2005 NRC RO Exam Flashcards
- The plant is operating at rated power and core flow, with the following:
- A reduction in core flow transient results in core flow of 65% of rated.
- Both Recirc pumps are still operating in high speed.
Which one of the following identifies the Tech Spec Thermal Limit LCO value that will be affected and how?
A. APLHGR LCO limit and it is now lower
B. APLHGR LCO limit and it is now higher.
C. MCPR LCO limit and it is now lower.
D. MCPR LCO limit and it is now higher
Answer: d. is correct. The MCPR LCO operating limit is HIGHER following a flow reduction. Per the COLR and TS
3.2.2 “MCPR shall be equal to or greater than the appropriate MCPR limits from Figures 2a and 2b times the K(f) shown in Figure 2c. …….” From Fig 2c, as flow is reduced below 100% to 65%, the value of K(f) rises from 1.00 to about 1.03
- The plant is in Single Loop operation, following an unplanned Recirc Pump trip. The following conditions exist:
- Indicated drive flow in the operating Recirculation loop is 21,000 gpm.
- Indicated total core flow on Control Room Panel P603 is 22 Mlbm/hr.
Which one of the following identifies the current relationship between indicated total core flow on
P603 flow recorder AND actual total Core Flow and the reason for the difference?
Indicated Total Core Flow (P603 Recorder) is ……
A. higher than actual due to natural circulation flow.
B. higher than actual due to idle jet pump reverse flow.
C. lower than actual due to natural circulation flow.
D. lower than actual due to idle jet pump reverse flow.
c is correct - NOTE 1 following Step H.6.0 of N2-OP-29, Reactor Recirculation System, states ‘When calculating total core flow in single loop operation and the operating loop drive flow is less than 22,000 gpm, Loop Flows should be added instead of subtracted”. In addition, Step 6.3 of N2-RESP-07, Single Recirculation Loop Operating Requirements, states “If, while in single loop operation, with the non-operating loop Recirculation Pump shutdown and the operating loop drive flow is less than 22,000 GPM the flow in the idle loop will be positive due to natural circulation head. The total core flow summing network assumes all flow in an idle recirculation loop is negative.
- The plant is operating at 100% power, with the following:
- Division I Diesel Generator 2EGS*EG1 is operating in parallel with offsite power for monthly surveillance testing.
- 2EGS*EG1 is supplying 3960 - 4400 KW to bus, THEN ….. Offsite breaker R-50 trips open.
Which one of the following describes the effect on 2EGSEG1 and the Electrical Distribution circuit breakers?
2EGSEG1 ……..
A. continues to run with its output breaker 101-1 closed. Offsite feeder breaker 101-13 is tripped open.
B. continues to run with its output breaker 101-1 and Offsite feeder breaker 101-13 tripped open.
C. trips on overspeed and its output breaker 101-1 is open. Offsite feeder breaker 101-13 is closed.
D. trips on overspeed and its output breaker 101-1 and Offsite feeder breaker 101-13 are tripped open.
A. is correct. R-50 trip results in a loss of offsite Line 5. Loss of offsite power causes offsite Feeder 101-13 to trip open. Diesel Generator 2EGS*EG1 continues to run with is output breaker 101-1 closed supplying the emergency
switchgear.
- The plant is operating at 100% power, with the following:
0600 - CSH is inoperable and out of service with Red Clearance applied
0715 - MSlV automatic isolation occurs
0715 - All Feedwater Pumps trip and cannot be restarted
0718 - RClC system starts and injects
0720 - RPV water level is 80 inches and steady
0720 - RPV pressure is maintained 800 to 1000 psig with SRVs
0720 - All Low Pressure ECCS systems are operable and in standby
0725 - CRS directs plant cooldown to cold shutdown be performed
0725 - A loss of BYS*SWG002A 125 VDC Bus occurs
Which one of the following describes the impact of these conditions on the use of systems to perform a plant cooldown?
A. RHS Loop B can be placed in Suppression Pool Cooling from the Main Control Room; RHS Loop A cannot be. RClC is no longer available to maintain water
level.
B. Both RHS loops can be placed in Suppression Pool Cooling from the Main Control Room. RClC continues to inject to maintain water level.
C. Alternate Pressure Control Systems other than the SRVs are required to depressurize. RClC is no longer available to maintain water level.
D. Alternate Pressure Control Systems including the SRVs are required to depressurize. RClC continues to inject to maintain water level.
D. is correct - A loss of Division 1 125 VDC BYS*SWG002A results in the loss of SRV relief mode “C” solenoids. The EOP Bases (page 4-61) allows ADS solenoids (Div II solenoid is still available) to be used in the unlikely event that SRV operation cannot be performed from P601. SRV are an Alternate Pressure Control Systems per N2-EOP-RPV. RClC continues to inject since the system was lined up and injecting when the loss of DC occurred. RClC can still operate even though all of its DC powered components are deenergized. The RClC Flow Controller is 120 VAC UPS powered.
- Plant startup is in progress, with the following:
- Total Core Flow is 70 Mlbm/hr
- Reactor Power is being held at 60%
- Reactor Feedpump B is in service with LV10B in AUTOMATIC
- Reactor Feedpump A is running on min flow with LV10A and LV55A in MANUAL and full closed for troubleshooting
- THEN, a spurious Main Generator Lockout trip occurs
- NPS-SWG001 and NPS-SWG003 fast transfer occurs
Which one of the following describes the condition of the Reactor Recirculation System (RCS) pumps and flow control valves (FCVs) one minute after the generator lockout?
A. Pumps downshifted to slow speed with FCVs at pre-transient position.
B. Pumps downshifted to slow speed with FCVs at minimum position.
C. Pumps tripped to zero speed with FCVs at pre-transient position.
D. Pumps tripped to zero speed with FCVs at minimum position.
a. is correct. Generator lockout results in a Main Turbine Trip. Stop Valve/Control Valve closure results in a reactor scram along with RCS system EOC RPT breaker trip and pump downshift to slow speed. From 60% power with two Feed pump operating (breakers closed), FCV runback will NOT occur when RPV level drops during the scram. The FCVs will remain at their pre-transient position. Additionally, with one Feed pump injecting following the scram, RPV water level will remain above the RCS pump trip to zero speed level of 108.8
inches. The pump also downshifts to slow speed if RPV water level drops below Level 3 (1 59.3 inches)
- The plant is operating at 100% power, with the following:
- An automatic reactor scram occurs
- All operating Feedwater Pumps trip during the transient
- N2-SOP-101C Reactor Scram IMMEDIATE ACTIONS are being taken
- RPV Pressure is 900 psig and lowering
- RPV water level is 125 inches and lowering
- One Turbine Bypass Valve remains open
Which one of the following describes the required condition for the Feedwater System LV10s and
LV55s and why, per N2-SOP-101C Reactor Scram?
A. In manual and closed to prevent uncontrolled water injection.
B. In manual and closed to allow for Feedwater Pump restart
C. In manual and open to allow for water level restoration.
D. In automatic and open to allow for water level restoration
A is correct. Per N2-SOP101C Immediate Action IF all feedwater pumps have tripped THEN Place ALL FWS-LV10 and LV55 controllers to “manual” and verify the valves are full closed. This is done to prevent uncontrolled injection if RPV pressure drops, which it will with a BPV open.
- The plant is being operated from the REMOTE SHUTDOWN PANEL during a Control Room Evacuation, with the following:
- RCIC is injecting to the RPV
- RPV level is 200 inches and rising
- Flow controller thumbwheel is set in AUTO to 400 gpm
- RClC Turbine speed is 1500 RPM
- RPV Level continues to rise
Which one of the following actions is required to stop the level rise, per N2-SOP-78, Control Room Evacuation?
A. Trip the turbine using manual trip pushbutton.
B. Close Steam Admission Valve using control switch.
C. Place Flow Controller to MANUAL and set to 0 output.
D. Adjust Flow Controller thumbwheel setpoint to 300 gpm.
B is correct, per SOP-78. If speed cannot be maintained above 1500 RPM and level continues to rise then close the Steam Admission Valve MOVl20.
A is incorrect. Trip the turbine is not required per SOP-78 and if injection needs to be restored, the trip and
throttle valve would have to be reset.
C is incorrect. Lowering controller output to 0 will result in turbine speed below 1500 RPM and violate the low RPM procedure limit of 1500 RPM.
D is incorrect. Lowering thumbwheel setting to 300 gpm violates the procedure conditional statement that if
lowering flow below 400 gpm, the controller should be placed in manual to prevent system flow oscillations. Also would result in speed below 1500 RPM.
- The plant has experienced a LOCA, with the following:
- Reactor Building Closed Loop Cooling (CCP) has been lost and cannot be recovered
- Residual Heat Removal (RHS) pumps are injecting to the RPV
- RPV water level is -25 inches (actual) and steady
Which one of the following identifies the required actions for the operating RHS pumps, per N2-SOP-13, LOSS Of CCP?
A. Continue to operate without cooling water but only until adequate core cooling is restored.
B. Continue to operate while shifting cooling water supply to Service Water System.
C. Must be tripped before motor temperature reaches 266°F to prevent damaging windings.
D. Must be tripped before pump temperature reaches 194°F to prevent damaging seals.
B is correct based on the need for RPV injection & restoration of component cooling to RHS pumps. N2-SOP-13 directs seal cooling shifted to Service Water supply per N2-OP-13 H.7.0. Continued pump operation is allowed.
- A plant startup is in progress, with the following:
- Feedwater Pump A is in service
- All three Feedwater Pump Suction MOVs are open (CNM-MOV84A,B,C)
- Low Flow Control Valve 2FWS-LV55A is controlling in AUTO
- 2FWS-LV55A is at 40% open position
- IAS pressure to ALL Feedwater Pumps valves is lost
- Any effected local air accumulators have depressurized
Which one of the following describes the effect on 2FWS-LV55A position and reactor water level? 2FWS-LV55A% Open, Reactor Water Level A. 0% open Lowering, below normal level B. 40% open Constant, normal level C. 40% open Lowering, below normal level D. 100% open Rising, above normal level
C. is correct because on loss of IAS, the LV55A fails as is and min flow valves in Feed & Condensate Systems fail open to divert flow from the reactor causing level to drop.
- The plant has just entered Mode 4 following an unplanned shutdown to perform Main Turbine repairs, with the following:
- RHS Loop B is operating in Shutdown Cooling (SDC)
- A transient results in RPV water level dropping to 140 inches before being stabilized
- With RPV water level still at about 140 inches a loss of Line 6 occurs
- Division II EDG fails to start and cannot be started
Which one of the following methods is used to restore CORE DECAY HEAT removal, per N2-SOP-31, Loss of Shutdown Cooling?
A. Start one Alternate Decay Heat Removal loop in normal ADH lineup.
B. Restore level to 178 to 187 inches and start RHS A in normal SDC lineup.
C. Restore level to 178 to 187 inches and start at least once RCS pump.
D. Raise level to about 255 inches and start RHS with flow through SRVs.
D. is correct, per SOP-31 use Alternate Shutdown Cooling Preferred Lineup.
A. is incorrect. ADH is not available following a normal shutdown for decay heat removal because suction is from
SFP with cavity gates installed and RPV head in place
B. is incorrect because with loss of line 6, no power is available to re-open the Div II SDC inboard containment isolation valve inside the drywell, which has automatically closed when level dropped below I59 inches The DW is not open for access under these conditions to locally open the MOV.
C. is incorrect because establishing coolant circulation with a Recirc (RCS) pump will not result in removal of
decay heat.
- Core Alterations are in progress, with the following:
- Bundle integrity is maintained
- An irradiated fuel bundle being moved from the reactor cavity to Spent Fuel Pool
- Bundle becomes ungrappled and falls into the reactor vessel downcomer area. (Between the vessel wall and the shroud)
Which one of the following workers is at greatest risk of radiation overexposure? A. I&C Tech at SLS Tank. B. Refuel SRO on the Bridge. C. Mechanic working on SRVs. D. RP Tech at Refuel Floor Access Point.
C is correct. Worker closest to the bundle with the least amount of shielding will be at greatest risk. SRVs are in the Drywell at the approximate elevation of the downcomer.
A, B, and D are incorrect because of the location of these components. SRO on the bridge is shielded by water
level within the cavity, as is the RP Tech at the access. SLC Tank is in Secondary Containment, which is shielded by Primary Containment wall.
- The plant has experienced a LOCA inside the Drywell, with the following:
- Drywell pressure is 5 psig
- Both Control Building Special Filter Train Booster Fans start at 1200
Which one of the following identifies the latest time that both Control Building Special Filter Train Booster Fans can remain running and why, per N2-OP-53A, Control Building Ventilation System?
A. 1220 to prevent excessive positive Control Room pressure.
B. 1220 to prevent excessive radiation exposure to personnel.
C. 2000 to prevent excessive positive Control Room pressure.
D. 2000 to prevent excessive radiation exposure to personnel.
B is correct - CAUTION in Step H 1.0 of N2-OP-53A states “BOTH Special Filter Trains start simultaneously on a valid LOCA Hi Rad signal. Failure to shutdown one of the operating fans 2HVC*FN2A(B) within 20 minutes of Actuation CAN result in the Control Room personnel receiving Excessive Radiation Exposure”.
- The plant is operating at loo%, with the following:
0000 - EHC Pressure Regulator A failed and is out of service. Operation continues on the backup regulator EHC Pressure Regulator B
0015 - Pressure transmitter supplying the backup EHC Pressure Regulator B fails downscale
Which one of the following describes the Turbine Bypass Valve (BPV) and Safety/Relief Valve (SRV) response to the transient?
A. BPVs regulate open to maintain RPV pressure below SRVs relief-mode setpoints and the SRVs remain closed.
B. BPVs regulate open but RPV pressure rises to SRVs relief-mode setpoints. SRVs cycle to limit pressure rise.
C. BPVs remain closed and RPV pressure rises to SRVs relief-mode setpoints. SRVs cycle to limit pressure rise.
D. BPVs remain closed and RPV pressure rises to SRVs safety-mode setpoints. SRVs cycle to limit pressure rise.
C is correct. When the Pressure transmitter supplying the backup regulator fails downscale, EHC senses lowering pressure and closes Turbine Control Valves and Bypass Valves.
This causes RPV pressure to rise and an automatic scram results on high RPV pressure of 1052 psig. The BPV remain closed since their sensing instrument is failed low. SRV operation in the relief mode senses actual RPV pressure from different instruments than those used in EHC. With actual pressure rising, the SRVs will lift in the relief mode.
- Reactor power is 10% during plant startup, with the following:
- RCIC Full Flow test surveillance is in progress
- Suppression Pool Average Water Temperature (SPT) is being logged every 5 minutes
- RCIC is operating at 600 gpm
- Average SPT is 90.1 F and rising
Which one of the following describes the requirement regarding RCIC testing?
A. Test can continue, however SPT must now be logged every minute.
B. Test can continue because SPT is still below applicable LCO limit.
C. Test must be stopped because SPT is above applicable LCO limit.
D. Test must be stopped because elevated SPT may cause pump damage.
B is correct. Per TS 3.6.2.1, with testing in progress that adds heat to the suppression pool, the applicable LCO limit for SPT is 5 105°F. Testing can continue. The normal limit without testing is 90°F.
- The plant has experienced a LOCA, with the following:
- Drywell Pressure peaked at 10 psig and is now slowly lowering
- Hottest Drywell Temperature peaked at 305°F and is now slowly lowering
- RPV Pressure is 50 psig
- ECCS Systems are injecting into the RPV
- Wide Range RPV water level is 30 inches and is steadily rising
- Fuel Zone instruments read upscale
Which one of the following describes the current requirement regarding entry into RPV Flooding EOP and why?
A. RPV Flooding must be entered because parameters are in the BAD region of RPV Saturation Temperature curve and reference leg flashing IS occurring.
B. RPV Flooding must be entered because parameters are in the BAD region of RPV Saturation Temperature curve even though reference leg flashing IS NOT occurring.
C. RPV Flooding entry is NOT required because water level readings are above Minimum Indicated Level values even though reference leg flashing IS occurring.
D. RPV Flooding entry is NOT required because water level readings are above Minimum Indicated Level values and reference leg flashing IS NOT occurring.
D is correct. Conditions are above DETAIL A RPV Water Level Instruments of EOP-PC and RPV. Elevated DWT and low RPV pressure can result in flashing. Level instruments can only be used if “there is NO evidence of instrument leg flashing AND the instrument reads above the Minimum Indicated Level (Table C). There is NO evidence that instrument leg boiling is taking place.
A and B incorrect. RPV Flooding is NOT required based solely on being in the BAD region of Fig B Detail A. As
long as NO evidence that instrument leg boiling is taking place exists.
C is incorrect. There is NO evidence that instrument leg boiling is taking place and the instrument reads above Minimum Indicated Level (Table C).
- The plant was operating at 100% power, when the following occurred:
- Breach in the Suppression Pool Wall occurs at Elevation 190 feet
- Actions to add water to the Suppression Pool are complete
- Suppression Pool Level (SPL) is 195 feet and lowering slowly
- EOP-RPV is entered from EOP-PC
- 1 rod inserts to position 26 and the rest fully insert, following the manual scram
Which one of the following strategies is used to mitigate the consequences of the breach per EOPs and Transient Mitigation Guidelines?
A. Open all Turbine Bypass Valves now. Opening all ADS Valves is NOT required even if SPL reaches 192 feet.
B. Open all Turbine Bypass Valves now. Open all ADS Valves prior to SPL of 192 feet.
C. Opening Turbine Bypass Valves is NOT permitted. Open all ADS Valves when SPL is 192 feet.
D. Opening Turbine Bypass Valves is NOT permitted. Open all ADS Valves now to prevent SRV tailpieces from uncovering.
B is correct. Per Transient Mitigation Guidelines for Suppression Pool Level TMG2.2.3.4 and 2.4.2, it is appropriate to “anticipate” a blowdown if a blowdown is imminent. In this case with SPL approaching 192 feet and the breach is at 190 feet, the limit will be exceeded. When SPL does reach 192 feet, a blowdown is then required and ADS valves must be opened, but only if at or above 192 feet (per EOP-C2).
- The plant has experienced a scram due to a loss of Feedwater transient, with the following:
- No injection sources available
- a RPV water level has continued to drop
- RPV pressure is being controlled between 800 - 1000 psig
Which one of the following identifies the LOWEST ACTUAL RPV water level at which adequate core cooling, by any mechanism, is still maintained?
A. -14 inches.
B. -39 inches.
C. -52 inches.
D. -62 inches.
C is correct - with no iniection sources available, the NMP2 EOP Basis Document indicates that ACC exists as long as RPV water level is above the Minimum Zero Injection RPV Water Level. A and B are incorrect. TAF (-14 inches) and MSCRWL (-39 inches) are both higher than Minimum Zero Injection RPV Water Level (-52 inches) D is incorrect. 2/3 Core Height (-62 inches) is below MZIRWL and requires 6350 gpm Core Spray flow injection.
- The plant is operating at 1 OO%, with the following:
0900 - Annunciator 601712 SLCS TANK 1 LEVEL HIGH/LOW alarms
0905 - Operator reports NO air bubbler flow observed at local SLS. Storage Tank level instrument indicator for 2SLS’FIC103 (Reactor Building 289).
0908 - MSlVs automatically close
0908 - RPV Pressure peaks at about 1125 psig
091 0 - Reactor power is 10%
Which one of the following describes the effects of these conditions on SLS pump start capability and SLS Tank level indication at P601?
SLS Pumps, SLS Tank Level Indication A. Start, Downscale B. Start, Upscale C. Can't Start, Downscale D. Can't Start, Upscale
A is correct. SLS Tank level indication is supplied from air bubble dip tube arrangement. On loss of the air signal tank level indication fails downscale resulting in storage tank low level alarm. The SLS pumps will still automatically start after a 98 second time delay with APRM power of 10% (above the APRM downscale setpoint of 4%). The SLS pumps have a start permissive and trip on low SLS tank level, but these signals are generated by the four RRCS tank level transmitters, which are not effected by the loss of air pressure. These are
differential pressure transmitters connected directly to the SLS storage tank.
- The plant is operating at power, with the following:
- Stack GEMS radiation reading is normal
- Vent GEMS radiation reading is higher than normal
Which one of the following identifies the possible release source?
A. Above Refuel Floor Ventilation exhaust.
B. Main Steam Tunnel Ventilation exhaust.
C. Standby Gas Treatment fan discharge.
D. Mechanical Vacuum Pump discharge.
A is correct - the Above Refuel Floor Ventilation exhaust discharges to the Reactor/Radwaste Building Vent Stack. B, C, D are incorrect. These systems discharge to the Main Stack via their respective ventilation systems.
- The plant is operating at 100% power, with the following:
- Fire Panel 129 goes into alarm for zone 377NW
- Fire is confirmed
- HVC*ACU1 A, CONTROL ROOM AC FAN trips
- HVC*ACU2A, RELAY ROOM AC FAN trips
Which one of the following identifies the actions required to be taken for Control Building Ventilation (HVC) and the reason?
A. Actuate Appendix R disconnects to prevent tripping the Division II ACUs due to faulty electrical circuits.
B. Actuate Appendix R disconnects to place HVC in a lineup that ensures the Control Room Envelope pressure does not become negative.
C. Defeat cross divisional interlocks to ensure Control Room Envelope temperature can be maintained 90°F or less.
D. Defeat cross divisional interlocks to prevent a Control Room evacuation due to smoke infiltration
C is correct. Per ARP-FPM, N2-OP53A off normal section H.15.0 is required to be performed immediately,
to defeat the HVC cross divisional interlocks. Implementation of this section directs the starting of Div II ACUs and using the cross divisional interlock key lock override switch to prevent loss of Div I I components because of fire affecting Div I components. Note 2 states Actuation of the override switches is required to be completed within 13 minutes after a fire that has disabled the previously running Control Room Envelope ACUs to ensure Control Room Envelope temperature remains <90°F.
A is incorrect. The Appendix R switches do not prevent ACU tripping. This function is performed by the cross divisional interlock override switch. B. is incorrect. Actuating Appendix R disconnects will not place the Control Room and Relay Room HVC ACUs in the correct lineup. ACUs do not realign when Appendix R switches are actuated. D is incorrect. N2-OP-53A H.14.0 Note 2 states this is required to maintain Control Room Envelope temperature below 90°F not to maintain positive pressure. This action is not taken prevent a Control Room evacuation to due smoke infiltration.
- A plant startup is in progress, with the following:
- RPV Pressure is 800 psig
- EHC Regulator Pressure Set is 800 psig
- Turbine Bypass Valve #1 is 50% open with all others closed
- Feedwater Pump A is injecting with LV55A in MANUAL
- RPV Water Level is steady at 183 inches
- THEN ….. a control rod is withdrawn AND APRM power rises and stabilizes at a higher value
Which one of the following describes the effect of these conditions on RPV Water Level and the reason?
A. Rises because steam flow is less than feed flow.
B. Lowers because steam flow is greater than feed flow.
C. Remains constant because steam flow and feed flow have NOT changed.
D. Remains constant because steam flow and feed flow changed by equal amounts.
B is correct. Level will lower because as power rises, steam flow will rise as BPV #1 opens to maintain pressure at 800 psig. With LV55A in MANUAL, feed flow will remain constant and steam flow will rise.
- The plant has experienced a LOCA, with the following:
- Drywell Pressure is 3.0 psig
- Hottest Drywell Temperature is 275F
- Drywell Cooling Fans are tripped
Which one of the following describes the effect on restoring Drywell Cooling System (DRS) per EOP support procedures?
A. After defeating interlocks, system operation can be fully restored.
B. Without defeating interlocks, system operation can be fully restored.
C. Cannot be restored, restoring CCP flow may result in water hammer.
D. Cannot be restored, restarting DRS fans may result in air duct damage.
C is correct. Per N2-EOP-6 Attachment 24, if DWT is above 250F, the containment isolation MOVs cannot be reopened, because the water volume in the section of piping between the inboard and outboard isolation valves may have flashed to steam due to the elevated DWT.
- The plant is operating at 90% power, with the following:
0700 - Annunciator 603443 CONTROL ROD DRIFT alarms
0700 - Control Rod 22-43 is observed to be at position 12 then 14 and still moving
0700 - Appropriate SOPs are entered by the crew
0703 - Control Rod 22-43 is being moved to the fully inserted position
0703 - Control Rod 18-27 is observed to be at position 02 then 04 and still moving
Which one of the following describes the actions required to be taken and why?
A. Fully insert all moving control rods to terminate the power rise.
B. Fully insert and disarm the moving control rods to comply with Tech Specs.
C. Reduce power to about 85% to provide adequate margin to Thermal Limits.
D. Place the Mode Switch to SHUTDOWN to terminate the power rise.
D is correct. Per N2-SOP-8, more than
one control rod drifting requires a
reactor scram.
- The plant is operating at 100% power, with the following:
- A transient results in an automatic Reactor Scram
- 32 control rods insert to Position 00
- All remaining control rods insert to Position 02
Which one of the following describes the CURRENT rod pattern with respect to EOPs and Tech Specs Shutdown Margin (SDM)?
Shutdown Per EOPs, SDM Pattern Achieved A. Yes, Yes B. Yes, No C. No, No D. No, Yes
B is correct. Per EOP-RPV and EOPC5 basis, the reactor will remain shutdown without boron if NO rods are withdrawn past 02 (Maximum Subcritical Banked Withdrawal Position MSBWP). Currently this condition IS met, therefore the reactor IS shutdown. TS SDM definition for rod positions is all rods fully inserted except for a single rod, which is assumed to be fully withdrawn. Definition condition is NOT achieved.
- A plant startup is in progress, with the following:
- Reactor Pressure is 500 psig
- The operating Control Rod Drive (RDS) Pump trips
- No RDS Pump can be started
- A Control Rod at position 12 has an accumulator pressure of 900 psig
Which one of the following describes when a manual scram is required to be initiated per N2-SOP-30, Control Rod Failures?
A. Immediately.
B. In 20 minutes.
C. If one control rod drifts in.
D. If any other control rod accumulator becomes inoperable.
A is correct - SOP-30 calls for immediate scram if reactor pressure is <900# and CRD charging water pressure is <940# and any accumulator is inop with its associated rod withdrawn .
- The plant is operating at 100% power, with the following:
0800 - HVRRE32A-1 BELOW REFUELING FLOOR OFFLINE GAS MONITOR indicates RED on DRMS display
0805 - Reactor Water Cleanup System WCS Pump Room A temperature is 160°F and steady
0805 - WCSMOV102, CLEANUP SUCT INBOARD ISOL VLV AND WCS*MOV112, CLEANUP SUCT OUTBOARD ISOL VLV are still open and can not be shut.
0820 - Radiation monitor RMS2A on Reactor Building Elevation 215 is reading 9.2 E+03 mr/hr steady and indicating RED on DRMS display
0820 - Radiation monitor RMS2B on Reactor Building Elevation 215 is reading 8.2 E+03 mr/hr steady and indicating RED on DRMS display
Which one of the following describes the proper implementation of EOP-SC with regards to area radiation Ievels?
A. Only one area is affected by elevated radiation levels. Continue to try to isolate WCS system. A normal plant shutdown is NOT required.
B. Two areas are affected by elevated radiation levels. A normal plant shutdown IS required. RPV Blowdown is NOT required.
C. Only one area is affected by elevated radiation levels. A manual scram IS required but an RPV Blowdown is NOT required.
D. Two areas are affected by elevated radiation levels. A manual scram IS required AND an RPV Blowdown IS required.
D is correct. Per the TMG, each area radiation monitor is treated as a separate area. IF RMS2A and 2B are reading above Max Safe Values, then 2 areas are affected and a Blowdown is required by EOP-SC Step SC-10 due to the fact that the leak can not be isolated.
- The plant has experienced a LOCA, with the following:
- All rods are full in
- Reactor pressure is 200 psig and slowly lowering
- Reactor level is 102 inches and steady
- Suppression Pool level is 211.8 feet and rising
Which one of the following injection systems is allowed to be used to maintain reactor level per the Emergency Operating Procedures?
A. RDS
B. Condensate
C. RHS in the LPCl mode
D. RClC with suction aligned to the CST
C is correct. With S/P level high (above 211.7 feet @ 200 psig), N2- EOP-PC, SPL-2 calls for injection sources that do not add to containment inventory
- The plant is experiencing a DBA LOCA, with the following:
- ALL RHS Pumps automatically started
- ALL RHS Injection MOVs are stroking open
- THEN …… Annunciator 601448 RHR A SYSTEM VALVES MOTOR OVERLOAD alarms AND P601 amber STATUS LIGHT LPCl A INJECT VLV RHS’MOV24A is lit
Which one of the following identifies the effect of these conditions on operation of RHS’MOV24A LPCl A INJECTION VLV?
A. Continues to travel open then remains full open.
B. Continues to travel open then strokes full closed.
C. Stops and cannot be opened from the control room.
D. Stops but can be throttled open from the control room.
C is correct. Per N2-ARP-01 601448 and INOP STATUS light response, the breaker is open or fuse is blown. The MOV cannot be opened from the control room. With 601448 actuated a possible cause is the thermal overload trip. Since the INOP STATUS light also lit, the breaker is tripped, not the thermal overloads.
- The plant is in MODE 4, with the following:
- Both Recirc Pumps are idle
- RHS A loop is running in Shutdown Cooling
- RHS A loop flow is 7450 gpm
- THEN RHS*MOV40A partially closes due to circuit malfunction resulting in RHS loop flow of 5500 gpm
Which one of the following identifies the consequences of the transient?
A. RPV heatup and subsequent pressurization.
B. RPV low water level isolation.
C. RHS heat exchanger overheating.
D. NMS incore instruments damage.
A is correct because reducing cooling flow can result in thermal stratification, which will result in rising temperature in the RPV. Rising temperature will cause pressure increase. B is incorrect. Changing flow on shutdown cooling will have no significant effect on level. C is incorrect. Heat exchanger cooling water flow is not affected, and is sufficient to prevent overheating. D is incorrect. lncore instruments are rated for high temperature, high pressure applications, but high flow above 5700gpm is a concern in Mode 5, with fuel removed from surrounding areas.
- The plant is in cold shutdown with Low Pressure Core Spray system being placed in a Full Flow Test lineup for pump operability testing, with the following:
- CSL*FV114, TEST RETURN TO SUPPR POOL THROTTLE is throttled to 6400 gpm
- Just as this flow is achieved, the thermal overloads trip for CSL*FV114
- THEN a circuit malfunction results in LPCI A/LPCS RESET white seal-in light illuminating and initiating CSL system response
Which one of the following identifies the resulting CSL system flow, two minutes after the system response begins?
A. 0 gpm through test and injection lines with flow through min flow line.
B. 0 gpm through test line and rated flow through injection line.
C. 6400 gpm through test line with 0 gpm through injection line.
D. Runout flow split through both test and injection lines.
B is correct. CSL*FV114, TEST RETURN TO SUPPR POOL THROTTLE receives a CLOSE signal on system initiation. Thermal overload tripping DOES NOT stop FV114 from stroking full closed. Thermal overload only provides an alarm and computer point and since this is a throttle valve, movement is not affected. The initiation signal contact in the valve close circuit bypasses the control switch contacts. Since RPV pressure is 0 psig while in Cold Shutdown, the injection valve MOV104 will auto open and rated flow through the injection line results. The 88 psid permissive for injection MOV opening is met. This design feature/interlock allows for testing and system realignment for injection with an initiation signal present. The two minute time frame accounts for the stroke time of FV114 (about 1 :30 minutes).
