ML032510029
ML032510029 | |
Person / Time | |
---|---|
Site: | Watts Bar ![]() |
Issue date: | 11/26/2002 |
From: | Tennessee Valley Authority |
To: | Office of Nuclear Reactor Regulation |
References | |
50-390/02-301, 50-391/02-301 | |
Download: ML032510029 (101) | |
Text
Draft Submittal (Pink Paper)
- 1. Senior Reactor Operator Written Exam WATTS BAR EXAM 2002-301 50-390 NOVEMBER 26 &
DECEMBER 9 13,2002 -
QUESTIONS REPORT for WBfindraft
-. .~1. 003A2.02S 00I/T2Gl/nGI/RCP/C/A 3.7/3.9n\l/WB02301/S/RLhl
- ~~ .-
Unit I Reactor Power has been reduced to remove LOOP3 RCP in accordance with AOI-5.
Unscheduled Removal of One RCP Below P-8.
Which ONE of the following describes the initial plant response when the RCP is tripped and action required.
A. Tavg in loop 3 increases to Thot of the other 3 loops and MFW flow must be reduced.
BY Tavg in loop 3 decreases to less than Tcold of the other 3 loops and MFW flow must be reduced.
C. Tavg in loop 3 increases to Thot of the other 3 loops and loop 3 PZR spray valve must be closed.
D. Tavg in loop 3 decreases to less than Tcold of the other 3 loops and loop 3 PZR spray valve must be closed.
R e f W B Lesson Plan 3-OT-AO10500, obj. 6 WB AOI-5, pp. 10 A & C are incorrect because loop 3 Tavg decreases (see quote from AOI 5 below)
D is incorrect because loop 3 has no spray valve B is correct based on based on quote from AOI 5 below and step 1, section 3.3 of AOI 5.
"When a RCP is removed from service, a reverse flow occurs in the affected loop. The result is a significant reduction in the RCS hot leg temperature and reduction in steam generation from the affected SG. Previous experience in losing a RCP "at power" at WBN showed that Tavg in the affected loop went below Tcold in the active loops until feedwater was isolated and a thermal equilibrium was reached. In this instance, Tavg for the affected loop went below the minimum temperature for criticality. Tavg returned to greater than 551°F in approximately 6 minutes following isolation of feedwater to the idle S/G. "
Thursday, October 31,200205:43:39 PM 1
QUESTIONS REPORT for WBfindraft
- 2. 005AK2.02 001 /TICI n I G I/DISCONNECT/C/A
-. .._ 2.5/2.6/N/WB020301/S/RLM Unit 1 was at 25% Power and rampinq up when the RO noticed that one of the Bank C control rods is 13 steps bkow the other rods% Bank C which were at 215 steps.
At 0900, immediately after discovery, power assension was halted.
At 0945, the rod was determined to have an electrical problem which was repaired.
At 1015, the management staff has concurred with realignment of the misaligned rod in accordance with AOI-2, Malfunction of the Reactor Control System.
Which ONE of the following outlines the method of realigment?
A. Record information from Bank Overlap Unit, step counters, and P/A converter. Disconnect lift coil for the affected rod, reset step counters, select Bank C and insert Bank C control rods.
B. Disconnect lift coil of the affected rod, select Bank C and insert Bank C.
CY Record information from Bank Overlap Unit, step counters, and P/A converter. Disconnect all lift coils in Bank C except the affected rod, reset step counters, select Bank C and withdraw affected control rod.
D. Disconnect all lift coils in Bank C except the affected rod, select Bank C and withdraw the affected rod.
Ref WB lesson plan 3-OT-AOI-0200, Obj. 8 WB procedure AOI-2 Distractor analysis:
A is incorrect the procedure for aligning a rod misaligned for >lhr (ie. move the rod to the bank, not the bank to the rod)
B is incorrect same as A, also missing some steps. However, this is the method at step 13 for recovery prior to repair IF it were a Bank D rod.
C is correct per AOI 2 steps 33 through 37 D is incorrect because information from BOU, P/A and step counters must be recorded prior to realignment.
43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Thursday, October 31,200205:43:40PM 2
QUESTIONS REPORT for WBfindraft
___3. OOSK5 03s 001/T2G3mC3/EMERGENCY
-- - BORATION/C/A
-- - 2-913 1/M/WB020301/S/RLM Given the following plant conditions:
- The unit is in MODE 6, refueling activities in progress inside containment.
- " A train RHR in service for core cooling and letdown to CVCS.
- Chemistry reports RCS boron concentration is 1925 ppm.
Which ONE of the following describes the correct actions and the reason?
A. Isolate Refueling Cavity from the Spent Fuel Pit by closing the transfer tube wafer valve to prevent dilution of the Spent Fuel Pit.
B. Place train"B" RHR in setvice, remove "A" train to isolate dilution paths connected to " A train RHR.
C? Initiate boration using AOI-34, "Immediate Boration" to increase boron concentration to minimum required limits.
D. Evacuate containment and verify contaiment integrity intact to ensure Technical Specfication 3.9.4, Contaiment Penetrations is met.
Ref: WB Exam bank, modified to add reason for SRO level question.
Need references GO-6, AOI-34 Distractor analysis:
A is incorrect in that closing the transfer tube valve will not help the regain SDM.
B is incorrect because swapping trains will not increase SDM C is correct because AOI provides guidance immediately increase Cb = 2100 ppm.
D is incorrect due to no procedural guidance to do so and it does not increase SDM.
43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Thursday, October 31, 2002 05:43:41 PM 3
QUESTIONS REPORT for WBfindraft
- 4. 007EA1.03001/TI G2/TIGU/C/A/BIWB02301/SIKFO
.~. ~. ~
An RCS cooldown is in broaress per ES-0.2. "Natural Circulation Cooldown'. The dant is being depressurized using auxiliary spray. As pressure drops through 1300 psig, a rapid rise in pressurizer level is observed. Charging and Letdown are in manual and are matched.
Which of the following describes the expected operator actions and the reason?
A. Isolate charging flow and raise the cooldown rate to 50 degrees F/hr to help shrink RCS inventory.
B. Isolate charging flow and place additional letdown orfice(s) in service to remove the excess RCS inventory.
C. Isolate the Cold Leg Acculmulators to prevent further introduction of nitrogen to the RCS.
DI Isolate the auxiliary spray and energize pressurizer B/U heaters to collapse the bubble in the Rx head.
WB Bank -
- a. incorrect - increasing the cooldown rate will further decrease RCS pressure
- b. incorrect - this will decrease the inventory but not address the pressure drop
- c. incorrect - isolating the cold leg accumulators will not effect the level or ppressure at this time
- d. correct - stopping the aux spray flow will stop the depressurization and truning the B/U htrs on will help recover the pressure.
43.5 Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
Thursday, October 31,200205:43:41 PM 4
QUESTIONS REPORT for WBfindraft 5.009EA2.34001fTIGUTlGUPROCEDURE/C/A (3.6/4.2)lBTwBO2301/SIKFO Given the following conditions on Unit 1:
- Reactor trip and safety injection have occurred
- MSlVs have just closed due to containment pressure
- RCS pressure is 1700 psig and stable
- CETCs indicate 570 F
- Total AFW flow is 700 gpm
- PZR level is 42%
Based on these known conditions, the operators should .........
A. actuate phase B to address the increased containment pressure.
BY terminate Safety Injection.
C. verify all RCPs are stopped.
D. initiate containment spray as a result of increased containment pressure.
Ref: bank from Byron '00, validated for WB in E-0, ES-1.1
- a. incorrect - Phase B actuated if containment pressure >2.8 psig,
- b. correct SI termination criteria met
- d. incorrect - if required the containment spray pumps would have auto started, containment presure only high enough to close MSlVs Thursday, October 31,2002 05:43:41 PM 5
QUESTIONS REPORT for WBfindraft 6.02XAA2.12 001/TlG3/T1G3/PZRLEVELICIA 3.3/3.4n\I/WB020301/S/RLM Given the following:
-Unit 1 is at TOO./,power
-Pressurizer level is decreasing slowly
-The output of the Pressurizer Level Controller is increasing
-The Charging Flow Controller is increasing
-Charging flow decreasing.
-Annuciator 922, PZR LEVEL LO-HTRS OFF & LTDN CLOSED is illuminated Which ONE of the following is the cause of the Pressurizer level decrease?
A. FCV 93, charging flow control valve has developed a diaphram leak.
B? The Charging Flow Controller is failing high.
C. The PZR Level Controller is failing high.
D. The Tav input to the PZR is failing high.
Ref: Watts Bar lesson plan 3-OT-SYS068C, obj. 15 Watts Bar lesson plan 3-OT-SYS062A Distractor analysis:
Answer A is incorrect because FCV-62-93fails open, hence a diaphram leak would tend to make the valve open (higher flow). Note: If the leak is small enough, the flow controller would handle it with increased output, but flow would stay on program until the controller maxed out and then flow would increase.
Answer B is correct because the Charging Flow Controller failing, in this case high, causes FCV-62-93 to close thus decreasing flow and hence PZR level.
Answer C is incorrect because the PZR Level Contoller failing high would call for more charging flow thus causing Charging flow and PZR level to increase.
Answer D is incorrect because the auctioneeried high controlling Tav would call for a level increase until it maxed out the program. This would cause charging flow to either increase or remain the same.
Thursday, October 31,200205:43:42PM 6
QUESTIONS REPORT for WBfindraft 7.038EA1.04001/TlG2/TlG2/PRESSUREREDUCTION/C/A4.5/4.8/NAVB020301/S/RLM
- Unit 1 was at 100% and experienceda failed open PORV for which the block valve only partially closed.
- After the immediate actions of 1-E-0, Reactor Trip or Safety Injection, it has been determined that I C SG is ruptured.
- The operating crew has isolated the ruptured SG and transitioned to 1-ECA-3.1, SGTR and LOCA - Subcooled Recovery
- RCS pressure has recovered and is 1750 psig and increasing
- Pressurizer level is 100%
- RCS temperature is 530" F
- I C SG Wide Range level is 85% and increasing
- All automatic systems have functioned properly and RCP's are running Which ONE of the following describes the actions required to stabilize SG break flow?
A. Cooldown by dumping steam from the non-ruptured SG's followed by depressurization of the RCS with Pressurizer Spray Valves.
B. Cooldown with RHR followed by depressurization of the RCS with Pressurizer Spray valves.
CY Cooldown by dumping steam from the non-ruptured SG's followed by depressurization of the RCS with Pressurizer PORV's.
D. Cooldown with RHR followed by depressurization of the RCS with Pressurizer PORV's.
Ref: WB EOP E-3, Stm Gen Tube Rupture, pg 16 and 17 Distractor analysis:
Answer A is incorrect because PZR spray is not effective in a PZR with level at 100%
Answer B is incorrect because RCS pressure is too high for RHR and spray ineffective Answer C is correct because PORV's are by procedure the next preferred depressurization method after PZR sprays and the SG's are the preferred heat removal method Answer D is incorrect because RCS pressure is too high for RHR Thursday, October 31,200205:43:42P M 7
QUESTIONS REPORT for WBfindraft 8.051AA2.02SOOl/TlGl/TlGlNACUUM/C/A 3.9/4.1/BIWB020301/S/RLM Given the following:
- Condenser pressure rising; operators dropping turbine load in attempt to maintain vacuum.
- Condenser backpressure is 5.7 Hga.
- Main turbine load is 43%.
Which ONE of the following would be the FIRST to automatically occur or be procedurally required if condenser pressure continues to rise?
A. Auto main turbine trip on low vacuum.
B. Manual reactor trip.
C. Loss of steam dump capability.
DY Manual turbine trip.
Ref: WB Lesson Plan 3-OT-A011100,obj. 2 AOI-11, Sec. 2.3; Sec. 3.0 steps 6-8 WB Exam bank Distractor analysis:
A is incorrect because auto trip does not occur until vacuum >7.0 Hga B is incorrect because the procedure directs turbine trip first.
C is incorrect because are capable unit1 vacuum reaches 76.5 Hga D is correct per guidance in A01 1I Thursday, October 31,2002 05:43:42 PM 8
QUESTIONS REPORT for WBfindraft
- 9. 056AK1.01S 001mlG3/TlG3/ES-0.2/C/A 3.7/4.2/"B02301/S/RLM I
-Unit 1 has experienced a Loss of Offsite Power
-The operating crew is currently performing a cooldown, in accordance with ES-0.2, Natural Circulation Cooldown
-Prior to initiating the cooldown, two CRDM fans trip Which ONE of the following describe the implications of the loss of the two CRDM fans?
A? The time to achieve RHR conditions is increased, requiring additional CST makeup.
B. Steam voiding in the RCS vessel will occur unless ERCW is supplied to the AFW suctions.
C. Loss of RCS subcooling will occur as the RCS is being depressuized.
D. At least one of the tripped fans must be restarted (total of 3 running) prior to commencing cooldown.
Ref: WB Lesson Plan 3-OT-EOP0000, obj. 15 WB Lesson Plan 3-OT-EOP0000 pp. 41 & 42 Distractor analysis:
A is correct because with less than three CRDM's, the max cooldown rate is reduced from 50"F/hr to 25"F/hr which challenges the CST makeup capability (see basis for step in lesson P W B is incorrect because voiding in the vessel is related to depressurization which in not related to the choice of filling the CST from ERCW.
C is incorrect because the procedure contols subcooling margin during depressurization D is incorrect because the procedure does not require 3 or more CRDM fans prior to start of cooldown.
(5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.
Thursday, October 31,2002 05:43:43 PM 9
QUESTIONS REPORT for WBfindraft
- 10. 057AA2.19 OOl/TlGl/TlGlNITAL BUS/C/A 4.0/4.3/NiWB020301/SlRLM
" down due to a failure of 120 VAC Vital Instrument Power Board 1-1. When Rx I Unit 1 is shuttina power is approximately IO%, the unit trips.
Which ONE of the following decribes the reason for the trip?
A. SRM High Flux Trip BY IRM High Flux Trip C. Low Setpoint of PRM High Flux Trip D. High Setpoint of PRM High Flux Trip WB lesson plan 3-OT-A012500, Obj. 1 and 2 WB procedure AOI-25, pp. 8 Distractor analysis:
A is incorrect because the plant is above P-6 B is correct because 1 of 2 IRM's high flux trip is in when the plant goes below P-10 which reinstates the IRM High Flux Trip function.
C is incorrect because coincidence for PRM trip not met D is incorrect because coincidence for PRM trip not met and power less than trip setpoint.
Thursday, October 31,200205:43:43PM 10
QUESTIONS REPORT for WBfindraft 11.060AA2.04 001/TlG2lTlGUGAS TANK LEAK/M/B/WBO23Ol/S/KFO Given the following plant condtions:
- Gas Decay Tank release in progress with ABGTS running for dilution air flow
- A leak occurs on the waste gas compressor which results in a gas release to the Auxiliary building RE-90-101, Auxiliary Building Vent Monitor, is in alarm
- Assume no operator action Which of the following indicates the effect this leak will have on the plant?
A. Gas Decay Tank release will be terminated: ABGTS will be stopped B. Gas Decay Tank release will be terminated; ABGTS will continue to run C. Gas Decay Tank release will continue; ABGTS will be stopped D? Gas Decay Tank release will continue; ABGTS will continue to run REF: WB 01 - verbatim question SRO Only (43.4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contaminationconditions.
Thursday, October 31,200205:4343PM 11
QUESTIONS REPORT for WBfindraft 12.073A2.01S O O ~ I T ~ . G ~ ~ T ~ G ~ ~ ' U R G 3.1/3.5/N/WB020301/S/RLM FKIA The following conditions exist for Unit 1:
-Mode 6
-Fuel movement in Containment in progress
-Contaiment Purge operating
-Annunciator 174-D, CNTMT PURGE EXH I-RM-I 30/131 INSTR MALF alarmed
-A construction worker called the control room a few minutes after the alarm to say that he accidently pulled some wires loose and a small pump stopped running in containment.
Which ONE of the following describes the required actions by the control room operators?
A. Restore the rad monitor to service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend fuel movement.
BY lmmediatley shutdown containment purge when the annunciator alarms.
C. Verify that containment purge automatically tripped.
D. Suspend fuel movement until the rad monitor is restored to service.
Ref: WB lesson plan OT-SYSOSOA, obj 7 ARI 174-D TS 3.6.6 Distractor analysis:
A is incorrect because neither the TS nor the ARI direct stopping fuel movement.
B is correct because the ARI directs shutting down purge if it is running C purge does not automatically trip on RM 130/131 low flow (instrument count rate will decrease).
D is incorrect because again there is no guidance in TS or the ARI to suspend movement and there are specific actions required within specified timeframes (ie secure purge).
Thursday, October 31, 2002 05:43:44PM 12
QUESTIONS REPORT for WBfindraft
- 13. 076AA2.02S 001/TI G 1/T1G l//C/A/N/WB0230l/S/KFO/RLM Given the following:
- Unit is at 100%
- Chem - Lab reported Reactor Coolant Dose Equivalent Iodine-131 Specific Activity is 6.3 pCilgm, which is somewhat higher than expected.
- The sample was taken @ 0730 on 11/04/02.
Based on these conditions, which ONE of the following operator actions are now required?
Reference provided A. Place all CVCS demins in service at maximum flow rate and continue power operations.
B. Monitor Dose Equivalent 1-131 within acceptable region of Appendix A once per 4 hr and reduce power as necessary to maintain within acceptable region of Appendix A.
C. Place unit in Mode 3 at less than or equal to 500 "F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
DI Continue power operations.
WB Bank - validated per AOI-28 and lesson plan 3-OT-A0112800
- a. incorrect - CVCS demins not required
- b. incorrect - c. incorrect - monitoring not requiredThis action causes the plant to be unnecessarily reduce power.
- c. This action causes the plant to be unnecessarily reduce power.
- d. correct - The Reactor Coolant Dose Equivalent Iodine-I31 Specific Activity per Appendix A of AOI 28 is less than the limit of 10 KCi/gm. No information is given about Dose Equivalent Iodine-131. Therefore, no action is required.
Note: This procedure, AOI 28, poorly distinguishes between the Specific Activity Spec and the Dose Equivalent Iodine Spec.
Thursday, October 31,2002 05:43:44P M 13
QUESTIONS REPORT for WBfindraft 14.086G2.4.25S~~IITZGUT~GUAPPENDIX R FIRWCIA 2.913.4/NIWB020301/ UM Unit 1 is currently at 100%
A fire has been reported in the Auxiliary Building The Turbine Driven AFW pump is disassembled for maintenance All other equipment is functional In accordance with AOI 30.2, Fire Safe Shutdown procedure, whit ONE of the llowing functions, if lost, would prevent meeting the Steam Generator Inventory Control Jnction?
A. 1A Motor Driven Auxiliary Feedwater Pump B. One channel of Steam Generator Level Control CI Suction from the Condensate Storage Tank D. Suction flow from one train of Essential Raw Cooling Water Ref: WB lesson plan 3-OT-AOI 3000, obi 12 AOI-30.2 Distractor Analysis:
According to the attached logic diagram, a loss of suction from the CST will prevent fulfillment of the SG Inventory Control Function. (see attached) This is not intuitive since one train of ERCW should suffice for supplying flow to AFW motor driven. Will need plant input on this.
Need to provide AOI 30.2 as reference Thursday, October 31,2002 05:43:44PM 14
QUESTIONS REPORT for WBfindraft
- 15. 103A2.03S00I/T2G3KZG2/PHASE B/M 3.5/3.8/N/WB020301/S/RLM
-Unit 1 has Safety lniected
-Phase A actuated .
-Phase B just actuated
-A review of the Main Control Board indicates that the Air Return Fans are not running Which ONE of the following describes the correct action and reason?
A. Immediatelystart the Air Return Fans because they should have started on a Phase B Isolation Signal.
B:' Start Air Return fans when 10 minutes have elapsed to prevent Hydrogen gas pockets from forming in Containment.
C. Immediatelystart the Air Return Fans to prevent Hydrogen gas pockets from forming in Containment.
D. Start Air Return fans when 10 minutes have elapsed to prevent overloading safety related electrical busses during initial transient.
WB lesson plan 3-OT-SYS030D, obj 3 WB procedure E-0, step 11, RNO Distractor analysis:
A and C are incorrect because E-0requires waiting 10 min.
D is incorrect because there are no reference in FSAR, or lesson plans to electrical loading issues.
6 is correct based on guidance in E-0 and secondary purpose of system Thursday, October 31, 2002 05:43:45PM 15
QUESTIONS REPORT for WBfindraft
- 16. G2.1.14001/T3/T3/NOTIFICATION/M2.5/3.3/NNB020301/S/RLM Which ONE of the following must be notified when a Temporary Alteration installation has been completed orJreturnedto normal?
A. Unit Operator B. Unit Supervisor C: Shift Manager D. Unit Manager Ref: WB procedure SPP-9.5, Temporary Alterations No lesson plan provided Distractor analysis:
See attached Thursday, October 31,200205:43:45PM 16
QUESTIONS REPORT for WBfindraft
- 17. (32.2.29OOl/T3/T3/FUELHANDLINGM 1.6/3.8/B/WB020301/S/lUM The following plant condition exists:
You are SRO for refueling into the reactor vessel when the US informs you that one source range channel has failed its surveillance.
Which ONE of the following is the required action?
A: Suspend core alterations until the failed source range channel is operable.
B. Continue fuel reload as one channel is operable.
C. Continue fuel reload for = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period until two source range channels operable.
D. Suspend core alterations until boron sampling has been completed.
Ref: San Onofre Bank 2000 WB Tech Specs, section 3.9.3 B and C are incorrect because they violate TS D is incorrect because it is part of the actions for loss of two source ranges Dont have GO-7Refueling procedure Thursday, October 31,200205:43:45PM 17
QUESTIONS REPORT for WBfindraft I
18.G2.2.8 001~3/T3/50.59/C/AI .8/3.3/BMrB020301/S/RLM .
Changes to which ONE of the-following will require a 10CFR50.59 review?
A. Change to the Physical Security Plan that requires moving a section of the perimeter fence.
B. Revision to the Radiological Emergency Plan that changes the designated assembly areas for accountability.
CY System modification that adds a full flow recirculation test line to the discharge of the Safety Injection pumps.
D. Changes to the Nuclear Quality Assurance Plan.
Reference:
WB procedure SPP-9.4 WB failed to provide SSP-9.4, will need if distractor analysis to be done.
(43.3) Facility licensee procedures required to obtain authority for design and operating changes in the facility Thursday, October 31,200205:43:46PM 18
QUESTIONS REPORT for WBfindraft
- 19. G2.3.8 001/T3/T3/WASTE GAS RELEASEN 2.3/3.2/N/WB020301/S/RLM Unit 1 is preparing to release Waste Gas Decay Tank E, which was remove from service 32 days ago, in accordance with Sol-77.02,WASTE GAS DISPOSAL SYSTEM.
Which ONE of the following decribes the minimum approval authority for the release?
A. UNIT SUPERVISOR and CHEMISTRY DUTY MANAGER B. SHIFT MANAGER and UNIT SUPERVISOR CY SRO and CHEMISTRY DUTY MANAGER D. SHIFT MANAGER and another SRO Ref: WB procedure Sol-77.02 No learning objective found Distractor analysis:
A is incorrect because the Unit Supervisor is not listed in the procedure as an approval authority.
B and D are incorrect because the Chemistry Duty Manager must approve release of tanks less than 60 days old.
C is correct per attached procedure Thursday, October 31,2002 05:43:46P M 19
QUESTIONS REPORT for WBfindraft 30.WE02EK1.2 COl/TIGUTlGl/SI TERMINATION/M 3.4/3.9iB/WB020301/S/RLM Given the following conditions:
- Main steam line break has occurred outside containment, resulting in a reactor triplsafety injection (SI).
- MSlV closure stopped the steam release.
- SI termination criteria was met and the crew is currently terminating the SI per ES-1.1, "SI Termination."
Which ONE of the following combinations of parameters would require an immediate reinitiation of safety injection?
Maximum RCS RCS PZR CNTMT Press Subcooling Pressure Level A. 1 psig 75°F Stable 18%
B. 2 psig 72°F dropping 20%
C. 3 psig 87°F dropping 34%
D? 4 psig 60°F Stable 24%
Ref: WB lesson plan 3-OT-EOP-0000, Obj. 8 Distractor analysis:
- a. Incorrect - with containment conditions below the adverse setpoint of 2.8 psig the reinitiation criteria is PZR level 4 5 % and subcooling < 65°F.
- b. Incorrect - both PZR level and subcooling are above the minimum for conditions below adverse setpoints.
- c. Incorrect - both PZR level and RCS subcooling are above the minimum for adverse containment conditions.
- d. Correct - with adverse containment conditions (22.8psig) the reinitiation criteria is PZR level ~ 3 3 % or RCS subcooling 4 5 ° F .
Thursday, October 31, 2002 05:43:46 PM 20
QUESTIONS REPORT for WBfindraft 2 1. WE04EA2.1001 iTlG2iTl GWROCEDURE TRANSITION/C/A 3.4/4.3/N/WB020301/S/RLM I
Unit 1 was at 100% and was manually Safety Injected due to decreasing pressurizer level.
Plant status is:
-The Operating Crew is performing E-0, Reactor Trip or Safety Injection
- All automatic actions occurred
-RCS pressure is stable at 1600 psig
-Pressuizer level is slowly rising at 17%
-Steam Generator pressures and levels are stable
-Steam Generator were trending normal prior to isolation and Condenser exhaust rad monitor is normal
-Containment conditions are pre-event
-Area monitor recorder 1-RR-90-1 and 0-RR-90-12A have significantly upscaled
-Vent monitor recorder 0-RR-90-101 was trending up prior to isolation Which ONE of the following describes the correct procedure transition?
A. Remain in E-0, Reactor Trip or Safety Injection.
B. Go to E-I, Loss of Reactor or Secondary Coolant.
CY Go to ECA-1.2, LOCA Outside Containment.
D. Go to ES-0.0, Rediagnosis.
Ref: WB Lesson Plan 3-OT-EOP0000, obj. 1 WB Lesson Plan 3-OT-ECAO101, obj. 8 Distractor analysis:
A is incorrect because Step 29 directs transition to ECA-1.2 due to abnormal Aux Bldg radiation levels.
B is incorrect because Containment conditions are pre-event.
C is correct because Step 29 directs transition to ECA-1.2 due to abnormal Aux Bldg radiation levels.
D is incorrect because it only applies after transition from E-0.
Thursday, October 31,200205:43:47PM 21
QUESTIONS REPORT for WBfindraft
- 22. WE06EA2.1001~1G1/T1GllFR-C.2/C/A/B/WB02301/S/RLM A LOCA is in progress with all RCPs secured, and the control room operators are attempting tc stabilize plant conditions. An operator who is monitoring plant parameters observes the following:
.. Core exit TCs: 780°F
885 psig 50%
Which one of the following describes current core cooling conditions and operational requirements?
A. Subcooled. Operator action is not required because core cooling is satisfactory.
B. Saturated. At their discretion, the operators can take action to restore subcooled core cooling per FR-C.3, "Response to Saturated Core Cooling."
CY Degraded. Prompt action must be taken per FR-C.2, "Response to Degraded'Core Cooling," or conditions could degrade.
D. Inadequate. Prompt action must be taken per FR-C.1 "Response to Inadequate Core Cooling, or core uncovery and fuel damage could occur.
Modified from a Surry Bank Question # 425.
Lesson Plan 3-OT-FRC0001 FR-C.1,C.2,C.3, objective # 1 A. Incorrect, the conditions given indicate that the RCS is in a superheat condition.
B. Incorrect, the conditions given indicate that the RCS is in a superheat condition.
C. Correct, the conditions given indicate that the RCS is in a degraded core cooling condition, and this is the correct remedial action to take.
D.Incorrect, the conditions given indicate a degraded core cooling condition.
Thursday, October 31, 2002 05:43:47PM 22
QUESTIONS REPORT for WBfindraft
- 23. WE08EA2.1S 001/TlGl/TlGl/F'TS/M 3.4/4.2/B/WB020301/S/RLM Given the following plant conditions:
- Crew is responding to a large-break LOCA
- FR-P.l currently being performed in response to a PTS ORANGE path
- Containment status tree is ORANGE Which ONE of the following is the correct crew response if the PTS status tree turns YELLOW prior to the completion of the Function Restoration Instruction?
A. Crew should stop performance of all Function Restoration Instructions, then evaluate all Critical Safety Functions to determine the appropriate procedure to implement.
B. Crew must complete FR-P.l since it is equivalent to the PTS RED path Function Restoration Instruction, unless it is superceded by a higher priority RED path.
CY Crew should continue with FR-P.l until transitioned out or the procedure is completed. Status trees will be evaluated at that time to determine the appropriate procedure.
D. Crew should stop performing FR-P.1 and implement the Containment ORANGE path Function Restoration Instruction since it is now the highest priority.
. Ref: WB Lesson Plans 3-OT-FRP0001, obj. 10 and 3-OT-PAI1204, obj. 5 Procedure PAI-1204, pp. 26 WB exam bank A is incorrect because while in FRP's, CSF status trees are monitored continuously B is incorrect because the plant conditions, not the procedure number determines implimentation priority.
C is correct based on reference PAI-1204 D is incorrect because it conflicts with guidance in PAI-1204 Thursday, October 31,200205:43:47PM 23
QUESTIONS REPORT for WBfindraft
- 24. WE13EA2.E 001 ~lG3/TIG3/0VERPRESSUREK/A2.9/3.3/B/WB02301/SRLM The Unit 1 operating crew is currently executing E-I, "Loss of Reactor or Secondary Coolant".
Plant conditions are as follows:
- Containment pressure is 4.5 psig and slowly decreasing.
- RCS temperature is 570°F.
- S/G Pressures: S/G # I = 1200 psig; S/G#2 = 1190 psig; S/G#3 = 1230 psig; S/G#4 = 1205 psig.
- SG NR Levels: S/G # I = 25%; S/G#2 = 30%; S/G#3 = 85%; S/G#4 = 35%.
- FR-H.2, "Steam Generator Overpressure", has been entered.
For the existing plant conditions, the Unit Supervisor should:
AI Direct the operators to NOT release steam from S/G#3 and transition to FR-H.3, "Steam Generator High Level" to control and lower S/G#3's level.
B. Direct the operators to NOT release steam from S/G#3 and continue with FR-H.2 to reduce S/G pressure.
C. Direct the operator to open the PORV on S/G#3 to drop pressure below 1220 psig then transition to FR-H.3, "Steam Generator High Level" to control and lower S/G#3's level.
D. Direct the operator to open the PORV on S/G#3 to drop pressure below 1220 psig and continue with FR-H.2 to reduce S/G pressure.
Ref: WB Lesson Plan 3-OT-FRH0001 obj 6 WB Lesson Plan 3-OT-FRH0001 pp 41 & 42 of 56 10CFR43.5 Source WB exam bank last used in '98 SRO audit Distractor analysis:
Answer A is correct based on FR-H.2 procedure step 3 RNO Answers B, C, & Dare incorrect based on inappropriate actions and branching directions Thursday, October 31,20020543:48 PM 24
QUESTIONS REPORT for WBfindraft
- 25. WE 16G2.3.10 00 1 /T 1 GuTl G2EXPOSURE REDUCTIONm 2.9/3.3/BiWB02030 1 /SEL/RLM Given the following:
- A Small Break LOCA occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.
- Containment pressure is 1.7 psig.
- Containment temperature is 220°F.
- Lower containment radiation indicated level is 25 Whr.
- FR-Z.3, "High Containment Radiation", is entered.
Which ONE of the following actions is required in accordance with FR-Z.3?
A. Peform a manual Phase 6 isolation. I BY Ensure control room isolation.
C. Sample containment atmosphere using PASF.
D. Ensure that all lower compartment coolers are in service.
Ref: WB Exam Bank WB Lesson Plan 3-OT-FRZOOOI , no specific learning objective WB Lesson Plan 3-OT-FR2.0001, pp. 15 Distactor analysis:
B correct because of step 4 in FR-2.3.
A, C, D,are incorrect because they are not required by the procedure.
Is this part of the sample?
Thursday, October 31,2002 05:43:48 PM 25
QUESTIONS REPORT for WBfindraft
- 1. 001AK3.0 1 OOI/T1 GZITIGIIICIA (3.213.6)/B/WBO2301/C/EL Given the following plant conditions:
- Plant at 65% power.
- Impulse pressure transmitter, 1-PT-1-73, fails high causing rods to step at 72 steps per minute.
- Rods were placed in MANUAL causing rod motion to stop 14 steps from their original position.
Which ONE of the following describes the appropriate course of action?
A. Ensure turbine load remains constant and dilute to restore original rod position.
B. Reduce turbine load to compensate for the rise in reactor power.
C. Withdraw rods manually to restore Tavg to program.
D I Insert rods manually to drop Tavg to program.
The correct answer is
- a. Incorrect - Diluting would further increase the difference between Tavg and Tref if turbine load were held constant.
- b. Incorrect - Turbine load would need to be increased to offset the increase in T-avg due to rods stepping out from the NI failure.
- c. Incorrect - withdrawing rods would further increase the difference between Tavg and Tref.
- d. Correct - Tavg would be elevated due to the rods stepping out on the PT failure.
Inserting rods manually to decrease Tavg to program is appropriate.
Thursday, October 31,200206:05:48PM 1
QUESTIONS REPORT for WBfindraft
- 2. 00 1K1.05 00 lIT2G 1IT2G1/NI FAILURE/C/A/N/WB0230 1ICIKFO Given the following:
- Unit power is 66%
- Control Rods are in Automatic .
- No operator actions Which ONE of the following would cause rods move in , then remain at the new position with a reduced T-avg.
A. Loop A Th fails low B. PT 1- 73 fails high C. Loop A Tc fails low D I Pwr channel NI-41 fails high New, REF: 3-OT-SYS85A
- a. incorrect - rod control circuit uses auct High Tave - failing low does not make this the auct hi
- b. incorrect - this channel of turbine pressure inputs the control rod logic and the Tref program is topped out at 588.2
- c. incorrect - rod control circuit uses auct High Tave - failing low does not make this the auct hi
- d. correct - Rods move in until the power mismatch rate signal decays, then remain at the new position with a reduced T-avg.
Thursday, October 31,200206:0548PM 2
QUESTIONS REPORT for WBfindraft
- 3. 002K5.10 001/T2G2/T2GZ/TEMPERTURE MISMATCH/C/A 3.6/4.l/N/WB020301/C/RLM Unit 1 is at 94% power and ramping up.
Rods are in automatic with Bank D at 210 steps The operator has met all requirementsto increase turbine load and has pressed the turbine control GO button Turbine control valves are opening and megawatts are increasing Tavg is in program Which ONE of the following describes Tavg behavior assuming no dilution by the operator?
A. Tavg and Tref will increase and continue to be matched until the control valves reach the limiter setting.
B. Tref will increase until the control valves reach the limiter setting, but Tavg will remain constant.
C. Tavg and Tref will remain constant and matched as the control valves reach the limiter setting.
DY Tref will increase and Tavg will initially increase, but then Tavg will decrease as the control valves reach the limiter setting.
Ref: WB lesson plant 3-OT-SYS085A, obj 7 & 21 Distactor analysis:
D is correct because Bank D hits the C11 rod stop at 220 steps. As the governor valves continue to open, turbine power continues to rise along with Pimp (Tref). However, no more positive reactivity is added (no dilution per stem) and no rods due to C11, but power defect adds negative reactivity which drives Tavg down until Moderator temp coefficient balances at a lower Tavg.
A, B, and C are incorrect they have Tavg either rising or remaining constant.
Thursday, October 31,200206:0548PM 3
QUESTIONS REPORT for WBfindraft 4.004K5.0400l/T2Gl/T2Gl/OXYGEN/M (2.8/3.2)/BnVBO23Ol/C/KFO Which one of the following is the primary reason for maintaining a hydrogen cover gas in the VCT during normal at power operations?
A. to assure N-16 concentrations are ALARA B. to maintain RCS pH within TRM limits C. to maintain conductivity below ,017 micro Mhos DY to maintain oxygen concentration below the TRM upper limit Ref NA 2002 - validated to WB Lesson plan 3-OT-SYS062A, TRM 3.4.4 Chemistry
- b. incorrect RCS pH is controlled by primary chemistry not with cover gases
- c. incorrect conductivity is controlled by water quality efforts not cover gases
- d. correct Hydrogen cover gases "scavenge" oxygen, thus lowering the oxygen concentration Thursday, October 31,2002 06:05:49 PM 4
QUESTIONS REPORT for WBfindraft
- 5. 006A1.11 001/T2G2/T2G2//M (3.1/3.4)/BIWB02301/C/EL/KFO Given the following plant conditions:
- A SGTR has occurred on SG #I.
- ES-3.1, "Post SGTR Cooldown Using Backfill", is in progress.
- Ruptured SG level is 25%.
- RCS is at 390°F.
- RCS is at 400 psig.
- Cooling down using steam dumps to condenser.
- RCP #4 in service.
ES-3.1 step 13 requires a return to step 3 if RCS temperature is greater than 200°F.
Step 3 requires the operator to ensure adequate shutdown margin.
Why is it necessary to reverify adequate shutdown margin at this point in the procedure?
A. The RCS temperature change during cooldown will cause significant boron concentration changes due to PZR outsurge.
B. Charging to maintain PZR level during cooldown will cause significant boron concentration changes.
CY The secondary fluid in the ruptured SG will cause significant boron concentration changes.
D. The auxiliary spray will cause significant boron concentration changes.
The correct answer is C Thursday, October 31,200206:05:49PM 5
QUESTIONS REPORT for WBfindraft
- 6. 006K1.07 001/T2G2/T2G2//C/A (2.6/2.9)/BIWSO2301/C/EL/KFO Given the following conditions:
- The plant is operating at 100% power.
- Inadvertent Safety Injection occurred
- #SG I level transmitter that controls MDAFW pump LCV failed low.
- #4 SG PORV opened momentarily after the reactor trip and developed a large packing leak.
Which ONE of the following would cause the initial main feedwater isolation during this transient?
A. The #I SG level reached 83%.
B: The safety injection actuation signal.
C. Tavg dropping to 564°F following the reactor trip.
D. When the south valve vault level had risen to 4 inches due to the PORV packing leak.
The correct answer is B.
- a. Incorrect - level may reach 83% but FWI would already have been actuated by the SI.
- b. Correct - SI causes immediate FWI.
- c. Incorrect - would normally actuate FWI following a reactor trip however the SI initiated the FWI immediately.
- d. lncorrecty - PORV leak would cause increase in level in the vault room however FWI would have already been actuated by the SI.
Thursday, October 31,2002 06:05:49PM 6
QUESTIONS REPORT for WBfindraft
- 7. 008AK1.01 OOliTl G2ITI G2IICIA (3.2/3.7)/B/WB0230I/C/KFO Given the following:
- Unit 1 is stable at 100% power
- A pressurizer safety valve opens and fails to reseat and the Unit trips Which of the following indications would the operator expect to see as a result of this event over the next 30 min?
A. Safety tailpipe temperature would increase to greater than 600 F and then slowly decrease.
B. Safety tailpipe temperature would increase to greater than 600 F and then slowly increase.
C? Safety tailpipe temperature would increase to between 220 F and 340 F and then slowly decrease and stablize.
D. Safety tailpipe temperature would increase to between 220 F and 340 F and then slowly increase and stablize.
Ref- Farley 2000, validated for WB -
- a. incorrect -the temperature is correct for pressures of 2240
- b. incorrect -the temperature is correct for pressures of 2240
- c. correct - since it relieves to the PRT, the pressure will increase until the rupture disc relieves (100 psig) and then the pressure (and temperature ) will decrease and eventually stablize
- d. incorrect - will not continue to increase once the PRT rupture disc relieves.
Thursday, October 31,200206:0550 PM 7
QUESTIONS REPORT for WBfindraft
- 8. 010K3.01 001iT2G2iT2G2iPRESS CONTROL/C/A 3.8/3.9/B/WB020301/C/RLM Given the following:
- Pressurizer pressure is 2230 psig and rising.
- The variable heaters are energized.
- The spray valves are closed.
- The Master Pressure Controller, I-PIC-68-340A, fails to a contstant output equivilent to 2230 psig.
Which ONE of the following describes the response of the pressure control system if the operator takes no further action?
A. Pressure will rise until PORV's PCV-68-334 and PCV-68-340A open to control pressure B:' Pressure will rise until relief valve PCV-68-334 opens to control pressure.
C. Pressure will rise until the spray valves open to control pressure.
D. Pressure will cycle on the variable heaters at a higher setpoint.
Ref WB lesson plan 3-OT-SYS068C Distractor analysis:
A is incorrect because PORV continues to receive a constant input and therefore remains closed.
B is correct because PORV 334 receives input from PT 323 which is seeing the actual pressure rise.
C is incorrect because the spray valves remain closed because there input is not changing from the master controller and is spray open setpoint.
D is incorrect because the input to the variable heaters is constant at a value less than their shutoff point.
Thursday, October 31,2002 06:05:50PM 8
QUESTIONS REPORT for WBfindraft 9.01 1A3.03 001iT2G2iT2GZIPZR LEVEL/C/A 3.2/3.3/B/WB020301/C/EL/RLM Given the following:
- Unit is at 50% power.
- All automatic control systems are in their normal lineup.
- Controlling pressurizer program level fails to an output corresponding to 50% load.
- Assume no operator action is taken.
Which of the following describes the effect on charging flow and PZR level as the plant load is increased to loo%?
A. Charging flow increases and actual PZR level remains constant.
B. Charging flow decreases and actual PZR level decreases.
C:' Charging flow decreases and actual PZR level increases.
D. Charging flow remains constant and actual PZR level increases.
Reference:
WB Lesson Plan 3-OT-SYS068C Obj. # I 4 Distractor analysis:
A is incorrect because Tav increases as power increases which will make PZR actual level increase.
B is incorrect, same reason as A C is correct because as PZR level rises with coolant expansion due to Tav increase, with LT-339 output at 50%, an error is generated that PZR level is too high, causing charging flow to decrease.
D is incorrect, same as A for PZR level, charging flow increases, see C.
Note, WB exam bank had answer C as "Charging flow rises and actual PZR level rises." Need to check this with them.
Thursday, October 31,200206:05:50PM 9
QUESTIONS REPORT for WBfindraft
- 10. OllEAl.04 001iTlG2/TlGl//C/A (4.4/4.4)/B/WBO2301/C/EL Given the following plant conditions:
- Unit 1 tripped due to a Large Break LOCA.
- Containment pressure = I 2 5 psid.
- RWST level = 20%.
- Containment Emergency Sump level = 15%.
- RHR Swapover to the Containment Sump could not be performed.
- The operating crew has transitioned to ECA - 1.1, "Loss of RHR Sump Recirculation."
- The crew is performing step 3 of ECA - 1. I , "Loss of RHR Sump Recirculation", to determine the proper Containment Spray pump alignment and operation.
Which ONE of the following actions will result in the Containment Spray pumps being in the proper alignment under the existing plant conditions?
A. Leave both Containment Spray pumps running until RWST level drops to 8%.
B. Stop both Containment Spray pumps and place handswitches in "pull-to-lock."
CY Stop one Containment Spray pump and allow the remaining pump to take suction from the RWST.
D. Stop both Containment Spray pumps, until suction can be aligned to the Containment Sump, then restart one pump.
Thursday, October 31,2002 06:05:51PM 10
QUESTIONS REPORT for WBfindraft
- 11. OllEK2.02 001/TlG2/T1Gl/lC/A (2.6/2.7)iS/WB02301/CiEL Given the following conditions:
- A large break LOCA occurred
- Operators have just completed swapover to Containment Sump
- A loss of offsite power occurs Which ONE of the following describes the actions required for this condition?
A. Pull to lock SI pumps and CCPs until the RHR pumps have been restarted after the shutdown boards are reenergized.
B.' Pull to lock the CCPs until the RHR pumps are restarted after the shutdown boards are reenergized.
C. Ensure both RHR pumps are started by the blackout sequencer after the diesel generators reenergize the shutdown boards then restart the SI pumps.
D. Ensure all ECCS pumps are started by the blackout sequencer when the diesel generators reenergize the shutdown boards.
The correct answer is B Thursday, October 31, 2002 06:05:51 PM 11
QUESTIONS REPORT for WBfindraft
- 12. 012K6. IO 00 I I T Z G ~ ~ T ~ T Z / P -.3/3.5/N/WB02030
~/M~ l/C/RLM Unit 1 is at 100% power Permissive 70-D, P-7 LO POWER TRIPS BLOCKED illuminates Which ONE of the following describes the effects on RPS?
A. The reactor will not trip on Pressurizer High Pressure.
B. The reactor will not trip on Pressurizer Low Water Level.
C:' The reactor will not trip on Pressurizer Low Pressure.
D. The reactor will not trip on Loss of Flow in one loop.
Ref: WB Lesson Plan 3-OT-SYSOQQA, obj. 17 Distractor analysis:
A is incorrect because P-7 is not an input to the trip.
B is incorrect because PZR Lo Water Level is not a trip.
C is correct, because P-7 blocks it when P-7 is off (light on).
D is incorrect because P-8 is unaffected and trips Rx on 114 logic.
hursday. October 31,2002 06:05:52 P M 12
QUESTIONS REPORT for WBfindraft
- 13. 013K2.01 001/T2Gl/T2Gl/PUMP TRIP LOGIC/M (3.6/3.S)/S/WBO2301/C/KFO Given the following:
- 1A-A and 1B-B SI pump breakers are "racked in"
- A fuse blows in the NORMAL DC Trip Circuit for the 1A-A SI pump
- A safety injection (SI) acutation occurs Which of the following describes the response of the SI pumps to the SI signal?
A. 1B-B SI pump will start, but 1A-A SI pump will not auto start until the control power supply is transferred.
B. 1B-B SI pump will start, but 1A-A SI pump will not auto start and must be started from MCR handswitch.
CY Both SI pumps will auto start, but the 1A-A SI pump can not be stopped from the MCR.
D. Both SI pumps will auto start, but the 1A-A SI pump can not be stopped from the mechanically at the breaker.
Watts Bar exam bank - NEED CONFIRMATION ON BREAKER LOGIC Thursday, October 31,2002 06:05:52PM 13
QUESTIONS REPORT for WBfindraft
- 14. 014A4.01OOl/T2G2iT2Gl/STARTUF'/C/A( 3.3/3.4)IB/WB02301/C/KFO Given the following:
- Operators are preparing for a reactor startup
- Both shutdown banks were withdrawn
- All control banks are still fully inserted
- The rod control startup reset switch is manipulated in error Which of the following describes the required actions to proceed with the startup?
A. Restore the P/A converter to 230 steps BY Restore the shutdown group step counters to 230 steps C. Restore the bank overlap unit to 230 steps D. Reinsert all shutdown banks INPO bank - validated for WB lesson plan 3-OT-SYS85A
- a. incorrect - P/A converter does not need to be reset because the control banks are fully inserted
- b. correct - all group step counters are reset to 0 by the reset switch
- c. incorrect - bank overlap counters are at 0 because the control rods are fully inserted
- d. the shutdown group counters can be manually reset - reinsertion is not required Thursday, October 31, 2002 06:05:52PM 14
QUESTIONS REPORT for WBfindraft
- 15. 0 15K4.06 00 1K2G1/T2G lliMIBANB02301ICIKFO While operating at 90% power, one power range channel of nuclear instrumentation Power Range High Flux Reactor Trip is placed in bypass.
What is the coincidence for a NIS reactor trip?
A. 2 o u t o f 4 B I 1 out of 3
- c. 2outof4 D. 1 out of 3 INPO bank
- a. incorrect - coincidence changes to 1 out of three when in bypass
- b. correct - coincidence changes to 1 out of 3
- c. incorrect -wrong logic and bypass limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- d. incorrect - bypass status limited to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Thursday, October 31, 2002 06:05:53PM 15
QUESTIONS REPORT for WBfindraft 16.017AK1.04OOliTlGliTl GI /LOSS OF FLOWICIA (3.7/4.1)lBiWB02301/C/RLM Given the following plant conditions:
- Unit is operating at 30% power.
- All control systems are in AUTO.
- Loop 3 Reactor Coolant Pump has just tripped.
Which ONE of the following is the overall plant response?
A. Reactor trips on HIGH steam generator level when the #3 steam generator level "swells".
B.Y Unit power remains the same with steam flow rising on the other steam generators.
C. Unit power is reduced to approximately 22% power (3/4of original power level).
D. The reactor trips on a Low RCS Flow condition.
WB bank Thursday, October 31, 2002 06:05:53 PM 16
QUESTIONS REPORT for WBfindraft
- 17. 017K3.O 1 00 1IT2G1/T2G 1/FAILED CORE EXITIMIBIWB0230 1/C/KFO If all core-exit thermocouples are inoperable during an event in which the RCPs were tripped, what indication(s) may be used to verify that natural circulation cooling is occurring?
A. RCS hot leg temperatures only B. RCS cold leg temperatures only CY Both RCS cold leg and hot leg temperatures D. There are no direct indications to verify natural circulation for this condition.
Bank (NA02) - validated for Watts Bar, ES-01, "Reactor Trip Response
- a. incorrect - insufficient information
- b. incorrect - insufficient information
- c. correct -the difference in temperatures will be adequate to determine of natural circulation has been established
- d. incorrect, using both hot and cold legs is adequate Thursday, October 31,200206:0553PM 17
QUESTIONS REPORT for WBfindraft
- 18. 022AG2.1.32 00 liT 1G1/T 1GULOW PRESSURE LETDOWNIM 3.4/3.8/N/wB02030 1ICIRLM During water Solid operations with letdown from RHR, Sol-62.01 requires that FCV-62-83, RHR LETDOWN FLOW CONTROL be full open.
Which ONE of the following describes the basis for this precaution?
A. To ensure maximum letdown flow rate for purification.
B. To ensure VCT level can be maintained under all charging flow conditions.
CY To ensure PCV-62-81, Letdown Pressure Control can control pressure transients.
D. To ensure RCS to RHR Supply Line Relief Valve (74-505) isn't challenged.
No specific learning objective found.
Distractor analysis:
Answer A is incorrect because charging flow controls letdown flow.
Answer B is incorrect because balancing charging and letdown controls VCT level.
Answer C is correct because with FCV-62-83 less than full open, it can in effect limit flow and prevent pressure reduction when PCV-62-81 fully opens in response to a high pressure transient.
Answer D is incorrect because the suction relief can be challenged by other factors (eg. pump starts) even with FCV-62-83 full open.
Thursday, October 31,2002 06:05:54 PM 18
QUESTIONS REPORT for WBfindraft
- 19. 02262.1.10 00l/T2GliT2Gl/CTMT AIR TEMP/M 2.7/3.9/MIWB020301/C/RLM Which ONE of the following correctly identifies the minimum and maximum allowable temperatures per Tech Spec for the Containment upper compartment temperature in Mode 2.
A. Between 85°F and 120°F B! Between 60°F and 110°F.
C. Between 60°F and 120°F.
D. Between 85°F and 110°F.
Ref: WB lesson plan 3-OT-SYS030C, obj 3 W 0 TS 3.6.5 Modified from WB exam bank which asked MODE 1 limits.
Distractor analysis:
See attached TS Thursday. October 31,2002 06:0554PM 19
QUESTIONS REPORT for WBfindraft
- 20. 024AK2.01 00 1/T1G 1/T 1G 1//M (2.7/2.7)/8iWB0230 1/CEL A condition has occurred which warrants entry into AOI-34, "Immediate Boration". While attempting to borate using the immediate emergency boration flowpath, the aligned boric acid pump fails to start.
Which ONE of the following immediate Boration flowpaths should be used in this condition?
A. To the suction of the CCPs through Emergency Borate valve 1-FCV-62-138 after re-aligning the boric acid pump on tank recirc.
B. To the suction of the CCPs through Manual Boration valve 1-ISV-62-929 after re-aligning the boric acid pump on tank recirc.
CY To the suction of the CCPs through 1-FCV-62-135 and 136 using the RWST as the boration source.
D. To the discharge of the CCPs through 1-FCV-63-125 and 126 using the BIT as the boration source.
The correct answer is C Thursday, October 31, 2002 06:05:54PM 20
QUESTIONS REPORT for WBfindraft
- 21. 025A3.02 001iT2G11T2G1IICIAIBIWB023011C1KF0 Given the following:
- Large Break LOCA has occurred causing a Reactor Trip and Safety Injection
- OAC observes annunciator "Glycol Exp Tank Level HIIHI-Hi" is lit Which of the following describes the most likely reason the annunciator is illuminated?
A. Phase A closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the auxilary building side of the isolation valves relieve glycol into the glycol expansion tank.
BY Phase A closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tank.
C. Phase B closes the glycol containment isolation valves: glycol inside containment heats up and relief valves on the auxilary building side of the isolation valves relieve glycol into the glycol expansion tank.
D. Phase B closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tank.
Bank, lesson plan OT-SYSOGIA, drawing 1-47-814-2 In the event of a LOCA, the glycol heats up from approximately -5 F to the containment accident temperature and expands harmlessly into the expansion tank. The liquid trapped between a pair of isolation valves is relieved around the inner isolatin valve through a bypass line via a small check valve. The bypass line also contains test connections for periodic leak testing of the isolation valves and check valve.
- a. incorrect - no relief valves feedback to the expansion tank
- b. correct
- c. incorrect - no relief valves feedback to the expansion tank
- d. incorrect phase B does not close the these valves Thursday, October 31,2002 06:05:55PM 21
QUESTIONS REPORT for WBfindraft
- 22. 025AA2.07001/Tl G2lTlG2/MIDLOOP/ClA(3.2/3.2)/B/WB02301/C/KFO Given the following:
- RCS temperature is 118 F
- Reactor Vessel head is removed
- Reactor Upper lnternals are installed in the reactor vessel
- Refueling Level is 716.8 ft.
- RCS draining is in process at 10 gpm
- RHR pump A is running with indicated flow of 2200 gpm
- RHR pump A begins to exhibit indications of cavitation The cavitation and subsequent loss of RHR heat removal is occurring due to .......
A. draining with the upper internals in place, which reduced the RHR suction pressure.
B. steam binding of the RHR pump, caused by low recirculation flow.
C.Y air entrapment at the RHR suction inlet, caused by the high flow conditions.
D. draining with the upper internals in place, which reduced the RHR discharge pressure.
Ref. Bank - WB verification: Sol-74.01, AOI-14, GO.10
- a. incorrect, upper internal installation will not effect RHR suction pressure.
- b. incorrect, recirculation flow valve shuts at 14000gpm
- c. correct, air entrapment occurs at higher flow rates, normal midloop flow rate is 2000
- d. incorrect, upper internals installed will not effect RHR discharge pressure to this extent Thursday, October 31,200206:05:55 PM 22
QUESTIONS REPORT for WBfindraft
- 23. 02502.1.27001/T2GllT2G1lPURPOSE OF ICE CONDIM 2.812.9/MIWB020301/C/RLM Which ONE of the following is a purpose of the Ice Condenser System?
A. Helps limit peak clad temperature of the fuel by maintaining a minimum back pressure on the RCS during blowdown phase.
B. Uses sodium tetraborate to remove elemental hydrogen from the containment atmosphere.
Cy Absorbs (thermal) energy released during LOCA to control the peak pressure in containment.
D. Uses sodium hydroxide to remove elemental iodine from the containment atmosphere.
Ref WB lesson plan 3-OT-SYS061A, obj 2 Distractor analysis:
Thursday, October 31,2002 06:05:55PM 23
QUESTIONS REPORT for WBfindraft
- 24. 026A I .01 00 1/T2GZ/T2G I /DESIGNIClAIM/WB0230 1ICiRLM A large break LOCA has occurred
- Containment Pressure is 1.6 psig and rising
- One High Containment Pressure bistable has illuminated Which ONE of the following describes the correct operator response to prevent Containment Pressure from exceeding design limits?
A. Continue to closely monitor Containment Pressure and the High Containment Pressure bistable status.
B. Manually actuate HS-30-64A, Phase B Actuation Switch on M-6, and HS-30-68A, Phase B Actuation Switch on M-5, simultaneously.
C . Manually start and align Train A and Train B Containment Spray Systems.
D! Manually actuate HS-30-64A, Phase B Actuation Switch on M-6, and HS-30-64B, Phase B Actuation Switch on M-6, simultaneously.
WB bank-modified Thursday, October 31, 2002 06:05:56 PM 24
QUESTIONS REPORT for WBfindraft
- 25. 026AK3.03 001/T1G1/T1G1/AOI 15/C/A (4.0/4.2)/B/WB02301/C/RLM Given the following:
- Unit is at 100% power.
- "A" Train CCS Surge tank level is dropping due to a leak.
- US has entered AOI-15, Loss of Component Cooling Water.
Which ONE of the following describes required actions in the event " A Train CCS surge tank level cannot be maintained.
A. Transfer " A Train CCS suction to the "B" Train side of the surge tank, isolate non ESF header.
B. Shift Thermal Barrier Booster pump suction to " B train, shutdown affected " A Train components, start " B Train components as necessary.
CY Stop the thermal barrier booster pumps, trip the Reactor and stop all RCPs.
D. Shutdown running " A Train components and place in auto, start "B" Train components as necessary.
WB Bank Thursday, October 31, 2002 06:05:56PM 25
QUESTIONS REPORT for WBfindraft
- 26. 027AK3.03 001/T1G1iT1G2/PORV/C/A 3.7/4.1 /N/WBO20301lC/RLM Unit 1 is at 100% power.
Annunciator 89A, PZR PORV LINE TEMP HI, illuminates.
Both PORVs indicate closed.
Pressurizer pressure is normal.
In accordance with AOI-18, Malfunction of Pressurizer Pressure Control System, which ONE of the following is the correct action and reason?
A. Close the associated block valve because a vapor-space leak causes PZR level to increase.
B. Close both block valves because a vapor-space leak causes PZR level to increase.
CY Close the associated block valve because the PRT will rupture.
D. Close both block valves and remove power because the PRT will rupture Ref WE lesson plan 3-OT-AOI1800, obj. 1 & 5 WE procedures AOI-18, AOI-6, ARI 89-A Disaster analysis:
Answer A and B are incorrect because PZR level rise is only associated with large leaks that affect PZR pressure.
Answer C is correct because it follows the ARI guidance and small leaks can raise PRT pressure to the rupture disc setpoint.
Answer D is incorrect because power should not be removed.
Thursday, October 31,2002 06:05:56 PM 26
QUESTIONS REPORT for WBfindraft
- 27. 029EA 1.13 00 liT 1G2/T 1G 1 /TURBINE TRIP/M 4.1/3.9/B/WB02030 l/C/RLM Which ONE of the following is the NEXT action the operator is required to take if the main turbine does NOT trip automatically and CANNOT be tripped from the MCR: per FR-S.l, "RESPONSE TO NUCLEAR POWER GENERATION/ATWS?
A. Place both EHC pumps control switches in P-T-L.
B. Trip the turbine locally at the front standard.
C y Manually RUNBACK the turbine.
D. Shut the MSIV's.
WB lesson plan 3-OT-FRS-0001, Obj. 3 WB exam bank Distractor analysis:
A is incorrect because it is a followup action later in the procedure, step 9 RNO.
6 is incorrect because it is a local action if MCR actions fail, step 9 RNO.
C is correct per RNO step 2 D is also in RNO step 2, but only occurs if runback doesn't work.
Thursday, October 31,200206:05:57 PM 27
QUESTIONS REPORT for WBfindraft
- 28. 029K1.02 00 1/T2G2/T2G2/RAD MONITOEUM 3.3/3.6/N/WB020301/C/RLM Which ONE of the following describes the sample path of RE-90-130, Cntmt Purge Exhaust, and effect of the alarm exceeding the alarm setpoint?
A. RE-90-130 samples the Cntmt Purge Exhaust discharge and initiates a Containment Purge trip upon alarm.
B.Y RE-90-130 samples the Cntmt Purge Exhaust suction and initiates a Containment Vent Isolation upon alarm.
C. RE-90-130 samples the Cntmt Purge Exhaust discharge and initiates a Containment Vent Isolation upon alarm.
D. RE-90-130 samples the Cntmt Purge Exhaust suction and initiates a Containment Purge trip upon alarm.
Ref: WB Lesson Plan 3-OT-SYS030C, obj. 10 WB Lesson Plan 3-OT-SYS090A, pp. 63 SO1 88.1, Checklist #3 Dwg. 1-47W866-1 Thursday, October 31, 2002 06:05:57PM 28
QUESTIONS REPORT for WBfindraft
- 29. 032AK 1.O 1 00 1/T1G2IT 1GZPOWER FAILUREICIAIMIWB0230l/C/KFO Given the following conditions:
- Reactor Startup in progress
- Shutdown Banks withdrawn
- Control Bank withdrawal is immenent
- SRM N132 indicates approximately 1000 cps
- SRM N131 is in bypass Which ONE of the following will occur if the control power fuse for SRM N131 blows?
A. Lose indication for SRM N131 on Main Control Board and NIS cabinets B. Both SRM drawers deenergizes and "non-operate" alarm acuates CY Reactor Trips D. Rod withdrawal is blocked Modified from WB bank - rewrote question stem and changed distractor. Validated in Lesson Plan SYS092A
- a. incorrect-not all indicatipon lost since instrument power is available
- b. incorrect-SRM N132 unaffected by loss of control power to SRM N131
- c. correct- loss of control power deenergizes bistables and initiates trip signal (112 logic)
- d. incorrect - Source range low does not initiate rod stop Thursday, October 31, 2002 06:05:58 PM 29
QUESTIONS REPORT for WBfindraft 30.034K4.01001/T2G3/T2GZ/LOSSOF AIWM (2.6/3.4)/BiWB02301/C/KFO Which one of the following describes a feature of the Refueling Machine designed to prevent the accidental release of a fuel assembly?
A. The Gripper is mechanically engaged and disengaged by a remote operating handle on the bridge and requires no power or air to operate.
BY The gripper requires air to disengage, however, a mechanical latch prevents gripper release under load even if air is supplied.
C. The gripper disengages upon loss of air, however, a mechanical latch prevents gripper release under load even if air is removed.
D. When the gripper is engaged, operators mechanically lock gripper in place with extension shaft which must be unlocked before the gripper can release.
Ref: lesson 3-OT-SYS079 (LO11)
- a. incorrect - air required to disengage
- b. correct - mechanical latch on gripper works under load
- c. incorrect - engages on loss of air
- d. incorrect - no operator action required for gripper mechanical latch to operate Thursday, October 31,2002 06:05:58PM 30
QUESTIONS REPORT for WBfindraft 3 1. 035K1.09 OOlIT2G2IT2G2ITRANSIENT RESPONSE/C/A 3.8/4.O/B/WB020301/C/EL/RLM Given the following plant conditions:
- The reactor is operating at 50% power.
- Rod control is in MANUAL.
- Turbine control is in IMP-IN.
- #3 SIG PORV fails OPEN.
Which ONE of the following describes the resulting steady-state conditions?
(Assume no reactor trip or operator action and turbine power remains constant)
A l Final Tavg < initial Tavg and final power > initial power B. Final Tavg < initial Tavg and final power = initial power.
C. Final Tavg = initial Tavg and final power > initial power.
D. Final Tavg = initial Tavg and final power = initial power.
Reference:
TAAOI 1, General theory section Distractor analysis:
A is correct steam loss through PORV causes Tav decrease which adds positive reactivitiy which causes power to rise. Tav will remain less than initial Tav because some of the reactivity is used to overcome power defect associated with power rise.
B, C, and D are incorrect because they conflict with the above correct answer.
Note: Since IMP-IN is given, do we need to tell them that turbine power remains constant?
Thursday, October 31,2002 06:05:58PM 31
QUESTIONS REPORT for WBfindraft
- 32. 037AK3.07 001iT1G2/T1G2/TUBE LEAK/M 4.2/4.4/B/WB020301/C/RLM Given the following:
- A SG tube leak of approximately 30 gpm has been identified on SG #3.
- The operating crew has entered AOI-33, Steam Generator Tube Leak.
- Operators have completed Step 21 of the AOI and have isolated feed flow to SG #3 after verifying level greater than 10%.
Which ONE of the following is a basis for ensuring the affected SG level greater than IO%?
A. To ensure that the pressure and temperature limits of the SG shell are maintained.
BY To prevent the RCS cooldown from causing depressurization of the affected SG.
C. To prevent SG overfill.
D. To prevent thermal shock to the tubes during RCS cooldown.
Ref: WB Lesson Plan 3-OT-A013300, obj. 8 A is incorrect in that these limits apply to CSD conditions B is correct because the insulating layer of water above the tubesheet helps trap pressure in the S/G and minimize tube d/p during cooldown.
C is incorrect because level control is not an issue.
D is incorrect because there is no sudden introduction of cold water after the level is attained.
Thursday, October 31, 2002 06:05:59PM 32
QUESTIONS REPORT for WBfindraft
- 33. 039A1.03 001lT2G2/T2G2/MS WARMUPICIA 2.6/2.7lBIWB020301/C/ELlRLM Given the following plant conditions:
- Startup in progress.
- Operators are warming the main steam lines using the MSlV bypasses.
- The OAC observes that the RCS has cooled down 108°F in the past hour.
- The CRO observes that the main steam lines have heated up 102°F in the past hour.
Which ONE of the following indicates the actions that should be taken by the operators and why?
A l Close the MSlV bypass valves: RCS cooldown limit was exceeded.
B. Close the MSlV bypass valves: main steam line heat-up limit was exceeded C. Close the MSlV bypass valves; both RCS and main steam line limits were exceeded.
D. Leave MSlV bypass valves open; NO RCS or main steam line limits were exceeded.
Ref: WB Exam Bank WB Lesson Plan 3-OT-SYSOOIA, obj 24
- a. Correct - RCS cooldown limit of 100"Flhr was exceeded; main steam line limit of 200"F/hr was NOT exceeded. Closing the bypass valves would terminate the cooldown
- b. Incorrect - main steam line limit was not exceeded. Examinee could confuse the RCS and main steam line limits.
- c. Incorrect - only the RCS cooldown limit was exceeded. Examinee may believe the limits were the same. Closing the bypass valve would terminate the cooldown.
- d. Incorrect - examinee could confuse the limits and believe that neither limit was exceeded, however the RCS cooldown limit was exceeded and closing the bypass valve would terminate the cooldown.
Thursday, October 31,200206:05:59PM 33
QUESTIONS REPORT for WBfindraft
- 34. 040AG2.4.6 001/TlGl/TlGl//C/A (4.0/4.3)/B/WBO2301/C/EL Given the following plant conditions:
- Unit was at 100% power.
- A main steam line break occurred in the Turbine Building.
- Operators were unable to close the MSlVs and transitioned to ECA-2.1, Uncontrolled Depressurizationof All Steam Generators.
- SI termination steps are in progress.
- Loop 3 MSlV is closed locally.
- The CRO observes the #3 SG pressure rising slowly.
Which ONE of the following actions should be performed?
A. Transition to E-2, Faulted SG Isolation.
B. Transition to ES-1. I , SI Termination.
C. Remain in ECA-2.1 until RHR is in service.
D. Remain in ECA-2.1 until SI is terminated.
The correct answer is D Thursday, October 31,2002 06:05:59PM 34
QUESTIONS REPORT for WBfindraft 35.041K3.04001/T2G3/T2G3/STEAM DUMP RX POWEFUC/A3.5/3.4/BANB020301/C/ELIRLM Given the following conditions:
- Unit at 100% power, EOL conditions.
- Turbine operating in IMP OUT.
- A steam dump valve inadvertently comes full open.
- All other control systems normal.
Which ONE of the following correctly describes the plant conditions, when plant stabilizes, and assuming NO operator action?
A. Megawatts electrical same as initial; reactor power rises.
B. Megawatts electrical same as initial: reactor power drops.
C:' Megawatts electrical drops; reactor power rises.
D. Megawatts electrical drops; reactor power drops.
Ref WB Exam Bank WB Lesson Plan 3-OT-SYSOOIB, obj 27 WB Lesson Plan 3-OT-SYSOOIB, pp. 24 Thursday, October 31, 2002 06:06:00PM 35
QUESTIONS REPORT for WBfindraft 36.045A3.05 OOl/TZG3iT2G3/GOVERNOR VALVE/C/A3.5/3.6/B/WBOZO3Ol/C/EL/RLM Given the following plant conditions:
- Plant operating at 100% power.
-- All systems aligned normal.
Turbine EHC control is in IMP OUT.
Which ONE of the following describes turbine governor valve operation while in IMP OUT mode?
A. Governor valve position is adjusted to maintain generator load constant and will NOT respond to changes in system frequency.
B. Governor valve position is adjusted to maintain generator load constant and will respond to changes in system frequency.
C. Maintains governor valves at a set reference position and will NOT respond to changes in system frequency.
DY Maintains governor valves at a set reference position but will respond to changes in system frequency.
Ref: WB Exam Bank WB Lesson Plan OT SYS047A Obj. 2 Lesson plan pp. 12 and 18 Info on pp. 12 and 18 seem to conflict, need to follow up w/ site.
- a. Incorrect - in the IMP OUT mode governor valves adjust to maintain load and system frequency.
- b. Incorrect - in the IMP OUT mode governor valves adjust to maintain load and system frequency.
- c. Incorrect - governor valves are set at a reference set in by the operator, but WILL change in response to system frequency changes
- d. Correct - governor valves are set at a reference set in by the operator and WILL change in response to system frequency changes.
Thursday, October 31,2002 06:06:00 PM 36
QUESTIONS REPORT for WBfindraft 3 7. 054AG2.4.48 00 1fT 1G2/T 1 G2lSG LEVELICIA 3.513.8/N/WB020301ICIRLM Unit 1 is at 100% power.
Annunciator 63-F, SG LEVEL DEVIATION, alarms and the operator notices S/G # I level rising along with MFP speed and the remaining SIG levels constant.
Which ONE of the follow describes the (1) cause, (2) required action and (3) consequence of no operator action?
A. (1) #I S/G FRV is opening, (2) return # I S/G level to program, (3) Auto Turbine Runback initiated BY (1) # I S/G FRV is opening, (2) return # I S/G level to program, (3) Feedwater Isolation initiated C. (1) MFP master contoller failing high, (2) control MFP speed using manual, (3) Auto Turbine Trip initiated D. (1) MFP master contoller failing high, (2) manually trip turbine, (3) Feedwater Isolation initiated Ref WB 3-AOI-1600 Note: electronic copy of AOI 16 corrupt Distractor analysis:
A is incorrect because the consequence is a P-14, Hi-Hi SG level which initaties a FW isolation.
B is correct because only one SG is rising, hence a FRV is the cause, action is from AOI-16 for FRV failure and FW isolation occurs with no operator action at P-14.
C is incorrect because a problem with the MFP controller would affect all SG's the same.
D is incorrect same as C.
rhursday, October 31,2002 06:06:00 PM 37
QUESTIONS REPORT for WBfindraft 38.055EK3.02001/T1G 1/T1 GI//M (4.3/4.6)/B/WB02301/C/EL/KFO Which ONE of the following is a purpose for depressurizing all intact SGs to 300 psig during the performance of ECA-0.0, "Loss of Shutdown Power"?
A. Reduces DP across SG U-tubes to minimize possibility of tube rupture.
BY Reduces DP across RCP seals to minimize leakage and loss of RCS inventory.
C . Maximizes Natural Circulation flow before Reflux cooling begins as the RCS becomes saturated.
D. Maximizes Natural Circulation flow to allow reactor vessel head to cool since CRDM are unavailable.
WB bank, validated with ECA-0.0 Thursday, October 31, 2002 06:06:01 PM 38
QUESTIONS REPORT for WBfindraft
- 39. 055K3.01 O O ~ I T ~ G ~ / T ~ G ~ N A CPUMPICIA UUM 2.5/2.7/B/WB020301/C/RLM Given the following conditions:
- Reactor power is steady-state at 100%.
- Rod control is in automatic.
- Condenser Vacuum Pumps 1A and 1B are running with I C pump out of service for maintenance.
Which ONE of the following conditions could result if NO operator action is taken in response to a COND VACUUM PUMP 1B SEAL WTR PRESS LOW alarm?
A. Rising megawatt output and rising steam seal header pressure.
B. Rising megawatt output and rising condenser hotwell level.
C. Dropping megawatt output and dropping condensate temperature.
DI Dropping megawatt output and rising condensate temperature.
WB Lesson plan 3-OT-SYS1100, obj 4 Distractor analysis:
Degraded vacuum causes megawatt output to decrease due to reduce delta H. Therefore, A and B are incorrect.
Condenser is a saturated system, so higher Psat means higher Tsat. Therefore D is correct and C is incorrect.
Thursday, October 31, 2002 06:06:01PM 39
QUESTIONS REPORT for WBfindraft 40.056K1.03 001/T2Gl/T2Gl/FEED PUMP TRIPICIA 2.6/2.6/N/WB020301/C/RLM Unit 1 is at 72% power. A control problem causes 2-FCV-210, Condensate Inlet to 1A MFPT Condenser to close.
Which ONE of the following describes the effect on continued plant operation?
A. 1A MFPT rolls to idle, the Standby MFP starts and Rx power can remain 72%
B: 1A MFPT trips, the Standby MFP starts and Rx power can remain 72%.
C. 1A MFPT trips, the Standby MFP does not start and Rx power must be reduced.
D. 1A MFPT rolls to idle, the Standby MFP does not start and Rx power must be reduced.
Ref: 3-OT-SYS002A, obj. 15 3-OT-SYS003A, obj. 5 & 7 Distractor analysis:
A and D are incorrect, because the 1A MFP trips on low condenser vacuum C is incorrect because the standby feed pump auto starts 8 is correct, because the standby feed pump starts and is able to carry -15% turbine power and the 1B MFP can carry 67%, the sum of which is above 72%.
Thursday, October 31,2002 06:06:02 PM 40
QUESTIONS REPORT for WBfindraft
- 41. 059AA1.01 001/T1G2/TlGl/RAD FLUID LEAKAGEIM 3.5/3.5iN/WB020301/C/RLM
-Unit 1 is operating at 50% power
-Annunciator 178-A, SG BLDN 1-RM-120/121 LIQ RAD HI alarms Which ONE of the following correctly describes plant response and the actions of the control room operators?
A. No automatic action and operators verify alarm validity.
B I Operators verify SG Blowdown is isolated to Cooling Tower Blowdown and aligned to Condensate Demin.
C. Operators verify Auxiliary Bldg Rad Waste discharge header is isolated from the blowdown line.
D. Operators verify Cooling Tower blowdown flow is bypassed to the 35 acre pond.
Ref: WB Lesson Plan 3-OT-A0131000, obj. 2 & 3 ARI 178-A Distractor analysis:
A is incorrect because RM 120/121 have auto actions B is correct base on ARI 178-A C is incorrect the Aux Bldg in not involved in SGBD stream D is incorrect because this action would not prevent an offsite release.
Thursday, October 31, 2002 06:06:02 PM 41
QUESTIONS REPORT for WBfindraft
- 42. 059K6.09 001iT2GlIT2G IISPEED CONTROLICIA 2.4/2.6/N/WB020301/C/RLM Unit 1 is at 60% power with both 1A and 1B MFP's operating in AUTO.
PT-1-33, Steam Header Pressure, output begins to slowly drift low.
Assume no operator action.
Which ONE of the following describes the effect on the Main Feed Water System?
A. Feed Water Reg valves begin to close and then both MFPs discharge pressure begins to increase.
B. Both MFP's discharge pressure begins to increase and all then Feed Water Reg valves begin to open.
CY Both MFPs discharge pressure begins to decrease and all then Feed Water Reg valves begin to open.
D. Feed Water Reg valves begin to close and then both MFP's discharge pressure begins to decrease.
Ref WB Lesson Plan 3-OT-SYS0003A, obj. 6 WB Dwg. 47W611-03-02 Distractor analysis:
C is correct because input from d/p program remains constant because steam flow remains contant. However, PT-1-33 failing low, causes the dlp actual (as sensed) to increase above program. This in turn causes the speed summer to decrease its output to the speed control station which will reduce feedpump speed and it's discharge pressure. Flow rate will decrease and the FRV's will open to increase flow to the S/G's.
All other answer's are incorrect because they are variations of the answer with one parameter going in the wrong direction.
Thursday, October 31, 2002 06:06:02PM 42
QUESTIONS REPORT for WBfindraft
- 43. 061A 1.04 00 l/T2Gl/T2G l/CSTICIA/MIWBO2301/C/KFO Which ONE of the following describes the base assumptions for minimum CST volume for a Loss of Offsite Power?
A. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in Mode 3 followed by 50 "F/hr cooldown rate to Mode 5.
B. Immediately cooldown at 50 "Flhr cooldown rate to Mode 4 C! 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in Mode 3 followed by a 50 "F/hr cooldown rate to Mode 4.
D. Immediately cooldown at 50 "Flhr cooldown rate to Mode 5.
Modified from Byron validated from WB AFW System description N3-38-4002
- a. incorrect - capacity is for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> hold then cool to mode 4
- b. incorrect - capacity for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and then cool to mode 4
- c. correct - stand pipe in CST ensures 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> hold and then 50 F/hr cooldown to mode 4
- d. incorrect - capacity to hold for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with 50 Flhr cooldown to mode 4 Thursday, October 31,2002 06:06:03 PM 43
QUESTIONS REPORT for WBfindraft
- 44. 06 1AA 1.O 1 00 1/T1G2/T 1G2//M/N/WB0230 1 /C/KFO Which ONE of the following area radiation monitors intiate a Containment Ventillation Isolation?
A. Waste Disposal System Gas Effluent Monitor, 0-RM-90-118 B.' Containment Purge Rad Monitor, 1RM-90-130 C. Fuel Pool Area Monitor, 0-RM-90-102 D. Personnel Access Area Monitor, RM-90-2 New - Lesson plan SYS9OA -
- a. incorrect - hi rad closes the vent header isol
- b. correct
- c. incorrect - isolates the aux building, does not generate an AB1
- d. incorrect - no auto actions Thursday, October 31, 2002 06:06:03PM 44
QUESTIONS REPORT for WBfindraft 45.062A3.05 0011T2G2lT2G21LOSP LOOPICIA 3.5/3.6/BIWB020301lClRLM Given that the following occurred in sequence:
- A small break LOCA occurred which resulted in a reactor trip and SI.
- The SI signal was reset during the performance of E-I, "Loss of Reactor or Secondary Coolant."
- A loss of offsite power (LOOP) occurred and the diesel generators loaded as designed.
Assuming no operator actions, which ONE of the following would be the status of the loads on the 6.9kV SD boards?
A. All equipment powered from the SD boards with the control board switch in automatic will be restarted.
B. No 6.9kV SD board loads are automatically restarted.
C? Equipment normally started during a LOSP will be automatically restarted; SI and RHR pumps remain OFF.
D. All equipment that was operating prior to the LOSP will be automatically restarted; All running ESF equipment will be reenergized
Reference:
WB Exam Bank (inadequate info to verify, missing lesson plans on EDG loading.
Thursday, October 31, 2002 06:06:03 PM 45
QUESTIONS REPORT for WBfindraft
- 46. 062AG2.4.24 00 UT1 GliTl G1/A4/BiWB02301/CIELIO Which one of the following correctly identifies the emergency cooling water supply to the control and station service air compressors, per AOI-13 "Loss of ERCW", if normal ERCW supply is lost?
A.
Raw Cooling Water header B." Raw Service Water header C. Unit 1 Primary Water header D. Demin Water header Ref - AOI-13, 47w850-1,47w845-5
- a. incorrect - RCW does not support the compressers
- c. incorrect - no ERCW connection to support compressers
- d. incorrect -
Thursday, October 31,200206:06:04PM 46
QUESTIONS REPORT for WBfindraft
- 41. 063K3.02 00 lIT2G2iT2G IICONTROL POWEWCIA 3.5/3.7i/CVB020301lClRLM Unit 1 was at 100% power DGIA was running paralled to the 6.9kV Shutdown Board for surveillance.
In additon to the expected post trip annuciators, the operator notes annunciators:
17-A 125 DC VITAL CHGFVBATT I ABNORMAL 17-8 125 DC VITAL BATT BD I ABNORMAL CKTS ISOLATED Which ONE of the following describes the response to this event by DGIA?
A. DGIA trips and its output breaker opens B. DGIA continues to run and its output breaker opens C . DGIA trips and its output breaker remains closed DY DGIA continues to run and its output breaker remains closed Ref: WB lesson plan 3-OT-A012100, obj. 1 & 2 3-OT-SYS057P, obj. 8 WB Dwgs 1-45W724-1 1-45W727 1-45W760-82-2 1-45W760-211-4 Distractor analysis:
A is incorrect because the DG can run using its own DC control power, but the output breaker has not control power to trip.
B is incorrect because the output breaker has no control power to trip.
C is incorrect because the DG does no trip D is correct because the DG has its own control power and the output breaker remains closed due to no control power.
Thursday, October 31,2002 06:06:04 PM 47
QUESTIONS REPORT for WBfindraft
- 48. 064K2.03 001/TZG2iT2GZ/DIGCONTROL POWEWM 3.2/3.6/NMrB02030l/C/RLM Unit 1 is at 100% power All Diesel Generators are in standby Annunciator 281-A, DG CONTROL POWER FAILURE for DGIA Which ONE of the following describes the status of the Diesel Generators AFTER the annunciator alarms?
A. DGIA starts and is operable.
B! DGIA does not start and is inoperable.
C. All four diesel generators start and are operable.
D. All four diesel generators do not start and are inoperable.
Ref: WB lesson plan 3-OT-SYS082B, obj. 10 ARI 281-A Dwg 1-45W727 1-45W760-82-2 1-45W760-82-4 1-45W760-82-6 Distractor analysis:
A is incorrect because the starting air solenoids need power from the Diesel 125V DC Distribution Panel 1-DPL-82-A-A which is deenergized as evidenced by the annunciator 281-A.
B is correct because the starting air solenoids have no power and cannot respond to an auto start signal C and D are incorrect because they continue to have control power and all 125V vital battery boards are still energized.
Thursday, October 31, 2002 06:06:04 PM 48
QUESTIONS REPORT for WBfindraft
- 49. 065AA1.01 001/T1G3/T1G2//C/A/N/WB023Ol/C/RLM Unit 1 is at 100% power
- Annuciator 42D, C&SS AIR COMPR SEQUENCER UNDERVOLTAGE
- Control Air pressure is slowly decreasing Which ONE of the following describes actions for locally controlling air pressure?
A. Take manual control of the Foxboro 43AP pneumatic controller B. Shift AC control power C. Start and stop Control Air Compressors DY Take manual control at the local control station using the solenoid manual valve New - ref: Watts Bar ARI 42-E and lesson plan 3-OT-SYS032A, obj 11 Distractor analysis:
A incorrect because controller has no power B incorrect because control power is DC, but shifting control power takes precedence over taking manual control of unloader C is incorrect due to no procedural guidance and undesirable from equipment standpoint D is correct IAW ARI Thursday, October 31, 2002 06:06:05 PM 49
QUESTIONS REPORT for WBfindraft
- 50. 067AK1.02 00 IM'I GI M'1Gl/FIRE FIGHTING/M (3.1/3.9)/M/WB02301/C/EL Which one of the following is the most effective method of fire fighting in the 5th DG Oil Pump Room?
A. Auto actuation of sprinkler system B. Auto actuation of fog system CY Auto actuation of foam system D. Auto actuation of C 0 2 system REF: Modified from Watts Bar Exam Bank SYS026A.21 Thursday, October 31,2002 06:06:05 PM 50
QUESTIONS REPORT for WBfindraft 5 1.068AK3.18 001/TIG1/TlGI/EVACUATION/M/N/WB02301/C/KFO Evacuation of the Control Room is required due to a control room fire. The actions of AOI-30.2, "Main Control Room Inaccessibility", prior to evacuating the control room include which of the following?
A. Tripping the feedwater pumps B:' Deenergizing the RCP start busses and Electrical Control Board C . Initiating main steam isolation D. Tripping unrequired diesel generators Ref AOI-30.2 Fire Safe Shutdown, appendix C steps 1 - 8,
- a. incorrect, feedwater pump status is not addressed prior to evacuation
- c. incorrect, ensure the MSlVs are closed but does not direst initiating a main steam isolation signal
- d. incorrect, addresses ensuring the 6.9 bus energized but does not address tripping any unnecessary DGs Thursday, October 31,2002 06:06:05PM 51
QUESTIONS REPORT for WBfindraft
- 52. 068K1.07 001/T2GllT2GllRAD WASTEIM 2.712.9/NIWB020301lCRLM Which one of the following describe how lncore lntrumentation Seal Table leakage enters the Liquid Radwaste System?
A. Drains to the Reactor Coolant Drain Tank and pumped to the Tritiated Drain Collector Tank.
BY Drains to the Reactor Building Floor and Equipment Drain Pocket Sump and pumps to the Reactor Building Floor and pumped via Reactor Building Floor and Equipment Drain Sump to the Tritiated Drain Collector Tank.
C. Drains to the Containment Pit Sump and pumped via the Reactor Building Floor and Equipment Drain Sump to the Floor Drain Collector Tank.
D. Drains to the Reactor Building Floor and Equipment Drain Sump and pumped to the Floor Drain Collector Tank.
Ref: WB lesson plan 3-OT-SYS077A, obj.
Dwg. 1-47wa51-1 Distractor analysis:
See attached drawing Note: From the drawing, it appears that the Reactor Building Floor and Equipment Drain Pocket Sump has its own pumps, but can overflow into the Reactor Building Floor and Equipment Drain Sump. If this becomes and issue, we can substitute the Passive Sump for distractor D.
Thursday, October 31,2002 06:06:06 PM 52
QUESTIONS REPORT for WBfindraft
- 53. 069AK2.03 OOl/TlGliTlGl/CTMT INTEGRITY/C/A 2.8/2.9/N/WB020301/C/RLM Unit 1 is at 100% power.
Annuciator 158-A, UPR CNTMT AIRLOCK INNEWOUTER alarmed for no apparent reason on the previous shift. Maintenance personnel have been dispatched to investigate the alarm.
They report that they have opened the outer door and found the inner door ajar.
Which ONE of the following describes the correct actions required by AOI 12, "Loss of Containment Integrity?"
A. Verify the outer door closed within one hour and restore the air lock to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Repair the inner door within one hour and lock the outer door within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.' Close the outer door within one hour and lock the outer door within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Commence plant shutdown within one hour and be in Mode 5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Ref WB 3-OT-A011200 , obj. 4 WB 3-OT-AOI1200, pp. 5 WB Tech Specs Distractor analysis:
A is incorrect because the air lock is not inoperable because the outer door is operable. These actions are for an inoperable air lock.
B is incorrect because there is no requirement to repair the inner door within one hour.
C is correct per Tech Specs 6.2 condition A.
D is incorrect because there is no requirement per AOI 12 to commence shutdown within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Thursday, October 31,2002 06:06:06 PM 53
QUESTIONS REPORT for WBfindraft
- 54. 071K3.05 001/T2Gl/T2Gl/ARM PRM/C/A 3.2/3.2/M/WB020301/C/RLM Given the following plant conditions:
- A Gas Decay Tank is being released to the atmosphere using the normal release path.
- The tank being released has HIGH gaseous activity.
- PCV-77-117, Plant Vent Pressure Control Valve fails toward the open position.
Which ONE of the following radiation monitor pairs will alarm to alert the operators and secure the release, respectively?
A. Shield Building Ventilation Monitor IRE-90-4001and Aux Building Vent Monitor
[O-RE-90-101].
B. Auxiliary Building Ventilation Monitor [RE-90-101A] and Shield Building Ventilation Monitor
[RE-90-400].
CY Shield Building Ventilation Monitor [RE-90-4001 and WDS Gas Effluent Monitor
[O-RE-gO-I 181.
D. Auxiliary Building Ventilation Monitor [RE-90-1OIA] and WDS Gas Effluent Monitor [O-RE-90-118].
Ref: WB lesson plan 3-OT-SYS077B, obj. 9 and 3-OT-SYS090A, obj. 7 r analysis Distract0 A is incorrect because the AB monitor is unrelated to WDS release B is incorrect same as A C is correct because the Shield Bldg monitor will upscale and the WDS effluent monitor will trip FCV-77-119 shut and secure release.
D is incorect same as B Thursday, October 31,2002 06:06:06PM 54
QUESTIONS REPORT for WBfindraft
- 55. 07262.4.31001/T2Gl/T2GI/AR1RESPONSEIM 3.3/3.4/N/WB020301/C/RLM
-Unit 1 is in Mode 6
-Fuel Movement is in progress
-Annuciator 186-B MCR AREA 0-RM-135 RAD HI alarms Which ONE of the following correctly describes the actions of the control room operators?
A. Verify Control Building Isolation occurs.
B. Notify fuel handling crew to stop all fuel movement.
CY Notify RADCON to investigate the alarm D. Verify emergency control building air cleanup and pressurizing fans RUNNING.
Ref WB Lesson Plan 3-OT-O9OA, obj. 9 ARI 186-8 Distractor analysis:
A and D are incorrect because they are auto actions which occur if the MCR Intake rad monitors 125 or 126 alarm B is incorrect because there would be no relation between Control Room area rad monitor and refueling operations (and no other rad monitor alarms are in)
C is correct per ARI guidance Thursday, October 31,2002 06:06:07 PM 55
QUESTIONS REPORT for WBfindraft
- 56. 075A4.01 001/T2G2/T2G2//M (3.2/3.2)/B/WB023Ol/C/KFO Given the following:
- Reactor trip and Safety Injection occurred while the plant was operating at 100% power
- Four ERCW pumps were running in their normal alignment before the Si occurred.
Which of the following identifies ERCW pump status after the SI and the effect it has on the Condenser Circulating Water (CCW) system make-up?
A. Four ERCW pumps running; CCW make-up is provided only from ERCW since RCW bypass strainer is isolated.
B. Four ERCW pumps running; CCW make-up is provided only from ERCW since RCW bypass strainer is routed through the overflow structure.
CY Four ERCW pumps running; CCW make-up is provided from both ERCW and RCW.
D. Four ERCW pumps running; CCW make-up is not required since the Unit is tripped.
has a bypass that ensures continuous make-up to CCWREF: lesson plans 3-OT-SYS027A (LO2) and 067A (LO13)
- a. incorrect - RCW has a bypass that ensures continuous make-up to CCW
- b. incorrect - RCW has a bypass that ensures continuous make-upto CCW
- c. correct - 2 pumps per train start on SI and RCW has a bypass that ensures continuous make-up to CCW
QUESTIONS REPORT for WBfindraft
- 57. 076K2.08 OOl/TZG3/TZG3/POWER SUPPLY/M3.1/3.3/N/WB020301/C/RLM Which ONE of the following describes the power supply for 1-FCV-67-91B, Lower Containment I C Cooler Supply, and the normal feeder to that power supply?
A l 480 V Reactor MOV Board 182-8 B. 480 V Shutdown Board 182-8 C. 480 V Reactor MOV Board 2B1-B D. 480 V Shutdown Board 1B1-B Ref: WB Lesson Plan 3-OT-SYS067A, no specific learning objective Dwgs: 1-45W760-67-5 1-45W751-11 1-45w749-4 1-45-W724-2 Distractor Analysis:
A is correct based on attached dwg's.
B and D are incorrect because the 480 V shutdown board does not directly feed any MOV's C is incorrect because they have unit 2 designators.
Thursday, October 31, 2002 06:06:08PM 57
QUESTIONS REPORT for WBfindraft
- 58. 079K4.0I 00 I/T2GZ/TZGZ/SAS CROSS CONNECTM 2.9/3.2/B/WB020301/C/EURLM If Station Control and Service Air System air pressure is dropping, the Service Air System automatically isolates from the Control Air System when pressure drops below which ONE of the following?
A! 80 psig.
B. 79.5 psig.
C. 78 psig.
D. 70 psig.
Ref WB Exam Bank WB Lesson Plan 3-OT-SYS032A, obj. 16 Distractor analysis:
A is correct, see lesson plan pp. 33 (attached)
B is incorrect, corresponds to isolation setpoint of Aux Air C is incorrect, doesn't correspond to any auto event D is incorrect, corresponds to essential and non-essential air to the Rx Bldg isolatation Thursday, October 31, 2002 06:06:08 PM 58
QUESTIONS REPORT for WBfindraft
- 59. G2.1.2 001/T3/T3/PROCEDURE COMPLIANCEiM 3.0/4.0iIWB02030 l/C/RLM Operators may take reasonable action that departs from a license condition or Technical Specifications under which ONE of the following circumstances?
A? In the event of a national security emergency and no action consistent with the license condition or TS that can meet the national security objectives is immediately apparent and the action is immediately needed to implement national security objectives as designated by the national command authority through the NRC.
B. In an emergency when this action is immediately needed to protect the public health and safety and no action consistent with the license conditions and TS that can provide adequate or equivalent protection is immediately apparent.
C. In the event of a national security emergency and no action consistent with the license condition or TS that can meet the national security objectives is immediately apparent and such action is approved by a licensed SRO.
D. In an emergency when this action is immediately needed to protect risk significant equipment and no action consistent with the license conditions and TS that can provide adequate or equivalent protection is immediately apparent.
Ref: WB procedure OPDP-1, sec. 3.4.3, TS compliance A is correct, see attached B is incorrect, lacks SRO approval statement C is incorrect, lacks national command authority requirement D is incorrect, refers to risk significant equipment Thursday, October 31,200206:06:08 PM 59
QUESTIONS REPORT for WBfindraft 60.G2.1.3001/T3/T3/SHIFTTURNOVEWM 3.7/3.8/B/WB020301/C/RLM A Unit 1 UO is preparing to relieve the on-shift UO for a lunch break during a normal shift.
Which one of the following describes their required miniumu actions when this occurs?
A. A review of the Operating Log since last held shift or 3 days, whichever is less, Standing Orders, LCO(s) in actions B. A review of the Rounds sheetslAbnormal readings , Standing Orders, any SI/Test in progresslplanned CY Abnormal or unusual plant conditions existing, any evolutions in progress, actions anticipated D. Radiological changes in plant during shift, a walkdown of the MCR control boards, SI/Test in progresslplanned Ref: Surry exam 2002 OPDP-1, pp. 24 and Shift Turnover Checklist A, B, and D are items from the Shift Turnover Checklist which is NOT required for a temporary relief per page 24 of OPDP-1, pp.24 and are therefore incorrect.
C are the items listed on pp. 24 as required for temporary turnover.
Thursday, October 31,200206:06:09 PM 60
QUESTIONS REPORT for WBfindraft 61.(32.1.32001/T3/T3/COMPONENT COOLING WA/M 3.4/3.8/N/WB020301/C/RLM Flowrates in the Component Cooling Water System is limited to 12000 gpm shell side flow.
Which ONE of the following explains the basis for this precaution?
A. It limits tube dlp and Heat Exchanger loading.
B. It limits pump runout and tube vibration.
CY It limits tube vibration and Heat Exchanger loading.
D. It limits pump runout and tube erosion Ref: WB lesson plan 3-OT-SYS070A, obj. 1 Sol-70.01, section 3, P&Ls Distractor analysis:
C is correct, see P&L A,B, and D are incorrect due to either erosion or pump runout which are not mentioned but is plausible at high flowrates.
Thursday, October 31,200206:06:09 PM 61
QUESTIONS REPORT for WBfindraft
- 62. G2.2.12 001/T3/T3lINVENTORY BALANCEICIA 3.013.4/NiWB0203011C/RLM Unit 1 is at 100%
SI-68-32, Reactor Coolant System Water Inventory Balance is in progress 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since commencing data collection Final readings from the RCSWIB indicate that the total RCS leakage rate is -0.08 gpm Which ONE of the following describes the correct action to be taken?
A. Sign the surviellance as satisfactory BY Continue data collection for an additional hour C. Void the surveillance and perform at a later time D. Investigate to determine the source of inleakage to the RCS Ref: WB procedure SI-68-32, pp. 16 & 17 A is incorrect because data must be collected for at least an additional hour before the surveillance can be termed complete B is correct, see SI-68-32, pp. 16 & 17 C is incorrect because it is contrary to procedure guidance D is incorrect unless the leakage continues to be negative by more than -0.10 gpm after the second data collection Thursday, October 31,2002 06:06:09 PM 62
QUESTIONS REPORT for WBfindraft 63.G2.2.13001/T3/T3/TAGGING/M 3.6/3.8/N/WB020301/C/RLM Which one of the following is NOT a reason to tag a device, component, or piece of equipment per SSP-10.2, Clearance Program?
A l Design deficiency B. DCN C . Test activity D. Open Work Orders WB procedure SPP-10.2, pp. 9 Distractor analysis:
See attached Thursday, October 31,2002 06:06:10 PM 63
QUESTIONS REPORT for WBfindraft
- 64. G2.2.22 001/T3/T3/SAFETY LIMITSIM 3.4l4.llMWB020301ICIRLM Which one of the following sets of conditions represents a violation of a technical specification safety limit and required action?
A. Power = IO%, Pressure = 2400 psig, Tavg = 655"F, be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> BY Power = 80%, Pressure = 2250 psig, Tavg = 640°F, be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Power = IO%, Pressure = 2400 psig, Tavg = 655"F, restore to within limits in = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. Power = 80%, Pressure = 2250 psig, Tavg = 640"F, restore to within limits in = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Ref Modified from TP 2000 by adding required action to pick up LCO part of KA.
WB TS Section 2, Safety limits Distractor analysis:
A and C are incorrect because they are within limits and no action required D is incorrect, because even though it is out of limits, it must be restore within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is the DNB parameter spec.
B is correct because it is both out of limits and has the correct required action per TS Thursday, October 31,200206:06:10 PM 64
QUESTIONS REPORT for WBfindraft
- 65. G2.3.1 001/T3/T3/DOSE EQUIVILENTS/M 2.6/3.O/BiWB020301/C/RLM Which one of the following dose components are included in a Radiation Worker's Occupational Dose?
A. Total Effective Dose Equivalent and Planned Special Exposures.
B. Planned Special Exposures and Committed Effective Dose Equivalent.
C. Deep Dose Equivalent and Planned Special Exposure DI Deep Dose Equivalent and Committed Effective Dose Equivalent.
Ref: Surry exam 2002 WB Rad con procedure SPP-5.1, section 5, pp. 32 WB lesson plan 3-OT-RAD0003, pp.10 Thursday, October 31,2002 06:06:10 PM 65
QUESTIONS REPORT for WBfindraft 66.G2.3.4OOliT3iT31EXPOSURE LIMITS/M 2.5/3.1/B/WB020301/C/RLM Given the following plant conditions:
- A LOCA has occurred and a SAE has been declared.
- The TSC and OSC have been activated.
- To prevent core damage it is recommended that entry be made into Safety Injection Pump Room I A .
- Projected dose rate in the pump room is 1 . 1 6 ~ 1 0 mr/hr.
~
- Duration of the exposure is expected to be 3 minutes.
Which ONE of the following must authorize this exposure?
A. Site Vice President B. Plant Manager C: Site Emergency Director D. Radcon Manager
REFERENCES:
EPIP-15 p.3, SPP-5.1 p.10 WBN Exam Bank
- d. incorrect - per EPIP-15 of the Radiological Emergency plan the Site Emergency Director must authorize emergency dose limits in excess of TVA admin limits and 10 CFR 20. Examinee may select: since the Radcon Manager is responsible for completing the paperwork and he must authorize exceeding the limit during non-emergency conditions.
- c. correct - With a projected dose of 1,16E+5 mrlhr, the total dose to respond to this emergency condition is 5.8 Rem.(l.I6E+5 mR/hr I 6 0 minutes x 3 minutes). Per EPIP-15 of the Radiological Emergency plan the Site Emergency Director must authorize emergency dose limits in excess of TVA admin limits and 10 CFR 20.
- b. incorrect - per EPIP-15 of the Radiological Emergency plan the Site Emergency Director must authorize emergency dose limits in excess of TVA admin limits and 10 CFR 20. Examinee may select since Plant Manager must authorize exceeding 5 R during non-emergency conditions.
- a. incorrect - per EPIP-15 of the Radiological Emergency plan the Site Emergency Director must authorize emergency dose limits in excess of TVA admin limits and 10 CFR 20. Examinee may select since Plant Manager must authorize exceeding 5 R during non-emergency conditions.
Thursday, October 31,2002 06:06:11 PM 66
QUESTIONS REPORT for WBfindraft 67.G2.3.9OO~/T~IT~/PURGEIM 2.5/3.4fl\[lWB020301lC/RLM
-Unit 1 is in Mode 3 following a refueling outage
-Both Containment Purge Systems are in operation
-The Shift Manager has directed that the Containment Purge System be secured in accordance with Sol-30.02, CONTAINMENT PURGE SYSTEM.
Reference Provided Which ONE of the following should be considered prior to securing Containment Purge?
A. Outside air temperature B. Outside atmospheric pressure CY Radiological implications D. Containment Purge HEPA and Charcoal filter DP Ref: WB lesson plan 3-OT-SYS30C, obj. 12 WB procedure Sol-30.02 Distractor analysis:
A and D are incorrect because they only apply while the system is in service B is incorrect, because it only applies when placing the system in service C is correct because changes in ventillation, particularly reduction in ventillation can have adverse affects on radiation levels. This is also a precaution in the procedure related to securing CTMT purge. (see below)
CAUTION Radiological implications (e.g.: causing an area to become airborne or raising the humidity in contaminated areas) should be considered any time Containment Purge is secured.
Thursday, October 31,2002 06:06:11 PM 67
QUESTIONS REPORT for WBfindraft
- 68. G2.4.1 001/T3/T3/IMMEDIATE OP ACTION/C/A 4.3/4.6/N/WB020301/C/RL,M
-The Unit is at 100% power.
-A Loss of Shutdown Power occurs Which ONE of the following describes the correct procedure and immediate operator action.
A. E-0, Rx Trip or Safety Injection, ensure Rx is tripped by Rod all bottom lights lit BY ECA-0.0, Loss of Shutdown Power, ensure Rx tripped by neutron flux dropping C. FR-S.l, Nuclear Power GeneratiodATWS, ensure Rx is tripped by neutron flux dropping D. ECA-0.0, Loss of Shutdown Power, ensure Rx tripped by rod bottom lights lit Ref: WB lesson plan 3-OT-PA11204, obj 1 WB procedures PAL1204 E-0 ECA-0.0 Need to check with site to verify that rod bottom lights have no power when shutdown boards deenergized.
Distractor analysis:
A is incorrect because rod bottom lits will not have power B is correct because emergency procedures can be entered directly from a Loss of Shutdown power and Nl's will still be powered from battery via inverter.
C is incorrect because FR-S.l is not an allowable procedure to enter EOP's D is incorrect because rod bottom lits will not have power Thursday, October 31, 2002 06:06:11 PM 68
QUESTIONS REPORT for WBfindraft 69.G2.4.11 001/T3/T3/SG LEAWCIA 3.4/3.6/M/WB020301/ClRL,M Unit 1 is at 100% power with known leakage in SG 2 of 0.05 gpm The Chem Lab reports that today's leakage is 0.06, up from yesterday's reading of 0.05 gpm Which ONE of the following should be performed?
Reference provided AY Be in Mode 3 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. Reduce load to hot standby in accordance with AOI-39, then cooldown and depressurize the RCS.
C. Trip the reactor; enter E-0, then transition to E-3.
D. Convene PORC to evaluate continued operation.
WB lesson plan 3-OT-A01300, obj. 8 Procedure AOI-33, appendix B and C Distractor analysis:
A is correct per table in App. B B is incorrect because it the action for greater than 600 per day thru all or 150 per day thru one C is incorrect because 0.6 is well within charging capability which is the decision point for E-0 D is incorrect because it is the action for leaks less than 0.05 per day Thursday, October 31, 2002 06:06:12 PM 69
QUESTIONS REPORT for WBfindraft
- 70. G2.4.16 001/T3/T3/GO TOIM 3.0/3.9/B/WB020301/ClRLM While in the Emergency Response procedures the team is directed to "Go To" another procedure, which one of the following is the correct implementation of this action?
A. The "GO TO" implies the procedure in use is no longer applicable, and any tasks in progress need not be completed.
B. Tasks still in progress must be completed prior to the transition directed by the "GO T O step.
C! The "GO T O implies the procedure in use is no longer applicable, but any tasks in progress should be completed.
D. Tasks still in progress need not be completed prior to the transition directed by the "GO TO" step, unless preceded by a double asterisk.
WB lesson plan 3-OT-PAI-1204, obj. 13 & 19 WB procedure PAI-1204 Bank: From Surry 2002 Distractor analysis:
Answer C is correct, see below paragraph from PAI-1204 Answer A and B are incorrect due to timing or required completion Answer D is incorrect because double astericks relates to high and low level steps vice transitions.
From PAI-1204:
Transition to another step or instruction may be completed before completion of the task in progress, provided that completion of the task is verified at a later time.
Transitions which are not high level action steps are identified with a double asterisk preceding the words GO TO and are in bold face type.
Thursday, October 31,2002 06:06:12PM 70
QUESTIONS REPORT for WBfindraft 7 1. G2.4.8001iT3iT3/PROCEDURETRANSITION/C/A3.0/3.7/B/WB020301/C/RLM Given the following condition:
- The crew has entered ECA-0.0 due to a loss of both SD Bds.
- The Load Dispatcher has recovered one 161KV line from Watts Bar Hydro.
- The crew has implemented AOI-35.
Which ONE of the following actions should the crew take?
A. Immediately transition to ECA-0.1, Recovery from Loss of Shutdown Power without SI required.
B. Immediately transition to ECA-0.2, Recovery from Loss of Shutdown Power with SI required.
C. Manually actuate SI and return to E-0, Rx Trip or Safety Injection.
DI Continue with ECA-0.0, Loss of Shutdown Power while concurrently performing AOI-35, Loss of Offsite Power.
Ref: WB procedure ECA-0.0 and AOI-35 WB bank question, changed two obviously incorrect distractors Thursday, October 31,200206:06:12 PM 71
QUESTIONS REPORT for WBfindraft
- 72. WE03EK2.2 001iTlG2/TlG21HEAT REMOVALICIA 3.7/4.OlB/WB020301/C/RLM Given the following plant conditions:
- A small break LOCA has occurred.
- RCPs have been tripped.
- Appropriate actions in accordance with E-0 and E-I have been completed.
- RCS pressure is stable at 1525 psig.
- ECCS is operating in cold leg injection mode.
Which ONE of the following statements describes the primary method of decay heat removal at this time?
A? Heat transfer between the RCS and the SlGs due to natural circulation flow.
B. Heat transfer between the RCS and CCS via the RHR Heat Exchangers C. Heat transfer from the injection of water from the RWST and the removal of steamlwater out of the break.
D. Heat transfer from Reflux boiling in the SlGs.
Ref WB Lesson Plan 3-OT-EOPOI00, no specific learning objective found WB lesson plan 3-OT-SYS063A, no specific learning objective found WB exam bank Distractor Analysis:
A is correct because due to the thermodynamic ? H between the primary and secondary and resultant heat transfer rate will exceed the heat transfer into the injection flow water.
B is incorrect because CCS flow is isolated from the RHR Hx's at this point in the accident.
C is incorrect same as A D is incorrect because at this point in the accident the SIG U-tubes are still filled with water.
Thursday, October 31, 2002 06:06:13 PM 72
QUESTIONS REPORT for WBfindraft
- 73. WEOSEAI .3 001/T1G2/T1G2/FEED AND BLEEDICIA 3.8/4.2/B/WB020301/C/RLM Given the following plant conditions:
- Unit is operating at 100% power at EOL.
- Total loss of feedwater occurs and operators implement FR-H.l, "Loss of Secondary Heat Sink".
- No means of feedwater addition is available and the operators have initiated feed and bleed.
- Manual Safety Injection was initiated and when the operator attempted to open the pressurizer PORVs, PCV-68-340 failed to open.
Which ONE of the following describes the correct operator mitigation strategy to respond to this problem?
A. Stop one Centrifugal Charging Pump to reduce loss of inventory through PORVs.
B. Close any open Pzr PORV to conserve RCS inventory and return to the steps to re-establish Main Feedwater.
CY Open the reactor head vents to reduce RCS pressure since one pressurizer PORV may not provide sufficient heat removal capacity.
D. Verify PORV, 1-PCV-68-334, and it's block valve open to reduce RCS pressure since 1 Pzr PORV provides adequate heat removal capacity for a loss of heat sink.
Ref WB lesson plan 3-OT-FRH0001, obj. 9 & 10 Distractor analysis:
- a. Incorrect - one PORV is not sufficient to provide adequate heat removal.
- b. Correct - increases the bleed path capability and reduce pressure to ensure the core remains cooled.
- c. Incorrect - procedure directs bleed and feed not depressurizing a SG which would be a less effective cooling method.
- d. Incorrect - more bleed path capacity is needed to ensure pressure reduction and cooling capability, not less injection.
Thursday, October 31,2002 06:06:13PM 73
QUESTIONS REPORT for WBfindraft
- 74. WE10EA2.2 001iT1G1/T1Gl/lCIA (3.4/3.8)/B/WBO2301/ClEL Given the following plant conditions:
- Reactor trip occurred with subsequent loss of RCPs.
- Operators have implemented ES-0.2, "Natural Circulation Cooldown".
- A cooldown rate of 25"F/hour has been established.
- RCS depressurization has been initiated while maintaining subcooling
> 165°F.
- Operators are monitoring PZR level and RVLIS for void formation.
- The OAC observes that loss of inventory in the Condensate Storage Tank is imminent.
Which ONE of the following describes the appropriate procedural actions?
A. Stop the cooldown and remain in ES-0.2.
B. Raise the cooldown rate and remain in ES-0.2.
C. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and lower the cooldown rate.
D.' Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and raise the cooldown rate.
The correct answer is D.
- a. Incorrect - loss of CST inventory should cue the examinee that transition to ES-0.3 is appropriate. Examinee may believe stopping cooldown is appropriate to conserve inventory.
- b. Incorrect - loss of CST inventory should cue the examinee that transition to ES-0.3 is appropriate. Examinee may believe raising cooldown rate would be appropriate in order to reach RHR conditions sooner however ES-0.2 does not provide instruction to do this.
- c. Incorrect - loss of CST inventory is an appropriate condition to require transition to ES-0.3 since more rapid cooldown rate is allowed while addressing voids in the RCS. Examinee may believe it is necessary to lower cooldown rate to conserve inventory.
- d. Correct - loss of CST inventory is an appropriate condition to require transition to ES-0.3 since more rapid cooldown rate is allowed while addressing voids in the RCS.
Thursday, October 31, 2002 06:06:14 PM 74
QUESTIONS REPORT for WBfindraft
- 75. WE 1 1EA1.3 OOliTl G2ITIG2/RECIRCULATION/C/A 3.7/4.2/B/WB02030 l/C/RLM Given the following plant conditions:
- Reactor trip and SI occurred on Unit 1 due to a small break LOCA.
- Crew has transitioned from ES-1.3, "Transfer to RHR Containment Sump", to ECA-1. I , "Loss of RHR Sump Recirculation", due to the failure of both RHR sump suction valves to open.
- Crew has reduced ECCS flow to 1 CCP per Figure 1 of ECA-1.I.
- Crew is performing Step 23 of ECA-1.Ito check makeup flow adequate and observes the following indications:
- Loop 2 RCP running
- RVLIS = 60% and slowly dropping Which one of the following lists the correct operator action for this condition?
A. Ensure additional makeup source to RWST has been aligned.
BY Control charging to raise makeup flow.
C. Place RHR shutdown cooling in service.
D. Slowly depressurize RCS to inject CLAs.
Ref: WB lesson plan 3-OT-ECA0101, obj. 1 WB procedure ECA-1.I Distractor analysis:
A is incorrect because this is a continuing action from earlier in the procedure, not a hold point.
6 is correct per step 23 RNO because RVLIS <63% w/ RCP running.
C is incorrect because stem does not indicate that pressure-temp conditions would allow.
D is incorrect because the depressurization step in later in the procedure assuming adequate subcooling and PZR level which are not indicated in the stem.
In original bank question the following was a distractor:
"Place at least one train of ECCS pumps inservice until RVLIS > 65%.". It has been replaced because step 23 RNO also has "OR restart ECCS pumps as necessary".
Thursday, October 31,200206:06:14PM 75