ML12188A680
| ML12188A680 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/03/2012 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML12188A680 (85) | |
Text
NRC Exam Site-Specific RO Written Examination Applicant Information Date: May 18, 2012 Facility/Unit: Browns Ferry Region: I H
III IV Reactor Type:
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 80.00 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 Value 75 Points Applicants Score Points Applicants Grade Percent Name:
QUESTION I
With Unit 1 at 100% power the rams head hold down assembly for Jet Pump #4 has failed.
When core flow conditions have stabilized, which ONE of the following completes the statements below?
Jet Pump #4 indicated flow on ICS JET PUMP FLOW screen will have (1).
Actual total core flow will have _(2).
A.
(1) lowered (2) lowered B.
(1) lowered (2) risen C.
(1) risen (2) lowered D.
(1) risen (2) risen
QUESTION 2
The plant has experienced a Loss of Offsite Power with a LOCA on Unit 3, the following plant conditions currently exist:
Unit 3 Drywell Pressure 5 psig Diesel Generators A, B, AND C are supplying their 4kV Shutdown Boards Diesel Generator D did NOT automatically start AND will NOT manually start Diesel Generators 3A, 3B, AND 3C are supplying their 4kV Shutdown Boards Diesel Generator 3D is tagged out of service 480V Shutdown Board 2B has been transferred to its ALTERNATE supply Which ONE of the following completes the statements below?
In accordance with 0-AOl-57-IA, Loss of Offsite Power (161 and 500 KV)/Station Blackout, transfer Diesel Aux. Board _(1)_ to its ALTERNATE power source, to ensure _(2)_ Standby Gas Treatment trains are in service to meet design flow requirements.
A.
(1)A (2) two B.
(1)A (2) three C.
(1)B (2) two D.
(1)B (2) three
QUESTION 3
A complete loss of power to Battery Board #1, Panel 11 has occurred.
Which ONE of the following describes how this affects the Unit 3 annunciator power supply to Panel 9-9 Cabinet 1?
A.
No affect; BOTH 48VDC power supplies to Unit 3 Panel 9-9 Cabinet 1 remain energized.
B.
The Unit 3 Panel 9-9 Cabinet 1 48VDC power supply remains from Battery Board #3, Panel II.
C.
The Unit 3 Panel 9-9 Cabinet I 48VDC power supply is now from Battery Board
- 2, Panel 11.
D.
The Unit 3 Panel 9-9 Cabinet I 48VDC power supply to the annunciators is de-energized.
QUESTION 4
Given the following plant conditions on Unit 3:
100% rated power when the OATC notices that number 3 Main Turbine Stop Valve (MTSV) position indication is indicating 50%.
Numbers 1, 2, and 4 MTSV position indications all indicate 100%.
Maintenance investigation determines that the cause of the MTSV position indicator failure is due to a mechanical failure of the Linear Variable Differential Transformer (LVDT).
SUBSEQUENTLY, the Main Turbine receives a trip signal.
Which ONE of the following completes the statements below?
The RPS logic contact for MTSV #3 _(1) function.
The Generator output breaker will _(2)_.
A.
(1) will (2) have to be manually opened B.
(1) will (2) automatically open C.
(1)will NOT (2) have to be manually opened D.
(1)will NOT (2) automatically open
QUESTION 5
3-EQ I-I, RPV Control, 3-EOI-2, Primary Containment Control and 3-EOI-3, Secondary Containment Control are being executed as a result of reactor coolant leaks. The following conditions exist on Unit 3:
Reactor Scrammed Reactor Pressure 600 psig Drywell Temperature (TI-64-52AB) 255° F Drywell Pressure 10 psig RWCU HX Room Temperature (69-29F 1
G,H) 245° F Which ONE of the following level instruments indicate an accurate Reactor Water Level?
Reference Provided A.
LI-3-53 indicates (+)5 inches B.
Ll-3-55 indicates (-i-)35 inches C.
Ll-3-208B indicates (+)10 inches D.
Ll-3-208D indicates (+)10 inches
QUESTION 6
Unit 1 and 2 Control Room evacuation was conducted. During the evacuation a Unit 2 Operator placed handswitch 2-HS-82-1, DIESEL GENERATORS START, on Panel 2-9-8 to START. The Unit I operators took no actions to start diesel generators.
In accordance with Unit I and Unit 2 AOl-I 00-2, Control Room Abandonment the required actions and attachments have been completed.
One hour later, a Loss of ALL Offsite Power occurs.
Which ONE of the following completes the statements below?
When the Unit 2 Operator placed switch 2-HS-82-1 to START, Diesel Generators
_(1) started.
When Offsite power was lost, the operating Diesel Generators (2) their respective shutdown boards.
A.
(1) B and D ONLY (2) automatically energized B.
(1)BandDONLY (2) have to be manually synched in order to energize C.
(1)A,B,CandD (2) automatically energized D.
(1)A,B,CandD (2) have to be manually synched in order to energize
QUESTION 7
Unit 3 is operating at 100% with the Unit 1 Spare RBCCW pump disassembled for maintenance.
One Unit 3 RBCCW pump trips and cannot be restarted.
Which ONE of the following completes the statements below?
The 3-FCV-070-48, RBCCW Sectionalizing Valve, will auto-close when the _(1)_.
An IMMEDIATE manual reactor scram _(2)_ in accordance with 3-AOI-70-1, Loss of RBCCW.
A.
(1) discharge header pressure lowers to 49 psig (2) is required B.
(1) suction header temperature rises to 105° F (2) is required.
C.
(1) discharge header pressure lowers to 49 psig (2) is NOT required D.
(1) suction header temperature rises to 105° F (2)is NOT required
QUESTION 8
Unit 2 is at 100% Reactor Power when a Control Air leak results in the following indication:
Which ONE of the following occurs FIRST as Control Air pressure lowers to the value indicated above?
A.
SERVICE AIR XTIE VLV, 0-FCV-33-1, OPENED B.
Unit 2 OUTBOARD MAIN STEAM ISOLATION VALVES CLOSED C.
CONDENSATE DEMIN BYPASS VALVE, 2-FCV-2-1 30, OPENED D.
Unit 2 to Unit 3 CONTROL AIR CROSSTIE, 2-PCV-032-3901, CLOSED
QUESTION 9
Unit 1 is in Mode 4. A loss of shutdown cooling has occurred.
The crew has placed RWCU in service in accordance with 1 -AOI-74-1, Loss of Shutdown Cooling.
Which ONE of the following completes the statements below?
The reason why 1-AOI-74-1 directs maximizing RWCU blowdown flow is to _(1)_.
The maximum allowed flow with two-pump operation in accordance with 1-01-69, RWCU System is _(2)_.
A.
(1) establish natural circulation (2) 320 gpm B.
(1) establish natural circulation (2) 200 gpm C.
(1) maintain reactor coolant temperature < 200° F (2) 320 gpm D.
(1) maintain reactor coolant temperature <2000 F (2) 200 gpm
QUESTION 10 Unit 3 is in Mode 5 when a refueling accident results in the following annunciator:
REFUELING ZONE EXHAUST RADIATION HIGH (3-9-3A, window 34)
Which ONE of the following completes the statement below that describes the expected plant response?
A.
ONLY the Refueling Zone Ventilation System isolates and ONLY the Refueling Zone dampers re-align to SGTS.
B.
ONLY the Refueling Zone Ventilation System isolates and the Reactor AND Refueling Zones dampers re-align to SGTS.
C.
The Refueling AND Reactor Zone Ventilation Systems isolate and ONLY the Refueling Zone dampers re-align to SGTS.
D.
The Refueling AND Reactor Zone Ventilation Systems isolate and the Reactor AND Refueling Zones dampers re-align to SGTS.
QUESTION 11 Unit 3 is operating at 100% power, Drywell Pressure Instrument 3-PIS-64-56A failed.
To comply with Technical Specifications; actions to place the channel in trip have been completed in accordance with 3-01-99, Reactor Protection System and 3-01-64, Primary Containment System.
REACTOR CHANNEL A AUTO SCRAM, (3-9-5B, window 1) is in alarm SUBSEQUENTLY, Drywell Pressure Instrument 3-PIS-64-56C fails to 5 psig.
Which ONE of the following completes the statement below?
Unit 3 _(1)_ AND an isolation in PCIS groups 2, 6, and 8 has _(2)_.
A.
(1) remains operating (2) NOT occurred B.
(1) remains operating (2) occurred C.
(1) has scrammed (2) NOT occurred D.
(1) has scrammed (2) occurred
QUESTION 12 In accordance with Technical Specifications, which ONE of the following is the reason for the automatic Reactor Recirculation Pump trip?
A.
Raises RPV water level during a LOCA.
B.
Reduces Reactor Power during an ATWS.
C.
Reduces RPV water level during an ATWS.
D.
Prevents motor damage when sprays are initiated during a LOCA.
QUESTION 13 Which ONE of the following completes the statement below?
When a DBA LOCA occurs with Suppression Pool water temperature initially at 102°Fthe A.
NPSH limits for RH R/GS could be exceeded B.
NPSH limit for RCIC could be exceeded C.
steam condensation capability of the suppression pool will be reduced D.
dynamic loading on the suppression chamber could be exceeded
QUESTION 14 Unit I has scrammed from 100% Reactor Power with the following conditions:
Drywell Temperature is 280° F and rising Drywell Pressure is 15 psig and rising Which ONE of the following completes the statements below under the conditions listed above?
IMMEDIATELY following the initiation of Drywell Sprays, the Drywell is expected to have a _(1)_ pressure drop.
The PRIMARY method of heat transfer when Drywell sprays are initially placed in service is _(2) cooling.
A.
(1) slow, steady (2) convective B.
(1) slow, steady (2) evaporative C.
(1) rapid, large (2) convective D.
(1) rapid, large (2) evaporative
QUESTION 15 A startup is in progress on Unit I with the following conditions:
Reactor Power 15%
Drywell and Suppression Chamber are de-inerted Drywell to Suppression Chamber D/P is NOT established Suppression Pool Water Level is (-)5.5 inches and lowering slowly Which ONE of the following requires the EARLIEST entry into Tech Spec Actions for Suppression Pool Water Level?
A.
(-)6.2 inches B.
(-)6.4 inches C.
(-)7.3 inches D.
(-)7.5 inches
QUESTION 16 A Loss of Offsite Power has occurred.
All eight Diesels start and tie to their shutdown boards.
o At 0800, Unit 2 Drywell Pressure is 5.0 psig and rising and Reactor Pressure is 400 psig and lowering.
At 0810, Unit 1 Reactor Water Level lowers to ()1 30 inches.
Which ONE of the following describes the effects on Unit I and Unit 2 RHR systems when Unit 1 Reactor Water Level lowers to (-)130 inches?
A.
Unit I RHR Pumps IA and IC start.
Unit 2 RHR Pumps 2B and 2D continue to operate.
B.
Unit I RHR Pumps IA, IB, IC and 1D start.
Unit 2 RHR Pumps 2B and 2D continue to operate.
C.
Unit 1 RHR Pumps IA and IC start.
Unit 2 RHR Pumps 2A and 2C continue to operate.
D.
Unit I RHR Pumps 1A, 1B, iCand ID start.
Unit 2 RHR Pumps 2A and 2C continue to operate.
QUESTION 17 On Unit 2 an ATWS has occurred with a RWCU line break in Secondary Containment with the following conditions:
ReactorPowerl5%
SLC was initiated RWCU HX Room has the following temperature indications o
69-29F indicates 2500 F o
69-29G indicates 230° F RWCU leak has been isolated SUBSEQUENTLY, SLC has injected to a tank level of 35% as indicated on 2-Ll-63-IA, SLC STORAGE TANK LEVEL.
In accordance with 2-EOl-1, RPV Control, which ONE of the following completes the statement below?
The Reactor shall be Reference Provided A.
stabilized below 1073 psig B.
rapidly depressurized irrespective of cooldown rate to below 100 psig and maintained in MODE 3 C.
depressurized below 100 psig maintaining the cooldown rate <100° F/hr and maintained in MODE 3 D.
depressurized below 100 psig maintaining the cooldown rate <100° F/hr and then continue cool down to cold shutdown
QUESTION 18 Which ONE of the following alarm response procedures (ARP5) directs lowering power to maintain stack releases within ODCM limits?
A.
OG PRETREATMENT RADIATION HIGH (2-9-3A, window 5)
B.
OG POST TRTMT RADIATION HIGH-HIGH (2-9-4C, window 34)
C.
STACK GAS RADIATION HIGH (2-9-3A, window 13)
D.
STACK GAS RADIATION HIGH-HIGH (2-9-.3A, window 6)
QUESTION 19 With all three units at 100% power the following initial conditions exist for the High-Pressure Raw Water Fire Protection System:
Fire Pump A is tagged out for maintenance Fire Pump B was found with a through wall leak on the discharge line and is tagged out SUBSEQUENTLY, the Diesel Fire Pump functional operational test was completed today and indicates the fire pump develops 2250 gpm at a system head of 200 feet.
In accordance with Fire Protection Report Volume 1, step 9.3/9.4, Fire Protection Systems Limiting Condition For Operating and Surveillance Requirements; which ONE of the following identifies the required actions (if any)?
Reference Provided A.
NO action required, the High-Pressure Fire Protection System remains OPRALE.
B.
With ONLY the diesel and NO electric fire pumps OPERABLE, restore at least one electric fire pump to OPERABLE status within 7 days.
C.
With at least one electric fire pump and NO diesel fire pump OPERABLE restore the diesel fire pump to OPERABLE status within 7 days.
D.
With NO high-pressure fire pumps OPERABLE, establish a backup fire water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
QUESTION 20 Unit 3 is at 100% power with the following plant conditions:
HPCI is operating in full flow test mode for post maintenance testing RHR Pump 3A is operating in Suppression Pool Cooling to support testing Average Suppression Pool temperature is 100° F and stable 4KV Unit Board 3A is energized from Start Bus IA All other Unit 3 electrical systems are in a NORMAL lineup A grid disturbance causes a differential Relay operation on CSST A and B, the following alarms are observed:
CSST RELAY OPERATION (3-9-8A, window 17) 4KV START BUS IA UNDERVOLTAGE (3-9-8B, window 4)
Which ONE of the following completes the statements below?
4KV Shutdown Board 3EA will be energized from (1)_.
Five minutes after the Differential Relay operation, Suppression Pool temperature will have _(2).
Assume NO operator action A.
(1) Diesel Generator 3A (2) increased B.
(1)USST3B (2) increased C.
(1) Diesel Generator 3A (2) remained stable D.
(1)USST3B (2) remained stable
QUESTION 21 Unit 2 has experienced an inadvertent MSIV closure.
RCIC is controlling Reactor Level from (+)2 to (+)51 inches HPCI is controlling Reactor Pressure from 800 to 1000 psig MSIVs remain closed Which ONE of the following completes the statement below?
The digital EHC system is in _(1)_ pressure control mode with the pressure setpoint currently set at _(2) psig.
A.
(1) Header (2) 700 B.
(1) Header (2) 955 C.
(1) Reactor (2) 700 D.
(1) Reactor (2) 955
QUESTION 22 Which ONE of the following completes the statements below?
In accordance with 3-01-74, Residual Heat Removal System the pumps utilized for reactor vessel drain down assist are the _(1).
The water removed from the reactor vessel can be directed to _(2)_.
A.
(1) RHR Pumps OR RHR Drain Pumps (2) Radwaste ONLY B.
(1) RHR Drain Pumps ONLY (2) Radwaste ONLY C.
(1) RHR Pumps OR RHR Drain Pumps (2) either Radwaste or the Main Condenser D.
(1) RHR Drain Pumps ONLY (2) either Radwaste or the Main Condenser
QUESTION 23 Unit 2 is at 100% power with CRD pump 2A tagged out for maintenance.
Unit I is in Mode 2 with a startup in progress with the following conditions:
Reactor Pressure 850 psig CRD Pump IA is in service Reactor Power is on Range 8 of the IRMs SUBSEQUENTLY, CRD Pump 1A trips on an electrical fault and can NOT be restarted.
Which ONE of the following describes the required operator actions in accordance with 1-AOI-85-3, CRD System Failure?
A.
Immediately attempt to place I B CRD Pump in service, manual scram is NOT required if charging water pressure can be restored and maintained above 940 psig.
B.
Immediately upon discovery of charging water header pressure less than 940 psig AND with ONE or more scram accumulators INOPERABLE, then verify all control rods with inoperable accumulators are fully inserted.
C.
Manually scram and immediately place the mode switch to shutdown.
D.
If charging water can NOT be restored and maintained above 940 psig within 20 minutes AND with TWO or more scram accumulators INOPERABLE with the associated control rod NOT fully inserted, then Manually scram and immediately place the mode switch to shutdown.
QUESTION 24 Unit 2 has the following plant conditions following a manual scram:
Reactor Power is 3%
Reactor Level is being controlled by feedwater in the level band of (+)2 to
(+)51 inches HPCI and RCIC have been manually started for Reactor Pressure control in accordance with EOl Appendices Reactor Pressure is 920 psig and stable Drywell Pressure is 2.0 psig and stable Suppression Pool Level is (+)2 inches and stable Which ONE of the following describes how RCIC will respond if Suppression Pool Level SUBSEQUENTLY increases to (-f-)8 inches with NO additional EOl Appendix actions taken.
A.
RCIC will continue to operate in pressure control.
B.
RCIC will be operating at shutoff head.
C.
RCIC will be operating on minimum flow.
D.
RCIC will trip due to low suction pressure.
QUESTION 25 In accordance with EOI-3, Secondary Containment Control, which ONE of the following describes the MINIMUM conditions requiring Emergency Depressurization?
A.
Area Radiation levels in two areas above Max Safe from a primary system discharging and the discharge was isolated.
B.
Area Radiation rises to Max Safe in any one area from a primary system discharging and the discharge was isolated.
C.
Area Radiation rises to Max Safe in any one area from a primary system discharging and the discharge CANNOT be isolated.
D.
Area Radiation levels in two areas above Max safe from a primary system discharging that CANNOT be isolated.
QUESTION 26 With all 3 Units at 100% power the following occurs on Unit 3:
RWCU Backwash Receiving Tank overflows during a backwash of RWCU Filter Demin.
3-RI-90-13A, NORTH CLEAN-UP SYSTEM RB El 593 reads 500 mr/hr 3-RI-90-14A, SOUTH CLEAN-UP SYSTEM RB El 593 reads 600 mr/hr 3-Rl-90-9, CLEAN-UP SYSTEM RB El 621 reads 250 mr/hr RX BLDG AREA RADIATION HIGH is in alarm (3-9-3A, window 22) 3-RM-90-142, RX ZONE EXH CH A RAD RTMR is reading 85 mrem/hr on BOTH channels 3-RM-90-143, RX ZONE EXH CH B RAD RTMR is reading 85 mrem/hr on BOTH channels Which ONE of the following indentifies the plant impact to these conditions?
A.
Control Room pressure remains unchanged and Plant Stack flow rate lowers.
B.
Control Room pressure remains unchanged and Plant Stack flow rate rises.
C.
Control Room pressure becomes more positive and Plant Stack flow rate lowers.
D.
Control Room pressure becomes more positive and Plant Stack flow rate rises.
QUESTION 27 With Unit I in Mode 2, the following alarm is received:
HPCI ROOM FLOOD LEVEL HIGH (1-9-4C, window 10)
A Radiation Protection Technician in the Unit I HPCI Area at elevation 519 reports water is rising in the HPCI Room and the leak is coming from the pumps in the adjacent quad.
Which ONE of the following identifies the possible pumps that are leaking?
A.
RHR Loop I Pumps B.
Core Spray Loop I Pumps C.
RHR Loop II Pumps D.
Core Spray Loop II Pumps
QUESTION 28 With Unit 3 at 100% power a LOOP and LOCA occur, the following conditions exist:
Reactor Level is (-)100 inches and lowering Reactor Pressure 400 psig and lowering All High Pressure Injection is out of service The following boards are energized:
o 4KVSDBD3EA o
4KVSDBD3ED o
48OVSDBD3A o
480V RMOV BD 3D Which ONE of the following identifies the ECCS Pump(s) that can be started and aligned for injection to the RPV?
A.
RHR and Core Spray 3A and 3D Pumps B.
ONLY RHR and Core Spray 3A Pumps C.
ONLY RHR Pump 3A D.
ONLY Core Spray Pump 3A
QUESTION 29 An accident occurred on Unit 2 AND resulted in the following conditions:
Reactor water level indicates (-)235 inches on Post Accident Range Level Indicators 2-LI-3-52162 Reactor pressure is 100 psig ALL RHR I LPCI are lost ONE Loop of Core Spray is injecting at 6500 gpm Which ONE of the following completes the statement below?
Adequate core cooling REFERENCE PROVIDED A.
does NOT exist B.
is provided by Spray Cooling C.
is provided by Steam Cooling D.
is provided by Core Submergence
QUESTION 30 Unit 2 is aligned with RHR Loop I in shutdown cooling and Loop II in standby readiness.
A leak occurs which results in the following conditions:
Reactor level is at zero inches and slowly lowering Drywell Pressure is at 3.0 psig and slowly rising RHR pumps A and C have tripped Which ONE of the following completes the statement below for the MINIMUM action(s) required to establish injection with RHR Loop II in accordance with 2-01-74, RHR System?
After 2-FCV-74-47 or 2-FCV-74-48 closed NOTE:
2-FCV-74-47, RHR Shutdown Cooling SUCT OUTBD ISOL VLV 2-FCV-74-48, RHR Shutdown Cooling SUCT INBD ISOL VLV A.
place 2-HS-74-67A, RHR SYS II LPCI INBD INJECT VALVE to open B.
depress the RHR SYS II SD CLG INBD INJECT ISOL RESET 2-XS-74-132 C.
depress the RHR SYS II SD CLG INBD INJECT ISOL RESET 2-XS-74-132 and then place 2-HS-74-67A, RHR SYS II LPCI INBD INJECT VALVE to open D.
depress the RHR SYS II SD CLG INBD INJECT ISOL RESET 2-XS-74-132, place 2-HS-74-67A, RHR SYS II LPCI INBD INJECT VALVE to open, then place 2-HS-74-66A, RHR SYS II LPCI OUTBD INJECT VALVE to open
QUESTION 31 HPCI has just been placed in CST-to-CST mode for a surveillance at rated flow.
The following initial conditions exist on Unit 1:
Suppression Pool temperature is 86° F NO Suppression Pool Cooling is in service Mode2 Reactor Power 8%
Which ONE of the following completes the statements below?
1-EOl-2 will be entered on Suppression Pool Temperature in _(1)_.
In accordance with Technical Specification 3.6.2.1, Suppression Pool Average Temperature HPCI surveillance testing will have to be suspended when pool temperature exceeds _(2).
A.
(1) 30 minutes (2) 95° F B.
(1) 30 minutes (2) 105° F C.
(1) 160 minutes (2) 95° F D.
(1) 160 minutes (2) 105° F
QUESTION 32 Unit 2 has experienced a Loss of Offsite Power concurrent with the following plant conditions:
SCRAM PRIMARY CTMT PRESS HIGH (2-XA-55-1 (First Out) window 24) in alarm Reactor Water Level is (-)1 00 inches and lowering Reactor Pressure is 105 psig and lowering 4KV SHUTDOWN BD C DEGRADED VOLTAGE (2-9-8B, window 33) in alarm DIESEL GEN C START FAILURE (112-9-23C, window 7) in alarm Which ONE of the following predicts the total flow rate for the Loop II Core Spray Pumps?
Assume NO operator actions A.
Ogpm B.
2400 gpm C.
6250 gpm D.
9100 gpm
QUESTION 33 A lockout on 4KV Shutdown Board B has occurred.
Which ONE of the following identifies the Unit 2 Standby Liquid Control Pump(s) available for use?
Assume NO operator actions A.
BOTH SLC 2A and 2B Pumps B.
ONLYSLC2APump C.
ONLY SLC 2B Pump D.
NEITHER SLC 2A or 2B Pumps
QUESTION 34 With Unit 2 at 100% power and electrical transient causes the output voltage of RPS Motor Generator B to be at 107 volts for 5 seconds and then return to normal.
Which ONE of the following identifies the status of the RPS Circuit Protector 2B2 indicating lights?
RPS Circuit Protector 2B2 2-lL-099 -02B2A RPS CKT PROTECTOR ON INDR CAB 2B2 2-IL-099 -02B2B RPS CKT PROTECTOR OFF INDRCAB2B2 Red Light Green Light A.
ON B.
ON C.
OFF OFF ON OFF D.
OFF ON
QUESTION 35 Unit 3 is starting up in Mode 2; all IRMs are on range 9 reading from 40 to 80. APRM downscale alarms are reset.
SUBSEQUENTLY, a Control Rod drop accident occurs, with the following plant conditions:
IRM CH A, C, E, G HI-H 1/INOP (3-9-5A, window 33)
IRM CH B, D, F, H HI-HI/INOP (3-9-5A, window 34)
NO Control Rod motion is observed The Unit Supervisor directs a manual scram. After the scram, all IRMs are indicating on Range 5 with readings lowering.
Which ONE of the following completes the statements below?
After the Control Rod Drop Accident the Unit Supervisor should direct entry into
_( I )_.
SUBSEQUENTLY, after the manual scram the Unit Supervisor should _(2)_.
A.
(1) 3-AOl-I 00-1, Reactor Scram ONLY (2) remain in 3-AOl-100-1, Reactor Scram ONLY B.
(I) 3-AOl-bC-i, Reactor Scram ONLY (2) enter 3-EQ I-i, RPV Control C.
(1) 3-AOl-I 00-1, Reactor Scram AND 3-EOI-1, RPV Control (2) remain in the RC/Q leg of 3-EOI-I D.
(1) 3-AOl-i 00-1, Reactor Scram AND 3-EOI-1, RPV Control (2) exit the RC/Q leg of 3-EOI-i and continue in 3-AOl-I 00-i, Reactor Scram
QUESTION 36 Unit 2 is performing a startup with the following conditions:
Mode Switch is in STARTUP Reactor is critical IRMs are steady on Range 2 Which ONE of the following identifies the IRM power source AND the effect of a loss of power to a single IRM?
IRM Power Source A.
24 VDC Battery B.
24VDC Battery C.
250 VDC Battery D.
250 VDC Battery Effect of Power Loss to IRM Rod Block ONLY Rod Block AND Half Scram Rod Block ONLY Rod Block AND Half Scram
QUESTION 37 The following plant conditions exist on Unit 2:
Reactor Mode Switch is in STARTUP ALL Intermediate Range Monitors (IRMs) are on Range 3 or 4 Source Range Monitor (SRM) A is retracted AND reading 0.5 cps SRMs B AND C are reading 5.3 x i0 4 cps SRM D mode switch (S-I) is in the STANDBY position Based on the above indications, which ONE of the following has caused a Rod Block signal to be generated?
A.
AnSRM High B.
An SRM NOT Full-In C.
An SRM Inoperable D.
An SRM Downscale
QUESTION 38 Unit 2 APRMs have the following indications:
APRM 1
- 106%
APRM2-104%
APRM3-104%
APRM4-105%
Recirc Loop A flow 60%
Recirc Loop B flow 64%
Which ONE of the following identifies the expected plant response to these conditions?
A.
Control Rod Withdrawal Block ONLY B.
Half Scram AND Control Rod Withdrawal Block C.
Full Scram AND Control Rod Withdrawal Block D.
Flow Compare Inverse Video Alarm on ODA ONLY
QUESTION 39 The following conditions exist on Unit 3:
The reactor scrammed due to a loss of the feedwater system HPCI is unavailable Reactor Core Isolation Cooling is maintaining RPV level at (+)30 inches Reactor pressure is 870 psig and lowering slowly The receipt of which ONE of the following annunciators indicate the MOST IMMEDIATE threat to RCICs ability to maintain adequate core cooling?
A.
RCIC STEAM LINE FLOW EXCESSIVE (3-9-3B, window 21)
B.
RCIC PUMP SUCTION PRESSURE HIGH (3-9-3C, window, 2)
C.
RCIC TURBINE BEARING OIL PRESSURE LOW (3-9-3C, window 16)
D.
RCIC STEAM LINE LEAK DETECTION TEMP HIGH (3-9-3D, window 10)
QUESTION 40 On Unit 3 the following alarm is received:
MAIN STEAM RELIEF VALVE OPEN (3-9-3C, window 25)
Given the attached illustration, which ONE of the following completes the statements below?
(1)_ SRV(s) indicate(s) OPEN or leaking.
The SRV Tailpipe Flow Monitor is placed in OFF and back to ON to _(2)_.
Illustration Attached A.
(1)One (2) attempt to close the SRV B.
(1)One (2) verify open position indication is NOT sealed in C.
(1)Three (2) attempt to close the SRV5 D.
(1) Three (2) verify open position indications are NOT sealed in
QUESTION 41 With Unit 3 at 100% power, the following occurs:
RX ZONE EXH RADIATION MONITOR DNSC (3-9-3A, window 35) is in alarm 3-RE-90-142A, Reactor Zone Channel A Detector A is downscale 3-RE-90-142B, Reactor Zone Channel A Detector B is downscale Which ONE of the following completes the statements below?
A PCIS Group 6 isolation _(1) occur.
Trips on the Reactor Zone/Refuel Zone Radiation Monitors (2) reset when the alarming condition resets.
A.
(1) will (2) will automatically B.
(1) will (2) must be manually C.
(1)will NOT (2) will automatically D.
(1)will NOT (2) must be manually
QUESTION 42 Which ONE of the following completes the statements below?
The SRVs discharge to the suppression pool via the (1), this enhances thermal mixing in the suppression pool.
Direct pressurization of the Suppression Chamber air space from an SRV discharge would occur when suppression pool level lowers to less than (2).
A.
(1) T-Quenchers (2) 11.5 feet B.
(1) T-Quenchers (2) 5.5 feet C.
(1) ring header (2) 11.5 feet D.
(1) ring header (2) 5.5 feet
QUESTION 43 Which ONE of the following completes the statements below concerning Unit 2?
Annunciator MAIN STEAM RELIEF VALVE OPEN, (2-9-3C, window 25) is actuated by
_(1).
SRV Tailpipe temperature monitoring is available _(2)_.
A.
(1) SRV Tailpipe Flow Monitor 2-FMT-1-4 (2) ONLY at MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1 B.
(1) MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1 (2) ONLY at MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1 C.
(1) SRV Tailpipe Flow Monitor 2-FMT-1-4 (2) at MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1 AND ICS D.
(1) MSRV Discharge Tailpipe Temperature Recorder, 2-.TR-1-1 (2) at MSRV Discharge Tailpipe Temperature Recorder, 2-TR-1-1 AND ICS
QUESTION 44 The following conditions currently exist on Unit I Plant Startup in progress Reactor Pressure at 250 psig 1-LCV-3-53, RFW Start-Up LCV is in service for level control Setpoint at 33 inches and in Automatic SUBSEQUENTLY, control air pressure to 1-LCV-3-53 lowers from 90 psig to 60 psig.
Which ONE of the following completes the statement below?
1-LCV-3-53 would initially _(1).
When air pressure is restored to 90 psig, operator action _(2)_ be required to return 1-LCV-3-53 to automatic operation.
A.
(1) fail closed (2) would B.
(I) tail closed (2) would NOT C.
(1) fail as is (2) would D.
(I)failasis (2) would NOT
QUESTION 45 Which ONE of the following completes the statement below?
The LOWEST value that the Rod Worth Minimizer Rod Blocks are automatically bypassed is when A.
ONLY total feedwater flow is above the LPSP B.
ONLY total steam flow is above the LPSP C.
BOTH total steam flow and feedwater flow are above the LPSP D.
ONLY total steam flow is above the LPAP
QUESTION 46 Which ONE of the following completes the statements below?
The suction source for the Standby Gas Treatment Fans when directed to vent in accordance with 1-AOl-64-1, Drywell Pressure and/or Temperature High, or Excessive Leakage Into Drywell is the _(1)_.
The preferred suction source for the Standby Gas Treatment Fans when directed to vent in accordance with 1-EOl Appendix-12, Primary Containment Venting is the
_(2)_.
A.
(1)Drywell (2) Drywell B.
(1) Drywell (2) Suppression Chamber C.
(1) Suppression Chamber (2) Drywell D.
(1) Suppression Chamber (2) Suppression Chamber
QUESTION 47 At panel 0-9-23-7, the following conditions exist for the A 4KV Shutdown Board:
0-25-21 1-A124A, 4kV SD BD A BKR 1716 SYNC switch is ON 0-43-211-A, 4kV SD BD A AUTO/LOCKOUT RESET switch is in the TRIPPED condition Alternate Supply Breaker is CLOSED Normal Supply Breaker is OPEN Which ONE of the following identifies how the Alternate and Normal Supply breakers will respond if the Unit Operator places the 0-43-211-A switch to the RESET position?
A.
Alternate supply breaker will trip open and the Normal supply breaker will close; the slow transfer will cause a momentary power loss to the board.
B.
Alternate supply breaker will trip open and the Normal supply breaker will close; the fast transfer will prevent a momentary power loss to the board.
C.
Alternate supply breaker will remain closed and the Normal supply breaker will remain open.
D.
Alternate supply breaker will trip open and the Normal supply breaker will remain open.
QUESTION 48 A Reactor SCRAM has occurred on Unit 1, an operator has observed the following indications on panel 1-9-5:
One half of the blue scram lights are NOT illuminated SRM/IRM detector power and position indication is NOT available LPRM meter lights and APRM alarm lights are NOT illuminated SLC A and B amber ready lights and valve position indication are NOT illuminated Which ONE of the following is the cause of the above conditions?
A.
Loss of Unit Preferred B.
Loss of Plant Preferred C.
Lossofl&CBusA D.
Lossofl&CBusB
QUESTION 49 Which ONE of the following is a concern if the Plant/Station Battery Rooms Exhaust Fans are NOT operating properly?
A.
The lead-calcium batteries tend to release toxic gas into the atmosphere above 900 F.
B.
The design limit for hydrogen concentration in the rooms may be reached when the batteries are being charged.
C.
Electrical Maintenance will not be able to obtain accurate cell specific gravity readings if temperature is above 90° F.
D.
The optimum recommended battery room temperatures will be exceeded.
QUESTION 50 Unit 1,2 and 3 are operating at 100% Reactor Power with 4KV SD BD B Alternate Feeder Breaker 1714 tagged out.
A LOCA occurs on Unit 1. Current conditions for Unit 1 are:
Drywell Pressure 6 psig and rising Reactor Level (-)125 inches and lowering Reactor Pressure 700 psig and lowering SUBSEQUENTLY, the 4KV SD BD B Normal Feeder Breaker 1616, trips open. There is NO fault on 4KV Shutdown Board B.
Which ONE of the following completes the statement below?
A480V Load Shed will A.
NOT occur B.
occur for Unit I ONLY C.
occur for Unit 2 ONLY D.
occurforUniti and2
QUESTION 51 Unit 3 was operating at 100% Reactor Power when a total Loss of Offsite Power occurs in conjunction with a LOCA.
Which ONE of the following completes the statements below?
After the Unit 3 Diesel Generator Output Breakers close, the first Core Spray Pump will start _(1 )_seconds later.
RHRSW Pumps assigned to EECW will start automatically _(2)_seconds after the Unit 3 Diesel Generator Output Breakers close.
A.
(1)0.1 (2) 14 B.
(1)0.1 (2) 28 C.
(1)7 (2) 14 D.
(1)7 (2) 28
QUESTION 52 Units 1, 2 and 3 are operating at 100% power with the following:
Control Air is in a normal configuration with G Control Air Compressor as the lead compressor and A-D Control Air Compressors set up with A and B compressors as LEAD, C as First LAG and D as Second LAG compressors.
Control Air pressure lowered to the indicated pressure on the attached illustration Control Air pressure is now slowly rising Which ONE of the following describes the current operating status of the air compressors?
Illustration Attached A.
ONLY Air Compressor G is running B.
ONLY Air Compressors A, B and G are running C.
ONLY Air Compressors A, B, C and G are running D.
Air Compressors A, B, C, D and G are running
00 Hill HI I
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QUESTION 53 Unit 3 was operating at 100% power with a normal electrical lineup.
The Unit SUBSEQUENTLY experiences a LOOP with the following conditions:
Diesel Generator 3C output breaker failed to close The operator places 480V SD BD 3B FDR Transfer, 3-XS-57-71 to ALT A Common Accident Signal (CAS) is received 3 minutes after the LOOP All breaker disagreements are IMMEDIATELY cleared as they come in Which ONE of the following completes the statement below for how Unit 3 RBCCW will respond to the above conditions?
A.
RBCCW Pump 3A will trip, RBCCW Pump 3B will NOT trip and RBCCW Pump 3A will automatically restart in 40 seconds.
B.
RBCCW Pump 3A will trip, RBCCW Pump 3B will NOT trip and RBCCW Pump 3A will NOT automatically restart.
C.
Both RBCCW Pumps will trip, ONLY RBCCW Pump 3A will automatically restart in 40 seconds.
D.
Both RBCCW Pumps will trip, NEITHER RBCCW Pump will automatically restart
QUESTION 54 Unit 3 has experienced an ATWS. Attached are the Control Rod positions.
Which ONE of the following identifies the correct rod insertion sequence in accordance with 3-EOI Appendix-I D, Insert Control Rods Using Reactor Manual Control System?
Reference Provided A.
22-43, 18-39, 26-39, 26-47, 18-47 and continue in this spiral order.
B.
30-31, 26-27, 34-27, 34-35, 26-35 and continue in this spiral order.
C.
30-35, 26-31, 34-31, 34-39, 26-39 and continue in this spiral order.
D.
18-31, 14-27, 22-27, 22-35, 14-35 and continue in this spiral order.
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QUESTION 55 Which ONE of the following completes the statement below identifying ALL the Rod Worth Minimizer indication(s) for a withdraw error?
02-43 is indicated in A.
withdraw error block ONLY B.
withdraw error block AND withdrawal permissive changes to withdrawal block and is now red ONLY C.
withdraw error block, withdrawal permissive changes to withdraw block and is now red, withdraw block light illuminates on RWM Status Indicator AND RWM ROD BLOCK (9-5B, window 35) alarms ONLY D.
withdraw error block, withdrawal permissive changes to withdraw block and is now red, withdraw block light illuminates on RWM Status Indicator, AND RWM ROD BLOCK (9-5B, window 35) AND CONTROL ROD SELECT BLOCK TIMER MALFUNCTION (9-5A, window 21) alarm.
QUESTION 56 Which ONE of the following describes the indications on the four rod display when control rod 30-59 is selected as illustrated on the attached illustrations?
Illustration Attached A.
B.
C.
D.
illi
QUESTION 57 Unit 2 is in ATWS with MSIVs closed. All Unit 2 RHR Pumps are unavailable.
Which ONE of the following completes the statement below that identifies available RHR crosstie connections in order to lower Suppression Pool temperature on Unit 2?
Unit 2 Loop I can be crosstied to AND Unit 2 Loop II can be crosstied to Unit 2 Loop I Unit 2 Loon II A.
Unit I Loop I Unit 3 Loop I B.
Unit I Loop I Unit 3 Loop II C.
Unit I Loop II Unit 3 Loop II D.
Unit I Loop II Unit 3 Loop I
QUESTION 58 Which ONE of the following identifies the required power supplies to place Unit 2 RHR Loop I in Drywell Spray Mode?
A.
4KV Shutdown Boards A and B, and 480V RMOV Board 2A ONLY B.
4KV Shutdown Boards A and C, and 480V RMOV Board 2A ONLY C.
4KV Shutdown Boards A and B, and 480V RMOV Board 2A and 2D D.
4KV Shutdown Boards A and C, and 480V RMOV Board 2A and 2E
QUESTION 59 Unit 3 is operating at 100% power when 3C CCW Pump trips and the 3C CCW Pump discharge valve remained OPEN.
Which ONE of the following completes the statement below?
On Control Room Panel 3-9-6, recorder 3-XR-2-2, Hotwell Temperature and Pressure:
Hotwell vacuum will _(1)_.
The discharge head for the Circulating Water Pumps that remain in service will _(2).
A.
(1) improve (2) lower B.
(1) improve (2) rise C.
(1) degrade (2) lower
- D.
(1) degrade (2) rise
QUESTION 60 Unit 2 is operating at 100% power with the following alarms due to a failure of the Turbine 1st stage pressure transmitter:
- RFWCS INPUT FAILURE (2-9-6C, Window 14)
- MAIN STEAM LINE VS STEAM FLOW MISMATCH (2-9-5B, Window 24)
FWLC is currently in 3 element control.
SUBSEQUENTLY, the Main Steam Line A flow signal slowly fails to ZERO over a 10 minute period.
Which ONE of the following completes the statements below?
The FINAL status of the Feedwater Level Control System will be (1) control.
In order to bypass the failed Main Steam Line A Flow signal the operator would reference _(2)_.
A.
(1) single element (2) 2-01-1, Main Steam System B.
(1) single element (2) 2-01-3, Reactor Feedwater System C.
(1) three element (2) 2-01-1, Main Steam System D.
(1) three element (2) 2-01-3, Reactor Feedwater System
QUESTION 61 During a unit startup shortly after placing 2A SJAE in service on main steam, the following conditions were reported:
Steam Supply pressure 150 psig Condenser Vacuum 10 Hg Condensate Pressure after the Demins 65 psig Steam Supply Valves to standby SJAE are closed Standby SJAE controller switch is in the close position Which ONE of the following completes the statement below?
In service SJAE 2A isolates due to A.
low condenser vacuum B.
low condensate pressure C.
low steam supply pressure D.
position of Standby SJAE steam supply valves
QUESTION 62 A breaker on Unit I l&C Bus A that supplies CONTROL ROOM ISOLATION RADIATION MONITOR, 0-RM-90-259A, has tripped OPEN and the following alarm is received in all three Control Rooms:
CONT RM ISOL RAD MONITOR DNSCL OR INOP (1,2,3-9-6B, window 10)
SUBSEQUENTLY, the following alarm is received in all three Control Rooms:
CONTROL ROOM HIGH RADIATION ISOLATION (1,2,3-9-6B, window 3) 0-RM-90-259B, CONTROL ROOM ISOLATION RADIATION MONITOR indicates 350 cpm Which ONE of the following describes the status of control room ventilation?
Control Room ventilation A.
isolated when 0-RM-90-259A failed downscale/INOP B.
isolated when 0-RM-90-259B detected high radiation C.
isolated when 0-RM-90-259B detected high radiation in conjunction with 0-RM-90-259A being downscale/INOP D.
remains unisolated because an isolation signal is NOT present
QUESTION 63 Which ONE of the following describes the operation of the Unit 3 Diesel Generator ventilation system when a Diesel Generator start signal is received?
A.
The A and B exhaust fans receive a start signal from diesel generator running logic, the fan outlet dampers and the diesel room inlet and outlet dampers receive their open signal from the fan start logic.
B.
The diesel room inlet and outlet dampers receive an open signal from diesel generator running logic, once these dampers are open the A and B exhaust fans start and their outlet dampers open.
C.
The A exhaust fan outlet damper receives an open signal from diesel generator running logic, once the outlet damper opens the A fan auto starts.
Diesel room inlet and outlet dampers then open.
D.
The A exhaust fan receives a start signal from diesel generator running logic, the fan outlet damper and the diesel room inlet and outlet dampers receive their open signal from the fan start logic.
QUESTION 64 Which ONE of the following describes the operation of the Reactor Building to Torus Vacuum Breakers?
A.
BOTH sets of Vacuum Breakers open when Reactor Building pressure is 0.25 psid greater than Torus pressure.
B.
BOTH sets of Vacuum Breakers open when Reactor Building pressure is 0.5 psid greater than Torus pressure.
C.
The air operated valves open when Reactor Building pressure is 0.25 psid greater than Torus pressure and the check valves open at 0.5 psid.
D.
The check valves open when Reactor Building pressure is 0.25 psid greater than Torus pressure and the air operated valves open at 0.5 psid.
QUESTION 65 With respect to Control Room Ventilation Systems, which ONE of the following completes the statements below?
Unit 1/2 Control Bay Supply Fans take a suction from _(1)_.
Upon an automatic initiation of Control Room Emergency Ventilation (CREV), the CREV System takes a suction from (2)_.
A.
(1) Vent Tower I (2) the Control Rooms B.
(I)VentTowerl (2) an outside air source C.
(1)VentTower2 (2) the Control Rooms D.
(1)VentTower2 (2) an outside air source
QUESTION 66 Which ONE of the following completes the statements below in accordance with OPDP-1, Conduct of Operations?
A standing order has recently been written dealing with a plant equipment problem; if the standing order is found to be in conflict with an operating instruction the crew is expected to follow the (1)_.
An exception to a peer check on the Peer Check Exemption List can be approved by the _(2)_.
A.
(1) operating instruction (2) Operations Manager ONLY B.
(1) operating instruction (2) Operations Manager OR Shift Manager C.
(1) standing order (2) Operations Manager ONLY D.
(1) standing order (2) Operations Manager OR Shift Manager
QUESTION 67 Unit 1 is operating at rated power. You are a control room operator in the control room sending a message to an Assistant Unit Operator (AUO) in the field. You are working with the AUO to perform a complex evolution with critical steps. The AUO and you have a copy of the instruction. Telephones are being utilized for communication.
In regards to the instruction steps, which ONE of the following identifies the proper use of three-way communication for this situation in accordance with NPG-SPP-18.2.2 Human Performance Tools?
A.
You are required to read each step to the AUO, the AUO can then paraphrase in his own words what you have read to him. You are required to read the noun names AND unique identifiers (UNID), the AUO shall repeat back the noun name AND UNID.
B.
You are required to read each step to the AUO, the AUO can then paraphrase in his own words what you have read to him. You are required to read the noun names OR unique identifiers (UNID), the AUO can repeat back the noun name OR UNID.
C.
You can tell the AUO to perform steps in the instruction; you are NOT required to read each step to the AUO. The AUO can then paraphrase in his own words what you just told him. If you have to identify a specific plant component you are required to use the noun name OR unique identifier (UNID), the AUO can repeat back noun name OR UNID.
D.
You can tell the AUO to perform steps in the instruction; you are NOT required to read each step to the AUO. The AUO can then paraphrase in his own words what you just told him. If you have to identify a specific plant component you are required to use the noun name AND unique identifier (UNID), the AUO shall repeat back the noun name AND UNID.
QUESTION 68 Which ONE of the following completes the statement below in accordance with EOl-1, RPV Control; NOTE 1?
The reactor will remain subcritical WITHOUT boron under all conditions is the same criteria for A.
all three units B.
Units 1 and 2 C.
Units 1 and 3 D.
Units2and3
QUESTION 69 Unit 3 is at rated power, the Offgas train is experiencing problems and must be swapped as soon as possible due to rapidly changing plant conditions.
While performing the evolution, procedure steps are found to be out of order.
As required by NPG-SPP-O1.2, Administration of Site Technical Procedures, which ONE of the following completes the statement below?
A/An _(1)_ procedure change is processed and approved, _(2)_ completing the required procedural steps.
A.
(1) urgent (2) before B.
(1) urgent (2) after C.
(1) one-time-only (2) before D.
(1) one-time-only (2) after
QUESTION 70 Given the following plant conditions:
o A Fuel Pool cleanout is in progress.
A failure of the Refuel Bridge monorail hoist allowed a bucket of irradiated stellite ball bearings to be raised above the fuel pool water level.
The AUO operating the Refuel Bridge received a dose of 12 rem while manually lowering the bucket below the water level.
Which ONE of the following completes the statements below?
In accordance with EPIP-15, Emergency Exposures, this _(1)_ constitute an Emergency Exposure.
The basis for this conclusion is _(2)_.
A.
(1) does (2) the federal dose limit of 5 REM was exceeded B.
(1) does (2) spontaneous actions taken to mitigate a problem are covered under EPIP-15 exposure limits C.
(1) does NOT (2) only planned exposures are covered under EPIP-15 limits D.
(1)does NOT (2) this exposure is classified as a Planned Special Exposure
QUESTION 71 Unit 2 Startup is in progress, Mechanical Vacuum Pump 2A is in service establishing a vacuum.
Given the attached illustration, which ONE of the following identifies the current status of Mechanical Vacuum Pump 2A?
Illustration Attached A.
Operating no direct trip from MSL Channel Al or A2 B.
Operating will trip if MSL Channel Al indicates UPSCALE C.
Operating will trip if MSL Channel Al indicates UPSCALE or DOWNSCALE D.
Tripped
MAIN STEAM LINE CH Al MAIN STEAM LINE Cl-f A2
QUESTION 72 Which ONE of the following completes the statement below?
The Wide Range Gaseous Effluent Radiation Monitor System (WRGERMS) consists of (1)_ ranges, AND has _(2)_.
A.
(1)TWO (2) a monitor in UNIT 2 Control Room ONLY B.
(1) THREE (2) a monitor in UNIT 2 Control Room ONLY C.
(1)TWO (2) monitors in ALL three Units Control Room D.
(1) THREE (2) monitors in ALL three Units Control Room
QUESTION 73 Unit 3 is at 35% power when Turbine vibration required the operator to insert a manual scram and trip the turbine.
Two (2) minutes after placing the Mode Switch in SHUTDOWN the following conditions exist:
Three Turbine Bypass Valves indicate full OPEN All Main Steam Isolation Valves (MSIVs) are OPEN RPV Narrow Range water level is (+)25 inches and stable RPV pressure is 965 psig and stable Which ONE of the following completes the statement below that identifies the procedure(s) that must be entered?
3-ACI-I 00-1, Reactor Scram A.
ONLY B.
AND 3-EOl-1, RPV Control ONLY C.
AND 3-C-5, Level/Power Control ONLY D.
AND 3-EOI-1, RPV Control, AND 3-C-5, Level/Power Control
QUESTION 75 Based on the attached steps from 1-EOI-3, Secondary Containment Control which ONE of the following completes the statements below?
The level value listed in steps SCIL-l I and SCIL-1 5 is _(1).
During execution of EOl-3, Isolation of all systems that are discharging into secondary containment is required, EXCEPT system(s) that are required to (2).
Illustration Attached A.
(1)2 inches (2) suppress a fire ONLY B.
(1)2 inches (2) be operated by the EOIs OR suppress a fire C.
(1) 20 inches (2) suppress a fire ONLY D.
(1) 20 inches (2) be operated by the EOI5 OR suppress a fire
i L
L L
t2
.SCL 1
- 1. 295001 AA2.03
- 2. 295003 AK3.06
- 3. 295004 AK1.02
- 4. 295005 G2.2.44
- 5. 295006 AA2.03
- 6. 295016 AA1.04
- 7. 295018 AKI.01
- 8. 295019 AA1.02
- 9. 295021 AK3.05
- 10. 295023 AK2.05
- 11. 295024 EK2.05
- 12. 295025 EK3.02
- 13. 295026 EK1.02
- 14. 295028 EK2.01
- 15. 295030 02.2.22
- 16. 295031 EK2.15
- 17. 295037 EA2.06
- 18. 295038 G2.4.46
- 19. 600000 02.2.40
- 20. 700000 AA1.05
- 21. 295007 AA1.05
- 22. 295008 AK2.10
- 23. 295022 02.4.1
- 24. 295029 EK2.09
- 25. 295033 EK3.01
- 26. 295034 EK1.02
- 27. 295036 EA2.03
- 28. 203000 K2.01
- 29. 203000 K3.04
- 30. 205000 A2.06
- 31. 206000 A2.08
- 32. 209001 G2.4.46
- 33. 211000 K2.01
- 34. 212000 A1.01
- 35. 215003 G2.4.2
- 36. 215003 K2.01
- 37. 215004 A1.04
- 38. 215005 K4.01
- 39. 217000 K5.07
- 40. 218000 A4.07
- 41. 223002 K6.03
- 42. 239002 K1.07
- 43. 239002 K5.04
- 44. 259002 A1.05
- 45. 259002 K4.02
- 46. 261000 K1.03
- 47. 262001 A3.01
- 48. 262002 K3.17
- 49. 263000 K1.03
- 50. 264000 A3.05
- 51. 264000 K5.06
- 52. 300000 A4.01
- 53. 400000 K6.07
- 54. 201002 02.1.25 55.201006 A3.01
- 56. 214000 A4.02 57.219000K3.01
- 58. 230000 K2.02
- 59. 256000 K1.18
- 60. 259001 A2.07
- 61. 271000 A1.15
- 62. 272000 K6.03
- 63. 288000 K4.03
- 64. 290001 K5.01
- 65. 290003 K1.03
- 66. 02.1.15
- 67. 02.1.38
- 68. 02.2.3
- 69. 02.2.6
- 70. 02.3.4
- 71. G2.3.5
- 72. 02.3.15
- 73. 02.4.2
- 74. 02.4.6
- 75. 02.4.22
- 76. 295001 AA2.04
- 77. 295005 AA2.03
- 78. 295018 02.4.9
- 79. 295021 AA2.05
- 80. 295026 02.1.30
- 81. 295028 02.2.25
- 82. 295038 02.2.12
- 83. 295008 02.4.18
- 84. 295013 AA2.02
- 85. 295020 02.2.37
- 86. 206000 A2.17
- 87. 211000 02.2.38
- 88. 261000 02.1.27
- 89. 223002 02.4.20
- 90. 239002 A2.04
- 91. 202002 A2.03
- 92. 214000 02.2.42
- 93. 234000 02.2.39
- 94. G2.1.17
- 95. 02.2.14
- 96. 02.2.4
- 97. 02.3.12
- 98. 02.3.15
- 99. 02.4.3 1 100. 02.4.37 D
C A
A D
B D
A D
B C
C C
C D
D C
C B
B D
C C
A D
A A
B C
D C
A D
B C
A A
D C
B D
D A
C B
B B
A C
D D
B C
A A
B C
B C
D C
B A
C B
D C
B D
A C
A D
A C
B C
B D
B B
A D
D A
C D
B D
C D
RO Reference Table of Contents 5.
EOl Caution #1, Curve 8 and Table 6 17.
EOl-3 Table 3 19.
Fire Protection Report pages 56-60 29.
PIP 95-64 for Unit 2 54.
3-EOl Appendix-ID, NO Notes