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.JS Systems 11-13-19 COPY > Refueling > Flashcards

Refueling Flashcards

1
Q

Given the following plant conditions: Mode 6. Refueling operations in progress. The refueling machine is moving to retrieve an irradiated fuel assembly in the upender. The CRS notifies the LSRO that there is a rapidly lowering fuel pool level and has implemented the LMEOP. The CRS directs the LSRO to place the fuel in a safe condition, and close PCN-V118 Fuel Transfer Tube Isolation Valve. Which of the following describes the required actions for the proper safe location of the fuel and location of the upender/carriage? The LSRO takes action to place the:

A. Fuel in the reactor vessel and retain the fuel carriage in containment.
B. Fuel in the upender and retain the upender vertical. Fuel Carriage either on the Fuel poolside or Containment.
C. Fuel in the intermediate storage rack and send the fuel carriage to the Fuel Building.
D. Fuel grappled at the uplimit on the RFM and lower the upender horizontal.

A

A. Fuel in the reactor vessel and retain the fuel carriage in containment.

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2
Q

The Unit is in Mode 6 with core off-load is in progress. Chemistry calls and reports that the Boron concentration is 2290 ppm in the RCS and 3010 in the refueling canal. The COLR limit is specified as 3000 ppm. What are all the action(s) if any that should be taken?

A. Suspend positive reactivity additions as soon as possible.
B. Initiate action to restore Boron concentration to within limits, suspend positive reactivity additions and core alternations immediately.
C. No action is required, refueling boron concentration is in specification.
D. Initiate action to restore Boron concentration to within limits, suspend core alternations within one hour.

A

B. Initiate action to restore Boron concentration to within limits, suspend positive reactivity additions and core alternations immediately.

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3
Q

The Concrete Cask heat removal system is OPERABLE if the:

A. difference between the average CONCRETE CASK air outlet temperature and ISFSI ambient temperature is greater than or equal to 102°F.
B. highest ISFSI outlet temperature is less than 102°F.
C. difference between the average CONCRETE CASK air outlet temperature and ISFSI ambient temperature is less than or equal to 92°F.
D. difference between the average CONCRETE CASK air outlet temperature and ISFSI ambient temperature is less than or equal to 102°F.

A

D. difference between the average CONCRETE CASK air outlet temperature and ISFSI ambient temperature is less than or equal to 102°F.

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4
Q

Which one of the following Radiation Monitors becoming inoperable would require suspension of core alterations during core offload? ASSUME all other conditions are acceptable/normal for the evolution.

A. RU 37, Power Access Purge Area Monitor
B. RU 33, Refueling Machine Area
C. RU 29, Control Room Ventilation Intake Monitor
D. RU 143, Plant Ventilation Low Range Monitor

A

B. RU 33, Refueling Machine Area

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5
Q

The unit is in Mode 6.
The core is being off-loaded to the Spent Fuel Pool.
I&C informs you that both Startup channels are incorrectly calibrated.
The following action(s) should be taken:

A. Suspend Core alterations and positive reactivity additions within 1 hour.
B. Determine the RCS boron concentrations by redundant methods immediately and every 12 hours thereafter.
C. Suspend Core alterations, suspend positive reactivity additions immediately and initiate action to restore one SRM to operable status immediately.
D. Initiate actions to restore one SRM to operable status within 4 hours and perform SR 3.9.1.1 (Verify boron concentration within limits of COLR) within 4 hours.

A

C. Suspend Core alterations, suspend positive reactivity additions immediately and initiate action to restore one SRM to operable status immediately.

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6
Q

Unit 1 is in Mode 6. Refueling is in progress.
The containment hatch is closed.
Refueling purge is in service.
If a Refueling Purge Exhaust Fan were to trip…

A. Spent Fuel Pool and Refuel Pool level will go down.
B. Spent Fuel Pool and Refuel Pool level will go up.
C. Spent Fuel Pool Level will rise, and Refuel Pool level will go down.
D. Spent Fuel Pool Level will lower, and Refuel Pool level will go up.

A

C. Spent Fuel Pool Level will rise, and Refuel Pool level will go down.

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7
Q

Design features prevent Spent Fuel Pool Level from inadvertently draining down to less than:

A. 130 ft 2 in
B. 130 ft 6 in
C. 131 ft 2 in
D. 131 ft 10 in

A

A. 130 ft 2 in

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8
Q

Mode 6.
Refueling operations in progress.
The refueling machine is moving to retrieve an irradiated fuel assembly in the upended.
The CRS notifies the LSRO that there is a rapidly lowering fuel pool level and has implemented the LMEOP.
The CRS directs the LSRO to place the fuel in a safe condition, and close PCN-V118 Fuel Transfer Tube Isolation Valve.
Which of the following describes the required actions for the proposer safe location of the fuel and location of the upender/carriage?
The LSRO takes action to place the:

A. Fuel in the upender and retain the upender vertical. Fuel Carriage either on the Fuel poolside or Containment.
B. Fuel in the reactor vessel and retain the fuel carriage in containment.
C. Fuel in the intermediate storage rack and send the fuel carriage to the Fuel Building.
D. Fuel grappled at the uplimit on the RFM and lower the upender horizontal.

A

B. Fuel in the reactor vessel and retain the fuel carriage in containment.

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9
Q

Given that Unit 1 is refueling with containment closed and fuel transfer canal in use, which of the following could cause Refueling Pool level to lower?

A. A Fuel Building supply fan trips.
B. Spent fuel temperature is raised.
C. A refueling purge supply fan trips.
D. Containment air temperature is lowered.

A

A. A Fuel Building supply fan trips.

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10
Q

Core re-load in progress.
Refueling Water Tank level is 14%.
Chemistry reports that the Refueling Pool boron concentration is not within limits.
Which one of the following actions is both available and procedurally directed as a makeup path that can be used to restore the refueling pool boron concentration?

A. Implement 40AO-9ZZ01, Emergency Boration, align HPSI pumps.
B. Implement 40AO-9ZZ01, Emergency Boration, align charging pump suction through CHN-UV-514 with BAMP pumps not available.
C. Implement 40EP-9EO11, Lower Mode Functional Recovery procedure, align charging pump suction to the alternate suction per SA-10, Charging Pump Alternate Suction to the RWT.
D. Implement 40EP-9EO11, Lower Mode Functional Recovery procedure, align charging pump suction to the Spent Fuel Pool per SA-11, Charging Pump Alternate Suction to the SFP.

A

A. Implement 40AO-9ZZ01, Emergency Boration, align HPSI pumps.

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11
Q

Unit 1 is in Mode 5 during a refueling outage.
‘A’ Train shutdown cooling is in service.
Spent Fuel Pool Level Hi or Lo is in alarm.
Spent Fuel Pool Level Lo-Lo is in alarm.
An Auxiliary Operator confirms Spent Fuel Pool level is 136 ft 6 inches and slowly lowering.
What is the current status of (a) LCO 3.7.14, Fuel Storage Pool Water Level (b) Spent Fuel Pool Cooling (c) and which procedure should be implemented to correct this condition?

A. (A) Entry in to LCO 3.7.14 is not required (B) SFP cooling must be secured at this level (C) 40AO-9ZZ23, Loss of SFP Level or Cooling.
B. (A) Entry in LCO 3.7.14 is required (B) SFP cooling can remain in operation at this level (C) 40AO-9ZZ23, Loss of SFP Level or Cooling.
C. (A) Entry in to LCO 3.7.14 is required (B) SFP cooling must be secured at this level (C) 40EP-9EO11, Lower Mode Functional Recovery Procedure.
D. (A) Entry in to LCO 3.7.14 is not required (B) SFP cooling can remain in operation at this level (C) 40EP-9EO11, Lower Mode Functional Recover Procedure.

A

B. (A) Entry to LCO 3.7.14 is required (B) SFP cooling can remain in operation at this level (C) 40AO-9ZZ23, Loss of SFP Level or Cooling.

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12
Q

Refueling pool level is 137’ 6” (>23 ft above the vessel flange).
Core RE-LOAD is in progress.
An irradiated fuel assembly is grappled and in the hoist box.
Train ‘B’ is under clearance for maintenance.
Train ‘A’ LPSI pump is gas bound.
Which ONE of the following complies with Technical Specifications 3.9.4 (Shutdown Cooling (SDC) and Coolant Circulation - High Water Level) required actions?

A. Core re-load may continue
B. Immediately stop core re-load, leave the fuel assembly in the hoist box.
C. Complete placing the fuel assembly in its designated core location, then suspend core re-load.
D. Immediately stop core re-load until you have verification that all activities that could result in boron dilution have been suspended.

A

B. Immediately stop core re-load, leave the fuel assembly in the hoist box.

(Note: Per TS 3.9.4 One SDC Cooling Loop shall be operable and in operation. The fact that B has no power and A is gas bound Condition A is not met and loading irradiated fuel must be suspended immediately)

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13
Q

Unit 1 is at 100% power.
Spent Fuel Pool (SFP) level is 137’10” and has been noted by the AO to be slowly losing level over the past several shifts.
Chemistry has just reported SFP Boron Concentration at 1900 ppm.
The crew is investigating the loss of level at this time.
You are directed by the CRS to add water to the SFP.
Which ONE of the following is the appropriate source of makeup water to the SFP?

A. Recycle Monitor Tank.
B. Refueling Water Tank.
C. Condensate Storage Tank.
D. Reactor Makeup Water Tank.

A

B. Refueling Water Tank.

Note: RWT is borated to >4400 ppm and is the correct source

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14
Q

Unit 3 is in a Refueling Outage.
The Containment LSRO is in process of loading a fuel bundle into the core.
The count rate on Startup Channel #1 increases by a factor of 5.
The count rate on Startup Channel #2 increases by a factor of 3.
No RMS alarms or trends are present in the Control Room.
Which ONE of the following is the correct required response to this event?

A. Withdraw the last inserted fuel assembly and observe Startup Channel response.
B. Stop all fuel movement and order an evacuation of non-essential personnel from containment.
C. Stop all fuel movement and initiate a CPIAS, Containment Purge Isolation Actuation Signal.
D. Fuel movement may continue provided that the Operability of Startup Channel #2 is confirmed.

A

A. Withdraw the last inserted fuel assembly and observe Startup Channel response.

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15
Q

PCA-P01 (Spent Fuel Pool Cooling Pump A) is operating on the Spent Fuel Pool.
A large break occurs in the discharge of the pump.
Which ONE of the following will prevent Spent Fuel Pool level from lowering to the point of uncovering fuel assemblies?

A. Excessive flow check valves will automatically close.
B. PCA-P01 (Spent Fuel Pool Cooling Pump A) will trip on high discharge flow.
C. PCA-P01 (Spent Fuel Pool Cooling Pump A) will trip on low suction pressure.
D. Fuel pool cooling suction piping will become uncovered by the lowering spent fuel pool level.

A

D. Fuel pool cooling suction piping will become uncovered by the lowering spent fuel pool level.

(Note: Fuel pool cooling suction piping is in the upper level of the SFP)

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16
Q

Unit 1 is in a Refueling outage.
Refueling pool level is at 138 ft 2 inches.
Per LCO 3.9.1 the minimum refueling pool boron concentration is ____ ppm, which is designed to maintain Keff < or equal ____ during fuel movement.

A. (1) 2150 (2) .95
B. (1) 2150 (2) .99
C. (1) 3000 (2) .95
D. (1) 3000 (2) .99

A

C. (1) 3000 (2) .95

Note: Per COLR and TS 3.9.1 bases

17
Q

Unit 1 is in a Refueling Outage.
The crew is establishing conditions for Core Offload per 40OP-9ZZ23, Outage GOP.
Refueling Pool level has been raised to 127 ft 7 inches and stabilized.
The CEA support plate has been lowered and is on the Guide Plate.
The L-SRO has verified that all CEA extension shafts have latched.
The SM has given permission to raise the UGS Lift Rig CEA Support Plate.
Subsequently
The Effluent tech reports that due to a procedural error both RU-29/30, Control Room Ventilation Monitors, are INOPERABLE.
Which ONE of the statements is correct?
Raising the CEA support Plate ____ considered a core alteration and ____.

A. (1) IS (2) movement of the CEA Support Plate must be suspended immediately.
B. (1) IS (2) movement of the CEA Support Plate must be suspended within 1 hour.
C. (1) IS NOT (2) no Core alterations are permitted until at least one CREFS train is in operation.
D. (1) IS NOT (2) no Core alterations are permitted until both monitors are declared OPERABLE.

A

A. (1) IS (2) movement of the CEA Support Plate must be suspended immediately.

(Note: This is considered a core alteration by TS, 40OP-9ZZ23 and the Core Reloading procedure. TS requires Core Alts to be suspended immediately.)

18
Q

Refueling pool level is 137’ 6” (<23 ft above the vessel flange).
Core re-load is in progress.
SDC train B is operable but not in operation.
SDC train A is operable and in operation with LPSI pump A providing SDC flow.
Subsequently
SIA-P02, LPSI pump A breaker trips.
Which of the following is correct?
Alarm window 2B06A, SDC TRAIN A/B FLOW LO, ____ and core reload must be suspended ____.

A. (1) Will alarm (2) immediately
B. (1) Will NOT alarm (2) immediately
C. (1) Will alarm (2) within 1 hour
D. (1) Will NOT alarm (2) within 1 hour

A

B. (1) Will NOT alarm (2) immediately

19
Q

Unit 1 is in Mode 6.
Refueling operations are on-going.
LSRO is stationed in containment.
(1) Reactor Operator monitors Spent Fuel Pool level to ensure it is maintained above the TS LCO 3.7.14, Fuel Storage Pool Water Level, MINIMUM of ____ feet over the top of irradiated fuel assemblies seated in the storage racks.
(2) As stated in 40DP-9OP02, Conduct of Shift Operations, the individual designated to maintain the Control Room Command function will normally be the CRS but may be….

A.  (1) 22.5
      (2) Only another qualified SRO.
B.  (1) 22.5
      (2) Either a qualified RO or SRO.
C.  (1) 23
      (2) Only another qualified SRO.
D.  (1) 23
      (2) Either a qualified RO or SRO.
A

D. (1) 23

(2) Either a qualified RO or SRO.

20
Q

A Dry Cask is being loaded then transported from Unit 3 to the Independent Spent Fuel Storage Installation, ISFSI.
Which of the following identifies who has responsibility and ownership for the Dry Cask….
(1) When it is being loaded?
(2) During transport to the ISFSI?

A. (1) Unit 3 Shift Manager (2) Unit 1 Shift Manager
B. (1) Unit 3 Shift Manager (2) Unit 3 Shift Manager
C. (1) Dry Cask Loading Coordinator (2) Unit 1 Shift Manager
D. (1) Dry Cask Loading Coordinator (2) Unit 3 Shift Manager

A

B. (1) Unit 3 Shift Manager (2) Unit 3 Shift Manager

21
Q

Unit 3 is performing a core offload.
Containment is closed.
The fuel transfer canal is open.
Subsequently:
The Area 3 operator notices that Spent Fuel Pool level is lower than it was when he started the shift.
Which ONE of the following would cause the lower level in the Spent Fuel Pool?

A. A Fuel Building supply fan tripped.
B. A Refueling Purge supply fan tripped.
C. A loss of Instrument Air to the Cask Loading Pit gate.
D. A loss of Instrument Air to the Decontamination Pit gate.

A

B. A Refueling Purge Supply fan tripped.

22
Q

Unit 1 is in MODE 6.
Core reload is in progress.
Subsequently:
Audible Indication of count rate for the Startup Range Monitors (SRMs) is lost inside Containment.
Audible and visual SRM indications remain available in the Control Room.
Based on these indications, the core reload…

A. MAY continue provided audible AND visuals source range indications are available in the control room.
B. MUST be suspended in accordance with LCO 3.3.12 Boron Dilution Alarm System, Condition A, for two required SRMs inoperable.
C. MAY continue provided audible source range indication is available in the control room AND the Refueling machine maintains constant communications with the control room.
D. MUST be suspended and action must be taken to restore audible indication in containment in accordance with LCO 3.9.2 Nuclear Instrumentation, Conditions A and B for two required SRMs inoperable.

A

D. Must be suspended and action must be taken to restore audible indication in containment in accordance with LCO 3.9.2 Nuclear Instrumentation, Conditions A and B for two required SRMs inoperable.

23
Q

Unit 1 is in MODE 6 performing a core off-load.
The Refueling Machine currently has a spent fuel assembly grappled and is transferring it to the Upender.
Subsequently:
A fault on the PLC caused the mast bumper to make contact with one of the guide pins actuating the Mast Bumper Interlock.
The grappled spent fuel assembly did NOT make contact with an obstruction.
Prior to clearing/overriding the Mast Bump Interlock, the Bridge and Trolley ____ and completion of a Fuel Handling Event Recover Checklist ____ required.

A.  1. CANNOT be moved in any direction
      2. IS
B.  1.  CANNOT be moved in any direction
      2. is NOT
C.  1.  May be moved using the manual hand wheel
      2. IS
D.  1.  May be moved using the manual hand wheel
      2. is NOT
A

C. 1. May be moved using the manual hand wheel
2. IS

(Note: First part is plausible since the Master Bumper Interlock does prevent all movement of the bridge and trolley, and it is plausible that this interlock would actuate a manual brake which would prevent use of the manual hand wheel, however the manual hand wheel is not locked out by this interlock. Second part is plausible since the fuel assembly did not make contact with any obstruction making the likelihood of any fuel damage extremely unlikely, however any fault of refueling equipment when a fuel assembly is grappled is considered to have placed the fuel at risk, therefore requiring the Fuel Handling Event Recovery Checklist to be completed.

24
Q

The transportation of a dry cask from the Unit 2 Fuel Building to its designated storage location at the ISFSI is complete.
Who has ownership of the dry cask concerning the performance of specific conditional surveillance’s and inspections?

A. Unit 1 Shift Manager
B. Unit 2 Shift Manager
C. Unit 1 Control Room Supervisor
D. Unit 2 Control Room Supervisor

A

A. Unit 1 Shift Manager

25
Q

Unit 2 is Mode 6.
Preparations for lifting the Upper Guide Structure (UGS) are bring made.
The Fuel transfer tube quick closure device and PCN-V118 are OPEN.
Refuel Pool level is 131’ 9”.
Fuel Canal level is 131’ 8” and SLOWLY LOWERING.
In accordance with the procedure, which ONE of the following states the correct control room guidance for this condition?

A. Proceed with direction to raise the UGS.
B. Close PCN-V118, Fuel Transfer Tube Isolation.
C. Raise Fuel Canal Level to match Refuel Pool Level.
D. Lower Spent Fuel Pool Level to match Fuel Canal Level.

A

B. Close PCN-V118, Fuel Transfer Tube Isolation.

26
Q

Which ONE o father following is true regarding Spent Fuel Pool Cooling as related to Control Room Board or Recorder indications?

A. Spent fuel pool levels are available.
B. Spent fuel cooling flow is available.
C. Spent fuel pool temperature is available.
D. Pump bearing temperature and alarms are available.

A

D. Pump bearing temperature and alarms are available.

27
Q

Unit 2 is Mode 6
Fuel movement is in progress from Containment to the Fuel Building.
A valid ‘Low Fuel Pool Gate Seal Air System Pressure Alarm’ is annunciated on B07.
The Auxiliary Operator reports that the Cask Loading Pit Gate Seal pressure is reading 30 psig.
Which ONE of the following is the correct communication and guidance for this condition?

A. Inform the LSRO of the potential for loss of Spent Fuel Pool Level and enter 40AO-9ZZ06, Loss of Instrument Air.
B. Inform the LSRO of the potential for loss of Spent Fuel Pool Level and enter 40AO-9ZZ03, Loss of Cooling Water.
C. Inform the Containment Coordinator of the potential for loss of Fuel Pool Level and enter 40AO-9ZZ06, Loss of Instrument Air.
D. Inform the Containment Coordinator of the potential for loss of Fuel Pool Level and enter 40EP-9EO11, Lower Mode Functional Recovery.

A

A. Inform the LSRO of the potential for loss of Spent Fuel Pool Level and enter 40AO-9ZZ06, Loss of Instrument Air.

28
Q

The Unit is in Mode 6 with core off-load is in progress.
Chemistry calls and reports that the Boron concentration is 2290 ppm in the RCS and 3010 in the refueling canal.
The COLR limit is specified as 3000 ppm.
What are all the action(s) if any that should be taken.

A. Suspend positive reactivity additions as soon as possible.
B. Initiate action to restore Boron concentration to within limits, suspend positive reactivity additions and core alternations immediately.
C. No action is required, refueling boron concentration is in specification.
D. Initiate action to restore Boron concentration to within limits, suspend core alterations within one hour.

A

B. Initiate action to restore Boron concentration to within limits, suspend positive reactivity additions and core alterations immediately.

29
Q

Which one of the following systems may be used to augment fuel pool cooling if the nuclear cooling water system can not handle the heat load during refueling?

A. Essential Chill Water system.
B. Containment Spray system.
C. Normal Chill Water system.
D. Shutdown Cooling system.

A

D. Shutdown Cooling system.

30
Q

The Unit is in MODE 6.
Both Control Room Emergency Air Temperature Control Systems (CREATCS) trains become INOPERABLE.
If in progress, which of the following evolutions must be stopped per the Technical Specifications?

A. New Fuel movement in the Refuel Pool.
B. New Fuel movement to the Spent Fuel Pool
C. Core Offload.
D. Any operation involving the reduction of Refueling Cavity level.

A

C. Core Offload.

31
Q

When using the Spent Fuel Pool (SFP) as a source for emergency boration, why must CHN-HV-532 be closed?

A. A gravity flow path would be established between the SFP and RWT.
B. The SFP boron concentration is higher than the RWT.
C. PC Clean-up must be isolated if the valve is left open.
D. Three charging pumps cannot run on the SFP with the valve open.

A

A. A gravity flow path would be established between the SFP and RWT.

32
Q

In reference to Tech Spec 3.7.14 (Fuel storage pool water level), the minimum level in the fuel pool is based on…

A. Providing adequate NPSH for the fuel pool cooling pumps.
B. Absorbing the iodine released during a fuel handling accident.
C. Satisfying the requirements to be considered a borated water source.
D. Ensuring that decay heat generated in the pool is adequately removed.

A

B. Absorbing the iodine released during a fuel handling accident.

33
Q

Design features prevent Spent Fuel Pool Level from inadvertently draining down to less than:

A. 130 ft 2 in
B. 130 ft 6 in
C. 131 ft 2 in
D. 131 ft 10 in

A

A. 130 ft 2 in

.JS Systems 11-13-19 COPY (41 decks)

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