ML20106F099
| ML20106F099 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/14/2020 |
| From: | NRC Region 1 |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML20106F099 (120) | |
Text
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: 3/18/2020 Facility/Unit SQN Region: I II X III IV Reactor Type: W X CE BW GE Start Time: Finish Time:
Instructions 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 percent overall, with 70 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 percent to pass.
You have 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-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-only portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results RO/SRO-Only/Total Examination Values ______ / ______ / ______ Points Applicants Score ______ / ______ / ______ Points Applicants Grade ______ / ______ / ______ Percent ES-401, Page 50 of 52
SQN ILT 2003 NRC Exam NAME:________________
- 1. Given the following:
- Unit 1 is at 70% power Subsequently,
- Main Condenser pressure increased to 7 psia
- Reactor was manually tripped per AOP-S.02, "Loss of Condenser Vacuum"
- Tave is stable at 545F Which one of the following completes the statements below?
MFPs (1) automatically trip.
RCS cooldown will be using (2) .
(1) (2)
A. will S/G ARVs B. will Steam Dumps C. will NOT S/G ARVs D. will NOT Steam Dumps 1
- 2. Given the following:
- "A" train Safety Injection pump is tagged out Subsequently
- Safety Injection occurs
- RCS pressure is 1220 psig and lowering
- Pressurizer level is rising
- "B" train SI pump trips immediately after starting
- The crew entered E-1, "Loss of Reactor or Secondary Coolant" and is performing Step 7, CHECK SI Termination Criteria.
Which one of the following completes the statements below?
The RCS leak location is (1) .
Safety Injection termination criteria (2) met.
(1) (2)
A. Pressurizer safety valve is B. Pressurizer safety valve is NOT C. Pressurizer heater well is D. Pressurizer heater well is NOT 2
- 3. Given the following:
- ES-1.3 "Transfer to RHR Containment Sump" is in progress
- Both RHR Pumps are running aligned to the Containment Sump
- The CCP and SI Pump suctions from the RWST have been isolated
- RWST level is 20%
- EA-63-2 "Refilling RWST" is in progress Subsequently,
Which one of the following completes the statements below?
CCPIT Inlet Flow (1) greater than 0 gpm.
In accordance with ES-1.3 the required action is to (2) .
A. (1) is (2) ensure 1B-B CCP and 1B-B SI Pumps are running and then place the 1A-A CCP and 1A-A SI Pumps control switches to the pull-to-lock (P-T-L) position B. (1) is (2) ensure the CCP and SI pump suctions are realigned to the RWST C. (1) is NOT (2) ensure 1B-B CCP and 1B-B SI Pumps are running and then place the 1A-A CCP and 1A-A SI Pumps control switches to the pull-to-lock (P-T-L) position D. (1) is NOT (2) ensure the CCP and SI pump suctions are realigned to the RWST 3
- 4. Given the following:
- Unit 1 is at 15% power
- AOP-R.04 "Reactor Coolant Pump Malfunctions" was entered due to RCP #1 Seal Temperature Which one of the following completes the statements below?
The P-8 LOW POWER LOW FLOW TRIP BLOCKED annunciator (Bypass and Permissive 1-XA-55-4A) (1) LIT for current plant conditions.
In accordance with AOP-R.04 the reactor (2) required to be tripped before the #1 RCP.
(1) (2)
A. is is B. is is NOT C. is NOT is D. is NOT is NOT 4
- 5. Given the following:
- Unit 2 is at 100% power
- The crew entered AOP-M.09, "Loss of Charging"
- The crew is re-establishing charging flow in accordance with EA-62-5, "Establishing Normal Charging and Letdown" Section 4.2 Establishing Charging flow
- RCP seal injection flows are as follows:
- 1 #2 #3 #4 9.2 gpm 10.5 gpm 11.9 gpm 13.4 gpm Which one of the following identifies the adjustment needed to 2-FCV-62-89, "Seal Water FCV" and the effect it will have on charging flow through the Regen Heat Exchanger?
2-FCV-62-89 needs Charging Flow to the to be throttled Regen Heat Exchanger WILL A. OPEN Increase B. OPEN Decrease C. CLOSED Increase D. CLOSED Decrease 5
- 6. Given the following:
- Both Units are at 100% power Which one of the following identifies...
(1) a condition that will cause CCS Train B flow/pressure to lower on BOTH units and (2) whether a Unit 2 manual reactor trip is required in accordance with AOP-M.03 "Loss of Component Cooling Water" if the Train B flow/pressure cannot be restored A. (1) Loss of 480v Shutdown Board 1A2-A (2) Reactor Trip is required B. (1) Loss of 480v Shutdown Board 1A2-A (2) Reactor Trip is NOT required C. (1) Loss of 480v Shutdown Board 2B2-B (2) Reactor Trip is required D. (1) Loss of 480v Shutdown Board 2B2-B (2) Reactor Trip is NOT required 6
- 7. Given the following:
- Unit 1 was operating at 50% power Subsequently,
- A steam line rupture occurred in containment
- FR-S.1, "Nuclear Power Generation / ATWS was entered when the reactor failed to trip
- Control rods are being inserted manually
- All PRMs are 20% and decreasing
- Phase B isolation has occurred Which one of the following completes the statements below?
In accordance with FR-S.1 RCPs (1) required to be secured immediately.
In accordance with EPM-3-FR-S.1"Basis Document for FR-S.1 Nuclear Power Generation/ATWS" the basis for this is (2) .
(1) (2)
A. are because support conditions have been lost B. are NOT because it could result in reduced heat removal and challenge fuel integrity C. are because of the positive reactivity addition from the RCP core cooling D. are NOT because the heat input from RCPs is adding negative reactivity 7
- 8. Given the following:
- Unit 1 operating at 100% power
- A steam line break downstream of the #3 S/G MSIV occurred
- All MSIVs failed to close and ECA-2.1, "Uncontrolled Depressurization of All Steam Generators" was entered
- EA-1-1, "Closing MSIVs Locally" is complete and 125v control power fuses have been removed
- Safety Injection termination is NOT in progress Which one of the following completes the statement below?
MSIV Valve position (1) available on 6K/6L Panels at 1-M-6 and ECA-2.1 Foldout Page transition to E-2, Faulted Steam Generator Isolation is based on (2) .
(1) (2)
A. remains S/G Pressure B. remains RCS Temperature C. does NOT remain S/G Pressure D. does NOT remain RCS Temperature 8
- 9. Given the following:
- Unit 1 is at 35% power during a plant startup.
- 1A MFW pump is in service.
- The "MFPT B RESET/TRIP" handswitch on 1-M-3 has the Green light LIT.
Subsequently, the 1A MFW pump trips.
Which one of the following identifies:
(1) the earliest time that the TDAFW Pump will auto-start and (2) the normal source of the cooling water to the TDAFW pump bearing oil cooler?
A. (1) at the time the 1A MFP tripped (2) a stage on the TDAFW pump B. (1) at the time the 1A MFP tripped (2) the ERCW system C. (1) at the time when SG level lowered to the auto-start setpoint (2) a stage on the TDAFW pump D. (1) at the time when SG level lowered to the auto-start setpoint (2) the ERCW system 9
- 10. Given the following:
- A Loss of Offsite Power and Reactor Trip occurred on Unit 1.
- Natural Circulation conditions are being verified in accordance with EA-68-6, "Monitoring Natural Circulation Conditions."
Which one of the following identifies conditions where natural circulation exists?
A. Core exit T/Cs equal to Tcold. Core exit T/Cs at saturation temperature for the S/G pressure.
B. Core exit T/Cs equal to Tcold. Tcold at saturation temperature for the S/G pressure.
C. Core exit T/Cs stable. Core exit T/Cs at saturation temperature for the S/G pressure.
D. Core exit T/Cs stable. Tcold at saturation temperature for the S/G pressure.
10
- 11. Given the following:
- Station Blackout has occurred
- Both Units have entered ECA-0.0 "Loss of All AC Power"
- Offsite Power is being restored using AOP-P.01 Attachment 1 Which one of the following completes the statement below?
In accordance with AOP-P.01 "Loss of Offsite Power" the designated source for restoring off-site power is the (1) line and this line is (2) .
(1) (2)
A. Hiwassee 1 161Kv B. Hiwassee 1 500Kv C. Chickamauga 1 161Kv D. Chickamauga 1 500Kv 11
- 12. Given the following:
- Both Units are at 100% power
- 125V DC Vital Battery Board IV is inadvertently deenergized Which one of the following completes the statements below?
(1) Diesel Generator(s) will auto-start.
In accordance with AOP-P.02 "Loss of 125V DC Vital Battery Board" the 2B-B EDG (2) be shutdown using the EMERGENCY STOP pushbutton on 0-M-26.
(1) (2)
A. Only one can B. Only one can NOT C. All four can D. All four can NOT 12
- 13. In accordance with AOP-M.01 "Loss of Essential Raw Cooling Water, Section 2.5 ERCW Supply Header 2A Rupture in Aux Building", which one of the following completes the statements below?
Unit 2 Train A CCP and SI Pump may experience bearing failure (1) after a loss of ERCW cooling.
The REACTOR COOLANT PUMPS MOTOR THRUST BEARING TEMP HIGH annunciator is required to be monitored on (2) .
(1) (2)
A. 10 minutes both Units B. 10 minutes Unit 2 ONLY C. 15 minutes both Units D. 15 minutes Unit 2 ONLY 13
- 14. Which one of the following completes the statements below?
In accordance with AOP M.02 "Loss of Control Air" 0-FCV-32-82 "Train A Control Air Supply" and 0-FCV-32-85 "Train B Control Air Supply" will close first as pressure reaches a setpoint of (1) and lowering in the Station Control & Service Air System.
The reason for this isolation is to (2) .
(1) (2)
A. 50 psig ensure control air is provided to the essential components for safe shutdown B. 50 psig prevent exceeding containment design pressure in the event of a design bases accident with an air leak is inside containment C. 69 psig ensure control air is provided to the essential components for safe shutdown D. 69 psig prevent exceeding containment design pressure in the event of a design bases accident with an air leak is inside containment 14
- 15. Given the following:
- Unit 1 is at 75%
- CRO reports Grid Frequency is 59.6 Hz Which one of the following completes the statements below?
In accordance with AOP-P.07 Degraded Grid or Abnormal Voltage Conditions the 6.9 kV SDBDs (1) required to be transferred to the DGs and The basis for the 58 Hz frequency trigger value that requires a manual reactor trip is (2) .
(1) (2)
A. are imminent automatic underfrequency trip B. are 25% of lifetime limit for off-frequency operation of LP turbine C. are NOT imminent automatic underfrequency trip D. are NOT 25% of lifetime limit for off-frequency operation of LP turbine 15
- 16. Given the following:
- Unit 1 was at 100% power
- A reactor trip and SI occurred due to a LOCA outside containment
- The crew has entered ECA-1.2 "LOCA Outside Containment" Which one of the following completes the statements below?
FCV-62-69 Letdown Isol Loop 3, (1) auto close from the SI signal.
In accordance with ECA-1.2 "LOCA Outside Containment" step 2 "ATTEMPT to isolate break from RCS" the operator is required to close the RHR (2) leg injection valve.
(1) (2)
A. will hot B. will cold C. will NOT hot D. will NOT cold 16
- 17. Given the following:
- The Crew has entered FR-H.1, "Loss of Secondary Heat Sink," due to a loss of inventory in the S/Gs and failure of the AFW pumps to start.
- A low pressure feed source from ERCW or HPFP has NOT been established.
Time: 0800 0810 0820 0830 S/G #1 WR (%) 41 33 28 23 S/G #2 WR (%) 39 32 20 19 S/G #3 WR (%) 46 42 31 19 S/G #4 WR (%) 37 28 19 16 o
Core Exit T/Cs ( F) 548 549 550 551 Cont. Press. (psid) 1.70 2.40 2.70 2.50 Which one of the following is the earliest time that the initiation of RCS Feed and Bleed is required?
A. 0800 B. 0810 C. 0820 D. 0830 17
- 18. Given the following:
- Unit 2 was operating at 100% power when a LOCA occurred.
- ES-1.3 "Transfer to RHR Containment Sump" has been completed
- ECA-1.3 "Containment Sump Blockage" was just entered
- 'B' Train pumps are in PULL TO LOCK
- 'A' train CCP, SI, RHR, and Containment Spray pumps are running and have all have indications of cavitation In accordance with ECA-1.3 which one of the following is an allowable sequence to secure 'A' Train pumps?
A. Containment Spray, RHR, SI, CCP B. RHR, SI, Containment Spray, CCP C. CCP, Containment Spray, RHR, SI D. SI, CCP, Containment Spray, RHR 18
- 19. Given the following:
- The unit is at 85% power
- Rod Control is in MAN
- A continuous uncontrolled Control Bank D rod withdrawal occurs Which one of the following completes the statements below?
In accordance with AOP-C.01 " Rod Control Malfunctions" the OATC (1) required to place Rod Control in AUTO and CHECK rod motion stopped.
If Rod motion stopped with reactor power at 98%, with no operator action, reactor power will stabilize at (2) .
(1) (2)
A. is ~85%
B. is ~98%
C. is NOT ~85%
D. is NOT ~98%
19
- 20. Given the following:
- Unit 2 was tripped from 100% power.
- The crew is performing ES-0.2 "Natural Circulation Cooldown."
- All steps have been completed up to Step 13,MAINTAIN the following RCS conditions.
- At time 18:00 the following plant conditions existed:
- Core exit T/Cs = 520°F
- RCS pressure = 1600 psig Subsequently, a PZR PORV failed OPEN.
- At time 18:15 the following plant conditions are observed :
- Core exit T/Cs remain at 520°F.
- RCS pressure is 800 psig and stable.
- PZR level is 70% and rising rapidly.
Which one of the following completes the statements below at time 18:15?
In accordance with ES-0.2 Foldout page a transition to E-0, Reactor Trip or Safety Injection (1) required.
PZR level is rapidly rising is due to (2) .
A. (1) is (2) an automatic Safety Injection actuation B. (1) is (2) drawing a bubble in the reactor vessel head C. (1) is NOT (2) an automatic Safety Injection actuation D. (1) is NOT (2) drawing a bubble in the reactor vessel head 20
- 21. Given the following:
- Unit 1 is at 40% power
- Two Condenser Vacuum Pumps are running Subsequently,
- Condenser pressure is 2.5 psia
- AOP-S.02, "Loss of Condenser Vacuum" was entered Which one of the following completes the statements below?
The third Condenser Vacuum Pump (1) be running.
In accordance with AOP-S.06, "Turbine Trip Below P-9 (50% Power)" if a turbine trip subsequently occurs, and C-9 Condenser Interlock is LIT, control rods are required be positioned to _(2)_.
A. (1) will (2) stabilize power with Tave = 547°F B. (1) will (2) stabilize power at approximately 13 -15%
C. (1) will NOT (2) stabilize power with Tave = 547°F D. (1) will NOT (2) stabilize power at approximately 13 -15%
21
- 22. Given the following:
- Both Units are at 100% power
- The following alarm is received:
RA-90-1A AUX BLDG AREA RAD MON HIGH RAD (0-M-12-A, A-7)
Subsequently, the following alarm is received:
RA-90-101A AUX BLDG VENT MONITOR HI RAD (0-M-12-B, B-1)
- No other rad monitors are in alarm.
Which one of the following completes the statements below?
The cause of the alarms is (1) .
0-AR-M12-B, B-1 Annunciator Response Procedure, (2) contain steps to check that automatic actions have occurred.
(1) (2)
A. Gas Decay Tank relief valve fails open does B. Gas Decay Tank relief valve fails open does NOT C. Gas Decay Tank pressure indicator sensing line breaks does D. Gas Decay Tank pressure indicator sensing line breaks does NOT 22
- 23. Given the following:
- Both Units are at 100%
- A fire in the Control Building requires evacuating the Main Control Room In accordance with AOP-C.04 "Shutdown from Auxiliary Control Room" which one of the following completes the statements below?
PRIOR to the reactor being tripped...
the OATC (1) dispatched outside the MCR and following the reactor trip the next action in the MCR is to (2) .
A. is ENSURE MSIV and MSIV bypass valve handswitches to CLOSE B. is RCP handswitches in STOP/PULL TO LOCK C. is NOT ENSURE MSIV and MSIV bypass valve handswitches to CLOSE D. is NOT RCP handswitches in STOP/PULL TO LOCK 23
- 24. Given the following:
- Unit 2 is at 100% power
- AOP-R.06 "High RCS Activity" is in progress Which of the following completes the sentences below?
AOP-R.06 "High RCS Activity" directs monitoring (1) .
LCO 3.4.16 "RCS Specific Activity" is applicable in Modes (2) .
A. (1) 2-RR-90-1A AUX BLDG AREA RAD MON (2) 1-4 B. (1) 2-RR-90-1A AUX BLDG AREA RAD MON (2) 1-5 C. (1) 0-RE-90-101B AUX BLDG VENT RADMON-TOTAL GAS (2) 1-4 D. (1) 0-RE-90-101B AUX BLDG VENT RADMON-TOTAL GAS (2) 1-5 24
- 25. Following a large steam line rupture, monitoring of Critical Safety Function Status Trees indicates a RED path for Pressurized Thermal Shock.
In accordance with EPM-3-FR-P.1 "Basis Document for FR-P.1 "Pressurized Thermal Shock" which one of the statements below identifies the limiting component and reason for the concern?
Limiting Component Reason for Concern A. Pressurizer Increased stresses resulting from a rapid depressurization condition at high temperature.
B. Pressurizer Increased stresses resulting from a cooldown of unexpected severity or an overpressure condition at low temperature.
C. Reactor Vessel Increased stresses resulting from a rapid depressurization condition at high temperature.
D. Reactor Vessel Increased stresses resulting from a cooldown of unexpected severity or an overpressure condition at low temperature.
25
- 26. Which one of the following completes the statements below in accordance with ES-0.3 "Natural Circulation Cooldown with Steam Void in Vessel (With RVLIS)"
Operators are (1) to attempt to start a RCP and RCS cooldown rate is limited to a maximum of (2) .
(1) (2)
A. required 50oF/hour B. NOT allowed 50oF/hour C. required 100oF/hour D. NOT allowed 100oF/hour 26
- 27. Given the following:
- Large Break LOCA is in progress on Unit 2
- Containment pressure is 1.9 psig and stable
- The STA reports an ORANGE condition on the CONTAINMENT (FR-Z)
Safety Function Status Tree due to high level in the containment sump Which one of the following...
(1) describes the action(s) that will be directed by FR-Z.2, "Containment Flooding,"
and (2) In accordance with EPM-3-FR-Z.2 "Basis Document for FR-Z.2 Containment Flooding" what is the concern if the action(s) are NOT successful?
A. (1) Transfer water from containment sump to the RWST.
(2) Components necessary for plant recovery could be damaged and rendered inoperable.
B. (1) Transfer water from containment sump to the RWST.
(2) Water reaching the bottom of the reactor vessel could result in thermal shock and vessel failure.
C. (1) Identify and isolate the source of excess water.
(2) Components necessary for plant recovery could be damaged and rendered inoperable.
D. (1) Identify and isolate the source of excess water.
(2) Water reaching the bottom of the reactor vessel could result in thermal shock and vessel failure.
27
- 28. Given the following:
- Unit 1 is at 9% power
- All control systems are in AUTO Subsequently,
- Loop 1 Reactor Coolant Pump tripped
- No operator actions have been taken Which one of the following is the plant response?
A. #2, #3, and #4 S/G steam flows rise.
B. #2, #3, and #4 S/G steam flows lower.
C. #2, #3, and #4 S/G steam flows do NOT change.
D. The reactor automatically trips on HIGH #1 steam generator level.
28
- 29. Given the following:
- Unit 1 is at 100%
- Annunciator TS-62-75 LOW PRESSURE LETDOWN RELIEF TEMP HIGH (1-M-6 Window C-4) is in alarm.
- RCS leakrate is calculated at 3 gpm To maintain PZR level stable, operator action (1) required.
The letdown relief flow (2) go to the PRT.
(1) (2)
A. is does B. is does NOT C. is NOT does D. is NOT does NOT 29
- 30. Given the following:
- Unit 1 is at 100% power
- Letdown in service at 75 gpm Which one of the following conditions will result in lowering the available NPSH to the CCPs?
A. Loss of air to 1-FCV-62-77, Letdown Flow Isolation B. Loss of air to 1-FCV-62-118, Letdown Divert to HUT LCV C. Loss of air to 1-FCV-62-79, Mixed Bed High Temp Bypass D. Loss of air to 1-TCV-70-192, Letdown HX Outlet Temperature Control 30
- 31. Which one of the following is powered from C&A Vent Board 1B1-B?
A. 1-FCV-74-1, RHR Suction From Loop 4 HL B. 1-FCV-74-21, RHR Pump 1B Suction Isolation C. 1-FCV-63-1, RHR Pump Suction from the RWST D. 1-FCV-63-93, RHR CL Inj To Loops 2 & 3 31
- 32. Given the following:
- Unit 1 was operating at 100% power.
- A loss of Vital Instrument Power Board 1-II occurred.
- The OATC observes the following:
- VCT to CCP suction valves 1-FCV-62-132, -133 automatically CLOSE Which one of the following completes the statement below?
The CCP suction source swapped to the RWST due to a loss of power to _(1) and In accordance with AOP-P.03, "Loss of Unit 1 Vital Instrument Power Board", operators will (2) .
(1) (2)
A. Separation Relays trip the Reactor B. Separation Relays manually transfer CCP suction source to VCT C. VCT level Instruments trip the Reactor D. VCT level Instruments manually transfer CCP suction source to VCT 32
- 33. Which one of the following is an AUTOMATIC action during automatic switchover to sump recirculation after a large-break LOCA?
A. RWST to CCP suction valves (FCV-62-135, -136) CLOSE.
B. RWST to RHR pump suction valves (FCV-74-3, -21) CLOSE.
C. RHR Discharge to CCP and SI Pump suction (FCV-63-7, -6) OPEN.
D. RHR heat exchanger discharge crosstie valves (FCV-74-33, -35) CLOSE.
33
- 34. Given the following:
- Unit 2 is at 90% power.
- Due to a leaking PORV, 2-FCV-68-332 PORV block valve was closed.
- PRT level is 89%
- PRT pressure is 7 psig
- PRT Temperature is 145oF Which one of the following completes the statements below?
In accordance with 2-SO-68-5, "Pressurizer Relief Tank," PRT temperature and (1) are outside the recommended band.
Primary Water flow for PRT cooling enters the tank via (2) .
(1) (2)
A. level a sparger at the bottom of the tank B. level spray nozzles at the top of the tank C. pressure a sparger at the bottom of the tank D. pressure spray nozzles at the top of the tank 34
- 35. Given the following:
- Unit 1 is being cooled down and has been placed on shutdown cooling with 'A' Train RHR in service.
- Temperature on 1-TI-70-157, "RHR Heat Exchanger 1A Outlet Temperature" reads 112°F and rising.
Which one of the following completes the statements below?
In accordance with "RHR HX A OUTLET TEMPERATURE HIGH" (M27-B-A, E-6), Annunciator response, RHR HX outlet temperature shall NOT exceed (1) for given conditions .
In order to reduce the RHR heat exchanger CCS outlet temperature, (2) .
A. (1) 115°F; (2) either the CCS flow or the RHR flow through the heat exchanger is allowed to be adjusted B. (1) 115°F; (2) only the CCS flow through the heat exchanger is allowed to be adjusted C. (1) 145°F; (2) either the CCS flow or the RHR flow through the heat exchanger is allowed to be adjusted D. (1) 145°F; (2) only the CCS flow through the heat exchanger is allowed to be adjusted 35
- 36. Which one of the following is the power supply to the valve position indication for PZR PORV 68-340A on Unit 1?
A. 125V Battery Board I B. 125V Battery Board IV C. 120V Vital Instrument Power Board 1-I D. 120V Vital Instrument Power Board 1-IV 36
- 37. Given the following:
- Unit 1 is at 100%
- Rod control has been placed in MANUAL with Tavg at 578.0°F Which one of the following identifies how the actual RPS trip setpoint value will change if Tavg decreases by 1°F? Assume AFD remains constant.
A. Both OTT and OPT trip setpoint values will decrease.
B. OTT trip setpoint value will increase and OPT trip setpoint value will decrease.
C. OTT trip setpoint value will increase and OPT trip setpoint value will remain the same.
D. OTT trip setpoint value will remain the same and OPT trip setpoint value will decrease.
37
- 38. Given the following:
- Unit 1 is in Mode 3 preparing for a reactor startup Which of the following completes the sentences below?
Technical Specification 3.5.2 ECCS - Operating (1) applicable for this plant condition.
LCO 3.5.2 helps ensure highest fuel cladding temperature following a LOCA will not exceed (2) .
(1) (2)
A. is 2200oF B. is 1200oF C. is NOT 2200oF D. is NOT 1200oF 38
- 39. Given the following:
- Both Units are at 100%
- Upper Compartment Cooling Units A-A and B-B are in service on both units Compare the effects of the inadvertent closing of the Lower Compartment Cooling Unit (LCCU) valves listed:
- Unit 1, LCCU 1A-A ERCW Inlet FCV (Outboard), 1-FCV-67-107
- Unit 2, LCCU 2A-A ERCW Inlet FCV (Outboard), 2-FCV-67-107 Which one of the following identifies the effect on the Upper Containment humidity on the respective unit(s) and the mitigation strategy, if any?
A. Upper containment humidity would RISE on Units 1 and 2.
No additional cooling unit would be available to be placed in service for either Unit.
B. Upper containment humidity would RISE on Units 1 and 2.
0-SO-30-4, Upper Compartment Cooling Units, would be used to place additional coolers in service on both Units.
C. Upper containment humidity would RISE on Unit 1 only.
No additional cooling unit would be available to be placed in service for this Unit.
D. Upper containment humidity would RISE on Unit 1 only.
0-SO-30-4, Upper Compartment Cooling Units, would be used to place additional coolers in service for this Unit.
39
- 40. Given the following:
- A LOCA occurred on Unit 1
- Phase B automatically actuated Subsequently
- ECA-1.1 "Loss of ECCS Sump Recirculation", was entered
- Annunciator status
- LS-63-50A RWST LVL LO, 1-M6-E window E-3 is in Alarm
- LS-63-50B RWST LVL LO-LO, 1-M6-E window E-4 is Dark
- STM GEN LEVEL ADVERSE SETPOINT, 1-M3-C window E-2 is Dark
- Both Containment Spray pumps are running
- The crew is implementing Step 9:
Which one of the following completes the statement below?
(1) Containment Spray Pump(s) are required to be secured (2) .
[REFERENCE PROVIDED]
(1) (2)
A. One now B. One when LS-63-50B RWST LVL LO-LO alarms C. Both now D. Both when LS-63-50B RWST LVL LO-LO alarms 40
- 41. The reason the Ice Condenser Lower Inlet doors are required to be closed during normal operations is to prevent which of the following?
A. Loss of Divider Barrier Integrity.
B. Excessive sublimation of the ice.
C. Frost buildup blocking flow channels.
D. Violating minimum containment air temperature.
41
- 42. Given the following:
- Unit 1 is at 100% power Subsequently,
- A LOCA occurred
- ES-1.3, "Transfer to RHR Containment Sump" is in progress
- Containment pressure peaked at 3.0 psig
- Current containment pressure is 1.8 psig and stable In accordance with ES-1.3 which one of the following identifies the MINIMUM action(s) necessary to allow 1B-B Containment Spray Pump to be stopped and placed in A-AUTO?
A. Reset the Train B Phase B signal and then the Train B Containment Spray signal B. Reset the Train B Containment Spray signal ONLY C. Simultaneously Reset BOTH Trains of Phase B D. Reset the Train B Phase B ONLY 42
- 43. Given the following:
A plant cooldown is in progress on Unit 2 in accordance with 0-GO-7, "Unit Shutdown From Hot Standby To Cold Shutdown."
at 08:00, conditions were achieved in accordance with 0-GO-7:
- RCS pressure is 1850 psig
- RCS temperature is 455°F Subsequently, at 08:15, an event occurred and the following conditions currently exist
- RCS pressure is 1700 psig and lowering at 10 psi per second
- S/G pressures are 700 psig and lowering at 25 psi per second
- Containment pressure is 1.2 psig and rising Which one of the following completes the statement below?
At 08:15, an automatic Safety Injection (1) occurred and a Main Steam Line Isolation (2) occurred.
(1) (2)
A. has has B. has has NOT C. has NOT has D. has NOT has NOT 43
- 44. Given the following:
- Unit 1 is at 25% power
- The #3 S/G MFW Reg valve is in Manual and throttled open
- The #3 S/G MFW Bypass valve is in Manual and closed Which one of the following completes the statement below for how controllers are required to be transferred from MANUAL to AUTO in accordance with 1-SO-98-1"Distributed Control System (DCS)"?
The (1) controller will be transferred first, otherwise SG level will (2) .
(1) (2)
A. MFW Reg valve Rise B. MFW Reg valve Lower C. MFW Bypass valve Rise D. MFW Bypass valve Lower 44
- 45. Given the following:
- Unit 1 is at 100% power.
- MFW header pressure transmitters (1-PT-3-1, 1A, 1B) fail LOW due to an instrument line leak.
- DCS does NOT transfer any MFW controllers to manual.
Which one of the following completes the statements below?
The failure will initially cause Steam Generator levels to _(1)_.
In accordance with AOP-S.01, "Main Feedwater Malfunctions," the operator is required to take manual control of _(2) to stabilize the plant.
(1) (2)
A. rise main feed pump speed control B. rise main feedwater regulating valves C. lower main feed pump speed control D. lower main feedwater regulating valves 45
- 46. Given the following:
- Unit 2 is at 50% power Subsequently, a reactor trip occurs
- The crew entered ES-0.1, "Reactor Trip Response" and is performing Step 1
- The following parameters are observed:
- PZR level is 25% and slowly lowering
- All S/G levels are between 12% and 18% NR and slowly rising
- S/G pressures are 990 psig and slowly lowering
- All RCPs are running
- Tavg is 545°F and slowly lowering
- RCS pressure is 2020 psig and slowly lowering
- NO operator actions have been taken In accordance with ES-0.1, which one of following is required to be performed FIRST?
A. Emergency borate B. Throttle Auxiliary Feedwater flow C. Close MSIVs and bypass valves D. Initiate Safety Injection 46
- 47. Given the following:
- Unit 2 is in Mode 1
- The TDAFW Pump is tagged out of service
- A Loss of Feedwater causes a reactor trip
- Concurrent with the trip, 2B-B 6.9kV SDBD de-energizes on Differential fault Assuming NO operator actions have been taken, which one of the following describes the Auxiliary Feedwater alignment and design flowrate for these conditions?
A. 1 and 2 S/Gs being fed at 220 GPM each B. 1 and 2 S/Gs being fed at 440 GPM each C. ALL S/Gs being fed at 110 GPM each D. ALL S/Gs being fed at 220 GPM each 47
- 48. Given the following:
SO-82-2 "Diesel Generator 1B-B", Section 8.3 Control Room Start is in progress for a Post maintenance test run
- Shutdown Boards are aligned to the Normal Supply Unit boards Which of the following completes the statement below?
The 1B-B Diesel Generator will be operating in parallel with the supply from the (1) 6.9 kV Unit Board.
and If the DG output breaker Overcurrent (50) Relay actuates during the maintenance run, while operating in parallel, it (2) cause the DG Output breaker to open.
(1) (2)
A. 1D will B. 1D will NOT C. 1C will D. 1C will NOT 48
- 49. Given the following:
- Both Units are at 100% power
- All Offsite power is lost to both Units
- 1A-A and 2B-B diesel generators start and load
- 1B-B and 2A-A diesel generators do NOT start
- NO operator action has yet been taken Which one of the following describes status of the 125V Vital Boards?
A. Vital boards I and II are energized by their battery.
B. Vital boards I and IV are energized by their battery.
C. Vital boards II and III are energized by their battery.
D. All Vital 125V DC boards are energized by their battery charger.
49
- 50. Which one of the following will cause the Emergency Diesel Generator (EDG) to receive a trip signal following an Emergency Start condition?
A. Engine Overspeed B. Low lube oil pressure C. High Jacket Water temperature D. Loss of Field (40) Relay actuation 50
- 51. Given the following:
- Unit 1 is at 100% power with Steam Generator Blowdown (SGBD) in service to the Cooling Tower Blowdown.
- The following alarm is received:
- "1-RA-120/121B STM GEN BLDN LIQ SAMP MON INSTR MALFUNC" (0-AR-M12A, B6), due to low sample flow.
- FCV-15-44, S/G Blowdown to CTBD, is open Which one of the following completes the sentences below?
Normally (1) of the rad monitors that provide input to this alarm is(are) in service.
In accordance with the ARP, the operator is required to (2) .
(1) (2)
A. one ensure FCV-15-44 is closed B. one dispatch operator to adjust sample flow C. both ensure FCV-15-44 is closed D. both dispatch operator to adjust sample flow 51
- 52. Given the following:
- Both units were operating at 100%
Subsequently,
- A loss of all off site power to both units occurs
Which ERCW pumps will have power available?
A. J-A and K-A B. J-A and Q-A C. K-A and R-A D. Q-A and R-A 52
- 53. Given the following:
- A Safety Injection has occurred on Unit 1
- ERCW pump L-B is not selected and not running
- ERCW pump M-B pump failed to automatically start Which one of the following describes the impact of this ERCW condition (if any) on the 1B-B D/G?
A. 1B-B D/G will NOT auto-start B. 1B-B D/G is required to be immediately stopped C. 1B-B D/G will be unaffected since the ERCW system is crosstied between the 1A and 1B trains D. 1B-B D/G will be unaffected since the 1B ERCW header is crosstied with the 2B ERCW header 53
- 54. Given the following:
- Unit 1 is at 100% power
- Annunciator "LS-32-63 AUX AIR COMPRP A LOW OIL LVL HI AIR TEMP" 1-AR-M15-B(C-6) is in alarm
- Auxiliary Building AUO reports a red indicating light for high discharge air temperature is LIT Which one of the following completes the statements below?
This condition (1) cause an automatic trip of the Auxiliary air compressor.
Cooling water to the Auxiliary Air Compressor (2) supplied from the Raw Cooling Water system.
(1) (2)
A. will is B. will is NOT C. will NOT is D. will NOT is NOT 54
- 55. Given the following:
- Unit 1 is in Mode 6.
- An inadvertent dilution is in progress.
- Source Range audible count rate is rising.
In accordance with SOURCE RANGE HIGH FLUX LEVEL AT SHUTDOWN (1-AR-M4-B) which ONE of the following completes the statements below?
The EARLIEST time that containment evacuation is required is when SR counts first reach (1) times above background.
An audible alarm inside containment (2) occur when the annunciator alarms.
(1) (2)
A. 3 will B. 3 will NOT C. 5 will D. 5 will NOT 55
- 56. Which one of the following completes the statement below?
The Unit 2 Power Range Overpower Rod withdrawal stop setpoint is (1) on (2) Power Range channels.
(1) (2)
A. 100% Power 1 of 4 B. 100% Power 2 of 4 C. 103% Power 1 of 4 D. 103% Power 2 of 4 56
- 57. Normal DC Control Power for the 1A-A Centrifugal Charging Pump breaker is powered from which of the following electrical boards?
A. Vital Battery Board I B. Vital Battery Board II C. Vital Battery Board III D. Vital Battery Board IV 57
- 58. Given the following:
FR-0 "Status Trees" for CORE COOLING is being evaluated
- RVLIS > 42% lower range blc/3-18-2020 Which one of the following completes the statement below?
A RED PATH in Core Cooling requires at least (1) thermocouples greater than (2) .
(1) (2)
A. four 700oF B. four 1200oF C. five 700oF D. five 1200oF 58
- 59. Given the following:
- The Rx has tripped from 65% power.
- 'A' Rx trip breaker failed to open (remains closed)
Which one of the following completes the statement below?
Control of steam dumps will .
A. transfer to the Rx Trip Controller and the steam dump valves will open B. remain on the Load Reject Controller and the steam dump valves will open C. transfer to the Rx trip controller, however, the steam dump valves will NOT open D. remain on the Load Reject Controller; however, the steam dump valves will NOT open 59
- 60. Given the following:
- Unit 2 is at 100%
- CRO observes the following on EHC Display Panel, 2-XX-47-2000:
- RUNBACK OPER light LIT
- VALVE POS LIMIT light DARK Which one of the following describes the event and turbine control response to the event in progress? (Assume no operator action.)
EVENT TURBINE CONTROL RESPONSE A. OTT Runback Reference and setter indicating changing values.
B. OTT Runback Reference and setter indicating the initial value.
C. HDTP Runback Reference and setter indicating changing values.
D. HDTP Runback Reference and setter indicating the initial value.
60
- 61. In accordance with AOP-S.02 "Loss of Condenser Vacuum" which one of the following completes the statements below?
When turbine load is less than 30%, the EARLIEST time a manual turbine trip is required is when condenser pressure first rises above (1) .
When turbine load is greater than 30%, the EARLIEST time a manual reactor trip is required is when condenser pressure first rises above (2) .
(1) (2)
A. 1.72 psia 3.5 psia B. 1.72 psia 5.4 psia C. 2.7 psia 3.5 psia D. 2.7 psia 5.4 psia 61
- 62. Which one of the following completes the statement below?
The 1A MFW Pump auto-trip setpoint for seal water is low ______ that lasts for 28 seconds.
A. injection pressure below 220 psig B. differential pressure below 10 psid C. injection pressure below 265 psig D. differential pressure below 20 psid 62
- 63. In accordance with 0-SO-77-1, "Waste Disposal System (Liquid)" which one of the following completes the statements below?
The minimum required dilution flow for radioactive liquid releases is (1) .
IF a total of two CCW Pumps are running at the site, THEN the minimum required dilution flow for radioactive liquid releases (2) met.
(1) (2)
A. 10,000gpm is B. 10,000gpm is NOT C. 17,000gpm is D. 17,000gpm is NOT 63
- 64. Which one of the following completes the statements below?
0-RE-90-125/126 "Main Control Room Intake Monitors", (1) the instruments that cause a Control Room Isolation.
If a Control Room Isolation occurs, 0-FCO-311-20 "MCR AHU A INLET" (2) required to be OPEN.
(1) (2)
A. are is B. are is NOT C. are NOT is D. are NOT is NOT 64
- High Pressure Fire Protection (HPFP) temporary cooling has been aligned in accordance with AOP-M.01
- No actions have been performed under Appendix H, TSC Actions in the event of Loss of ERCW.
Subsequently, A total loss of the High Pressure Fire Protection system occurs.
Which of the following have lost their source of TEMPORARY cooling?
A. Glycol Chillers B. Centrifugal Charging Pumps C. Residual Heat Removal Pumps D. Component Cooling System Pumps 65
- 66. Which one of the following identifies when a required periodic verification of a locked valve may be waived in accordance with OPDP-6, Locked Valve/Breaker Program?
A. Valve located in area where the heat stress stay time <1 hour.
B. Valve located in containment raceway during normal power operations.
C. Valve inside a Clearance boundary with system's status control not being maintained.
D. Valve located within a locked area and access to the area has not occurred since the last verification.
66
- 67. In accordance with Tech Spec 3.4.16, "RCS Specific Activity", which one of the following identifies the specific activity limits for the primary coolant in Mode 1?
Dose Equivalent Xe-133 Dose Equivalent I-131 A. < 1612.6 microcuries/gram < 0.10 microcuries/gram B. < 1612.6 microcuries/gram < 0.35 microcuries/gram C. < 1200 microcuries/gram < 0.10 microcuries/gram D. < 1200 microcuries/gram < 0.35 microcuries/gram 67
- 68. Which one of the following completes the statements below?
The license thermal power limit is based on a (1) AVERAGE.
In accordance with OPDP-1 "Conduct of Operations", secondary-side control valve oscillations that cause AVERAGE thermal power to exceed the licensed thermal power limit (2) allowable.
(1) (2)
A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> are B. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> are NOT C. 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> are D. 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> are NOT 68
- 69. Given the following:
- 1C HWP has been secured for three days for maintenance.
- Hold order was removed and the pump was started at 1005.
- Immediately after the motor came up to speed, the pump was shut down.
- The pump was restarted at 1020
- The pump continued to run until 1045, when it was shutdown again.
In accordance with GOI-6, "Apparatus Operations," which one of the following identifies if/when the 1C HWP can be restarted?
A. Pump can be restarted immediately.
B. 20 minutes cooldown is required prior to restarting.
C. 45 minutes cooldown is required prior to restarting.
D. Starting requirements were violated, do not restart the pump.
69
- 70. Which one of the following completes the statements below?
The Safety Limit (Tech Spec 2.1.2) for RCS pressure states RCS pressure shall be maintained < (1) .
Tech Spec 2.1.2 is applicable in modes (2) .
(1) (2)
A. 2485 psig 1-4 B. 2485 psig 1-5 C. 2735 psig 1-4 D. 2735 psig 1-5 70
- 71. In accordance with 0-SO-77-1 "Waste Disposal System" Section 6.2, Monitor Tank Recirculation and Release, what is the minimum required recirculation time?
A. 5 minutes B. 10 minutes C. 50 minutes D. 60 minutes 71
- 72. Given the following:
- A Unit 1 Lower Containment entry in accordance with 0-PI-OPS-000-011.0, "Containment Access Control during Modes 1-4" is scheduled to add oil to #1 RCP
- The Incore Flux Detectors are within 10 feet of the bottom of the core Which one of the following completes the statements below?
The Incore Flux detectors (1) in an approved storage location to be TAGGED.
and UNIT 1 UPR/LWR AIR LOCK BREACH (0-M12-C, A-5) (2) expected to alarm.
(1) (2)
A. are is B. are is NOT C. are NOT is D. are NOT is NOT 72
- 73. In accordance with EPM-4 Users Guide which one of the following completes the statements below?
One of the verbs used to visually identify a Continuous Action Step is _(1)_ .
Equipment or control devices _(2)_ be manipulated when performing a step with the word CHECK.
(1) (2)
A. MONITOR must B. MONITOR should NOT C. ENSURE must D. ENSURE should NOT 73
- 74. Given the following:
The crew has reached a point in the EOPs where FRPs are being monitored and implemented when required.
In accordance with EPM-4,"Users Guide" which one of the following completes the statements below?
If a RED or ORANGE priority condition comes in and clears prior to FRP entry, the FRP (1) performed.
FR-C.2, "Degraded Core Cooling", includes steps for depressurizing intact S/Gs which may cause a RED path on the FR-P.1, "Pressurized Thermal Shock status tree". In this case (2) has priority.
(1) (2)
A. must be FR-C.2 B. must be FR-P.1 C. does not need to be FR-C.2 D. does not need to be FR-P.1 74
- 75. Which one of the following procedures contains at least one immediate operator action?
A. AOP-M.02, Loss of Control Air B. ECA-0.0, Loss of All AC Power C. FR-C.1 Inadequate Core Cooling D. AOP-C.02, Uncontrolled RCS Boron Concentration Changes 75
SQN ILT 2003 NRC Exam NAME:________________
- 76. Given the following:
- Unit 1 is in Mode 4
- Containment Pressure is rising slowly Which one of the following completes the statements below?
Technical Specification LCO 3.6.4, "Containment Pressure" (1) applicable in MODE 4.
In accordance with Technical Specification 3.6.4, Bases, a (2) results in a higher peak containment pressure and is the bounding event when both worst case events are considered.
(1) (2)
A. is LOCA B. is SLB C. is NOT LOCA D. is NOT SLB 76
- 77. Given the following:
- Unit 1 is at 100% power
- Pressurizer level starts to lower
- Initially, both of the following temperature indications indicate a lowering trend 1-TI-62-71, "REGEN HX OUTLET TEMP - LETDOWN" 1-TI-62-87, "REGEN HX OUTLET TEMP - CHARGING" Subsequently, the crew entered AOP-R.05 "RCS Leak" and performed the following actions:
- Charging flow was controlled to stabilize PZR level
- VCT level could NOT be maintained and CCP suction was aligned to the RWST
- A manual Reactor trip was inserted due to the inability to stop the boration.
Which one of the following completes the statements below?
The leak is located on the (1) line downstream of the Regenerative Heat Exchanger.
In accordance with AOP-R.05, the Unit SRO (2) required to implement AOP-C.02, "Uncontrolled RCS Boron Concentration Changes."
(1) (2)
A. Letdown is B. Letdown is NOT C. Charging is D. Charging is NOT 77
- 78. Given the following:
- Unit 1 is in MODE 5 performing AOP-R.03, RHR System Malfunction, due to a loss of CCS cooling
- CCS flow could not be established to either 'A' or 'B' RHR heat exchanger
[REFERENCE PROVIDED]
Which one of the following completes the statements below?
The 'A' RHR pump mini-flow valve (1) in the correct position.
In accordance with AOP-R.03, the crew is required to GO TO (2) .
(1) (2)
A. is AOP-M.03, Loss of Component Cooling Water B. is AOP-R.03 Section 2.6, RCS Alternate Heat Sink using S/Gs or RCS Feed and Bleed C. is NOT AOP-M.03, Loss of Component Cooling Water D. is NOT AOP-R.03 Section 2.6, RCS Alternate Heat Sink using S/Gs or RCS Feed and Bleed 78
- 79. Given the following:
- Unit 1 has entered AOP-I.11, Eagle 21 Malfunction Subsequently,
- AOP-I.04, Pressurizer Instrument and Control Malfunctions, is entered to remove Pzr Pressure Instrument 1-P-68-340 from service.
- The Loop 1 OTDT setpoint is NORMAL Which one of the following completes the statement below?
The Unit Supervisor _(1)_ required to perform Attachment 1, Removing Channel I Pzr Press Instrument P-68-340 from Service (Including Channel I OTDT Bistables) and in accordance with the Basis for Tech Spec 3.3.1 "Reactor Trip System Instrumentation" the Overtemperature (OT) DT trip Function ensures the _(2)_.
(1) (2)
A. is integrity of the fuel B. is design limit DNBR is met C. is NOT integrity of the fuel D. is NOT design limit DNBR is met 79
- 80. Given the following:
- A tube rupture has occurred in SG #1
- The crew is performing E-3, Steam Generator Tube Rupture
- RCS subcooling is 46F
- Pressurizer level is 22%
Which one of the following identifies the procedure that will cooldown and depressurize and allow RHR to be placed in service in the least amount of time?
A. ES-3.1, Post-SGTR Cooldown Using Backfill.
B. ES-3.2, Post-SGTR Cooldown Using Blowdown.
C. ES-3.3, Post-SGTR Cooldown Using Steam Dump.
D. ECA-3.2, SGTR With Loss of Reactor Coolant - Saturated Recovery Desired.
80
- 81. Given the following:
- Both Units are operating at 100% power.
0700 - 120V AC Vital Instrument Power Board (VIPB) 2-III was declared INOPERABLE.
0900 - Unit 1 OATC reports all channel status lights on RX Trip - SI Status panels are dark.
Which one of the following completes the statement below?
At 0900, 120V AC VIPB (1) was lost.
In accordance with Tech Specs, the earliest time required to enter Mode 3 is (2) .(Assuming no repairs have been completed)
REFERENCE PROVIDED A. (1) 1-I (2) 2100 B. (1) 1-I (2) 2300 C. (1) 1-II (2) 2100 D. (1) 1-II (2) 2300 81
- 82. Given the following:
- Unit 1 is at 90% power
- Control Bank D rods at 215 steps Subsequently,
- A runback occurred on Unit 1 due to a MFP trip
- The OATC reports:
- Control Bank D is at 115 steps
- Control Bank D rods D4 and D12 are at 130 steps due to liftcoil failures
[REFERENCE PROVIDED]
Which one of the following completes the statements below?
LCO 3.1.4 "Rod Group Alignment Basis", Condition A (1) required to be entered.
In accordance with AOP-C.01 "Rod Control Malfunctions" this condition will be corrected by (2) .
(1) (2)
A. is rod realignment B. is reactor shutdown C. is NOT rod realignment D. is NOT reactor shutdown 82
- 83. Given the following:
- Startup in progress in accordance with 0-GO-4, Power Ascension from Less than 5%
Reactor Power to 30% Reactor Power
- Power is being held at 7%
0800, 29 OCT N-35 declared INOPERABLE 0700, 30 OCT N-36 failed to 20%, actual power was still at 7%
Which one of the following completes the statement below?
The earliest time Unit 1 is required to reduce Thermal Power < P-6 is(1) and when power is < P-6 the Source Range (2) automatically reinstate.
[REFERENCE PROVIDED]
(1) (2)
A. 0800, 30 OCT will B. 0800, 30 OCT will NOT C. 0900, 30 OCT will D. 0900, 30 OCT will NOT 83
- 84. Which one of the following completes the following statement IAW the SQN Fire Protection Report Part II - Fire Protection Plan?
A continuous fire watch requires that a trained individual be in the specified area at (1) , and that each compartment in the specified area be patrolled at least once (2) .
(1) (2)
A. all times every 5 minutes B. all times every 15 minutes C. least every 15 minutes every 5 minutes D. least every 15 minutes every 15 minutes 84
- 85. Which one of the following completes both statements in accordance with FR-C.3 "Saturated Core Cooling"?
IF ECA-3.2 "SGTR With Loss of Reactor Coolant-Saturated Recovery Desired", is in progress, THEN FR-C.3 (1) be performed.
FR-C.3, Step 5: (CHECK RCS Inventory Loss Paths) (2) .
(1) (2)
A. must all block valves are required to be closed B. must at least one block valve is required to be open C. is NOT required to all block valves are required to be closed D. is NOT required to at least one block valve is required to be open 85
- 86. Given the following:
-Unit 2 is implementing FR-C.2 "Degraded Core Cooling"
-All RCPs are running Which one of the following completes the statement below?
In accordance with FR-C.2 "Degraded Core Cooling" (1) RCP(s) will be secured.
In accordance with EPM-3-FR-C.2 "Basis Documents for FR-C.2 Degraded Core Cooling" the pump(s) (is/are) secured based on (2) .
(1) (2)
A. One reserving for future use B. One reducing heat input to RCS C. Three reserving for future use D. Three reducing heat input to RCS 86
- 87. Given the following plant conditions:
- Unit 1 is in MODE 2.
- A loss of 125 VDC Vital Battery Board I occurs.
Which one of the following completes the statements below?
RTA (reactor trip breaker A) main control board indication (1) available.
In accordance with Basis of LCO 3.3.1 "RTS Instrumentation" RTA (2) OPERABLE.
(1) (2)
A. is remains B. is is NOT C. is NOT remains D. is NOT is NOT 87
- 88. Given the following:
- Unit 1 is at 100% power Subsequently,
- A Main Steam Line break occurred on #2 SG upstream of the MSIV
- RX was manually tripped
- Safety Injection was actuated
- E-0 "Reactor Trip or Safety Injection" was entered
- After Immediate Operator Action steps completed the OATC reports
- RCS pressure 1400 psig and lowering
- Containment pressure 2.9 psig and rising
- One Pressurizer safety valve is open Which one of the following completes the statements below?
The MSIVs (1) automatically close.
The FIRST procedure transition from E-0 will be to (2) .
(1) (2)
A. will E-1, Loss of Reactor or Secondary Coolant B. will E-2, Faulted Steam Generator Isolation C. will NOT E-1, Loss of Reactor or Secondary Coolant D. will NOT E-2, Faulted Steam Generator Isolation 88
- 89. Given the following:
- Unit 1 is at 70% power
- AOP-I.08 "Turbine Impulse Pressure Malfunction" is in progress
- Two turbine impulse pressure channels failed low
- P-1-73
- P-47-13 Which one of the following completes the statements below?
Automatic Rod Withdrawal (1) blocked.
AOP-I.08 "Appendix A, Placing Steam Dumps in Pressure Mode" (2) required to be performed.
(1) (2)
A. is is B. is is NOT C. is NOT is D. is NOT is NOT 89
- 90. Given the following:
- Both units are in Mode 1 with all 6.9 kV Unit Boards in Automatic and aligned to USSTs.
- The USST 1A LTC CONTROL SWITCH (1-HS-241-107) and USST 1B LTC CONTROL SWITCH (1-HS-241-108) are in the MANUAL - PUSHED IN position Which one of the following completes the statement below?
LCO 3.8.1 AC Sources - Operating (1) met.
1-HS-241-107 and -108 are located (2) .
(1) (2)
A. is at 1-M-1 B. is on the Electrical Control Boards C. is NOT at 1-M-1 D. is NOT on the Electrical Control Boards 90
- 91. Given the following:
- Unit 1 is at 100% power
- Backup Bank B Pressurizer heaters lost power In accordance with LCO 3.4.9 "Pressurizer", which one of the following completes the statements below?
(1) group(s) of pressurizer heaters is(are) required to be OPERABLE.
For the given condition the Pressurizer is (2) .
(1) (2)
A. One OPERABLE B. One NOT OPERABLE C. Two OPERABLE D. Two NOT OPERABLE 91
- 92. Which one of the following completes both statements for Tech Spec 3.3.3, Post Accident Monitoring Instrumentation?
In Table 3.3.-1 (PAM Instrumentation), for Function 17-Neutron Flux, (1) are required to be operable.
In accordance with the Basis for "Function 17 - Neutron Flux" these instrument(s)
(2) required for diagnosing positive reactivity insertion.
A. (1) ONLY the Source Range Instruments (2) are B. (1) ONLY the Source Range Instruments (2) are NOT C. (1) BOTH the Source Range and Intermediate Range Instruments (2) are D. (1) BOTH the Source Range and Intermediate Range Instruments (2) are NOT 92
- 93. Given the following:
- Unit 1 is at 100% power
- A Train Lower Containment Purge is in service IAW 0-SO-30-3, "Containment Purge System Operation" FCV-30-56 LOWER PURGE EXHAUST fails closed Which of the following completes the statements below?
Annunciator 1-M6-E window C-6, ZS-61-186 ICE CONDENSER LOWER INLET DOOR OPEN (1) be LIT.
and In accordance with 0-PI-OPS-000-011.0 "Containment Access Control During Modes 1-4" Plant Manager authorization for Containment access to #1 Accumulator Room to locally inspect 1-FCV-30-56 (2) required.
(1) (2)
A. will is B. will is NOT C. will NOT is D. will NOT is NOT 93
- 94. Given the following:
A Work Control Center (WCC) SRO has previously held a SRO license at SQN, but does not currently hold a SRO license.
In accordance with OPDP-1 "Conduct of Operations" which of the following completes the statements below?
This WCC SRO (1) authorize switchyard access.
This WCC SRO (2) be the incident commander.
(1) (2)
A. can can B. can can NOT C. can NOT can D. can NOT can NOT 94
- 95. Given the following:
- Unit 1 Ice bed maximum temperature readings are being logged every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in accordance with SR 3.6.12.1 Date Time Maximum Ice Bed Temperature 25 Oct 0830 19.50F 25 Oct 2030 21.50F 26 Oct 0830 23.50F 26 Oct 2030 25.50F Which one of the following completes the statements below?
In accordance with LCO 3.6.12 "Ice Bed", if current temperature trend continues the earliest the Ice Bed will be INOPERABLE is at (1) .
In accordance with SR 3.0.2 to comply with the Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> the reading may be taken a maximum of (2) from the previous reading.
(1) (2)
A. 27 Oct 0830 13.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. 27 Oct 0830 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> C. 28 Oct 2030 13.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. 28 Oct 2030 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> 95
- 96. In accordance with NPG-SPP-10.2 "Clearance Procedure to Safely Control Energy" which one of the following completes the statements below?
Local Control Pushbuttons/Hand switches (1) be used as as an energy isolation device for a clearance.
A licensed SRO who has not stood watch in the control room SRO for 6 months (i.e, an inactive SRO) (2) allowed to approve a clearance for placement or release.
(1) (2)
A. can is B. can is NOT C. can NOT is D. can NOT is NOT 96
- 97. In accordance with NPG-SPP-07.2.11, "Shutdown Risk Management," which one of the following completes the statements below?
The Defense-in-Depth checklist must be completed (1) .
A planned entry into a RED condition (2) .
A. (1) each shift (2) requires Plant Manager authorization B. (1) each shift (2) is NOT allowed C. (1) every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (2) requires Plant Manager authorization D. (1) every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (2) is NOT allowed 97
- 98. Given the following:
- Both Units are at 100% power
- LS-87-3 SPENT FUEL PIT LEVEL HIGH-LOW annunciator is LIT Which one of the following completes the statements below?
The Spent Fuel Pit level annunciator is located on (1) .
In accordance with Technical Specification 3.7.13, "Spent Fuel Pool Water Level Basis", the minimum water level (2) .
A. (1) both Units (2) provides long term cooling following a core unload B. (1) both Units (2) meets the assumptions of iodine decontamination factors following a fuel handling accident C. (1) Unit 1 ONLY (2) provides long term cooling following a core unload D. (1) Unit 1 ONLY (2) meets the assumptions of iodine decontamination factors following a fuel handling accident 98
- 99. Which one of the following completes the following statements in accordance with EPIP-8, "Personnel Accountability and Evacuation?"
The decision to utilize the Assembly and Accountability System to invoke the Two Person Line of sight Rule will be made by the (1) based upon the recommendation of the (2) .
(1) (2)
A. Nuclear Security Response Shift Manager or SED Team Leader B. Shift Manager or SED Nuclear Security Response Team Leader C. Operations Support Center Nuclear Security Response Team Leader D. Nuclear Security Response Operations Support Center Team Leader 99
SQN ILT 2003 NRC Exam 100. In accordance with EPIP-1 "Emergency Plan Classification Matrix" which one of the following completes the statement below?
If a condition existed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago that met an EAL threshold but no emergency was declared and the basis for the emergency no longer exists at the time of discovery, then the emergency condition .
A. must be declared and reported to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. must be declared and reported to the NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. shall NOT be declared, but must be reported to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. shall NOT be declared, but must be reported to the NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 100
SQN Loss of ECCS Sump Recirculation ECA-1.1 Unit 1 & 2 Rev. 0017 Step Action/Expected Response Response Not Obtained
- 9. DETERMINE containment spray requirements:
- a. CHECK Cntmt Spray pump a. IF Cntmt Spray pump suction suction ALIGNED to RWST. is aligned to sump, THEN GO TO Step 11.
- b. DETERMINE number of spray pumps required from table below:
RWST LEVEL CNTMT PRESSURE NUMBER OF CNTMT SPRAY
(%) (PSIG) PUMPS REQUIRED Greater than 12.0 2 Greater than 8 Between 9.5 and 12.0 1 Less than 9.5 0 Less than 8 -------- 0 (Step continued on next page.)
Page 7 of 71
Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Two electrical power distribution trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC A.1 --------------NOTE--------------
electrical power Enter applicable Conditions distribution subsystems and Required Actions of inoperable due to one or LCO 3.8.4, "DC Sources -
more Unit 1 AC Operating," for vital DC shutdown boards electrical power trains inoperable. made inoperable by inoperable AC electrical power distribution subsystems.
Restore Unit 1 AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power distribution subsystem(s) to OPERABLE status.
B. One or more AC vital B.1 Restore AC vital instrument 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> instrument power power distribution distribution subsystems subsystem(s) to inoperable. OPERABLE status.
C. One or more vital DC C.1 Restore vital DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> electrical power power distribution distribution subsystems subsystem(s) to inoperable. OPERABLE status.
SEQUOYAH - UNIT 1 3.8.9-1 Amendment 334
Distribution Systems - Operating 3.8.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
NOTES--------------
- 1. Only applicable during planned maintenance.
- 2. Only applicable when Unit 2 is defueled or in MODE 6 following defueled with Unit 2 refueling water cavity level 23 ft. above top of reactor vessel flange.
D. One or more AC D.1 Declare associated Immediately electrical power required feature(s) distribution subsystems inoperable.
inoperable due to one or more Unit 2 AC shutdown boards inoperable.
E. One or more AC E.1 Restore Unit 2 AC electrical 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> electrical power power distribution distribution subsystems subsystem(s) to inoperable due to one or OPERABLE status.
more Unit 2 AC shutdown boards inoperable for reasons other than Condition D.
F. One or more DG DC F.1 Declare associated Immediately electrical power supported DG inoperable.
distribution panels inoperable.
G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND G.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SEQUOYAH - UNIT 1 3.8.9-2 Amendment 334
Distribution Systems - Operating 3.8.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. Two or more electrical H.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of safety function.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance required AC, vital DC, DG DC, and AC vital with the instrument electrical power distribution subsystems. Surveillance Frequency Control Program SEQUOYAH - UNIT 1 3.8.9-3 Amendment 334
Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and control rods shall be OPERABLE.
AND Individual indicated rod positions shall be within 12 steps of their group step counter demand position.
APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod(s) A.1.1 Verify SDM to be within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. limits specified in the COLR.
OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.
AND A.2 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B. One rod not within B.1 Restore rod to within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> alignment limits. alignment limits.
OR B.2.1.1 Verify SDM to be within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> limits specified in the COLR.
OR SEQUOYAH - UNIT 1 3.1.4-1 Amendment 334
Rod Group Alignment Limits 3.1.4 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.2.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SDM to within limit.
AND B.2.2 Reduce THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> POWER to 75% RTP.
AND B.2.3 Verify SDM is within the Once per limits specified in the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> COLR.
AND B.2.4 Perform SR 3.2.1.1. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND B.2.5 Perform SR 3.2.2.1.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND B.2.6 Re-evaluate safety analyses and confirm 5 days results remain valid for duration of operation under these conditions.
C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B not met.
D. More than one rod not D.1.1 Verify SDM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> within alignment limit. limits specified in the COLR.
OR SEQUOYAH - UNIT 1 3.1.4-2 Amendment 334
Rod Group Alignment Limits 3.1.4 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required SDM to within limit.
AND D.2 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within alignment limit. In accordance with the Surveillance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement (trippability) by In accordance moving each rod not fully inserted in the core with the 10 steps in either direction. Surveillance Frequency Control Program SR 3.1.4.3 Verify rod drop time of each rod, from the fully Prior to criticality withdrawn position, is 2.7 seconds from the after each beginning of decay of stationary gripper coil voltage removal of the to dashpot entry, with: reactor head
- a. T avg 500°F and
- b. All reactor coolant pumps operating.
SEQUOYAH - UNIT 1 3.1.4-3 Amendment 334
RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.1-1.
ACTIONS
NOTE----------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.1-1 required channels or for the channel(s) or trains inoperable. train(s).
B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Trip channel inoperable. OPERABLE status.
OR B.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> C. One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. OPERABLE status.
OR C.2.1 Initiate action to fully insert 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> all rods.
AND SEQUOYAH - UNIT 1 3.3.1-1 Amendment 334
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.2.2 Place the Rod Control 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> System in a condition incapable of rod withdrawal.
D. One Power Range -------------------NOTES------------------
Neutron Flux - High 1. The inoperable channel may channel inoperable. be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment of other channels.
- 2. Perform SR 3.2.4.2 if input to QPTR from one or more Power Range Neutron Flux channels are inoperable with THERMAL power >75% RTP.
D.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR U
D.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> SEQUOYAH - UNIT 1 3.3.1-2 Amendment 334 343
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable. -------------------NOTE--------------------
The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
E.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR E.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> F. One Intermediate Range F.1 Reduce THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Neutron Flux channel POWER to < P-6.
OR F.2 Increase THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> POWER to > P-10.
G. Two Intermediate Range G.1 --------------NOTE--------------
Neutron Flux channels Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.
Suspend operations Immediately involving positive reactivity additions.
AND G.2 Reduce THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> POWER to < P-6.
SEQUOYAH - UNIT 1 3.3.1-3 Amendment 334
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. One Source Range H.1 --------------NOTE---------------
Neutron Flux channel Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.
Suspend operations Immediately involving positive reactivity additions.
I. Two Source Range I.1 Open reactor trip breakers. Immediately Neutron Flux channels inoperable.
J. One Source Range J.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Neutron Flux channel OPERABLE status.
OR J.2.1 Initiate action to fully insert 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> all rods.
AND J.2.2 Place the Rod Control 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> System in a condition incapable of rod withdrawal.
SEQUOYAH - UNIT 1 3.3.1-4 Amendment 334
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME K. One channel -------------------NOTE---------------------
inoperable. The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
K.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR K.2 Reduce THERMAL POWER 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> to < P-7.
L. One Turbine Trip -------------------NOTE---------------------
channel inoperable. The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
L.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR L.2 Reduce THERMAL POWER 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> to < P-9.
M. One train inoperable. --------------------NOTE--------------------
One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing provided the other train is OPERABLE.
M.1 Restore train to OPERABLE 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> status.
OR M.2 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> SEQUOYAH - UNIT 1 3.3.1-5 Amendment 334
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME N. One reactor trip breaker --------------------NOTE-------------------
train inoperable. One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing, provided the other train is OPERABLE.
N.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.
OR N.2 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> O. One or more channels O.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit conditions.
OR O.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> P. One or more channels P.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit conditions.
OR P.2 Be in MODE 2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> SEQUOYAH - UNIT 1 3.3.1-6 Amendment 334
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME Q. One trip mechanism --------------------NOTE-------------------
inoperable for one The reactor trip breaker train shall reactor trip breaker. not be bypassed while one of the diverse trip features is inoperable except for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for performing maintenance to restore the breaker to OPERABLE status Q.1 Restore inoperable trip 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> mechanism to OPERABLE status.
OR Q.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> R. One channel inoperable. -------------------NOTE--------------------
The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels.
R.1 For the affected protection 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> set, adjust the Trip Time Delay for one affected steam generator (T S ) to match the Trip Time Delay for multiple affected steam generators (T M ).
AND R.2 Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SEQUOYAH - UNIT 1 3.3.1-7 Amendment 334
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME S. One channel inoperable. S.1 For the affected protection 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> set, adjust the Steam Generator Water Level -
Low-Low (EAM) channels trip setpoint to the same value as Steam Generator Water Level - Low-Low (Adverse).
OR S.2 For the affected protection 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> set, place the Steam Generator Water level--Low-Low channel(s) in trip.
OR S.3 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> T. One channel inoperable. T.1 For the affected protection 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> set, adjust the Trip Time Delays (T S and T M )
threshold power level for zero seconds time delay to 0% RTP.
OR T.2 For the affected protection 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> set, place the Steam Generator Water Level--
Low-Low channel(s) in trip.
OR T.3 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> U. Required Action and U.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition R not met.
SEQUOYAH - UNIT 1 3.3.1-8 Amendment 334
ANSWER KEY REPORT for RO Exam Test Form: 0 Answers
- 0 1 A 2 B 3 A 4 A 5 A 6 D 7 B 8 A 9 A 10 D 11 C 12 D 13 A 14 C 15 A 16 D 17 D 18 D 19 C 20 B 21 B 22 C 23 B 24 A 25 D 26 C 27 C 28 A 29 C 30 A 31 B 32 B 33 B 34 B 35 C 36 A 37 C 38 A 39 C 40 C 41 B 42 B 43 C 44 B 45 A 46 B 47 A Tuesday, February 25, 2020 10:31:43 AM 1
ANSWER KEY REPORT for RO Exam Test Form: 0 Answers
- 0 48 C 49 C 50 A 51 B 52 B 53 D 54 D 55 A 56 C 57 A 58 D 59 A 60 A 61 A 62 A 63 C 64 A 65 B 66 D 67 B 68 D 69 A 70 D 71 D 72 B 73 B 74 C 75 B SECTION 75.001 ( 75 items)
Tuesday, February 25, 2020 10:31:43 AM 2
ANSWER KEY REPORT for SRO Exam Test Form: 0 Answers
- 0 1 (76) A 2 (77) D 3 (78) D 4 (79) D 5 (80) C 6 (81) A 7 (82) D 8 (83) B 9 (84) B 10 (85) D 11 (86) A 12 (87) D #87: Answer Key Changed to "C" 13 (88) A 14 (89) A 15 (90) C 16 (91) D 17 (92) C 18 (93) B 19 (94) A #94: Also accept "B" 20 (95) B 21 (96) C 22 (97) B 23 (98) D 24 (99) B 25 (100) C SECTION 25.001 ( 25 items)
Tuesday, February 25, 2020 10:33:17 AM 1