation.
Since control rod 16-45 is not identified as a high notch worth control rod, the period alarm and period indications provided in the stem are not expected, and the 'A' RO should perform the actions listed above.
A is incorrect but plausible - the examinee may select this response if he/she believes that insertion of 16-45 and continuation of the startup is appropriate with the conditions provided in the stem.
B is incorrect but plausible - transient short period alarms are expected during a startup. The stem states that the period is 25 seconds and stable, so continuing with rod withdrawal is not appropriate.
C is incorrect but plausible - this action is appropriate if criticality is achieved outside the ECP during a non-BOC startup (CPS 2202.04 step 6.2). Since this is a BOC startup, this action in not appropriate.
KA justification - this question meets the KA because the examinee is required to determine required actions during a control rod withdrawal maneuver with the neutron monitoring system indications provided in the stem.
CPS OPS ILT EXAM Page: 111 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 24 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: 896315 User-Defined ID: CL-ILT-888057A Cross Reference Number:
A reactor startup is in progress following a refueling outage.
Topic:
Per the Estimated Critical Posit Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 112 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3001.01 Rev. 25e Revision Number:
- CPS 5005.02 (2K) Rev.
29c
- CPS 2202.04 Rev. 11
- CPS 2202.04F001 Rev.
5 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 295014 Inadvertent Reactivity Addition Category / KA Statement: AA1. Ability to operate and/or monitor the following as they apply to INADVERTENT REACTIVITY ADDITION:
AA1.05 Neutron monitoring system (CFR: 41.7 / 45.6)
RO Value: 3.9 SRO Value: 3.9 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 113 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 24 215004.11 EVALUATE given key Source Range Monitor System parameters, if needed DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
.1 High Alarm
.2 High Trip
.3 Downscale
.4 Inoperative
.5 Retract Not Permitted
.6 Short Period CPS OPS ILT EXAM Page: 114 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 25 ID: 896316 Points: 1.00 The plant was operating at rated thermal power for a prolonged period of time when a station blackout occurred.
4.16 KV Bus 1C1 was reenergized from an Emergency Diesel Generator.
The CRS has directed you to control reactor pressure in accordance with CPS 4200.01 Loss Of AC Power, section 4.4.2 Pressure Control Actions.
Based on the requirements for controlling reactor pressure in the Station Blackout section of CPS 4200.01 Loss of AC Power, which one of the listed SRVs would be your FIRST choice for controlling reactor pressure?
A. F041B B. F041C C. F041G CPS OPS ILT EXAM Page: 115 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version D. F051B Answer: C Answer Explanation C (41G) is correct:
During a Station Blackout, the only available heat sink for rejecting decay heat is the suppression pool, either by SRV lifts or by RCIC operation. This will result in high suppression pool temperature. Pressure control strategies in CPS 4200.01 Loss of AC Power direct operating 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 4200.01 Loss of AC Power, section 4.4.2 Pressure Control Actions, during a SBO RPV pressure is to be stabilized below 1065 psig using SRV's or RCIC. SRVs are to operated as follows:
Use non-ADS SRVs first, followed by ADS SRVs in a manner that:
- precludes uneven suppression pool heating, and
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°).
During a SBO event, the CRS would direct the RO's to maintain RPV pressure within a prescribed pressure band. The RO's would be expected to operate the SRVs per the guidelines provided in CPS 4200.01.
A is incorrect but plausible (41B) - does not meet the location or non-ADS requirement. The examinee may select this choice because it is located away from the RCIC suction and if they incorrectly believe that ADS SRVs should be used first during a SBO.
B is incorrect but plausible (41C) - meets the location requirement but is an ADS SRV.
D is incorrect but plausible - meets the non-ADS requirement but is located near the HPCS Pump suction.
KA justification - this question meets the KA because the examinee has to determine the correct SRV opening sequence to use during a SBO condition to prevent localized heating of the suppression pool.
CPS OPS ILT EXAM Page: 116 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 25 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: 896316 User-Defined ID: CL-ILT-888091A Cross Reference Number:
The plant was operating at rated thermal power for a prolonged Topic:
period of time when a station black Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 117 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 4200.01 Rev. 23a Revision Number:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. CPS 3101.01 Figure 1 -
Ensure ON-## not provided) note below the figure provides clues to Q3 (CL-ILT-887888)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPR)
KA Data KA Number / System Name: 295013 High Suppression Pool Water Temperature Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE:
AA2.02 Localized heating/stratification (CFR: 41.10 / 43.5 /
45.13)
RO Value: 3.2 SRO Value: 3.5 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: 118 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 25 (420001.01) respond to a Total Loss of AC Power CPS OPS ILT EXAM Page: 119 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 26 ID: 896317 Points: 1.00 A loss of coolant accident (LOCA) is in progress.
Which of the following parameters would require entry into EOP-6 Primary Containment Control?
A. RPV water level below Level 3 B. Suppression Pool level at 19'0" C. Containment H2 concentration at 0.6%
D. Any floor drain sump above max normal Answer: C Answer Explanation C is correct:
Per CPS 4402.01 Primary Containment Control, containment or drywell hydrogen above 0.5% requires entry into EOP-6.
A is incorrect but plausible - Low water level is an EOP-1 entry condition but is not an entry parameter for EOP-6 Primary Containment Control.
B is incorrect but plausible - SP Level at 19'0" is above the low level entry condition and below the high level entry condition for EOP-6 (19'5").
D is incorrect but plausible - Any floor drain sump above max normal is an EOP-8 entry. It is plausible because a loss of coolant accident is in progress.
KA justification - this question meets the KA because the examinee must be able to recognize the EOP-6 entry conditions that required execution of the hydrogen control leg of EOP-6.
CPS OPS ILT EXAM Page: 120 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896317 User-Defined ID: CL-ILT-812600 Cross Reference Number:
A loss of coolant accident (LOCA) is in progress. Which of the Topic:
following parameters would require Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 121 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 4402.01 Rev. 29 Revision Number:
- EOP-TB (pg. 8-4) Rev.
6 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 500000 High Containment Hydrogen Concentration 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. (CFR: 41.10 / 43.2 / 45.6)
RO Value: 4.5 SRO Value: 4.7 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.2 CPS OPS ILT EXAM Page: 122 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 26 LP87558.01.01 From memory, state the plant conditions which require entry/reentry to EOP-6.
CPS OPS ILT EXAM Page: 123 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 27 ID: 896318 Points: 1.00 The plant has been scrammed due to a reactor coolant system leak.
Current plant parameters and trends are as follows:
Parameter Value Trend DW Temperature 100 degrees Rising at 2 degrees / minute Cnmt Temperature 89 degrees Rising at 5 degrees / minute DW Pressure 0.75 psig Rising at 0.1 psig / minute Cnmt Pressure 0.1 psig Rising at 0.1 psig / minute If current trends continue, which of the following parameters will result in the EARLIEST entry into EOP-6?
A. DW Pressure B. Cnmt Pressure C. DW Temperature D. Cnmt Temperature Answer: D Answer Explanation D is correct:
Per the EOP Tech Bases, the Primary Containment Control entry conditions are symptomatic of an emergency or a condition that could become an emergency. The specified parameters are the same as the key parameters controlled by the procedure. The specified setpoints have been chosen to be operationally significant, unambiguous, readily identifiable, and familiar to plant operators. In general, they are also setpoints for scrams, alarms, trips, ECCS initiation, or Technical Specification limits. These action levels provide advance warning of potential emergency conditions, allowing action to be taken sufficiently early to prevent more severe consequences.
The EOP-6 entry conditions for the parameters in the stem are as follows:
- DW temperature - 150 degrees
- Cnmt temperature - 122 degrees
- DW Pressure - 1.68 psig
- Cnmt Pressure - not an EOP-6 entry condition Calculations are as follows:
Parameter Current Value EOP-6 Entry Difference Rate (per min) Time to entry Value (minutes)
DW Temp 100 150 50 2 25 Cnmt Temp 89 122 33 5 6.6 DW Press 0.75 1.68 0.93 0.1 9.3 Therefore, EOP-6 entry is required on high containment temperature in 6.6 minutes.
CPS OPS ILT EXAM Page: 124 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version A is incorrect but plausible if the examinee incorrectly calculates the time required to reach the EOP entry conditions for the parameters listed above and determines that DW pressure will exceed the EOP-6 entry condition limit first.
B is incorrect but plausible - containment pressure is monitored by EOP-6 but is not an entry parameter.
D is incorrect but plausible if the examinee incorrectly calculates the time required to reach the EOP entry conditions for the parameters listed above and determines that DW temperature will exceed the EOP-6 entry condition limit first.
KA justification - this question meets the KA because the examinee is required to assess the parameters listed in the stem and then determine when EOP-6 Primary Containment Control is required to be entered to mitigate the challenge to the Containment safety function.
CPS OPS ILT EXAM Page: 125 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896318 User-Defined ID: CL-ILT-812601A Cross Reference Number:
The plant has been scrammed due to a reactor coolant system Topic:
leak. Current plant parameters and Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 126 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with 4402.01 Rev. 29 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 295011 High Containment Temperature (Mark III Containment Only)
Category / KA Statement: 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7 /
43.5 / 45.12)
RO Value: 4.0 SRO Value: 4.6 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 127 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 27 LP87558.01.01 From memory, state the plant conditions which require entry/reentry to EOP-6.
CPS OPS ILT EXAM Page: 128 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 28 ID: 896319 Points: 1.00 The plant is operating at rated thermal power with the following conditions:
- Component Cooling Water (CCW) Header Pressure is operating at the low end of the normal pressure range in accordance with CPS 3203.01 Component Cooling Water (CC).
- Plant Service Water (WS) Header Pressure is being maintained at the high end of the normal pressure range in accordance with CPS 3212.01 Plant Service Water (WS).
- Turbine Building Closed Cooling Water Header Pressure is 83 psig.
If the WT and CC Heat Exchangers were to develop a tube leak, in which direction would the leakage occur?
A. WT into WS CC into WS B. WT into WS WS into CC C. WS into WT CC into WS D. WS into WT WS into CC Answer: D Answer Explanation D is correct:
The CC and WT systems are cooled by the WS system via CC and WT system heat exchangers. WS flows through the tubes of each. The tubes of the system heat exchangers act as a barrier to prevent the potentially contaminated fluid from having a direct flowpath to the environment.
- CPS 3212.01 section 8.1.1 System Startup requires WS header pressure to be maintained between 100 - 130 psig during normal system operation.
- CPS 3203.01 section 8.1.10 Adjusting CCW Header Pressure requires CCW header pressure to be maintained above 90 psig.
With WS pressure at 130 psig, CCW at 90 psig, and WT at 83 psig, WS will flow into the CCW and WT systems if a tube leak develops in the associated heat exchanger.
A is incorrect but plausible if the examinee incorrectly believes that CC and WT normally operate at higher pressure than WS.
B is incorrect but plausible if the examinee incorrectly believes that WT normally operates at higher pressure than WS.
C is incorrect but plausible - incorrectly believes that CC normally operates at higher pressure than WS.
KA justification - this question meets the KA because the examinee must be knowledgeable of the physical connections and the effect of WS to CC/WT heat exchanger tube leaks to answer correctly.
CPS OPS ILT EXAM Page: 129 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 28 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: 896319 User-Defined ID: CL-ILT-812602 Cross Reference Number:
The plant is operating at rated thermal power with the following Topic:
conditions: Component Cooling Wa Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 130 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3212.01 Rev. 31 Revision Number:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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 Category / KA Statement: K1. Knowledge of the physical connections and / or cause-effect relationships between CCWS and the following: K1.01 Service water system (CFR:
41.2 to 41.9 / 45.7 to 45.8)
RO Value: 3.2 SRO Value: 3.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.2 to 41.9 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 131 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 28 400005.08 Given the PLANT SERVICE WATER system, DESCRIBE the systems supported and the nature of the support.
CPS OPS ILT EXAM Page: 132 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 29 ID: 896320 Points: 1.00 Complete the following statement concerning the IRM detectors.
IRM detectors are located in _____(1)______. During normal full power operations, detectors are
_____(2)_____ the core.
A. (1) dry tubes (2) inserted in B. (1) wet tubes (2) inserted in C. (1) dry tubes (2) withdrawn from D. (1) wet tubes (2) withdrawn from Answer: C Answer Explanation C is correct:
Per N-CL-OPS-215003, the IRM detectors are housed within a dry tube mated with the reactor vessel and extending vertically into the reactor core.
Per N-CL-OPS-215003 and CPS 3002.01 Heatup and Pressurization, the IRMs are withdrawn from the core during a reactor startup after the mode switch is placed in Run.
A is incorrect but plausible if the examinee believes that the IRMs remain inserted in the core (like the LPRMs).
B is incorrect but plausible if the examinee believes the IRMs are housed in wet tubes for cooling or for neutron moderation purposes and that the IRMs remain inserted in the core (like the LPRMs). The examinee may select this response because the LPRM and TIP tubes are housed within an instrument tube that has holes drilled through the tube wall, along its length, allowing reactor coolant to cool the detectors.
D is incorrect but plausible if the examinee believes the IRMs are housed in wet tubes for cooling or for neutron moderation purposes. The examinee may select this response because the LPRM and TIP tubes are housed within an instrument tube that has holes drilled through the tube wall, along its length, allowing reactor coolant to cool the detectors.
KA justification - this question meets the KA because the examinee must have knowledge of the physical connections of the IRMs and the reactor vessel in order to answer correctly.
CPS OPS ILT EXAM Page: 133 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896320 User-Defined ID: CL-ILT-812603 Cross Reference Number:
Complete the following statement concerning the IRM Topic:
detectors. IRM detectors are located in _____
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 134 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3002.01 Rev. 30 Revision Number:
- N-CL-OPS-215003 Rev. 1 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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 System Category / KA Statement: K1. Knowledge of the physical connections and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following: K1.07 Reactor vessel (CFR: 41.2 to 41.9 / 45.7 to 45.8)
RO Value: 3.0 SRO Value: 3.0 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.2 to 41.9 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 135 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 29 215003.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following IRM System components.
.1 Detectors (1C51N002A through H)
.2 Detector Drive Mechanisms (1C51S001E through M)
.3 Voltage Preamplifiers (1C51K002A through H)
.4 Equipment Drawers (1C51K601A through H)
.5 Range Switches (1C51Z8A through D, S1 through S4)
.6 Recorders (1C51R603A, B, C, &
D)
.7 Digital Control System (DCS)
Displays CPS OPS ILT EXAM Page: 136 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 30 ID: 896321 Points: 1.00 Which of the following statements is correct concerning the impact of a loss of power to the Div 3 NSPS Distribution Panel?
High Pressure Core Spray (HPCS)...
A. will NOT automatically initiate.
B. can be manually initiated using the HPCS Manual Initiation pushbutton.
C. will automatically initiate as long as Div 4 NSPS Distribution Panel remains energized.
D. can NOT be initiated by using the pump control switch to manually start the HPCS Pump.
Answer: A Answer Explanation A is correct:
Per CPS 3509.01C003 Division 3 NSPS Bus (1C71-P001C) Outage, opening CB-7 on the Div 3 NSPS Distribution Panel will result in a loss of power to the HPCS automatic and manual initiation logic, ATMs, and transmitters - fails in the non-tripped condition.
Per CPS 3309.01 High Pressure Core Spray section 8.1.4 Manual Initiation - Logic NOT Operable, HPCS is manually initiated by starting the HPCS Pump and opening 1E22-F004.
B is incorrect but plausible if the examinee fails to recall that the HPCS manual initiation pushbutton receives power from Div 3 NSPS.
C is incorrect but plausible if the examinee fails to recall that the initiation logic requires signals from transmitters powered from Div 3 and Div 4 NSPS.
D is incorrect but plausible if the examinee believes that a loss of Div 3 NSPS prevents the HPCS Pump from being manually operated from its respective control switch on 1H13-P601.
KA justification - this question meets the KA because the examinee is required to determine how a loss of Div 3 NSPS power affects HPCS initiation logic.
CPS OPS ILT EXAM Page: 137 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 30 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: 896321 User-Defined ID: CL-ILT-812604A Cross Reference Number:
Which of the following statements is correct concerning the Topic:
impact of a loss of power to the Div 3 Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 138 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3509.01C003 Revision Number: Rev. 9e
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 209002 High Pressure Core Spray System Category / KA Statement: K2. Knowledge of electrical power supplies to the following: K2.03 Initiation logic: BWR-5,6 (CFR: 41.7)
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 CPS OPS ILT EXAM Page: 139 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 30 209002.07 Given the HIGH PRESSURE CORE SPRAY system, DESCRIBE the systems supporting and the nature of the support.
CPS OPS ILT EXAM Page: 140 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 31 ID: 896322 Points: 1.00 The Reactor Protection System (RPS) Analog Trip Modules (ATMs) in 1H13-P661, P662, P663, and P664 are normally powered from the...
A. RPS distribution panels from inverted DC.
B. NSPS distribution panels from inverted DC.
C. RPS distribution panels from rectified and inverted AC.
D. NSPS distribution panels from rectified and inverted AC.
Answer: B Answer Explanation B is correct:
Per N-CL-OPS-212000 Reactor Protection System and Alternate Rod Insertion, the four NSPS power supplies provide instrumentation and logic power to RPS. Division 1, 2, 3, and 4 NSPS inverters supply power to RPS Logic Channels A, B, C, and D respectively.
Per N-CL-OPS-700004 Nuclear System Protection System, the NSPS Divisional Power loads are supplied from a 125 VDC power supply through an inverter where it is converted to a 60 Hz, 120 VAC supply.
A is incorrect but plausible if the examinee incorrectly believes the RPS ATMs are powered from the RPS distribution panels and also incorrectly recalls that the normal power supply to RPS is from rectified and inverted AC.
C is incorrect but plausible if the examinee incorrectly believes the RPS ATMs are powered from the RPS distribution panels.
D is incorrect but plausible if the examinee incorrectly recalls the normal power supply flowpath to the NSPS distribution panels (DC through an inverter to the distribution panel).
KA justification - this question meets the KA because the examinee must have knowledge of the electrical power supply to the RPS ATMs to answer correctly.
CPS OPS ILT EXAM Page: 141 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 31 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: 896322 User-Defined ID: CL-ILT-812605 Cross Reference Number:
The Reactor Protection System (RPS) Analog Trip Modules Topic:
(ATMs) in 1H13-P661, P662, P663, and P664 Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 142 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- N-CL-OPS-212000 Revision Number: Rev. 1
- N-CL-OPS-700004 Rev. 5 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 212000 Reactor Protection System Category / KA Statement: K2. Knowledge of electrical power supplies to the following: K2.02 Analog trip system logic cabinets (CFR: 41.7)
RO Value: 2.7 SRO Value: 2.9 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 143 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 31 700004.03 DESCRIBE the function, operation, interlocks, trips, physical location, and power supplies of the following NSPS System components.
.1 NSPS Divisional Power Inverter
.2 NSPS Divisional Power Step-Down Transformer
.3 NSPS Solenoid Bus Inverter
.4 NSPS Solenoid Bus Power Monitor
.5 NSPS Solenoid Bus Step-Down Transformer
.6 Analog Trip Module
.7 Analog Trip System Display and Control Module
.8 Analog Trip System Card Select Decoder
.9 Self Test System
.10 Self Test Diagnostic Terminal
.11 Self Test Controller
.12 Self Test Card Select Monitor
.13 Self Test Power Supply Monitor CPS OPS ILT EXAM Page: 144 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 32 ID: 896323 Points: 1.00 Which of the following methods can be used to depressurize the reactor with a loss of Div 1 DC power?
A. Any of the SRVs can be opened using the keylock switches on 1H13-P601.
B. Any of the SRVs can be opened using the keylock switches on 1H13-P642.
C. ONLY ADS SRVs can be opened using the keylock switches on 1H13-P601.
D. ONLY ADS SRVs can be opened using the keylock switches on 1H13-P642.
Answer: B Answer Explanation B is correct:
Per CPS 4201.01C001, a loss of DC MCC 1A will result in a loss of power to the 'A' SRV solenoids (ADS and non-ADS), preventing operation from 1H13-P601.
Per N-CL-OPS-239001, Control room handswitches for the SRVs are on panels 1H13-P601and 1H13-P642.
A is incorrect but plausible if the examinee incorrectly recalls the SRV keylock switches on P601 energize the 'A' solenoids which are powered from DC MCC 1A.
C is incorrect but plausible if the examinee incorrectly recalls the ADS SRV keylock switches on P601 energize the 'A' solenoids which are powered from DC MCC 1A.
D is incorrect but plausible if the examinee incorrectly believes that the non-ADS SRVs cannot be operated from P642 during a loss of DC MCC 1A.
KA justification - this question meets the KA because the examinee must determine the impact of a loss of DC power on the ability to rapidly depressurize the reactor.
CPS OPS ILT EXAM Page: 145 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 32 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: 896323 User-Defined ID: CL-ILT-812606A Cross Reference Number:
Which of the following methods can be used to depressurize Topic:
the reactor with a loss of Div 1 DC pow Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 146 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- N-CL-OPS-239000 Revision Number: Rev. 3
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 239002 Safety Relief Valves Category / KA Statement: K3. Knowledge of the effect that a loss or malfunction of the RELIEF/SAFETY VALVES will have on following: K3.03 Ability to rapidly depressurize the reactor (CFR: 41.7 / 45.4)
RO Value: 4.3 SRO Value: 4.4 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 147 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 32 239001.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following MAIN STEAM System components.
.1 System Piping
.2 Safety/Relief Valves and Piping
.3 SRV Acoustic Monitoring System
.4 Main Steam Line Flow Restrictor
.5 Main Steam Isolation Valves
.6 Guard Pipes
.7 Main Steam Line Radiation Monitors
.8 Main Steam Shutoff Valves
.9 Pressure/Flow Equalizing Header
.10 Steam Bypass Valves
.11 Main Steam Line Drain and Vent Valves
.12 Main Steam to Auxiliary Steam System Valve and Control Valve
.13 Crossaround Steam to Auxiliary Steam System Valve and Control Valve CPS OPS ILT EXAM Page: 148 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 33 ID: 896324 Points: 1.00 Assuming no other failures/conditions exist, answer the following:
(1) Would a failure of the RCIC Flow Controller to operate in automatic PREVENT operating the Reactor Core Isolation Cooling (RCIC) system in pressure control mode?
(2) Would Annunciator 5063-3E Suppression Pool Water Level High (Suppression Pool Level indicates 19' 11.5") being locked in require defeating interlocks prior to operating the RCIC system in pressure control mode?
A. (1) NO (2) NO B. (1) NO (2) YES C. (1) YES (2) NO D. (1) YES (2) YES Answer: B Answer Explanation B is correct:
Per CPS 4411.09 RPV Pressure Control Sources, Appendix A and CPS 3310.01 Reactor Core Isolation Cooling, in pressure control mode RCIC is started to establish a flowpath from tank to tank via 1E22-F022 and F059 using manual control of the flow controller 1E51-R600 to control turbine speed.
Per 5063-1E, a high suppression pool water level will cause 1E51-F022 and F059 RCIC Pmp First (Second) Test Valve to Stor Tank to automatically close, preventing operation in tank to tank mode.
A is incorrect but plausible if the examinee fails to recall that suppression pool high level causes 1E51-F022 and 59 to automatically close.
C is incorrect but plausible if the examinee fails to recall that RCIC speed is controlled manually in pressure control mode and that suppression pool high level causes 1E51-F022 and 59 to automatically close.
D is incorrect but plausible if the examinee fails to recall that RCIC speed is controlled manually in pressure control mode.
KA justification - this question meets the KA because the examinee has to recall the RCIC alignment for pressure control mode and then determine how the conditions provided in the stem impact that alignment.
CPS OPS ILT EXAM Page: 149 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 33 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: 896324 User-Defined ID: CL-ILT-812607 Cross Reference Number:
Assuming no other failures/conditions exist, answer the Topic:
following: (1) Would a failure of the RCI Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 150 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 5063.03 (3E) Rev. 33c Revision Number:
- CPS 4411.09 Rev. 6
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 217000 Reactor Core Isolation Cooling System Category / KA Statement: K3. Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will have on following: K3.02 Reactor vessel pressure (CFR: 41.7 / 45.4)
RO Value: 3.6 SRO Value: 3.6 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 151 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 33 217000.02 DESCRIBE the major flowpaths for the following modes of the REACTOR CORE ISOLATION COOLING System operation.
.1 Normal Standby Lineup (Figure 1)
.2 Steam Supply and Exhaust (Figure 2)
.3 Injection into the Reactor vessel (Figure 3)
.4 Tank to Tank (Figure 4)
.5 Water Leg Pump Operability Test (Figure 5)
.6 Lube Oil Cooler cooling water (Figure 3)
CPS OPS ILT EXAM Page: 152 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 34 ID: 896325 Points: 1.00 In the simplified NSSS logic diagram below, which parameter / sensors are being described?
A. Main Steam Line Flow B. Main Condenser Vacuum C. Main Steam Line Pressure D. Reactor Pressure Vessel Level Answer: C Answer Explanation C is correct:
The Group 1 isolation signals are as follows:
- RPV Level 1
- MSL Low Pressure
- MSL High Flow
- Low Main Condenser Vacuum
- MSL Tunnel High Temperature
- MSL Turbine Building High Temperature Of the isolation signals listed, the only one that is bypassed when the Reactor Mode Switch is in any position other than run is MSL Low Pressure.
A is incorrect but plausible - High MSL flow is a group 1 isolation signal, but is not bypassed when the Reactor Mode Switch is in any position other than run.
B is incorrect but plausible - Low Main Condenser Vacuum is a group 1 isolation signal, but is not bypassed when the Reactor Mode Switch is in any position other than run.
D is incorrect but plausible - Low RPV Level is a group 1 isolation signal, but is not bypassed when the Reactor Mode Switch is in any position other than run.
CPS OPS ILT EXAM Page: 153 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version KA justification - this question meets the KA because the examinee must be knowledgeable of the fact that the MSL Low Pressure Group 1 CRVICS isolation signal is automatically bypassed with the RMS in any position other than Run.
CPS OPS ILT EXAM Page: 154 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 34 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: 896325 User-Defined ID: CL-ILT-812608 Cross Reference Number:
In the simplified NSSS logic diagram below, which parameter /
Topic:
sensors are being described?
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 155 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5066.02 (2D) Rev.
Revision Number: 25a
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-DR)
KA Data KA Number / System Name: 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off Category / KA Statement: K4. Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF design feature(s) and/or interlocks which provide for the following: K4.04 Automatic bypassing of selected isolations during specified plant conditions (CFR: 41.7)
RO Value: 3.2 SRO Value: 3.6 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 156 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 34 239001.05 Discuss the MAIN STEAM system automatic functions/interlocks including purpose, signals, set points, sensing points, when bypassed, how/when they are.
CPS OPS ILT EXAM Page: 157 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 35 ID: 896326 Points: 1.00 The Automatic Depressurization System (ADS) has actuated.
Which of the following graphics show the initiation signal CLEAR and ready to be reset?
(Note - only those lights that are illuminated are labelled as "ON").
A.
CPS OPS ILT EXAM Page: 158 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version B.
C.
CPS OPS ILT EXAM Page: 159 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version D.
Answer: D Answer Explanation D is correct - When the ADS logic is actuated, the red lights for ADS A/E/B/F illuminate. When the initiation signal is clear and ready to reset, the white lights illuminate. The white and red lights extinguish when the seal-in reset pushbuttons are depressed.
A is incorrect but plausible if the examinee believes the red and white lights extinguish when the initiation signal is clear.
B is incorrect but plausible if the examinee believes the red lights extinguish and the white lights illuminate when the initiation signal is clear.
C is incorrect but plausible if the examinee believes the red lights illuminate and the white lights extinguish when the initiation signal is clear.
KA justification - this question meets the KA because the examinee must have knowledge of the ADS indications present when the initiation signal is clear and ready to be reset.
CPS OPS ILT EXAM Page: 160 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896326 User-Defined ID: CL-ILT-812609 Cross Reference Number:
The Automatic Depressurization System (ADS) has actuated.
Topic:
Which of the following graphics show th Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 161 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with N-CL-OPS-218000 Rev. 2 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 218000 Automatic Depressurization System Category / KA Statement: K4. Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature(s) and/or interlocks which provide for the following:
K4.03 ADS logic control (CFR: 41.7)
RO Value: 3.8 SRO Value: 4.0 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 162 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 35 218000.04 STATE the physical location and function of the following AUTOMATIC DEPRESSURIZATION (ADS) system components, controls, indicators, and/or sensors.
.1 Valve controls
.2 Actuation inhibit controls
.3 Manual initiation controls
.4 Manual ADS reset controls CPS OPS ILT EXAM Page: 163 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 36 ID: 896327 Points: 1.00 The plant was operating at rated thermal power with CPS 9052.01 LPCS Pump Operability Test in progress.
The LPCS Pump was running with 1E21-F012 LPCS Test Valve To Suppr Pool throttled open.
Then, a LOCA occurred inside the Drywell, raising DW pressure above the LPCS initiation setpoint.
Which of the following correctly describes the LPCS system response to these conditions?
Valve Number Description 1E21-F012 LPCS Test Valve to Suppr Pool 1E21-F005 LPCS to CNMT Outbd Isol Valve 1E21-F011 LPCS Pump Min Flow Recirc Valve A.
- 1E21-F012 will CLOSE.
- 1E21-F011 will REMAIN CLOSED.
B.
- 1E21-F012 will CLOSE.
- 1E21-F011 will OPEN.
C.
- 1E21-F012 will REMAIN OPEN.
- 1E21-F011 will REMAIN CLOSED.
- Annunciator 5063-6H LPCS Injection Valve in Manual Override will be received.
D.
- 1E21-F012 will REMAIN OPEN.
- 1E21-F011 will REMAIN CLOSED.
Answer: B Answer Explanation B is correct:
Per 9080.21 Diesel Generator 1A - ECCS Integrated, section 8.2 ECCS Initiation - DG 1A Start verifies that LPCS system response to an ECCS initiation with the system not configured in a standby lineup.
During the test, 1E21-F012 is opened, LPCS is manually initiated, and 1E21-F012 is verified to automatically close.
Per 3313.01 Appendix A: LPCS Initiation/Shutdown Hard Card, 1E21-F005 is verified to open when RPV pressure is < 472 psig.
Per 3313.01 section 8.1.7, 1E21-F011 opens whenever LPCS flow is < 875 gpm, and shuts whenever LPCS flow is 875 gpm.
A is incorrect but plausible if the examinee believes that a LPCS initiation signal provides an isolation signal to the LPCS Min Flow Valve. A Group 11 isolation signal will cause the 1E21-F012 to close.
CPS OPS ILT EXAM Page: 164 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version C is incorrect but plausible if the examinee fails to recall that 1E21-F012 will automatically close on an initiation signal and confuses override annunciators received when the RHR full flow test valves are opened with LPCI initiation signals present.
D is incorrect but plausible if the examinee incorrectly believes that the 472 psig interlock must be met before 1E21-F012 will close. The injection valve permissive affects 1E21-F005 only.
KA justification - this question meets the KA because the examinee must be knowledgeable of the impact of a LPCS initiation signal on the LPCS system during surveillance testing.
CPS OPS ILT EXAM Page: 165 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 36 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: 896327 User-Defined ID: CL-ILT-812610 Cross Reference Number:
The plant was operating at rated thermal power with CPS Topic:
9052.01 LPCS Pump Operability Test in prog Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 166 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3313.01 Rev. 16b Revision Number:
Question History: (i.e. LGS Modelled from 1999 DAEC NRC-05, OYS CERT-04) NRC exam Q42 Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised to apply to CPS History: (i.e. Modified system valve numbers and distractor b to make setpoints.
plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 209001 Low Pressure Core Spray System Category / KA Statement: K4. Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design feature(s) and/or interlocks which provide for the following:
K4.10 Testability of all operable components (CFR: 41.7)
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 CPS OPS ILT EXAM Page: 167 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 36 209001.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following LPCS System components.
.1 LPCS Suction Strainer
.2 LPCS Pump
.3 LPCS/RHR A Water Leg Pump
.4 LPCS Spray Sparger
.5 LPCS Pump Suction Valve
.6. LPCS PUMP Min Flow Valve
.7 LPCS Pump Suppression Pool Test Return Valve
.8 LPCS Injection Valve
.9 LPCS Testable Check Valve
.10 LPCS Manual Shutoff Valve
.11 LPCS Pump Room Cooler
.12 LPCS System Initiation Logic Power Supply CPS OPS ILT EXAM Page: 168 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 37 ID: 896328 Points: 1.00 While operating at 55% power, annunciators 5005-2L LPRM UPSC AND 5005-3L LPRM DNSC were received numerous times on LPRM 30-31C.
The asterisked LPRMs in the table below are currently bypassed.
Div 1 APRM Channel A LPRM Detectors06-23A 06-15B* 14-15C 14-07D 06-39A 06-31B 14-31C
- 14-23D 22-07A
- 22-15B
22-39A
- 38-15B
- 30-47C 30-39D
- 46-23D 38-39A
- 47-47C
- Which of the following describes the impact of bypassing LPRM 30-31C on:
(1) the APRM Inop Circuit (2) Core Thermal Power calculation A. (1) tripped (2) no impact B. (1) tripped (2) indicates lower C. (1) NOT tripped (2) no impact D. (1) NOT tripped (2) indicates lower Answer: C Answer Explanation C is correct:
Per 5004-1H APRM A UPSC TRIP OR INOP, an APRM inop trip is generated when < 16 LPRM Inputs are available to the channel. With 30-31C bypassed, 17 LPRM inputs remain so an inop trip will NOT be generated.
Per CPS 2208.01 & 2208.01F001 Core Thermal Power Determination, parameters that are used to determine core thermal power include:
- Reactor Pressure
- Feedwater Flow
- RWCU Flow
- CRD Flow
- Feedwater Temperature
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version
- RWCU Outlet Temperature Thermal power is obtained by performing an energy balance on the reactor system and is not affected by LPRM inputs.
A is incorrect but plausible if the examinee incorrectly believes an APRM inop trip is generated with 17 LPRM inputs.
B is incorrect but plausible if the examinee incorrectly believes an APRM inop trip is generated with 17 LPRM inputs and that CTP calculation is affected by LPRM readings.
D is incorrect but plausible B is incorrect but plausible if the examinee incorrectly believes that CTP calculation is affected by LPRM readings.
KA justification - this question meets the KA because the examinee must have knowledge of the impact of bypassing an LPRM on CTP calculation and APRM inop trip circuits to answer correctly.
CPS OPS ILT EXAM Page: 170 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 37 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: 896328 User-Defined ID: CL-ILT-812611A Cross Reference Number:
While operating at 55% power, annunciators 5005-2L LPRM Topic:
UPSC AND 5005-3L LPRM DNSC were received n Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 171 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5004.01(1H) Rev.
Revision Number: 28
- CPS 2208.01 Rev. 11a
- CPS 2208.01F001 Rev.
8
- N-CL-OPS-215005 Rev. 1 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 215005 Average Power Range Monitor/Local Power Range Monitor Category / KA Statement: K5. Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM : K5.01 LPRM detector operation (CFR: 41.5 / 45.3)
RO Value: 2.8 SRO Value: 2.9 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 172 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 37 215005.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following AVERAGE POWER RANGE MONITOR System components.
.1 Local Power Range Monitor (LPRM) Detector
.2 LPRM High Voltage Power Supply
.3 LPRM Card
.4 LPRM Multiplexer
.5 LPRM Count Circuit
.6 APRM Averaging Amplifier
.7 APRM Meter
.8 APRM Meter Function Switch
.9 APRM Inop Circuit
.10 APRM Flow Channel
.11 APRM Trip Reference Card
.12 Reactor Mode Switch
.13 NSPS Sensor Bypass Switches CPS OPS ILT EXAM Page: 173 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 38 ID: 896329 Points: 1.00 How will a loss of Div 1 DC impact the following equipment?
(1) 'A' RPS Inverter (2) Div 1 NSPS Inverter A. (1) no impact (2) no impact B. (1) no impact (2) transfers to alternate power source C. (1) transfers to alternate power source (2) no impact D. (1) transfers to alternate power source (2) transfers to alternate power source Answer: B Answer Explanation B is correct:
Per CPS 5002.04 (4N) NSPS INV SOURCE XFR ALT SOURCE is received whenever a divisional NSPS Inverter solid state transfer switch (SSTS) has transferred to it's alternate power source. For Div 1 NSPS, the alternate power source is CB MCC E2 (safety related AC) and its primary power source comes from DC MCC 1A.
Per CPS 3509.01 Instrument Power System, discussion step 2.1.5 and Figure 4 states that the normal power source for the RPS Distribution Panels comes from the battery charger supply (CB MCC A). If the normal AC power source is lost, DC power is supplied to the RPS Inverter from DC MCC 1E. A loss of Div 1 DC would therefore have no effect on the 'A' RPS Inverter.
A is incorrect but plausible if the examinee believes that Div 1 NSPS Inverter is normally powered from it's AC power source (like the RPS inverters are).
C is incorrect but plausible if the examinee believes that the A RPS inverter is normally powered from DC MCC 1A. The inverter is normally powered from CB MCC A.
D is incorrect but plausible if the examinee believes both Inverters are normally powered from DC MCC 1A. As explained above, the 'A' RPS inverter is normally powered from CB MCC A.
KA justification - this question meets the KA because the examinee must determine the impact of a loss of DC electrical power on the NSPS and RPS inverters to answer the question.
CPS OPS ILT EXAM Page: 174 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 38 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: 896329 User-Defined ID: CL-ILT-812612 Cross Reference Number:
How will a loss of Div 1 DC impact the following equipment?
Topic:
(1) 'A' RPS Inverter (2) Div 1 NSPS I Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 175 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3509.01 Rev. 20d Revision Number:
- CPS 5002.04 (4N) Rev.
33b Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) history Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 262002 Uninterruptable Power Supply (A.C. /D.C.)
Category / KA Statement: K6. Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) : K6.02 D.C. electrical power (CFR: 41.7 / 45.7)
RO Value: 2.8 SRO Value: 3.1 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 176 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 38 263000.08 Given the BATTERY & DC DISTRIBUTION system, DESCRIBE the systems supported and the nature of the support.
.1 Nuclear System Protection System (NSPS)
.2 Reactor Core Isolation Cooling System (RCIC)
.3 Auxiliary Power System
.4 Remote Shutdown System
.5 Turbine Lube Oil System
.6 Seal Oil System
.7 Diesel Generator System
.8 Main Steam System
.9 Switchyard System CPS OPS ILT EXAM Page: 177 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 39 ID: 896330 Points: 1.00 The plant was operating at rated thermal power when a LOCA AND Loss of Offsite Power (LOOP) occurred.
Div 1, 2, and 3 DGs responded as designed.
Which of the following describes the status of Battery Chargers 1A, 1B, 1C, 1D, 1E and 1F 30 seconds after the event occurred?
Battery Chargers 1A, 1B, 1C, Battery Chargers 1E & 1F 1D Alignment 1 In-service Deenergized - can NOT be restored Alignment 2 Load shed - automatically restored by Load shed - automatically restored by load sequencing load sequencing Alignment 3 In-service In-service Alignment 4 Load shed - automatically restored by Load shed - can be manually restored load sequencing A. Alignment 1 B. Alignment 2 C. Alignment 3 D. Alignment 4 Answer: A Answer Explanation A is correct:
A loss of off-site power will result in deenergization of the non-safety related battery chargers which cannot be restored until off-site power is restored.
During a LOOP/LOCA event, Divisional AC power will be lost to the divisional battery chargers until 4.16 KV Busses 1A/1B/1C are reenergized by their associated DG. The battery chargers are not load shed and sequenced back onto the bus.
B is incorrect but plausible if the examinee believes that the divisional and non-divisional battery chargers are load shed and resequenced onto the bus similar to the Divisional ECCS pumps. The non-divisional battery chargers are powered from non-divisional 480V AC which is deenergized during a LOOP/LOCA.
C is incorrect but plausible if the examinee believes that the non-divisional battery chargers (E & F) are powered from the divisional AC buses and that they remain in service after the DGs restore the divisional AC buses.
D is incorrect but plausible if the examinee believes that the divisional and non-divisional battery chargers are load shed during a LOOP/LOCA event and that the non-divisional battery chargers (E & F) can be manually restored during a LOOP/LOCA event.
CPS OPS ILT EXAM Page: 178 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version KA justification - this question meets the KA because the examinee must determine the impact of a loss of off-site power on the safety and non-safety related battery chargers to answer the question.
CPS OPS ILT EXAM Page: 179 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896330 User-Defined ID: CL-ILT-812613A Cross Reference Number:
The plant was operating at rated thermal power when a LOCA Topic:
AND Loss of Offsite Power (LOOP) occurr Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 180 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3503.01E001 Rev.
Revision Number: 14
- CPS 5060.03 (3D) Rev.
30a
- CPS 3514.01C012 Rev. 2b
Question History: (i.e. LGS 2009 Hope Creek NRC NRC-05, OYS CERT-04) exam Q11 Question Source: (i.e. New, Modified Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Modified question for History: (i.e. Modified application to CPS.
distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 263000 D.C. Electrical Distribution Category / KA Statement: K6. Knowledge of the effect that a loss or malfunction of the following will have on the D.C.
ELECTRICAL DISTRIBUTION: K6.01 A.C. electrical distribution (CFR: 41.7 / 45.7)
RO Value: 3.2 SRO Value: 3.5 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 181 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 39 263000.03 DESCRIBE the function, operation, interlocks, trips, physical location and power supplies of the following BATTERY & DC DISTRIBUTION System components.
.1 Batteries
.2 Battery Chargers
.3 DC Motor Control Centers
.4 High DC Voltage Shutdown Relays
.6 Float/Equalize Switch
.7 Ground detectors CPS OPS ILT EXAM Page: 182 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 40 ID: 896331 Points: 1.00 The plant is operating at rated thermal power.
Div 1 DG is operating in parallel with off-site power.
DG parameters are as follows:
- 3700 KW
- 3500 KVAR Under these conditions, which of the following statements is correct? (See attached DG 1A Reactive Load Capability Curve.)
The Div 1 DG is operating...
A. outside the capability curve; reduce KW loading by 1000 KW.
B. outside the capability curve; Reduce KVAR loading by 1000 KVARs.
C. within the capability curve; VARS can be raised as long as power factor is maintained less than 0.7.
D. within the capability curve; KW can be raised as long as the continuous KW load rating is NOT exceeded.
Answer: B Answer Explanation B is correct:
Per CPS 3506.01 Limitation 6.1.5:
- The DG shall also be operated within the limits of Appendix A, DG 1A(1B) Reactive Load Capability Curve or Appendix B, DG 1C Reactive Load Capability Curve as applicable.
- The DG should be operated at a power factor between 0.8 lagging and 1.0 to observe machine design ratings and minimize circulating currents.
Per CPS 3506.01 Appendix A DG 1A(1B) Reactive Load Capability Curve, the maximum VAR loading for 3700 KW and 0.8 pf is 2900 KVARs. At 3500 KVARs, Div 1 DG is operating outside the limits of the capability curve. To reduce VAR loading to within limits, DG voltage must be reduced by positioning the voltage regulator control switch to lower.
A is incorrect but plausible - reducing KW loading enough will restore the DG to within the limits of the capability curve, however a 1000 KW reduction is still outside the limits of the capability curve.
C is incorrect but plausible if the examinee incorrectly determines that DG 1A is operating within the limits of the capability curve. The examinee may select this response by determining that the limit for KVAR loading at the current KW load is 3600 KVAR based on the 0.7 pf line.
D is incorrect but plausible if the examinee incorrectly determines that DG 1A is operating within the limits of the capability curve. The examinee may select this response by determining that the DG will be operating below the 0.7 pf line if KW load is raised to the continuous KW load rating.
CPS OPS ILT EXAM Page: 183 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version KA justification - this question meets the KA because the examinee must determine that the DG is operating outside the limits of the estimated capability curve and determine mitigating actions to correct.
CPS OPS ILT EXAM Page: 184 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896331 User-Defined ID: CL-ILT-812614A Cross Reference Number:
The plant is operating at rated thermal power. Div 1 DG is Topic:
operating in parallel with off-site po Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 185 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3506.01 Rev. 37 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): CPS 3506.01 Appendix A (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPR)
KA Data KA Number / System Name: 264000 Emergency Generators (Diesel/Jet)
Category / KA Statement: A1. Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEL/JET) controls including: A1.03 Operating voltages, currents, and temperatures (CFR: 41.5 / 45.5)
RO Value: 2.8 SRO Value: 2.9 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 186 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 40 264000.10 EXPLAIN the reasons for given DIESEL GENERATOR/DIESEL FUEL OIL System operating limits and precautions.
.1 Turning off the Sync Scope when operating a Diesel Generator in parallel
.2 Operating a Diesel Generator at low load
.3 Stopping a Diesel Generator with the Emergency Stop button
.4 Running versus stopping a Diesel Generator after restoring from a loss of cooling water
.5 Loss of the Diesel Generator Ventilation Supply Fan
.6 LOCA signal
.7 An Air Start Motor failing to disengage following engine starting.
.8 Not fully opening all Cylinder Test Valves while barring diesel engines
.9 Not fully closing cylinder Test Valves prior to engine starting
.10 Starting a Diesel Generator with personnel in the DG HVAC Room
.11 Not holding the Manual Feed Prime pushbutton for one minute
.12 Circuits 13(14) and 32 not energized on their associated DC MCC for Div. 1A(1B).
.13 Placing DG in Lockout
.14 LOCA/LOOP with DG in Idle Position CPS OPS ILT EXAM Page: 187 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 41 ID: 896332 Points: 1.00 The SGTS system has initiated due to a leak in the secondary containment.
10 minutes later, system parameters have stabilized and indicate as shown:
Based on these indications, which of the following malfunctions has occurred?
A. Heaters have failed to energize.
B. Charcoal combustion has occurred.
C. Downstream HEPA filter is clogged.
D. Flow control damper has failed open.
Answer: A CPS OPS ILT EXAM Page: 188 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Answer Explanation A is correct - during an auto or manual initiation of the SGTS, the electric heaters are verified to be operating by comparing Train inlet and outlet temperature meters. Since the outlet temperature is slightly less than the inlet temperature, the electric heater has failed to energize.
B is incorrect but plausible since the inlet and outlet temperature indicators are showing an elevated temperature, however charcoal combustion is indicated by receipt of annunciator 5050-4J High Temp SGTS A Charcoal Bed which has a setpoint of 200°F.
C is incorrect but plausible - the alarm setpoint for SGTS downstream HEPA Filter high differential pressure is 2.5 in. H20. While the indication is elevated, it is not indicative of a clogged filter. In addition, SGTS system flowrate does not support a clogged filter diagnosis.
D is incorrect but plausible - normal SGTS flowrate is 4000 plus or minus 10%. The SGTS High Flow annunciator setpoint is 4500 cfm. The flow shown on the meter indication is normal.
KA justification - this question meets the KA because the examinee must be able to determine normal system operating parameters from the meter graphic shown in the stem and then determine that the SGTS heater is not working properly.
CPS OPS ILT EXAM Page: 189 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 41 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: 896332 User-Defined ID: CL-ILT-812615 Cross Reference Number:
The SGTS system has initiated due to a leak in the secondary Topic:
containment. 10 minutes later, syste Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 190 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5050.03 (3H) Rev.
Revision Number: 30c
- CPS 5050.04 (4J) Rev.
32c
- CPS 5050.07 (7G) Rev.
33
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 261000 Standby Gas Treatment System Category / KA Statement: A1. Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including:
A1.07 SBGTS train temperature (CFR: 41.5 / 45.5)
RO Value: 2.8 SRO Value: 2.9 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 191 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 41 261000.04 STATE the physical location and function of the following VG SBGT STANDBY GAS TREATMENT system controls, indicators, and/or sensors.
.1 VG Train Demister
.2 VG Train Electric Heater
.3 VG Train Pre-Filter
.4 VG Train Upstream HEPA Filter
.5 VG Train Charcoal Filter
.6 VG Train Downstream HEPA Filter
.7 VG Train Cooling Fan
.8 VG Exhaust Fans
.9 VG System Dampers
.10 Charcoal Bed Deluge
.11 VG Room Cooling Units
.12 Containment HVAC Isolation Valve Radiation Interlock Bypass Switches
.13 System Initiation Reset CPS OPS ILT EXAM Page: 192 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 42 ID: 896333 Points: 1.00 The plant was operating at rated thermal power with RAT 'A' out of service for a maintenance outage.
Then, the Turbine / Generator tripped (cause unknown).
(1) Which of the following is correct regarding the impact of these conditions on the non-vital 4.16 AND 6.9 KV busses?
(2) What mitigation actions are required?
A. (1) ONLY 6.9 KV Bus 1A deenergizes (2) Verify associated 480V Unit Sub Tie Breakers close.
B. (1) ONLY 4.16 KV Bus 1A deenergizes (2) Verify associated 480V Unit Sub Tie Breakers close.
C. (1) BOTH 6.9 KV Buses 1A AND 1B deenergize (2) Reenergize 6.9 KV Buses 1A AND 1B when RAT 'A' is available.
D. (1) BOTH 4.16 KV Buses 1A AND 1B deenergize (2) Reenergize 4.16 KV Buses 1A AND 1B when RAT 'A' is available.
Answer: C Answer Explanation C is correct - per N-CL-OPS-262001 Figure 4, RAT 'A' is the reserve power source for 6.9 KV Buses 1A and 1B. A TG trip coupled with a RAT 'A' outage will result in a loss of power to 6.9 KV Buses 1A and 1B.
A is incorrect but plausible if the examinee confuses the offsite power distribution to the 6.9 KV Buses.
RAT 'B' is the offsite power source to 4.16 KV Bus 1A. If a single 6.9 KV bus were to deenergize, appropriate actions would include verification that the associated 480V Unit Sub Tie Breakers automatically close.
B is incorrect but plausible if the examinee confuses the offsite power distribution to the 4.16 / 6.9 KV Buses. RAT 'B' is the offsite power source to 4.16 KV Bus 1A. If a single 6.9 KV bus were to deenergize, appropriate actions would include verification that the associated 480V Unit Sub Tie Breakers automatically close. The 480V Unit Subs powered from 4.16 KV Bus 1A and 1B are not equipped with tie breakers.
D is incorrect but plausible if the examinee confuses the offsite power distribution to the 4.16 / 6.9 KV Buses. RAT 'B' is the offsite power source to 4.16 KV Bus 1A.
KA justification - this question meets the KA because the examinee must be able to predict the impact of a TG trip on the 4.16 and 6.9 KV Buses.
CPS OPS ILT EXAM Page: 193 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 42 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: 896333 User-Defined ID: CL-ILT-812616 Cross Reference Number:
The plant was operating at rated thermal power with RAT 'A' Topic:
out of service for a maintenance outag Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 194 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- N-CL-OPS-262001 Revision Number: Figures 2, 4, and 5 Rev. 6
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 262001 A.C. Electrical Distribution Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.01 Turbine/generator trip (CFR: 41.5 / 45.6)
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 CPS OPS ILT EXAM Page: 195 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 42 262001.16 EVALUATE the following Auxiliary Power indications/responses and DETERMINE if the indication/
response is expected and normal.
.1 UAT Lockout
.2 RAT Lockout
.3 Transformer Lockout
.4 4.16 kV Bus Loss of Power
.5 Trip of DG Output Breaker CPS OPS ILT EXAM Page: 196 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 43 ID: 896334 Points: 1.00 While operating at 50% power with the Feedwater Level Control System (FWLC) in three element control, Main Steam Line Flow transmitter C34N003D fails high.
How will this INITIALLY affect FWLC and Rx water level?
A. Feed flow will rise and RPV level will rise.
B. Feed flow will lower and RPV level will lower.
C. FWLC will switch to single element control and level will remain constant.
D. FWLC will lock up the master level controller at the last ordered signal and reactor water level will remain constant.
Answer: A Answer Explanation A is correct:
Per N-CL-OPS-259002, an upscale failure of one of the four FWLC steam flow instruments will cause the FWC system to increase feedwater flow to the reactor, causing RPV water level to rise. A single channel failure generally results in level being controlled at a new higher level.
C is incorrect but plausible - there are no automatic shifts to single element control at CPS.
B is incorrect but plausible if the examinee incorrectly determines that lowering the steam flow input to FWLC will result in lowering the feedwater flow signal.
D is incorrect but plausible - there is no failure sensing circuit for steam flow (only level). When FWLC senses a high steam flow it will send a signal to feed water system to raise feed flow due to mismatch resulting in a level rise.
KA justification - this question meets the KA because the examinee must be able to predict the impact of a steam flow instrument failure on the FWLC system. The 'B' part was omitted as permitted by ES-401 2.a because a psychometrically sound distractor could not be written for the low cog part of the question.
CPS OPS ILT EXAM Page: 197 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896334 User-Defined ID: CL-ILT-888524A Cross Reference Number:
While operating at 50% power with the Feedwater Level Topic:
Control System (FWLC) in three element contr Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 198 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- N-CL-OPS-259002 Revision Number: Rev. 1
Question History: (i.e. LGS 2009 Vermont Yankee NRC NRC-05, OYS CERT-04) exam Q87 Question Source: (i.e. New, Modified Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Modelled from 2009 VY History: (i.e. Modified NRC Exam and from CL-distractor b to make ILT-1437. Added the (b) plausible based on OTPS portion to the question to review) match KA 259002 A2.01 (based on those predictions, use procedures to correct, control, or mitigate the consequences fo those abnormal conditions or operations)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 259002 Reactor Water Level Control System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.01 Loss of any number of main steam flow inputs (CFR:
41.5 / 45.6)
RO Value: 3.3 SRO Value: 3.4 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 199 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 43 259002.15 Given FEEDWATER CONTROL System initial conditions, PREDICT how the system and/or plant parameters will respond to the manipulation of the following controls.
.1 Control signal failure to the Feed Reg Valve (1FW004)
.2 Control signal failure to a Turbine Driven Reactor Feedwater Pump
.3 Reactor Feedwater Pump Flow Controller failure
.4 Reactor water level signal failure (high/low/as is) to the Startup Level Controller
.5 Reactor water level signal failure (high/low/as is) to the Master Level Controller
.6 Feedwater flow signal failure to the Master Level Controller
.7 Steam flow signal failure to the Master Level Controller
.8 Startup Level Controller failure
.9 Master Level Controller failure
.10 Loss of 125VDC CPS OPS ILT EXAM Page: 200 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 44 ID: 896335 Points: 1.00 The plant is operating at Rated Thermal Power when the following occurs:
- An air line ruptures in the Turbine Building Service Air Ring Header.
- NO other building Service Air or Instrument Air supplies are affected.
- ALL other air header isolation valves are STILL OPEN.
Which ONE of the following describes the procedural actions required to mitigate these conditions?
A. Lower reactor power to stabilize lowering RPV Level.
B. Place Hotwell Level Control in manual to mitigate rising Hotwell level.
C. Manually operate the Travelling Screens to prevent high differential pressures across the screens.
D. Maximize cooling to the Auxiliary Building Steam Tunnel to mitigate rising ABST temperatures.
Answer: C Answer Explanation C is correct:
Per CPS 3214.01 Plant Air (IA & SA), section 8.2.1 Ring Header Auto Isolation and Concerns While Isolated, a loss of Turbine Building Service Air will result in a loss of air to the Screen Wash Bubblers.
The bubblers will stop functioning and should a high or high-high differential pressure occur due to large trash accumulation, the Traveling Screens will not auto start. CPS 3210.01 Screen Wash (SW) section 8.3.1 Loss of Air directs starting the screens manually if air to the bubblers is lost.
A is incorrect but plausible - a loss of instrument air to the turbine building will cause the Condensate &
Condensate Booster Pump minimum flow valves to fail open resulting in lowering RPV level due to insufficient feedwater delivery to the RPV. Per CPS 4002.01 Abnormal RPV Level / Loss of Feedwater at Power, immediate action step 3.2 requires lowering reactor power to within the capacity of the existing FW system configuration using RR flow control valves.
B is incorrect but plausible - a loss of instrument air to the turbine building will cause the hotwell normal makeup and overflow valves to fail open. Per CPS 3104.01 Condensate / Condensate Booster (CD/CB) section 8.6.1 Abnormal Condenser Hotwell Level HIGH Level, manually control hotwell level as necessary. The examinee may select this response if he/she recalls only that the hotwell makeup valve fails open.
D is incorrect but plausible - a loss of Control Building IA will result in a loss of the Plant Chillers (WO) causing the ABST temperature to rise. A general mitigating strategy of EOP-8 Secondary Containment Control is to operate Fuel Building Ventilation and area coolers if area temperatures cannot be maintained below max normal values. The examinee may select this response if he/she believes that a loss of TB SA will result in a loss of cooling to the ABST.
KA justification - this question meets the KA because the examinee must have knowledge of the Abnormal Operations section (8.2) of CPS 3214.01 Plant Air (SA & IA) and CPS 4004.01 Instrument Air Loss off normal procedures to answer this question.
CPS OPS ILT EXAM Page: 201 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 44 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: 896335 User-Defined ID: CL-ILT-889259 Cross Reference Number:
The plant is operating at Rated Thermal Power when the Topic:
following occurs: An air line ruptures in Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 202 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 4004.01 Rev. 9e Revision Number:
- CPS 3214.01 Rev. 26
- CPS 3104.01 Rev. 29
- CPS 3210.01 Rev. 16
- CPS 4002.01 Rev. 4
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Modified from CL-ILT-6091 Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Modified stem and answer History: (i.e. Modified choices of CL-ILT-6091 to a distractor b to make loss of TB Service Air and plausible based on OTPS added plausibility review) statements for the distractors.
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 300000 Instrument Air System Category / KA Statement: 2.4.11 Knowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13)
RO Value: 4.0 SRO Value: 4.2 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: 203 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 44 PB400401.01.04 Describe the effect a loss of Instrument Air has on the following:
.1 Reactor Protection System (RPS)
.2 Main Steam Isolation Valves
.3 Automatic Depressurization System (ADS)
.4 Condenser Vacuum System (CA)
.6 Condensate/Condensate Booster System (CD/CB)
.7 Reactor Water Cleanup System (RT)
.8 Off-Gas System (OG)
.9 Drywell Purge System (VQ)
.10 CNMT, Fuel, Auxiliary, Turbine and Radwaste Building HVAC systems (VR, VF, VA, VT, VW)
.11 Plant Chillers (WO)
.12 Drywell and CNMT Equipment/Floor Drain System (RE/RF)
CPS OPS ILT EXAM Page: 204 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 45 ID: 896336 Points: 1.00 Plant conditions are as follows:
- An ATWS is in progress.
- The Reactor is at 58% power.
- Reactor pressure is 980 psig.
- SLC has been initiated.
If SLC system parameters are indicating as shown below, is SLC 'A' injecting into the Reactor? If not, what malfunction(s) exist?
A. Yes, SLC is injecting into the Reactor.
B. No; the squib valve has NOT fired.
C. No; a flowpath to the reactor does NOT exist with the manual shutoff valve closed.
D. No; the SLC discharge pressure indicates the pump discharge relief valve is lifting.
CPS OPS ILT EXAM Page: 205 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Answer: A Answer Explanation A is correct:
Per CPS 4411.10 SLC Operations, SLC injection is verified by observing:
SLC Pump Disch Header Press, 1C41-R600 is:
- Is < 1400 psig. [If > 1400 psig, pump relief may be lifting.]
Following require SLC system response time before verifying.
- Reactor power lowering.
Per 5066.06 (6F), the SLC Storage Tank Low Level alarm Level alarms at 3574 gallons which is also the ITS limit on SLC storage tank level. With level in the stem indicated at 3500 gallons, SLC tank level is lower than normal.
B is incorrect but plausible - CPS 3314.01 Standby Liquid Control step 2.3 states that when the squib valve is fired, it is possible for the shorted valve assembly to indicate continuity. With pump discharge pressure < 1400 psig and slightly higher than reactor pressure, flow through the squib valve is verified.
C is incorrect but plausible - SLC is normally aligned to the HPCS injection line via 1C41-F334. The SLC Manual Shutoff Valve indication on 1H13-P601 indicates the position of 1C41-F008 SLC Injection -
Bottom Head which is normally a locked closed valve.
D is incorrect but plausible - the SLC Pump Discharge Relief lift setpoint is 1400 psig.
KA justification - this question meets the KA because the examinee must be able to determine the status of SLC injection given the panel indications provided in the stem.
CPS OPS ILT EXAM Page: 206 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896336 User-Defined ID: CL-ILT-889135 Cross Reference Number:
Plant conditions are as follows: An ATWS is in progress. The Topic:
Reactor is at 58% power. Reactor pre Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 207 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 4411.10 Revision Number: (Appendix A) Rev. 6
- CPS 3314.01 Rev. 11c
- CPS 3314.01V001 Rev.
10a
- CPS 5066.06 (6F) Rev.
25d Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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: A3. Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including: A3.01 Pump discharge pressure: Plant-Specific (CFR: 41.7 / 45.7)
RO Value: 3.5 SRO Value: 3.5 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 208 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 45 211000.16 EVALUATE the following STANDBY LIQUID CONTROL indications/responses and DETERMINE if the indication/response is expected and normal.
.1 System Initiation
.2 Indication of boron injection
.3 System Testing CPS OPS ILT EXAM Page: 209 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 46 ID: 896337 Points: 1.00 A plant shutdown and cooldown is in progress.
- Reactor coolant temperature is 290°F.
- RHR 'B' has just been placed in Shutdown Cooling (SDC) Mode.
Under these conditions, which of the following valves are normally throttled to control cooldown rate?
A. 1E12-F047B RHR 'B' Hx Inlet Valve B. 1E12-F003B RHR 'B' Hx Outlet Valve C. 1E12-F042B LPCI FM RHR 'B' Shutoff Valve D. 1E12-F037B RHR 'B' to Cnmt Pool Cooling Shutoff Valve Answer: B Answer Explanation B is correct:
Per CPS 3312.03 section 8.1.2.22.5, cooldown rate and flow is maintained by throttling:
- 1E12-F003B RHR B Hx Outlet Valve
- 1E12-F048B RHR B Hx Bypass Valve
- 1E12-F053B RHR B to Feedwater S/D Cooling Rtrn Vlv
- 1E12-F037B RHR B To CNMT Pool Cooling Shutoff Vlv. (If used when RPV head is removed.)
A is incorrect but plausible - 1E12-F047B is in the SDC flowpath, but is not a throttleable valve.
C is incorrect but plausible if the examinee incorrectly believes that SDC flows through the LPCI injection line back to the RPV.
D is incorrect but plausible - 1E12-F037B can only be used when the RPV head is removed. With reactor coolant temperature at 290°F, the reactor is still pressurized and the RPV head is still installed.
KA justification - this question meets the KA because the examinee must have knowledge of the valve operations required to control Shutdown Cooling flow and the RPV cooldown rate.
CPS OPS ILT EXAM Page: 210 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896337 User-Defined ID: CL-ILT-812620A Cross Reference Number:
A plant shutdown and cooldown is in progress. Reactor coolant Topic:
temperature is 290?F. RHR 'B' has j Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 211 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3312.03 Rev. 10 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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: K5. Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): K5.02 Valve operation (CFR: 41.5 / 45.3)
RO Value: 2.8 SRO Value: 2.9 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 212 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 46 203000.03 DESCRIBE the function, operation, interlocks, trips, physical locations, and power supplies of the following RESIDUAL HEAT REMOVAL System components.
.1 Suppression Pool Suction Strainer
.2 RHR Pumps
.3 RHR Heat Exchangers
.4 B/C Water Leg Pump
.5 Containment Spray Header and Nozzles
.6 Suppression Pool Suction Valves F004A, F004B.
.7 RH Shutdown Cooling Suction Valves F006A and F006B
.8 Shutdown Cooling Inboard and Outboard Isolation Valves F009 and F008
.9 RH B Supply to Reactor Head Spray Valve F023
.10 RH C Full Flow Test Valve F021
.11 RH A (B) Full Flow Test Valves F024A and F024B
.12 RH A (B) Containment Outboard Isolation Valves F027A and F027B
.13 RH A(B) Containment Spray A(B) Shutoff Valves F028A and F028B
.14 RH A(B) to Containment Pool Cooling Shutoff Valves F037A and F037B
.15 LPCI From RH Shutoff Valves F042A, F042B, and F042C
.16 LPCI From RH Testable Check Valves F041A, F041B, and F041C
.17 RH Heat Exchanger Inlet Valves F047A and F047B
.18 RH Heat Exchanger Outlet CPS OPS ILT EXAM Page: 213 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Valves F003A and F003B
.19 RH B Radwaste First and Second Isolation Valves F049 and F040
.20 RH Heat Exchanger Bypass Valves F048A and F048B
.21 RH to Feedwater Shutdown Cooling Return Valves F053A and F053B
.22 RH Heat Exchanger First and Second Sample Valves F060A, F060B, F075A and F075B
.23 RH Pump Minimum Flow Recirc Valves F064A, F064B and F064C
.24 RH Heat Exchanger SSW Inlet and Outlet Valves F014A, F014B, F068A and F068B
.25 RH Fuel Pool Cooling Assist Suction Valve F066 CPS OPS ILT EXAM Page: 214 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 47 ID: 896338 Points: 1.00 The plant was operating at rated thermal power when a Loss of Offsite Power AND Loss of Coolant Accident (LOOP/LOCA) occurred.
Assuming the plant operates as designed, the Div 1 SX Pump will _____(1)_____. Once running, pump minimum flow protection _____(2)_____.
A. (1) automatically start (2) is automatically aligned B. (1) have to be manually started (2) is automatically aligned C. (1) automatically start (2) is manually aligned by restarting the LPCS and RHR Pump Room Coolers D. (1) have to be manually started (2) is manually aligned by restarting the LPCS and RHR Pump Room Coolers Answer: A Answer Explanation A is correct:
Per CPS 3211.01 Shutdown Service Water (SX), section 8.3.1 Automatic Initiation On Low WS Header Pressure and/or Loss of Coolant Accident and/or Loss of Off-Site Power, operator actions are to verify that the SX Pumps have started and that 1SX063A(B)(6C) have opened to provide min flow protection for the associated SX pump.
B is incorrect but plausible if the examinee fails to recall that the Div 1 SX Pump resequences back onto the bus after a LOOP/LOCA event.
C is incorrect but plausible - Div 3 SX Pump min flow protection is provided by flow through the associated DG heat exchanger or the SX Pump Room and HPCS Pump room coolers. The examinee may select this response if he/she believes min flow protection for the Div 1 SX Pump can be provided by the LPCS and RHR Pump Room Coolers, and that they have to be manually started after the bus reenergizes during a LOOP/LOCA event.
D is incorrect but plausible if the examinee fails to recall that the Div 1 SX Pump resequences back onto the bus after a LOP/LOCA event and that minimum flow protection for Div 1 SX Pump can be provided by the LPCS and RHR Pump Room Coolers, and that they have to be manually started after the bus reenergizes during a LOOP/LOCA event.
KA justification - this question meets the KA because the SX Pumps automatically start on a LOCA signal to support the low pressure ECCS systems (pump room cooling, heat exchanger cooling, etc.) The examinee must be able to determine the impact of a LOOP/LOCA (LPCI initiation) event on the initiation logic for the Div 1 SX Pump to answer the question.
CPS OPS ILT EXAM Page: 215 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896338 User-Defined ID: CL-ILT-812621 Cross Reference Number:
The plant was operating at rated thermal power when a Loss of Topic:
Offsite Power AND Loss of Coolant Ac Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 216 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3211.01 Rev. 31 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: 203000 RHR/LPCI: Injection Mode (Plant Specific)
Category / KA Statement: A4. Ability to manually operate and/or monitor in the control room: A4.01 Pumps (CFR: 41.7
/ 45.5 to 45.8)
RO Value: 4.3 SRO Value: 4.1 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 217 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 47 400002.03 DESCRIBE the function, operation, interlocks, trips, physical location and power supplies of the following SHUTDOWN SERVICE WATER System components.
.1 SX Pumps
.2 SX Strainers
.3 SX Strainer Inlet, Outlet, Bypass and Backwash Valves
.4 WS to SX Header Isolation Valves
.5 SX Division 1 & 2 Cross-tie Valves
.6 SX Division 1 & 2 Containment Isolation Valves
.7 SX Sluice Gate
.8 SX Flow Control Valves
.9 SX Division 1 & 2 Component Isolation Valves
.10 SX Division 1 & 2 RHR HXs SX Bypass Valves
.11 SX Pump Room Cooling Fans
.12 SX Pump Room Cooling Coils
.14 SX Loads that return to the UHS CPS OPS ILT EXAM Page: 218 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 48 ID: 896339 Points: 1.00 A reactor startup is in progress per CPS 3001.01 Preparation For Startup & Approach To Critical.
Criticality was achieved at 08:17.
The following data was recorded into Table 3 Manual Period (Doubling Time) Calculation of CPS 3001.01:
Table 3: Manual Period (Doubling Time) Calculation (OK to duplicate this Table and attach to procedure as needed.)
Date/Time SRM/IRM SRM/IRM SRM/IRM Elapsed Period = Initials Channel Reading Reading Time for Elapsed Doubled SRM/IRM Time
- xxxx Reading to (Seconds)
Double (Seconds) 06/15/13 A 600 1200 60 08:17:00 06/15/13 A 1200 2400 60 08:18:00 No additional control rod motion has occurred.
Doubling times for the remaining SRM channels (B, C, and D) are consistent with SRM 'A'.
With the table data provided above, actual period is between _____(1)_____ seconds and is
_____(2)_____ the procedurally desired band for achieving heating power.
A. (1) 60 - 90 (2) within B. (1) 100 - 150 (2) within C. (1) 60 - 90 (2) shorter than D. (1) 100 - 150 (2) shorter than Answer: C Answer Explanation C is correct - per CPS 3001.01 Preparation For Startup & Approach To Criticality step 8.3.1, control rods are withdrawn per the Control Rod Sequence to increase power to heating power level. (A Rx period of 100-150 seconds is desirable.) Per 3001.01 Table 3, period is calculated by multiplying doubling time by 1.443.
1.443
- 60 seconds = 86.58 seconds which is shorter than the desired period of 100 - 150 seconds.
A is incorrect but plausible - part 1 is correct but actual period is shorter than the desired period.
CPS OPS ILT EXAM Page: 219 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version B is incorrect but plausible if the examinee incorrectly calculates period between 100 - 150 seconds and then correctly determines that desired period is within 100 - 150 seconds.
D is incorrect but plausible if the examinee incorrectly calculates period between 100 - 150 seconds and also incorrectly determines that desired period is outside the calculated band.
KA justification - this question meets the KA because the examinee is required to calculate period based on doubling time information provided in Table 3 and then determine if actual period is within the procedure guidance for desired period when withdrawing control rods to achieve heating power.
CPS OPS ILT EXAM Page: 220 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 48 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: 896339 User-Defined ID: CL-ILT-889265 Cross Reference Number:
A reactor startup is in progress per CPS 3001.01 Preparation Topic:
For Startup & Approach To Critical.
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 221 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3001.01 Rev. 25e Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPR)
KA Data KA Number / System Name: 215004 Source Range Monitor System Category / KA Statement: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
(CFR: 41.10 / 43.5 / 45.12)
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 Associated objective(s):
Question 48 complete Control Room actions to perform RPV heatup and pressurization CPS OPS ILT EXAM Page: 222 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version CPS OPS ILT EXAM Page: 223 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 49 ID: 896340 Points: 1.00 In which of the following scenarios is ADS required to be INHIBITED?
A. During Station Blackout conditions.
B. Scram with shutdown criteria NOT met.
C. During a complete loss of Instrument Air.
D. Scram with no high pressure injection sources available.
Answer: B Answer Explanation B is correct:
Inhibiting ADS is the first step in CPS 4404.01 ATWS RPV Control before performing any actions in the level, pressure, or power legs.
A is incorrect but plausible if the examinee incorrectly believes that ADS is inhibited during Station Blackout conditions to conserve the air supply to the ADS valves and/or conserve the Division 1 and 2 batteries.
C is incorrect but plausible if the examinee incorrectly believes that ADS is inhibited during a loss of Plant Air event to conserve the air supply to the ADS valves.
D is incorrect but plausible if the examinee incorrectly believes that ADS is inhibited when high pressure injection systems are not available for injection. Under these conditions, ADS is permitted to actuate automatically as designed.
CPS OPS ILT EXAM Page: 224 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version KA justification - this question meets the KA because the examinee must be knowledgeable of when ADS is inhibited during an ATWS event in order to answer the question. RO's are trained to stand by the ADS inhibit switches awaiting the command from the CRS to inhibit ADS. Inhibiting ADS is a general mitigating strategy for ATWS RPV Control and is therefore RO knowledge.
CPS OPS ILT EXAM Page: 225 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 49 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: 896340 User-Defined ID: CL-ILT-812623A Cross Reference Number:
In which of the following scenarios is ADS required to be Topic:
INHIBITED?
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 226 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 4404.01 Rev. 29 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 218000 Automatic Depressurization System Category / KA Statement: 2.4.1 Knowledge of EOP entry conditions and immediate action steps. (CFR: 41.10 / 43.5 /
45.13)
RO Value: 4.6 SRO Value: 4.8 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: 227 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 49 LP87553.01.03 Given a diagram of EOP-1A:
.01 Describe the conditions to exit/transfer from EOP-1A
.02 State the bases for each individual step/action of EOP-1A
.03 Discuss the importance of verifying that the appropriate automatic actions of EOP-1A occur as required
.04 List the available methods to be used to stabilize/control RPV pressure in EOP-1A
.05 List the Preferred ATWS level control systems.
CPS OPS ILT EXAM Page: 228 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 50 ID: 896341 Points: 1.00 With the plant operating at rated thermal power, the following annunciator was received:
- 5063-3G LPCS Pump Discharge Pressure Abnormal What is a possible impact of this condition on the Low Pressure Core Spray System?
A. Damage to LPCS System piping and components if LPCS Pump is started.
B. The LPCS Pump is incapable of producing an ADS permissive signal if started.
C. The LPCS injection valve will immediately open if the LPCS system is automatically initiated.
D. The LPCS line break detection instrumentation is incapable of detecting a LPCS injection line sparger break.
Answer: A Answer Explanation A is correct:
The LPCS Pump Discharge Pressure Abnormal annunciator is received on a low pressure (35 psig) or high pressure (540 psig) condition. A possible cause for the annunciator is a trip of the LPCS & RHR 'A' Water Leg Pump, or a valve misalignment. High pressure is caused by RPV backleakage through the LPCS injection line.
Per the annunciator procedure, if a low pressure condition exists, determine and correct the cause and then perform a fill and vent of the system IAW 3313.01 Low Pressure Core Spray (LPCS) or CPS 9052.04 LPCS/RHR A System Header Fill and Flow Path Verification.
A loss of system fill and vent could result in piping damage due to water hammer in the event the LPCS Pump is started.
B is incorrect but plausible - LPCS Pump discharge pressure provides an input signal to the ADS initiation logic via ATMs 1E21-N652 and 653. The ATMs feeding the LPCS Pump Discharge Pressure Abnormal alarm is 1E21-N654 and 655.
C is incorrect but plausible - the ATMs inputting into the 472 psig LPCS injection valve permissive to open are 1B21-N697A & E, not 1E21-N654 and 655.
D is incorrect but plausible - the ATM inputting into the LPCS Line Break Detection circuitry is 1E31-N680A, not 1E21-N654 and 655.
KA justification - this question meets the KA because the examinee must determine that the annunciator provided in the stem is an indication of a possible loss of LPCS system fill and vent that can cause damage to LPCS system piping and components if the LPCS Pump is started.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 50 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: 896341 User-Defined ID: CL-ILT-812624 Cross Reference Number:
With the plant operating at rated thermal power, the following Topic:
annunciator was received: 5063-3G Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 230 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5063.03 (3G) Rev.
Revision Number: 33c
- CPS 5067.04 (4A) Rev.
31
- CPS 5063.07 (7H) Rev.
30c
- CPS 5063.08 (8H) Rev.
35 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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: K5. Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM : K5.05 System venting (CFR: 41.5 / 45.3)
RO Value: 2.5 SRO Value: 2.5 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 231 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 50 209001.11 EVALUATE given key LPCS System parameters, if needed DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
.3 LPCS Pump Auto Trip
.4 LPCS Pump Discharge Pressure Abnormal
.5 LPCS Injection Valve Permissive
.6 High/Low Temp LPCS Pump Room
.7 LPCS Out Of Service CPS OPS ILT EXAM Page: 232 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 51 ID: 896342 Points: 1.00 With the reactor operating at 60% power and 70% of rated Reactor Recirculation (RR) flow, the RR System Flow Converter for APRM Channel A fails upscale.
What is the status of the following APRM A outputs/trips (assume TRIPPED means action has occurred)
(1) Flow Reference-Upscale Rod Block (2) Flow-Biased Thermal Alarm/Rod Block (3) Flow-Biased Thermal Scram Trip A. (1) NOT Tripped (2) NOT Tripped (3) NOT Tripped B. (1) Tripped (2) NOT Tripped (3) NOT Tripped C. (1) NOT Tripped (2) Tripped (3) Tripped D. (1) Tripped (2) Tripped (3) Tripped Answer: B Answer Explanation B is correct:
Per CPS 5004.02 (2K) Flow Reference Upscale, a rod block will be initated from any flow reference upscale when the Mode Switch is in RUN.
With a higher flow input to the comparators for the Flow-Biased Alarm/Rod Block trip and the Flow-Biased Thermal scram trip, a higher power would be needed to trip these outputs. Since power did not change, these outputs/trips remain NOT TRIPPED (1)(2).
A is incorrect but plausible if the examinee fails to recall the impact of a flow reference upscale condition on the flow biased alarm / rod block circuitry.
C is incorrect but plausible if the examinee incorrectly recalls the impact of the flow reference upscale condition on the flow reference rod block circuitry, the flow biased alarm / rod block circuitry and the flow biased thermal scram (RPS) trip circuitry.
D is incorrect but plausible if the examinee incorrectly recalls the impact of the flow reference upscale condition on the flow biased alarm / rod block circuitry and the flow biased thermal scram (RPS) trip circuitry.
KA justification - this question meets the KA because the examinee must have knowledge of the effect of an upscale failure of the flow converter for APRM 'A' on the flow reference rod block circuitry for APRM 'A' in order to answer this question.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896342 User-Defined ID: CL-ILT-891872 Cross Reference Number:
With the reactor operating at 60% power and 70% of rated Topic:
Reactor Recirculation (RR) flow, the RR S Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 234 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 5004.02 (2K) Rev. 29c Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - duplicate of CL-LC-Bank, Modified) 598172 Low KA Justification (if NA required):
Revision History: Revision Revised plausibility History: (i.e. Modified statements. Added KA distractor b to make justification statement.
plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 215005 Average Power Range Monitor/Local Power Range Monitor Category / KA Statement: 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 (CFR: 41.7 /
45.7)
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 CPS OPS ILT EXAM Page: 235 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 51 215005.04 STATE the physical location and function of the following AVERAGE POWER RANGE MONITOR system components, controls, indicators, and/or sensors
.1 Local Power Range Monitor (LPRM) Detector
.2 LPRM High Voltage Power Supply
.3 LPRM Card
.4 LPRM Multiplexer
.5 LPRM Count Circuit
.6 APRM Averaging Amplifier
.7 APRM Meter
.8 APRM Meter Function Switch
.9 APRM Inop Circuit
.10 APRM Flow Channel
.11 APRM Trip Reference Card
.12 Reactor Mode Switch
.13 NSPS Sensor Bypass Switches CPS OPS ILT EXAM Page: 236 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 52 ID: 896343 Points: 1.00 Reactor power is on IRM range 6 with a reactor heatup and pressurization in progress.
Then, annunciator 5005-2H RPS CH B IRM UPSC TRIP OR INOP was received due to an trip on IRM 'B'.
(1) Receipt of which of the following additional alarm indications will result in a scram?
(2) Under which conditions are the IRM Upscale Trip or Inop scram and rod block signals bypassed from IRM 'B'?
A.
(1)
(2) Reactor Mode Switch is in RUN ONLY B.
(1)
(2) Reactor Mode Switch is in RUN ONLY CPS OPS ILT EXAM Page: 237 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version C.
(1)
(2) Reactor Mode Switch is in RUN OR IRM 'B' is on Range 1 D.
(1)
(2) Reactor Mode Switch is in RUN OR IRM 'B' is on Range 1 Answer: B Answer Explanation B is correct:
CPS OPS ILT EXAM Page: 238 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version To answer this question correctly, the examinee must know that IRMs B and F are in the same division (Div 2) and that the RPS trip logic is 2 out of 4. To satisfy the RPS logic, trips have to be received from 2 different divisions.
IRM Channels are arranged as follows:
Div 1 - IRM A and E Div 2 - IRM B and F Div 3 - IRM C and G Div 4 - IRM D and H Per CPS 5005.02 (2H), an RPS Channel B IRM Upscale Trip or Inop signal will initiate a rod block and an RPS trip (if a second RPS channel upscale or inop trip is received).
A trip of IRM G will complete the 2 out of 4 logic needed for an RPS trip.
Per CPS 3306.01 Source/Intermediate Range Monitors (SRM/IRM) discussion item 2.5, RPS trips from the IRMs are bypassed when the mode switch is in RUN.
A is incorrect but plausible - a trip of IRM F (Div 2) will not satisfy the 2 out of 4 RPS logic requirement.
C is incorrect but plausible - a trip of IRM F (Div 2) will not satisfy the 2 out of 4 RPS logic requirement.
IRM downscale rod blocks are bypassed with the associated IRM channel on range 1, but RPS trips from the IRMs are only bypassed with the RMS in Run.
D is incorrect but plausible - IRM downscale rod blocks are bypassed with the associated IRM channel on range 1, but RPS trips from the IRMs are only bypassed with the RMS in Run.
KA justification - this question meets the KA because the examinee must be able to determine if a scram would be initiated given the alarm indications provided in the answer choices.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896343 User-Defined ID: CL-ILT-812626 Cross Reference Number:
Reactor power is on IRM range 6 with a reactor heatup and Topic:
pressurization in progress. Then, annun Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 240 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5005.02 (2H) Rev.
Revision Number: 29c
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 215003 Intermediate Range Monitor System Category / KA Statement: A3. Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM including: A3.02 Annunciator and alarm signals (CFR: 41.7 / 45.7)
RO Value: 3.3 SRO Value: 3.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 241 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 52 215003.05 Discuss the IRM system automatic functions/interlocks including purpose, signals, set points, sensing points, when bypassed, how/when they are.
.1 Scrams
.2 Control Rod Withdrawal Blocks CPS OPS ILT EXAM Page: 242 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 53 ID: 896344 Points: 1.00 The plant is in Mode 5.
RPV metal and coolant temperatures are being monitored per CPS 9000.06 Reactor Coolant and Vessel Metal/Pressure Temperature Limit Logs and has been lowered to < 120°F as required by CPS 3312.03 RHR - Shutdown Cooling (SDC) & Fuel Pool Cooling and Assist (FPC&A).
Under these conditions, where are Reactor Recirculation loop temperatures monitored?
A. Point A - 1H13-P601 B. Point B - 1H13-P614 C. Point C - 1H13-P678 CPS OPS ILT EXAM Page: 243 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version D. Point D - 1H13-P680 Answer: B Answer Explanation B is correct - Per CPS 3312.03 step 8.1.6.1, RR Loop temperatures are monitored on recorder B33-R604 located on 1H13-P614.
A is incorrect but plausible - the RHR Service Temperature Recorder E12-R601 is located on 1H13-P601 but RR loop temperature indications cannot be monitored there.
C is incorrect but plausible - 1H13-P678 Standby Information Panel contains a number of RR System recorders/meters, but not RR Loop temperature indications.
D is incorrect but plausible - 1H13-P680 contains RR loop temperatures, but the points are converted from RR system pressure and are not available below 212°F.
KA justification - this question meets the KA because the examinee has to choose the location for monitoring RR Loop temperatures from a graphic showing the MCR Panels.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 53 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: 896344 User-Defined ID: CL-ILT-812627A Cross Reference Number:
The plant is in Mode 5. RPV metal and coolant temperatures Topic:
are being monitored per CPS 9000.06 Re Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 245 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3312.03 Rev. 9 Revision Number:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-S)
KA Data KA Number / System Name: 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)
Category / KA Statement: A4. Ability to manually operate and/or monitor in the control room: A4.12 Recirculation loop temperatures (CFR: 41.7 / 45.5 to 45.8)
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 CPS OPS ILT EXAM Page: 246 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 53 NB - Nuclear Boiler Instrumentation Perform the following MCR tasks:
CPS OPS ILT EXAM Page: 247 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 54 ID: 896345 Points: 1.00 Which of the following graphics shows the expected response of the RWCU system to an extended loss of CCW flow to the in-service NRHx? (Duplicate graphic is attached.)
A.
B.
CPS OPS ILT EXAM Page: 248 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version C.
D.
A. Graphic A B. Graphic B C. Graphic C D. Graphic D Answer: A Answer Explanation A is correct:
CPS OPS ILT EXAM Page: 249 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version The RWCU Non-Regenerative Heat Exchangers are cooled by the Component Cooling Water System (CCW). A loss of CCW will cause NRHX effluent temperature 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 - graphic shows 1G33-F001 RWCU Suct Inbd Isol closed.
C is incorrect but plausible - graphic shows 1G33-F001 & F004 closed.
D is incorrect but plausible - graphic shows all RT primary containment isolation valves closed. These are the expected positions for a CRVICS Group 4 Isolation.
KA justification - this question meets the KA because the examinee has to determine the impact of a loss of CCW on the RWCU system.
CPS OPS ILT EXAM Page: 250 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 54 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: 896345 User-Defined ID: CL-ILT-812628A Cross Reference Number:
Which of the following graphics shows the expected response Topic:
of the RWCU system to an extended loss Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 251 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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 No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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: K1. Knowledge of the physical connections and/or causeeffect relationships between REACTOR WATER CLEANUP SYSTEM and the following:
K1.04 Component cooling water systems (CFR: 41.2 to 41.9
/ 45.7 to 45.8)
RO Value: 2.9 SRO Value: 2.9 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.2 to 41.9 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 252 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 54 204000.04 STATE the physical location and function of the following RWCU system controls, indicators, and/or sensors.
.1 RT return temperature
.3 RT temperatures
.4 RT Pumps
.5 Regenerative heat exchanger inlet pressure
.6 RT Panel 1G36-P002 Indications
.7 Main Control Room Parameter Indications CPS OPS ILT EXAM Page: 253 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 55 ID: 896346 Points: 1.00 The MCR is switching the operating FC Pump and Heat Exchanger in accordance with CPS 3317.01 Fuel Pool Cooling and Cleanup (FC).
A summary of the actions that have been performed are as follows:
- The CCW Inlet Valve (1CC075A/B) has been verified open to the on-coming FC Heat Exchanger.
- The third CCW Pump has been started.
The next step of the procedure directs throttling 1CC080 Return Line Throttle Valve, as necessary to LOWER CCW system header pressure to the desired value as read in the MCR.
To LOWER CCW system header pressure, the RO will tell the Equipment Operator in the field to throttle 1CC080 Return Line Throttle Valve in the _____(1)_____ direction, which will cause FC Motor Heat Exchanger flow to ______(2)_____.
A. (1) closed (2) rise B. (1) closed (2) NOT change C. (1) open (2) rise D. (1) open (2) NOT change Answer: C Answer Explanation C is correct:
1CC080 Return Line Throttle Valve is located on the effluent of the FC Heat Exchangers. When opened, it causes CCW Header pressure to lower due to increasing the flow through the FC Heat Exchangers.
CPS 3317.01 section 8.1.2.4 cautions that the FC Pump Motor Cooler Flow shall be monitored anytime CCW System Header Pressure is affected. In service FC Pump will trip if Motor Cooler Hx flow < 12.2 gpm for > 100 sec.
3317.01 also states that 1CC080 will need to be throttled open to raise flow to accomodate for two HXs and motor coolers. 1CC080 may need to be repositioned to maintain FC pump motor cooling flow.
Opening 1CC080 will raise FC pump motor cooling flow.
3317.01 step 8.1.2.5 - Throttle 1CC080, Return Line Throttle Valve, as necessary to lower CCW system header pressure to the desired value as read in the MCR.
A is incorrect but plausible - for the FC system, upper containment pool flow is controlled by throttling 1FC177 Spent Fuel Pool Inlet Isolation. If upper containment pool flow is low, 1FC177 is closed to raise upper pool flow. If upper containment pool flow is high, 1FC177 is opened. The examinee may select this choice if the operation of 1CC080 is confused with the operation of 1FC177.
CPS OPS ILT EXAM Page: 254 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version B is incorrect but plausible - for the FC system, upper containment pool flow is controlled by throttling 1FC177 Spent Fuel Pool Inlet Isolation. If upper containment pool flow is low, 1FC177 is closed to raise upper pool flow. If upper containment pool flow is high, 1FC177 is opened. The examinee may select this choice if the operation of 1CC080 is confused with the operation of 1FC177. B is also incorrect if the examinee fails to recall that the flow through the FC Motor Coolers is determined by the differential pressure across the FC Heat Exchangers. As FC Heat Exchanger flow rises (by opening 1CC080), FC Motor Cooler flow rises. The examinee may select this response if he/she incorrectly believes that the FC Motor Coolers are cooled by FC instead of CCW.
D is incorrect but plausible if the examinee fails to recall that the flow through the FC Motor Coolers is determined by the differential pressure across the FC Heat Exchangers. As FC Heat Exchanger flow rises (by opening 1CC080), FC Motor Cooler flow rises. The examinee may select this response if he/she incorrectly believes that the FC Motor Coolers are cooled by FC instead of CCW.
KA justification - this question meets the KA because the examinee must describe understanding of what happens when 1CC080, which is a manual valve located in the Fuel Building) is operated and how it affects MCR indications. The question does not address the location portion of the KA as allowed by ES-401 2.a.
CPS OPS ILT EXAM Page: 255 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896346 User-Defined ID: CL-ILT-812629 Cross Reference Number:
The MCR is switching the operating FC Pump and Heat Topic:
Exchanger in accordance with CPS 3317.01 Fuel Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 256 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3317.01 Rev. 29 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 233000 Fuel Pool Cooling and Clean-up Category / KA Statement: 2.1.30 Ability to locate and operate components, including local controls. (CFR: 41.7 /
45.7)
RO Value: 4.4 SRO Value: 4.0 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 257 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 55 400001.16 EVALUATE the following Component Cooling Water indications/responses and DETERMINE if the indication/
response is expected and normal.
.1 Normal Operation CPS OPS ILT EXAM Page: 258 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 56 ID: 896347 Points: 1.00 The plant is operating at rated thermal power.
Plant status is as follows:
- RCIC is running and data collection has begun.
- Both loops of RHR have been started in FULL Suppression Pool Cooling Mode to prevent Suppression Pool temperature from exceeding procedure limitations.
Then, a LPCI initiation signal was received.
Under these conditions, if directed to realign both RHR loops into FULL Suppression Pool Cooling Mode, 1E12-F024A & B RHR A(B) Test Valve To Suppr Pool can be opened _____(1)_____ and 1E12-F048A
& B RHR A(B) Hx Bypass Valve can be reclosed _____(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: B Answer Explanation B is correct:
A LPCI initiation signal will result in RHR Loops 'A' and 'B' automatically shifting from Suppression Pool Cooling 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) is opened immediately. A note above the step for opening 1E12-F048A(B) states that 1E12-F048A(B) will open for 10 minutes after receipt of a LPCI signal, and than can be repositioned.
A is incorrect but plausible if the examinee fails to recall the 10 minute time delay interlock on 1E12-F048A(B).
CPS OPS ILT EXAM Page: 259 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version C 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 1E12-F048A(B) and not to 1E12-F024A(B).
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.
CPS OPS ILT EXAM Page: 260 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896347 User-Defined ID: CL-ILT-812630A Cross Reference Number:
The plant is operating at rated thermal power. Plant status is Topic:
as follows: CPS 9054.01C002 RCIC Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 261 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3312.01 Rev. 44 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-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 (CFR: 41.7 / 45.4)
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 CPS OPS ILT EXAM Page: 262 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 56 203000.15 Given RESIDUAL HEAT REMOVAL System initial conditions, PREDICT how the system and/or plant parameters will respond to the manipulation of the following controls.
.1 From Standby, Arming/Depressing Div 1(2)
Manual Initiation Pushbutton.
.2 From Standby, Arming/Depressing Div 1(2)
Manual Containment Spray Initiation Pushbutton
.3 System Operating in response to High Drywell Pressure, Arming/Depressing Div 1(2)
Manual Containment Spray Initiation Pushbutton
.4 System Operating in response to High Drywell Pressure, Operation of Pump Control Switch and/or F042A (B), (C)
Control Switch CPS OPS ILT EXAM Page: 263 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 57 ID: 896348 Points: 1.00 The valve in the graphic below is used to _____(1)_____ initiate RHR flow into the _____(2)_____ during post-LOCA conditions.
A. (1) manually (2) 'B' FW line ONLY B. (1) manually (2) 'A' AND 'B' FW lines C. (1) automatically (2) 'B' FW line ONLY D. (1) automatically (2) 'A' AND 'B' FW lines Answer: B Answer Explanation B is correct:
Per CPS 3312.01 Residual Heat Removal (RHR) section 8.3.1 Feedwater Leakage Control System (FWLCS), the FWLCS is required to be placed in service when a DBA LOCA signature is identified and within 20 minutes after FW/CB/CD injection is no longer available.
CPS OPS ILT EXAM Page: 264 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Per N-CL-OPS-259001 Feedwater, The Residual Heat Removal system Feedwater Leakage Control Mode provides a water seal on the feedwater lines between 1B21F065A/B and 1B21F010A/B post LOCA.
Valves 1E12-F496/497 are opened to initiate the Feedwater Leakage Control system, opening either valve will provide seal water to both Feedwater lines. Opening 1E12-F496 aligns RHR B to both FW lines between 1B21-F010A/B and 32A/B. Opening 1E12-F497 aligns RHR A to both FW lines between 1B21-F032A/B and 65A/B.
A is incorrect but plausible if the examinee fails to recall that either RHR subloop (A or B) inject to both FW lines. The injection point for RHR 'B' is between 1B21-F010A and 32A on FW line 'A' and 1B21-F010B and 32B on FW Line 'B'.
C is incorrect but plausible if the examinee incorrectly recalls that (1) the FWLCS is manually aligned.
The automatic feature of 1E12-F496 is an auto closure on high reactor pressure at 330 psig, and (2) fails to recall that both RHR subloops (A and B) inject to both FW lines. The injection point for RHR 'B' is between 1B21-F010A and 32A on FW line 'A' and 1B21-F010B and 32B on FW Line 'B'.
D is incorrect but plausible if the examinee incorrectly recalls that the FWLCS is manually aligned. The automatic feature of 1E12-F496 is an auto closure on high reactor pressure at 330 psig.
KA justification - this question meets the KA because the examinee must have knowledge of the function of the Feedwater Leakage Control System (FWLCS), which is used to supplement the isolation function of primary containment isolation valves in the feedwater lines penetrating the containment. KA 223001 describes systems whose function is to contain fission products after a LOCA, and since FWLCS provides this function, it is appropriate to link it to 223001 Primary Containment System and Auxiliaries.
CPS OPS ILT EXAM Page: 265 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 57 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: 896348 User-Defined ID: CL-ILT-812631 Cross Reference Number:
The valve in the graphic below is used to _____(1)_____
Topic:
initiate RHR flow into the _____(2)_____ d Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 266 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3312.01 Rev. 44 Revision Number:
- CPS 4001.02 Rev. 17a
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-I)
KA Data KA Number / System Name: 223001 Primary Containment System and Auxiliaries Category / KA Statement: K4. Knowledge of PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES design feature(s) and/or interlocks which provide for the following:
K4.02 Contains fission products after a LOCA (CFR: 41.7)
RO Value: 3.6 SRO Value: 3.7 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 267 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 57 203000.03 DESCRIBE the function, operation, interlocks, trips, physical locations, and power supplies of the following RESIDUAL HEAT REMOVAL System components.
.1 Suppression Pool Suction Strainer
.2 RHR Pumps
.3 RHR Heat Exchangers
.4 B/C Water Leg Pump
.5 Containment Spray Header and Nozzles
.6 Suppression Pool Suction Valves F004A, F004B.
.7 RH Shutdown Cooling Suction Valves F006A and F006B
.8 Shutdown Cooling Inboard and Outboard Isolation Valves F009 and F008
.9 RH B Supply to Reactor Head Spray Valve F023
.10 RH C Full Flow Test Valve F021
.11 RH A (B) Full Flow Test Valves F024A and F024B
.12 RH A (B) Containment Outboard Isolation Valves F027A and F027B
.13 RH A(B) Containment Spray A(B) Shutoff Valves F028A and F028B
.14 RH A(B) to Containment Pool Cooling Shutoff Valves F037A and F037B
.15 LPCI From RH Shutoff Valves F042A, F042B, and F042C
.16 LPCI From RH Testable Check Valves F041A, F041B, and F041C
.17 RH Heat Exchanger Inlet Valves F047A and F047B
.18 RH Heat Exchanger Outlet CPS OPS ILT EXAM Page: 268 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Valves F003A and F003B
.19 RH B Radwaste First and Second Isolation Valves F049 and F040
.20 RH Heat Exchanger Bypass Valves F048A and F048B
.21 RH to Feedwater Shutdown Cooling Return Valves F053A and F053B
.22 RH Heat Exchanger First and Second Sample Valves F060A, F060B, F075A and F075B
.23 RH Pump Minimum Flow Recirc Valves F064A, F064B and F064C
.24 RH Heat Exchanger SSW Inlet and Outlet Valves F014A, F014B, F068A and F068B
.25 RH Fuel Pool Cooling Assist Suction Valve F066 CPS OPS ILT EXAM Page: 269 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 58 ID: 896349 Points: 1.00 Plant conditions are as follows:
- A power ascension is in progress.
- Reactor power is 35%.
- The Main Generator is synchronized to the grid.
Then, annunciator 5017-1C Overheating Gen Core was received.
The 'B' RO depresses the Core Monitor Filter pushbutton and observes that the trace returns to normal.
(1) What additional initial action is required to be taken?
(2) Based on the actions and observations of the 'B' RO, which of the following identifies the validity of the core monitor alarm (valid or invalid)?
A. (1) Lower generator load.
(2) Alarm is valid.
B. (1) Lower generator load.
(2) Alarm is NOT valid.
C. (1) Trip the Main Turbine.
(2) Alarm is valid.
D. (1) Check the operation of the Stator Cooling System.
(2) Alarm is NOT valid.
Answer: A Answer Explanation A is correct:
Per CPS 5017.01 (1C), Within 5 minutes; simultaneously:
Reduce load until:
- the alarm clears, OR
- until unloaded (including excitation), OR
- until alarm is determined to be false.
Depress FILTER push-button on Remote Core Monitor Panel (1H13-P826) for 1 minute, or until trace returns to normal.
- IF The trace returns to normal, THEN The alarm is due to overheating, and load reduction should continue.
- IF The trace does not return to normal, THEN Refer to CPS 3105.05, Generator (TG), Improper Operation of Core Monitor.
B is incorrect but plausible if the examinee incorrectly interprets the trace when the filter pushbutton is depressed.
CPS OPS ILT EXAM Page: 270 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version C is incorrect but plausible if the examinee incorrectly recalls the required actions for a core monitor alarm.
D is incorrect but plausible if the examinee incorrectly interprets the trace when the filter pushbutton is depressed, and also incorrectly recalls that generator load must be reduced while determining the validity of the alarm.
KA justification - this question meets the KA because the examinee must be able to describe the operational impact of a Generator Core Monitor alarm.
CPS OPS ILT EXAM Page: 271 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 58 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: 896349 User-Defined ID: CL-ILT-812632A Cross Reference Number:
Plant conditions are as follows: A power ascension is in Topic:
progress. Reactor power is 35%. The Main Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 272 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5017.01 (1C) Rev.
Revision Number: 26
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 245000 Main Turbine Generator and Auxiliary Systems Category / KA Statement: K5. Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS :
K5.07 Generator operations and limitations (CFR: 41.5 /
45.3)
RO Value: 2.6 SRO Value: 2.9 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 273 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 58 245008.11 EVALUATE given key Generator Gas System parameters, if needed DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
.1 Low Hydrogen Purity
.2 Generator Core Monitor Prompt Drop
.3 Excess Flow Check Valve Isolation
.4 Loss of Plant Service Water
.5 Loss of Seal Oil
.6 Falling Generator Gas Pressure CPS OPS ILT EXAM Page: 274 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 59 ID: 896350 Points: 1.00 The Fire Protection System was in a normal standby configuration when electrical power was lost to the Makeup Water Pump House (MWPH).
Which of the following describes the expected response of the Fire Protection Water System (FP) to these conditions?
Under these conditions...
A. ONLY 'A' Fire Pump has started.
B. ONLY 'B' Fire Pump has started.
C. BOTH 'A' AND 'B' Fire Pumps (0FP01PA/B) have started.
D. NEITHER 'A' NOR 'B' Fire Pumps (0FP01PA/B) have started.
Answer: A Answer Explanation A is correct - per N-CL-OPS-286000 Fire Protection - Detection:
The Fire Protection Water System is normally maintained pressurized by the Jockey Pump, located in the Makeup Water Pump House.
Any event that prevents the Jockey Pump from maintaining the Fire Protection Water System header pressure above the setpoint, such as loss of power from MWPH MCC A, will result in the A (140 + 3 psig and/or B (130 + 3 psig) Diesel Driven Fire Pump(s) to automatically starting on low system pressure.
Since the stem indicates that the only malfunction is a loss of power to the MWPH, the expected response of the FP system is for the 0FP01PA to automatically start at 140 psig to maintain pressure in the FP system.
B is incorrect but plausible if the examinee fails to correctly recall that the auto start setpoint for the 'A' Fire Pump is 10 psig higher than the auto start setpoint for the 'B' Fire Pump.
C is incorrect but plausible if the examinee fails to correctly recall that the auto start setpoint for the 'A' Fire Pump is 10 psig higher than the auto start setpoint for the 'B' Fire Pump.
D is incorrect but plausible if the examinee fails to correctly evaluate the impact of a loss of the fire protection jockey pump on the Diesel Driven Fire Pumps.
KA justification - this question meets the KA because the examinee is required to know how a loss of AC power to the Fire Protection Jockey Pump affects the Fire Protection System Diesel Driven Fire Pumps.
CPS OPS ILT EXAM Page: 275 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 59 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: 896350 User-Defined ID: CL-ILT-812633A Cross Reference Number:
The Fire Protection System was in a normal standby Topic:
configuration when electrical power was lost to Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 276 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- 3213.01E002 Rev. 10 Revision Number:
- N-CL-OPS-286000 Rev. 2 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS Modelled from River Bend NRC-05, OYS CERT-04) 2010 NRC Exam Q63 Question Source: (i.e. New, Modified Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised question for History: (i.e. Modified applicability to CPS distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: 286000 Fire Protection System Category / KA Statement: K6. Knowledge of the effect that a loss or malfunction of the following will have on the FIRE PROTECTION SYSTEM K6.01 A.C. electrical distribution:
Plant-Specific (CFR: 41.7 / 45.7)
RO Value: 3.1 SRO Value: 3.1 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 277 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 59 286000.11 EVALUATE given key FP FD FIRE PROTECTION - DETECTION System parameters, if needed DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
.1 Trip Signal
.2 Isolation Signal
.3 Auto Start Signal
.4 Condition/Lineup CPS OPS ILT EXAM Page: 278 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 60 ID: 896351 Points: 1.00 While shifting the SJAEs, what is the operational impact of losing the intercondenser loop seal?
A. Overloading the desiccant dryers due to increased off-gas flow.
B. Possible system isolation on a post treatment PRM high radiation alarm.
C. Overheating the catalyst section of the recombiner due to the loss of dilution steam flow.
D. Reduced system process flow (short cycling), resulting in a loss of main condenser vacuum.
Answer: D Answer Explanation D is correct - per CPS 4004.02 Loss of Vacuum, loss of the intercondenser loop seal will result in low/deteriorating vacuum and is a symptom for loss of vacuum.
A blown SJAE Intercondenser Loop Seal may be characterized by decreasing or zero OG Stream Flow (Recorder 1N66-R602A/B on 1H13-P845) due to flow being routed to the Main Condenser rather than through the SJAE-Recombiner train.
A is incorrect but plausible if the examinee incorrectly determines that a loss of the intercondenser loop seal will result in high OG flow rate. As explained above a blown SJAE Intercondenser Loop Seal may be characterized by decreasing or zero OG Stream Flow (Recorder 1N66-R602A/B on 1H13-P845) due to flow being routed to the Main Condenser rather than through the SJAE-Recombiner train.
B is incorrect but plausible if the examinee incorrectly recalls that a loss of the intercondenser loop seal will cause OG radiation levels to rise resulting in an OG system isolation.
C is incorrect but plausible if the examinee determines that a loss of the intercondenser loop seal will cause a loss of dilution steam flow to the OG recombiners.
KA justification - this question meets the KA because the examinee is required to predict the impact of a loss of the OG Steam Jet Air Ejector Intercondenser loop seal on Main Condenser vacuum.
CPS OPS ILT EXAM Page: 279 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896351 User-Defined ID: CL-ILT-889414 Cross Reference Number:
While shifting the SJAEs, what is the operational impact of Topic:
losing the intercondenser loop seal?
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 280 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 4004.02 Rev. 5 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised CL-ILT-1530; History: (i.e. Modified added plausibility distractor b to make statements for each of the plausible based on OTPS distractors and provided KA review) justification statement.
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: 271000 Offgas System Category / KA Statement: A1. Ability to predict and/or monitor changes in parameters associated with operating the OFFGAS SYSTEM controls including: A1.01 Condenser vacuum (CFR: 41.5 / 45.5)
RO Value: 3.3 SRO Value: 3.2 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 281 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 60 271000.11 EVALUATE given key OFFGAS System parameters, if needed DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
.1 Desiccant Dryer Discharge High Moisture Content
.2 Double Block and Seal Failure
.3 Startup Off Gas Flow High Range High
.4 Startup Off Gas Flow High Range High-High
.5 Normal Off Gas Flow Low Range Low
.6 Lowering Main Condenser Vacuum
.7 Lowering Recombiner temperatures
.8 High Condensate System temperatures
.9 Adsorber Inlet Relative Humidity
.10 Adsorber Bed Depth
.11 Adsorber Air Velocity
.12 Adsorber Particle Size
.13 Adsorber Bed Temperature
.14 High Hydrogen Concentration CPS OPS ILT EXAM Page: 282 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 61 ID: 896352 Points: 1.00 The plant is operating at rated thermal power with annunciator 5015-1E Low Level LP Htr 3A locked in due to a malfunctioning Normal Drain Valve controller.
This malfunction has NOT caused level alarms on any other Feedwater Heaters.
Under these conditions, the condensate drain temperature from LP Htr 3A to LP Htr 2A will
_____(1)_____.
(2) Which of the following actions is required?
A. (1) lower (2) Take prompt action to manually control level in LP Htr 3A at 1PA05J.
B. (1) rise (2) Take prompt action to manually control level in LP Htr 3A at 1PA05J.
C. (1) lower (2) Actions to recover level in LP Htr 3A may be delayed until level alarms are received on other FW Heaters.
D. (1) rise (2) Actions to recover level in LP Htr 3A may be delayed until level alarms are received on other FW Heaters.
Answer: B Answer Explanation B is correct:
During normal plant operation, the Low Pressure Feedwater Heaters receive extraction steam from the Low Pressure Turbines and preheats Reactor Condensate flowing through tubes in the feedwater heaters. The extraction steam is condensed in the feedwater heater and then drains through the heater normal drain valves to the next upstream feedwater heater (cascading drains).
Per CPS 3102.01 Extraction Steam / Htr Vent & Drains (ES/HD) section 8.3.1 Feedwater Heater Abnormal Level, a low level in the heater may cause level to be too near the bottom of the Feedwater Heater "snorkel" which will introduce a possible steam path into the drain cooler which would cause increased vibration and would lead to severe tube damage.
If FW Heater tubes are ruptured, condensate flowing through the tubes will flood the shell side of the affected FW heater.
Per CPS 3102.01 section 8.3.3 Feedwater Heater High Drain Temperature, low FW Heater level will result in high heater drain temperature cascading to the upstream heater.
A is incorrect but plausible if the examinee misunderstands how low level in a FW Heater affects FW Heater Drain Temperature.
C is incorrect but plausible if the examinee misunderstands how low level in a FW Heater affects FW Heater Drain Temperature and also misunderstands the procedural requirements for mitigating low level conditions in a FW Heater.
CPS OPS ILT EXAM Page: 283 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version D is incorrect but plausible if the examinee misunderstands the procedural requirements for mitigating low level conditions in a FW Heater. It is also plausible based on CPS plant OPEX where the MCR did not recognize the implications of operating a FW heater with a low level condition which resulted in heater tube ruptures.
KA justification - this question meets the KA because the examinee has to predict the impact of a FW heater low level condition on the Reactor Condensate system, and what actions are required to mitigate the low feedwater heater level condition.
CPS OPS ILT EXAM Page: 284 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896352 User-Defined ID: CL-ILT-812635 Cross Reference Number:
The plant is operating at rated thermal power with annunciator Topic:
5015-1E Low Level LP Htr 3A locked Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 285 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5015.01 (1E) Rev.
Revision Number: 25
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 256000 Reactor Condensate System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.09 Low feedwater heater level (CFR: 41.5 / 45.6)
RO Value: 2.8 SRO Value: 2.8 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 286 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 61 239003.11 EVALUATE given key EXTRACTION STEAM, HEATER VENTS & DRAINS System parameters, if needed DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
.1 Low heater level on system performance
.2 Any heater reaching it's high level setpoint
.3 High heater level on system performance
.4 Any heater reaching it's high-high level setpoint
.5 Heater string isolation valve closure
.6 Loss of control power
.7 Effect on other heaters when heaters are removed from service/
returned to service
.8 Indications of an ES Bellows rupture
.9 Respond to FW Heater High Drain Temperature CPS OPS ILT EXAM Page: 287 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 62 ID: 896353 Points: 1.00 The reactor is currently operating at 42% with the FW system aligned as shown in the graphic below.
A power reduction is planned from 42% to 28% power.
(1) As power is lowered from 42% to 28%, how is indicated RPV water level affected?
Given the below indications, TDRFP 'A' speed is being controlled _____(2)_____.
A. (1) indicated level lowers (2) directly by the Start-Up Level Controller C34-R602 B. (1) indicated level stays the same (2) directly by the Start-Up Level Controller C34-R602 C. (1) indicated level lowers (2) by the Start-Up Level Controller C34-R602 via the RFPT A Flow Controller C34-R601A CPS OPS ILT EXAM Page: 288 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version D. (1) indicated level stays the same (2) by the Start-Up Level Controller C34-R602 via the RFPT A Flow Controller C34-R601A Answer: A Answer Explanation A is correct:
Per CPS 3103.01 Feedwater (FW), discussion step 2.1.6, at < 82% steam flow, the FW Control System Steam Programming function modifies the input to the S/U and Master Level controllers such that RPV level is controlled below the setpoint. When steam flow is < 37%, the maximum difference between indicated level and the setpoint is 5 inches. Steam Programming serves to increase the efficiency, of the RPV moisture separators, at less than rated steam flow.
From 42% to 37% power, steam programming will function to lower indicated RPV level.
Per N-CL-OPS-259002 Feedwater Level Control, the Startup Level Controller R602 uses a single element control principle. The feedwater control system generates a feedwater flow demand error signal by comparing actual vessel level to a level setpoint. The flow demand error is then passed to one of the turbine driven RFP speed control systems or motor driven RFP feed regulating valve position control system. Turbine speed or valve position is varied in response to the feedwater flow demand signal in order to maintain reactor vessel level. When all running RFP loop flow controllers are in MANUAL, the Startup Level Controller controls the selected device. The Start Mode Actuator Selector switch determines the RFP being controlled. The MANUAL indicating light is inhibited on the loop flow controller for the RFP selected to the startup level controller. Both the manual and auto indicating lights on the loop flow controller for the device selected by the Start Mode Actuator Selector switch are extinguished indicating which device is being controlled by the Startup Level Controller.
B is incorrect but plausible if the examinee fails to recall the function of steam programming and determines that indicated water level remains the same during the down power.
C is incorrect but plausible if the examinee fails to recall that C34-R601A is not in the circuit in single element control.
D is incorrect but plausible if the examinee fails to recall the function of steam programming and determines that indicated water level remains the same during the down power, and also fails to recall that C34-R601A is not in the circuit in single element control.
KA justification - this question meets the KA because the examinee is required to determine how indicated RPV water level is affected when lowering reactor power.
CPS OPS ILT EXAM Page: 289 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 62 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: 896353 User-Defined ID: CL-ILT-812636A Cross Reference Number:
The reactor is currently operating at 42% with the FW system Topic:
aligned as shown in the graphic below Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 290 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3103.01 Rev. 26a Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 259001 Reactor Feedwater System Category / KA Statement: A3. Ability to monitor automatic operations of the REACTOR FEEDWATER SYSTEM including: A3.04 Reactor water level (CFR: 41.7 / 45.7)
RO Value: 3.8 SRO Value: 3.7 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 291 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 62 259002.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following FEEDWATER CONTROL System components.
.1 Narrow Range Water Level Instrumentation
.2 Rector Water Level Chennel Selector Switch
.3 FWC System Steam Programming Function
.4 Feed Pump Discharge Flow Instrumentation
.5 FeedWater Inlet Flow Instrumentation
.6 Main Steam Flow Instrumentation
.7 Flow Controller, FC-FW231
.8 RFPT Manual Potentiometers
.9 RFPT Auto/Manual Transfer Switches
.10 Startup Mode Actuator Switch
.11 Startup Level Controller
.12 Master Level Controller
.13 Reactor Feed Pump (RFP) Loop Flow Controllers CPS OPS ILT EXAM Page: 292 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 63 ID: 896354 Points: 1.00 The plant was at rated thermal power when a transient occurred.
Which of the following transients will result in the RR System indications shown in the attached graphic?
A. Turbine Trip B. Manual ARI Initiation C. RPV Level < Level 2 D. DW Pressure > 1.68 psig Answer: A Answer Explanation A is correct:
The indications in the graphic show the RR Pumps operating in slow speed (5A & 5B breakers tripped, 1A/B & 2A/B breakers closed).
Per 5003.02 (2F & 2M), RR Pumps A & B will transfer to slow speed if the turbine trips when 33.3%
power.
B is incorrect but plausible - per CPS 5008.01 (1K & 1L) an automatic ARI initiation (Level 2 or High RPV pressure) will result in the RR Pumps tripping to off, however a manual ARI initiation will not.
C is incorrect but plausible - RPV Level < 2 will result in an ARI initiation, which will trip the RR Pumps to off (1A/B, 2A/B, and 5A/B) breakers will trip open.
D is incorrect but plausible - High DW pressure will cause the RR FCVs to lockout, and would be indicated by FCV Motion Inhibit Reset A/B white lights being illuminated.
KA justification - this question meets the KA because the examinee has to determine how the RR Pump indicating lights will respond to various actuations listed in the stem.
CPS OPS ILT EXAM Page: 293 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 63 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: 896354 User-Defined ID: CL-ILT-812637 Cross Reference Number:
The plant was at rated thermal power when a transient Topic:
occurred. Which of the following transients Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 294 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5003.02 (2F &
Revision Number: 2M) Rev. 34f
- CPS 5008.01 (1K & 1L)
Rev. 27 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: 202001 Recirculation System Category / KA Statement: A4. Ability to manually operate and/or monitor in the control room: A4.05 Lights and alarms (CFR: 41.7 / 45.5 to 45.8)
RO Value: 3.3 SRO Value: 3.3 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 295 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 63 202001.04 STATE the physical location and function of the following Reactor Recirculation system components, controls, indicators, and/or sensors.
.1 Reactor Recirculation Pumps Controls
.2 Recirculation Flow Control Valve Controls
.3 Recirculation Pump Suction and Discharge Valves Controls
.4 Hydraulic Power Units Controls
.5 Low Frequency Motor Generator (LFMG) Set Controls
.6 Recirculation Flow Instrumentation CPS OPS ILT EXAM Page: 296 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 64 ID: 896355 Points: 1.00 If the main feed breaker to Auxiliary Building MCC 1F trips while at rated thermal power, how would operation of Reactor Recirculation Hydraulic Power Unit (HPU) subloop A1 be affected?
Subloop 1A power is...
A. automatically transferred to AB MCC 1G.
B. automatically transferred to AB MCC 1H.
C. automatically transferred to AB MCC 1I.
D. NOT transferred; subloop A1 remains deenergized.
Answer: D Answer Explanation D is correct:
- The 4 RR HPU subloops are powered from non-vital Motor Control Centers (MCCs) in the Auxiliary Building (AB MCC 1F, 1H, 1G, and 1I).
- AB MCC 1F, 1H, 1G, and 1I are powered from two non-vital 480V Unit Substations (1L and 1M). AB MCC 1F and 1H are powered from Unit Sub 1L, and AB MCC 1G and 1I are powered from Unit Sub 1M.
- 480V Unit Substation 1L and 480V Unit Substation 1M are powered from 6.9 KV Bus 1A and 1B respectively.
The MCCs listed above are NOT equipped with cross tie breakers, so if the main feed breaker to the MCC trips, the associated MCC will deeneergize along with all loads supplied from the MCC.
The Unit Substations listed above are equipped with cross tie breakers fed from the opposite 6.9KV Bus, so if the unit substation deenergizes due to a loss of it's associated 6.9KV feed, the associated Unit Sub cross tie breaker will automatically close to reenergize the unit sub and associated loads.
A is incorrect but plausible if the examinee fails to recall that 480V MCCs are not equipped with cross-tie breakers. The examinee may select this choice if he/she incorrectly believes that the alternate power supply to AB MCC 1F is AB MCC 1G.
B is incorrect but plausible if the examinee fails to recall that 480V MCCs are not equipped with cross-tie breakers. The examinee may select this choice if he/she incorrectly believes that the alternate power supply to AB MCC 1F is AB MCC 1H.
C is incorrect but plausible if the examinee fails to recall that 480V MCCs are not equipped with cross-tie breakers. The examinee may select this choice if he/she incorrectly believes that the alternate power supply to AB MCC 1F is AB MCC 1I.
KA justification - this question meets the KA because the examinee is required to have knowledge of the electrical power supplies to the RR HPUs to answer the question.
CPS OPS ILT EXAM Page: 297 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 64 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: 896355 User-Defined ID: CL-ILT-812638A Cross Reference Number:
If the main feed breaker to Auxiliary Building MCC 1F trips Topic:
while at rated thermal power, how woul Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 298 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3302.01E001 Rev.
Revision Number: 9
- CPS 3502.01E001 Rev.
16 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-PEO)
KA Data KA Number / System Name: 202002 Recirculation flow Control System Category / KA Statement: K2. Knowledge of electrical power supplies to the following: K2.02 Hydraulic power unit:
Plant-Specific (CFR: 41.7)
RO Value: 2.6 SRO Value: 2.6 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 299 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 64 202001.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following Reactor Recirculation System components.
.1 Reactor Recirculation Pumps
.2 RR Pump Mechanical Seal
.3 Recirculation Flow Control Valves
.4 Recirculation Pump Suction and Discharge Valves
.5 Jet Pumps
.6 Hydraulic Power Units
.7 HPU Servo Control Valve
.8 HPU Pilot Operated Isolation Valve
.9 HPU Pilot Operated Lockout Valve
.10 HPU Shuttle Valve
.11 HPU Solenoid Operated Isolation Valves
.12 HPU Subloop Discharge Bypass Valve
.13 Low Frequency Motor Generator (LFMG) Sets
.14 Piping
.15 Flow Diverters
.16 Recirculation Flow Instrumentation CPS OPS ILT EXAM Page: 300 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 65 ID: 896356 Points: 1.00 Core Alterations are in progress with 22' 10" of water above the reactor flange.
4160 VAC Bus 1A1 is out of service in support of outage work.
Which ONE of the following would require IMMEDIATE suspension of core alterations?
A. Division 3 Diesel Generator is declared inoperable.
B. RHR B Shutdown Cooling is declared inoperable.
C. An inadvertent Containment Building HVAC isolation.
D. The "B" Main Control Room HVAC air handling unit trips.
Answer: D Answer Explanation D is correct:
Per CPS 3007.01 PREPARATION AND RECOVERY FROM REFUELING OPERATIONS step 4.7, Core Alterations SHOULD be stopped for any of the following conditions:
- 9. Loss of both trains of Control Room Ventilation System. ITS LCO 3.7.3 & 3.7.4 In addition, ITS 3.7.3 Required Action G.2 requires immediate suspension of core alterations if both Control Room Ventilation subsystems become inoperable during core alterations.
With Bus 1A1 out of service for maintenance, a trip of the B Main Control Room HVAC Air Handling Unit would result in a loss of both Control Room Ventilation trains.
A is incorrect but plausible if the examinee incorrectly believes that inoperability of the Div 3 DG along with a 4160V 1A1 outage requires suspension of core alterations due to a loss of the minimum number of AC power sources. ITS LCO 3.8.2 only requires one operable DG in mode 5. With Div 2 DG operable, suspension of core alterations is not required.
B is incorrect but plausible - ITS 3.9.8 requires one RHR shutdown cooling subsystem to be OPERABLE and in operation. Per ITS 3.9.8 Condition A, if the required RHR shutdown cooling subsystem is inoperable, verify an alternate method of decay heat removal is available within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Inoperability of the B RHR SDC subsystem does NOT require immediate suspension of core alts.
C is incorrect but plausible - it is desired, but not required to operate Containment Building Ventilation during core alterations. A loss of CBV does not require immediate suspension of core alts.
KA justification - this question meets the KA because the examinee has to analyze the conditions in the stem and determine what conditions require suspending core alterations per Technical Specification requirements.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 65 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: 896356 User-Defined ID: CL-ILT-889438A Cross Reference Number:
Core Alterations are in progress with 22' 10" of water above the Topic:
reactor flange. 4160 VAC Bus 1A Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 302 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3007.01 Rev. 18 Revision Number:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - duplicate of CL-ILT-Bank, Modified) 6864 Low KA Justification (if NA required):
Revision History: Revision Improved answer History: (i.e. Modified explanation and added distractor b to make plausibility and KA plausible based on OTPS justification statements.
review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2RI)
KA Data KA Number / System Name: 288000 Plant Ventilation Systems Category / KA Statement: 2.2.40 Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5 / 45.3)
RO Value: 3.4 SRO Value: 4.7 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.2 & 43.5 Associated objective(s):
Question 65 LP86602.01.02 List, as a minimum ten (10) conditions which shall require the suspension of core alterations.
CPS OPS ILT EXAM Page: 303 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version CPS OPS ILT EXAM Page: 304 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 66 ID: 896357 Points: 1.00 The unit was operating at rated thermal power (3368 MWth and 1116 MWe) when the following annunciators were received:
- 5067-8L SRV Monitoring System Trouble
- 5066-5B ADS or Safety Relief Valve Leaking Current plant conditions are as follows:
Parameter Value Trend Generator Output 1100 MWe stable
'A' SRV Solenoid Lights (above the SRV keylock switches) All green NA
'B' SRV Solenoid Lights (on vertical section of P601) All deenergized NA SRV F041G Tailpipe Temperature 290°F stable Remaining SRV Tailpipe Temperatures 85°F stable PPC Display 2H (Containment Support Display) (see below) red for 41G and stable 51C Under these conditions, which of the following describes the status of the Safety Relief Valves?
A. SRV 41G is leaking; all other SRVs are closed.
B. SRV 41G is fully open; all other SRVs are closed.
CPS OPS ILT EXAM Page: 305 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version C. SRV 41G is fully open; SRV 51C is partially open.
D. SRV 41G is partially open; all other SRVs are closed.
Answer: D Answer Explanation D is correct:
Annunciator 5067-8L SRV Monitoring System Trouble alarms whenever the SRV acoustic monitor detects flow downstream of the SRV.
Annunciator 5066-5B ADS or Safety Relief Valve Leaking alarms whenever an SRV tailpipe temperature reaches 220°F.
Per 4009.01 Inadvertent Opening Safety/Relief Valve, actions are not required to be taken per the off-normal procedure for a leaking SRV (confirmed by no acoustic monitor noise and no MWe decrease).
Since MWe has decreased and acoustic monitor alarms are present as indicated by the presence of 5067-8L and PPC Display 2H, an SRV is at least partially open.
Per N-CL-OPS-239001, each SRV is rated at 936,454 lbm per hour at 1205 psig inlet pressure (approximately 6.5% of total steam flow). Since MWe has only lowered 16 MWe (~1.4%), SRV 41G is only partially open.
A is incorrect but plausible if the examinee fails to recall that leaking SRVs will not result in a decrease in MWe or acoustic monitor noise.
B is incorrect but plausible if the examinee fails to recall that a fully open SRV will pass 6.5% of steam flow and that tailpipe temperatures for a full open SRV are typically > 375°F.
C is incorrect but plausible if the examinee fails to recall that a fully open SRV will pass 6.5% of steam flow and that tailpipe temperatures for a full open SRV are typically > 375°F, and also believes that the acoustic monitor alarm for 51C proves that 51C is partially open. An open SRV's flow noise can be picked up by another SRV's acoustic monitor. This phenomenon is called Cross Talk. Acoustic Monitors will indicate more SRVs are open than actually are. Use alternate indications (e.g. tailpipe temperatures, MSL Flows) to validate the actual number of SRVs open. Since the tailpipe temperature for SRV 51C is at ambient, it can be concluded that 51C is closed.
KA Justification - this question meets the KA because the examinee has to use redundant and diverse indications to validate the status of the SRVs.
CPS OPS ILT EXAM Page: 306 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 66 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: 896357 User-Defined ID: CL-ILT-812640 Cross Reference Number:
The unit was operating at rated thermal power (3368 MWth and Topic:
1116 MWe) when the following annuncia Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 307 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 5067.08 (8L) Rev.
Revision Number: 31
- CPS 4009.01 Rev. 12c
- CPS 5066.05 (5B) Rev.
28 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New question Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: NA Category / KA Statement: 2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 / 43.5 / 45.4)
RO Value: 4.3 SRO Value: 4.3 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.7 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 308 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 66 DB400901.04 Explain the methods that can be used to determine which SRV has lifted.
CPS OPS ILT EXAM Page: 309 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 67 ID: 896358 Points: 1.00 Plant conditions are as follows:
- Refueling operations are in progress.
- Upper Containment Fuel Pool Gates are removed.
- RHR 'B' is operating in Shutdown Cooling Mode.
- Fuel Pool Cooling Pump 'B' is operating.
- Control Rod Drive Pump (CRD) 'B' is operating and injecting water to the RPV at 40 gpm.
- Reactor Water Cleanup system is in service and rejecting water to Radwaste at 40 gpm.
- The Main Condenser is available.
- The CY Storage Tank is available.
Then, the RWCU pumps tripped (cause unknown), causing the FC Surge Tank level to rise.
Under these conditions, which of the following is a procedurally approved method to stabilize FC Surge Tank level from the MCR without securing CRD Pump 'B'?
A. Drain water to Radwaste using the RHR system.
B. Drain water to the Main Condenser using the Main Steam (MS) system.
C. Drain Reactor Vessel Pool to Condenser per CPS 3317.01 Fuel Pool Cooling and Cleanup (FC).
D. Reject Skimmer Surge Tank water to Cycled Condensate System per CPS 3317.01 Fuel Pool Cooling and Cleanup (FC).
Answer: A Answer Explanation A is correct:
Per CPS 3317.01 Fuel Pool Cooling & Cleanup, section 8.2.8 Maintaining Vessel Pool Level, Vessel Head Removed, CRD Injecting Water, the methods listed to maintain level are as follows:
- Reject water from RT to the condenser or radwaste
- Drain FC water to Fuel Building RE
- Reject FC water to CY
- Drain vessel pool to condenser With the RT pumps tripped, the only method available to control RPV level from the MCR is by rejecting RPV water to Radwaste from RHR. This is accomplished by opening 1E12-F049 and 1E12-F040 from 1H13-P601.
B is incorrect but plausible - RPV Level Control using the MSL Inboard Drains is a proceduralized method for RPV level control, however this method can only be used in Mode 4.
C is incorrect but plausible - this is a proceduralized method for RPV level control but requires local valve manipulations outside the MCR.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version D is incorrect but plausible - this is a proceduralized method for RPV level control but requires local valve manipulations outside the MCR.
KA Justification - this question meets the KA because the examinee has to determine which systems can be used to control RPV level during fuel handling operations in the event of a loss of the normal level control method.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 67 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: 896358 User-Defined ID: CL-ILT-812641A Cross Reference Number:
Plant conditions are as follows: Refueling operations are in Topic:
progress. Upper Containment Fuel Poo Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 312 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- CPS 3317.01 Rev. 29 Revision Number:
- CPS 3312.03 Rev. 10
Question History: (i.e. LGS 2005 DAEC NRC exam NRC-05, OYS CERT-04) Q70 Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised DAEC question for History: (i.e. Modified applicability to CPS distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (2-RI)
KA Data KA Number / System Name: NA Category / KA Statement: 2.1.44 Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. (CFR: 41.10 / 43.7 / 45.12)
RO Value: 3.9 SRO Value: 3.8 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.7 CPS OPS ILT EXAM Page: 313 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 67 LP85801.2.1.44 Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the fuel handling area, communications with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. (Moved from .2.2.30)
CPS OPS ILT EXAM Page: 314 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 68 ID: 896359 Points: 1.00 Which, if any, of the following methods are permitted to be used to add positive reactivity to the core during end of cycle coastdown to maximize electrical output?
(1) Raising Pressure Regulator Setpoint (2) Reducing Feedwater inlet temperature to the Reactor (FFWTR)
A. Both methods can be used.
B. Neither method can be used.
C. Method 1 can be used, but NOT method 2 D. Method 2 can be used, but NOT method 1 Answer: A Answer Explanation A is correct:
There are two proceduralized methods for adding positive reactivity to the core for the purpose of maximizing plant electrical energy output during end of cycle coastdown. They are:
- CPS 3102.01 Final Feedwater Temperature Reduction (FFWTR) - FFWTR is implemented at the end of a fuel cycle to maximize power generation and optimize fuel burnout. FFWTR is accomplished by removing extraction steam to both #6 FW Heaters.
- Pressure Regulator adjustment per CPS 3005.01 Unit Power Changes, section 8.3 End of Cycle Coastdown - maximizes plant electrical energy output by increasing pressure set to maintain reactor pressure as close to full power steam dome pressure as possible. During each coastdown, the reduced steam flow from the RPV results in a lower steam line pressure drop between the reactor and the TCVs. As a result, reactor steam dome pressure decreases as power level decreases during the coastdown. Increasing the pressure control setpoint maintains the reactor steam dome pressure at its full power value, thereby yielding a slight gain in core reactivity and reactor outlet steam flow, resulting in an increase in plant gross electrical output.
B is incorrect but plausible if the examinee fails to recall the above methods for maximizing plant electrical energy output during end of cycle coastdown. Examinee may select this response based on 3005.01 Limitation 6.1.9 that states that reactivity control is only allowed with control rods, recirc flow, or FFWTR.
C is incorrect but plausible if the examinee fails to recall that raising the pressure regulator setpoint can be used to maximize plant electrical energy output during end of cycle coastdown.
D is incorrect but plausible if the examinee fails to recall that FFWTR can be used to maximizing plant electrical energy output during end of cycle coastdown.
KA justification - this question meets the KA because the examinee has to determine what proceduralized methods exist for maximizing plant electrical energy output during the end of cycle coastdown.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 68 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: 896359 User-Defined ID: CL-ILT-812642 Cross Reference Number:
Which, if any, of the following methods are permitted to be used Topic:
to add positive reactivity to the Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 316 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: 0General Data Technical Reference with
- CPS 3005.01 Rev. 40 Revision Number:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: NA Category / KA Statement: 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR: 41.10 / 43.6 / 45.6)
RO Value: 4.1 SRO Value: 4.3 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.6 CPS OPS ILT EXAM Page: 317 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 68 LP87441.01.05 Recall the following CPS 3005.01 limitations while operating the plant or on an exam:
.1 Reactor Power Changes and Reactivity Management
.2 First Stage Turbine Pressure
.3 Control Rod Sequence
.4 MELLLA Limit Operational Concerns.
.5 Unit Power Change general limitations CPS OPS ILT EXAM Page: 318 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 69 ID: 896360 Points: 1.00 Average reactor coolant temperature is 220°F.
Within procedural limitations and Technical Specifications definitions, which of the following is/are the possible MODE(s) of operation that the plant could be operating in at this temperature?
ONLY the following MODE(s):
A. 2 B. 3 C. 2 OR 3 D. 1, 2, OR 3 Answer: C Answer Explanation C is correct - per ITS Definitions 1.1, MODE is defined as follows:
A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
Per ITS Table 1.1-1 MODES:
Mode Title Reactor Mode Switch Position Average Reactor Coolant Temperature (°F) 1 Power Operation Run NA 2 Startup Refuel (a) or Startup / Hot Standby NA 3 Hot Shutdown (a) Shutdown > 200 4 Cold Shutdown (a) Shutdown < 200 5 Refueling (b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensioned.
Per CPS 3002.01 Heatup and Pressurization, Mode 1 is entered after the reactor has been been pressurized to ~ 910 psig with APRMs between 5% and 12%, which is well past 220°F.
Therefore, the only modes that are possible at 220°F are modes 2 and 3.
A is incorrect but plausible if the examinee fails to recall that Mode 3 is entered with the Mode Switch in Shutdown with reactor coolant temperature > 200°F.
B is incorrect but plausible if the examinee fails to recall that reactor heatup and pressurization is performed while in Mode 2.
D is incorrect but plausible if the examinee fails to recall that Mode 1 is entered after heatup and pressurization is complete between 5% and 12% power. The examinee may select this choice based on the fact that ITS Table 1.1-1 lists NA for the temperature requirement for Mode 1.
KA justification - this question meets the KA because the examinee must be able to determine ITS mode of operation from the conditions listed in the stem.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version CPS OPS ILT EXAM Page: 320 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 69 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: 896360 User-Defined ID: CL-ILT-812643 Cross Reference Number:
Average reactor coolant temperature is 220?F. Within Topic:
procedural limitations and Technical Specific Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 321 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- ITS Table 1.1-1 Revision Number:
Question History: (i.e. LGS 2011 Grand Gulf NRC NRC-05, OYS CERT-04) Exam Q48 Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised question for CPS History: (i.e. Modified applicability; added distractor b to make plausibility and KA plausible based on OTPS justification statements.
review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: NA Category / KA Statement: 2.2.35 Ability to determine Technical Specification Mode of Operation. (CFR: 41.7 /
41.10 / 43.2 / 45.13)
RO Value: 3.6 SRO Value: 4.5 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.7 & 41.10 10CFR55-43 (SRO) Data: 43.2 Associated objective(s):
Question 69 LP85802.2.2.35 Ability to determine Technical Specification Mode of Operation. (Moved from 2.1.22)
CPS OPS ILT EXAM Page: 322 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version CPS OPS ILT EXAM Page: 323 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 70 ID: 896361 Points: 1.00 In the following M05 diagram, 1HD039A is normally _____(1)_____ at rated thermal power and fails
_____(2)_____ on a loss of air.
A. (1) open (2) open B. (1) open (2) closed C. (1) closed (2) open D. (1) closed (2) closed Answer: B Answer Explanation B is correct:
Per M05-1001 Sht. 001, valves on M05 drawings are depicted in their normal full plant operation position.
A valve that is clear is normally open during full plant operation and a valve that is blackened in is normally closed at full plant operation.
CPS OPS ILT EXAM Page: 324 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version In addition, air operated valves are shown in their normal position at full plant operation with the state of their air operators (loaded or unloaded). If the valve symbol shows the valve normally closed with its air operator loaded the valve fails open. If the valve symbol shows the valve normally open with its air operator loaded the valves fails closed.
Therefore, in the graphic shown in the question stem, the valve (1HD039A) is normally open during full plant operation and fails closed on a loss of air.
A is incorrect but plausible if the examinee fails to correctly recall the symbology for an air operated valve that fails closed on a loss of air.
C is incorrect but plausible if the examinee fails to correctly recall the symbology for an air operated valve that is normally open at full plant operation and the symbology for a valve that fails closed on a loss of air.
The examinee may select this choice based on the knowledge that electrical prints (E02 prints) are shown in the "on the shelf" configuration and assumes that the mechanical prints are drawn the same way.
D is incorrect but plausible if the examinee fails to correctly recall the symbology for an air operated valve that is normally open at full plant operation and also fails to recall the symbology for a valve that fails closed on a loss of air . The examinee may select this choice based on the knowledge that components in the electrical prints (E02 prints) are shown in the "on the shelf" configuration and assumes that the mechanical prints are drawn the same way.
CPS OPS ILT EXAM Page: 325 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version KA justification - this question meets the KA because the examinee has to interpret the symbols on a mechanical print in order to answer the question.
CPS OPS ILT EXAM Page: 326 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 70 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: 896361 User-Defined ID: CL-ILT-812644 Cross Reference Number:
In the following M05 diagram, 1HD039A is normally Topic:
_____(1)_____ at rated thermal power and fails _
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 327 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with M05-1001-1 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-S)
KA Data KA Number / System Name: NA Category / KA Statement: 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (CFR:
41.10 / 45.12 / 45.13)
RO Value: 3.5 SRO Value: 3.9 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: NA Associated objective(s):
Question 70 LP85802.2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.
(Moved from 2.1.24)
CPS OPS ILT EXAM Page: 328 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version CPS OPS ILT EXAM Page: 329 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 71 ID: 896362 Points: 1.00 Which ONE of the following describes the bases for the Minimum Critical Power Ratio (MCPR) Safety Limit?
The MCPR Safety Limit is established to ensure that...
A. the fuel design limit of 280 cal/gm is NOT exceeded during a Control Rod Drop accident.
B. the 1% plastic strain limit on the cladding is NOT exceeded during normal power operations.
C. the peak cladding temperature does NOT exceed 2200°F following a postulated design basis LOCA.
D. at least 99.9% of the fuel rods in the core would NOT experience the onset of transition boiling during operational transients.
Answer: D Answer Explanation D is correct - per ITS B2.1.1, the MCPR fuel cladding integrity SL ensures that during normal operation and during AOOs, at least 99.9% of the fuel rods in the core do not experience transition boiling.
A is incorrect but plausible - this is the bases for Control Rod Pattern (ITS B3.1.6) and Control Rod Block Instrumentation (Rod Pattern Controller) (ITS 3.3.2.1).
B is incorrect but plausible - this is the bases for LHGR (ITS B3.2.3).
C is incorrect but plausible - this is the bases for APLHGR (ITS B3.2.1).
KA Justification - this question meets the KA because the examinee must have knowledge of the bases for the ITS MCPR Safety Limit in order to answer.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 71 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: 896362 User-Defined ID: CL-ILT-812645 Cross Reference Number:
Which ONE of the following describes the bases for the Topic:
Minimum Critical Power Ratio (MCPR) Safety Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 331 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- ITS B2.1.1 Revision Number:
- ITS B3.1.6
- ITS B3.3.2.1
- ITS B3.2.3
Question History: (i.e. LGS 2009 QC NRC Exam Q69 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Added KA justification and History: (i.e. Modified plausibility statements.
distractor b to make plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-F)
KA Data KA Number / System Name: NA Category / KA Statement: 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions l for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)
RO Value: 3.2 SRO Value: 4.2 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.5 & 41.7 10CFR55-43 (SRO) Data: 43.2 CPS OPS ILT EXAM Page: 332 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 71 LP85802.2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
CPS OPS ILT EXAM Page: 333 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 72 ID: 896363 Points: 1.00 You are an operator currently working in the drywell on an assigned task during a refuel outage.
The RWP controlling your task includes the following information:
- RWP Dose Entry Limit 300 mrem
- ED Dose Alarm 240 mrem
- Dose Rate Alarm 800 mrem/hr The actual dose rate in your work area is 60 mrem/hr.
You have accumulated 191 mrem and require more time in the area to complete the task.
Which of the following describes your response to the given situation while maximizing your time working on the task and also meeting the requirements of RP-AA-1008 Unescorted Access To And Conduct In Radiologically Controlled Areas, and why?
A. Continue to work in the area for 45 - 48 minutes, because the requirement is to leave the RCA prior to reaching the ED Dose Alarm setpoint.
B. Continue to work in the area for up to 74 minutes because the requirement is to leave the RCA prior to exceeding the RWP Dose Entry Limit.
C. Exit the area immediately because the requirement is to leave the RCA when your ED is approaching or has reached 80% of the ED Dose Alarm setpoint.
D. Continue to work in the area until the ED Dose Alarm is received because the requirement is to leave the RCA when you receive the ED Dose Alarm setpoint.
Answer: C Answer Explanation C is correct:
Per RP-AA-1008 step 4.3:
4.3. LEAVE the RCA as quickly as possible, consistent with safety, for any of the following reasons:
- When instructed or signaled to do so by Radiation Protection Department personnel.
- Failure or suspected failure of personal protective equipment
- Unexpected deterioration of radiological conditions
- Loss of or damage to any personal dosimetry
- When electronic dosimetry is approaching or has reached 80% of the accumulated dose or dose rate alarm setpoint.
- Assembly sirens sound.
- Completion of work assignment
- Injury
- Unexpected area radiation monitor alarm 191 mrem is 79.6% of the ED dose alarm (191 / 240 = 79.6%)
CPS OPS ILT EXAM Page: 334 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version A is incorrect but plausible if the examinee incorrectly believes that RP-AA-1008 permits continuing until just prior to reaching the cumulative dose alarm. If the worker stays in the area for 45 minutes, his/her cumulative dose will be 236 mrem, or 98.3% of the ED Dose Alarm which exceeds the 80% limit of step 4.3.
B is incorrect but plausible if the examinee incorrectly believes that RP-AA-1008 permits continuing until the dose entry limit is reached. Per RP-MW-403-1001, the RWP Dose Entry Limit is calculated at 1.25 times the ED Dose Alarm (240
- 1.25 = 300). If the worker stays in the area until he/she receives 300 mrem, his/her cumulative dose will be 300 mrem, or 125% of the ED Dose Alarm which exceeds the 80%
limit of step 4.3.
D is incorrect but plausible if the examinee incorrect believes that RP-AA-1008 permits continuing until the ED Dose Alarm is received. If the worker stays in the area until the ED Dose Alarm is received, his/her cumulative dose will be 240 mrem, or 100% of the ED Dose Alarm which exceeds the 80% limit of step 4.3.
KA justification - this question meets the KA because the examinee must be able to determine when the RCA must be exited based on the dose received in the stem.
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EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 72 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: 896363 User-Defined ID: CL-ILT-812646A Cross Reference Number:
You are an operator currently working in the drywell on an Topic:
assigned task during a refuel outage.
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 336 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with
- RP-MW-403-1001 Rev.
Revision Number: 6
- RP-AA-1008 Rev. 3 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS QC 09-1 NRC Exam Q72 NRC-05, OYS CERT-04)
Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Added KA justification and History: (i.e. Modified plausibility statements.
distractor b to make Revised correct answer plausible based on OTPS choice to conform to rev. 3 review) of RP-AA-1008.
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: NA Category / KA Statement: 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR: 41.12 / 45.10)
RO Value: 3.5 SRO Value: 3.6 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.12 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 337 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 72 LP85803.2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
CPS OPS ILT EXAM Page: 338 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 73 ID: 896364 Points: 1.00 A transient has resulted in RPV level lowering to -50" Wide Range and is now trending up slowly. The Drywell Fission Product Monitor Skids (Iodine/Noble Gas and Air Particulate Monitor) will...
A. be unaffected.
B. automatically shift to the suction line of Containment CAM #3.
C. be unavailable because the suction and discharge paths are isolated.
D. be available if the MCR places the Div 1 and 2 RHR Isolation Switches on 1H13-P632 and P642 in BYPASS and restarts the Fission Product Monitor.
Answer: C Answer Explanation C is correct:
Per CPS 3315.02 Leak Detection (LD), section 8.2.9.1 Automatic Isolation, the Fission Product Monitoring CT Isolation Valves 1E31-F014, F015, F017, and F018 will close on High DW Pressure, RPV Lvl 2, or Loss of Power.
1E31-F014, F015, F017, and F018 are the Fission Product Monitor Drywell Isolation Valves. Closure of these valves will render the Fission Product Monitor unavailable.
A is incorrect but plausible if the examinee fails to recall that the FPM skid will isolate at Level 2 (-45.5").
B is incorrect but plausible - the process radiation monitoring system containment building CAM #3 (1RIXPR023) takes suction downstream of the inlet Leak Detection drywell isolation valves and discharges upstream of the outlet Leak Detection drywell isolation valves. The examinee may select this response if he/she incorrectly recalls the flowpath / interrelationship between PR023 and the FPM.
D is incorrect but plausible - operation of the RHR Isolation Switches is directed by CPS 3315.02 Leak Detection (LD) to bypass RHR Area Temperature Isolation Signals, but these switches have no effect on an automatic isolation of the DW FPM.
KA Justification - this question meets the KA because the examinee must have knowledge of the response of the DW Fission Product Monitor system to a low RPV level condition.
CPS OPS ILT EXAM Page: 339 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 73 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: 896364 User-Defined ID: CL-ILT-890006A Cross Reference Number:
A transient has resulted in RPV level lowering to -50" Wide Topic:
Range and is now trending up slowly.
Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 340 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3315.02 Rev. 14d Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC Exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - duplicate of CL-ILT-Bank, Modified) 3511 Low KA Justification (if NA required):
Revision History: Revision Added KA justification and History: (i.e. Modified plausibility statements.
distractor b to make Revised distractor D for plausible based on OTPS plausibility.
review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Higher (3-SPK)
KA Data KA Number / System Name: NA Category / KA Statement: 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12 / 43.4 / 45.9)
RO Value: 2.9 SRO Value: 3.1 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.12 10CFR55-43 (SRO) Data: 43.4 CPS OPS ILT EXAM Page: 341 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 73 223006.16 EVALUATE the following LEAK DETECTION indications/responses and DETERMINE if the indication/
response is expected and normal.
.1 Auto Start Signal
.2 Trip Signal
.3 Isolation Signal CPS OPS ILT EXAM Page: 342 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 74 ID: 896365 Points: 1.00 A fire brigade of _____(1)_____ members, including the fire brigade leader, must be on site at all times.
These fire brigade members _____(2)_____ be the Safe Shutdown Qualified Operator (SSQ).
A. (1) Four (2) May B. (1) Five (2) May C. (1) Four (2) May NOT D. (1) Five (2) May NOT Answer: D Answer Explanation D is correct:
Per OP-CL-101-102-1001, CPS Minimum On-Shift Staffing Functions (Table 1), in Modes 1/2/3, we're required to have:
- a SSQ (who cannot be the 'A' or 'B' RO, Fire Brigade Member or EROC). Must be C Area qualified.
- 1 FB Leader
- 4 FB Members A is incorrect but plausible - incorrect number of FB members; the SSQ cannot be a FB member.
B is incorrect but plausible - the SSQ cannot be a FB member.
C is incorrect but plausible - incorrect number of FB members.
KA Justification - this question meets the KA because the examinee must be knowledgeable of the minimum staffing requirements for the fire brigade and safe shutdown operator.
CPS OPS ILT EXAM Page: 343 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Question 74 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: 896365 User-Defined ID: CL-ILT-890012 Cross Reference Number:
A fire brigade of _____(1)_____ members, including the fire Topic:
brigade leader, must be on site at all Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 344 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with OP-CL-101-102-1001 Rev.
Revision Number: 6 Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS No previous NRC Exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - duplicate of CL-ILT-Bank, Modified) 6697 Low KA Justification (if NA required):
Revision History: Revision Added KA justification and History: (i.e. Modified distractor plausibility distractor b to make statements.
plausible based on OTPS review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: NA Category / KA Statement: 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage. (CFR: 41.10 / 43.5 / 45.12)
RO Value: 3.1 SRO Value: 3.6 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: 345 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 74 LP85804.2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
CPS OPS ILT EXAM Page: 346 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 75 ID: 896366 Points: 1.00 Which of the following completes the statement below concerning subsequent actions in CPS 4100.01 Reactor Scram?
Resetting the scram is a priority and should be done as soon as possible following a scram with a(n)...
A. trip of the Reactor Water Cleanup (RT) Pumps to minimize the effects of crud generation.
B. initiation of the High Pressure Core Spray (HPCS) system to minimize vessel cooldown rate.
C. trip of the Reactor Recirculation (RR) Pumps to minimize thermal stratification in the bottom head region.
D. failed fuel assembly to minimize transfer of highly radioactive water to the Containment Equipment Drain system.
Answer: C Answer Explanation C is correct:
Per CPS 4100.01 Reactor Scram, discussion step 6.2:
"Thermal stratification sufficient to exceed RPV pressure/temperature limits could occur at saturated conditions and no forced RR flow.
After a scram from full power, natural circulation is insufficient to prevent bottom head area thermal stratification due to cold water (specifically: CRD, FW, RCIC, HPCS & RWCU Return) being injected into the core.
Timely operator action to restoring forced recirculation flow, resetting the scram, resetting RR FCV runback (3302.01 section 8.4.2), if required, fully opening RR FCV's (3302.01 section 8.1.3, Transfer to slow speed) and verifying ITS LCO 3.4.11 temperature differentials will prevent exceeding any RCS Pressure and Temperature safety limits.
Exceeding the ITS LCO 3.4.11 temperature differential limits does not harm plant components.
It is the uncontrolled heatup of the cooler bottom head region when forced circulation resumes that produced the stresses that could lead to RPV penetration failure."
A is incorrect but plausible - it is desirable to restore RWCU so that crud generated by the scram can be cleaned up. A loss of the RWCU pumps is not a reason to promptly reset the scram.
B is incorrect but plausible - HPCS initiation after a scram will cause RPV pressure to lower at a significant rate, which is increased by injecting 200 gpm of CRD into the RPV post-scram. The examinee may select this choice if he/she believes that resetting the scram will reduce the rate of pressure decrease post-scram.
D is incorrect but plausible - the scram off-normal provides direction on the controls/actions required to reset the scram if fuel failure has occurred or is suspected to prevent transfer of highly radioactive water to Radwaste. Fuel failure, however, is not a reason to promptly reset the scram.
CPS OPS ILT EXAM Page: 347 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version KA justification - this question meets the KA because the examinee must determine the conditions where resetting a scram is given a high priority.
CPS OPS ILT EXAM Page: 348 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version 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: 896366 User-Defined ID: CL-ILT-812586A Cross Reference Number:
Which of the following completes the statement below Topic:
concerning subsequent actions in CPS 4100.01 Num Field 1:
Num Field 2:
Text Field:
CPS OPS ILT EXAM Page: 349 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Comments: General Data Technical Reference with CPS 4100.01 Rev. 22 Revision Number:
Justification for Non SRO CFR NA Link:
Question History: (i.e. LGS 2010 MNGP NRC Exam NRC-05, OYS CERT-04) Q75 Question Source: (i.e. New, Bank Bank, Modified)
Low KA Justification (if NA required):
Revision History: Revision Revised for applicability at History: (i.e. Modified CPS. Added KA distractor b to make justification and distractor plausible based on OTPS plausibility statements.
review)
ILT Supplied Ref (If appropriate): None (i.e. ABN-##)
Excluded
Reference:
(i.e. None Ensure ON-## not provided)
LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)
General Information Question Level (RO/SRO) RO Station Clinton Cognitive Level Memory (1-P)
KA Data KA Number / System Name: NA Category / KA Statement: 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. (CFR: 41.7 / 41.10 / 43.5 / 45.12)
RO Value: 3.6 SRO Value: 4.4 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.7 & 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 350 of 351 27 August 2013
EXAMINATION ANSWER KEY ILT 12-1 NRC RO Written Exam - Final Version Associated objective(s):
Question 75 LP85804.2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal /
emergency operations.