AOP1 Flashcards
State entry conditions for OS1201.04 - RCS Valve Stem Leak
Abnormal RCDT level or run times on RCDT pumps
Computer alarms associated with a high stem leakoff condition
State entry conditions for OS1202.04 - Rapid Boration
Inadequate SDM
Unexplained or uncontrolled reactivity addition
Failure of two or more rods to insert fully shutdown or reactor trip
State entry conditions for OS1210.05 - Dropped Rod
DRPI dropped rod bottom light lit
Rod Deviation alarm
State when AOPs can be used in parallel with EOPs
AOPs may be used in parallel with EOPs provided AOP actions do not interfere with EOP strategy, intent or TCAs
This should be generally avoided
State major actions of RCS leak
Check if Pressurizer level can be maintained
- adjust charging or letdown
- Trip and SI if PZR level can’t be maintained >7% with 1 CCP
Determine appropriate procedure step transition
Isolate potential RCS leakage sources
Check for RHR leakage
Isolate leakage from Letdown or Charging
State E-Plan entry from RCS leakage
MU4:
RCS unidentified or pressure boundary leakage >10GPM for 15min
- OR -
RCS identified leakage >25GPM for 15min or longer
- OR -
Leakage from the RCS to a location outside containment >25GPM for 15min or longer
State the major actions on OS1201.07 - Pressurizer Level Channel or failed controllers
Identify the failure
Compensate for failure
Restore system alignment back to normal
Review TS requirements
State the major actions of OS1201.06 - PZR Pressure Channel failed
Mitigate the effects of failure
Identify the failure
Realign Pressurizer Pressure Channels
Verify TS compliance
State the major actions of OS1211.01 PR NI failure
Check if PR failed high Bypass the failed PR channel Verify proper P-10 indication Verify TS compliance Defeat affected PR NI inputs Restore rod control to AUTO
State what is required if P-10/13 is not in its required state
Restore P-10/13 w/in 1 hour
- OR -
Initiate plant shutdown as required per T.S. 3.0.3
State Major actions of dropped rod
Stabilize the plant Evaluate conditions for dropped rod recovery Notify I&C Recover the dropped rod Restore the controls to normal
State the difference between a dropped rod and a misaligned rod
A dropped rod reaches the bottom of the core
A misaligned to only drops partially into the core
State what must be done if the reactor is made subcritical from a dropped rod
Shutdown the plant to MODE 3.
The rod will be recovered during the subsequent reactor startup
State the major action for a misaligned Rod
Validate misaligned Rod Stabilize Plant Conditions Verify TS Compliance Notify SM and RE Check Rod Control Status Perform Rod Realignment Restore control to normal
State what must be done if more than one control rod is misaligned >48 steps
Trip the reactor
Go to E-0
State Alert and Danger Values for RCP shaft vibes
Alert: 15 mils and increasing at 1 mil/hr
Danger: 20 mils
State Alert and Danger Values for RCP Frame vibes
Alert: 3 mils and increasing at 0.2 mils/hr
Danger: 5 mils
State actions for stopping an RCP with power < P-8
Place affected SG FRV in manual
Feed SG to 60 to 70% NR level
Defeat affected loop Delta-T and Tave inputs
Stop affected RCP
State Rx trip for #1 seal and temp
1 seal leak off flow <1 GPM
- AND -
Temp increasing
Trip the Rx
State the Rx trip for #1 seal, total seal flow and temp
#1 seal >6 GPM - AND - Total <8 GPM - AND - Temp increasing Trip the Rx
State the Rx trip for total seal flow
> 8 GPM
Trip the Rx
State the Rx trip for motor bearing or winding temp
Motor bearing >/= 195F
- OR -
Winding >/= 302F
Trip the Rx
State the conditions for total loss of seal cooling and actions
RCP seal injection <6 GPM
- AND -
No Thermal barrier cooling pump running
Then: trip the Rx
State the Rx trip for RCP seal inlet temp
RCP seal inlet temp >230F
Trip the Rx
State basis for 230F to seal inlet temp
Ensures that the RCP has stopped rotating by the time seal water heats up to 230F to ensure that the SDS is not damaged
DO NOT REESTABLISH COOLING FLOW
State Temp Rx must be cooled to and why on an RCS high activity
<500F to prevent lifting an ASDV incase of a primary to secondary leak
State major actions of an inadvertent phase A
Verify Containment Isolation is not required Charge to seals only Check if letdown can be established Realign PCCW system Valves Restore systems as Required Reset CVI Determine if Plant operation can continue Verify Normal Component Positions
How do we verify that a rod is trippable
If no rod stops are present
- AND -
The IN/OUT rod demand light does not lite with rod motion requested,
THEN the control failure is electrical in nature and rods are verified trippable
State what must be done if SDM is less than the requirement in the COLR
Immediately and continue boration equivalent to 30 gpm at a boron concentration greater than equal to the limit specified in the COLR until the required SDM is restored
Why do we maintain AFD within the limits
This assures that the design limits on peak local power density and minimum DNBR are not exceeded and the consequences of any non-LOCA event would be within specified acceptance criteria
State major actions for Rod or Rod bank failure to move or stop moving
Stabilize Plant Power Level
Try to determine Cause of Rod Control Failure
Check if Rod control is restored
State what happens if an urgent failure alarm is reset, without correcting the cause of the alarm
A group of control rods may drop
State what must occur if 1 CRDM coil fuse is replaced
Replace both fuses to prevent premature failure of the remaining fuse
State what must happen if 1 or more full-length rod is immovable due to friction or mechanical interference
Determine SDM per T.S. 3.1.1.1 within 1 hr and be in hot standby within 6 hr
State what must be done if rod motion can not be stopped
Trip the Reactor
State major actions for loss of MPCS
Determine if Plant Computer Available Mitigate loss of Computer Functions Monitor reactor Power to Ensure that Power Level of an 8hr shift will not exceed 3648MW Check for Loss of an IRTU Restore Normal Computer functions Restore Plant Calorimetric Functions Restore Normal Plant Conditions
State Major Steps for Loss of Vital PP A-D
Stabile the Plant
Dispatch NSO to restore instrument bus
Restore letdown
Restore valid inputs
State SSPS response to a loss of PP-1A or 1B
Slave relays have lost power
Safeguards equipment must be manually aligned
SSPS power supplies must be reset upon re-energization
State Major Steps for Loss of Vital PP-E/F
Dispatch NSO to restore bus
Manually control affected systems
Verify RDMS in service
Power restoration may isolate PCCW to WPB and Containment
State how loss of PP-1E affects Charging and Letdown
CS-HCV-182 fails open
CS-HCV-189 fails closed
State what will cause a CVI
COP rad monitor 2/2 in either train Manipulator crane rad monitor Any S signal Phase A (T) Manual CVS
State the major actions for PZR level Inst Failure
Identify the failure
Compensate for the failure
Restore system alignment back to normal
Review tech specs
State major actions for PR NI failure
Verify load is stable and place rod control in MANUAL Bypass the failed channel ROD STOP Restore Tave Bypass the failed power Range Channel Verify P-10 Verify Tech Spec Compliance Defeat PR NI inputs Restore rod control to AUTO