Week 11 Flashcards
- Unit 1 is exiting an outage with the plant at 345°F Tcold.
- During the outage, AFA-P01 was torn down for maintenance.
- A new governor assembly was installed due to older one having excessive tolerances.
- AFA-P01 is aligned and ready.
- All maintenance activities have been completed, as have all applicable Surveillance Requirements, with the exception of SRs 3.7.5.2, 3.7.5.3, and 3.7.5.4.
AFA-P01 is considered…
A. operable, SR 3.0.1 allows the unit to complete required surveillances when plant conditions can support.
B. operable, however SR 3.0.4 will prevent the mode change until these surveillance requirements are complete.
C. inoperable, however the mode change can be completed and the required surveillances must be completed within 24 hours.
D. inoperable, however the mode change can be completed and the required surveillances must be completed within 72 hours.
A. operable, SR 3.0.1 allows the unit to complete required surveillances when plant conditions can support.
• Unit 1 is in a refueling Outage.
• RCS temperature is 250 degrees and stable.
• RCS pressure is 450 psia and stable.
• RCA-HV-106 (PZR/RV HEAD VENT TO CTMT) was declared Inoperable 5 hours ago.
Which ONE of the following describes the required action (if any)?
A. No action required due to only ONE (1) vent path being Inoperable.
B. Lower RCS pressure to < 385 psia within 72 hours.
C. Restore ONE (1) pressurizer vent path to Operable within 1 hour.
D. Restore TWO (2) pressurizer vent paths to Operable status within 67 hours.
D. Restore TWO (2) pressurizer vent paths to Operable status within 67 hours.
- Unit 1 is in Mode 4
- RCS pressure is currently 380 psia
- HPSI pump A is Operable
- HPSI pump B is Inoperable while performing breaker alignments
- Containment Spray Pump A is Operable
- Containment Spray Pump B is functional, following an oil change but not all required Surveillance Testing has been completed
- You have been requested to raise RCS pressure to 410 psia to allow testing of the SIT outlet valve interlocks
(A) Which LCO(s) prevent the pressure increase?
(B) Can the provisions of LCO 3.0.4 be used to increase RCS pressure to 410 psia? Why or why not?
A) LCO 3.6.6 (B) Any of the following responses is correct.
No, 3.0.4.a does not allow relief - LCO 3.6.6 does not provide continued operation for an unlimited time
Yes, 3.0.4.b could be used if a risk assessment is performed
No, 3.0.4.c does not allow relief
- The plant is in Mode 6.
- The core is being off loaded to the Spent Fuel Pool.
- Containment Refueling Purge is in progress.
The STA informs you that one channel of RU-37, Access Purge has failed its surveillance test.
List the LCO(s) that would be entered due to this event (if any). Include the LCO, Condition, Required Action, and Completion Time.
None, only one channel is required per Tech Spec 3.3.8.
• Unit 1 was manually shutdown for a refueling outage.
• LPSI pump “A” is in a boron recirculation alignment.
• SDC is not in service at this time.
• RCS temperature is 230 degrees and slowly lowering.
• RCS pressure is 360 psia and stable.
• RCPs 2A and 2B are in operation.
• CST level is reported as 28 feet.
Which (if any) LCO(s) should be entered at this time?
A. No LCO entry required at this time.
B. 3.6.6 Containment Spray System only.
C. 3.7.6 Condensate Storage Tank only.
D. 3.6.6 Containment Spray System and 3.7.6 Condensate Storage Tank.
C. 3.7.6 Condensate Storage Tank only.
• 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. No action is required, refueling boron concentration is in specification.
C. Initiate action to restore Boron concentration to within limits, suspend core alternations within one hour.
D. Initiate action to restore Boron concentration to within limits, suspend positive reactivity additions and core alternations immediately.
D. Initiate action to restore Boron concentration to within limits, suspend positive reactivity additions and core alternations immediately.
The plant is completing a refueling outage. While performing 40ST-9ZZM6 it is discovered that
Start-Up channel #2 is pegged low (PMS and ERFDADS also indicate zero). Which of the following describes the impact of this issue on placing the first fuel assembly into the core.
A. This has no impact on refueling, only one startup channel is required.
B. The first fuel assembly can be loaded next to the operating detector while the other detector is tested by I&C per LCO 3.0.5.
C. The first fuel assembly can be loaded next to the detector that is reading zero while that detector is tested by I&C per LCO 3.0.5
D. The first fuel assembly may not be placed in the core until the indication can be assessed to be consistent with current operating conditions.
D. The first fuel assembly may not be placed in the core until the indication can be
assessed to be consistent with current operating conditions.
• Unit 1 is in refueling outage.
• Fuel movement is in progress.
• RU-29, CREFAS “A” is Out Of Service due to a power supply failure.
• The Effluents Tech reports that RU-30, CREFAS “B” has failed a surveillance test.
Which one of the following is the MINIMUM actions required to comply with Tech Specs?
A. Immediately place one train of CREFAS in operation AND suspend movement of irradiated fuel assemblies, positive reactivity additions and core alterations.
B. Immediately place one train of CREFAS in operation OR suspend movement of irradiated fuel assemblies, positive reactivity additions and core alterations.
C. Within 1 hour place one train of CREFAS in operation OR suspend movement of irradiated fuel assemblies, positive reactivity additions and core alterations.
D. Within 1 hour place one train of CREFAS in operation AND suspend movement of irradiated fuel assemblies, positive reactivity additions and core alterations.
B. Immediately place one train of CREFAS in operation OR suspend movement of irradiated fuel assemblies, positive reactivity additions and core alterations.
The plant has been shut down for refueling.
The following timeline of events is available:
2000 03/29/13, Reactor Power Reduction Commenced.
0000 03/30/13, Reactor Trip breakers are open.
0500 03/30/13, Mode 4 Conditions are reached.
1000 03/30/13, Mode 5 Conditions are reached.
0030 04/02/13, Mode 6 Conditions are reached.
1600 04/03/13, Refueling cavity is filled to 137’ 6”.
Which ONE of the following describes the EARLIEST time that fuel may be removed from the reactor vessel in accordance with Tech Specs?
A. 0400 on 04/02/13
B. 0400 on 04/03/13
C. 0430 on 04/06/13
D. 2000 on 04/07/13
B. 0400 on 04/03/13
- Refueling pool level is 138’ 1”
- Core reload is in progress.
- An irradiated fuel assembly is the hoist box and suspended over the reactor vessel.
- Train ‘B’ LPSI pump is under clearance for maintenance.
- Train ‘A’ LPSI pump is gas bound.
- Which of the following complies with Technical Specifications required actions?
A. Core reload must be suspended, immediately.
B. Initiate action to establish ≥ 23 ft water above the reactor vessel flange, immediately.
C. Complete placing the fuel assembly in its designated core location, then suspend core re-load.
D. Core reload can continue for up to 1 hour provided there is verification that all activities that could result in boron dilution have been suspended.
A. Core reload must be suspended, immediately.
• The plant is in Mode 2 with the reactor subcritical (Keff < 1).
Which ONE of the following Tech Spec related DNB parameters applies per LCO 3.4.1, RCS Pressure, Temperature, and Flow DNB Limits?
A. RCS total flow ONLY
B. Pressurizer pressure ONLY
C. RCS cold leg temperature (Tc) ONLY
D. Both RCS temperature and pressure
B. Pressurizer pressure ONLY
