ML102630307

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2010 Palisades Initial License Examination - SRO Written Exam
ML102630307
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/14/2010
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Division of Nuclear Materials Safety III
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Download: ML102630307 (25)
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SRO Question 76 Palisades 2010 NRC Initial License Exam Source of Question:

MODIFIED - Bank K/A: 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 G2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures Tier:

1 Group: 1 SRO Imp:

4.7 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO-only question because the candidate must assess the facility conditions given in the stem and use those conditions to select the appropriate procedure to mitigate the consequences of the Loss of off site power. Determining follow-up EOP using the event diagnostic flow chart in EOP-1.0 is also an SRO-only task (PL-000 471 05 03).

Palisades Learning Objective: TBCORE_CK01.0

References:

EOP-1.0 attachment 1 Question:

Given the following:

  • The Plant trips due to a loss of all offsite power
  • 2400 VAC Bus 1C is de-energized due to Diesel Generator (D/G) 1-1 failing to start
  • An attempt to manually start D/G 1-1 was not successful
  • 2400 VAC Bus 1D is energized from D/G 1-2
  • During the transient, Y10, Preferred AC Bus, de-energizes
  • The Control Room team is performing actions of EOP-1.0, "Standard Post Trip Actions" Which one of the following procedures does EOP-1.0, Attachment 1, "Event Diagnostic Flow Chart," direct the Control Room team to use for this event?
a. EOP-2.0, "Reactor Trip Recovery."
b. EOP-3.0, "Station Blackout Recovery."
c. EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery."
d. EOP-9.0, "Functional Recovery Procedure."

DISTRACTOR ANALYSIS

a.

Plausible because the student may think that since at least one 2400 VAC vital bus is energized that the recovery procedure can be used.

b.

Plausible because the student may think that since Bus 1C is de-energized that EOP-3.0 is appropriate.

c.

CORRECT - With all forced PCS flow lost, power available to one 2400 VAC bus and 3 of 4 preferred AC buses, EOP-8.0 is the correct procedure.

d.

Plausible because of the loss of Y10, but two preferred AC buses must be lost before transitioning to the functional recovery procedure.

Level of Knowledge:

HIGH Difficulty:

2

SRO Question 77 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: 000015/17 RCP Malfunctions / 4 AA2.01 - Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Cause of RCP failure Tier:

1 Group: 1 SRO Imp:

3.5 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO-only question because the candidate must assess the facility conditions given in the stem and use those conditions to select the appropriate procedure to mitigate the consequences of the sheared PCP shaft.

Palisades Learning Objective: TBCORE_CK01.0

References:

EOP-1.0 attachment 1; EOP-8.0 basis introduction Question:

Given the following with the Plant operating at full power:

  • P-50A, Primary Coolant Pump (PCP) ammeter lowers to approximately 100 amps
  • The reactor automatically trips approximately two seconds later
  • All other PCPs remain operating normally Which one of the following describes the cause of the P-50A failure and the procedure the Control Room team will transition to after EOP-1.0, "Standard Post Trip Actions," are complete?
a. P-50A shaft seized. EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery."
b. P-50A shaft seized. EOP-2.0, "Reactor Trip Recovery."
c. P-50A shaft sheared. EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery."
d. P-50A shaft sheared. EOP-2.0, "Reactor Trip Recovery."

DISTRACTOR ANALYSIS

a.

Plausible because amps are abnormal but amps will be higher than normal operating amps if the pump shaft seized.

b.

Plausible because amps are abnormal but amps will be higher than normal operating amps if the pump shaft seized.

c.

Plausible because one PCP is lost but EOP-8.0 entry is not required unless all 4 PCPs are not running.

d.

CORRECT - PCP amps indicate the shaft sheared and since 3 other PCPs are in service, EOP-2.0 is the correct procedure.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 78 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades 2009 NRC SRO Exam #12 K/A: 000027 Pressurizer Pressure Control System Malfunctions / 3 G2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm Tier:

1 Group: 1 SRO Imp:

4.3 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO only question because the candidate must assess the facility conditions given in the stem and use those conditions to select the appropriate procedure to control Pressurizer pressure with both pressure controllers malfunctioning.

Palisades Learning Objective: IOTF_CK03.0

References:

ONP-18, 4.2.1.b; ARP-4, window 54 Question:

Given the following during a Plant heatup in MODE 3:

  • The PCS is at normal operating pressure with TAVE at 500°F
  • PIC-0101A, A Pressurizer Pressure Controller, is out of service due to a controller failure
  • EK-0754, "PRESSURIZER PRESSURE OFF NORMAL HI-LO," annunciates
  • The Reactor Operator observes the following for PIC-0101B, 'B' Pressurizer Pressure Controller:

Which one of the following procedures will the Control Room team use to control Pressurizer pressure for this event?

a. ONP-24.4, "Loss of Preferred AC Bus Y40."
b. ONP-18, "Pressurizer Pressure Control Malfunctions."
c. ONP-2.3, "Loss of DC Power."
d. SOP-1C, "Primary Coolant System - Heatup."

DISTRACTOR ANALYSIS

a.

Plausible if the student believes that the affected controller is powered from Y40 - actually powered from Y20.

b.

CORRECT - ONP-18 contains directs for manually controlling pressure because there are no controllers available.

c.

Plausible if the student believes that the controller is powered from a DC bus.

d.

Plausible because this is the in use procedure but there is no direction for this condition.

Level of Knowledge:

HIGH Difficulty:

2

SRO Question 79 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: 000054 (CE/E06) Loss of Main Feedwater / 4 EA2.1 - Ability to determine and interpret the following as they apply to the (Loss of Feedwater): Facility conditions and selection of appropriate procedures during abnormal and emergency operations Tier:

1 Group: 1 SRO Imp:

3.9 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO-only question because the candidate must assess the facility conditions given in the stem and use those conditions to select the appropriate procedure to mitigate the consequences a loss of all feedwater using AFW flow control valves in manual.

Palisades Learning Objective: TBCORE_CK01.0

References:

EOP-7.0 step 9; EOP supplement 19, section 5.0 Question:

Given the following:

  • The Plant is also experiencing a loss of all instrument air
a. EOP Supplement 19, "Alternate Auxiliary Feedwater Methods."
b. ONP-7.1, "Loss of Instrument Air."
c. SOP-12, "Feedwater System."
d. EOP Supplement 31, "Supply AFW Pumps From Alternate Sources."

DISTRACTOR ANALYSIS

a.

CORRECT - Supplement 19 contains directions for manually initiating AFW flow by manually operating AFW control valves without air.

b.

Plausible because the student may believe there is guidance in ONP-7.1 for manually operating the AFW control valves without instrument air.

c.

Plausible because the student may believe there is guidance in SOP-12 for manually operating the AFW control valves without instrument air.

d.

Plausible because the student may believe there is guidance in EOP supplement 31 for manually operating the AFW control valves, however, this procedure is used to establish a water source if T-2 is not available.

Level of Knowledge:

HIGH Difficulty:

2

SRO Question 80 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: 000058 Loss of DC Power / 6 G2.2.44 - Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Tier:

1 Group: 1 SRO Imp:

4.4 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO only question because the candidate must recall specific knowledge from LCO 1.2, logical connectors to determine which actions satisfy to LCO.

Palisades Learning Objective: IOTF_CK09.0

References:

LCO 3.8.10 (PROVIDE); ONP-2.3, attachment 6; LCO 1.2, Logical connectors Question:

With the Plant in MODE 5 the following indications are received in the Control Room simultaneously:

  • 25F7 and 25H9, Main Generator Breakers, position indicating lights are OUT Based on these conditions, which one of the following describes (1) the DC Bus that is affected and (2) the action, if taken, that will satisfy the REQUIRED ACTIONS of CONDITION A of LCO 3.8.10, "Distribution Systems - Shutdown?" Assume the affected DC bus is a required bus to support equipment required to be OPERABLE.
a. (1) D11-1.

(2) Action A.1.

b. (1) D11-1.

(2) Action A.2.1.

c. (1) D11A.

(2) Action A.1.

d. (1) D11A.

(2) Action A.2.1.

DISTRACTOR ANALYSIS

a.

CORRECT - Conditions given in the stem indicate a loss of D11-1 and action A.1 is the correct logic for completing the action.

b.

Plausible if the student believes that A.2.1 is the only action needed since it is immediately after the logical connector

'OR'.

c.

Plausible if the student believes that the indications received in the control room are associated with DC bus D11A.

d.

Plausible for a combination of 'b' and 'c'.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 81 Palisades 2010 NRC Initial License Exam Source of Question:

MODIFIED - Bank K/A: 000062 Loss of Nuclear Svc Water / 4 AA2.03 - Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition Tier:

1 Group: 1 SRO Imp:

2.9 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply specific knowledge from Tech Spec Bases 3.6.6 and 3.7.8 to determine if 100% post accident cooling capability is available for the Containment Cooling and Service Water Systems.

Palisades Learning Objective: IOTF_CK09.0

References:

Tech Spec 3.6.6 Basis; Tech Spec 3.7.8 basis Question:

Given the following conditions with the Plant in MODE 3:

  • Alarm EK-1163, "CRITICAL SERV WATER HEADER 'B' LO PRESSURE," annunciates
  • Alarm EK-1347, "CONTAINMENT AIR COOLERS SERV WATER LEAK," annunciates
  • The leak is isolated by closing CV-0824, Service Water from Containment, and CV-0847, Service Water to Containment After isolating the leak, 100% post accident cooling capability (1) provided for the Containment Cooling System and (2) provided for the Service Water System.
a. (1) is (2) is
b. (1) is (2) is not
c. (1) is not (2) is
d. (1) is not (2) is not DISTRACTOR ANALYSIS
a.

Plausible because with 2 spray pumps and 2 spray valves 100% containment cooling is available but not with the MSIV bypass valves open.

b.

Plausible for the same reason as 'a' above and the student believes that service water cooling capability is tied to operation of containment air coolers.

c.

CORRECT - Containment cooling is not met because at least 2 CACs are required and Service Water cooling is met because 2 pumps can supply service water if either non-critical or containment is capable of being isolated.

d.

Plausible if the student believes that service water cooling capability is tied to operation of containment air coolers.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 82 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: 000005 Inoperable/Stuck Control Rod / 1 AA2.03 - Ability to determine and interpret the following as they apply to the Inoperable / Stuck Control Rod:

Required actions if more than one rod is stuck or inoperable Tier:

1 Group: 2 SRO Imp:

4.4 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply specific knowledge from Tech Spec Bases 3.1.4 to determine which LCO actions are taken for a stuck rod.

Palisades Learning Objective: CRD_CK22.0

References:

LCO 3.1.4.E; LCO 3.1.4 bases page 7 Question:

A Plant startup is in progress at 13% power. A review of post-maintenance documentation indicates that there is no reasonable assurance that Control Rod 17 is trippable. Which one of the following describes the Limiting Condition for Operation (LCO) that contains the actions which are required to be performed and the reason for those actions?

a. LCO 3.1.4, "Control Rod Alignment." Plant is outside of the safety analysis because all shutdown rods are assumed to insert on a reactor trip to achieve a 3.5% shutdown margin.
b. LCO 3.1.4, "Control Rod Alignment." Plant is outside of the safety analysis because one additional rod is assumed to stick on a reactor trip.
c. LCO 3.1.5, "Shutdown and Part-Length Control Rod Group Insertion Limits." Plant is outside of the safety analysis because all shutdown rods are assumed to insert on a reactor trip to achieve a 3.5% shutdown margin.
d. LCO 3.1.5, "Shutdown and Part-Length Control Rod Group Insertion Limits." Plant is outside of the safety analysis because one additional rod is assumed to stick on a reactor trip.

DISTRACTOR ANALYSIS

a.

Plausible because the student may believe that SDM cannot be met with a shutdown rod stuck, however, adequate overall SDM can be obtained by adjusting boron concentration.

b.

CORRECT - this question meets the K/A because the safety analyses assumes the most reactive rod will stick on a reactor trip, and if rod 17 is stuck, this makes two rods.

c.

Plausible because the rod that is stuck is a shutdown rod, however adequate overall SDM can be obtained by adjusting boron concentration.

d.

Plausible because the rod that is stuck is a shutdown rod.

Level of Knowledge:

LOW Difficulty:

4

SRO Question 83 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: 000024 Emergency Boration / 1 G2.4.21 - 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.

Tier:

1 Group: 2 SRO Imp:

4.6 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO-only question because the candidate must assess the facility conditions given in the stem and use those conditions to select the appropriate section of EOP-9.0 safety function success path criteria that must be used to mitigate the consequences of the event.

Palisades Learning Objective: TBAH_E01.01

References:

EOP-9.0 attachment A; EOP-9.0 basis page 4 Question:

After a Plant trip from full power, the following conditions exist:

  • EOP-1.0, "Standard Post-Trip Actions," are complete
  • The Control Room team is implementing EOP-9.0, "Functional Recovery Procedure"
  • PCS pressure is 1400 psia and lowering slowly Which one of the following describes the minimum in-use Success Path acceptance criteria that must be met per EOP-9.0 for the above conditions?
a. RC-1, "CRD Insertion."
b. RC-2, "Boration using CVCS."
c. RC-3, "Boration using SIS."
d. RC-2 and RC-3.

DISTRACTOR ANALYSIS

a.

Plausible because all full length control rods are inserted for this event but if SIS is actuated, RC-1 success path acceptance criteria cannot be used.

b.

Plausible because emergency boration is in progress because SIS is actuated (<1605 psia) but the higher numbered success path criteria must be used. The student could also select this because PCS pressure is above the shutoff head setpoint of the HPSI pumps.

c.

CORRECT - Since SIAS is present, RC-3 is the required in use success path.

d.

Plausible because RC-2 and RC-3 are both in-use but the higher numbered success path criteria must be used.

Level of Knowledge:

HIGH Difficulty:

2

SRO Question 84 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: 000067 Plant Fire On-site / 8 AA2.16 - Ability to determine and interpret the following as they apply to the Plant Fire on Site: Vital equipment and control systems to be maintained and operated during a fire Tier:

1 Group: 2 SRO Imp:

4.0 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply specific knowledge from Tech Spec Bases 3.5.2 to determine that LCO 3.0.3 must be entered because both trains of ECCS are inoperable.

Palisades Learning Objective: CAS_CK21.0

References:

Tech Spec Bases 3.5.2 page 9; EI-1, attachment 1; ARP-7, window 18 Question:

Given the following with the Plant at full power:

  • An Auxiliary Operator reports that there is a fire in MCC-7 and EC-40, "Radwaste Panel"
  • The Control Room team de-energizes MCC-7 by opening breaker 52-1103, MCC-7 Supply Breaker, on Panel C-04
  • EK-1118, "HIGH PRESSURE CONTROL AIR COMPRESSORS LO PRESS,"

annunciates on Panel C-13

  • An Auxiliary Operator reports:

o T-9B, HP Control Air Compressor Receiver Tank, pressure indicates 245 psig o There is significant damage to the MCC-7 switchgear panel and EC-33, Redundant Safety Injection Panel Based on the above conditions, 100% of the required Safety Injection flow (1) available and Emergency Plan entry (2) required.

a. is is
b. is not is
c. is is not
d. is not is not DISTRACTOR ANALYSIS
a.

Plausible if the student does not realize that a loss of WESG HP Air results in a loss of operating air to both CV-3027 and CV-3056 which causes a loss of 100% post accident ECCS flow.

b.

CORRECT - With T-9B pressure, 260 psig, CV-3027 and CV-3056 are both inoperable which renders both trains of ECCS inoperable.

c.

Plausible if the student does not realize that a loss of WESG HP Air results in a loss of operating air to both CV-3027 and CV-3056 which causes a loss of 100% post accident ECCS flow and that an emergency plan entry is required.

d.

Plausible if the student does not realize that an emergency plan entry is required.

Level of Knowledge:

HIGH Difficulty:

2

SRO Question 85 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: CE/E09 Functional Recovery G2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator Tier:

1 Group: 2 SRO Imp:

4.1 Applicable 10CFR55 Section:

43.1 - Conditions and limitations in the facility license. This exam question meets the criteria for an SRO only question because the candidate must apply knowledge contained in 10CFR50.72, "Immediate Notification Requirements for Operating Nuclear Reactors." This is a condition of the Palisades license because the license states that the facility must operate the plant within the regulations of the commission (NRC).

See Palisades Renewed License No. DPR-20 section 1.D. This item also is not required knowledge for Reactor Operators.

Palisades Learning Objective: APOR_E01.05

References:

10CFR50.72; EI-1, attachment 1; EI-3, 5.2.1.c Question:

A manual reactor trip occurred 20 minutes ago due to a loss of D21-2, DC Bus. EOP-9.0, "Functional Recovery Procedure," is entered. Due to this event, the NRC must be notified...

a. after notifying the county and state but no longer than one-hour from event classification per EI-3, "Communications and Notifications."
b. after notifying the county and state but no longer than 15 minutes from event classification per EI-3, "Communications and Notifications."
c. of a non-emergency event within one-hour per ADMIN 4.00, "Operations Organization, Responsibilities and Conduct."
d. within one-hour per 10CFR50.72, "Immediate notification requirements for operating nuclear power reactors," via the Emergency Response Data System (ERDS).

DISTRACTOR ANALYSIS

a.

CORRECT - Loss of D21-2 requires entry into the Emergency Plan which requires a one-hour notification to the NRC.

b.

Plausible if the student believes that the NRC must be notified in the same time frame as the local and state authorities.

c.

Plausible if the student believes that this is a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reportability issue.

d.

Plausible if the student believes that ERDS is an acceptable form of notification.

Level of Knowledge:

HIGH Difficulty:

2

SRO Question 86 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: 005 Residual Heat Removal A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown Tier:

2 Group: 1 SRO Imp:

3.7 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO-only question because the candidate must assess the facility conditions given in the stem and use those conditions to select the appropriate section of ONP-17 to recover primary system cooling.

Palisades Learning Objective: IOTF_CK07.0

References:

ONP-17, attachment 5, 6, and 7 Question:

Given the following conditions:

  • Neither LPSI Pump can be started
  • PCS temperature is 175°F
  • The Reactor Vessel Head is fully tensioned
  • The Pressurizer Manway is removed Which one of the following sections of ONP-17, "Loss of Shutdown Cooling," will the Control Room Supervisor implement to restore Primary Coolant heat removal?
a. Attachment 6, "S/G Heat Removal."
b. Attachment 5, "Option 3: PCS Boil Off and Makeup."
c. Attachment 5, "Option 2: Spent Fuel Pool Cooling."
d. Attachment 5, "Option 1: Containment Spray."

DISTRACTOR ANALYSIS

a.

Plausible because the reactor head is installed but the PCS must be able to be pressurized.

b.

Plausible because the PZR manway is removed but containment spray is a higher priority.

c.

Plausible because the SDC system and the spent fuel pool systems have a manual cross-tie but the reactor cavity must be full for this option.

d.

CORRECT - This question matches the K/A because the candidate must understand the implications of the PZR manway being removed. If the PZR manway were installed, damage to the spray pump suction could occur from PCS pressure transients.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 87 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: 026 Containment Spray G2.2.40 - Ability to apply Technical Specifications for a system Tier:

2 Group: 1 SRO Imp:

4.7 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply specific knowledge from LCO 1.3 to determine that when the Plant must be in MODE 3 when a subsequent INOPERABILITY is experienced for the Containment Spray System.

Palisades Learning Objective: CSS_CK21.0

References:

LCO 3.6.6 (PROVIDE); LCO 1.3, Completion Time Extension criteria Question:

Given the following conditions:

  • The Plant is operating at full power
  • On Tuesday at 1500, P-54B is repaired, tested, and declared OPERABLE If P-54C remains INOPERABLE, which one of the following is the latest allowable day and time that the Plant must be in MODE 3?
a. Thursday, 1400.
b. Thursday, 2100.
c. Friday, 0800.
d. Friday, 1400.

DISTRACTOR ANALYSIS

a.

CORRECT - The condition specifies one or more trains not one or more pumps. Since P-54B and P-54C are on the same train an extension is not allowed.

b.

Plausible if the student believes that an extension is allowed and utilizes 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the subsequent inoperability and adds 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to be in MODE 3.

c.

Plausible if the student believes that an extension is allowed and utilizes 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the original stated completion time but does not factor 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to be in MODE 3.

d.

Plausible if the student believes that an extension is allowed and utilizes 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the original stated completion time and adds 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to be in MODE 3.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 88 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: 061 Auxiliary/Emergency Feedwater A2.07 - Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air or MOV failure Tier:

2 Group: 1 SRO Imp:

3.5 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply knowledge that describes what is required for the left train of AFW to be operable to determine if the LCO is met and the action that will allow exiting the applicable action statement.

Palisades Learning Objective: AFW_CK21.0

References:

LCO 3.7.5 (PROVIDE); SOP-12 Section 4.7.b; SOP-19 Attachment 2 Question:

The Plant is at 50% power with the following conditions:

  • FIC-0737A, P-8C AFW Pump to A S/G, is in AUTO with it's associated valve closed
  • FIC-0736A, P-8C AFW Pump to B S/G, is in PF mode supplying 80 gpm to 'B' S/G
  • Then, the Nitrogen line to CV-0727, P-8A/B AFW Pumps to 'B' S/G, develops a severe leak and is isolated o Instrument air to CV-0727 is still lined-up Given these conditions, which one of the following identifies whether LCO 3.7.5, "Auxiliary Feedwater System," is currently satisfied and, if not, also identifies the minimum actions required to satisfy the LCO without reliance on any action statement?
a. LCO 3.7.5 is met.

No action statements are required to be entered.

b. LCO 3.7.5 is not met.

Placing FIC-0737A to CASCADE will allow all action statements to be exited.

c. LCO 3.7.5 is not met.

Repairing and testing the Nitrogen line to CV-0727 and will allow all action statements to be exited.

d. LCO 3.7.5 is not met.

Placing FIC-0736A to CASCADE or AUTO will allow all action statements to be exited.

DISTRACTOR ANALYSIS

a.

CORRECT - P-8C flow controllers are operable in any mode except manual and nitrogen backup to CV-0727 is for station blackout purposes not Tech Specs.

b.

Plausible if student does not recall that FIC-0737A is operable in AUTO position.

c.

Plausible if student believes that backup nitrogen is required for CV-0727 operability.

d.

Plausible if student does not recall that FIC-0736A is operable in PF mode.

Level of Knowledge:

HIGH Difficulty:

4

SRO Question 89 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: 064 Emergency Diesel Generator G2.2.25 - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits Tier:

2 Group: 1 SRO Imp:

4.2 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply specific knowledge from LCO 3.8.2 Bases to determine that the required Diesel Generator is inoperable and entry into the subject LCO is required.

Palisades Learning Objective: EDG_CK22.0

References:

LCO 3.8.2 (PROVIDE); LCO 3.8.2 bases page 2; ONP-24.2 attachment 1; SOP-30, 4.2.1 Question:

Given the following:

  • The Plant is in MODE 5
  • Bus 1C is removed from service for maintenance
  • Bus 1D is being supplied by Safeguards Transformer 1-1
  • Switchyard 'R' Bus is removed from service for maintenance Which one of the following will cause LCO 3.8.2, "AC Sources - Shutdown," to be not met for the above conditions?
a. Y20, Preferred AC Bus, de-energizes.
b. Bus 1D voltage is 2485VAC as read on temporary voltmeters installed in Panel C-04.
c. Y30, Preferred AC Bus, de-energizes.
d. 152-402, Station Power Transformer 1-2 Breaker, is racked to the DISCONNECT position.

DISTRACTOR ANALYSIS

a.

CORRECT - Loss of Y20 renders the right train sequencer inoperable which renders D/G 1-2 inoperable which causes LCO 3.8.2 to be not met since it is the required D/G.

b.

Plausible because this is higher than normal but within the required range of operability of 2407 - 2518 VAC.

c.

Plausible because this will make D/G 1-1 inoperable but this D/G cannot be the required D/G with 1C Bus de-energized.

d.

Plausible because in MODE 5 this source can be used to power the 2400 VAC buses and to meet the LCO but since the safeguards transformer is supplying the bus, the LCO is still met.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 90 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: 076 Service Water A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS Tier:

2 Group: 1 SRO Imp:

3.7 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO-only question because the candidate must assess the facility conditions given in the stem and use those conditions to select the appropriate procedure and action to mitigate the consequences of the event.

Palisades Learning Objective: IOTF_CK08.0

References:

ONP-6.1, step 5 Question:

The Plant is at full power during the month of January. Then, the following occurs:

  • EK-1124, "TRAVELING SCREEN HI dp" alarms due to ice buildup on the traveling water screens
  • The North Bay level has begun lowering rapidly
  • The South Bay level is stable Which one of the following will the CRS direct the crew to perform first to address these conditions?
a. Align P-5, Warm Water Recirculation Pump for siphon operation per SOP-14, "Circulating Water and Chlorination Systems."
b. Trip Dilution Water Pumps P-40A and P-40B per ONP-6.1, Loss of Service Water.
c. Trip Dilution Water Pump P-40A only per ONP-6.1, Loss of Service Water.
d. Lineup F-4B and F-4C, Traveling Water Screens, for continuous backwash per SOP-15, "Service Water System."

DISTRACTOR ANALYSIS

a.

Plausible, but not first action (step 8 of ONP-6.1 section 4.0)

b.

Plausible if student believes ONP-6.1 requires tripping both of these pumps for the given conditions

c.

CORRECT - ONP-6.1 directs this action first.

d.

Plausible, but not first action (step 7 of ONP-6.1 section 4.0)

Level of Knowledge:

HIGH Difficulty:

4

SRO Question 91 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: 014 Rod Position Indication G2.2.22 - Knowledge of limiting conditions for operations and safety limits Tier:

2 Group: 2 SRO Imp:

4.7 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply specific knowledge concerning LCO 3.2.1 to determine if the LCO is met and the actions that will allow LCO 3.2.1 to be met without relying on any of its actions statements.

Palisades Learning Objective: CRD_CK21.0

References:

LCO 3.2.1 (PROVIDE); LCO 3.8.7 (PROVIDE); LCO 3.8.9 (PROVIDE); ONP-24.4, step 4.5 note Question:

Given the following:

  • The Plant is at full power
  • At 0800 a loss of Y40, Preferred AC Bus, occurs due to a failure of ED-09, Inverter #4
  • No other equipment is out of service Based on these conditions, which one of the following identifies whether LCO 3.2.1, "Linear Heat Rate," is currently met and, if not, also identifies the minimum action(s) required to meet the LCO without performing any LCO 3.2.1 REQUIRED ACTIONS?
a. LCO 3.2.1 is met.

No action statements are required to be entered.

b. LCO 3.2.1 is not met.

Repair Inverter #4 and verify unloaded output voltage and frequency are within limits by 1500.

c. LCO 3.2.1 is not met.

Repair Inverter #4 and re-energize Y40 by 2200.

d. LCO 3.2.1 is not met.

Place Y40 on the Bypass Regulator by 0900.

DISTRACTOR ANALYSIS

a.

Plausible if student does not recall tie to Y40 loss and LCO 3.2.1.

b.

Plausible if student believes that output voltage and frequency must be verified to meet LCO 3.8.9.B.

c.

Plausible if student uses 24 hrs for Inverter LCO 3.8.7.A.

d.

CORRECT - LCO 3.2.1.B would be entered which allows 2 hrs to reduce power to <85%.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 92 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades 2009 NRC SRO Exam #17 K/A: 015 Nuclear Instrumentation A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty or erratic operation of detectors or compensating components Tier:

2 Group: 2 SRO Imp:

3.5 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO only question because the candidate must apply knowledge from TS Bases 3.3.9 that defines what constitutes a channel of neutron monitoring in the given MODE or other specified condition in the applicability. The candidate must also apply knowledge from TS Bases 3.3.1 that defines which WR NI indication (i.e., plasma display) is qualified as post accident instrumentation.

Palisades Learning Objective: NI_CK22.0

References:

LCO 3.3.7 including table (PROVIDE); LCO 3.3.1 Bases Table B 3.3.1-1; LCO 3.3.9 (PROVIDE); LCO 3.3.9 Bases page 2 Question:

Given the following conditions:

  • The Plant is in MODE 3 with a Primary Coolant System (PCS) temperature of 532°F and pressure of 2060 psia
  • The PCS is being diluted in preparation for critical approach tomorrow
  • The Wide Range flux level plasma indication for Source/Wide Range NI-1/3 on Panel C-06 begins to act erratically and is determined to be unreliable
  • The NI-1/3 analog count rates on Panel C-02 are indicating normal
  • NI-1/3 indications on Panel C-02 channel check to NI-2/4 indications Given these conditions, which one of the following identifies (1) if LCO 3.3.9, Neutron Flux Monitoring Channels, and LCO 3.3.7, Post Accident Monitoring Instrumentation, are satisfied and (2) identifies the minimum REQUIRED ACTIONS, if any, that are required?
a. (1) LCO 3.3.9 is met, LCO 3.3.7 is met.

(2) No actions are required.

b. (1) LCO 3.3.9 is not met, LCO 3.3.7 is met.

(2) Immediately stop dilution of the PCS and perform a SDM verification within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

c. (1) LCO 3.3.9 is met, LCO 3.3.7 is not met.

(2) Restore NI-1/3 plasma indication to OPERABLE status within 7 days.

d. (1) LCO 3.3.9 is met, LCO 3.3.7 is not met.

(2) Restore NI-1/3 plasma indication to OPERABLE status within 30 days.

DISTRACTOR ANALYSIS

a.

Plausible if the student believes that plasma indication is not a PAM instrument.

b.

Plausible if the student believes that a channel of NMS is lost.

c.

Plausible if the student believes that LCO action 3.3.7.C applies.

d.

CORRECT - LCO 3.3.9 is not specific as to which indication must be operable to meet the LCO; LCO 3.3.7 specifically addresses the plasma indicators being required to meet the LCO.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 93 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: 035 Steam Generator G2.1.20 - Ability to interpret and execute procedure steps Tier:

2 Group: 2 SRO Imp:

4.6 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply specific knowledge from Tech Spec Bases 3.4.7 to determine which condition would result in LCO 3.4.7 being not met.

Palisades Learning Objective: PCS_CK21.0

References:

LCO 3.4.7; LCO 3.4.7 bases page 4 Question:

The Plant is in MODE 5 with the secondary system tagged out for a Turbine replacement and the following conditions:

  • Both Primary Coolant System (PCS) loops are filled
  • PCS is solid and pressurized at 250 psia and 120°F
  • Primary Coolant Pumps (PCPs), P-50B and P-50C, are operating
  • P-8A, AFW Pump, is removed from service for repairs
  • P-67B, LPSI Pump, is removed from service for repairs For the above conditions, which one of the following events will cause LCO 3.4.7, "PCS Loops - MODE 5, Loops Filled, to be not met? (See excerpt from LCO 3.4.7 below) a T-58, Safety Injection Refueling Water Tank, level is lowered from 97% to 75%.
b. P-50B, Primary Coolant Pump, supply breaker trips due to overcurrent.
c. The Primary Coolant System is diluted by 50 ppm Boron.
d. P-8C, AFW Pump, motor-pump coupling separates during starting.

DISTRACTOR ANALYSIS

a.

Plausible if student believes that a borated makeup flow path is required for the shutdown cooling train to be considered operable. Swapping the suction source of the LPSI pump to the SIRWT is a very quick operation, however, the SIRWT is only required to be operable in Modes 1-4.

b.

Plausible if student believes that PCP operation is needed for the LCO to be met.

c.

Plausible if student believes diluting the PCS will cause the LCO to be not met.

d.

CORRECT - loss of AFW Pump P-8C results in no feedwater paths to be available.

Level of Knowledge:

HIGH Difficulty:

4 LCO 3.4.7 One Shutdown Cooling (SDC) train shall be OPERABLE and in operation with 2810 gpm flow through the reactor core, and either:

a.

one additional SDC train shall be OPERABLE; or

b.

The secondary side water level of each Steam Generator (SG) shall be -84%

SRO Question 94 Palisades 2010 NRC Initial License Exam Source of Question:

NEW K/A: G2.1.5 - Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Tier:

3 Group:

SRO Imp:

3.9 Applicable 10CFR55 Section:

43.1 - Conditions and limitations in the facility license. This exam question meets the criteria for an SRO only question because the candidate must apply knowledge contained in 10CFR26, "Fitness for Duty Programs," subpart I to determine who must determine that a waiver is necessary and who must authorize the waiver. This is a condition of the Palisades license because the license states that the facility must operate the plant within the regulations of the commission (NRC). See Palisades Renewed License No. DPR-20 section 1.D. This item also is not required knowledge for Reactor Operators.

Palisades Learning Objective: APCO_E14.01

References:

10CFR26.207; EN-OM-123, 5.9[2]

Question:

Federal law requires Operators to work within prescribed work hour control limits. If it is desired to grant waivers for an Operator to exceed these limits, who, as a minimum, must (1) determine that the waivers are necessary and (2) approve the waivers?

a. Shift Manager.

Operations Manager.

b. Shift Manager.

Plant Manager.

c. Assistant Operations Manager-Shift.

Operations Manager.

d. Assistant Operations Manager-Shift.

Plant Manager.

DISTRACTOR ANALYSIS

a.

Correct determiner and incorrect approver.

b.

CORRECT

c.

Incorrect determiner and incorrect approver.

d.

Incorrect determiner and correct approver.

Level of Knowledge:

LOW Difficulty:

3

SRO Question 95 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: G2.1.36 - Knowledge of procedures and limitations involved in core alterations Tier:

3 Group:

SRO Imp:

4.1 Applicable 10CFR55 Section:

43.6 - Procedures and limitations involved in initial core loading, alterations in core configuration, control rod programming, and determination of various internal and external reactivity effects. This exam question meets the criteria for an SRO only question because the candidate must apply knowledge from Tech Spec Bases 3.9.2 to determine if the conditions are met to perform alterations in core configuration.

Palisades Learning Objective: IOTD_E02.10

References:

LCO 3.9.2 Bases Question:

Given the following conditions:

  • The Plant is in MODE 6
  • GCL 11.2, "Refueling Handling Operation Shift Checklist, is in progress in preparation for refueling operations
  • NI-1/2, Source Range Nuclear Instruments, are in operation
  • NI-3, Wide Range Nuclear Instrument, is in operation
  • NI-4, Wide Range Nuclear Instrument, is out of service
  • The Audible Count Rate Drawer at Panel C-27 is de-energized Based on these conditions, which one of the following describes the status of conditions being met to perform CORE ALTERATIONS and the reason?
a. Conditions are not met because both channels of Source Range and Wide Range Instruments are required to be in operation.
b. Conditions are met because both channels of Source Range Instruments are in operation.
c. Conditions are met because both channels of Source Range are in operation and at least one Wide Range channel is in operation.
d. Conditions are not met because the Audible Count Rate Drawer is de-energized.

DISTRACTOR ANALYSIS

a.

Plausible if the student believes that both WR and SR are required for core alternations.

b.

Plausible if the student believes that only SR indication is required for core alternations.

c.

Plausible if student believes both SR and one WR is required for core alterations.

d.

CORRECT - LCO 3.9.2 requires the Control Room to have audible count rate indication.

Level of Knowledge:

HIGH Difficulty:

2

SRO Question 96 Palisades 2010 NRC Initial License Exam Source of Question:

MODIFIED - Palisades 2009 NRC Exam #21 K/A: G2.2.18 - Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

Tier:

3 Group:

SRO Imp:

3.9 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO only question because the candidate must assess the facility conditions given in the stem, i.e., Plant MODE, and use those conditions to select the appropriate procedure for performing a risk assessment. Plant MODE is required in the stem because the risk assessment procedure changes if the Plant is below MODE 3. This exam question also meets the criteria for an SRO only question because performing a risk assessment is an SRO only task.

Palisades Learning Objective: ADAO_E02.02

References:

ADMIN 4.02, attachment 3, section 2.0 Question:

Given the following conditions:

  • The Plant is in MODE 5
  • A severe thunderstorm warning is in effect
  • Irradiated fuel moves are in progress in the Spent Fuel Pool
  • Y30, Preferred AC Bus, is planned to be removed from service on the next shift Which one of the following procedures will be used to perform a risk assessment for removing Y30 from service?
a. Admin 4.02, "Control of Equipment."
b. Admin 4.11, "Safety Function Determination Program."
c. GOP-14, "Shutdown Cooling Operations."
d. GOP-11, "Refueling Operations and Fuel Handling."

DISTRACTOR ANALYSIS

a.

Plausible since this procedure would be used with the plant in MODE 1, 2, or 3.

b.

Plausible since this procedure addresses safety functions.

c.

CORRECT - This procedure is used to perform a risk assessment anytime shutdown cooling is in service.

d.

Plausible since this procedure is in effect and the student believes that there is a process for performing a risk assessment during fuel moves.

Level of Knowledge:

LOW Difficulty:

3

SRO Question 97 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: G2.2.40 - Ability to apply Technical Specifications for a system Tier:

3 Group:

SRO Imp:

4.7 Applicable 10CFR55 Section:

43.2 - Facility operating limitations in the technical specifications and their bases.

This exam question meets the criteria for an SRO-only question because the candidate must apply specific knowledge from LCO 3.0.3 to determine the MODE the plant must be placed in and the amount of time in which the plant has to perform the MODE change.

Palisades Learning Objective: APTS_E01.14

References:

LCO 3.0.3 Question:

Given the following with the Plant in MODE 1:

  • On October 1st at 0815, a Limiting Condition for Operation (LCO) that is applicable in MODES 1-3 is discovered to be not met
  • All associated Conditions of the LCO are not met
  • The Control Room team implements the actions required by LCO 3.0.3 Per LCO 3.0.3, if the LCO continues to be not met then the Plant must be placed, at a minimum, in (1) by (2) on October 2nd.
a. (1) MODE 5 (2) 2115
b. (1) MODE 5 (2) 2015
c. (1) MODE 4 (2) 1515
d. (1) MODE 4 (2) 1415 DISTRACTOR ANALYSIS
a.

Plausible if the student misapplies LCO 3.0.3 and believes the plant must be in MODE 5 even though the LCO is not applicable in MODE 4.

b.

Plausible if the student misapplies LCO 3.0.3 and believes the plant must be in MODE 5 even though the LCO is not applicable in MODE 4 and does not add the hour of prep.

c.

CORRECT - Since the LCO applies in MODE 1-3, the plant only needs to be taken to MODE 4 to satisfy LCO 3.0.3.

d.

Plausible if the student does not add the hour of prep.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 98 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions Tier:

3 Group:

SRO Imp:

3.7 Applicable 10CFR55 Section:

43.4 - Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions. This exam question meets the criteria for an SRO-only question because the candidate must have knowledge of the radiological hazards associated with a rescue of a plant employee during an emergency. This exam questions also meets the requirements of an SRO-only question because performing the duties of the Emergency Plant Manager is an SRO job that cannot be delegated to an RO.

Palisades Learning Objective: N00153_E18.0

References:

EI-2.1, 5.11 Question:

Given the following conditions:

  • A General Emergency was declared due to a LOCA with extremely high off-site radioactive release rates.
  • EOP-1.0, "Standard Post Trip Actions," are completed
  • EOP-4.0, "Loss of Coolant Accident Recovery" is being implemented
  • The Shift Manager is the acting Emergency Plant Manager
  • An Auxiliary Operator (AO) has sustained life-threatening injuries in a high dose area while attempting to isolate the uncontrolled release
  • The estimated exposure for the rescue is 20 Rem In accordance with EI-2.1, Emergency Plant Manager," which one of the following describes the minimum authorization requirements to attempt a rescue of the injured AO?
a. Any on-shift SRO may authorize the rescue.
b. The Shift Manager may authorize the rescue.
c. Site Vice President permission is required to authorize the rescue.
d. The Radiation Protection Manager and Shift Manager are required to authorize the rescue.

DISTRACTOR ANALYSIS

a.

Plausible if the student misinterprets dose limit restrictions for life saving services during an emergency and believes that any SRO can authorize exceeding these dose limits.

b.

CORRECT - Since the Shift Manager is the Emergency Plant Manager, then he/she can authorize this exposure.

c.

Plausible if the student believes the SVP is required to authorize exceeding these dose limits.

d.

Plausible if the student believes that both SM and RP manager permission is required authorize exceeding these dose limits.

Level of Knowledge:

LOW Difficulty:

4

SRO Question 99 Palisades 2010 NRC Initial License Exam Source of Question:

BANK - Palisades K/A: G2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures Tier:

3 Group:

SRO Imp:

4.7 Applicable 10CFR55 Section:

43.5 - Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. This exam question meets the criteria for an SRO-only question because the candidate must assess the facility conditions given in the stem and use those conditions to select the appropriate procedure to mitigate the consequences of the lowering SFP level. This question also cannot be answered solely with system knowledge.

Palisades Learning Objective: IOTF_CK03.0

References:

ONP-23.4 Question:

Given the following with the Plant at full power:

  • New fuel bundles are being placed in the Spent Fuel Pool (SFP) in preparation for a refueling outage
  • EK-1309, "SPENT FUEL POOL HI/LO LEVEL," annunciates on Panel C-13
  • The Control Room team observes SFP level lowering on the remote monitor
  • An Auxiliary Operator reports that Nitrogen pressure to the SFP South Tilt Pit Gate is reading abnormally low Which one of the following describes the procedure that the Control Room team will implement to mitigate this event?
a. ONP-23.3, Loss of Refueling Water Accident.
b. ONP-23.4, Loss of Spent Fuel Pool Cooling.
c. SOP-27, "Fuel Pool System," Attachment 2, Addition of Water to the Spent Fuel Pool.
d. ONP-11.2, Fuel Handling Accident.

DISTRACTOR ANALYSIS

a.

Plausible if the student believes that since fuel handling is occurring in the SFP that ONP-23.3 applies - this would apply only if the fuel pool were cross connected to the reactor cavity.

b.

CORRECT - Even though actual cooling has not been lost, this is the correct procedure if the fuel pool is not cross connected to the reactor cavity or there hasn't been an actual fuel handling accident.

c.

Plausible if the student believes that since SOP-27 may be used to add water to the SFP in normal situations that it can be used in this situation, however it does not contain other mitigating actions that are necessary.

d.

Plausible if student believes ONP-11.2 has actions that may help mitigate the event.

Level of Knowledge:

HIGH Difficulty:

3

SRO Question 100 Palisades 2010 NRC Initial License Exam WRITTEN QUESTION DATA SHEET Source of Question:

BANK - Palisades K/A: G2.4.29 - Knowledge of the emergency plan Tier:

3 Group:

SRO Imp:

4.4 Applicable 10CFR55 Section:

None - This is an exception to the 10CFR55.43(b) applicability. This exam question meets the criteria for an SRO only question because it is an SRO only duty to classify emergency events during implementation of the emergency plan. (SRO task # PL-344 019 05 03)

Palisades Learning Objective: PL-N00113_E01.09

References:

EI-1 Attachment 1 (Hot) - Fission Product Boundaries FU1 Question:

Given the following with the Plant initially at full power:

  • A Plant shutdown is commenced per ONP-9, Excessive Load
  • Shortly after the Plant reaches MODE 3, a tube leak in the A S/G is detected Which one of the following is the lowest Primary to Secondary leak rate in the 'A' S/G that requires the declaration of an Unusual Event for these conditions per the Emergency Implementing Procedures?
a. 0.3 gpm.
b. 1.0 gpm.
c. 12 gpm.
d. 26 gpm.

DISTRACTOR ANALYSIS

a.

Plausible if the student confuses the TS limit for this (0.1 gpm)

b.

Plausible if the student confuses the Reactor Trip criteria for this (0.4 gpm).

c.

CORRECT - FU1 - 10 gpm for loss of Containment barrier with an unisolable steam leak from affected S/G.

d.

Plausible if the student confuses the EAL entry criteria for PCS identified leakage for this.

Level of Knowledge:

HIGH Difficulty:

4

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