ML082750419
| ML082750419 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/05/2008 |
| From: | Ryan Lantz Operations Branch IV |
| To: | Entergy Operations |
| References | |
| 50-313/08-301, 50-368/08-301, ES-401, ES-401-8 50-313/08-301, 50-368/08-301 | |
| Download: ML082750419 (117) | |
Text
s-401 Site-Specific SRO For -401-Cover Sheet US. Nuclear Regulatory commission U Region: I II Ill [? IV 1 ReactorType: W U C E U B W a G E [ I l Start Time: Finish Time:
Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
nt ~ e ~ i f i c a t i o n I All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Resuits RO/SRO-Only/TotalExamination Values - 75 /- 25 / 100 Points 1 Applicants Scores -/-/-
Points 1 Applicants Grade -J-/- Percent
ES-401 ~ ~ t e - S ~ e RO c i ~ ~ cen Examination or -401-7 Cover Sheet U S . Nuclear Regulatory Commission Site-Specific n ~xam~nation Name:
I Date: 9/5/2008 I Facility/Unit: ANO-1 1
I Region: I 0I I u Ill IV Ixl Reactor Type: W 0CE c]BW m G E c]
Start Time: Finish Time:
I nst ructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results Examination Vaiue 75 Points Applicants Score Points Applicants Grade Percent
Question No. 1 QID: 0680 Point Value: 1 Answer:
C. AC Breaker "B" and DC Breaker "C" Open and Electronic Trip "E"Tripped.
__ - - - _ _ ~ ~- _ -
Question No. 2 Answ~r:
A. 250 degrees F is correct.
Question No. 3 QID: 0506 Point Value: 1 Answer:
B. EFlC High Range 2" to 8"/min in Auto or 340gpmlSG in Manual Question No. 4 QID: 0684 Point Value: 1 Answer:
C. Override and secure ail HPI pumps.
Question No. 5 QID: 0682 Point Value: I Answer:
D. Loop "B" Tc lowering.
- - - _ - _ _ _ I _ --_ _- - -- - -- __ - ____
Question No. 6 QID: 0183 Point Value: 1 Answer:
C. if RCP seal bleedoff temperatures are >I 80 degrees, seal injection control valve (CV-12.07) is slowly opened to minimize thermal shock to the RCP seals.
Question No. 7 QID: 0164 Point Value: I Answer:
A. Reduce decay heat removal flow until flow has stablized.
QID: 0683 Point Value: 1 Answer:
C. Select LIS-1002on C04
-~ -- - _- _- ~- -
Question No. 9 QID: 5328 Point Value: ?
Answer:
A. Depress the CRD Power Supply Breaker Trip Pushbuttons.
_ _ _ _ - - _ I _ - - ___-
Question No. 10 QID: 0685 Point Value: I Answer:
D. RCS temperature of 420 degrees due to hydraulic lifting of fuel assemblies.
Question No. 1I QID: 0686 Point Value: 1 Answer:
A. Verify EFW isol and control valves to " A OTSG closed.
-~ ~ -_- _ -
Question No. 12 QID: 0752 Point Value: 1 Answer:
B. "B" Main Feedwater block valve CV-2675 Question No. 13 QID: 0688 Point Value: 1 Answer:
D. K i 2435, ! F i A TURBINE TRIP" and K09-A2, "TRAIN A SUBCLG MARG LO" Question No. 14 QID: 0689 Point Value: 1 Answer:
D. Initiate full HPI per RT 3.
QID: 0690 Point Value: 1 Answer:
B. Pressurizer level control valve (CVl235) fails to 50%, Seal injection control valve (CV1207) fails to 50%.
QID: 0513 Point Value: I Answer:
C. EDG #I will NOT start automatically but may be started manually by overriding the governor run solenoid.
Question No. 17 ID: 0691 Point Value: 1 Answer:
C. Verify standby Instrument Air Compressor is running.
- - _ -__ - -- _~
Question No. 18 QID: 0692 Point Value: 1 nswer:
B. Low Pressure Injection Pump Question No. 39 QiD: 0001 Point Value: 1 nswer:
B. Transfer Group 7, Rod 3 to the Aux Bus and pull programmer control fuses for the Aux Power Supply.
Question No. 20 QID: 0694 Point Va!us: 1 Answer:
D. Main Steam Line High Range Radiation Monitors Question No. 21 QID: 0695 Point Value: 1 Answer:
A. Unit 1 siippiies the Fire Brigade Leader, Unit 2 supp~ies3 Fire supplies one support member
~
__ -- ~-
Question No. 22 QID: 0696 Point Value: I Answer:
C. Cycling HPI pump from breaker.
Question No. 23 QID: (2693 Paint Value: ?
Answer:
A. CV-1221, "L/D Cooler Outfet," Qreer; light, on (218; SV-1270, '*Seai Bleedoff Alternate Path," red light, on C13; CV-1270, "Seal Bleedoff Normal Path," green light, on C18.
_ _ ___ ~- -- - -- - -- _--_ - - --
QID: 0370 Point Value: I Answer:
B. 1203.018, "Turbine Trip below 43% Power" Question No. 25 QID: 0049 Point Value: I Answer:
B. Lake level >340 ft. and forecasted lake level at site >350 ft.
Question No. 26 QID: 0697 Point Value: 1 Answer:
C. Take manual control of "A" EFW Control Valve and reduce feed flow.
Question No. 27 QID: 0348 Point Value: 1 Answer:
- 9. Thiuitie the "PHPI valve until "A" line flow is within 20 gpm of "D" line flow to minimize inventory loss on a line break.
- ___ - -- - - - -___ - _ ~ -_ - -
Question No. 28 QID: 0698 Point Value: 1 Answer:
A. Function: Flux / delta Flux I Flow Reason: Assures DNBR is not exceeded.
QID: 0267 Point Value: 1 nswer:
C. Reactor Coolant Pump P-32B seal cooler leak.
Questior, No. 30 OSD: 0699 Point V ~ ~ u I ~ :
Answer:
D. 150 psig; T-I 1, "Aux Bldg Equip Drain Tank."
Question No. 31 QID: 0353 Point Value: 1 Answer:
D. One high pressure injection pump, one low pressure injection pump, and both core flood tanks.
Question No. 32 ID: 070 Answer:
D. RCS temperature rises, RCS pressure rises, and Pressurizer level rises.
Question No. 33 9 Answer:
A. LPI suctions from BWST(CV-I436 & CV-1437) verify open and BWST outlet valves (CV-1407 & CV-1408) verify closed.
-~ - ___ _-_ _- - - -
Question No. 34 QID: 0702 Point Value: 1 Answer:
C. 100 psig
- - - ____ ~ - --
Question No. 35 QID: 0703 Point Value: 1 Answer:
n t Compressors C-28A,& E3 D. ~ n s t r u ~ eAir
ID: 0521 Point Value: 1 Answer:
D. An outsurge from the pressurizer has occurred.
Question Nc. 37 QID: 0?31 Pcint Value: 1 Answer:
A. The RPS would be placed in a 2 out of 2 coincidence logic.
Question No. 38 QID: 0057 Point Value: I Answer:
B. Removal of the RB Pressure Buffer Amplifier from Analog Channel 1.
Question No. 39 QID: 0704 Point Value: 1 Answer:
A. A108 and A208 Question No. 40 QID: 0705 Point Value: I Answer:
B. 86171 and B5171
- - ~-
Question No. 41 QID: 0706 Point Value: I Answer:
C. Override and Stop both RB spray pumps and overide and close CV-2400 and CV-2401 RB Spray Biock Vaives.
Question No. 42 QID: 0707 Point Value: 1 Answer:
B. 910
uestion No. 43 QID: 022 Point Value:
Answer:
C. All TBVs will close, both ADV isolations will open, both ADV control valves control at setpoint
- __--- - ____ _ _ _ ~
Question No. 44 QID: 0708 Point Value: 1 Answer:
D. MFP will speed up to 5800 RPM.
uestion No. 45 ID: 0709 Point Value: 1 Answer:
B. "A" OTSG filling at 5"/minute, "6"OTSG filling at 2"lminute.
Question No, 46 QID: 0710 Point V a ~ u @ ~1 Answer:
C. Delta T-cold between the loops lowering.
Question No. 47 ID: 0711 Point Va~ue: 1 Answer:
B. Impacts: MCC starters may not pick up to energize loads; Mitigation: Motors should be started one at a time and allowed to reach run speed to minimize further voltage degradation.
Question No. 48 QID: 0384 Point Value: 1 Answer:
A. Impacts: No immediate impact.
Mitigation: Electrical maintenance support is required to determine ground location.
- -~
Point Value: I Answer:
6.D03A, "Battery Charger" inoperable and D03B, "Battery Charger" inoperable.
Question NQ. 50 QtD: 0713 Point Value: 1 Answer:
D. In service bulk storage tank filter (F-27) clogged.
~ -_ ~ ___ _________
Question No, 51 QID: 0089 Point Value: 1 Answer:
A. Verify no flow on Discharge to Flume, Fl-4642 Question No. 52 QID: 0388 Point Value: 1 Answer:
A. No cooling to the RCP motor and seal coolers.
Question No. 53 QID: 0714 Point Value: 1 Ar.s:.:e::
C.As Is Question No. 54 QID: 0715 Point Value: I Answer:
- 5. Moisture in the air system may affect air operated equipment; As directed by the AOP, 1203.024, "Loss of Instrument Air."
- __ --__ --.- __I-
_ I --_-_ - --
Question No. 55 QID: 0716 Point Value: I Answer:
C. Maximize Reactor Building Cooling.
-~ _ -
uestion No. 56 QID: 0717 ointValue: I Answer:
D. Sequence inhibit.
Question No. 57 C!D: 0718 Point Value: 1 Answer:
B. AutolManual difference Question No. 58 QID: 0134 Point Value: I Answer:
C. Discrimination separates out gamma and alpha pulses to provide a true neutron pulse.
With the discrimination set too high, power will indicate lower than actual power.
_ _ _ _ -- ~ - - -
~ _-____ _ _ -
Question No. 59 QID: 0719 Point Value: 1 Answer:
- 6. Provide indication of core outlet temperature distribution, and input to margin to saturation.
Question No. 60 QID: 0723 Point Value: 1 Answer:
A. M-55A B-53; M-55B B-61 Question No. 61 QID: 0720 Point Value: 1 Answer:
E. Suspend core aiterations and place the assembly in the Fuel Handling Canal fuel storage rack.
Question No. 62 QID: 0721 Point Value: 1 Answer:
C. The "A" train Main Steam Safety valves.
QID: 0100 Point Value: 1 nswer:
C. PZR makeup flow would drop.
Question No, 54 QID: 0722 Point Value: I Answer:
B. Open RB purge outlets CV-7401 a n d CV-7403, when RE pressure equals atmospheric pressure, then Open RB purge Inlets CV7402 and CV-7404, place RB purge exhaust fan VEF-15 in auto, start RB purge Supply Fan VSF-2, a n d verify RB purge exhaust fan VEF-15 starts.
uestion No. 65 QID: 0379 Point Value: I Answer:
i3.Adjust the setpoint t o less than or equal to max high alarm setpoint before recording the As-Left Setpoint.
Question No. 6 QiD: 8339 Point Value: I er:
C. Prior to use, e B change number.
Question No. 67 QID: 0245 Point Value: 1 4nswer:
D. The valve must be stroked electrically to confirm proper clutch engagement.
- - - - - ---__-____-__~___-__ -
Question No. 68 QID: 0724 Point Value: 1 Answer:
B. Line-up section of the System Procedure
Question No. 69 ID: 0725 Point Value: 1 Answer:
D. Operations Supervisor Question No. 70 Ql5: 0487 PcrZnt Value: I Question No. 71 QID: 0751 Point Value: 1 Answer:
A. TEDE 2000 mrem per year, SDE, W6= 40 rem, and LDE= 12 rem Question No. 72 QID: 0727 Point Value: 1 Answer:
- 6. Perform 1103.013, "RCS Leak Detection."
Question No. 73 QID: 0025 Point Value: 1 Answer:
A. Main Turbine Anticipatory trip.
_ _- -- __ - -- -_-- ___---______~
Question No. 74 QID: 0728 Point Value: I Answer:
D. Both SG pressures 580 psig, with levels of 20" and EFW feeding.
Question No. 75 QID: 0726 Point Value: 1 Answer:
A. Reactor Building pressure 19.7 psia.
~ -
Point Va~ue: I Answer:
D. 1202.001, "Reactor Trip."
QID: 0729 Point Value: 1 Answer:
C. Place one channel in bypass and a second in trip.
Question No. 78 QID: 0731 Point Value: 1 Answer:
D. A cooldown rate of 1lOF/hr with Tcold at 330F.
Question No. 79 QID: 0732 Point Value: 1 Answer :
D. Restore one channel to operable status within 7 days or be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in Mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
u e s t ~ QNo.
~ 80 ID: 0733 Point Value: 1 Answer:
B. Overheating (1202.004)
Question No. 81 QID: 0734 ~ o iV~~ i tu e : 1 Answer:
A. "Main Generator Winding Trouble", 1203.045 Question No. 82 QID: 0735 Point Value: 1 Answer:
A. Nuclear Overpower trip.
Question No. 83 QID: 0736 Point Value: 1 Answer:
- 6. 1203.019 High Activity In Reactor Coolant 50%
Answer:
A. Loss of Subcooling Margin (1202.002)
Point Value: 1 Answer:
A. Reduce cooldown rate per 1203.013, "Natural Circulation Cooldown."
Question No. 86 QID: 0738 Point Value: 1 Answer:
C. Reduce reactor power to within the capacity of unaffected RCP combination and trip the pump per Section 5, "Motor / Bearing Trouble."
Question No. 87 QID: 0607 Point Value: 1 Answer:
C. 1203.026, Loss of Reactor Coolant Makeup, Section 2 - Large Makeup and Purification System Leak Question No. 88 QID: 0730 Point Value: 1 Answer:
A. ESAS 1202.010 Question No. 89 QID: 0739 Point Value: 1 Answer:
B. P35A spray flow is less than 1050gpm 55 seconds after ES channel actuation, and may be mitigated by 1203.O12Jl "KI 1-C6 RB SPRAY P35A ES FAILURE."
Question No. 90 QID: 0740 Point Value: 1 Answer:
D. Valves failed open; 1203.036, "Loss of 125 V DC" Question No. 91 QID: 0742 Point Value: 1 Answer:
A. Needed to protect the public safety.
743 ~ o i nValue:
t i Answer:
D. Suspend operations involving positive reactivity changes..
744 o~ntVa~ue: 4 Answer:
B. 1203.012F, "SASS Mismatch" ACA Question No. 94 QID: 0745 Point Value: 1 Answer:
B. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of work including 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of turnover within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Question No. 95 QID: 0746 Point Value: 1 Answer:
B. The fuel assembly may be hung up on a grid strap, you must lower fuel assembly to relieve overload and slowly bump fuel assembly in 1/4 inch steps until grid interface is passed Question No. 96 QID: 0747 Point Value: 1 Answer:
D. Expedited Work Order.
Question No. 97 QID: 0748 Point Value: 1 Answer:
C. Planned dose shall not exceed 25 Rem TEDE with TSC Director's authorization.
n.....-b:.-.-
U(UGJLIUII hi..
IUU. s!! =:E: 0749 n...:-a
&!?#.-g
\W"-!l_t!s.
- -I..-. 4 Answer:
C. SPING 1 channel 5 two-minute average value exceeds set point.
Question No. 99 QID: 0520 Point Value: 1 Answer:
C. 1202.001, Reactor Trip
Answer:
D. Verifying all RCP breakers stay open per Fires in Areas Affecting Safe Shutdown procedure 1203.049
~ ....
Question No. 1 QID: 0680 To ensure all Control Rod Drives are de-energized on a reactor trip, which of the following CRD breakedelectronic combinations are necessary:
A. AC Breaker "A" or AC Breaker lfBffOpen and Electronic Trips "E" or "F" Tripped.
B. AC Breaker "A" and DC Breaker "C" and Electronic Trip "E" Tripped.
C. AC Breaker "B" and DC Breaker "C" Open and Electronic Trip "E" Tripped D. AC Breaker "B" and DC Breaker "D" Open and Electronic Trip "F" Tripped.
Question No. 2 QID: 0681 Given:
Reactor Trip on high pressure due to a load rejection.
RCS pressure at 2150 psig and lowering slowly.
K09-B4 "QUENCH TANK LEVEL HI / LO" annunciator in fast flash.
K09-D3 "PZR LEVEL HI" annunciator in fast flash.
K09-A1 "RELIEF VALVE OPEN" annunciator in fast flash.
Quench tank pressure 30 psig.
Reactor Building pressure is 16.1 psia.
Which of the following tail pipe temperatures would indicate the Electromatic Relief Valve /
Code Safety Valves have RESET?
A. 250 degrees F B. 280 degrees F.
C. 290 degrees F.
D. 300 degrees F
Question No. 3 QID: 0506 Given:
- A Small Break LOCA has occurred.
- ATC has tripped the reactor.
- CBOT has tripped the turbine.
- Both OTSG Pressure's are at 895 psig
- SCM is25"F.
- All RCPs are OFF.
The desired final OTSG levels will be maintained wit, EFW using I ? Level instrument(s) and obtained with a fill rate of ? .
A. EFlC Low Range, 2" to 8"/min in Manual or 340gpmISG in Auto B. EFlC High Range 2" to 8"/min in Auto or 340gpm/SG in Manual C. EFlC Low Range 2" to 8"/min in Auto or 340gpm/SG in Manual D. EFlC High Range 2" to 8"/min in Manual or 340gpm/SG in Auto
Given:
A Large Break LOCA has occurred Full ESAS actuation.
LPVHPI flow rates are as follows:
"A" LPI flow--3100 gpm "B" LPI flow--3050 gpm "A" HPI flow--475 gpm "C" HPI flow--l50 gpm BWST level is 12 feet Which of the following action is required per the ESAS EOP for these conditions?
A. Restore full HPI flow on "C" HPI pump.
B. Secure the "C" HPI pump only.
C. Override and secure all HPI pumps.
D. Swap to RB sump recirculation.
Question No. 5 QID: 0682 Given Plant Power at 70%
Feedwater Loop Demands in HAND "A" Reactor Coolant Pump Trips No operator action.
Considering heat transfer between the RCS Loops and their associated Steam Generators, which of the following temperatures would be impacted the GREATEST and in which direction?
A. Loop "A" Tc rising.
B. Loop "B" Tc rising.
C. Loop "A" Tc lowering.
D. Loop "B" Tc lowering.
Question No. 6 QID: 0183 During restoration of normal makeup and seal injection, which of the following is correct?
A. If PZR level is 4 5 " , normal makeup is restored before seal injection to raise RCS inventory.
B. If RCP seal bleedoff temperatures are >I80 degrees, seal injection control valve (CV-1207) is quickly opened to establish previous flow rate.
C. If RCP seal bleedoff temperatures are >I80 degrees, seal injection control valve (CV-1207) is slowly opened to minimize thermal shock to the RCP seals.
D. BWST outlet valve associated with the operating HPI pump must be closed prior to opening seal injection control valve (CV-1207) to prevent borating RCS.
Question No. 7 QID: 0164 An outage is in progress with the following conditions:
- The RCS is drained to 371.5 feet as indicated by RCS hot leg level.
- Decay heat removal flow becomes erratic.
- Indicated decay heat removal flow is -2500 gpm.
Which action should be taken first to prevent a Loss of Decay Heat?
A. Reduce decay heat removal flow until flow has stablized.
- 8. Start the Standby Decay Heat pump C. Raise RCS level.
D. Raise decay heat removal flow.
Question No. 8 QID: 0683 Given:
Reactor power is 100%
K09-C3, "Pzr Level Lo" in fast flash K09-A3, "Pzr Level Lo Lo" in fast flash The ATC operator reports the following:
Pressurizer Level LRS-1001 on C04 reads 40 inches Pressurizer Level LIS-I002 on C04 reads 210 inches RCS Pressure is 2155 psig steady.
What actions are required for these conditions?
A. Isolate Letdown B. Trip the Reactor and refer to 1202.001 Rx Trip C. Select LIS-I002 on C04 D. Trip the Reactor and refer to 1203.039 Excess RCS leakage.
Question No. 9 OlD: 0328 Plant is operating at 100% power.
As the ATC you observe the following indications:
- "A" and "B" Main Feedwater Pumps are tripped
- CRD groups I, 2, 3,and 4 are at the out limit.
- CRD groups 5 , 6, and 7 are at the in limit.
- NI-3 indicates 1 E-8 and lowering.
What action should be performed FIRST per 1202.001, "Reactor Trip" EOP?
A. Depress the CRD Power Supply Breaker Trip Pushbuttons.
B. Dispatch an operator to open the CRD AC Power Supply Breakers.
C. Commence Emergency Boration per RT-12.
D. Manually insert CRD groups 1, 2, 3, and 4.
__ ~
ritten Examinati
~.
Question No. 10 QID: 0685 Given :
Steam Generator Tube Rupture has occurred.
Per the floating steps of 1202.006, "Tube Rupture" EOP at what temperature does the procedure require securing the fourth Reactor Coolant Pump and why?
A. RCS temperature of 390 degrees due to hydraulic lifting of fuel assemblies.
B. RCS temperature of 390 degrees due to RCP motor loading concerns.
C. RCS temperature of 420 degrees due to RCP motor loading concerns.
D. RCS temperature of 420 degrees due to hydraulic lifting of fuel assemblies.
Question No. il QID: 0686 The reactor has been tripped due to a Main Steam Line Rupture The following post-trip conditions exist:
- "A" OTSG pressure = 425 psig
- "B" OTSG pressure = 580 psig
- RCS temperature = 495 degrees F
- RCS pressure = 1500 psig
- MSLl has actuated Which of the following actions is correct for this event?
A. Verify EFW isolation and control valves to "A" OTSG closed B. Verify EFW isolation and control valves to '73'OTSG closed.
C. Verify at least one EFW pump running with flow to both OTSGs.
D. Trip all running RCPs.
Question No. 42 QID: 0752 Which of the following plant components, if inoperable, would require entry into Technical Specification action statement?
A. Main Feedwater Pump P-1B B. "B" Main Feedwater block valve CV-2675 C. Control Room supply fan VSF-8A D. #I EDG Starting Air compressor C-4A-1
Question No. 13 QID: 0688 Given:
Station Blackout, The following alarms are in:
K02-A1, "SU IL.O. RELAY TRIP" K02-A6, "AI L.O. RELAY TRIP" K09-A2, "TRAIN A SUBCLG MARG LO" K12-B5, "P7A TURBINE TRIP" Which two annunciators are the highest priority per 1202.008, "Blackout" EOP?
A. K02-A1, "SU 1 L.O. RELAY TRIP" and K09-A2, "TRAIN A SUBCLG MARG LO" B. K12-B5, "P7A TURBINE TRIP" and K02-A1, "SU 1 L.O. RELAY TRIP" C. K09-A2, "TRAIN A SUBCLG MARG LO" and K02-A6, "A1 L.O. RELAY TRIP" D. K12-B5, "P7A TURBINE TRIP" and K09-A2, "TRAIN A SUBCLG MARG LO"
Question No. 14 QlD: 0689 Given:
A Degraded Power event occurred.
Both EDGs are supplying associated ES buses.
Pressurizer level is 200 inches.
CET temperatures indicate 600 degrees RCS pressure 1850 psig.
MSLI and EFW have been actuated.
Which of the following actions is correct?
A. Verify EFW level set point is 300 to 340 inches per RT6 B. Initiate HPI cooling per RT 4.
C. Restore letdown for inventory control per RT 13.
D. Initiate full HPI per RT 3.
Question No. 15 QID: 0690 The response of the makeup and purification system to a loss of all NNI X AC and NNI X DC power is:
A. Pressurizer level control valve (CV-1235) fails closed, Seal injection control valve (CV-1207) fails closed.
B. Pressurizer level control valve (CV-1235) fails to 50%,
Seal injection control valve (CV-1207) fails to 50%.
C. Pressurizer level control valve (CV-1235) fails closed; Seal injection control valve (CV-1207) fails to 50%.
D. Pressurizer level control valve (CV-1235) fails to 50%;
Seal injection control valve (CV-1207) fails closed.
Question No. 16 QfD: 0513 Given:
- Degraded power event in progress
- KOI-D1, "EDG 1 NOT AVAILABLE" is in alarm
- The Inside A 0 reports that engine DC control power was lost to EDG #I What is expected effect on EDG # I following a loss of engine DC control power?
A. EDG #I will NOT start automatically and CANNOT be started manually due to the governor run solenoid failed closed.
B. EDG # I will start and run at idle speed but will NOT accelerate to run speed due to the governor run solenoid failed to minimum load C. EDG # I will NOT start automatically but may be started manually by overriding the governor run solenoid.
D. EDG # I will start and run at load rpm speed but CANNOT be placed on its associated 4160 VAC Essential Bus due to the governor run solenoid causing a lockout.
Question No. 57 QID. 069.4 Given:
- Instrument Air pressure on both Units has been degrading for approximately 30 minutes.
- Instrument Air leak is discovered on Unit 2.
SUDDENLY, Unit One lnst. Air pressure drops to 67 psig.
Which of the following actions are required in accordance with 1203.024 "Loss of Instrument Air?"
A. Isolate Letdown by closing, Letdown Coolers Outlet valve CV-1221 B. Isolate Unit 1 Inst. Air from Unit 2.
C. Verify standby Instrument Air Compressor is running.
D. Monitor ICW Surge Tank Levels due to loss of level control.
Question No. 18 QID: 0692 Given:
Unit is in Cold Shutdown RCS is Intact RCS Loops not filled Steam Generators are not available Emergency Feedwater System is not available BWST Level 30 feet An unidentified leak in the common suction header in the Reactor Building has caused loss of operating Decay Heat Systems.
RCS pressure has increased to 120 psig due to loss of Decay Heat Removal.
Under these conditions, what is the preferred method of RCS Makeup to provide Core Cooling?
A. Gravity feed from BWST B. Low Pressure Injection Pump C. Spent fuel Cooling Pump P-40A D. High Pressure Injection Pump
Question No. 19 QID: 0001 Given:
- Plant runback to 39% power.
- Group 7 Rod 3 API indication not moving.
- Group 7, Rod 3, stator temperature is 193 O F and rising.
- A stator temperature HI alarm in.
- All other Control Rod stator temperatures are normal.
Which action would be performed FIRST per 1203.003, " Control Rod Drive Malfunction,"
to reduce temperature on the Group 7, Rod 3 stator?
A. Manually trip the reactor due to Group 7, Rod 3 stator temperature exceeding 190 OF.
B. Transfer Group 7, Rod 3 to the Aux Bus and pull programmer control fuses for the Aux Power Supply.
C. Drop Group 7, Rod 3 by removing the six stator fuses for the rod in the CRD transfer cabinet.
D. Transfer Group 7, Rod 3 to the DC Hold Bus to reduce stator current.
Question NO. 20 QID: 0694 Given:
Plant is at 100% power, OTSG N-16 monitor alarms on both Steam Generators, Steam Generator Tube Leak is suspected, Which of the following may be inconclusive at verifying which Steam Generator has the tube leakage?
A. SGTR display on SPDS B. Nuclear Chemistry Sample C. Plant Monitoring System N16T screen D. Main Steam Line High Range Radiation Monitors
Question No. 21 QID: 0695 Per 1015.007, "Fire Brigade Organization and Responsibilities," which of the following describes the Ops Manning composition of the Fire Brigade for the initial response to a fire on Unit I?
A. Unit 1 supplies the Fire Brigade Leader, Unit 2 supplies 3 Fire Brigade members, Security supplies one support member.
B. Unit 1 supplies the Fire Brigade Leader and 2 Fire Brigade members, Unit 2 supplies 1 Fire Brigade member, Security supplies one support member.
C. Unit 2 supplies the Fire Brigade Leader, Unit 1 supplies 3 Fire Brigade members, Security supplies one support member.
D. Unit 2 supplies the Fire Brigade Leader and 1 Fire Brigade member, Unit 1 supplies 2 Fire Brigade members, Security supplies one support member.
Question No. 22 QID: (1696 How is RCS inventory controlled after an immediate control room evacuation per 1203.002, "Alternate Shutdown" EOP?
A. Local manual operation of Pressurizer makeup valve.
B. Local manual operation of letdown isolation valve.
C. Cycling HPI pump from breaker.
D. Local manual operation of HPI motor operated valves.
Question No. 23 QlD: 0693 Given:
1203.019, "High Activity in Reactor Coolant" AOP Due to dose rates you are directed to isolate Letdown and swap RCP seal bleed-off from the Normal path to the Alternate path (Quench Tank.)
Which of the following combinations of indications and locations are correct for the desired plant line-up?
A. CV-1221, "L/D Cooler Outlet," green light, on SV-1270, "Seal Bleedoff Alternate Path," red light, on C13; CV-1270, "Seal Bleedoff Normal Path," green light, on C18.
B. CV-1221, "L/D Cooler Outlet," green light, on SV-1270, "Seal Bleedoff Alternate Path," green CV-1270 ,"Seal Bleedoff Normal Path," red light, on C18.
C. CV-1221, "L/D Cooler Outlet," red light, on SV-1270, "Seal Bleedoff Alternate Path," red CV-1270, "Seal Bleedoff Normal Path," green light, on C26.
D. CV-1221, "L/D Cooler Outlet," green light, on SV-1270, "Seal Bleedoff Alternate Path," green light, on C23; CV-1270, "Seal Bleedoff Normal Path," red light, on (226.
nit 2 -
Question No. 24 QID: 0370 Given:
Plant power 39%.
Power escalation in progress.
The following conditions are observed:
- Rapid rise in RCS temperature
- Rapid rise in RCS pressure
- Rapid rise in PZR level
- Megawatt output = zero (0)
- MSSV open alarm No other annunciators in alarm except for those expected for the above conditions.
What procedure contains the required mitigating operator actions?
A. 1203.001, "ICs Abnormal Operating" B. 1203.018, "Turbine Trip below 43% Power" C. 1203.027, "Loss of Steam Generator Feed" D. 1202.001, "Reactor Trip Procedure"
Question No. 25 QID: 0049 Given:
Lake Dardanelle level rising due to severe weather and heavy rains.
Which of the following is the minimum level to commencing a plant shutdown in accordance with 1203.025, "Natural Emergencies?"
A. Lake level >330 ft. and forecasted lake level at site >340 ft.
B. Lake level >340 ft. and forecasted lake level at site >350 ft.
C. Lake level >350 ft. and forecasted lake level at site >360 ft.
D. Lake level >360 ft. and forecasted lake level at site >370 ft.
Question No. 26 QID: 0697 Given:
Degraded Power Performing Natural Circulation Cooldown per 1203.013 SCM is 50 degrees F and slowly lowering Cooldown rate is 70 degrees F per hour and slowly rising "A" OTSG EFlC flow rate 350 gpm "B" OTSG EFlC flow rate 50 gpm The EFIC screen indicates the "A" OTSG level is above the EFlC calculated setpoint.
The EFlC screen indicates the "B" OTSG level is at the EFlC calculated setpoint.
What actions are required by RT-5?
A. Select Reflux Boiling setpoint.
B. Take EFlC Control valves to Vector Override.
C. Take manual control of "A" EFW Control Valve and reduce feed flow.
D. Take manual control of "B" EFW Control Valve and raise to >340 gpm.
Question No. 27 QID: 0348 Given:
A LOCA has occurred ES actuation of channels 1 through 4.
Flow from the "OP" HPI pump is as follows:
300 gpm to "A" HPI line.
65 gpm to "B" HPI line.
85 gpm to "C" HPI line.
95 gpm to "D" HPI line.
RCS pressure is 950 psig.
All valves are in ES actuated position What operator action is required?
A. No action is required since flow is greater than 500 gpm.
B. Close the isolation for the line with the highest flow to stop inventory loss due to a line break.
C. Throttle the "A" HPI valve until "A" line flow is within 20 gpm of "B" line flow to reduce red train inventory loss on a line break.
D. Throttle the "A" HPI valve until "A" line flow is within 20 gpm of "D"line flow to minimize inventory loss on a line break.
Question No. 28 QIB: 0698 Which Reactor Protection System trip function protects the core during a Reactor Coolant Pump coast down and why?
A. Function: Flux / delta Flux / Flow Reason: Assures DNBR is not exceeded.
B. Function: Power to Pumps Reason: Assures DNBR is not exceeded.
C. Function: Flux / delta Flux / Flow Reason: Assures Linear Heat Rate is not exceeded.
D. Function: Power to Pumps Reason: Assures Linear Heat Rate is not exceeded.
Question No. 29 Qi5: 0269 The ATC observes a change in seal injection flow rates and notes the following values:
"A" RCP 8.5 gpm "B" RCP 15.0 gpm "C" RCP 8.0 gpm "D" RCP 8.0 gpm Which of the following explains the seal injection flow indications?
A. Reactor Coolant Pump P-32B trip due to a motor fault.
B. Seal injection line break in the Upper North Piping Penetration Room .
C. Reactor Coolant Pump P-32B seal cooler leak.
D. Seal injection flow transmitter failure.
Question No. 30 QID: 0699 During power operation the CV-1248, "Letdown 3-way Valve" is positioned to BLEED with both the degassifier inlet (CZ-8) and bypass (CZ-9) shut.
What would letdown pressure be and where would flow be going?
A. 100 psig; 1-20, "Dirty Waste Drain Tank."
B. 150 psig; T-20, "Dirty Waste Drain Tank."
- c. 100 p i g ;
T - I 1, "Aux Bldg Equip Drain Tank."
D. 150 psig; T-1 1, "Aux Bldg Equip Drain Tank."
Question No. 31 QID: 0353 In the event of a double-ended break of the RCS cold leg pipe, what is the minimum equipment required to limit peak cladding temperature to less than 2,200 O F ?
A. Two high pressure injection pumps, two low pressure injection pumps, and both core flood tanks.
B. Two high pressure injection pumps, one low pressure injection pump, and both core flood tanks.
C. One high pressure injection pump, two low pressure injection pumps, and both core flood tanks.
D. One high pressure injection pump, one low pressure injection pump, and both core flood tanks.
Given:
Plant is in mode 5, "A" Decay Heat System is in service, RCS is intact, Steam Generators not available, What affect would a loss of Decay Heat Removal have on Reactor Coolant System parameters?
A. RCS temperature lowers, RCS pressure rises, Pressurizer level rises.
B. RCS temperature rises, RCS pressure lowers, Pressurizer level lowers.
C. RCS temperature lowers, RCS pressure lowers, Pressurizer level lowers.
D. RCS temperature rises, RCS pressure rises, Pressurizer level rises.
Question No. 33 QID: 0701 What is the proper alignment to transfer ECCS suction from the Borated Water Storage Tank to the Containment Building Sump per attachment 1 of 1202.010,"ESAS" after verification of RB Sump outlet valves (outside RB) and RB Sump outlet valves (inside RB) open?
A. LPI suctions from BWST(CV-1436 & CV-1437) verify open and BWST outlet valves (CV-1407 & CV-1408) verify closed B. LPI suctions from BWST (CV-1436 & CV-1437) verify closed and BWST outlet valves (CV-1407 & CV-1408) verify open.
C. LPI suctions from BWST (CV-1436 & CV-1437) verify open and BWST outlet valves (CV-1407 & CV-1408) verify open.
D. LPI suctions from BWST (CV-1436 & CV-1437) verify closed and BWST outlet valves (CV-1407 & CV-1408) verify closed.
Question No. 34 QiD: 0702 At what Quench tank pressure would you first expect the Quench tank to relieve to the Containment atmosphere?
A. 80 psig B. 90 psig C. 100 psig D. 110 psig
Question No. 35 QID: 0703 Which of the following is NOT an ICW load?
A. Waste gas compressor aftercooler E-40A,B B. lsophase bus coolers E-l-/A,B.
C. Pressurizer sample cooler E-30.
D. Instrument Air Compressors C-28A,B
Question No. 36 QID: 0524 Given:
Reactor Trip from 80% power.
A malfunction of Rapid Feedwater Reduction (RFR) has caused MFW to overfeed both OTSGs.
All PZR heater banks are in AUTO.
No other operator actions are taken.
Why are the PZR heaters de-energized?
A. The pressurizer spray valve is open.
B. The ERV is open.
C. An insurge from the pressurizer has occurred.
D. An outsurge from the pressurizer has occurred.
Question No. 37 QID: 0131 Given:
Channel "A" of the RPS is currently in channel bypass.
What would result if the channel bypass switch for Channel "B"was placed in the bypass position AND the channel bypass block circuit ction as designed7 A. The RPS would be placed in a 2 out of 2 coincidence log B. Both RPS channels A and B would drop out of bypass.
C. The B channel would be in bypass and the A channel would drop out of bypass.
D. Both RPS channels A and B would trip, resulting in a Reactor Trip.
Question No. 38 QID: 6057 Which of the following would result in all ten (IO) ESAS Digital Channels receiving an Analog Channel Trip signal?
A. Removal of the low RCS Pressure Bistable from Analog Channel 1 B. Removal of the RB Pressure Buffer Amplifier from Analog Channel 1 C. Removal of the 30 psig RB Pressure Bistable from Analog Channel 2.
D. Removal of the RCS Pressure Buffer Amplifier from Analog Channel 2.
Question No. 39 QID: 8704 Which of the following supply power to the Main Chiller Motors?
A. A108 and A208 B. A308 and A408 C. B113 and B713 D. 6112 and 6212
Which of the following supply power to the Containment Spray Motor Operated Valves CV-2400 and CV-2401?
A. B2271 and B3271 B. B6171 and B5171 C. B4171 and B3171 D. B6571 and B5571
Question No. 41 QID: 0706 Given:
Large break LOCA has occurred All 10 Channels of ESAS have actuated Shifted to Reactor Building Sump Recirculation per Attachment 1 of 1202.010, ESAS "A" and "B" Low Pressure Injection flows are 2800 gpm.
High Pressure Injection has been secured.
No Containment Breach The ATC notices LPI pump flows fluctuating.
What must be performed per Attachment 1 of 1202.010, "ESAS" to stop the pump fluctuations?
A. Close CV-1276 and CV-1277 Decay Heat Supply to Makeup Pump Suctions.
B. Override and throttle CV-1400 and CV-1401 LPI Injection Valves to 1050 to 1200 gpm per train.
C. Override and Stop both RB spray pumps AND overide and close CV-2400 and CV-2401 RB Spray Block Valves.
D. Initiate full HPI per RT3 and secure LPI pumps.
Question No. 42 QID: 0707 Given:
Turbine control is in ICs auto.
Generator output is 100 Megawatts.
The turbine bypass valves are full closed.
Turbine header pressure setpoint is 900 psig.
At what pressure will the turbine bypass valves first open?
A. 890 8.910 C. 950 D. 1000
Question No. 43 QID: 0229 Given:
Plant startup in progress with Reactor Power at 5 YO.
Condenser E-I 1A Vacuum Pressure Switch (PS-2850) fails to 0" Hg.
What effect will this have on Turbine Bypass Valve (TBV) and Atmospheric Dump Valve (ADV) operations?
A. All TBVs will remain open, both ADV isolations will open, both ADV control valves will remain closed.
B. Only TBVs for E - I 1A will close, both ADV isolations open,
'A' SG ADV will begin controlling 'A' SG pressure.
C. All TBVs will close, both ADV isolations will open, both ADV control valves control at setpoint D. Only TBVs for E-I 1A will close, both ADV isolations will open, both ADV control valves control at setpoint
nit4 . xa~inat~on Question No. 44 QID: 0708 Given:
Plant is operating at 60% power, "A" and "B" Main Feedwater Pumps (MFP) in service.
What affect will the "B" MFP Hand/Auto station failing to 100% demand have on the "B" MFP?
A. MFP discharge pressure will reduce MFP speed B. MFP will shift to manual demand substitution.
C. MFP will shift to direct governor valve control.
D. MFP will speed up to 5800 RPM.
nit 1 - ritten Exa~ination
~- -
Question No. 45 QID: 5759 Given:
RCPs have been secured, "A" OTSG pressure is 925 psig EFW feed rate is 4"/minute "5" OTSG pressure is 750 psig EFW feed rate is G"/minute What OTSG flow rates should the operator establish for these conditions?
A. "A" OTSG filling at 2"/ minute, "BI OTSG filling at 5"/minute.
C. "A" OTSG filling at 4"/ minute, "B" OTSG filling at G"/minute.
D. "A" OTSG filling at 6"/ minute, "B" OTSG filling at 4"/minute.
~
en inati Question No. 46 QID: 0710 Given:
The EFlC system is automatically feeding the S/Gs to the natural circulation cooldown setpoint.
Which of the following does NOT indicate Primary to Secondary Heat Transfer has been established?
A. T-cold tracking the associated SG T-sat.
B.T-hot / T-cold difference stable or dropping.
C. Delta T-cold between the loops dropping.
D. T-hot tracking CET temperatures.
en Question No. 47 QID: 0711 Given:
Plant recovering from a Blackout.
Startup #I transformer voltage degraded at 18.5 KV.
Busses A I and A3 energized from Startup #I at 3760 V , "Blackout Breaker Alignment and UV Relay Defeat has been performed.
Given these conditions, what are the impacts to the electrical distribution system AND what actions would mitigate these consequences?
A. Impacts: Motors may trip on overload, overheat due to high running currents or stall; Mitigation: No actions are necessary due to the performance of "Blackout Breaker Alignment and UV Relay Defeat."
B. impacts: MCC starters may not pick up to energize loads; Mitigation: Motors should be started one at a time and allowed to reach run speed to minimize further voltage degradation.
C. Impacts: AC Auxiliary relays may not pick up to provide interlock or load energization features; Mitigation: No actions are necessary due to the performance of "Blackout Breaker Alignment and UV Relay Defeat.
E. impacts: LOWsystem vdtqes may result in IOLVmotor ci;rreri:s and low po\;v.er oiitput.
Mitigation: Motors should be started one at a time and allowed to reach run speed to minimize further voltage degradation.
Question No. $8 QID: 0384 Given:
Annunciator K01-D7, "DO1 TROUBLE," is in alarm.
The A 0 reports the local trouble annunciator indicates a DC ground on the positive bus.
Given these conditions, what are the impacts to the DC electrical distribution system and what actions would mitigate these consequences?
A. Impacts: No immediate impact.
Mitigation: Electrical maintenance support is required to determine ground location.
B. Impacts: No immediate impact Mitigation: Transfer D11 to D21 and see if ground is still present on D o l .
C. Impacts: The DC electrical distibution system will short.
Mitigation: Electrical maintenance support is required to determine ground location.
D. Impacts: The DC electrical distibution system will short.
Mitigation: Immediately transfer D l Ito 1321 and see if ground is still present on DO?.
Question No. 49 QID: 0742 Which of the following conditions requires entry into Technical Specification 3.8.4, "DC Systems, Operating?"
A. D03Al "Battery Charger" inoperable and D07, "Battery" operable.
B. D03B, "Battery Charger" inoperable and D04A, "Battery Charger" inoperable.
C. D03AI "Battery Charger" inoperable and D03Bl "Battery Charger" inoperable.
D. D04B, "Battery Charger" inoperable and DOT, "Battery" operable.
Question No. 50 QID: 0713 Given:
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> endurance run surveillance on # I Emergency Diesel Generator is in progress.
- Annunciator KO1-F4, EDG FUEL OIL TROUBLE actuated.
- Diesel Storage Tank levels (T57A and T57B) = 147 inches.
- Fuel Oil Transfer Pump (P16A) discharge pressure = 20 psig.
- T-25 Bulk Storage Tank Level is 5 feet.
- Valve alignment verified correct.
- T-30A #I EDG Fuel Oil Day Tank is at 200 gallons and slowly lowering What is the most likely cause of the alarm?
A. P16A auto start failure.
B. P16A discharge pressure high.
C. T-25 Bulk storage tank level low.
D. In service bulk storage tank filter (F-27) clogged.
Question No. 51 QID: 0089 Given:
- Treated Waste Monitor Tank, T16A, release in progress
- "PROC MONITOR RADIATION HIGH", K10-B2, in alarm
- Liquid Radwaste Process Monitor, Rl-4642, in alarm What should your FIRST action be?
A. Verify no flow on Discharge to Flume, Fl-4642.
B. Trip the running Radwaste Transfer pump, P-53A/B.
C. Close Liquid Waste to Flume valve, CV-4642.
D. Verify proper setting on Rl-4642 per the release permit.
ESAS has actuated on RB pressure alone.
The CRS is in "Overcooling" 1202.003 procedure RT-10 directs you to stop all running RCP's.
Why is this action being performed?
A. No cooling to the RCP motor and seal coolers.
B. Loss of subcooling margin is imminent.
C. RCP seal bleedoff path is isolated.
D. RCP seal injection is isolated.
A Loss of Instrument Air has occurred.
What is the expected position of the Startup (CV-2623 and CV-2673) and Low Load Control Valves (CV-2622 and 2672)?
A. Startups fail closed, Low Loads fail closed.
B. Startups fail closed, Low Loads fail as is.
C. Startups fail as is, Low Loads fail as is D. Startups fail as is, Low Loads fail closed.
Procedure I104.024, "instrument Air System" directs the operator to avoid bypass operation of Air Dryers.
What is the reason for this precaution and what exception applies?
A. Particulates in the air system may affect orifices in control valves; As required by system loading.
B. Moisture in the air system may affect air operated equipment; As directed by the AOP, 1203.024, "Loss of Instrument Air."
C. Entrained oil in the air system may affect control bellows in valve positioners; As directed by the AOP, 1203.024, "Loss of Instrument Air."
D. Moisture in the air system will cause corrsion induced system piping failures; As required by system loading.
Question No. 55 QID: 0716 Given:
Plant power 100%
Rising Reactor Building temperature Slowly rising Reactor Building pressure Rising Reactor Building Dew Point Reactor Building Leak Detector rising activity Per 1203.039, "Excess RCS Leakage", what action addresses these conditions?
A. Initiate Reactor Building Purge.
- 6. Start the Hydrogen Recombiners.
C. Maximize Reactor Building Cooling.
D. Place a second Main Chiller in service.
Given:
Reactor Power is 100%.
The Group 7 Rods average position is 92% withdrawn.
An operator moves the group 6 rod 4 Relative Position Indication (RPI) to 0%
Group 6 has 8 rods.
What is the expected result?
A. Asymmetric rod runback.
B. Asymmetric rod alarm.
C. Out inhibit.
D.Sequence inhibit.
4 -
Given:
Performing RT-12 Emergency Boration Letdown has been maximized Pressurizer Level is 110 inches.
Pressurizer Level Setpoint has been changed to 220 inches.
Pressurizer Level Control Valve CV-1235 is in automatic.
What information is the Pressurizer Level control station indicating when in Measured Variable with the station in Automatic?
A. Proportional/l ntegral output B. Auto/Manual difference C . Analog memory output D. Integral output only
The Gamma Metrics system uses discrimination circuitry to provide accurate indication of source range power levels.
Why is discrimination necessary in source range nuclear instrumentation and what is the result of incorrect discrimination?
A. Discrimination separates out alpha and neutron pulses to provide a true gamma pulse.
With the discrimination set too high power will indicate higher than actual power.
- 6. Discrimination separates out gamma and neutron pulses to provide a true alpha pulse.
With the discrimination set too low, power will indicate higher than actual power.
C. Discrimination separates out gamma and alpha pulses to provide a true neutron pulse.
With the discrimination set too high, power will indicate lower than actual power.
D. Discrimination separates out beta and gamma pulses to provide a true neutron pulse.
With the discriminator set too low, power will indicate lower than actual power.
nit 1 28 xam ination Question No. 59 QID: 0719 What is the purpose and function of the Core Exit Thermocouples (CET)?
A. Provide core outlet temperature distribution and monitor for Reactor Vessel head void formation.
B. Provide input to margin to saturation and input to the RPS high temperature trip.
C. Provide indication of core outlet temperature distribution, and input to margin to saturation.
D. Provide input to the Safety Parameter Display System and the RPS high temperature trip.
Unit 4 -
Question No. 60 QfD: 0723 What are the power supplies to the Hydrogen Recombiners, M-55A and M-558?
A. M-55A B-53; M-55B B-61.
B. M-55A B-6; M-55B B-5.
C. M-55A B-61; M-55B B-53.
D. M-55A B-5; M-55B B-6.
nit 1 - riaen Examinatio Question No. 61 QID: 0720 Given:
- Refueling is in progress.
- A fuel assembly is being moved from the Up-ender to the Reactor Core.
- Source Range channel NI-502 power supply fails.
Which of the following actions is appropriate for these conditions?
A. All refueling operations can continue as long as one Source Range channel is operable.
B. Suspend core alterations and consider placing the assembly in the Fue!
Handling Canal fuel storage rack.
C. Place the fuel assembly in any alternate core location during repairs of NI-502.
D. The fuel assembly must be placed back in its original position in the Spent Fuel Pool.
Question No. 62 QID: 0721 Given:
- Plant at 100% power.
- "A" Main Steam Isolation Valve goes closed.
What is controlling pressure for the "A" Steam Generator?
A. The "A" train Turbine Bypass valves.
B. The Emergency Feedwater Initiation and Control system.
C. The "A" train Main Steam Safety valves.
D. The "A" train Atmospheric Dump Control Valves
Question No. 63 QID: 0108 Given:
Plant Power 90%
A Main Turbine EH control system malfunction causes a spurious OPC actuation.
Which of the following would occur during the transient?
A. RCP seal injection flow would drop.
- 6. PZR spray flow would drop C. PZR makeup flow would drop.
D. FW flow to both OTSGs would rise.
Question No. 64 QID: 0722 Plant Shutdown in Mode 5 for refueling outage Reactor Building pressure is 15.7 psia An approved Reactor Building Purge permit has arrived in Control Room.
You are tasked to start the Reactor Building purge in accordance with the permit With the above conditions, which are the correct actions to start the Reactor building purge?
A. Open RB purge Inlets CV7402 and CV-7404, when RB pressure equals atmospheric pressure, then open RB purge outlets CV-7401 and CV-7403, place RB purge Supply Fan VSF-2 in Auto, start RB purge exhaust fan VEF-15 and verify RB purge supply fan VSF-2 starts.
B. Open RB purge outlets CV-7401 and CV-7 when RB pressure equals atmospheric pressure, then Open RB purge Inlets CV7402 and CV-7404, place RB purge exhaust fan VEF-15 in auto, start RB purge Supply Fan VSF-2, and verify RB purge exhaust fan VEF-15 starts.
C. Open RB purge inlets CV7402 and CV-7404, when RB pressure equals atmospheric pressure, then open RB purge outlets CV-7401 and CV-7403, place RB purge exhaust fan VEF-I5 in auto, start RB purge Supply Fan VSF-2, and verify RB purge exhaust fan VEF-15 starts.
D. Open RB purge outlets CV-7401 and CV-7403, when RB pressure equals atmospheric pressure, then Open RB purge Inlets CV7402 and CV-7404, place RE3 purge Supply Fan VSF-2 in Auto, start RB purge exhaust fan VEF-I5 and verify RB purge supply fan VSF-2 starts.
~ ~ e No.
s 55~ ~ o QID:
~ 0379 During performance of 1305.001, Supplement 6, Area Radiation Monitor Monthly Alarm Check, you discover Relay Room Area Monitor, RI-8002, high alarm setpoint is greater than the maximum allowable value.
What are the required actions?
A. Record the value found, and document set-point drift in Section 3.0 of the surveillence test.
B.Adjust the setpoint to less than or equal to max high alarm setpoint before recording the As-Left Setpoint.
C. Record the value found, then have I&C make the required adjustment under a "blanket" Work Order.
D. Record the value found and continue, nothing eise needs to be done since RI-8002 is not a Tech Spec required monitor.
Question No. 66 QID: 0389 Given:
-A job is in progress that will last for several weeks.
-The procedure has been verified at the start of the job.
-A pre-job brief has been completed for all participants.
How often should the procedure for this job be verified current and what source is used?
A. Once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, eB change number.
B. Once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the work order reference.
C. Prior to each use, eB change number D. Prior to each use, the work order reference.
-2 ritten Exan?in ation
__ -~
uestiom No. 57 QID: 0245 The feedwaterkondensate system startup is in progress.
A main feedwater isolation valve had been closed by operation of the manual handwheel to isolate the system.
Prior to declaring this valve operable, what action must be taken?
A. The valve must be fully opened using the local handwheel.
B. Electricians must check the torque switch adjustment.
C. The measured torque value required to remove the valve from its seat is verified below the limit.
D. The valve must be stroked electrically to confirm proper clutch engagement.
Question No. E8 QID: 072.45 What information source is used to determine the correct "At Power" configuration of plant equipment?
A. Piping and Instrument Diagrams.
B. Line-up section of the System Procedure.
C. Work Order Instructions.
D. Component Database of the lndus system.
Question No. 69 QID: 0725 In the Protective Tagging process, who ensures that all compensatory measures listed on the tagout are performed?
A. Operations Manager.
B. Tagout Preparer C. Tagout Reviewer.
D. Operations Supervisor.
Question No. 70 QID: 0481 During a Refueling outage, who is responsible for tracking a Delayed Post Maintenance Test identified as an Operability Restraint in accordance with "Control of Post -Maintenance testing" 1025.033?
A. Outage Desk.
B. PMT Coordinator C. Work Week Manager.
D. Responsible shop (e.g., Electrical).
Question No. 71 QID: 0751 Which of the following exposure limits are Entergy's Routine Annual Administrative Guidelines?
A. TEDE 2000 mrem per year, SDE, WB= 40 rem, and LDE= 12 rem B. TEDE 5000 mrem per year, SDE, WB= 40 rem, LDE= 12 rem C. TEDE 5000 mrem per year, SDE, WB= 50 rem, LDE= 15 rem D. TEDE 2000 mrem per year, SDE, WB= 50 rem, LDE= 15 rem
Given:
Unit is at 100% Power, Received Annunciator K10-B2, "PROC MONITOR RADIATION HI" Upon investigation you discover "RB Atmos Gaseous Monitor Rl-7461 in Radiation High alarm and slowly rising.
What action is required for this alarm in accordance with "Annunciator K10 Corrective Action" 1203.0121?
A. Have Radiation Protection perform an air sample.
- 6. Perform 1103.013, "RCS Leak Detection."
C. Adjust Rl-7461 alarms setpoint per 1305.001 Sup 5 D. Commence plant shutdown per 1203.045, "Rapid Plant Shutdown."
Question No. 73 QID: 0025 The following plant conditions existed just prior to an automatic reactor trip:
- Reactor power at 50%
- Loss of Bus H-I due to an electrical fault
- "B" Main Feedwater Pump tripped
- Condenser vacuum at 23.5 inches Hg
- RCS pressure at 1950 psig Which of the following was the cause of the automatic reactor trip?
A. Main Turbine Anticipatory trip.
B. Pawer to Pumps trip.
C. Variable Low Pressure trip D. Main Feedwater Anticipatory trip
Question No. 74 QID: 0728 Which of the following indicates proper Emergency Feedwater operation?
A. All RCPs off and SG level stable at 32".
B. All RCPs on and SG level stable at 45" with EFW control valves open.
C. "A" SG 580 psig, "B" SG 800 psig, and EFW feeding both SGs.
D. Both SG pressures 580 psig, with levels of 28" and EFW feeding both SGs.
Question No. 75 QID: 0726 Which of the following RCS parameters would require manual trip of the Reactor?
A. Reactor Building pressure 19.7 psia.
B. Pressurizer level 105 inches and lowering.
C. RCS Hot Leg Temperature 614 O F D. Reactor Coolant System Pressure 1850 psig.
ritten Exarninatjon Question No. 76 QID: 0741 Given:
- Plant Power 48%
- Low Pressure Turbine Boot fails causing vacuum to rapidly fall to 24 inHg.
Which procedure should be used to stabilize the plant?
A. 1203.016, "Loss of Condenser Vacuum."
B. 1203.045, "Rapid Plant Shutdown."
C. 1203.012D, "K05-B3 Vacuum Pump Auto-start ACA.
D. 1202.001, "Reactor Trip."
Question No. 79 QID: 0729 Given:
Plant Power 40%,
I&C performing "Unit 1 DROPS Trip Test" per 1304.178, I&C accidentally causes an AMSAC trip, resulting in a Main Turbine Trip, EFW did not respond as required due to "A" and "D" Emergency Feedwater Initiation Channels being inoperable.
What is the most limiting action required per Technical Specifications?
A. Restore one channel to an operable status.
B. Place the plant in mode 3.
6 . Place one channel in bypass and a second in trip.
D. Place the plant in mode 4
ritten ~ x a ~ ~ n a t ~ o n Question No. 78 QID: 0731 Given:
Plant transient excessive overcooling has occurred, Which of the conditions below would have invoked PTS limits AND violate Technical Specification limits?
A. A cooldown resulting in a step change of 51F in 10 minutes with Tcold at 360F.
B. A cooldown rate of 9OF/hr with Tcold at 290F.
C. A cooldown resulting in a step change of 2EF in 10 minutes with Tcold at 279F D. A cooldown rate of 7 7 OFlhr with Tcold at 330F.
Question No. 79 QID: 07332 Reference Provided Given:
The plant is operating at 100% power.
PZR level transmitter LT-1002 is out of service for calibration, A loss of power occurs to Vital AC Bus RS-1 to PZR level transmitter LT-1001.
1203.015, "Pressurizer System Failure" AOP has been entered due to a loss of pressurizer level control.
Which of the following actions are required by Technical Specification 3.3.15 and Table 3.3.15-I?
A. Restore one channel to operable status within 30 days.
B. Initiate actions to submit a special report immediately.
C. Restore one channel to operable status within 30 days or be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in Mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D. Restore one channel to operable status within 7 days or be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in Mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
nit 1 280 xa~ination Question No. 80 QiD: 0733 Given:
Reactor tripped 4 minutes ago, All four RCP are running, T-hot 590 degrees and rising, RCS pressure 2000 psig, A&B OTSG pressures at 900 psig, A&B OTSG levels at 32 inches and lowering, The following Annunciators were received:
- K12-A5, "EFW Actuation Signal"
- K12-B5, "P-7A Turbine Trip"
- K02-B6, "A3 L.O. Relay Trip" Considering current plant conditions and alarms, which of the following procedures should be used to mitigate this event?
A. Loss of Subcooling Margin (I 202.002)
B. Overheating (1202.004)
C. Inadequate Core Cooling (1202.005)
D. Reactor Trip (1202.001)
N ritten Exa~ination Question No. 81 QID: 0734 Given:
Severe Thunderstorms are resulting in changing Main Generator parameters, Investigation finds the output current to be exceeding the Generator Capability Curve, Annunciator K04-B6, "Generator H2 Temp High" alarms, Temperature recorder TR-9001 point 13 (delta T) is in alarm, Generator H2 Condition Monitor AI-9002 output is reading 0.2, Which of the following procedures should be used for this event?
A. "Main Generator Winding Trouble", 1203.045.
B. "Generator Capability Curve" 1102.004 Attachment "N".
C. "Generator Field Overcurrent" 1203.012C K04-B7.
D. "Generator Hydrogen System", 1106.002 Exhibit "A".
ritten ~xamination Question No. 82 QIB: 0735 Given:
100% power, ICs in manual, Turbine in Integrated control, Loss of Condenser Vacuum in progress, Assuming no Operator actions, which of the following Technical Specification required Core Operating Limits will be challenged FIRST?
,A. Nuclear Overpower trip.
B. Reactor Coolant Pressure trip.
C. Reactor Coolant High Temperature trip.
D. RCS Flow / Axial Power / Imbalance trip.
Question No. 83 BID: 0736 Given:
- Reactor at 100% power.
- Failed fuel ratio, as indicated by the WCO logs, has dropped by 50%.
According to ? , Reactor power must be reduced to ? power A. 1203.045 Rapid Plant Shutdown 50%
B. 1203.0 19 High Activity In Reactor Coolant 50%
- 6. 1203.045 Rapid Plant Shutdown 60%
D. 1203.019 High Activity In Reactor Coolant 60%
Question No. 84 QID: 0421 Given:
Rx trip has occurred and one minute later the following conditions are observed:
- RCS pressure is stable 1700 psig.
- CET average temperature is 600 degrees F.
Which Emergency Operating Procedure should be used to mitigate this event?
A. Loss of Subcooling Margin (1202.002)
B. ESAS (1202.010)
C. Overheating (1202.004)
D. Inadequate Core Cooling (1202.005
Question No. 85 QID: 0737 Given:
Reactor Trip due to Degraded Power condition, "B" OTSG is dry, Plant is cooling down via Natural Circulation on " A OTSG, Tube to Shell delta T is 110 F tubes colder, Subcooling Margin is adequate.
Which procedural action is correct for this condition?
A. Reduce cooldown rate per 1203.013, "Natural Circulation Cooldown."
B. Establish 40-60 F Tube to Shell delta T per 1203.013, "Natural Circulation Cooldown."
C. Reduce cooldown rate per 1202.007, "Degraded Power."
D. Establish 40-60 F Tube to Shell delta T per 1202.007, "Degraded Power."
Question No. 86 QID: 0738 Given:
100% Power,
" A RCP seal bleed off temperature 30 F above 1st stage seal temp, "A" RCP motor bearing temperature 195 F and rising slowly, "A" RCP motor inboard vibration alert alarm, "A RCP seal cavity pressure oscillations of 450 psia peak to peak.
What is the appropriate action and section of 1203.031, "Reactor Coolant Pump and Motor Emergency" which will mitigate the consequences of these malfunctions?
A.Reduce reactor power to within the capacity of unaffected RCP combination and trip the pump per Section 1, "Seal Degradation."
B. Trip the Reactor and trip the affected pump per Section 1, "Seal Degradation."
C. Reduce reactor power to within the capacity of unaffected RCP combination and trip the pump per Section 5, "Motor / Bearing Trouble."
D. Trip the Reactor and trip the affected pump per Section 5, "Motor I Bearing Trouble."
Question No. 83 QID: 0603 Given:
- P-36A is the in-service Makeup Pump.
- Pressurizer level has dropped from 220" to 218" in 10 minutes.
- P-36A suction pressure is 40 psig and going down slowly.
- Makeup Tank level is 78" and trending down slowly.
- Seal Injection flow is oscillating from 38 to 43 gpm.
- MU-34D HPI temperature TE-1069A is reading 255°F.
- Aux. Building sump level is going up.
Considering the above conditions, which procedure will direct the Makeup Pump to be secured?
A. 1203.039, Excess RCS Leakage B. 1203.026, Loss of Reactor Coolant Makeup, Section 1 - Loss of HPI Pump C. 1203.026, Loss of Reactor Coolant Makeup, Section 2 - Large Makeup and Purification System Leak D. 1203.032, HPI Line Temperature High
Question No. 88 QID: 0730 Given:
- A reactor trip has occurred.
- Reactor Building pressure is 5 psig.
- RCS pressure is 1580 psig,
- RCS T-cold is 542 degrees F,
- "A" OTSG pressure is 910 psig,
- "B" OTSG pressure is 970 psig,
- "A." OTSG level is 60 inches,
- "B" OTSG level is 30 inches, Which emergency operating procedure should be used for this event?
A. ESAS 'l202.010 B. Overcooling 1202.003 C. Tube Rupture 1202.006 D. Loss of Subcooling Margin 1202.002
ritten ~ x a ~ ~ n a t ~ o n Question No. 89 QID: 0739 Given:
- A Large break LOCA has been in progress for 2 minutes.
- RCS pressure at 300 psig.
- RB pressure is 34 psig and rising.
- Annunciator RB SPRAY P35A ES FAILURE, is in alarm.
Which condition caused the alarm and which procedure will be used?
A. P35A spray pump has a high motor winding temperature >300 degrees F; 1203.012G, "K08-C6 RB SPRAY P35A ES FAILURE."
B. P35A spray flow is less than 1050gpm 55 seconds after ES channel actuation; 1203.012J, "KI 1-C6 RB SPRAY P35A ES FAILURE."
C. P35A spray pump has a high motor winding temperature >300 degrees F; 1203.012J, "KI 1-C6 RB SPRAY P35A ES FAILURE."
D. P35A spray flow is less than 1050gpm 55 seconds after ES channel actuation; 1203.012G, "K08-C6 RB SPRAY P35A ES FAILURE."
Question No. 90 QID: 0740 Given:
- Unit Tripped on loss of DO1
- EFW has actuated What is the status of EFW control valve CV-2646, "P7B to A OTSG" and EFW control valve CV-2648, "P7A to B OTSG"; and which procedure should FIRST be used to address the EFW system?
A. Valves closed; 1202.003, "Overcooling" B. Valves closed; 1203.036, "Loss of 125 V DC" C. Valves open; 1202.003, "Overcooling" D.Valves open; 1203.036, "Loss of 125 V D C
Question No. 91 QID: 0742 Given:
- Degraded Power
- Natural Circulation Cooldown in progress
- Pressurizer and Spray fluid delta T is 500 F.
- It has been suggested that Aux Spray be used to lower RCS pressure When may the SRO approve the use of Aux Spray per 1203.013, "Natural Circulation Cooldown?"
A. Needed to protect the public safety.
B. It is not allowed at this differential temperature.
C. Aux spray may be used at any time.
D. Only after an Engineering evaluation has been performed.
Question No. 92 QID: 0743 Given:
Plant at NOP NOT All Rods Latched in preparation for plant startup.
Intermediate range channel 3 (N1505) is reading 1 E-I 1 amps.
intermediate range channel 4 (N1506) is reading 1 E-11 amps.
I&C report both Source Range Nuclear Instruments are inoperable.
Which is the most limiting action required per Technical Specification 3.3.9?
A. Open control rod drive trip breakers.
B. Restore the required source range channel to operable status.
C. Place reactor in mode 4.
D. Suspend operations involving positive reactivity changes.
Question No. 93 QID: 0744 Given:
Plant power 100%
TE-1014 "A" Loop Narrow Range T-hot INSTANTLY fails low What procedure should be used for this condition?
A. 1203.001, "ICs Abnormal Operation"
- 6. 1203.012F, "SASS Mismatch" ACA C. 1202.001 "Reactor Trip" D. 1105.006, "Reactor Coolant System NNI"
Question No. 94 QID: 0745 Per Unit 1 Technical Specifications section 5 and OM-I 23, "Working Hour Limits," which of the following overtime conditions is allowed without prior management approval?
A. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> of work including 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> turnover.
B. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of work including 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of turnover within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> of work including 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of turnover within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, D. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> of work including 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of turnover within one week
Question No. 95 QID: 0746 You are the SRO in Charge of Fuel Handling and a fuel assembly is being removed from the core.
What is the implication of the Fuel Load Cell reading 2600 pounds, and what actions are required if any?
A. The fuel assembly is improperly grappled; you must stop fuel handling and repair grapple mechanism .
B. The fuel assembly may be hung up on a grid strap; you must lower fuel assembly to relieve overload and slowly bump fuel assembly in 114 inch steps until grid interface is passed C. The fuel assembly cannot be moved in fast speed; continue with fuel handling using jog speed.
D. No problern exists this is within the allowed weight tolerance; continue fuel handling.
Question No. 96 QID: 0747 Given:
20:OO Thursday Evening, You are the Shift Manager, You receive a report that the Train Bay handrail on the Turbine Deck is missing, Per EN-WM-100, "Work Request (WR) Generation, Screening and Classification,"
which work order process should be used to immediately correct this condition.
A. Priority One Work Order
- 5. Priority Two Work Order C. Priority Three Work Order D. Expedited Work Order
Question No. 97 QID: 0748 Given:
LOCA has occurred; with 5% failed fuel.
EOF, TSC, and OSC have been activated and are operational CV-1221, Letdown Cooler Outlet valve, failed to close, causing an offsite release due to a downstream break.
Projected dose rates will exceed PA guidelines at site boundary in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if leak continues.
The OSC is dispatching a Repair Team of volunteers to attempt close CV-1221.
What is the maximum dose each member of the team is allowed to receive and whose authorization is required?
A. Planned dose shall not exceed 5 Rem TED with RPM authorization.
B. Planned dose shall not exceed 10 Rem TEDE with OSC Director's authorization.
C. Planned dose shall not exceed 25 Rem TED with TSC Director's authorization.
D. Planned dose shall not exceed 50 Rem TEDE with EOF Director's authorization.
Question No. 98 QID: 0949 Given:
- Plant shutdown and cool down in progress
- RCS Tave 145°F
- RB Purge in progress to lower RB atmospheric activity
- RB Purge projected release duration is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
- RB Purge release commenced one (1) hour ago
- Nuclear Chemistry stated gaseous releases projected to exceed quarterly limits by 30%
- Release report preliminary release rate 1.8 E4 cfm
- Design flow rate I.38 E4 cfm to 2.06 E4 cfm Which of the following would violate the RB Purge permit and require RB Purge termination?
A. Actual (stable) RB purge flow rate of 1.5 E4 cfm.
B. RB Atmosphere Gaseous Detector slowly trending upward.
C. SPING Ichannel 5 two-minute average value exceeds set point.
D. Loss of Decay Heat Removal results in RCS temperature at 185°F
a -
it 1 200 xa rni n ation Question No. 99 QID: 0520 The plant is operating at 100% power when the ATC reports a loss of all ICs power as indicated by the ICs lntrument Power Supply status lights on C13 OFF and a loss of all HAND and AUTO lights on ICs HIA stations.
The CRS has entered AOP 1203.001, ICs Abnormal Operations.
Which procedure should be used in conjunction with this AOP?
A. 1203.047, Loss of NNI Power B. 1202.003, Qverccoiing C. 1202.001, Reactor Trip D. 1203.027, Loss of Steam Generator Feed
nit 4 -
Question No. I 0 0 QID: 0750 Given:
- Severe Fire in Corridor 98 on Unit 1
- Reactor has been tripped As CRS what task would you direct the Outside A 0 to perform and what procedural guidance would be used to perform the this task?
A. Fire fighting tasks per "Fire or Explosion" procedure 2203.034.
B. Securing Polishers per "Reactor Triploutage Recovery" procedure 1 102.006.
C. Placing the Startup Boiler in service per "Startup Boiler Operation" procedure I 106.022.
D. Verifying all RCP breakers stay open per "Fires in Areas Affecting Safe Shutdown" procedure 1203.049